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Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000
March 21, 2012
U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555-0001
Watts Bar Nuclear Plant, Unit 2NRC Docket No. 50-391
Subject: Watts Bar Nuclear Plant (WBN) Unit 2 - Submittal of Pre-op TestInstructions
The following approved WBN Unit 2 Pre-op Test Instructions (PTIs) are enclosed:
PTI NUMBER Rev. TITLE
2-PTI-001-03 0 Main Steam Safety Valves
2-PTI-003A-02 0 Feedwater and Steam Generator Level
2-PTI-068-02 0 Reactor Coolant Flow Measurement
If you have any questions, please contact Pete Olson at (423) 365-3294.
Respectfully,
Raymond A. Hruby, Jr.General Manager, Technical ServicesWatts Bar Unit 2
Enclosures
,dejt
U.S. Nuclear Regulatory CommissionPage 2March 21, 2012
cc (Enclosures):
U. S. Nuclear Regulatory CommissionRegion IIMarquis One Tower245 Peachtree Center Ave., NE Suite 1200Atlanta, Georgia 30303-1257
NRC Resident Inspector Unit 2Watts Bar Nuclear Plant1260 Nuclear Plant RoadSpring City, Tennessee 37381
WATTS BAR NUCLEAR PLANT
UNIT 2 PREOPERATIONAL TEST
TITLE: MAIN STEAM SAFETY VALVES
Instruction No: 2-PTI-001-03
Revision No: 0000
PREPARED BY: J*Ls )ChCA / J,&a k--J DATE: 05/i S/,tPRINT NAME / SIGNATURE
REVIEWED BY: 14- i , /---- z-,./, . DATE: ___5_- _2-PRINT NAME I SIGNATURE
INSTRUCTION APPROVAL
JTG MEETINC. • -/ - 0V5
JTG CHAIRMArI. -- DATE:
PREOPEATiONAL STARTUP MANAGER DATEii1&4•
TEST RESULTS APPROVAL
JTG MEETING No:
JTG CHAIRMAN: DATE:
APPROVED BY: DATE:PREOPERATIONAL STARTUP MANAGER
SMP-8.0, Administration of Preoperational Test instructions, Appendix B 12/07/2010
Revision Log
Revision Affectedor Change Effective Page
Number Date Numbers Description of Revision/Change
0000 ALL Initial issue. This procedure was written usingUnit 1 PTI-001-03, Rev 0 as a guide.
Table of Contents
1.0 INTRODUCTION .................................................................................................. 4
1.1 Test Objectives ....................................................................................................... 4
1.2 Scope ............................................................................................................................ 4
2.0 REFERENCES ...................................................................................................... 5
2.1 Perform ance References .............................................. I .......................................... 5
2.2 Developmental References ...................................................................................... 5
3.0 PRECAUTIONS AND LIM ITATIO NS ........................................................................ 7
4.0 PREREQ UISITE ACTIO NS ....................................................................................... 8
4.1 Prelim inary Actions .................................................................................................. 84.2 Test Equipm ent .................................. ...................................................................... 10
4.3 Field Preparations ................................................................................................... 10
4.4 Approvals and Notifications .................................................................................... 10
5.0 ACCEPTANCE CRITERIA ..................................................................................... 11
6.0 PERFORMANCE ................................................................................................... 13
6.1 Main Steam Safety Valve Pressure Setpoint Testing ....................... ... 13
7.0 PO ST PERFORMANCE ACTIVITY ....................................................................... 16
8.0 RECO RDS .................................................................................................................. 17
8.1 QA Records ................................................................................................................ 178.2 Non-QA Records .................................................................................................... 17
Appendix A: TEST PROCEDURES/INSTRUCTIONS REFERENCE
REVIEW ................................................................................................. 18
Appendix B: TEM PORARY CONDITION LOG ........................................................... 19
Date
1.0 INTRODUCTION
1.1 Test Objectives
Demonstrate proper operation of the Main Steam Safety Valves (MSSVs).
1.2 Scope
Demonstrate (using a pressure assist device to measure the lifting pressure) thateach MSSV's setpoint meets its design requirement.
Demonstrate each MSSV properly reseats with absence of seat leakage followingsetpoint verification.
Date
2.0 REFERENCES
2.1 Performance References
A. SMP-9.0, Test Conduct
B. 2-S1-1-907, Testing and Setpoint Adjustment of Main Steam Safety ValvesUsing Trevitest Equipment.
C.' N3C-945, Procedure for Evaluation and Qualification of Piping SystemVibrations.
D. 2-PTI-068-01, HFT Heatup and Cooldown.
2.2 Developmental References
A. Final Safety Analysis Report (FSAR) Amendment 107
1. FSAR Table 14.2-1, Sheet 64 of 89, Steam Generator & AtmosphericRelief Valves Test Summary
2. FSAR Chapter 10.3 Main Steam Supply System
B. Drawings
1. Flow Diagrams
a. 2-47W801-1, Rev 3, FLOW DIAGRAM MAIN AND REHEAT STEAM.DRA 53949-201, Rev 0DRA 53949-202, Rev 0DRA 53949-203, Rev 0DRA 53949-204, Rev 0
2. Mechanical
a. 47W415-1 (AD), Rev 10, MECHANICAL MAIN STEAM RELIEF &SAFETY VALVE VENTSDRA 53949-100, Rev I
Date
2.2 Developmental References (continued)
C. Documents
1. NPG-SSD-WBN2-1-4002, Rev 3, Main Steam System.
2. 2-TSD-1-3, Rev 1, Main Steam Safety Valves Test.
3. 2-PTI-068-01, Draft, HFT Heatup and Cooldown.
4. 1-Si-1 -907, Rev 19 Testing and Setpoint Adjustment of Main Steam SafetyValves Using Trevitest Equipment.
To be verified against 2-SI-1-907 (Current Draft/Rev), Testing and SetpointAdjustment of Main Steam Safety Valves Using Trevitest Equipment, inAppendix A.
Date
3.0 PRECAUTIONS AND LIMITATIONS
A. Steps may be repeated if all components cannot be tested in a step. However,if the test has been exited, prerequisite steps must be re-verified and aChronological Test Log (CTL) entry made.
B. Discrepancies between component ID tags and the description in aprocedure/instruction do not require a TDN in accordance with SMP-14.0 if theUNIDs match, exclusive of place-keeping zeros and train designators (e.g.2-HS-31-468 vs 2-HS-031-0468) and the noun description is sufficient toidentify the component. If the component label needs to be changed, a TagRequest (TR Card) should be processed in accordance with TI-12.14. Make anentry in the CTL and continue testing.
C. All open problems are to be tracked by a corrective action document andentered on the appropriate system punchlist.
D. Problems identified during the test shall be annotated on the Chronological TestLog (CTL) from SMP-9.0 including a description of the problem, the procedurestep when/where the problem was identified, corrective action steps taken toresolve the problem, and the number of the corrective action document, if onewas required.
E. Observe all Radiation Protection (RP) requirements when working in or nearradiological areas.
F. Ensure no adverse effects to the operation of Unit 1 structures, systems orcomponents result from test performance.
G. During performance of this test, system components will be hot. Test personnelshall exercise care in order to avoid contact with these surfaces.
H. Testing activities will occur in areas that will be physically demanding due tohigh temperatures. Heat stress of personnel could occur if safety precautionsare not followed.
1. A loud noise will occur anytime a Main Steam Safety Valve lift is achieved or if aSteam Generator Power Operated Valve is exercised for pressure control.Double hearing protection shall be used in the U2 Valve Vault Rooms duringperformance of this test.
J. Caution signs should be posted at the entrances to the Valve Vault rooms whiletesting is in progress to warn of heat stress and hearing risks.
WBN MAIN STEAM SAFETY VALVES 2-PTI-001 -03Unit 2 Rev. 0000
Page 8 of 19
Date
4.0 PREREQUISITE ACTIONS
NOTE
Prerequisite steps may be performed in any order unless otherwise stated and should becompleted as close in time as practicable to the start of Section 6.0
4.1 Preliminary Actions
[1] VERIFY the test/performance copy of this Preoperational TestInstruction (PTI) is the current revision and, as needed,each test person assisting in this test has the current revisionincluding any change notices.
[2] OBTAIN copies of the applicable forms from the latest revisionof SMP-9.0, AND
ATTACH to this PTI for use during the performance of this PTI.
[3] ENSURE changes to the references listed on Appendix A havebeen reviewed and determined NOT to adversely affect thetest results.
[4] VERIFY current revisions and change paper for referenceddrawings has been reviewed and determined NOT toadversely affect the test performance, AND
ATTACH documentation of current drawing revision numbersand change paper that were reviewed to data package.
[5] EVALUATE open items for system 001 in Watts Bar IntegratedTask Equipment List (WITEL), AND
ENSURE that they will NOT adversely affect the testperformance and results.
[6] ENSURE required Component Testing has been completedprior to start of test.
Date
4.1 Preliminary Actions (continued)
[7] ENSURE outstanding Design Change Notices (DCN's),Engineering Design Change Requests (EDCR's) or TemporaryAlterations (TA's) do NOT adversely impact testing, AND
ATTACH documentation of DCNs, EDCRs and TAs that werereviewed to the data package.
[8] ENSURE a review of outstanding Clearances has beencoordinated with Operations for impact to the testperformance, AND
RECORD in Appendix B, Temporary Condition Log, ifrequired.
[9] VERIFY System cleanness, as required for the performance ofthis test, has been completed, in accordance with SMP-7.0and 2-CP-01-01.
[10] ENSURE components contained within the boundaries of thistest are under the jurisdictional control of PreoperationalStartup Engineering (PSE) and/or Plant Operations.
[11] ENSURE all piping supports required for testing are installedand adjusted, as required.
[12] VERIFY the U2 Reactor Coolant System is at the 5570FPlateau, in accordance with 2-PTI-068-01.
[13] PERFORM a pretest walkdown on equipment to be tested toensure no conditions exist that will impact test performance.
[14] CONDUCT a pretest briefing with Test and Operationspersonnel, in accordance with SMP-9.0.
[15] ENSURE that communications are available for areas wheretesting is to be conducted.
[16] ENSURE Surveillance Instruction 2-SI-1-907 has beensubmitted to the JTG for concurrence that it adequatelysatisfies the requirements of this procedure.
JTG Meeting # 2-S1-1-907, Rev #
Date
4.2 Test Equipment
Measuring & Test Equipment utilized for this procedure will be specified in2-SI-1-907.
4.3 Field Preparations
None
4.4 Approvals and Notifications
[1] OBTAIN permission of the Preoperational Startup Manager tostart the test.
Preoperational Startup Manager DateSignature
[2] OBTAIN Unit 2 Supervisor (US/SRO) or Shift Manager (SM)authorization.
U2 US/SRO/SM Signature Date
Date
5.0 ACCEPTANCE CRITERIA
[1] Main Steam Safety Valves lift at the following pressures(determined using a pressure-assist device) (Step 6.1141):
Valve Setpoint (psig)
Steam Generator Loop I
2-SFV-1-522 1211.76-1236.24
2-SFV-1-523 1202.85-1227.15
2-SFV-1 -524 1192.95-1217.05
2-SFV-1 -525 1183.05-1206.95
2-SFV-1 -526 1173.15-1196.85
Steam Generator Loop 2
2-SFV-1 -517 1211.76-1236.24
2-SFV-1 -518 1202.85-1227.15
2-SFV-1 -519 1192.95-1217.05
2-SFV-1 -520 1183.05-1206.95
2-SFV-1 -521 1173.15-1196.85
Steam Generator Loop 3
2-SFV-1-512 1211.76-1236.24
2-SFV-1-513 1202.85-1227.15
2-SFV-1-514 1192.95-1217.05
2-SFV-1-515 1183.05-1206.95
2-SFV-1-516 1173.15-1196.85
Steam Generator Loop 4
2-SFV-1-527 1211.76-1236.24
2-SFV-1 -528 1202.85-1227.15
2-SFV-1 -529 1192.95-1217.05
2-SFV-1-530 1183.05-1206.95
2-SFV-1-531 1173.15-1196.85
Date
5.0 ACCEPTANCE CRITERIA (continued)
[2] Main Steam Safety Valves reseat with no audible or visibleseat leakage (Step 6.1[5]).
Valve
Steam Generator Loop I Steam Generator Loop 3
2-SFV-1-522 2-SFV-1 -512
2-SFV-1-523 2-SFV-1-513
2-SFV-1 -524 2-SFV-1-514
2-SFV-1 -525 2-SFV-1-515
2-SFV-1-526 2-SFV-1 -516
Steam Generator Loop 2 Steam Generator Loop 4
2-SFV-1-517 2-SFV-1 -527
2-SFV-1 -518 2-SFV-1 -528
2-SFV-1-519 2-SFV-1 -529
2-SFV-1-520 2-SFV-1 -530
2-SFV-1 -521 2-SFV-1 -531
Date
6.0
6.1
PERFORMANCE
Main Steam Safety Valve Pressure Setpoint Testing
[1] VERIFY that all Prerequisites Actions in Section 4.0 arecomplete.
NOTES
1) 2-SI-1-907 shall be performed (through Post Performance Activities) for all twentyMain Steam Safety Valves.
2) Steps 6.1[2] through 6.1[5] may be performed concurrently, on a component bycomponent basis.
[2] PERFORM 2-S1-1-907, Testing and Setpoint Adjustment ofMain Steam Safety Valves Using Trevitest Equipment.
NOTES
1) Piping vibration is to be visually monitored in accordance with N3C-945 (visualmethod), during transient conditions.
2) Walkdown should be performed on a loop by loop basis, where a given MSS loopwalkdown is performed during MSSV lift of a valve on that loop.
3) Post Test walkdown may be performed for areas/components inaccessible duringtesting to determine if damaging vibration occurred during the test.
4) If vibration is excessive, initiate a Test Deficiency Notice (TDN) and initial Step 6.1[3].
[3] WALKDOWN the portions of the Main Steam System locatedin the Valve Vault Rooms and U2 Containment, AND
VERIFY the transient piping and component vibration isacceptable.
Date
6.1 Main Steam Safety Valve Pressure Setpoint Testing (continued)
NOTES
1) 2-SI -1-907 will exercise each MSSV until two consecutive lift setpoints, withoutadjustment between lifts, are verified to be within acceptance criteria.
2) The "Last, As-Left Setpoint" is the final acceptable valve lift and the "Next to Last, AsLeft Setpoint" is the lift performed just prior to the "Last, As-Left Setpoint".
[41 RECORD as-left setpoint data from 2-SI-1-907 for each MainSteam Safety Valve, AND
VERIFY the setpoint data meets the listed acceptance criteria.(Acc Crit)
UNID Last, As-Left, Next to Last, As-Left, Acceptance Acceptance CriteriaSetpoint (PSIG) Setpoint (PSIG) Criteria (PSIG) Met
(INITIAL for Yes)2-SFV-1 -512 1211.76-1236.24
2-SFV-1 -513 1202.85-1227.15
2-SFV-1-514 1192.95-1217.05
2-SFV-1-515 1183.05-1206.95
2-SFV-1 -516 1173.15-1196.85
2-SFV-1-517 1211.76-1236.24
2-SFV-1-518 1202.85-1227.15
2-SFV-1-519 1192.95-1217.05
2-SFV-1-520 1183.05-1206.95
2-SFV-1-521 1173.15-1196.85
2-SFV-1-522 1211.76-1236.24
2-SFV-1-523 1202.85-1227.15
2-SFV-1-524 1192.95-1217.05
2-SFV-1-525 1183.05-1206.95
2-SFV-1 -526 1173.15-1196.85
2-SFV-1 -527 1211.76-1236.24
2-SFV-1-528 1202.85-1227.152-SFV-1-529 1192.95-1217.05
2-SFV-1-530 1183.05-1206.95
2-SFV-1-531 1173.15-1196.85
Date
6.1 Main Steam Safety Valve Pressure Setpoint Testing (continued)
[5] VERIFY no, as-left, seat leakage (audible/visible) was notedduring 2-SI-1 -907 performance, after final re-seat for each ofthe following valves: (Acc Crit)
UNID Acceptance Criteria Met
(INITIAL for Yes)
2-SFV-1-512
2-SFV-1 -513
2-SFV-1-514
2-SFV-1-515
2-SFV-1-516
2-SFV-1 -517
2-SFV-1-518
2-SFV-1 -519
2-SFV-1-520
2-SFV-1-521
2-SFV-1-522
2-SFV-1 -523
2-SFV-1 -524
2-SFV-1-525
2-SFV-1-526
2-SFV-1 -527
2-SFV-1-528
2-SFV-1 -529
2-SFV-1 -530
2-SFV-1-531
Date
7.0 POST PERFORMANCE ACTIVITY
[1] ENSURE that Post-test calibration of the M&TE used in2-S1-1 -907 to record quantitative acceptance criteria in thisprocedure has been satisfactorily performed, AND
ATTACH a copy of Post-test calibration results to this testpackage.
[2] ENSURE any temporary conditions recorded in Appendix B,Temporary Condition Log, are addressed for necessaryrestoration as applicable (N/A if no conditions recorded).
1 st
Cv
[3] ATTACH a copy of the 2-SI-1 -907 data record utilized inperformance of this procedure to this test package.
[4] NOTIFY the Unit 2 US/SRO/SM of the test completion andsystem alignment.
Date
8.0 RECORDS
8.1 QA Records
Completed Test Package
8.2 Non-QA Records
None
Appendix A(Page I of 1)
TEST PROCEDURES/INSTRUCTIONS REFERENCE REVIEW
Date
NOTES
1) Additional copies of this table may be made as necessary.
2) Initial and date indicates review has been completed for impact.
PROCEDURE/ INITIAL AND DATE.INSTRUCTION REVISIONICHANGES (NIA for no change)
U2 FSAR - Amendment 104
Section 10.3
Table 14.2-1 Sh 64 of 89
NPG-SSD-WBN2-1-4002,Rev 3
2-TSD-1-3, Rev 1
2-PTI-068-01, Draft
1-S1-1-9071, Rev 19
___________________________ I _____________________________ I ___________________
1 To be Reviewed against current, equivalent, U2 Procedure/Instruction for impact
Appendix B(Page 1 of 1)
TEMPORARY CONDITION LOG
Date
NOTE
These steps will be N/A'd if no temporary condition existed. Additional copies of this tablemay be made as necessary.
ITEM TEMPORARY CONDITION PERFORMED RETURNED TO NORMALNo. DESCRIPTION Step Performed By/Date Step Returned By/Date
No. CV By/Date No. CV By/Date
WATTS BAR NUCLEAR PLANT
UNIT 2 PREOPERATIONAL TEST
TITLE: Feedwater and Steam Generator Level
Instruction No: 2-PTI-003A-02
Revision No: 0000
PREPARED BY: 10$epis E.hJod-fe,.. DATE: ___________
PRINT NAME /iVIGNATURE
REPVIENWED BY: e 2-A RDATE:PRINT NAME / SIGNATURE
INSTRUCTION APPROVAL
JTG MEETING No:
JTG CHAIRMAN:
APPROVED BY:
DATE: Un-
DATE: t
TEST RESULTS APPROVAL
JTG MEETING No:
JTG CHAIRMAN:
APPROVED BY:
DATE:
DATE:PREOPERATIONAL STARTUP MANAGER
SMP-8.0, Administration of Preoperational Test instructions, Appendix B 12/07/2010
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 2 of 182
Revision Log
Revision Affectedor Change Effective PageNumber Date Numbers Description of RevisionlChange
0 ALL Original Issue
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 3 of 182
Table of Contents
1.0 INTRODUCTION ................................................ 6
1.1 T est O bjectives ........ i .............................................................................................. 6
1 .2 S co pe ....................................................................................................... , ................. .. 6
2.0 REFERENCES ................................................. 6
2.1 Perform ance References ... 6......................................................................................... 6
2.2 Developm ental References ......................................................................................... 7
3.0 PRECAUTIONS AND LIMITATIONS ......................................................................... 12
4.0 PREREQUISITE ACTIONS . 14
4.1 Preliminary Actions ............................................ 14
4.2 Special Tools, Measuring and Test Equipment, Parts, and Supplies ...................... 17
4.3 Field Preparations .............................................. 18
4.4 Approvals and Notifications ................................................................................... 22
5.0 ACCEPTANCE CRITERIA ............... . . .............................................. 23
6.0 PERFORMANCE ..................................................... 25
6.1 SG 1 Narrow Range Level Instrument Test ............................. 26
6.2 SG 2 Narrow Range Level Instrument Test ............................. 41
6.3 SG 3 Narrow Range Level Instrument Test ......................................................... 55
6.4 SG 4 Narrow Range Level Instrument Test ............................. 69
7.0 POST PERFORMANCE ACTIVITY ............................................................................ 83
8.0 R EC O R D S ................................................................... ............................................ 8 3
Appendix A: Test Procedureslinstructions Reference Review ................ 84
Appendix B: Temporary Condition Log ............. ..................................................... 86
Appendix C: Permanent Plant Instrumentation Log ............................................... 87
Table 1: Computer Point Verification Log ............................ 90
Table 2: Train A Plastic Screw Verification ...................................................... 91
Table 3: Train B Plastic Screw Verification ........................... 93
Data Sheet 1: SG I - Initial Level Verification Data ......................... 95
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 4 of 182
Data Sheet 2:
Data Sheet 3:
Data Sheet 4:
Data Sheet 5:
Data Sheet 6: -
Data Sheet 7:
Data Sheet 8:
Data Sheet 9:
Data Sheet 10:
Data Sheet 11:
Data Sheet 12:
Data Sheet 13:
Data Sheet 14:
Data Sheet 15:
Data Sheet 16:
Data Sheet 17:
Data Sheet 18:
,Data Sheet 19:
Data Sheet 20:
Data Sheet 21:
Data Sheet 22:
Data Sheet 23:
Data Sheet 24:
Data Sheet 25:
Data Sheet 26:
Table of Contents (continued)
SG I - 50% Level Verification Data.............................. 97
SG I - 75% Level Verification Data ..................................................... 99
SG I - 100% Tap Verification Data .............................. ........................... 101
SG I - 100% Level Verification Data ..................................................... 102
SG I - 75% Level Verification Data ......................... 104
SG 1 - 50% Level Verification Data ........................................................ 106
SG I - 25% Level Verification Data ........................................................ 108
SG I - 0% Tap Verification Data ............................................................. 110
SG 1 - 0% Level Verification Data ........................... 1
SG I - 25% Level Verification Data ........................................................ 113
SG I - Final Level Verification Data ............................... 115
SG 2 - Initial Level Verification Data•..................................................... 117
SG 2 - 50% Level Verification Data ........ ................................................ 119
SG 2 - 75% Level Verification Data ......................... 121
SG 2 - 100% Tap Verification Data ........ ...................... I ................... 123,
SG 2 - 100% Level Verification Data ..................................................... 124
SG 2 - 75% Level Verification Data ......................... 126
SG 2 - 50% Level Verification Data ......................... 128
SG 2 - 25% Level Verification Data .................................................... 130
SG 2 - 0% Tap Verification Data ...................................................... 132
SG 2 -0% Level Verification Data ........................................................ 133
SG 2 - 25% Level Verification Data ......................... 135
SG 2 - Final Level Verification Data ......................... 137
SG 3 - Initial Level Verification Date ..... ............................ ............... 139
SG 3 - 50% Level Verification Data ......................... 141
I WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page5 of 182
Data Sheet 27:
Data Sheet 28:
Data Sheet 29:
Data Sheet 30:
Data Sheet 31:
Data Sheet 32:
Data Sheet 33:
Data Sheet 34:
Data Sheet 35:
Data Sheet 36:
Data Sheet 37:
Data Sheet 38:
Data Sheet 39:
Data Sheet 40:
Data Sheet 41:
Data Sheet 42:
Data Sheet 43:
Data Sheet 44:
Data Sheet 45:
Data Sheet 46:
Data Sheet 47:
Data Sheet 48:
Table of Contents (continued)
SG 3 - 75% Level Verification Data .................................. 143
SG 3 - 100% Tap Verification Data ...................................... ................ 145
SG 3 - 100% Level Verification Data ...................................................... 146
SG 3 - 75% Level Verification Data ......................... 148
SG 3 - 50% Level Verification Data ....................................................... 150
SG 3 - 25% Level Verification Data ................................... 152
SG 3 -0% Tap Verification Data ............................................................. 154
SG 3 -0% Level Verification Data .......................... 155
SG 3 - 25% Level Verification Data ....................................................... 157
SG 3 - Final Level Verification Data ...................................................... 159
SG 4 - Initial Level Verification Data ................................... ................... 161
SG 4 - 50% Level Verification Data ......................... 163
SG 4 - 75% Level Verification Data ....................................................... 165
SG 4 - 100% Tap Verification Data............................ 167
SG 4 - 100% Level Verification Data ......................... 168
SG 4 - 75% Level Verification Data .............................. 170
SG 4 - 50% Level Verification Data ........... ...... I ...................................... 172
SG 4 - 25% Level Verification Data ....................................................... 174
SG 4-0% Tap Verification Data ............... .............................................. 176
SG 4 - 0% Level Verification Data ...................................................... 177
SG 4 - 25% Level Verification Data .............. ........... 179
SG 4 - Final Level Verification Data ........ ........................... 1 81
WBN, Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 6 of 182
1.0 INTRODUCTION
1.1 Test Objectives
This test will demonstrate the following test objectives:
A. Proper operation of the narrow range level indication over the full Narrow-Range (NR).
'B. NR instrumentation digital outputs to the Solid State Protection System (SSPS).
1.2 Scope
A. The NR level instrumentation shall agree between each loop.
1. The highest and lowest indication for the three NR level indicators for eachsteam generator shall be within 5% of each other.
2. The highest and lowest calculated level for the three NR level transmittersfor each steam generator shall be within 1.1% of each other.
B. The NR level instrumentation provides digital outputs to the Solid StateProtection System for the following conditions:
1. Hi-Hi level digital output from the NR level instrumentation to the SSPS.
2. Lo-Lo level digital output from the NR level instrumentation to the SSPS.
2.0 REFERENCES
2.1 Performance References
A. SMP-9.0, Conduct of Test
B. SMP-15.0, Status and Control of Isolation Devices
C. 2-SOI-2&3.01, Condensate and Feedwater System
D. 2-SOI-15.01, System Operating Instruction for Steam Generator Blowdown
E. 2-PTI-68-1, Hot Functional Testing
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 7 of 182
2.2 Developmental References
A. Final Safety Analysis Report (FSAR), Amendment 107
1. Table 14.2.1, Integrated Hot Functional Tests Test Summary, Sheet 77
2. Table 14.2.1, Integrated Hot Functional Tests Test Summary, Sheet 78
3. Table 14.2.1, Integrated Hot Functional Tests Test Summary, Sheet 79
B. Drawings
1. Flow Diagrams
a. 2-47W801-2, Rev. 4, Flow Diagram Steam Generator BlowdownSystem, DRA-53177-2 and -3 Rev. 0, DRA-53223-1 Rev. 0, DRA-53949-205 through -208, -219 through -222, Rev. 0, DRA-54449-1,Rev. 0, DRA-52340-90, Rev. 0, DRA -53606-18, Rev. 0 DRA-54623-100, Rev. 0
b. 2-47W803-1, Rev. 5, Flow Diagram Feedwater, DRA-53128-110, Rev.0,- DRA-53276-22, Rev. 0, DRA-53380-1, -2, Rev. 0, DRA-53390-45, -46, Rev. 0, DRA-53391-35, Rev. 0, DRA-53525-1, Rev. 0, DRA-53876-1through -5,-320 Rev. 0, DRA-54039-75, Rev. 0, DRA-52310-12, Rev. 0, DRA-52317-304 through -308, Rev. 0, DRA-54145-111, -
112, Rev. 0, DRA-54263-96 through -99, Rev, 0
2. Electrical
a. 45N2676-1, Rev. E, Wiring Diagram Solid State Protection Sys TrainA Connection Diagram Sh-1
b. 45N2676-2, Rev. E, Wiring Diagram Solid State Protection Sys TrainA Connection Diagram Sh-2
c. 45N2676-4, Rev. AA, Wiring Diagram Solid State Protection Sys TrainA Connection Diagram Sh-4, DRA 56336-114, Rev. 0, DRA 54706-166, Rev. 0
d. 45N2676-5, Rev. K, Wiring Diagram Solid State Protection Sys TrainA Connection Diagram Sh-5, DRA 56•336-115, Rev. 0
e. 45N2677-1, Rev. E, Wiring Diagram Solid State Protection Sys TrainB Conhection Diagram Sh-1
f. 2-45N2677-2, Rev. E, Wiring Diagram Solid State Protection SysTrain B Connection Diagram Sh-2
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2.2 Developmental References (continued)
g. 45N2677-4, Rev. AA, Wiring Diagram Solid State Protection Sys TrainB Connection Diagram Sh-4, DRA 56336-116, Rev. 0
h. 45N2677-5, Rev. L, Wiring Diagram Solid State Protection Sys Train BConnection Diagram Sh-5, DRA 56336-117, Rev. 0
3. Mechanical
None
4. Logic/Control
a. 2-47W610-3-1, Rev. 2, Electrical Control Diagram Main Aux FWSystem, DRA-52319-6, Rev. 0, DRA-53301-110, Rev. 0, DRA-55180-37, Rev. 0, DRA-55347-54, Rev. 0, DRA-52378-415, Rev. 2, DRA-52317-55, Rev. 0
b. 2-47W610-3-1A, Rev. 0, Electrical Control Diagram Main Aux FWSystem, DRA-52319-7, Rev. 0, DRA-53301-111 through -116, Rev. 0,DRA-55180-38, Rev. 0, DRA-52378-423, Rev. 0
c. 2-47W610-3-1B, Rev. 0, Electrical Control Diagram Main Aux FWSystem, DRA-52319-8, Rev.0, DRA-53600-7, Rev. 0, DRA-53873-311, Rev. 0, DRA-55347-55,-56, Rev. 0, DRA-52310-13, Rev. 0,52378-416, Rev. 2, DRA-54144-7,-322, Rev. 0
d. 2-47W610-3-IC, Rev. 1, Electrical Control Diagram Main Aux FWSystem, DRA-52319-9, Rev. 0, DRA-55180-40, Rev. 0, DRA-55347-47, Rev. 0, DRA-52378-539, Rev. 1, DRA-52675-3, Rev. 0
e. 2-47W610-3-1D, Rev. 2, Electrical Control Diagram Main Aux FWSystem, DRA-52319-10, Rev. 0, DRA-53600-8, Rev. 0, DRA-55180-41, Rev. 0, DRA-55347-58, -59, Rev. 0, 52378-417, Rev. 2, DRA-53217-56, Rev. 0, DRA-54144-233, Rev. 0
f. 2-47W610-3-2, Rev. 1, Electrical Control Diagram Main & Aux FWSystem, DRA-52319-11, Rev. 0, DRA-55180-42, Rev. 0, DRA-55347-60, Rev. 0, DRA-52378-540, Rev. 1, DRA-52675-5, Rev. 0
g. 2-47W610-3-2A, Rev. 3, Electrical Control Diagram Main & Aux FWSystem, DRA-52319-12, Rev. 0, DRA-53315-2,-3, Rev. 0, DRA-53559-157, Rev. 0, 53600-9, Rev. 0, 53876-301 ,-304, Rev. 0, DRA-'55180-43, Rev. 0, DRA-55347-61, -62, Rev. 0, DRA-52378-418, Rev.1, DRA-52378-419, Rev.2, DRA-53217-57, Rev. 0, DRA-51444-2341Rev. 0
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2.2 Developmental References (continued)
h. 2-47W610-3-2B, Rev. 1, Electrical Control Diagram Main & Aux FWSystem, DRA-52319-13, Rev. 0, DRA-55180-44, rev. 0, DRA-55347-63, Rev. 0, DRA-52378-541, Rev. 1
i. 2-47W610-3-2C, Rev. 3, Electrical Control Diagram Main & Aux FWSystem, DRA-52319-14, rev. 0, DRA-53600-10, Rev. 0, DRA-55180-45, Rev. 0, DRA-55347-64,-65, Rev. 0, DRA-52378-420, Rev. 1, DRA-53217-58, Rev. 0, DRA-54144-235, Rev. 0
j. 2-47W610-3-4, Rev. 2, Electrical Control Diagram Main & Aux FWSystem, DRA-52319-15, Rev. 0, DRA-53097-14, Rev. 0, DRA-53315-1, Rev. 0, DRA-53876-305, Rev. 1, DRA-53876-307, Rev. 0, DRA-52378-421, Rev. 0
k. 2-47W61.1-3-2, Rev. 5, Electrical Logic Diagram Feedwater System,DRA-53876-317, Rev. 0, 54144-237,-238, Rev. 0
1. 2-47W611-3-3, Rev. 2, Electrical Logic Diagram Auxiliary FeedwaterSystem, DRA-52376-7, Rev. 1, DRA-52343-34,-35, Rev. 0, DRA-54208-21, Rev. 0, DRA-52427-43, Rev. 0, DRA-53288-69,-70, Rev. 0,DRA-54145-7,-8, Rev. 0
m. 2-47W611-3-5, Rev. 2, Electrical Logic Diagram Feedwater System,DRA-53876-316, Rev. 0, DRA-52378-604, Rev. 1
n. 2-45B655-3C, Rev. 0, Main Control Room Annunciator Inputs WindowBox XA-55-3C, DRA-53301-132, Rev. 0, DRA-54449-12, Rev. 0,DRA-55180-3, Rev. 0, DRA-52343-230, Rev. 0, DRA-52378-222,-233,-252, Rev. 0, 54144-1, Rev. 0, DRA-54145-12, Rev. 0
o. 2-45B655-4C, Rev. 0, Main Control Room Annunciator Inputs WindowBox XA-55-4C, DRA-55180-7, Rev. 0, DRA-52408-10, Rev. 0, DRA-53439-10, Rev. 0, DRA-53939-329, Rev. 0
p. 2-45B655-4D, Rev. 0, Main Control Room Annunciator Inputs WindowBox XA-55-4D, DRA-55180-9, Rev. 0
q. 2-45B655-6B, Rev. 0, Main Control Room Annunciator Inputs WindowBox XA-55-6B, DRA-53301-135, Rev. 0, DRA-55180-14, Rev. 0
5. Vendor Drawings
a. 108D408-1, Rev. 43, Process Control Block Diagram
b. 108D408-17, Rev. 12, Process Control Block Diagram
c. 108D408-19, Rev. 10, Process Control Block Diagram
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2.2 Developmental References (continued)
d. 108D408-20, Rev. 16, Process Control Block Diagram
e. 108D408-33, Rev. F, Process Control Block Diagram
f. 108D408-34, Rev. 9, Process Control Block Diagram
g. 108D408-41, Rev. D, Process Control Block Diagram
h. 108D408-49, Rev. 2, Process Control Block Diagram
i. 108D408-50, Rev. 2, Process Control Block Diagram
j. 108D408-54, Rev. 2, Process Control Block Diagram
k. 108D408-55, Rev. 3, Process Control Block Diagram
I. 108D408-56, Rev. 3, Process Control Block Diagram
m. 2-54114-1-7246D11-06, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-763, Rev. 0
n. 2-54114-1-7246Dl1-07, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-764, Rev. 0
o. 2-54114-1-7246Dl1-09, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-766, Rev. 0
p. 2-54114-1-7246311-11, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-768, Rev. 0
q. 2-54114-1-7246Dl1-12, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-769, Rev. 0
r. 2-54114-1-7246D11-20, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-777, Rev. 0, DRA-53352-96,Rev. 0
s. 2-54114-1-7246D11-21, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-778, Rev. 0
t. 2-54114-1-7246Dl1-22, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-779, Rev. 0
u. 2-54114-1-7246Dl1-24, Rev. K, Solid State Protection SystemInterconnection Diagram, DRA-52328-781, Rev. 0
v. 1082H70-27D, Rev. AE, Output Relays
2.2
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Developmental References (continued)
6. Other
a. 2-TSD-3A-2, Rev. 0, Feedwater and Steam Generator Level TestScoping Document
b. SSD-1-LPF-3-35, Rev. 11, Scaling & Setpoint Document LoopDrawing Steam Generator I Level Control To be verified against SSD-2-LPF-3-35 [Later] in Appendix A
c. SSD-1-LPF-3-48, Rev. 10, Scaling & Setpoint Document LoopDrawing Steam Generator 2 Level Control To be verified against SSD-2-LPF-3-48 [Later] in Appendix A
d. SSD-1-LPF-3-90, Rev. 10, Scaling & Setpoint Document LoopDrawing Steam Generator 3 Level Control To be verified against SSD-2-LPF-3-90 [Later] in Appendix A
e. SSD-1-LPF-3-103, Rev.10, Scaling & Setpoint Document LoopDrawing Steam Generator 4 Level Control To be verified against SSD-2-LPF-3-103 (Later] in Appendix A
C. Vendor Manuals
None
D. Documents
1. 2-L-3-38, Rev. 0, Setpoint and Scaling Document Steam Generator NRLevel
2. 2-L-3-39, Rev. 0, Setpoint and Scaling Document Steam Generator NRLevel
3. 2-L-3-42, Rev. 0, Setpoint and Scaling Document Steam Generator NRLevel
4. 2-L-3-51, Rev. 0, Setpoint and Scaling Document Steam Generator NRLevel
5. 2-L-3-52, Rev. 0, Setpoint and Scaling Document Steam Generator NRLevel
6. 2-L-3-55, Rev. 0, Setpoint and Scaling Document Steam Generator NRLevel
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2.2 Developmental References (continued)
7. 2-L-3-93, Rev. 0, Setpoint and Scaling Document Steam Generator NRLevel
8. 2-L-3-94, Rev. 0, Setpoint and Scaling Document Steam Generator NRLevel
9. 2-L-3-97, Rev. 0, Setpoint and Scaling Document Steam Generator NRLevel
10. 2-L-3-106, Rev. 0, Setpoint and Scaling Document Steam Generator NRLevel
11. 2-L-3-107, Rev. 0, Setpoint and Scaling Document Steam Generator NRLevel
12. 2-L-3-110, Rev. 0, Setpoint and Scaling Document Steam Generator NR
Level
13. 2-SOI-2&3.01, Rev. 0 [Draft], Condensate and Feedwater System
14. 2-SOI-15.01, Rev. 0 [Draft], Steam Generator Blowdown System
3.0 PRECAUTIONS AND LIMITATIONS
A. Standard precautions shall be followed for working around energized electricalequipment in accordance with TVA Safety Procedure 1021.
B. Steps may be repeated if all components cannot be tested in a step. However,if the test has been exited, prerequisite steps must be re-verified and aChronological Test Log (CTL) entry made.
C. Discrepancies between component ID tags and the description in aprocedure/instruction do not require a Test Deficiency Notice, TDN, in.accordance with SMP-14.0, if the UNIDs match, exclusive of place-keepingzeros and train designators (e.g. 2-HS-31-468 vs. 2-HS-031-0468) and thenoun description is sufficient to identify the component. If the component labelneeds to be changed,. a Tag Request Form (TR Card) should be processed inaccordance with TI-12.14. Make an entry in the CTL and continue testing.
D. All wires removed/lifted from a terminal shall be identified and taped or coveredwith an insulator to prevent personnel or equipment hazard and possiblespurious initiations. The wires should be labeled with the work implementing.document number that required them to be lifted if left unattended.
E. All open problems are to be tracked by a corrective action document andentered on the appropriate system punchlist.
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3.0 PRECAUTIONS AND LIMITATIONS (continued)
F. Problems identified during the test shall be annotated on the CTL from SMP-9.0including a description of the problem, the procedure step when/where theproblem was identified, corrective action steps taken to resolve the problem,and the number of the corrective action document, if one was required.
G. Observe all Radiation Protection (RP) requirements when working in or nearcontaminated areas.
H. Ensure there are no adverse effects to the operation of Unit 1 structures,systems, or components.
1. Test personnel will coordinate with Unit 1 Operations when manipulating Unit 1equipment if required.
J. System water chemistry is within system specifiable parameters especially forfluids supplied from external sources.
K. During Hot Functional Testing, feedwater additions should be controlled tominimize the thermal stress cycles of the feedwater nozzle. Feedwateradditions should be slow in order to minimize the possibility of water hammerand thermal shock to the steam generator internals.
L. Primary to secondary differential pressure should not exceed 1600 psid duringnormal plant operations.
M. At Operations discretion, steam generator blowdown may be initiated orincreased during level decreases to allow some feedwater flow to bemaintained. It is preferable that blowdown be kept to a minimum during levelincreases to avoid lowering Reactor Coolant System (RCS) temperature due toexcessive feedwater flowrates.
N. The Steam Generator Hi Level Alarms and Low Pwr Lo Level Alarmsassociated with 2-L-148, 2-L-156, 2-L-164, 2-L-171, 2-L-172, 2-L-173, 2-L-174,and 2-L-175 should operate at approximately 74% and 25%. If this does notoccur, appropriate work documents should be generated and an entry made inthe CTL.
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4.0 PREREQUISITE ACTIONS
NOTE
Prerequisite steps may be performed in any order unless otherwise stated and should be completedas close in time as practicable to the start of the instruction subsection to which they apply.
4.1 Preliminary Actions
[1] OBTAIN copies of the applicable forms from the latest revisionof SMP-9.0, AND
ATTACH to this PTI for use during the performance of this PTI.
[2] ENSURE changes to the references listed on Appendix A,have been reviewed, and determined NOT to adversely affectthe test performance.
[3] VERIFY current revisions and change paper for referenceddrawings has been reviewed and determined NOT toadversely affect the test performance, and
ATTACH documentation of current drawing revision numbersand change paper that were reviewed to the data package.
[4] VERIFY the test/performance copy of this Preoperational TestInstruction (PTI) is the current revision including any changenotices and as needed, each test person assisting in this testhas the current revision including any change notices.
[5] EVALUATE open items in Watts Bar Integrated TaskEquipment-List (WITEL), ANDENSURE that they will NOT adversely affect the test
performance results.
A. Subsection 6.1
B. Subsection 6.2
C. Subsection 6.3
D. Subsection 6.4 _
[6] ENSURE required Component Testing has been completedprior to start of test
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4.1 Preliminary Actions (continued)
[7] ENSURE outstanding Design Change Notices (DCN's),Engineering Document Construction Releases (EDCR's) orTemporary Alterations (TA's) do NOT adversely impact testing,AND
ATTACH documentation of DCN's, EDCR's and TA's thatwere reviewed to the data package.
[8] ENSURE a review of outstanding Clearances has beencoordinated with Operations for impact to the testperformance. If required, items will be recorded in AppendixB, Temporary Condition Log.
[9] ENSURE all piping supports required for testing are installedand adjusted as required.
[10] VERIFY System cleanness as required for the performance ofthis test has been completed in accordance with SMP-7.0.
[11] VERIFY plant instruments required for test performance, listed onAppendix C, Permanent Plant Instrumentation Log, have been filled,
vented; (as required) placed in service and are within their calibrationinterval.
A. Subsection 6.1
B. Subsection .6.2
C. Subsection 6.3
D. Subsection. 6.4
[12] VERIFY Measuring and Test Equipment (M&TE) required for testperformance has been (as required) filled, vented , placed inservice and recorded on Measuring and Test Equipment Log(Appendix F of SMP-9.0)
A. Subsection 6.1
B. Subsection 6.2
C. Subsection 6.3
D. Subsection 6.4
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4.1 Preliminary Actions (continued)
[13] VERIFY M&TE calibration due dates will support the completionof this test performance.
A. Subsection 6.1
B. Subsection 6.2
C. Subsection 6.3
D. Subsection 6.4
[14] ENSURE System 55, Annunciator and Sequential EventsRecording System applicable TBK switches are ON, the applicableMaster Switches are ON, and window software input (s) are
ENABLED for the following'Annunciator windows:
A. 2-XA-55-3C/60-B (SubSection 6.1)
B. 2-XA-55-3C/60-D (SubSection 6.1)
C. 2-XA-55-3C/61-B (SubSection 6.2)
D. 2-XA-55-3C/61-D (SubSection 6.2)
E. 2-XA-55-3C/62-B (SubSection 6.3)
F. 2-XA-55-3C/62-D (SubSection 6.3)
G. 2-XA-55-3C/63-B (SubSection 6.4)
H. 2-XA-55-3C/63-D (SubSection 6.4)
I. 2-XA-55-3C/63-F (SubSections 6.1, 6.2, 6.3, and 6.4)
J. 2-XA-55-6B/116-B (SubSection 6.1)
K. 2-XA-55-6B/1 17-B (SubSection 6.2)
L. 2-XA-55-6B/1 18-B (SubSection 6.3)
M. 2-XA-55-6B/1 19-B (SubSection 6.4)
N. 2-XA-55-6B/1 16-D (SubSection 6.1)
0. 2-XA-55-6B/1 17-D (SubSection 6.2)
P. 2-XA-55-6B/1 18-D (SubSection 6.3).
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4.1 Preliminary Actions (continued)
Q. 2-XA-55-6B/1 19-D (SubSection 6.4)
R. 2-XA-55-6B/1 16-E (SubSection 6.1)
S. 2-XA-55-6B/11 17-E (SubSection 6.2)
T. 2-XA-55-6B/118-E (SubSection 6.3)
U. 2-XA-55-6B/1 19-E (SubSection 6.4)
[15] ENSURE components contained within the boundaries of thistest are under the jurisdictional control of PreoperationalStartup Engineering (PSE) and/or Plant Operations.
[16] PERFORM a pretest walkdown on equipment to be tested toensure no conditions exist that will impact test performance.
[17] CONDUCT a pretest briefing with Test and Operationspersonnel in accordance with SMP-9.0.
[18] ESTABLISH communications in areas where testing is to beconducted.
[191 REVIEW preventive maintenance for system/componentscovered by this test, AND
VERIFY no conditions exist that will impact test performance.
4.2 Special Tools, Measuring and Test Equipment, Parts, andSupplies
[11 ENSURE eighteen (18) digital multimeters (0-1.5 VDC +0.02%) are available. Twelve will be installed in Step 4.3[3]and six will be installed and used consecutively in Sections6.1, 6.2, 6.3, and 6.4
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4.3 Field Preparations
[1] ENSURE the Plant Computer is available and the ComputerPoints listed on Table 1 are active and the description andstatus for each computer point has been verified.
[2] ENSURE the following systems are operational and have been
placed in service to the extent necessary to perform this test:
A. System 032, Control Air - Provide control air to all AOVs.
B. System 003A, Main Feedwater - Has the SteamGenerator Level controls.
C. System 003B, Auxiliary Feedwater - Provide feedwater toraise Steam Generator levels.
D. System 015, Steam Generator Blowdown - Provideblowdown to lower Steam generator levels.
E. System 002, Condensate - provide a source of water tothe Main Feedwater System and condenser vacuum.
F. System 99, Reactor Protection System - inputs to and.from the Steam Generator level control system.
G. System 98, Foxboro I/A (DCS) - inputs to and from theSteam Generator Level Control.
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4.3 Field Preparations (continued)
NOTE
The test points are located on the front of each of the cabinets listed in 4.3[3]. If there arenot enough multi-meters available to install all of them for all Subsections, the test mayproceed with installation of those necessary to perform each subsection.
[3] ENSURE voltmeters are installed and labeled at the followinglocations:
A.: Panel 2-R-12, SG 1 Level trip, Test Point 2LP/517B(Subsection 6.1) (Control Building Auxiliary InstrumentRoom 708/C10P)
Cv
B. Panel 2-R-11, SG 1 Level trip, Test Point 2LP/518B(Subsection 6.1) (Control Building Auxiliary InstrumentRoom 708/C9P)
Cv
C. Panel 2-R-5, SG 1 Level trip, Test Point 2LP1519B(Subsection 6.1) (Control Building Auxiliary InstrumentRoom 708/C9Q)
Cv
D. Panel 2-R-12, SG 2 Level trip, Test Point 2LP/527B(Subsection 6.2) (Control Building Auxiliary InstrumentRoom 708/CI0P)
CV
E. Panel 2-R-1 1, SG 2 Level trip, Test Point 2LP/528B(Subsection 6.2) (Control Building Auxiliary InstrumentRoom 708/C9P)
Cv
F. Panel 2-R-5, SG 2 Level trip, Test Point 2LP/529B(Subsection 6.2) (Control Building Auxiliary InstrumentRoom 708/C9Q)
CV
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4.3 Field Preparations (continued)
G. Panel 2-R-12, SG 3 Level trip, Test Point 2LP/537B(Subsection 6.3) (Control Building Auxiliary InstrumentRoom 708/C10P)
CV
H.: Panel 2-R-1 1, SG 3 Level trip, Test Point 2LP/538B(Subsection 6.3)(Control Building Auxiliary InstrumentRoom 708/C9P)
CV
I. Panel 2-R-5, SG 3 Level trip, Test Point 2LP/539B(Subsection 6.3) (Control Building Auxiliary InstrumentRoom 708/C9Q)
CV
J. Panel 2-R-12, SG 4 Level trip, Test Point 2LP/547B(Subsection 6.4)(Control Building Auxiliary InstrumentRoom 708/C10P)
CV
K. Panel 2-R-1 1, SG 4 Level trip, Test Point 2LP/548B(Subsection 6.4) (Control Building Auxiliary InstrumentRoom 708/C9P)
CV
L. Panel 2-R-5, SG 4 Level trip, Test Point 2LP/549B(Subsection 6.4) (Control Building Auxiliary InstrumentRoom 708/C9Q)
CV
[4] VERIFY Steam Generator I level is stable at 38%(programmed level) as indicated on 2-FR-3-35, STM-FWFLOW & NR LEVEL on panel 2-M-4 (SubSection 6.1).
[5] VERIFY Steam Generator 2 level is stable at 38%(programmed level) as indicated on 2-FR-3-48, STM-FWFLOW & NR LEVEL on panel 2-M-4 (SubSection 6.2).
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4.3 Field Preparations (continued)
[6] VERIFY Steam Generator 3 level is stable at 38%(programmed level) as indicated on 2-FR-3-90, STM-FWFLOW & NR LEVEL on panel 2-M4 (SubSection 6.3).
[7] VERIFY Steam Generator 4 level is stable at 38%-(programmed level) as indicated on 2-FR-3-103, STM-FWFLOW & NR LEVEL on panel 2-M-4 (SubSection 6.4).
[8] VERIFY that Hot Functional Testing is in progress at the 5570 Fplateau per 2-PTI-68-1.
[9] VERIFY that SG 1 LEVEL CONTROL is in Manual.(SubSection 6.1)
[10] VERIFY that SG 2 LEVEL CONTROL is in Manual.(SubSection 6.2)
[11] VERIFY that SG 3 LEVEL CONTROL is in Manual.(SubSection 6.3)
[12] VERIFY that SG 4 LEVEL CONTROL is in Manual.(SubSection 6.4)
,[13] ENSURE that the field side wiring is landed with plastic screwsin 2-R-48 at the terminals listed on Table 2 in accordance withSMP-15.0. These will isolate the trips and Feedwater isolationsignals.
[14] ENSURE that the field side wiring is landed with plastic screwsin 2-R-51 at the terminals listed on Table 3 in accordance withSMP-15.0. These will isolate the trips and Feedwater isolationsignals.
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4.4 Approvals and Notifications
[1] Prior to start of the test; OBTAIN permission of thePreoperational Startup Manager to start the test.
Preoperational Startup ManagerSignature
Date
[21 Prior to start of the test; OBTAIN the Unit 2 Supervisor's(US/SRO) or Shift Manager's (SM) authorization.
US/SRO/SM Signature Date
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5.0 ACCEPTANCE CRITERIA
A. Paragraph/sentences/tables/steps which determine acceptance criteria shall bedesignated by [ACC CRIT]
B. The NR level instrumentation shall agree between each loop
1. The highest and lowest indication for the three NR level indicators for eachsteam generator shall be within 5% of each other.
a. Steam Generator 1 (Step 6.1[461)
b. Steam Generator 2 (Step 6.2[46])
c. Steam Generator 3 (Step 6.3[46])
d. Steam Generator 4 (Step 6.4[46])
2. The highest and lowest calculated level for the three NR level transmittersfor each steam generator shall be within 1.1% of each other.
a. Steam Generator 1 (Step 6.1(46])
b. Steam Generator 2 (Step 6.2[46])
c. Steam Generator 3 (Step 6.3[46])
d. Steam Generator 4 (Step 6.4[46])
C. The NR level instrumentation provides digital outputs to the solid stateprotection system for the following conditions.
1. Hi-Hi Level 82.4% (79.9% - 84.9%)
a. Steam Generator 1 (Step 6.1(11])
b. Steam Generator 2 (Step 6.2111])
c. Steam Generator 3 (Step 6.3(11])
d. Steam Generator 4 (Step 6.4[11])
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5.0 ACCEPTANCE CRITERIA (continued)
2. Lo-Lo Level 17% (14.5% - 19.5%)
a. Steam Generator I (Step 6.1[311)
b. Steam Generator 2 (Step 6.2131])
c. Steam Generator 3 (Step 6.3[31])
d. Steam Generator 4 (Step 6.4[31])
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6.0 PERFORMANCE ~NOTES
1) Subsections 6.1, 6.2, 6.3, and 6.4 may be performed in any order, but cannot beperformed concurrently.
Table 6.0-1 Comparison of Narrow Range and Wide Range Indications
Narrow Range Wide Range Elevation
100% 100% 773.833
90% 95.8% 771.891
80% 91.6% 769.950
70% 87.4% 768.008
60% 83.2% 766.066
50% 79.0% 764.125
40% 74.8% 762.183
30% 70.6% 760.241
20% 66.4% 758.300
10% 62.1% 756.358
0% 58.0% 754.420
These numbers were calculated from the elevations given for the wide and narrowranges from the Scaling and Setpoint Documents (SSD).
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
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6.1 SG I Narrow Range Level Instrument TestNOTES
1) At the Operators discretion, Steam Generator Blowdown may be initiated or increased.during level decreases to allow some feedwater flow to the generator. It is preferablethat blowdown flow be maintained as low as possible to avoid decreasing primarytemperature due to excessive feedwater flow.
2) The levels in the Steam Generator are adjusted by regulation of feedwater flow(2-SOI-2&3.01), into the generator, and blowdown flow from the generator (2-SOI-15.01). Operation of the equipment required to perform these actions is not a part ofthis test and therefore, will not be specifically detailed in this test.
[11 VERIFY prerequisites listed in Section 4.0 for Subsection 6.1
have been completed.
[2] COMPLETE Data Sheet 1.
[3] VERIFY Annunciator Window 2-XA-55-3C, 63-F, SG LEVELDEVIATION, at 2-M-3 is CLEAR.
[4] VERIFY Unit 2 Events Display Legend indicates 63-F, SG 1LEVEL HI is CLEAR.
[5) SLOWLY INCREASE the level in SG 1 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, alarms.
A. VERIFY Unit 2 Events Display.Legend indicates 63-F SG1 LEVEL HI (LS-3-42D) is in ALARM (Red).
B. RECORD the level indication from 2-FR-3-35, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE), at 2-M-4.
2-FR-3-35, STM FW FLOW & NR LEVEL* %
C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.115)B.[Programmed level +5% (_>2%, <8%)]
- 38% =
[6] SLOWLY INCREASE the level in Steam Generator 1 untilapproximately 50% is indicated on 2-LI-3-38, SG 1 LEVEL at2-M-4.
[7] COMPLETE Data Sheet 2.
Date
6.1 SG I Narrow Range Level Instrument Test (continued)
NOTE
Annunciator Window 2-XA-55-3C, 60-B, SG1 LEVEL HI, will alarm at approximately 74%level. The alarm may be acknowledged and silenced. No other action is required.
[8] SLOWLY INCREASE the level in Steam Generator 1 untilapproximately 75% is indicated on 2-LI-3-38, SG 1 LEVEL at2-M-4.
[9] COMPLETE Data Sheet 3.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 28 of 182
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6.1 SG I Narrow Range Level Instrument Test (continued)
[10] INSTALL and LABEL digital multimeters AND
VERIFY trip signals are OFF as indicated by presence ofvoltage at the following locations: (2-R-46 - Control BuildingAuxiliary Instrument Room 708/C8P, 2-R-49 - Control BuildingAuxiliary Instrument Room 7081C8P)
A. TB 403-5 and TB 403-6 in Panel 2-R-46(Dwg 45N2676-2)
Cv
B. TB 403-5 and TB 403-6 in Panel 2-R-49.(Dwg 45N2677-2)
Cv
C. TB 304-1 and TB 304-2 in Panel 2-R-46(Dwg 45N2676-2)
Cv
D. TB 304-1 and TB 304-2 in Panel 2-R-49(Dwg 45N2677-2)
Cv
E. TB 205-9 and TB 205-10 in Panel 2-R-46(Dwg 45N2676-1)
F. TB 205-9 and TB 205-10 in Panel 2-R-49(Dwg 45N2677-1)
Cv
Cv
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 29 of 182
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6.1 SG 1 Narrow Range Level Instrument Test (continued)
NOTE
Annunciator Window 2-XA-55-6B, 116-B, SG 1 LEVEL HI-HI, will alarm at approximately82% level. The alarm may be acknowledged and silenced. No other action is required.
NOTE
Steps 6.1 [11]A, B, and C may be signed off as they occur
[11] SLOWLY INCREASE the level in Steam Generator 1 AND
A. WHEN TB 403-5 and TB 403-6 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),
RECORD the SG 1 Level on 2-LI-3-42, SG 1 LEVEL, at2-M-4. (ACC CRIT) 5.OC.1 [82.4% (79.9% - 84.9%)]
B. WHEN TB 304-1 and TB 304-2 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),
RECORD the SG I Level on 2-LI-3-39, SG 1 LEVEL, at2-M-4. (ACC CRIT) 5.0C.1 [82.4% (79.9% - 84.9%)]
C. WHEN TB 205-9 and TB 205-10 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),
RECORD the SG 1 Level on 2-LI-3-38, SG 1 LEVEL, at2-M-4. (ACC CRIT) 5.OC.1 [82.4% (79.9% - 84.9%)]
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000
Page 30 of 182
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6.1 SG 1 Narrow Range Level Instrument Test (continued)
NOTE
The following two steps will raise the SG 1 level to the upper NR tap. Data collection shouldbe completed as rapidly as possible.
[12] SLOWLY INCREASE the level in the SG 1 until the meterslabeled SG 1 installed in 2-R-5, 2-R-1 1, and 2-R-12 no longerindicate increasing voltage which indicates the water level hasreached the upper tap:
A. 2-R-5, SG 1 Level
B. 2-R-11, SG 1 Level
C. 2-R-12, SG 1 Level
[13] COMPLETE Data Sheet 4
[14] SLOWLY DECREASE the level in SG I until level change isindicated on the following instruments which indicates thewater level has fallen below the upper tap:
A. 2-LI-3-42, SG 1 LEVEL
B. 2-LI-3-39, SG 1 LEVEL
C. 2-LI-3-38, SG 1 LEVEL
[15] COMPLETE Data Sheet 5
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 31 of 182
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6.1 SG 1 Narrow Range Level Instrument Test (continued)
NOTE
Steps 6.1[16]A through 6.1[16]C may be signed off as they occur.
NOTE
Annunciator Window 2-XA-55-6B, 116-B, SG 1 LEVEL HI-HI, will clear at approximately81% level. The alarm may be acknowledged and silenced. No other action is required.
[16] SLOWLY DECREASE the level in SG 1 AND
A. WHEN TB 403-5 and TB 403-6 in Panels 2-R-46 and 2-R-49 indicate trip signals are OFF (voltage indicated),
RECORD the SG 1 Level on 2-LI-3-42, SG 1 LEVEL, at2-M-4, indication. [81.4% (78.9% - 83.9%)]
B. WHEN TB 304-1 and TB 304-2 in Panels 2-R-46 and 2-R-49 indicate trip signals are OFF (voltage indicated),
RECORD the SG 1 Level on 2-LI-3-39, SG 1 LEVEL, at2-M-4, indication. [81.4% (78.9% - 83.9%)]
C. WHEN TB 205-9 and TB 205-10 in Panels 2-R-46 and 2-R-49 indicate trip signals are OFF (voltage indicated),
RECORD the SG 1 Level on 2-L1-3-38, SG 1 LEVEL, at2-M-4, indication. [81.4% (78.9% - 83.9%)]
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 32 of 182
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6.1 SG 1 Narrow Range Level Instrument Test (continued)
[171 REMOVE Digital Multimeters installed in at the followinglocations:
A. TB 403-5 and TB 403-6 in Panel 2-R-46
B. TB 403-5 and TB 403-6 in Panel 2-R-49
CV
CV
C. TB 304-1 and TB 304-2 in Panel 2-R-46
CV
D. TB 304-1 and TB 304-2 in Panel 2-R-49
E. TB 205-9 and TB 205-10 in Panel 2-R-46
CV
CV
CV
F. TB 205-9 and TB 205-10 in Panel 2-R-49
NOTE
Annunciator Window 2-XA-55-3C, 60-B, SG 1 LEVEL HI, will clear at approximately 74%level. The alarm may be acknowledged and silenced. No other action is required. j
[18] SLOWLY DECREASE the level in SG 1 until approximately75% is indicated on 2-LI-3-38, SG 1 LEVEL.
[19] COMPLETE Data Sheet 6
.[20] SLOWLY DECREASE the level in SG 1 until approximately50% is indicated on 2-LI-3-38, SG 1 LEVEL.
[21] COMPLETE Data Sheet 7
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 33 of 182
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6.1 SG 1 Narrow Range Level Instrument Test (continued)
[22] SLOWLY DECREASE the level in SG 1 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, CLEARS.
A., VERIFY Unit 2 Events Display Legend indicates 63-F SG1 LEVEL HI (LS-3-42D) is NORMAL (Blue)
B. RECORD the level indication from 2-FR-3-35, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE)
C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.1[22]B.[Programmed level +4% (>1 %, :7%)]
% - 38% =%
[23] SLOWLY DECREASE the level in-SG 1 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, ALARMS.
A. VERIFY Unit 2 Events Display Legend. indicates 63-F SG1 LEVEL LO (LS-3-42E) is in ALARM (Red)
B. RECORD the level indication from 2-FR-3-35, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE)
C. DETERMINE the percent deviation by subtracting theindication recorded in Step 6.1[23]B from 38%.[Programmed level -5% (>2%,-<8%)]
% - 38% =
NOTE
Annunciator Window 2-XA-55-3C, 60-D, SG 1 LEVEL LO, will alarm approximately 25%level. The alarm may be acknowledged and silenced. No other action is required.
[24] SLOWLY DECREASE the level in SG 1 until approximately25% is indicated on 2-LI-3-38, SG ILEVEL.
[25] COMPLETE Data Sheet 8
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 34 of 182
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6.1 SG I Narrow Range Level Instrument Test (continued)
[26] INSTALL and LABEL Digital Multimeters AND
VERIFY trip signals are OFF as indicated by presence ofvoltage at the following locations: (2-R-46 - Control BuildingAuxiliary Instrument Room 708/C8P, 2-R-49 - Control BuildingAuxiliary Instrument Room 708/C8P)
A. TB 404-5 and TB 404-6 in Panel 2-R-46
(Dwg 45N2676-2)
CV
B. TB 404-5 and TB 404-6 in Panel 2-R-49(Dwg 45N2677-2)
CV
C. TB 305-1 and TB 305-2 in Panel 2-R-46(Dwg 45N2676-2)
CV
D. TB 305-1 and TB 305-2 in Panel 2-R-49(Dwg 45N2677-2)
CV
E. TB 206-3 and TB 206-4 in Panel 2-R-46(Dwg 45N2676-1)
CV
F. TB 206-3 and TB 206-4 in Panel 2-R-49(Dwg 45N2677-1)
CV
[27] VERIFY Annunciator Window 2-XA-55-6B, 116-D, SG 1LO-LO LEVEL TTD INITIATED, at 2-M-6 is CLEAR.
[28] SLOWLY DECREASE the level in Steam Generator 1.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
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6.1 SG I Narrow Range Level Instrument Test (continued)
NOTE
Steps 6.1[31]A through 6.1[31]F may be signed off as they occur.
NOTE
Annunciator Window 2-XA-55-6B, 116-E, SG 1 LEVEL LO-LO, will alarm at approximately17% level. The alarm may be acknowledged and silenced. No other action is required.
[29] VERIFY Annunciator Window 2-XA-55-6B, 116-D, SGI LO-LOLEVEL TTD INITIATED, at 2-M-6, ALARMS as the SteamGenerator level reaches 17% (14.5 %- 19.5%).
[30] VERIFY the following Event Display Legends are in alarm.Stop decreasing Steam Generator level when all three are in.
A. 116-D SG I LOLO LEVEL TTD INITIATED (ILY/519H).
B. 116-D SG 1 LOLO LEVEL TTD INITIATED (ILY/518H).
C. 116-D SG 1 LOLO LEVEL TTD INITIATED (ILY/517H).
NOTE
After the time delay (TTD) has finished (approximately 8 minutes), all three trip channelsshould come in.
[31] RECORD the level from the specified indicators AND
VERIFY status of associated computer points as the followingtrip signals come ON as indicated by absence of voltage at thefollowing locations:
A. TB 404-5 and TB 404-6 in Panel 2-R-46 and 2-R-49, SG 1Level indication on 2-L-3-42, SG 1 LEVEL, at 2-M-4.(ACC CRIT) 5.0C.2 [17% (14.5 %- 19.5%)]
B. Computer Point L0405D indicates TRIP.(ACC CRIT) 5.OC.2
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
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6.1 SG I Narrow Range Level Instrument Test (continued)
C. TB 305-1 and TB 305-2 in: Panel 2-R-46 and 2-R-49, SG 1Level indication on, 2-LI-3-39, SG 1 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5 %- 19.5%)]
D. VERIFY Computer Point L0404D indicates TRIP.(ACC CRIT) 5.OC.2
E. TB 206-3 and TB 206-4 in Panel 2-R-46 and 2-R-49, SG ILevel indication on 2-LI-3-38, SG 1 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5 %- 19.5%)]
F. Computer Point L0403D indicates TRIP. (ACC CRIT).5.OC.2
NOTE
The following two steps will decrease the Steam Generator Level to the lower NR tap. Datacollection should be completed as rapidly as possible.
[32] SLOWLY DECREASE the level in SG 1 until the meterslabeled SG 1 installed in 2-R-5, 2-R-11, and 2-R-12 no longerindicate decreasing voltage which indicates the water level hasreached the lower tap.
A. 2-R-5, SG 1 Level trip
B. 2-R-1 1, SG 1 Level trip
C. 2-R-12, SG I Level trip
[33] COMPLETE Data Sheet 9.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 37 of 182
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6.1 SG 1 Narrow Range Level Instrument Test (continued)
[34] SLOWLY INCREASE the level in SG 1 until level change isindicated on the following instruments which indicates thewater level has risen above the lower tap:
A. 2-LI-3-42, SG 1 LEVEL
B. 2-LI-3-39, SG 1 LEVEL
C. 2-LI-3-38, SG 1 LEVEL
[35] COMPLETE Data Sheet 10.~NOTE
Steps 6.1 (36]A through 6.1 [36]F may be signed off as they occur.
INOTE
Annunciator Window 2-XA-55-6B, 11 6-E, SG 1 LEVEL LO-LO, will clear at approximately18% level. The alarm may be acknowledged and silenced. No other action is required.
[36] SLOWLY INCREASE the level in SG 1 AND
RECORD the level from the specified indicators AND
VERIFY status of associated computer points as the followingtrip signals CLEAR as indicated by presence of voltage at thefollowing locations:
A. TB 404-5 and TB 404-6 in Panel 2-R-46 and 2-R-49,2-LI-3-42, SG 1 LEVEL, at 2-M-4. [18% (15.5% - 20.5%)]
B. Computer Point L0405D indicates NOT TR.
C. TB 305-1 and TB 305-2 in Panel 2-R-46 and 2-R-49,2-LI-3-39, SG 1 LEVEL, at 2-M-4.[18% (15.5% - 20.5%)]
D. Computer Point L0404D indicates NOT TR.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 38 of 182
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6.1 SG I Narrow Range Level Instrument Test (continued)
E. TB 206-3 and TB 206-4 in Panel 2-R-46 and 2-R-49,2-LI-3-38, SG 1 LEVEL, at 2-M-4. [18% (15.5% - 20.5%)]
F. Computer Point L0403D indicates NOT TR.
[37] REMOVE Digital Multimeters installed at the followinglocations:
A. TB 404-5 and TB 404-6 in Panel 2-R-46
CV
B. TB 404-5 and TB 404-6 in Panel 2-R-49
CV
C. TB 305-1 and TB 305-2 in Panel 2-R-46
CV
D. TB 305-1 and TB 305-2 in Panel 2-R-49
CV
E. TB 206-3 and TB 206-4 in Panel 2-R-46
CV
F. TB 206-3 and TB 206-4 in Panel 2-R-49
CV
[38] VERIFY Annunciator Window 2-XA-55-6B, 116-D, SG 1LO-LO LEVEL TTD INITIATED, CLEARS when all trip signalsare cleared.
[39] VERIFY Unit 2 Events Display Legend indicates 116-D, SG 1LO-LO LEVEL TTD INITIATED is in CLEAR (Blue).
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 39 of 182
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6.1 SG I Narrow Range Level Instrument Test (continued)
NOTE
Annunciator Window 2-XA-55-3C, 60-D, SG 1 LEVEL LO, will clear at approximately 25%level. The alarm may be acknowledged and silenced. No other action is required.
[40] SLOWLY INCREASE the level in Steam Generator 1 untilapproximately 25% is indicated on 2-LI-3-38, SG 1 LEVEL.
[41] COMPLETE Data Sheet 11
[42] SLOWLY INCREASE the level in SG 1 until AnnunciatorWindow 63-F, SG LEVEL DEVIATION, CLEARS.
A. VERIFY Unit 2 Events Display Legend indicates 63-F SG1 LEVEL LO (LS-3-42E) is in CLEAR (Blue).
B. RECORD the level indication from 2-FR-3-35, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE).
C. DETERMINE the percent deviation by subtracting theindication recorded in Step 6.1[42]B from 38%.[Programmed level -4% (>1%, :7%)]
- 38% %/
[43] SLOWLY INCREASE the level in Steam Generator 1 untilapproximately 38% is indicated on 2-LI-3-38, SG 1 LEVEL.
[44] COMPLETE Data Sheet 12
[45] REMOVE the meters from the following test points:
A. Panel 2-R-5, SG 1 Level, Test Point 2LP/519B
B. Panel 2-R-1 1, SG 1 Level, Test Point 2LP/518B
C. Panel 2-R-12, SG 1 Level, Test Point 2LP/517B
CV
CV
CV
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 40 of 182
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6.1 SG I
[46]
Narrow Range Level Instrument Test (continued)
VERIFY that level indications and calculated levels satisfyAcceptance Criteria 5.0B.1 and 5.0B.2 as specified on thefollowing Data Sheets. (ACC CRIT)
A. Data Sheet 1
B. Data Sheet 2
C. Data Sheet 3
D.. Data Sheet 5
E. Data Sheet 6
F. Data Sheet 7
G. Data Sheet 8
H. Data Sheet 10
I. Data Sheet 11
J. Data Sheet 12
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000
Page 41 of 182
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6.2 SG 2 Narrow Range Level Instrument TestNOTES
1) At the Operators'discretion, Steam Generator Blowdown may be initiated or increasedduring level decreases to allow some feedwater flow to the generator. It is preferablethat blowdown flow be maintained as low as possible to avoid decreasing primarytemperature due to excessive feedwater flow.
2) The levels in the Steam Generator are adjusted by regulation of feedwater flow (2-SOI-2&3.01), into the generator, and blowdown flow from the generator (2-SOl-15.01).Operation of the equipment required to perform these actions is not a part of this testand therefore, will not be specifically detailed in this test.
[1] VERIFY prerequisites listed in Section 4.0 for Subsection 6.2
have been completed.
[2] COMPLETE Data Sheet 13
[3) VERIFY Annunciator Window 2-XA-55-3C, 63-F, SG LEVELDEVIATION, at 2-M-3 is CLEAR.
[4] VERIFY Unit 2 Events Display Legend indicates 63-F SG 2LEVEL HI is CLEAR.
[5] SLOWLY INCREASE the level in SG 2 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, alarms.
A. VERIFY Unit 2 Events Display Legend indicates 63-F SG2 LEVEL HI (2-LS-3-55D) is in ALARM (Red).
B. RECORD the level indication from 2-FR-3-48, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE), at 2-M-4.
2-FR-3-48, STM FW FLOW & NR LEVEL %
C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.2[5]B.[Programmed level +5% (>2%, -8%)]
% - 38% %
[6] SLOWLY INCREASE the level in Steam Generator 2 untilapproximately 50% is indicated on 2-LI-3-51, SG 2 LEVEL at2-M-4.
[7] COMPLETE Data Sheet 14
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 42 of 182
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6.2 SG 2 Narrow Range Level Instrument Test (continued)
NOTE
Annunciator Window 2-XA-55-3C, 61-B, SG 2 LEVEL HI, will alarm at approximately 74%level. The alarm may be acknowledged and silenced. No other action is required.
[8] SLOWLY INCREASE the level in Steam Generator 2 untilapproximately 75% is indicated on 2-LI-3-51, SG 2 LEVEL at2-M-4.
[91 COMPLETE Data Sheet 15.
[10] INSTALL and LABEL digital multimeters AND
VERIFY trip signals are OFF as indicated by presence ofvoltage at the following locations: (2-R-46 - Control BuildingAuxiliary Instrument Room 708/C8P, 2-R-49 - Control BuildingAuxiliary Instrument Room 708/C8P)
A. TB 207-11 AND TB 207-12 in Panel 2-R-46.(Dwg 45N2676-1)
CV
B. TB 207-11 AND TB 207-12 in Panel 2-R-49.(Dwg 45N2677-1)
CV
C. TB 304-3 AND TB 304-4 in Panel 2-R-46.(Dwg 45N2676-2)
CV
D. TB 304-3 AND TB 304-4 in Panel 2-R-49.(Dwg 45N2677-2)
CV
E. TB 403-7 AND TB 403-8 in Panel 2-R-46.(Dwg 45N2676-2)
CV
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 43 of 182
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6.2 SG 2 Narrow Range Level Instrument Test (continued)
F. TB 403-7 AND TB 403-8 in Panel 2-R-49.(Dwg 45N2677-2)
CV
NOTE
Annunciator Window 2-XA-55-6B, 117-B, SG 2 LEVEL HI-HI, will alarm at approximately82% level. The alarm may be acknowledged and silenced. No other action is required.
NOTE
Steps 6.2[1 ]A, B, and C may be signed off as they occur
[11] SLOWLY INCREASE the level in Steam Generator 2 AND
A. WHEN TB 403-7 and TB 403-8 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),
RECORD the SG 2 LEVEL on 2-LI-3-55, SG 2 LEVEL, at2-M-4. (ACC CRIT) 5.OC.1 [82.4% (79.9%- 84.9%)]
B. WHEN TB 304-3 and TB 304-4 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),
RECORD the SG 2 LEVEL on 2-LI-3-52, SG 2 LEVEL, at2-M-4. (ACC CRIT) 5.OC.1 [82.4% (79.9%- 84.9%)]
C. WHEN TB 207-11 and TB 207-12 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),
RECORD the SG 2 LEVEL on 2-LI-3-51, SG 2 LEVEL, at2-M-4. (ACC CRIT) 5.OC.1 [82.4% (79.9%- 84.9%)]
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 44 of 182
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6.2 SG 2 Narrow Range Level Instrument Test (continued)
NOTE
The following two steeps will raise the SG 2 level to the upper NR tap. Data collection shouldbe completed as rapidly as possible.
[12] SLOWLY INCREASE the level in the SG 2 until the meterslabeled SG 2 Level installed in 2-R-5, 2-R-11, and 2-R-12 nolonger indicate increasing voltage which indicates the waterlevel has reached the upper tap:
A. 2-R-5, SG 2 Level
B. 2-R-11, SG 2 Level
C. 2-R-12, SG 2 Level
[13] COMPLETE Data Sheet 16.
[14] SLOWLY DECREASE the level in SG 2 until level change isindicated on the following instruments which indicates thewater level has fallen below the upper tap:
A. 2-LI-3-55, SG 2 LEVEL
B. 2-LI-3-52, SG 2 LEVEL
C. 2-LI-3-51, SG 2 LEVEL
[15] COMPLETE Data Sheet 17.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 45 of 182
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6.2 SG 2 Narrow Range Level Instrument Test (continued)
NOTE
Steps 6.2[16]A through 6.2[16]C may be signed off as they occur.
NOTE
Annunciator Window 2-XA-55-6B, 117-B, SG 2 LEVEL HI-HI, will clear at approximately81% level. The alarm may be acknowledged and silenced. No other action is required.
[16] SLOWLY DECREASE the level in SG 2 AND
A. WHEN TB 403-7 and TB 403-8 in Panels 2-R-46 and 2-R-49 indicate the trip is OFF (voltage indicated),
RECORD SG 2 Level on 2-L-3-55, SG 2 LEVEL, at2-M-4. [81.4% (78.9% - 83.9%)]
B. WHEN TB 304-3 and TB 304-4 in Panels 2-R-46 and,2-R-49 indicate the trip is OFF (voltage indicated),
RECORD SG 2 Level on 2-LI-3-52, SG 2 LEVEL, at2-M-4. [81.4% (78.9 - 83.9)]
C. WHEN TB 205-1land TB 205-12 in Panels 2-R-46 and 2-R-49 indicate the trip is OFF (voltage indicated),
RECORD SG 2 Level on 2-LI-3-51, SG 2 LEVEL, at2-M-4. [81.4% (78.9 - 83.9)]
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 46 of 182
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6.2 SG 2 Narrow Range Level Instrument Test (continued)
[17] REMOVE Digital Multimeters installed in at the followinglocations:
A. TB 403-7 and TB 403-8 in Panel 2-R-46
CV
B. TB 403-7 and TB 403-8 in Panel 2-R-49
CV
C. TB 304-3 and TB 304-4 in Panel 2-R-46
CV
D. TB 304-3 and TB 304-4 in Panel 2-R-49
CV
E. TB 205-11 and TB 205-12 in Panel 2-R-46
CV
F. TB 205-11 and TB 205-12 in Panel 2-R-49
CV
NOTE
Although not within the scope of this test, Annunciator Window 2-XA-55-3C, 61-B, SG 2LEVEL HI, will clear at approximately 74% level. The alarm may be acknowledged andsilenced. No other action is required.
[18] SLOWLY DECREASE the level in SG 2 until approximately
75% is indicated on 2-LI-3-51, SG 2 LEVEL.
[19] COMPLETE Data Sheet 18.
[20] SLOWLY DECREASE the level in SG 2 until approximately50% is indicated on 2-LI-3-51, SG 2 LEVEL.•
[21] COMPLETE Data Sheet 19.
Date
6.2 SG 2 Narrow Range Level Instrument Test (continued)
[22] SLOWLY DECREASE the level in SG 2 until Annunciator 2-XA-55-3C, Window 63-F, SG LEVEL DEVIATION, CLEARS.
A. VERIFY Unit 2 Events Display Legend indicates 63-F SG2 LEVEL HI (LS-3-55D) is NORMAL (Blue).
B. RECORD the level indication from 2-FR-3-48, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE).
C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.2[22]B.[Programmed level +4% (--1%, <7%)]
% - 38% %
[23] SLOWLY DECREASE the level in SG 2 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, ALARMS.
A. VERIFY Unit 2 Events Display Legend indicates 63-F SG2 LEVEL LO (LS-3-55E) is in ALARM (Red).
B. RECORD the level indication from 2-FR-3-48, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE).
C. DETERMINE the percent deviation by subtracting theindication recorded in Step 6.2[23]B from 38%.[Programmed level -5% (>2%, <8%)]
% - 38% = %
NOTE
Annunciator Window 2-XA-55-3C, 61-D, SG 2 LEVEL LO, will alarm approximately 25%level. The alarm may be acknowledged and silenced. No other action is required.
[24] SLOWLY DECREASE the level in SG 2 until approximately25% is indicated on 2-LI-3-51, SG 2 LEVEL.
[25] COMPLETE Data Sheet 20.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 48 of 182
Date
6.2 SG 2 Narrow Range Level Instrument Test (continued)
[26] INSTALL and LABEL Digital Multimeters AND
VERIFY trip signals are OFF as indicated by presence ofvoltage.at the following locations: (2-R-46 - Control BuildingAuxiliary Instrument Room 708/C8P, 2-R-49 - Control BuildingAuxiliary Instrument Room 708/C8P)
A. TB 404-7 and TB 404-8 in Panel 2-R-46(Dwg 45N2676-2)
B. TB 404-7 and TB 404-8 in Panel 2-R-49(Dwg 45N2677-2)
CV
CV
CV
C. TB 305-3 and TB 305-4 in Panel 2-R-46(Dwg 45N2676-2)
D. TB 305-3 and TB 305-4 in Panel 2-R-49(Dwg 45N2677-2)
E. TB 210-1 and TB 210-2 in Panel 2-R-46(Dwg 45N2676-1)
CV
CV
CV
F. TB 210-1 and TB 210-2 in Panel 2-R-49(Dwg 45N2677-1)
[27] VERIFY Annunciator Window 2-XA-55-6B, 117-D, SG 2LO-LO LEVEL TTD INITIATED, at 2-M-6 is CLEAR.
[28] SLOWLY DECREASE the level in Steam Generator 2.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 49 of 182
Date
6.2 SG 2 Narrow Range Level Instrument Test (continued)
NOTE
Steps 6.2[31]A through 6.2[31]F may be signed off as they occur.
NOTE
Annunciator Window 2-XA-55-6B, 11 7-E, SG 2 LEVEL LO-LO, will alarm at approximately17% level. The alarm may be acknowledged and silenced. No other action is required.
[29] VERIFY Annunciator Window 2-XA-55-6B, 117-D, SG2 LO-LOLEVEL TTD INITIATED, at 2-M-6, ALARMS as the SteamGenerator level reaches 17% (14.5 %- 19.5%).
[30] VERIFY the following Event Display Legends are in alarm.
Stop decreasing Steam Generator level when all three are in.
A. 117-D SG 2 LOLO LEVEL TTD INITIATED (ILY/529H).
B. 117-D SG 2 LOLO LEVEL TTD INITIATED (ILY/528H).
C. 117-D SG 2 LOLO LEVEL TTD INITIATED (ILY/527H).
NOTE
After the time delay (TTD) has finished (approximately 8 minutes), all three trip channelsshould come in. ]
[31] RECORD the level from the specified indicators AND
VERIFY status of associated computer points as the followingtrip signals come ON as indicated by absence of voltage at thefollowing locations:
A. TB 404-7 and TB 404-8 in Panel 2-R-46 and 2-R-49, SG 2Level indication on 2-LI-3-55, SG 2 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5% - 19.5%)]
B. Computer Point L0425D indicates TRIP.(ACC CRIT) 5.OC.2
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 50 of 182
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6.2 SG 2 Narrow Range Level Instrument Test (continued)
C. TB 305-3 and TB 305-4 in Panel 2-R-46 and 2-R-49, SG 2Level indication on 2-LI-3-52, SG 2 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5% - 19.5%)]
D. Computer Point L0424D indicates TRIP.(ACC CRIT) 5.OC.2
E. TB 210-1 and TB 210-2 in Panel 2-R-46 and 2-R-49, SG 2Level indication on 2-LI-3-51, SG 2 LEVEL, at 2-M-4.(ACC CRIT) 5.0C.2 [17% (14.5% - 19.5%)]
F. Computer Point L0423D indicates TRIP.(ACC CRIT) 5.OC.2
NOTE
The following two steps will decrease the Steam Generator Level to the lower NR tap. Datacollection should be completed as rapidly as possible.
[32] SLOWLY DECREASE the level in SG 2 until the meterslabeled SG 2 Level installed in 2-R-5, 2-R-11, and 2-R-12 nolonger indicate decreasing voltage which indicates the waterlevel has reached the lower tap.
A. 2-R-5, SG 2 Level
B. 2-R-11, SG 2 Level
C. 2-R-12, SG 2 Level
[33] COMPLETE Data Sheet 21.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 51 of 182
Date
6.2 o SG 2 Narrow Range Level Instrument Test (continued)
[34] SLOWLY INCREASE the level in SG 2 until level change isindicated on the following instruments which indicates thewater level has risen above the lower tap:
A. 2-L-3-55, SG 2 LEVEL
B. 2-LI-3-52, SG 2 LEVEL
C. 2-L-3-51, SG 2 LEVEL
[35] COMPLETE Data Sheet 22.
[ NOTE
Steps 6.2[36]A through 6.2[36]F may be signed off as they occur.
NOTE
Annunciator Window 2-XA-55-6B, 11 7-E, SG 2 LEVEL LO-LO, will clear at approximately18% level. The alarm may be acknowledged and silenced. No other-action is required.
[36] SLOWLY INCREASE the level in SG 2 AND
RECORD the level from the specified indicators AND
VERIFY status of associated computer points as the following*trip signals CLEAR as indicated by. presence of voltage at thefollowing locations:
A. TB 404-7 and TB 404-8 in Panel 2-R-46 and 2-R-49,2-L-3-55, SG 2 LEVEL, at 2-M-4. [18% (15.5% - 20.5%)]
B. Computer Point L0425D indicates NOT TR.
C. TB 305-3 and TB 305-4 in Panel 2-R-46 and 2-R-49,2-LI-3-52, SG 2 LEVEL, at 2-M-4. [18% (15.5% - 20.5%)]
D. Computer Point L0424D indicates NOT TR.
E. TB 210-1 and TB 210-2 in Panel 2-R-46 and 2-R-49,2-LI-3-51, SG 2 LEVEL, at 2-M-4. [18% (15.5% - 20.5%)]
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 52 of 182
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6.2 SG 2 Narrow Range Level Instrument Test (continued)
F. Computer Point L0423D indicates NOT TR.
(371 REMOVE Digital Multimeters installed at the followinglocations:
A. TB 404-7 and TB 404-8 in Panel 2-R-46
B. TB 404-7 and TB 404-8 in Panel 2-R-49
.C. TB 305-3 and TB 305-4 in Panel 2-R-46
CV
CV
CV
CV
CV
CV
D. TB 305-3 and TB 305-4 in Panel 2-R-49
E. TB 210-1 and TB 210-2 in Panel 2-R-46
F. TB 210-1 and TB 210-2 in Panel 2-R-49
[38] VERIFY Annunciator Window 2-XA-55-6B, 117-D, SG 2LO-LO LEVEL TTD INITIATED, CLEARS when all trip signalsare cleared.
[39] VERIFY Unit 2 Events Display Legend indicates 11 7-D, SG 2LO-LO LEVEL TTD INITIATED is in CLEAR (Blue).
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 53 of 182
Date
6.2 SG 2 Narrow Range Level Instrument Test (continued)
NOTE
Annunciator Window 2-XA-55-3C,. 61-D, SG 2 LEVEL LO, will clear at approximately 25%level. The alarm may be acknowledged and silenced. No other action is required.
[40] SLOWLY INCREASE the level in Steam Generator 2 untilapproximately 25% is indicated on 2-LI-3-51, SG 2 LEVEL.
[41] COMPLETE Data Sheet 23.
[42] SLOWLY INCREASE the level in SG 2 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, CLEARS.
A. VERIFY Unit 2 Events Display Legend indicates 63-F SG2 LEVEL LO (LS-3-55E) is CLEAR (Blue).
B. RECORD the level indication from 2-FR-3-48, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE)
C. DETERMINE the percent deviation by subtracting theindication recorded in Step 6.2[42]B from 38%.[Programmed level -4% (>1%, <7%)]
% 38% %
[43] SLOWLY INCREASE the level in Steam Generator 2 untilapproximately 38% is indicated on 2-LI-3-51, SG 2 LEVEL.
[44] COMPLETE Data Sheet 24.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 54 of 182
Date
6.2 SG 2 Narrow Range Level Instrument Test (continued)
[45] REMOVE the meters from the following test points:
A. Panel 2-R-5, SG 2 Level, Test Point 2LP/529B
Cv
B. Panel 2-R-1 1, SG 2 Level, Test Point 2LP/528B
Cv
C. Panel 2-R-12, SG 2 Level, Test Point 2LP/527B1
Cv
[46] VERIFY that level indications and calculated levels satisfyAcceptance Criteria 5.0 B.land 5.0 B.2 as specified on thefollowing Data Sheets. (ACC CRIT)
A. Data Sheet 13.
B. Data Sheet 14.
C. Data Sheet 15.
D. Data Sheet 17.
E. Data Sheet 18.
F. Data Sheet 19.
G. Data Sheet 20.
H. Data Sheet 22.
I. Data Sheet 23.
J. Data Sheet 24.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 55 of 182
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6.3 SG 3 Narrow Range Level Instrument Test
NOTES
1) At the Operators discretion, Steam Generator Blowdown may be initiated or increasedduring level decreases to allow some feedwater flow to the generator. It is preferablethat blowdown flow be maintained as low as possible to avoid decreasing primarytemperature due to excessive feedwater flow.
2) The levels in the Steam Generator are adjusted by regulation of feedwater flow (2-SOI-2&3.01), into the generator, and blowdown flow from the generator (2-SO1-15.01).Operation of the equipment required to perform these actions is not a part of this testand therefore, will not be specifically detailed in this test.
[1] VERIFY prerequisites listed in Section 4.0 for Subsection 6.3
have been completed.
[2] COMPLETE Data Sheet 25.
[3] VERIFY.Annunciator Window 2-XA-55-3C, 63-F, SG LEVELDEVIATION, at 2-M-3 is CLEAR.
[4] VERIFY Unit 2 Events Display Legend indicates 63-F SG 3LEVEL HI is CLEAR.
[5] SLOWLY INCREASE the level in SG 3 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, alarms.
A. VERIFY Unit 2 Events Display Legend indicates 63-F SG3 LEVEL HI (LS-3-97D) is in ALARM (Red)..
B. RECORD the level indication from 2-FR-3-90, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE), at 2-M-4.
2-FR-3-90, STM FW FLOW & NR LEVEL __ -%
C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.3[5]B.[Programmed level +5% (>-2%, <8%)]
% - 38% =%
[6] SLOWLY INCREASE the level in Steam Generator 3 untilapproximately 50% is indicated on 2-LI-3-93, SG 3 LEVEL at2-M4.
[7] COMPLETE Data Sheet 26.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 56 of 182
Date
6.3 SG 3 Narrow Range Level Instrument Test (continued)
NOTE
Annunciator Window 2-XA-55-3C, 62-B, SG 3 LEVEL HI, will alarm at approximately 74%level. The alarm may be acknowledged and silenced. No other action is required.
[8] SLOWLY INCREASE the level in Steam Generator 3.untilapproximately 75% is indicated on 2-LI-3-93, SG 3 LEVEL at2-M-4.
[9] COMPLETE Data Sheet 27.
[10] INSTALL and LABEL digital multimeters AND
VERIFY trip signals are OFF as indicated by presence ofvoltage at the following locations: (2-R-46 - Control BuildingAuxiliary. Instrument Room 708/C8P, 2-R-49 - Control BuildingAuxiliary Instrument Room 708/C8P)
A. TB 403-9 and TB 403-10 in Panel 2-R-46(Dwg 45N2676-2)
CV
B. TB 403-9 and TB 403-10 in Panel 2-R-49(Dwg 45N2677-2)
C. TB 304-5 and TB 304-6 in Panel 2-R-46(Dwg 45N2676-2)
CV
CV
D. TB 304-5 and TB 304-6 in Panel 2-R-49(Dwg 45N2677-2)
E. TB 210-9 and TB 210-10 in Panel 2-R-46(Dwg 45N2676-1)
CV
CV
WBN Feedwater & Steam Generator Level 2 PTI-003A-02Unit2 Rev.0000
Page 57 of 182
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6.3 SG 3 Narrow Range Level Instrument Test (continued)
F. TB 210-9 and TB 210-10 in Panel 2-R-49(Dwg 45N2677-1)
CV
NOTE
Annunciator Window 2-XA-55-6B, 118-B, SG 3 LEVEL HI-HI, will alarm at approximately82% level. The alarm may be acknowledged and silenced. No other action is required.
NOTE
Steps 6.3[1 ]A, B, and C may be signed off as they occur
[11] SLOWLY INCREASE the level in Steam Generator 3 AND
A. WHEN TB 403-9 and TB 403-10 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),
RECORD SG 3 Level on 2-LI-3-97, SG 3 LEVEL, at2-M-4. (ACC CRIT) 5.OC.1 [82.4% (79.9% - 84.9%)]
B. WHEN TB 304-5 and TB 304-6 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),
RECORD SG 3 Level on 2-LI-3-94, SG 3 LEVEL, at2-M-4. (ACC CRIT) 5.OC.1 [82.4% (79.9% - 84.9%)]
C. WHEN TTB 210-9 and TB 210-10 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),
RECORD SG 3 Level on 2-LI-3-93, SG 3 LEVEL, at2-M-4. (ACC CRIT) 5.0C.1 [82.4% (79.9% - 84.9%)]
0/
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 58 of 182
Date
6.3 SG 3 Narrow Range Level Instrument Test (continued)
NOTE
The following two steps will raise the SG 3 level to the upper NR tap. Data collection shouldbe completed as rapidly as possible.
[12] SLOWLY INCREASE the level in the SG 3 until the meterslabeled SG 3 Level installed in 2-R-5, 2-R-1 1, and 2-R-1 2 nolonger indicate increasing voltage which indicates the waterlevel has reached the upper tap:
A. 2-R-5, SG 3 Level
B. 2-R-11, SG 3 Level
C. 2-R-12, SG 3 Level
[13] COMPLETE Data Sheet 28.
[14] SLOWLY DECREASE the level in SG 3 until level change isindicated on the following instruments which indicates thewater level has fallen below the lower tap:
A. 2-LI-3-97, SG 3 LEVEL
B. 2-LI-3-94, SG 3 LEVEL
C. 2-LI-3-93, SG 3 LEVEL
[151 COMPLETE Data Sheet 29.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 59 of 182
Date.
6.3 SG 3 Narrow Range Level Instrument Test (continued)
Steps 6.3[16]A through 6.3[16]C may be signed off as they occur.
NOTE
Annunciator Window 2-XA-55-6B, 118-B, SG 3 LEVEL HI-HI, will clear at approximately81% level. The alarm may be acknowledged and silenced. No other action is required.
[16] SLOWLY DECREASE the level in SG 3 AND
A. WHEN TB 403-9 and TB 403-10 in Panels 2-R-46 and2-R-49 indicate the trip is off (voltage indicated),
RECORD SG 3 Level on 2-LI-3-97, SG 3 LEVEL, at2-M-4. [81.4% (78.9% - 83.9%)]
B. WHEN TB 304-5 and TB 304-6 in Panels 2-R-46 and2-R-49 indicate the trip is off (voltage indicated),
RECORD SG 3 Level on 2-LI-3-94, SG 3 LEVEL, at2-M-4. [81.4% (78.9% - 83.9%)]
C. WHEN TB 210-9 and TB 210-10 in Panels 2-R-46 and2-R-49 indicate the trip is off (voltage indicated),
RECORD SG 3 Level on 2-LI-3-93, SG 3 LEVEL, at2-M-4. [81.4% (78.9% - 83.9%)]
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 60 of 182
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6.3 SG 3 Narrow Range Level Instrument Test (continued)
[17] REMOVE Digital Multimeters installed in at the followinglocations:
-A. TB 403-9 and TB 403-10 in Panel 2-R-46
B. TB 403-9 and TB 403-10 in Panel 2-R-49
C. TB 304-5 and TB 304-6 in Panel 2-R-46
CV
CV
CV
CV
D. TB 304-5 and TB 304-6 in Panel 2-R-49
E. TB 210-9 and TB 210-10 in Panel 2-R-46
F. TB 210-9 and TB 210-10 in Panel 2-R-49
CV
CV
NOTE
Annunciator Window 2-XA-55-3C, 62-B, SG 3 LEVEL HI, will clear at approximately 74%level. The alarm may be acknowledged and silenced. No other action is required. I
[18] SLOWLY DECREASE the level in SG 3 until approximately75% is indicated on 2-LI-3-93, SG 3 LEVEL.
[19] COMPLETE Data Sheet 30.
[20] SLOWLY DECREASE the level in SG 3 until approximately50% is indicated on 2-LI-3-93, SG 3 LEVEL.
[21] COMPLETE Data Sheet 31
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 61 of 182
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6.3 SG 3 Narrow Range Level Instrument Test (continued)
[22] SLOWLY DECREASE the level in SG 3 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, CLEARS.
A. VERIFY Unit 2 Events Display Legend indicates 63-F SG3 LEVEL HI (LS-3-97D) is NORMAL (Blue)
B. RECORD the level indication from 2-FR-3-90, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE)
C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.3[22]B.[Programmed level +4% (21%, 57%)]
% - 38% %
[23] SLOWLY DECREASE the level in SG 3 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, ALARMS.
A. VERIFY Unit 2 Events Display Legend indicates 63-F SG3 LEVEL LO (LS-3-97E) is in ALARM (Red)
B. RECORD the level indication from 2-FR-3-90, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE)
C. DETERMINE the percent deviation by subtracting theindication recorded in Step 6.3[23]B from 38%.[Programmed level -5% (>2%, <8%)]
%/ 38% = %/
NOTE
Annunciator Window 2-XA-55-3C 62-D, SG 3 LEVEL LO, will alarm approximately 25%level. The alarm may be acknowledged and silenced. No other action is required.
[24] SLOWLY DECREASE the level in SG 3 until approximately25% is indicated on 2-LI-3-93, SG 3 LEVEL.
[25] COMPLETE Data Sheet 32.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 62 of 182
Date
6.3 SG 3 Narrow Range Level Instrument Test (continued)
[261 INSTALL and LABEL Digital Multimeters AND
VERIFY trip signals are OFF as indicated by presence ofvoltage at the following locations: (2-R-46 - Control BuildingAuxiliary Instrument Room 708/C8P, 2-R-49 - Control BuildingAuxiliary Instrument Room 7081C8P)
A. TB 404-9 and TB 404-10 in Panel 2-R-46(Dwg 45N2676-2)
B. TB 404-9 and TB 404-10 in Panel 2-R-49(Dwg 45N2677-2)
C. TB 305-5 and TB 305-6 in Panel 2-R-46(Dwg 45N2676-2)
D. TB 305-5 and TB 305-6 in Panel 2-R-49(Dwg 45N2677-2)
E. TB 210-3 and TB 210-4 in Panel 2-R-46(Dwg 45N2676-1)
F. TB 210-3 and TB 210-4 in Panel 2-R-49(Dwg 45N2677-1)
(271 VERIFY Annunciator Window 2-XA-55-6B, 118-D, SG 3LO-LO LEVEL TTD INITIATED, at 2-M-6 is CLEAR.
CV
CV
CV
CV
CV
CV
[28] SLOWLY DECREASE the level in Steam Generator 3.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 63 of 182
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6.3 SG 3 Narrow Range Level Instrument Test (continued)
NOTE
Steps 6.3[31]A through 6.3[31]F may be signed off as they occur.
NOTE
Annunciator Window 2-XA-55-6B, 118-E, SG 3 LEVEL LO-LO, will alarm at approximately17% level. The alarm may be acknowledged and silenced. No other action is required.
[29] VERIFY Annunciator Window 2-XA-55-6B, 11 8-D, SG3 LO-LOLEVEL TTD INITIATED, at 2-M-6, ALARMS as the Steam.Generator level reaches 17%.(14.5 %- 19.5%).
[30] VERIFY the following Event Display Legends are in alarm.Stop decreasing Steam Generator level when all three are in.
A. 118-D SG 3 LOLO LEVEL TTD INITIATED (ILY/539H).
B. 118-D SG 3 LOLO LEVEL TTD INITIATED (ILY/538H).
C. 118-D SG 3 LOLO LEVEL TTD INITIATED (ILY/537H).
NOTE
After the time delay (TTD) has finished (approximately 8 minutes), all three trip channelsshould come in.
[31] RECORD the level from the specified indicators AND
VERIFY status of associated computer points as the followingtrip signals come ON as indicated by absence of voltage at thefollowing locations:
A. TB 404-9 and TB 404-10 in Panel 2-R-46 and 2-R-49, SG3 Level indication on 2-LI-3-97, SG 3 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5% - 19.5%)]
B. Computer Point L0445D indicates TRIP.(ACC CRIT) 5.0C.2
WBNu Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 64 of 182
Date
6.3 SG 3 Narrow Range Level Instrument Test (continued)
C. TB 305-5 and TB 305-6 in Panel 2-R-46 and 2-R-49, SG 3Level indication on 2-LI-3-94, SG 3 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5%- 19.5%)]
D. Computer Point L0444D indicates TRIP.(ACC CRIT) 5.OC.2
E. TB 210-3 and TB 210-4 in Panel 2-R-46 and 2-R-49, SG 3Level indication on 2-LI-3-93, SG 3 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5% - 19.5%)]
F. Computer Point L0443D indicates TRIP.(ACC CRIT) 5.OC.2
NOTE
The following two steps will decrease the Steam Generator Level to the lower NR tap. Datacollection should be completed as rapidly as possible.
[32] SLOWLY DECREASE the level in SG 3 until the meterslabeled SG 3 Level installed in 2-R-5, 2-R-11, and 2-R-12 nolonger indicate decreasing voltage which indicates the waterlevel has reached the lower tap.
A. 2-R-5, SG 3 LEVEL
B. 2-R-11, SG 3 LEVEL
C. 2-R-12, SG 3 LEVEL
[33] COMPLETE Data Sheet 33.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 65 of 182
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6.3 SG 3 Narrow Range Level Instrument Test (continued)
[34] SLOWLY INCREASE the level in SG 3 until level change isindicated on the following instruments which indicates thewater level has risen above the lower tap:
A. 2-LI-3-97, SG 3 LEVEL
B. 2-LI-3-94, SG 3 LEVEL
C. 2-L-3-93, SG 3 LEVEL
.[35] COMPLETE Data Sheet 34.
NOTE
Steps 6.3[36]A through 6.3[36]F may be signed off as they occur.
NOTE
Annunciator Window 2-XA-55-6B, I I8-E, SG 3 LEVEL LO-LO, will clear at approximately18% level. The alarm may be acknowledged and silenced. No other action is required.
[36] SLOWLY INCREASE the level in SG 3 AND
RECORD the level from the specified indicators AND
VERIFY status of associated computer points as the followingtrip signals CLEAR as indicated by presence of voltage at thefollowing locations:
A. TB 404-9 and TB 404-10 in Panel 2-R-46 and 2-R-49, SG3 Level indication on 2-LI-3-97, SG 3 LEVEL, at 2-M-4.[18% (15.5% - 20.5%)]
B. Computer Point L0445D indicates NOT TR.
C. TB 305-5 and TB 305-6 in Panel 2-R-46 and 2-R-49, SG 3Level indication on 2-LI-3-94, SG 3 LEVEL, at 2-M-4.[18% (15.5% - 20.5%)]
D. Computer Point L0444D indicates NOT TR.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 66 of 182
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6.3 SG 3 Narrow Range Level Instrument Test (continued)
E. TB 210-3 and TB 210-4 in Panel 2-R-46 and 2-R-49, SG 3Level indication on 2-LI-3-93, SG 3 LEVEL, at 2-M-4.[18% (15.5% - 20.5%)]
F. Computer Point L0443D indicates NOT TR.
[37] REMOVE Digital Multimeters installed at the following
locations:
A. TB 404-9 and TB 404-10 in Panel 2-R-46
CV
B. TB 404-9 and TB 404-10 in Panel 2-R-49
CV
C. TB 305-5 and TB 305-6 in Panel 2-R-46
CV
D. TB 305-5 and TB 305-6 in Panel 2-R-49
CV
E. TB 210-3 and TB 210-4 in Panel 2-R-46
CV
F. TB 210-3 and TB 210-4 in Panel 2-R-49
CV
[38] VERIFY Annunciator Window 2-XA-55-6B, 11 8-D, SG 3LO-LO LEVEL TTD INITIATED, CLEARS when all trip signalsare cleared.
[39] VERIFY Unit 2 Events Display Legend indicates 11 8-D, SG 3LO-LO LEVEL TTD INITIATED is in CLEAR (Blue).
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 67 of 182
Date
6.3 SG 3 Narrow Range Level Instrument Test (continued)
NOTE
Annunciator Window 2-XA-55-3C, 62-D, SG 3 LEVEL LO, will clear at approximately 25%level. The alarm may be acknowledged and silenced. No other action is required.
[401 SLOWLY INCREASE the level in Steam Generator 3 untilapproximately 25% is indicated on 2-L-3-93, SG 3 LEVEL.
[41] COMPLETE Data Sheet 35.
[42] SLOWLY INCREASE the level in SG 3 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, CLEARS.
A. VERIFY Unit 2 Events Display Legend indicates 63-F SG3 LEVEL LO (LS-3-97E) is CLEAR (Blue).
B. RECORD the level indication from 2-FR-3-90, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE)
C. DETERMINE the percent deviation by subtracting theindication recorded in Step 6.3[42]B from 38%.[Programmed level -4% (51%, <7%)]
38% %/
[43] SLOWLY INCREASE the level in Steam Generator 3 untilapproximately 38% is indicated on 2-LI-3-93, SG 3 LEVEL.
[44] COMPLETE Data Sheet 36.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 68 of 182
Date,
6.3 SG 3 Narrow Range Level Instrument Test (continued)
[45] REMOVE the meters from the following test points:
A. Panel 2-R-5, SG 3 Level, Test Point 2LP/539B
B. Panel 2-R-1 1, SG 3 Level, Test Point 2LP/538B
C. Panel 2-R-12, SG 3 Level, Test Point 2LP/537B
Cv
Cv
Cv
[46] VERIFY that level indications and calculated levels satisfyAcceptance Criteria 5.0 B.land 5.0 B.2 as specified on thefollowing Data Sheets. (ACC CRIT)
A. Data Sheet 25.
B. Data Sheet 26.
C. Data Sheet 27.
D. Data Sheet 29.
E. Data Sheet 30.
F. Data Sheet 31.
G. Data Sheet 32.
H. Data Sheet 34.
I. Data Sheet 35.
J. Data Sheet 36.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 69 of 182
Date
6.4 SG 4 Narrow Range Level Instrument TestNOTES
1) At the Operators discretion, Steam Generator Blowdown may be initiated or increasedduring level decreases to allow some feedwater flow to the generator, It is preferablethat blowdown flow be maintained as low as possible to avoid decreasing primarytemperature due to excessive feedwater flow.
2) The levels in the Steam Generator are adjusted by regulation of feedwater flow (2-SOI-2&3.011), into the generator, and blowdown flow from the generator (2-SOl-1 5.01).Operation of the equipment required to perform these actions is not a part of this testand therefore, will not be specifically detailed in this test.
[1] VERIFY prerequisites listed in Section 4.0 for Subsection 6.4
have been completed.
[2] COMPLETE Data Sheet 37.
[3] VERIFY Annunciator Window 2-XA-55-3C, 63-F, SG LEVELDEVIATION, at 2-M-3 is CLEAR.
[4] VERIFY Unit 2 Events Display Legend indicates 63-F SG 4LEVEL HI is CLEAR.
[5] SLOWLY INCREASE the level in SG 4 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, alarms.
A. VERIFY Unit 2 Events Display Legend indicates 63-F SG4 LEVEL HI (LS-3-1 10D) is in ALARM (Red).
B. RECORD the level indication from 2-FR-3-103, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE), at 2-M-4.
2-FR-3-103, STM FW FLOW & NR LEVEL %
C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.4[5]B.[Programmed level +5% (-2%, <8%)]
% 38% %
[6] SLOWLY INCREASE the level in Steam Generator 4 until.approximately 50% is indicated on 2-LI-3-106, SG 4 LEVEL at2,M-4.
[71 COMPLETE Data Sheet 38.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 70 of 182
Date
6.4 SG 4 Narrow Range Level Instrument Test (continued)
NOTE
Annunciator Window 2-XA-55-3C, 63-B, SG 4 LEVEL HI, will alarm at approximately 74%level. The alarm may be acknowledged and silenced. No other action is required.
[8] SLOWLY INCREASE the level in Steam Generator 4 untilapproximately 75% is indicated on 2-LI-3-106, SG 4 LEVEL at2-M-4.
[9] COMPLETE Data Sheet 39.
[10] INSTALL and LABEL digital multimeters AND
VERIFY trip signals are OFF as indicated by presence ofvoltage at the following locations: (2-R-46 - Control BuildingAuxiliary Instrument Room 708/C8P, 2-R-49 - Control BuildingAuxiliary Instrument Room 708/C8P)
A. TB 403-11 and TB 403-12 in Panel 2-R-46(Dwg 45N2676-2)
CV
B. TB 403-11 and TB 403-12 in Panel 2-R-49(Dwg 45N2677-2)
CV
C. TB 304-7 and TB 304-8 in Panel 2-R-46(Dwg 45N2676-2)
CV
D. TB 304-7 and TB 304-8 in Panel 2-R-49(Dwg 45N2677-2)
CV
E. TB 205-11 and TB 205-12 in Panel 2-R-46(Dwg 45N2676-1) _
CV
WBN Feedwater & Steam Generator Level 2 PTI-003A-02Unit2 Rev.0000
Page 71 of 182
Date
6.4 SG 4 Narrow Range Level Instrument Test (continued)
F. TB 205-11 and TB 205-12 in Panel 2-R-49(Dwg 45N2677-10
CV
NOTE
Annunciator Window 2-XA-55-6B, 119-B, SG 4 LEVEL HI-HI, will alarm at approximately82% level. The alarm may be acknowledged and silenced. No other action is required.
NOTE
Steps 6.4[l 1]A, B, and C may be signed off as they occur
[11] SLOWLY INCREASE the level in Steam Generator 4 AND
A. WHEN TB 403-11 and TB 403-12 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),
RECORD SG 4 Level on 2-LI-3-1 10, SG 4 LEVEL, at2-M-4. (ACC CRIT) 5.OC.1 [82.4% (79.9% - 84.9%)]
B. WHEN TB 304-7 and TB 304-8 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),
RECORD SG 4 Level on 2-LI-3-107, SG 4 LEVEL, at2-M-4. (ACC CRIT) 5.OC.1 [82.4% (79.9% - 84.9%)]
C. WHEN TB 205-11 and TB 205-12 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),
RECORD SG 4 Level on 2-LI-3-106, SG 4 LEVEL, at2-M-4. (ACC CRIT) 5.OC.1 [82.4% (79.9% - 84.9%)]
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
~Page 72 of 182
Date
6.4 SG 4 Narrow Range Level Instrument Test (continued)
NOTE
The following two steps will raise the SG 4 level to the upper NR tap. Data collection shouldbe completed as rapidly as possible.
[12] SLOWLY increase the level in the SG 4 until the meterslabeled SG 4 Level installed in 2-R-5, 2-R-11, and 2-R-12 nolonger indicate increasing voltage which indicates the waterlevel has reached the upper tap:
A. 2-R-5, SG 4 Level
B. 2-R-11, SG 4 Level
C. 2-R-12, SG 4 Level
(13] COMPLETE Data Sheet 40.
[14] SLOWLY DECREASE the level in SG 4 until level change isindicated on the following instruments which indicates thewater level has fallen below the upper tap:
A. 2-LI-3-110, SG 4 LEVEL
B. 2-LI-3-107, SG 4 LEVEL
C. 2-LI-3-106, SG 4 LEVEL
[15] COMPLETE Data Sheet 41.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 73 of 182
Date
6.4 SG 4 Narrow Range Level Instrument Test (continued)
NOTE
Steps 6.4116]A through 6.4[16]C may be signed off as they occur.
NOTE
Annunciator Window 2-XA-55-6B, 119-B, SG 4 LEVEL HI-HI, will clear at approximately81% level. The alarm may be acknowledged and silenced. No other action is required.
[16] SLOWLY DECREASE the level in SG 4 AND
A. WHEN TB 403-11 and TB 403-12 in Panels 2-R-46 and 2-R-49 indicate the trip is OFF (voltage indicated),
RECORD SG 4 Level indication on 2-LI-3-1 10, SG 4LEVEL, at 2-M-4. [81.4% (78.9% - 83.9%)]
B. WHEN TB 304-7 and TB 304-8 in Panels 2-R-46 and 2-R-49 indicate the trip is OFF (voltage indicated),
RECORD SG 4 Level indication on 2-LI-3-107, SG 4LEVEL, at 2-M-4. [81.4% (78.9% - 83.9%)]
C. WHEN TB 205-1 land TB 205-12 in Panels 2-R-46 and 2-R-49 indicate the trip is OFF (voltage indicated),
.RECORD SG 4 Level indication on 2-LI-3-106, SG 4LEVEL, at 2-M-4. [81.4% (78.9% - 83.9%)]
%I
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 74 of 182
Date
6.4 SG 4 Narrow Range Level Instrument Test (continued)
[17] REMOVE Digital Multimeters installed in at the followinglocations:
A. TB 403-11 and TB 403-12 in Panel 2-R-46
B. TB 403-11 and TB 403-12 in Panel 2-R-49
CV
CV
C. TB 304-7 and TB 304-8 in Panel 2-R-46
D. TB 304-7 and TB 304-8 in Panel 2-R-49
E. TB 205-11 and TB 205-12 in Panel 2-R-46
CV
CV
,CV
CV
F. TB 205-11 and TB 205-12 in Panel 2-R-49
NOTE
Annunciator Window 2-XA-55-3C, 63-B, SG 4 LEVEL HI, will clear at approximately 74%level. The alarm may be acknowledged and silenced. No other action is required.
[18] SLOWLY DECREASE the level in SG 4 until approximately75% is indicated on 2-LI-3-106, SG 4 LEVEL.
[19] COMPLETE Data Sheet 42.
[20] SLOWLY DECREASE the level in SG 4 until approximately50% is indicated on 2-LI-3-106, SG 4 LEVEL.
[21] COMPLETE Data Sheet 43.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 75 of 182
Date
6.4 SG 4 Narrow Range Level Instrument Test (continued)
[22] SLOWLY DECREASE the level in SG 4 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION., CLEARS.
A. VERIFY Unit 2 Events Display Legend indicates 63-F SG4 LEVEL HI (LS-3-11OD) is NORMAL (Blue)
B. RECORD the level indication from 2-FR-3-103, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE)
C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.4[22]B.[Programmed level +4% (>1%, <7%)]
% - 38% =
[23] SLOWLY DECREASE the level in SG 4 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, ALARMS.
A. VERIFY Unit 2 Events Display Legend indicates 63-F SG4 LEVEL LO (LS-3-1 10 E) is in ALARM (Red)
B. RECORD the level indication from 2-FR-3-103, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE)
C. DETERMINE the percent deviation by subtracting theindication recorded in Step 6.4[23]B from 38%.[Programmed level -5% (>2%, -8%)]
% - 38% %
NOTE
Annunciator Window 2-XA-55-3C, 63-D, SG 4 LEVEL LO, will alarm approximately 25%level. The alarm may be acknowledged and silenced. No other action is required.
[24] SLOWLY DECREASE the level in SG 4 until approximately25% is indicated on 2-LI-3-106, SG 4 LEVEL.
[25] COMPLETE Data Sheet 44.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 76 of 182
Date
6.4 SG 4 Narrow Range Level Instrument Test (continued)
[26] INSTALL and LABEL Digital Multimeters AND
VERIFY trip signals are OFF as indicated by presence ofvoltage at the following locations: (2-R-46 - Control BuildingAuxiliary Instrument Room 708/C8P, 2-R-49 - Control BuildingAuxiliary Instrument Room 708/C8P)
A. TB 404-11 and TB 404-12 in Panel 2-R-46(Dwg 45N2676-2)
CV
B. TB 404-11 and TB 404-12 in Panel 2-R-49(Dwg 45N2677-2)
CV
C. TB 305-7 and TB 305-8 in Panel 2-R-46(Dwg 45N2676-2)
CV
D. TB 305-7 and TB 305-8 in Panel 2-R-49(Dwg 45N2677-2)
CV
E. TB 206-5 and TB 206-6 in Panel 2-R-46(Dwg 45N2676-1)
CV
F. TB 206-5 and TB 206-6 in Panel 2-R-49(Dwg 45N2677-1)
CV
[27] VERIFY Annunciator Window 2-XA-55-6B, 119-D, SG 4LO-LO LEVEL TTD INITIATED, at 2-M-6 is CLEAR.
[28] SLOWLY DECREASE the level in Steam Generator 4.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 77 of 182
Date
6.4 SG 4 Narrow Range Level Instrument Test (continued)
NOTE
Steps 6.4[31]A through 6.4[31]F may be signed off as they occur.
NOTE
Annunciator Window 2-XA-55-6B, 119-E, SG 4 LEVEL LO-LO, will alarm at approximately17% level. The alarm may be acknowledged and silenced. No other action is required.
[29] VERIFY Annunciator Window 2-XA-55-6B, 11 9-D, SG4 LO-LOLEVEL TTD INITIATED, at 2-M-6, ALARMS as the SteamGenerator level reaches 17% (14.5 %- 19.5%).
[30] VERIFY the following Event Display Legends are in alarm.
Stop decreasing Steam Generator level when all three are in.
A. 119-D SG 4 LOLO LEVEL TTD INITIATED (ILY/549H).
B. 119-D SG 4 LOLO LEVEL TTD INITIATED (ILY/548H).
C. 119-D SG 4 LOLO LEVEL TTD INITIATED (ILY/547H).
NOTE
After the time delay (TTD) has finished (approximately 8 minutes), all three trip channelsshould come in.
[31] RECORD the level from the specified indicators AND
VERIFY status of associated computer points as the followingtrip signals come ON as indicated by absence of voltage at thefollowing locations:
A. TB 404-11 and TB 404-12 in Panel 2-R-46 and 2-R-49,SG 4 Level indication on 2-LI-3-1 10, SG 4 LEVEL, at2-M-4. (ACC CRIT) 5.0C.2 [17% (14.5% - 19.5%)]
B. Computer Point L0465D indicates TRIP.(ACC CRIT) 5.OC.2
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 78 of 182
Date
6.4 SG 4 Narrow Range Level Instrument Test (continued)
C. TB 305-7 and TB 305-8 in Panel 2-R-46 and 2-R-49, SG 4Level indication on 2-LI-3-107, SG 4 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5% - 19.5%)]
D. Computer Point L0464D indicates TRIP.(ACC CRIT) 5.0C.2
E. TB 206-5 and TB 206-6 in Panel 2-R-46 and 2-R-49, SG 4Level indication on 2-LI-3-106, SG 4 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5% - 19.5%)]
F. Computer Point L0463D indicates TRIP.(ACC CRIT) 5.OC.2
NOTE
The following two steps will decrease the Steam Generator Level to the lower NR tap. Datacollection should be completed as rapidly as possible.
[32] SLOWLY DECREASE the level in SG 4 until the meterslabeled SG 4 Level installed in 2-R-5, 2-R-1 1, and 2-R-12 nolonger indicate decreasing voltage which indicates the waterlevel has reached the lower tap.
A. 2-R-5, SG 4 Level
B. 2-R-!1, SG4 Level
C. 2-R-12, SG 4 Level
[33] COMPLETE Data Sheet 45.
[34] SLOWLY INCREASE the level in SG 4 until level change isindicated on the following instruments which indicates thewater level has risen above the lower tap:
A. 2-LI-3-110, SG4 LEVEL
B. 2-LI-3-107, SG 4 LEVEL
C. 2-LI-3-106, SG 4 LEVEL
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 79 of 182
Date
6.4 SG4 Narrow Range Level Instrument Test (continued)
.[35] COMPLETE Data Sheet 46.
NOTE
Steps 6.4[36]A through 6.4[36]F may be signed off as they occur.
NOTE
Annunciator Window 2-XA-55-6B, 11 9-E, SG 4 LEVEL LO-LO, will clear at approximately18% level. The alarm may be acknowledged and silenced. No other action is required.
[36] SLOWLY INCREASE the level in SG 4 AND
RECORD the level from the specified indicators AND
VERIFY status of associated computer points as the followingtrip signals CLEAR as indicated by presence of voltage at thefollowing locations:
A. TB 404-11 and TB 404-12 in Panel 2-R-46 and 2-R-49,SG 4 Level indication on 2-LI-3-1 10, SG 4 LEVEL, at2-M-4. [18% (15.5% - 20.5%)]
B. Computer Point L0465D indicates NOT TR.
C. TB 305-7 and TB 305-8 in Panel 2-R-46 and 2-R-49, SG 4.Level indication on 2-LI-3-107, SG 4 LEVEL, at 2-M-4.[18% (15.5% - 20.5%)]
D. Computer Point L0464D indicates NOT TR.
E. TB 206-5 and TB 206-6 in Panel 2-R-46 and 2-R-49, SG 4Level indication on 2-LI-3-106, SG 4 LEVEL, at 2-M-4.(18% (15.5% - 20.5%)]
%/
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 80 of 182
Date
6.4 SG 4 Narrow Range Level Instrument Test (continued)
F. Computer Point L0463D indicates NOT TR.
[37] REMOVE Digital Multimeters installed at the followinglocations:
A. TB 404-11 and TB 404-12 in Panel 2-R-46
B. TB 404-11 and TB 404-12 in Panel 2-R-49
C. TB 305-7 and TB 305-8 in Panel 2-R-46
CV
CV
CV
CV
CV
CV
D. TB 305-7 and TB 305-8 in Panel 2-R-49
E. TB 206-5 and TB 206-6 in Panel 2-R-46
F. TB 206-5 and TB 206-6 in Panel 2-R-49
[38] VERIFY Annunciator Window 2-XA-55-6B, 11 9-D, SG 4LO-LO LEVEL TTD INITIATED, CLEARS when all trip signalsare cleared.
[39] VERIFY Unit 2 Events Display Legend indicates 119-D, SG 4LO-LO LEVEL TTD INITIATED is in CLEAR (Blue).
NOTE
Annunciator Window 2-XA-55-3C, 63-D, SG 4 LEVEL LO, will clear at approximately 25%level. The alarm may be acknowledged and silenced. No other action is required.
[40] SLOWLY INCREASE the level in Steam Generator 4 untilapproximately 25% is indicated on 2-LI-3-106, SG 4 LEVEL.
[41] COMPLETE Data Sheet 47.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 81 of 182
Date
6.4 SG 4 Narrow Range Level Instrument Test (continued)
[42] SLOWLY INCREASE the level in SG 4 until AnnunciatorWindow 2-XA-55-3C 63-F, SG LEVEL DEVIATION, CLEARS.
A. VERIFY Unit 2 Events Display Legend indicates 63-F SG4 LEVEL LO (LS-3-1 10E) is CLEAR (Blue).
B. RECORD the level indication from 2-FR-3-103, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE)
C. DETERMINE the percent deviation by subtracting theindication recorded in Step 6.4[42]B from 38%.[Programmed level -4% (-1 %, <7%)],
% - 38% =
[43] SLOWLY INCREASE the level in Steam Generator 4 until
approximately 38% is indicated on 2-LI-3-106, SG 4 LEVEL.
[44] COMPLETE Data Sheet 48.
[45] REMOVE the meters from the following test points:
A. Panel 2-R-5, SG 4 Level, Test Point 2LP/549B
CV
B. Panel 2-R-11,ZSG 4 Level, Test Point 2LP/548B
CV
C. Panel 2-R-12, SG 4 Level, Test Point 2LP/547B
CV
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 82 of 182
Date
6.4 SG 4 Narrow Range Level Instrument Test (continued)
[461 VERIFY that level indications and calculated levels satisfyAcceptance Criteria 5.0 B.land 5.0 B.2 as specified on thefollowing Data Sheets. (ACC CRIT)
A. Data Sheet 37.
-B. Data Sheet 38.
C. Data Sheet 39.
D. Data Sheet 41.
E.. Data Sheet42.
F. Data Sheet 43.
.G. Data Sheet 44.
H. Data Sheet 46.
I. Data Sheet 47.
J. Data Sheet48.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02•Unit 2 Rev. 0000
Page 83 of 182
7.0 POST PERFORMANCE ACTIVITY
[1] NOTIFY the Unit 2 US/SRO of the test completion and systemalignment.
[2] VERIFY that Post-test calibration of the M&TE used to recordquantitative acceptance criteria has been satisfactorily performed,
AND
RECORD the results on M&TE Log.
[3] VERIFY that Post-test calibration of permanent plant instrumentsused to record quantitative acceptance criteria has beensatisfactorily performed,
AND
RECORD the results on Appendix C, Permanent PlantInstrumentation Log.
8.0 RECORDS
A. QA Records
Completed Test Package
B. Non-QA Records
None
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 84 of 182
Appendix A(Page 1 of 2)
Test Proceduresllnstructions Reference Review
NOTES
1) Additional copies of this table may be made as necessary.
2) Initial and date indicates review has been completed for impact.
PROCEDURE/INSTRUCTION REVISIONICHANGES
Unit 2 FSAR - Amendment 107
Table 14.2.1 Sheet 77
Table 14.2.1 Sheet 78
Table 14.2.1 Sheet 79
2-SOI-2&3.01
2-SO1-15.01
2-TSD-3A-2
SSD-2-LPF-3-35
(review against SSD-1-LPF-3-35)
SSD-2-LPF-3-48
(review against SSD-1-LPF-3-48)
SSD-2-LPF-3-90
(review against SSD-1-LPF-3-90)
SSD-2-LPF-3-103
(review against SSD-1-LPF-3-103)
2-L-3-38
2-L-3-39
2-L-3-42
2-L-3-51
2-L-3-52
IMPACT
Yes/NoINITIAL AND DATE.(N/A for no change)
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 85 of 182
Appendix A(Page 2 of 2)
Test Proceduresllnstructions Reference Review
PROCEDURE/ IMPACT INITIAL AND DATE.INSTRUCTION REVISIONICHANGESYes/No (N/A for no change)
2-L-3-55
2-L-3-93
2-L-3-97
2-L-3-106
2-L-3-107
2-L-3-1 10
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 86 of 182
Appendix B(Page 1 of 1)
Temporary Condition Log
Date
NOTE
These steps will be marked NIA if no temporary condition existed. Additional copies of thistable may be made as necessary.
TEMPORARY PERFORMED RETURNED TO NORMALITEM CONDITION Step Perf. By/Date Step Returned By/Date
NUMBER DESCRIPTION Number CV/Date Number CV/Date
.WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 87 of 182
Appendix C(Page 1 of 3)
Permanent Plant Instrumentation Log
Date
POST-TEST
FILLED AND PLACED IN CALIBRATION
INSTRUMENT OR VENTED(1) SERVICE(1) USED FOR QUANTITATIVE ACC CRIT ACCEPTABLE
INSTRUMENT POST-TEST CALLOOP CAL DUE DATE INITIDATE INITIDATE YES NO DATE(2) INIT/DATE
2-L-3-38
2-L-3-39
2-L-3-42
2-L-3-51
2-L-3-52
2-L-3-55
2-L-3-93
2-mL-3-94
2-L-3-97
2-L-3-106
2-L-3-107
2-L-3-1 10
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 88 of 182
Appendix C(Page 2 of 3)
Permanent Plant Instrumentation Log
Date
POST-TESTFILLED AND PLACED IN CALIBRATION
INSTRUMENT OR VENTED(I) SERVICE(1) USED FOR QUANTITATIVE ACC CRIT ACCEPTABLEINSTRUMENT POST-TEST CAL
LOOP CAL DUE DATE INITIDATE INITIDATE YES NO DATE(2) INITIDATE
2-L-3-35
2-L-3-48
2-L-3-90
2-L-3-103
2-L-3-231
2-L-3-232
2-L-3-233
2-L-3-234
2-L-3-43
2-L-3-56
2-L-3-98
2-L-3-1 11
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 89 of 182
Appendix C(Page 3 of 3).
Permanent Plant Instrumentation Log
Date
POST-TEST
FILLED AND PLACED iN CALIBRATIONINSTRUMENT OR VENTED(1) SERVICE(1) USED FOR QUANTITATIVE ACC CRIT ACCEPTABLE
INSTRUMENT POST-TEST CALLOOP CAL DUE DATE INITIDATE INITIDATE YES NO DATE(2) INIT/DATE
2-L-3-148
2-L-3-156
2-L-3-164
2-L-3-171
2-L-3-172
2-L-3-173
2-L-3-174
2-L-3-175
(1) These items may be initialed and dated by personnel performing the task. Instrumentation not required to be filled and ventedmay be identified as Not Applicable (NA).
(2) May be identified as NA if instrument was not used to verify/record quantitative acceptance criteria data.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 90 of 182
Table 1
(Page 1 of 1)
Computer Point Verification Log
Date
Computer Point Description Status Initials
Set Reset
L0403D STM GEN 1 LO-LO TRIP NOT TRLI PART RE
L0404D STM GEN 1 LO-LO TRIP NOT TRL2 PART RE
L0405D STM GEN 1 LO-LO TRIP NOT TRL3 PART RE
L0423D. STM GEN 2 LO-LO TRIP NOT TRL1 PART RE
L0424D STM GEN 2 LO-LO TRIP NOT TRL2 PART RE
L0425D STM GEN 2 LO-LO TRIP NOT TRL3 PART RE
L0443D STM GEN 3 LO-LO TRIP NOT TRL1 PART RE
L0444D STM GEN 3 LO-LO TRIP NOT TRL2 PART RE
L0445D STM GEN 3 LO-LO TRIP NOT TRL3 PART RE
L0463D STM GEN 4 LO-LO TRIP NOT TRLi PART RE
L0464D STM GEN 4 LO-LO TRIP NOT TRL2 PART RE
L0465D STM GEN 4 LO-LO TRIP NOT TRL3 PART RE
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 91 of 182
Table 2(Page 1 of 2)
Train A Plastic Screw Verification
.Date
Panel TB Drawing Point Initials
2-R-48 634 2-45N2676-5 1
2-R-48 634 2-45N2676-5 2
2-R-48 634 2-45N2676-5 3
2-R-48 634 2-45N2676-5 4
2-R-48 634 2-45N2676-5 5
2-R-48 634 2-45N2676-5 6
2-R-48 634 2-45N2676-5 7
2-R-48 634 2-45N2676-5 8
2-R-48 634 2-45N2676-5 11
2-R-48 634 2-45N2676-5 12
2-R-48 635 2-45N2676-5 I
2-R-48 635 2-45N2676-5 2
2-R-48 632 2-45N2676-5 1
2-R-48 632 2-45N2676-5 .2
2-R-48 630 2-45N2676-5 9
2-R-48 630 2-45N2676-5 10
2-R-48 631 2-45N2676-5 5
2-R-48 631 2-45N2676-5 6
2-R-48 631 2-45N2676-5 7
2-R-48 631 2-45N2676-5 8
2-R-48 648 2-45N2676-5 1
2-R-48 648 2-45N2676-5 2
2-R-48 648 2-45N2676-5 3
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 92 of 182
Table 2(Page 2 of 2)
Train A Plastic Screw Verification
Date
Panel TB Drawing Point Initials
2-R-48 648 2-45N2676-5 4
2-R-48 649 2-45N2676-5 1
2-R-48 649 2-45N2676-5 2
2-R-48 649 2-45N2676-5 3
2-R-48 649 2-45N2676-5 4
2-R-48 621 2-45N2676-4 9
2-R-48 621 2-45N2676-4 10
2-R-48 621 2-45N2676-4 11
2-R-48 621 2-45N2676-4 12
2-R-48 622 2-45N2676-4 1
2-R48 622 2-45N2676-4 2
2-R-48 622 2-45N2676-4 5
2-R-48 622 2-45N2676-4 6
2-R-48, 622 2-45N2676-4 7
2-R-48 622 2-45N2676-4 8
2-R-48 622 2-45N2676-4 9
2-R-48 622 2-45N2676-4 10
Table 3(Page 1 of 2)
Train B Plastic Screw Verification
Date
Panel TB Drawing Point Initials
2-RW51 634 2-45N2677-5 1
2.,R-5 634 2-45N2677-5 2
2-*R-51 634 2-45N2677-5 3
2-R-51 634 2-45N2677-5 4
* 2-R-51 634 2-45N2677-5 5
2-R-51 634 2-45N2677-5 6
2-R-51 634 2-45N2677-5 7
2-R-51. 634 2-45N2677-5 8
2-R-51 634 2-45N2677-5 1i
2-R-51 . 634 2-45N2677-5 12
2-R-51 635 2-45N2677-5 1
2-R-51 635 2-45N2677-5 2
2-R-51 632 2-45N2677-5 1
2-R-51 632 2-45N2677-5 2
2-R-51 630 2-45N2677-5 9
2-R-51 630 2-45N2677-5 10
2-PýR5.1 631 2-45N2677-5 5
2-R-51 631 2-45N2677-5 6
2-R-51 631 2-45N2677-5 7
2-R-51 631 2-45N2677-5 8
2-R-51. 648 2-45N2677-5 1
2-R-51 648 2-45N2677-5 2
2-R-51 648 2-45N2677-5 3
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2- Rev. 0000
Page 94 of 182
Table 3(Page 2 of 2)
Train B Plastic Screw Verification
Date
Panel TB Drawing Point Initials
2-R-51 648 2z.45N2677-5 4
2-R-51 649 2-45N2677-5 1
2-R-51 649 2-45N2677-5 2
2-R-51 649 2-45N2677-5 3
2-R-51 649 2-45N2677-5 4
2-R-51 621 2-45N2677-4 9
2-R-51 621 2-45N2677-4 10
2-R-51 621 2-45N2677-4 11
2-R-51 621 2-45N2677-4 12
2-R-51 622 2-45N2677-4 1
2-R-51 622 2-45N2677-4 .2
2-R-51 622 2-45N2677-4 5.
2-R-51 622 2-45N2677-4 6
2-R-51 622 2-45N2677-4 7
2-R:51 622 2745N2677-4 8
2-R-51 622 2-45N2677-4 9
2-R-51 622 2-45N2677-4 10
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000
Page 95 of 182
Data Sheet I(Page 1 of 2)
SG I - Initial Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage 0)(3)
2-LI-3-38 (2) 2-R-5 - 2LP/519B
2-LI-3-39 (2) 2-R-1 1 - 2LP/518B
2-LI-3-42 2) 2-R-12 - 2LP/517B
2-FR-3-35 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-43A N/A N/A N/A N/A
2-LI-3-43B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen. 1 Red)
2-LI-3-164 N/A N/A N/A N/A
2-LI-3-164C N/A N/A N/A N/A
2-LI-3-174 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 96 of 182
Data Sheet I(Page 2 of 2)
SG I - Initial Level Verification Data
Date
(1) Calculations
2LP/51 9B Calculated Level = (Indicated Voltage - 0. 19829)x 100%
0.79315100%
Calculated Level = ( -0.19829) x 0.7931%5)
Calculation Performed By: Verified By:
2LP/518B 100%Calculated Level = (Indicated Voltage - 0.19829) x
0.79315100%
Calculated Level= ( -- 0.19829)x 0 15%)•0.79315
Calculation Performed By: Verified By:
2LP/51 7B Calculated Level = (Indicated Voltage - 0. 19829) x 100%0.79315
100%Calculated Level= ( -0.19829)x 0.7931%)
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 97 of 182
Data Sheet 2(Page I of 2)
SG I - 50% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials
Location Voltage ()3)
2-LI-3-38 (2) 2-R-5 - 2LP/519B
2-LI-3-39 (2) 2-R-11 - 2LP/518B
2-LI-3-42 (2) 2-R-12 - 2LP/517B
2-FR-3-35 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-43A N/A N/A N/A N/A
2-LI-3-43B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen 1 Red)
2-LI-3-164 N/A N/A N/A N/A
2-LI-3-164C N/A N/A N/A N/A
2-LI-3-174 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 98 of 182
Data Sheet 2(Page 2 of 2)
SG 1 - 50% Level Verification Data
Date
(1) Calculations
2L-P/519B 100%Calculated Level = (Indicated Voltage- 0. 19829)x
0.79315
Calculated Level =( -0.19829)x 100%0.79315
Calculation Performed By: Verified By:
2LP/51 8B 100%Calculated Level = (Indicated Voltage - 0.19829)x 0.91
0.79315
Calculated Level= -0.19829)x 0%5 - ( %)
Calculation Performed By: Verified By:
2LP/517B Calculated Level = (Indicated Voltage- 0. 19829) x 100%
0.79315100% _
Calculated Level = ( -0.19829)x 0.79315 %)0.79315
rCalculation Performed By: jVerified B .y:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 99 of 182
Data Sheet 3(Page 1 of 2)
SG I - 75% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1)(3)
2-LI-3-38 (2) 2-R-5 - 2LP/519B
2-LI-3-39 (2) 2-R-11 - 2LP/518B
2-LI-3-42 (2) 2-R-12 - 2LP/517B
2-FR-3-35 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-43A N/A N/A N/A N/A
2-LI-3-43B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen 1 Red)
2-LI-3-164 N/A N/A N/A N/A
2-LI-3-164C N/A N/A N/A N/A
2-LI-3-174 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000
Page 100 of 182
Data Sheet 3(Page 2 of 2)
SG 1 -75% Level Verification Data
Date
(1) Calculations
2LP/51 9B Calculated Level = (Indicated Voltage- 0. 19829)x 100%
0.79315
Calculated Level= ( -0.19829)x 0 .7 %)0 .79315
Calculation Performed By: Verified By:
2LP/51 8B Calculated Level = (Indicated Voltage - 0. 19829) x
0.79315100%
Calculated Level ( - 0.19829)x- 0.9)1
Calculation Performed By: Verified By:
2LP/517B Calculated Level = (Indicated Voltage - 0. 19829)x 0.3
Calculated Level:= ( -0.19829)x 100% =( %0.793150
Calculation Performed By: Verified By:
WBN Feedwater & St eam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 101 of 182
Data Sheet 4(Page I of 1)
SG 1 - 100% Tap Verification Data
Date
DVM Test Point Location Indicated Voltage M&TE No. Initials
2-R-52LP/519B
2-R-112LP/518B
.2-R-:122LP/517B
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 102 of 182
Data Sheet 5
(Page 1 of 2)
SG I - 100% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials
Location Voltage (1X3)
2-LI-3-38 (2) 2-R-5 - 2LP/519B
2-LI-3-39 (2) 2-R-11 - 2LP/518B
2-LI-3-42 (2) 2-R-12 - 2LP/517B
2-FR-3-35 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-43A N/A N/A N/A N/A
2-LI-3-43B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen 1 Red)
2-LI-3-164 N/A N/A N/A N/A
2-LI-3-164C N/A N/A N/A N/A
2-LI-3-174 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000
Page 103 of 182
Data Sheet 5
(Page 2 of 2)
SG 1 - 100% Level Verification Data
Date
(1) Calculations
2LP/51 9B 10Calculated Level = (Indicated Voltage- 0. 19829)x 100%0.79315
Calculated Level = ( -0.19829)x 100% =( %)0.79315
Calculation Performed By: Verified By:
.2LP/518B 100%Calculated Level = (Indicated Voltage - 0. 19829) x 100%
Calculated Level = ( -0.19829)x 100%%)/ 0.79315
Calculation Performed By: Verified By:
2LP/517B 1 000/Calculated Level = (Indicated Voltage- 0.19829)x
0.79315
Calculated Level= ( -0.19829)x 100% =%)0.79315
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 104 of 182
Data Sheet 6(Page I of 2)
SG 1 - 75% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1)(3)
2-LI-3-38 (2) 2-R-5 - 2LP/519B
2-LI-3-39 (2) 2-R-1I - 2LP/518B
2-LI-3-42 (2) 2-R-12 - 2LP/517B
2-FR-3-35 N/A N/A NIA N/A(Pen 3 Blue)
2-LI-3-43A N/A N/A. N/A N/A
2-LI-3-43B N/A N/A N/A N/A
2-LR-3-43 N/A -N/A N/A N/A(Pen 1 Red)
2-LI-3-164 N/A N/A N/A N/A
2-LI-3-164C N/A N/A N/A N/A
2-LI-3-174. N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000
Page 105 of 182
Data Sheet 6(Page 2 of 2)
SG 1 - 75% Level Verification Data
Date
(1) Calculations
2LP/519B 100%Calculated Level = (Indicated Voltage - 0. 19829) x 0.79315
Calculated Level = ( -0.19829)x 10.7 %)
Calculation Performed By: Verified By:
2LP/518B Calculated Level = (Indicated Voltage - 0.19829) x 100%0.793 15
Calculated Level = -0.9829 100% ( %)0.79315
Calculation Performed By: Verified By:
2LP/517B 100%Calculated Level = (Indicated Voltage - 0. 19829) x
0.79315
Calculated Level =( -0.19829)x 7100% %0.79315n o Be y
rCalculatio~n Performed• By: Verified By:
WBNUnit 2
Feedwater & Steam Generator Level 2-PTI-003A-02Rev. 00.00Page 106 of 182
Data Sheet 7
(Page 1 of 2)
SG 1 - 50% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1X3)
2-LI-3-38 (2) 2-R-5 - 2LP/519B
2-LI-3-39 (2) 2-R-11 - 2LP/518B
2-LI-3-42 (2) 2-R-12 - 2LP/517B
2-FR-3-35 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-43A N/A N/A N/A N/A
2-LI-3-43B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen 1 Red)
2-LI-3-164 N/A N/A N/A N/A
2-LI-3-164C N/A N/A N/A •N/A
2-LI-3-174 I N/A. N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 107 of 182
Data Sheet 7(Page 2 of 2)
SG I - 50% Level Verification Data
Date
(1) Calculations
2LP/51 9B 10Calculated Level = (Indicated Voltage -0.19829)× 100%0.79315
Calculated Level= ( -0.19829)x 0.79315 %)
Calculation Performed By: Verified By:
2LP/518B , - • 10Calculated Level = (Indicated Voltage - 0.19829) 100%0.79315
100%Calculated Level= (. -0.19829)x 0791 %)
Calculation Performed By: Verified By:
2LP/517B , 100%Calculated Level = (Indicated Voltage- 0.19829) xVoltge '0.79315
100%Calculated Level= ( -0.19829)x 0915
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000
Page 108 of 182Data Sheet 8
(Page 1 of 2)
SG 1 - 25% Level Verification Data
Date
Instrument Indication % DVM Test Point. M&TE No. Indicated Calculated Level InitialsLocation Voltage (IX3)
2-LI-3-38 (2) 2-R-5 - 2LP/519B
2-LI-3-39 (2) 2-R-1 I - 2LP/518B.
2-LI-3-42 .(2) 2-R-12 - 2LP/517B
2-FR-3-35 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-43A N/A N/A N/A N/A
2-LI-3-43B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen 1 Red)
2-LI-3-164 N/A N/A N/A N/A
2-LI-3-164C N/A N/A N/A N/A
2-LI-3-174 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000
Page 109 of 182
Data Sheet 8(Page 2 of 2)
SG I - 25% Level Verification Data
Date
(1) Calculations
2LP1519B : Calculated Level = (Indicated'Voltage -0.19829)x 100%
0.79315
Calculated Level=( -0.19829)x 100% 5 %)0.79315
Calculation Performed By: Verified By:
2LP/518B 192~x100%Calculated Level = (Indicated Voltage-0. 019829)x 150.79315
CalculatedLevel=( -0.19829)x 100% 6(0.79315
Calculation Performed By: Verified By:
2LP/51 7B Calculated Level = (Indicated Voltage- 0. 19829) x 100%
Calculated Level = ( -0.19829)x 100%
0 .79315
Calculation Performed By: FVerified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 110 of 182
Data Sheet 9(Page 1 of 1)
SG 1 - 0% Tap Verification Data
Date
DVM Test Point Location Indicated Voltage M&TE No. Initials
2-R-5
2LP/519B
2-R-112LP/518B
2-R-122LP/517B
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 111 of 182
Data Sheet 10(Page 1 of 2)
SG 1 -0% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1X3)
2-LI-3-38 (2) 2-R-5 - 2LP/519B
2-LI-3-39 (2) 2-R-1 1 - 2LP/518B
2-LI-3-42 (2) 2-R-12 - 2LP/517B
2-FR-3-35 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-43A N/A N/A N/A N/A
2-LI-3-43B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen I Red)
2-LI-3-164 N/A N/A N/A N/A
2-LI-3-164C N/A N/A N/A N/A
2-LI-3-174 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 112 of 182
Data Sheet 10(Page 2 of 2)
SG,1 - 0% Level Verification Data
Date
(1) Calculations
2LP/519B 100%2 Calculated Level = (Indicated Voltage - 0. 19829) x 100%
0.79315
Calculated Level = ( -0.19829)x 0.79315)
Calculation Performed By: Vedfied By:
2LP/51 8B Calculated Level = (Indicated Voltage - 0. 19829) x 100%
0.79315100%
Calculated Level= ( -0.19829)x 0.79315 ( %)
Calculation Performed By: Verified By:
2LP/517B Calculated Level = (IndicatedVoltage - 0. 19829) x 100%
0.79315
Calculated Level = ( - O.19829)x 710%
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 113 of 182
Data Sheet 11(Page 1 of 2)
SG I - 25% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1)(3)
2-LI-3-38 (2) 2-R-5 - 2LP/519B
2-LI-3-39 (2) 2-R-11 - 2LP/51 8B
2-LI-3-42 (2) 2-R-12 - 2LP/517B
2-FR-3-35 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-43A N/A N/A N/A N/A
2-LI-3-43B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen I Red)
2-LI-3-164 N/A N/A N/A N/A
2-LI-3-164C N/A N/A N/A N/A
2-LI-3-174 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 114 of 182
Data Sheet 11(Page 2 of 2)
SG 1,, 25% Level Verification Data
Date
(1) Calculations
2LP/519B 100%Calculated Level = (Indicated Voltage - 0. 19829) x 100
0.79315- Calculated Levei= ( -O. 19829) 0.79315%)
Calculation Performed By: Verified By:
2LP/518B Calculated Level = (Indicated Voltage- -. 19829) x 100%
g0.79315100%Calculated Level = ( -0.19829)x 079 15%)0.79315
Calculation Performed By: Verified By:2LP/517B 100%
Calculated Level = (Indicated Voltage- 0.19829)x 100.79315
Calculated Level -0.19829)x 100% %
0.79315
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000
Page 115 of 182
Data Sheet 12(Page I of 2)
SG I - Final Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials(2) Location Voltage (1X3)
2-LI-3-38 (2) 2-R-5 - 2LP/519B
2-LI-3-39 (2) 2-R-1 I - 2LP/518B
2-LI-3-42 (2) 2-R-12 - 2LP/517B
2-FR-3-35 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-43A N/A N/A N/A N/A
2-LI-3-43B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen 1 Red)
2-LI-3-164 N/A N/A N/A N/A
2-LI-3-164C N/A N/A N/A N/A
2-LI-3-174 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 116 of 182
Data Sheet 12(Page 2 of 2)
SG 1 - Final Level Verification Data
Date
(1) Calculations
2LP/519B 100%Calculated Level = (Indicated Voltage- 0. 19829) x
0.79315
Calculated Level = ( -0.19829)x 100% %)0.79315
Calculation Performed By: Verified By:
2L-P/51 8B 100%Calculated Level = (Indicated Voltage - 0.19829)x 0.79315
Calculated Level = ( -0.19829)x 100% %0.793150
Calculation Performed By: Verified By:
2LP/517B 100%Calculated Level = (Indicated Voltage- 0. 19829)x
0.79315
Calculated Level = ( -0.19829)x 0791 %)C.om31B
[Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 117 of 182
Data Sheet 13(Page 1 of 2)
SG 2 - Initial Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials
Location Voltage (1)(3)
2-LI-3-51 (2) 2-R-5 - 2LP/529B
2-LI-3-52 (2) 2-R-1 I - 2LP/528B
2-LI-3-55 (2) 2-R-12 - 2LP/527B
2-FR-3-48 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-56A N/A N/A N/A N/A
2-LI-3-56B N/A N/A N/A NIA
2-LR-3-43 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-156 N/A N/A N/A N/A
2-LI-3-156C N/A N/A N/A N/A
2-LI-3-173 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 22-PTI-003A-02Unit 2 Rev. 0000
Page 118 of 182
Data Sheet 13(Page 2 of 2)
SG 2 - Initial Level Verification Data
Date
(1) Calculations
2LP/529B 100%Calculated Level = (indicated Voltage - 0. 19829) x 100%Vlae 0.79315
Calculated Level=( -0.19829) x 100% . %)0.79315
Calculation Performed By: Verified By:
2LP/528B (Indicated . 100%Calculated Level = Voltage- 0. 19829) x
100%_Calculated Level = ( -0.19829)x 0.79315 %)
Calculation Performed By: Verified By:2LP/527B 100%
Calculated Level =(Indicated Voltage - 0. 19829) x0.79315
100%Calculated Level= ( -0.19829)x 015 %)
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 119 of 182
Data Sheet 14(Page 1 of 2)
SG 2 - 50% Level Verification Data
Date
Instrument Indication % DVM Test Point
Location
2-LI-3-51 (2) 2-R-5 - 2LP/529B
2-LI-3-52 (2) 2-R-1 1 - 2LP/528B
2-LI-3-55 (2) 2-R-12 - 2LP/527B
2-FR-3-48 N/A(Pen 3 Blue)
2-LI-3-56A N/A
2-LI-3-56B N/A
2-LR-3-43 N/A(Pen 2 Green)
2-LI-3-156 N/A
2-LI-3-156C N/A
2-LI-3-173 N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
-1
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 120 of 182
Data Sheet 14(Page 2 of 2)
SG 2 - 50% Level Verification Data
Date
(1) Calculations
2L-P/529B Calculated Level = (Indicated Voltage- 0. 19829) x 100%
0.793 15100%
Calculated Level= ( -0.19829)x 715)0.79315 -(
Calculation Performed By: Verified By:2LP/528B 100%
2/ Calculated Level = (Indicated Voltage- 0. 19829)x 0.3'•. 0.79315
100%Calculated Level= ( -0.19829)x 07 %)::: 0.79315
Calculation Performed By: Vedfied By:
2LP/527B 100%Calculated Level = (Indicated Voltage- 0. 19829)x 0.79315
100%Calculated Level= ( -0.19829)x 0.79315 %)
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000
Page 121 of 182
Data Sheet 15(Page 1 of 2)
SG 2 - 75% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1)(3)
2-LI-3-51 (2) 2-R-5 - 2LP/529B
2-LI-3-52 (2) 2-R-1 1 - 2LP/528B
2-LI-3-55 (2) 2-R-12 - 2LP/527B
2-FR-3-48 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-56A N/A N/A N/A N/A
2-LI-3-56B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-156 N/A N/A N/A N/A
2-LI-3-156C N/A N/A N/A N/A
2-LI-3-173 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 122 of 182
Data Sheet 15(Page 2 of 2)
SG 2 - 75% Level Verification Data
Date
(1) Calculations
2LP/S29B 100%Calculated Level = (Indicated Voltage - 0. 19829) x
0.79315
Calculated Level= ( -0.19829)x 100.9%3 %)0.79315
Calculation Performed By: Verified By:
S2LP/528B 100%Calculated Level = (Indicated Voltage- 0. 19829) x
0.79315
CalculatedLevel=( -0.19829)x 100.73 ( %)6.79315
Calculation Performed By: Verified By:
2LP/527B 100%Calculated Level = (Indicated Voltage- 0. 19829)x 100%0.79315
Calculated Level=( -0.19829)x 1700% 5 %)0.79315
Calculation Performed By: T _Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 123 of 182
Data Sheet 16(Page 1 of 1)
SG 2 - 100% Tap Verification Data
Date
DVM Test Point Location Indicated Voltage M&TE No. Initials
2-R-52LP/529B
2-R-112LP/528B
2-R-122LP/527B
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 124 of 182
Data Sheet 17(Page I of 2)
SG 2 - 100% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1)(3)
2-LI-3-51 (2) 2-R-5 - 2LP/529B
2-LI-3-52 (2) 2-R-1 I - 2LP/528B
2-LI-3-55 (2) 2-R-12 - 2LP/527B
2-FR-3-48 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-56A N/A N/A N/A N/A
2-LI-3-56B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-156 N/A N/A N/A N/A
2-LI-3-156C N/A N/A N/A N/A
2-LI-3-173 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000
Page 125 of 182
Data Sheet 17(Page 2 of 2)
SG 2 - 100% Level Verification Data
Date
(1) Calculations
2LP/529B IOCalculated Level = (Indicated Voltage- 0.19829)x 100%
0.79315100%
Calculated Level = ( -0.19829)x 0.73 ( %)0.79315
Calculation Performed By: Verified By:
2LP/528B Calculated Level = (Indicated Voltage - 0. 19829) x 100%
0.79315
Calculated Level = ( -0.19829)x 0.79315%
Calculation Performed By: Verified By:
2LP/527B 100%Calculated Level = (Indicated Voltage- 0. 19829) x0.79315
Calculated Level = ( -0.19829) x 100% . %)0.79315
Caclation Performed By: . Vedlfied By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 126 of 182
Data Sheet 18(Page 1 of 2)
SG 2 - 75% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (XH3)
2-LI-3-51 (2) 2-R-5 - 2LP/529B
2-LI-3-52 (2) 2-R-1 1 - 2LP/528B
2-LI-3-55 (2) 2-R-12 - 2LP/527B
2-FR-3-48 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-56A N/A N/A N/A N/A
2-LI-3-56B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-156 N/A N/A N/A N/A
2-LI-3-156C N/A N/A N/A N/A
2-LI-3-173 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-I e-003A-02Unit 2 Rev.0000
Page 127 of 182
Data Sheet 18(Page 2 of 2)
SG 2 - 75% Level Verification Data
Date
(1) Calculations
2LP/529B Calculated Level = (Indicated Voltage - 0.19829) x 100%0.79315
100%Calculated Level= ( -0.19829)x 100931%)0.79315
Calculation Performed By: Verified By:
2LP/528B Calculated Level = (Indicated Voltage- 0. 19829) x 100%0.79315
100%/Calculated Level= ( -0.19829)x 0.79315 %)
Calculation Performed By: Verified By:
2LP/527B 100%Calculated Level = (Indicated Voltage- 0. 19829)x 1
0.79315100%_
Calculated Level- ( -0.19829)x 0.7931%)0.79315
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 128 of 182
Data Sheet 19(Page 1 of 2)
SG 2 - 50% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1)(3)
2-LI-3-51 (2) 2-R-5 - 2LP/529B
2-LI-3-52 (2) 2-R-1 I - 2LP/528B
2-LI-3-55 (2) 2-R-12 - 2LP/527B
2-FR-3-48 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-56A N/A N/A N/A N/A
2-LI-3-56B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-156 N/A N/A N/A N/A
2-LI-3-156C N/A N/A N/A N/A
2-LI-3-173 N/A N/A N/A N/A) MI
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1 %
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 129 of 182
Data Sheet 19(Page 2 of 2)
SG 2 - 50% Level Verification Data
Date
(1) Calculations
2LPi529B 100%Calculated Level = (Indicated Voltage- 0. 19829)x 0.30.79315
100%Calculated Level= ( -0.19829)x 0.793 15 %)
Calculation Performed By: Verified By:
2LP/528B 100%Calculated Level = (Indicated Voltage - 0.19829) x 0.79315
Calculated Level=( -0.19829)x 100% .3 %0.79315
Calculation Performed By: Verified By:
2LP/527B 100%Calculated Level = (Indicated Voltage- 0. 19829) x 100%0.79315
Calculated Level = ( -0.19829)x( %)0.79315
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000
Page 130 of 182
Data Sheet 20(Page 1 of 2)
SG 2 - 25% Level Verification Data
DateInstrument Indication % DVM Test Point
Location
2-LI-3-51 (2) 2-R-5 - 2LP/529B
2-LI-3-52 (2) 2-R-1 1 - 2LP/528B
2-LI-3-55 (2) 2-R-12 - 2LP/527B
2-FR-3-48 N/A(Pen 3 Blue)
2-LI-3-56A N/A
2-LI-3-56B N/A
2-LR-3-43 N/A(Pen 2 Green)
2-LI-3-156 N/A
2-LI-3-156C N/A
2-LI-3-173 N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 131 of 182
Data Sheet 20(Page 2 of 2)
SG 2 - 25% Level Verification Data
Date
(1) Calculations
,2L-P/529B 1 00%Calculated Level = (Indicated Voltage- 0. 19829)x 100%
0.79315
Calculation Performed By: Verified By:
2LP/528B 10l0%-Calculated Level = (Indicated Voltage- 0. 19829) x010
Calculated Level = ( --0.1982+) 100__% %)0.79315
Calculation Performed By: Verified By:2LP/527B (Idctd-. 100%
Calculated Level = (Indicated Voltage- 0. 19829) x0.3
Calculated Level = ( -0.19829)x 100. - ( %)0.79315
Calculation Performed By: T erifiedByFcBy:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 132 of 182
Data Sheet 21(Page l of 1)
SG 2 - 0% Tap Verification Data
Date
DVM Test Point Location Indicated Voltage M&TE No. Initials
2-R-52LP/529B
2-R-112LP/528B
2-R-122LP/527B
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 133 of 182
Data Sheet 22(Page 1 of 2)
SG 2 - 0% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1)(3)
2-LI-3-51 (2) 2-R-5 - 2LP1529B
2-LI-3-52 (2) 2-R-1 1 - 2LP/528B
2-LI-3-55 (2) 2-R-12 - 2LP/527B
2-FR-3-48 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-56A N/A N/A N/A N/A
2-LI-3-56B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-156 N/A N/A N/A N/A
2-LI-3-156C N/A N/A N/A N/A
2-LI-3-173 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 134 of 182
Data Sheet 22(Page 2 of 2)
SG 2 - 0% Level Verification Data
Date
(1) Calculations
2LP/529B 100%Calculated Level = (Indicated Voltage - 0. 19829) x 0.731
0.79315
Calculated Level = ( -0.1 9829)x 7100% %)0.79315=
Calculation Performed By: Verified By:2LP/528B "100%
Calculated Level (Indicated Voltage - 0. 19829) x 10.70./79315
100%/Calculated Level=( -0.19829)x 0.91 =%0.79315
Calculation Performed By: Verified By:
2LP/527B 100%Calculated Level = (Indicated Voltage- 0.19829)x0• 0.79315
100%_Calculated Level= ( -0.19829)x 0.79315 %)
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-RTI-003A-02Unit 2 Rev.0000
Page 135 of 182
Data Sheet 23(Page 1 of 2)
SG 2 - 25% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1X3)
2-LI-3-51 (2) 2-R-5 - 2LP/529B
2-LI-3-52 (2) 2-R-1 1 - 2LP/528B
2-LI-3-55 (2) 2-R-12 - 2LP/527B
2-FR-3-48 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-56A N/A N/A N/A N/A
2-LI-3-56B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-156 N/A N/A N/A N/A
2-LI-3-156C N/A N/A N/A N/A
2-LI-3-173 NIA N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 136 of 182
Data Sheet 23(Page 2 of 2)
SG 2 - 25% Level Verification Data
Date
(1) Calculations2LP/529B 100%
Calculated Level = (Indicated Voltage - Oý. 19829)x
0.79315
Calculated Level=( -0.19829)x 100% .3 %0.79315
Calculation Performed By: Verified By:
2LP/528B 100%2LP/528B Calculated Level = (Indicated Voltage- 0. 19829)x 0.30.79315
Calculated Level= ( -0.19829)x 10.9 %)
Calculation Performed By: * Verified By:
2LP/527B 100%Calculated Level = (Indicated Voltage- 0. 19829) x
0.79315
Calculated Level= ( -0.19829)x 100% .1%)0.79315
[Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000
Page 137 of 182
Data Sheet 24(Page 1 of 2)
SG 2 - Final Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials(2) Location Voltage (1 X3)
2-LI-3-51 (2) 2-R-5 - 2LP/529B
2-LI-3-52 (2) 2-R-1 1 - 2LP/528B
2-LI-3-55 (2) 2-R-12 - 2LP/527B
2-FR-3-48 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-56A N/A N/A N/A N/A
2-LI-3-56B N/A N/A N/A N/A
2-LR-3-43 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-156 N/A N/A N/A N/A
2-LI-3-156C N/A N/A N/A N/A
2-LI-3-173 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 138 of 182
Data Sheet 24(Page 2 of 2)
SG 2 - Final Level Verification Data
Date
(1) Calculations
2LP/529B Calculated Level = (Indicated Voltage - O. 19829)x 100%
0.79315
Calculated Level=( -0.19829)x 100% %)0.79315
Calculation Performed By: Verified By:
2LP/528B 100%Calculated Level = (Indicated Voltage -0. 19829)×x 100
0.79315
Calculated Level = ( - 0.19829) x 0.7935%)
Calculation Performed By: Verified By:
2LP/527B Calculated Level = (Indicated Voltage - O..19829)x 100%
0.79315
Calculated Level = ( -0.19829)x 10.3 %)
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 139 of 182
Data Sheet 25(Page 1 of 2)
SG 3 - Initial Level Verification Date
Date
Instrument Indication % DVM Test Point
Location
2-LI-3-93 (2) 2-R-5 - 2LP/539B
2-LI-3-94 (2) 2-R-1 1 - 2LP1538B
2-LI-3-97 (2) 2-R-12 - 2LP/537B
2-FR-3-90 N/A(Pen 3 Blue)
2-LI-3-98A N/A
2-LI-3-98B N/A
2-LR-3-98 N/A(Pen 1 Red)
2-LI-3-148 N/A
2-LI-3-148C N/A
2-LI-3-172 N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 140 of 182
Data Sheet 25(Page 2 of 2)
SG 3 - Initial Level Verification Date
Date
(1) Calculations
2L-P/539B Calculated Level = (Indicated Voltage- 0. 19829) x 100%
0.79315
Calculated Level=( -0.19829)x 100% .3 %0.79315
Calculation Performed By: Verified By:
2LP/538B Calculated Level = (Indicated Voltage- 0. 19829)x 100%
0.79315
Calculated Level=( -0.19829)x 100% .1%)0.79315
Calculation Performed By: Verified By:
2LP/537B Calculated Level = (Indicated Voltage - 0.19829) x 100%
0.79315
Calculated Level: ( -0.19829)x 10.9 %)0.7Cm15
Calculation Performed By: Verifie d By:
WBN Feedwater & Steam Generator Level 22-PTI-003A-02Unit 2 Rev. 0000
Page 141 of 182
Data Sheet 26(Page 1 of 2)
SG 3 - 50% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials
Location Voltage (1)(3)
2-LI-3-93 (2) 2-R-5 - 2LP/539B
2-LI-3-94 (2) 2-R-1 I - 2LP/538B
2-LI-3-97 (2) 2-R-12 - 2LP/537B
2-FR-3-90 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-98A N/A N/A N/A N/A
2-LI-3-98B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 1 Red)
2-LI-3-148 N/A N/A N/A N/A
2-LI-3-148C N/A N/A N/A N/A
2-LI-3-172 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 142 of 182
Data Sheet 26(Page 2 of 2)
SG 3 - 50% Level Verification Data
Date
(1) Calculations
2LP/539B Calculated Level = (Indicated Voltage- 0. 19829)x 100%
0.79315,100%
Calculated Level = ( -0.19829)x 10.79 %)
Calculation Performed By: Verified By:
.2LP/538B 100%Calculated Level (Indicated Voltage- 0. 19829) x 100%
Calculated Level=( -0.19829)x 100% %)0.79315 -
Calculation Performed By: - Verified By:
2LP/537B Calculated Level = (Indicated Voltage- 0. 19829) x 100%
0.79315
Calculated Level= ( -0.19829)x 100% 1 ( %)0.79315
Calculation Performed By: Verified By:
WBN' Feedwater & Steam Generator Level 2,PTI-003A-02Unit 2 Rev. 0000
Page 143 of 182
Data Sheet 27(Page I of 2)
SG 3 - 75% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1)(3)
2-LI-3-93 (2) 2-R-5 - 2LP/539B
2-LI-3-94 (2) 2-R-1 1 - 2LP/538B
2-LI-3-97 (2) 2-R-12 - 2LP/537B
2-FR-3-90 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-98A N/A N/A N/A N/A
2-LI-3-98B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 1 Red)
2-LI-3-148 N/A N/A N/A N/A
2-LI-3-148C N/A N/A N/A N/A
2-LI-3-172 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 144 of 182
Data Sheet 27(Page 2 of 2)
SG 3 - 75% Level Verification Data
Date
(1) Calculations
2LP/539B Calculated Level = (Indicated Voltage - 0. 19829)x 100%
0.79315
Calculated Level = ( -0.19829)x 10.9 %)
Calculation Performed By: Verified By:
2LP/538B Calculated Level = (Indicated Voltage- 0.19829) x 100%
0.79315Calculated Level=( -0.19829)x 100% =( %)
0.79315
Calculation Performed By: Verified By:
2LP/537B Calculated Level = (Indicated Voltage- -. 19829)x 100%
0.79315100%
Calculated Level=( -0.19829)x 100% . %)0.79315
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 145 of 182
Data Sheet 28(Page I of 1)
SG 3 - 100% Tap Verification Data
Date
DVM Test Point Location Indicated Voltage M&TE No. Initials
2-R-52LP/539B
2-R-112LP/538B
2-R-122LP/537B
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 146 of 182
Data Sheet 29(Page I of 2)
SG 3 - 100% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1)(3)
2-LI-3-93 (2) 2-R-5 - 2LP/539B
2-LI-3-94 (2) 2-R-1 I - 2LP/538B
2-LI-3-97 (2) 2-R-12 - 2LP/537B
2-FR-3-90 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-98A N/A N/A N/A N/A
2-LI-3-98B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 1 Red)
2-LI-3-148 N/A N/A N/A N/A
2-LI-3-148C N/A N/A N/A N/A
2-LI-3-172 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 147 of 182
Data Sheet 29(Page 2 of 2)
SG 3 - 100% Level Verification Data
Date
(1) Calculations
2L-P/539B 100%Calculated Level = (Indicated Voltage- 0. 19829) x 0.79315
.100%Calculated Level-- ( -0.19829)x 00%-3 ( %)
Calculation Performed By: Verified By:
2LPI538B 100%Calculated Level = (Indicated Voltage - 0. 19829) x 100%0.79315
Calculated Level =( -0.19829)x 100 %)0.793 15
Calculation Performed By: Verified By:
2LP/537B 100%Calculated Level = (Indicated Voltage- 0. 19829)x 10.30.79315
Calculated Level=( -0.19829)x 100% ( %)0.79315
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 148 of 182
Data Sheet 30(Page 1 of 2)
SG 3 - 75% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1)(3)
2-LI-3-93 (2) 2-R-5 - 2LP/539B
2-LI-3-94 (2) 2-R-1 I - 2LP/538B
2-LI-3-97 (2) 2-R-12 - 2LP/537B
2-FR-3-90 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-98A N/A N/A N/A N/A
2-LI-3-98B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 1 Red)
2-LI-3-148 N/A N/A N/A N/A
2-LI-3-148C N/A N/A N/A N/A
2-LI-3-172 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%.
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 149 of 182
Data Sheet 30(Page 2 of 2)
SG 3 - 75% Level Verification Data
Date
(1) Calculations2LP/539B 100%
• Calculated Level= (Indicated Voltage -0.19829) x 0.3
Calculated Level= ( -0.19829)x 100%7915%)0,79315
Calculation Performed By: Verified By:
2L-P/538B Calculated Level = (Indicated Voltage - 0.19829)x 100%0.79315
Calculated Level=( -0.19829)x 100731 %)0.79315
Calculation Performed By: Verified By:
2LP/537B. (indictedO-0 100%Calculated Level = (Indicated Voltage- 0.19829)x 0.7
Calculated Level = ( - 0.19829)X 100%73 %)0.79315
•[Calculation Performed By: . Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 150 of 182
Data Sheet 31(Page 1 of 2)
SG 3 - 50% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No.. Indicated Calculated Level InitialsLocation Voltage (1)(3)
2-LI-3-93 (2) 2-R-5 - 2LP/539B
2-LI-3-94 (2) 2-R-1 1 - 2LP/538B
2-LI-3-97 (2) 2-R-12 - 2LP/537B
2-FR-3-90 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-98A N/A N/A N/A N/A
2-LI-3-98B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 1 Red)
2-LI-3-148 N/A N/A N/A N/A
2-LI-3-148C N/A N/A N/A N/A
2-LI-3-172 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 151 of 182
Data Sheet 31(Page 2 of 2)
SG 3 - 50% Level Verification Data
Date
(1) Calculations
2L-P/539B Calculated Level = (Indicated Voltage- 0. 19829) x 100%
0.79315
Calculated Level=( -0.19829)x 100%. =( %)'0.79315
Calculationý Performed By: Verified By:
2LP/538B Calculated Level = (Indicated Voltage- 0. 19829) x 100%0.79315
Calculated Level = ( -0.19829)x 100% %)0.79315
Calculation Performed By: Verified By:
2L-P/537B Calculated Level = (Indicated Voltage- 0. 19829) x 100%
0.79315
Calculated Level=( -0.19829)x 100% _( %0.793 15
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 152 of 182
Data Sheet 32(Page I of 2)
SG 3 - 25% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1X3)
2-LI-3-93 (2) 2-R-5 - 2LP/539B
2-LI-3-94 (2) 2-R-1 1 - 2LP/538B
2-LI-3-97 (2) 2-R-12 - 2LP/537B
2-FR-3-90 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-98A N/A N/A N/A N/A
2-LI-3-98B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 1 Red)
2-LI-3-148 N/A N/A N/A N/A
2-LI-3-148C N/A N/A N/A N/A
2-LI-3-172 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 153 of 182
Data Sheet 32(Page 2 of 2)
SG 3 - 25% Level Verification Data
Date
(1) Calculations
2LP/539B Calculated Level = (Indicated Voltage- 0.1 9829) x 100%
0.79315100%
Calculated Level -0.19829)x 007931 ( %)0.79315
Calculation Performed By: Verified By:
2LP/538B Calculated Level = (Indicated Voltage- 0. 19829)x 100%
0.79315
Calculated Level = ( -0.19829)x 100% %)0.79315
Calculation Performed By: Verified By:2LP/537B . acltdLvl=100%
BCalculated Level = (Indicated Voltage- 0. 19829) x
0.79315
Calculated Level =( -0.19829)x 100% %)0.79315
Calculation Performed By: Verified By:Fy
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 154 of 182
Data Sheet 33(Page 1 of 1)
SG 3 - 0% Tap Verification Data
Date
DVM Test Point Location Indicated Voltage M&TE No. Initials
2-R-52LP/539B
2-R-112LP/538B
2-R-122LP/537B
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 155 of 182
Data Sheet 34(Page I of 2)
SG 3 - 0% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1X3)
2-LI-3-93 (2) 2-R-5 - 2LP/539B
2-LI-3-94 (2) 2-R-1 1 - 2LP/538B
2-LI-3-97 (2) 2-R-12 - 2LP/537B
2-FR-3-90 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-98A N/A N/A N/A N/A
2-LI-3-98B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 1 Red)
2-LI-3-148 N/A N/A N/A N/A
2-LI-3-148C N/A N/A N/A N/A
2-LI-3-172 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000
Page 156 of 182
Data Sheet 34(Page 2 of 2)
SG 3 - 0% Level Verification Data
Date
(1) Calculations
2LP/539B 100%Calculated Level = (Indicated Voltage - 0. 19829) x 1V0.79315
100%CalculatedLevel=( -0.19829)x 0.79315 %)
Calculation Performed By: Verified By:
2LP/538B 100%Calculated Level = (Indicated Voltage - 0. 19829) x 100%
Calculated Level = ( -0. 19829)x 100% ( %)0.79315
Calculation Performed By: Verified By:
2LP/537B .100%Calculated Level = (Indicated Voltage- 0. 19829)x 0.3
Calculated Level = ( -0.19829)x 100% =%)0.79315
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 22-PTI-003A-02Unit 2 Rev. 0000
Page 157 of 182
Data Sheet 35(Page 1 of 2)
SG 3 - 25% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials
Location Voltage (1)(3)
2-LI-3-93 (2) 2-R-5 - 2LP/539B
2-LI-3-94 (2) 2-R-1 1 - 2LP/538B
2-LI-3-97 (2) 2-R-12 - 2LP/537B
2-FR-3-90 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-98A N/A N/A N/A N/A
2-LI-3-98B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 1 Red)
2-LI-3-148 N/A N/A N/A N/A
2-LI-3-148C N/A N/A N/A N/A
2-LI-3-172 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 158 of 182
Data Sheet 35(Page 2 of 2)
SG 3 - 25% Level Verification Data
Date
(1) Calculations
2LP/539B Calculated Level = (Indicated Voltage- 0.19829) x 100%
Calculated Level = ( -0.19829)x 100% %)0.79315
Calculation Performed By: Verified By:
2LP/538B Calculated Level = (Indicated Voltage- 0.19829) x 100%
0.79315100%Calculated Level = ( -0.19829)x 07 = ( %)
Calculation Performed By: Verified By:
2LP/537B _100%Calculated Level = (Indicated Voltage - 0. 19829) x
0.79315
Calculated Level = ( -0. 19829)x 0 = ( %)0.793 15
Calculation Performed By: Verified By:
W BN Feedwater & Steam Generator Level 2- TI-003A-02Unit 2 Rev. 0000
Page 159 of 182
Data Sheet 36(Page 1 of 2)
SG 3 - Final Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials(2) Location Voltage (1X3)
2-LI-3-93 (2) 2-R-5 - 2LP/539B
2-LI-3-94 (2) 2-R-1 I - 2LP/538B
2-LI-3-97 (2) 2-R-12 - 2LP/537B
2-FR-3-90 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-98A N/A N/A N/A N/A
2-LI-3-98B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 1 Red)
2-LI-3-148 N/A N/A N/A N/A
2-LI-3-148C N/A N/A N/A N/A
2-LI-3-172 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 160 of 182
Data Sheet 36(Page 2 of 2)
SG 3 - Final Level Verification Data
Date
(1.) Calculations
2LP/539B Calculated Level = (Indicated Voltage - 0. 19829) x 100%
g0.79315
Calculated Level = ( -0.19829)x 100 ( %0.79315
Calculation Performed By: Verified By:
2LP/538B 100%Calculated Level = (Indicated Voltage - 0.19829)x
0.79315100%
Calculated Level=( -0.19829)x 109% ()~0.79315
Calculation Performed By: Verified By:
2LP/537B 100%Calculated Level = (Indicated Voltage - 0. 19829)x: 0.79315
Calculated Level= ( - 0.19829)x' %)Ccanerd)r .By:
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 161 of 182
Data Sheet 37(Page 1 of 2)
SG 4 - Initial Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials
Location Voltage (1 X3)
2-LI-3-106 (2) 2-R-5 - 2LP/549B
2-LI-3-107 (2) 2-R-1 1 - 2LP/548B
2-LI-3-110 (2) 2-R-12 - 2LP/547B
2-FR-3-103 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-111A N/A N/A N/A N/A
2-LI-3-111B N/A NIA N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-171 N/A N/A N/A N/A
2-LI-3-171C N/A NIA N/A N/A
2-LI-3-175 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 162 of 182
Data Sheet 37(Page 2 of 2)
SG 4 - Initial Level Verification Data
Date
(1) Calculations
2LP/549BCalculated Level = (Indicated Voltage- 0.19829) 100%.
0.79315
Calculated Level=( -0.19829)x 100% %)0.79315
Calculation Performed By: Verified By:2LP/548B 100%
Calculated Level = (Indicated Voltage- 0.19829)x 0.3
0.79315.100%Calculated Level =( - 0.19829)x • 0.731 %)
Calculation Performed By: Verified By:
2LP/547B 100%Calculated Level = (Indicated Voltage- 0. 19829) x
0.79315
Calculated Level= ( -0. 19829)x 00%3 ( %)
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 163 of 182
Data Sheet 38(Page I of 2)
SG 4 - 50% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1X3)
2-LI-3-106 (2) 2-R-5 - 2LP/549B
2-LI-3-107 (2) 2-R-1 1 - 2LP/548B
2-LI-3-110 (2) 2-R-12 - 2LP/547B
2-FR-3-103 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-111A N/A N/A N/A N/A
2-LI-3-111B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-171 N/A N/A N/A N/A
2-LI-3-171C N/A N/A N/A N/A
2-LI-3-175 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 164 of 182
Data Sheet 38(Page 2 of 2)
SG 4 - 50% Level Verification Data
Date
K
(1) Calculations
2LP/549B 1000%Calculated Level = (Indicated Voltage - 0. 19829) x 100%Voltge /0.79315
Calculated Level=( -0.19829)x 100% =%)0.79315
Calculation Performed By: Verified By:2LP/548B 100%
Calculated Level = (Indicated Voltage- 0.19829) x 100%g'0.79315
Calculated Level=( -0.19829)x 100% =%)
0.79315
Calculation Performed By: Verified By:
* 2LP/547B Calculated Level = (Indicated Voltage -10.%19829) x 005
0.79315
Calculated Level = P0B.V19829)xr B: %)
Calculation Performed By: Verified By--
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 165 of 182
Data Sheet 39(Page 1 of 2)
SG 4 - 75% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1)(3)
2-LI-3-106 (2) 2-R-5 - 2LP/549B
2-LI-3-107 (2) 2-R-1 I - 2LP/548B
2-LI-3-1 10 (2) 2-R-12 - 2LP/547B
2-FR-3-103 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-111A N/A N/A N/A N/A
2-LI-3-111B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-171 N/A N/A N/A N/A
2-LI-3-171C N/A N/A N/A N/A
•2-LI-3-175 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 166 of 182
Data Sheet 39(Page 2 of 2)
SG 4 - 75% Level Verification Data
Date
(1) Calculations
2LP/549B •.100%Calculated Level = (Indicated Voltage - 0. 19829) x 100%
Calculated Level =( -0.19829)x 100% -0.79315-( %
Calculation Performed By: Verified By:
2LP/548B Calculated Level = (Indicated Voltage -0.19829) x 100%
0.79315
Calculated Level = ( - 0.19829)x- 100% %)
Calculation Performed By: Verified By:
2LP/547B Calculated Level = (Indicated Voltage- 0. 19829) x 100%
0.79315
Calculated Level = ( -0.19829)x 100% % %)
0.79315,
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 167 of 182
Data Sheet 40(Page 1 of 1)
SG 4 - 100% Tap Verification Data
Date
DVM Test Point Location Indicated Voltage M&TE No. Initials
2-R-52LP/549B
2-R-112LP/548B
2-R-122LP/547B
WBN Feedwater & Steam Generator Level 12-PTI-003A-02Unit 2 Rev. 0000
Page 168 of 182
Data Sheet 41(Page 1 of 2)
SG 4 - 100% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials
Location Voltage (1)3)
2-LI-3-106 (2) 2-R-5 - 2LP/549B
2-LI-3-107 (2) 2-R-11 - 2LP/548B
2-LI-3-110 (2) 2-R-12 - 2LP/547B
2-FR-3-103 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-111A N/A N/A N/A N/A
2-LI-3-111B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-171 N/A N/A N/A N/A
2-LI-3-171C N/A N/A NiA N/A
2-LI-3-175 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 169 of 182
Data Sheet 41(Page 2 of 2)
SG 4 - 100% Level Verification Data
Date
(1) Calculations
2LP/549B 100%Calculated Level = (Indicated Voltage- 0.19829)x 0.79315
Calculated Level = ( -0. 19829)x 100% =%)
0.79315
Calculation Performed By: Verified By:
2LP/5 .48B Calculated Level (Indicated Voltage- 0. 19829)x 100%0.79315
Calculated Level=( -0.19829)x 100%0.79315
Calculation Performed By: Verified By:
2LP/547B 100%Calculated Level = (Indicated Voltage - 0. 19829) x 0.79315
Calculated Level = ( -0.19829)x =7 ( %)
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 170 of 182
Data Sheet 42(Page 1 of 2)
SG 4 - 75% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1X3)
2-1-k3-106 (2) 2-R-5 - 2LP/549B
2-LI-3-107 (2) 2-R-1I - 2LP/548B
2-LI-3-1 10 (2) 2-R-12 - 2LP/547B
2-FR-3-103 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-111A N/A N/A N/A N/A
2-LI-3-111B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-171 N/A N/A N/A N/A
2-LI-3-171 C N/A N/A N/A N/A
2-LI-3-175 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 171 of 182
Data Sheet 42(Page 2 of 2)
SG 4 - 75% Level Verification Data
Date
(1) Calculations
2LP/549B Calculated Level = (Indicated Voltage- 0.19829) x 100%
1 0.79315100%
Calculated Level = ( - 0.19829)x 0.793 15 %)
Calculation Performed By: Verified By:
2LP1548B Calculated Level = (Indicated Voltage- 0.19829) x D1.0
100%Calculated Level ( -- 0.19829)x 0.9 %)
Calculation Performed By: Vedfied By:
2LP/547B Calculated Level = (Indicated Voltage- 0.19829) x 073
Calculated Level: ( -0.19829)x 0•%73 %)
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 172 of 182
Data Sheet 43(Page 1 of 2)
SG 4 - 50% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1 X3)
2-LI-3-106 (2) 2-R-5 - 2LP/549B
2-LI-3-107 (2) 2-R-1 1 - 2LP1548B
2-LI-3-1 10 (2) 2-R-12 - 2LP/547B
2-FR-3-103 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-1IIA N/A N/A N/A N/A
2-LI-3-1IIB N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-171 N/A N/A N/A N/A-
2-LI-3-171C N/A N/A N/A N/A
2-LI-3-175 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000
Page 173 of 182
Data Sheet 43(Page 2 of 2)
SG4 - 50% Level Verification Data
Date
(1) Calculations
2LP/549B Calculated Level = (Indicated Voltage- 0.19829)x 100%
0.79315
Calculated Level = ( -0.19829)x 10% %)
Calculation Performed By: Verified By:
2LP/548B 100%Calculated Level = (Indicated Voltage- 019829) 0
0.79315
Calculated Level= ( -0.19829)x 0.7931%)
Calculation Performed By: Verified By:
2LP1547B 100%Calculated Level = (Indicated Voltage -0.19829) x 0.9• 0.79315
100%Calculated Level= ( -. 0.19829)x 0.731 %)
[Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 174 of 182
Data Sheet 44(Page 1 of 2)
SG 4 - 25% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (OX3)
2-LI-3-106 (2) 2-R-5 - 2LP/549B
2-LI-3-107 (2) 2-R-1 I - 2LP/548B
2-LI-3-110 (2) 2-R-12 - 2LP/547B
2-FR-3-103 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-111A N/A N/A N/A N/A
2-LI-3-111B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-171 N/A N/A N/A N/A
2-LI-3-171C N/A NIA N/A N/A
2-LI-3-175 N/A N/A N/A N/A
•(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 22-PTI-003A-02Unit 2 Rev. 0000
Page 175 of 182
Data Sheet 44(Page 2 of 2)
SG 4 - 25% Level Verification Data
Date
(1) Calculations
2LP/549B Calculated Level = (Indicated Voltage- 0. 19829)x 100%0.79315
100%/Calculated Level= ( -0.19829)×x 0.7935 %)
Calculation Performed By: Verified By:
2LP/548B 10Calculated Level = (Indicated Voltage - 0. 19829)x 100%
0.79315
Calculated Level= ( -0.19829)x 100% %0.79315=( %
Calculation Performed By: Verified By:
2LP/547B 100%Calculated Level = (Indicated Voltage - 0.19829)x 0.79315
100%CalculatedLevel=( -0.19829)x 0.79315 %)
0.79315
[Calculation Performed By: Verifie~d 7By:
WBN Feedwater & Steam Generator Level 2-RTe-003A-02Unit 2 Rev.0000
Page 176 of 182
Data Sheet 45(Page 1 of 1)
SG 4 - 0% Tap Verification Data
Date
DVM Test Point Location Indicated Voltage M&TE No. Initials
2-R-52LP/549B
2-R-112LP/548B
2-R-122LP/547B
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 177 of 182
Data Sheet 46(Page I of 2)
SG 4 - 0% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1)(3)
2-LI-3-106 (2) 2-R-5 - 2LP/549B
2-LI-3-107 (2) 2-R-11 - 2LP/548B
2-LI-3-1 10 (2) 2-R-12 - 2LP/547B
2-FR-3-103 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-111A N/A N/A N/A N/A
2-LI-3-111B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-171 N/A N/A N/A N/A
2-LI-3-171C. N/A N/A N/A N/A
I2-LI-3A175 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 178 of 182
Data Sheet 46(Page 2 of 2)
SG 4 - 0% Level Verification Data
Date
(1) Calculations
•2LP/549B 1.00%Calculated Level = (Indicated Voltage - 0. 19829) x
0.79315
Calculated Level = ( -0.19829)x 1 %)0.79315-
Calculation Performed By: Verified By:
2LP/548B 100%Calculated Level (Indicated Voltage - 0. 19829) x
0.79315100%
Calculated Level= ( -0.19829)x 0910
Calculation Performed By: Verified By:
2LP/547B -. " 100%Calculated Level = (Indicated Voltage- 0.19829)x 100%0.79315
100%_CalculatedLevel=( -0.19829)x 0.79315 %)
Calculation Performed By: Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 179 of 182
Data Sheet 47(Page 1 of 2)
SG 4 - 25% Level Verification Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1)(3)
2-LI-3-106 (2) 2-R-5 - 2LP/549B
2-LI-3-107 (2) 2-R-1 1 - 2LP/548B
2-LI-3-1 10 (2) 2-R-12 - 2LP/547B
2-FR-3-103 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-111A N/A N/A N/A N/A
2-LI-3-111B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-171 N/A N/A N/A N/A
2-LI-3-171 C N/A N/A N/A N/A
2-LI-3-175 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 180 of 182
Data Sheet 47(Page 2 of 2)
SG 4 - 25% Level Verification Data
Date
(1) Calculations• 2LPi549B 100%
Calculated Level= (Indicated Voltage-0.19829)x
0.79315100%1
Calculated Level= ( -0.19829)x 0.79315. = %)
Calculation Performed By: Verified By: .
2LP/548B Calculated Level = (IndicatedVoltage- -. 19829) x 100%
' 0.79315
Calculated Level=( -0.19829)x 100%%)0.79315
Calculation Performed By: Verified By:
2LP/547B Calculated Level = (Indicated Voltage- 0.19829) x 100%
Voltge '0.79315
Calculated Level = ( -0. 19829)x 0091 =%)0.79315
rCalculation Performed .By: [Verified By:
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 181 of 182
Data Sheet 48(Page 1 of 2)
SG 4 - Final Level Verification' Data
Date
Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials( 2) Location Voltage (1)(3)
2-LI-3-106 (2) 2-R-5 - 2LP/549B
2-LI-3-107 (2) 2-R-1 1 - 2LP/548B
2-LI-3-1 10 (2)- 2-R-12 - 2LP/547B
2-FR-3-103 N/A N/A N/A N/A(Pen 3 Blue)
2-LI-3-111A N/A N/A N/A N/A
2-LI-3-111B N/A N/A N/A N/A
2-LR-3-98 N/A N/A N/A N/A(Pen 2 Green)
2-LI-3-171 N/A N/A N/A N/A
2-LI-3-171C N/A N/A -N/A N/A
2-LI-3-175 N/A N/A N/A N/A
(2) Maximum and Minimum indicated levels are within 5%
(3) Maximum and Minimum calculated levels are within 1.1%
WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000
Page 182 of 182
Data Sheet 48(Page 2 of 2)
SG 4 - Final Level Verification Data
Date
(1) Calculations
2LP/549B 10Calculated Level= (Indicated Voltage -0.. 19829)x
0.79315
Calculated Level = ( -0. 19829)1x 0% %)0.79315
Calculation Performed By: Verified By:
2LP/548B Calculated Level = (Indicated Voltage -0.19829) x 100%0.79315
Calculated Level= ( -0.19829)x = ( %)0.793/15
Calculation Performed By: Verified By:
2LP/547B Calculated Level = (Indicated Voltage- 0. 19829) x 100%: 0.79315
Calculated Level= ( -0.19829)x 100% %)0.79315
Calculation Performed By: Verified By:
WATTS BAR NUCLEAR PLANT
UNIT 2 PREOPERATIONAL TEST
TITLE: •;•eio•"- C..oo•oi•+ Flow MewA.reintn
Instruction No: Z-P-Th- 8- OZ.
Revision No: 0000
PREPARED BY: ])an e.i b. Ore /Q c - 10m-, DATE: (.-21-11PRINT NAME I SIGNATURE
REVI EWE D BY: kc" 5' 0-Th DATE: (,2 Z01 IPRINT NAME /SIG(A•LiRE- - /•
INSTRUCTION APPROVAL
JTG MEETINPTo: 9,- t2 -- oat!A=
JTG CHAI RMA • ) DATEN••I'1••
APPROVED BY: DATE:PREOPE RAt6AL STARTUP MANAGER
TEST RESULTS APPROVAL
JTG MEETING No:
JTG CHAIRMAN: DATE:
APPROVED BY: DATE:PREOPERATIONAL STARTUP MANAGER
SMP-8.0 R7 Administration of Preoperational Test instructions, Appendix B
WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev. 0000
Page 2 of 33
Revision Log
Revision Affectedor Change Effective Page
Number Date Numbers Description of RevisionlChange
0000 3/f .. ALL Initial Issue based on Unit 1 PTI-068-002 Rev. 0CN 3
Table of Contents
1.0 INTRODUCTION .......................................................................................................... 51.1 T est O bjectives ......................................................................... ..................................... 5
1.2 S co pe ........................................... 5................................................................................ 5
2.0 REFERENCES ..................................................................................................... 62.1 Performance References .......................................................................................... 6
2.2 Developmental References ......................................................................................... 6
3.0 PRECAUTIONS AND LIMITATIONS ........................................................................ 8
4.0 PREREQUISITE ACTIONS ................................................................................... 10
4.1 Preliminary Actions ................................................................................................. 10
4.2 Special Tools, Measuring and Test Equipment, Parts, and Supplies ............ 144.3 Field Preparations................................................................................................. 144.4 Approvals and Notifications ..................................................................................... 15
5.0 ACCEPTANCE CRITERIA .................................................................................... 16
6.0 PERFORMANCE .................................................................................................... 17
6.1 Reactor Coolant System (RCS) Loop No. I Flow Adjustment and (RCS)Low Flow Alarm Verification ................................................................................... 17
6.2 Reactor Coolant System (RCS) Loop No. 2 Flow Adjustment and (RCS)Low Flow Alarm Verification ........................................ 20
6.3 Reactor Coolant System (RCS) Loop No. 3 Flow Adjustment and (RCS)Low Flow Alarm Verification ................................................................................... 23
6.4 Reactor Coolant System (RCS) Loop 4 Flow Adjustment and (RCS)Low Flow Alarm Verification ................................................................................... 26
7.0 POST PERFORMANCE ACTIVITY ........................................................................ 29
8.0 RECORDS .................................................................................................................. 29
Appendix A: TEST PROCEDURESIINSTRUCTIONS REFERENCEREVIEW .......................... ...................... 30
Appendix B: TEMPORARY CONDITION LOG ........................................................... 31
WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev. 0000
Page 4 of 33
Appendix C: PERMANENT PLANT INSTRUMENTATION LOG ................................ 32
WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev. 0000
Page 5 of 33
1.0 INTRODUCTION
1.1 Test Objectives
This test will demonstrate the operability of the Reactor Coolant Flow MeasurementSystem and Reactor Coolant Low flow alarm signals.
1.2 Scope
A. Demonstrate proper operations of the Reactor Coolant System Loop FlowMeasurements.
B. This test is being performed to satisfy a temporary condition during HotFunctional Test (HFT) simulating the core being in place by adjusting ReactorCoolant flow instrumentation to indicate 110% (106-110) flow with all RCPs inservice.
WBN Reactor Coolant Flow Measurement 2-PTI-068-02.Unit 2 Rev. 0000
Page 6 of 33
2.0 REFERENCES
2.1 Performance. References
A. 2-SOI-68.02, System Operating Instruction, Reactor Coolant Pumps
B. SMP-9.0, Conduct of Test
C. 2-PTI-068-01, Hot Functional Test (HFT), Heatup & Cooldown
D. 2-SI-68-25 Recalibration of Channel I Reactor Coolant System Flow Loops
E. 2-SI-68-26 Recalibration of Channel II Reactor Coolant System Flow Loops
F. 2-SI-68-27 Recalibration of Channel III Reactor Coolant System Flow Loops
2.2 Developmental References
A. Unit 2 Final Safety Analysis Report - Amendment 107
1. Table 14.2-1 Sheet 77, 78 and 79 of 89 Integrated Hot Functional Test-Summary
2. Section 5.0 Reactor Coolant System
B. Drawings
1. Flow Drawings
a. 2-47W813-1, Rev 5, Flow Diagram Reactor Coolant System
2. Electrical
a. 2-45B655-E6B, Rev 0, Electrical Annunciator Window Box XA-55-6BEngraving
b. 2-47B601-55-71, Rev 1, Electrical Instrument Tabulation
3. Mechanical
None
4. Logic/Control
WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev. 0000
Page 7 of 33
2.2 Developmental References (continued)
a. 2-47W610-68-1, Rev 1, Electrical Control Diagram, Reactor CoolantSystem
b. 2-47W610-68-2, Rev 1, Electrical Control Diagram, Reactor CoolantSystem
c. 2-47W610-68-3, Rev 2, Electrical Control Diagram, Reactor CoolantSystem
d. 2-47W610-68-4, Rev 1, Electrical Control Diagram, Reactor CoolantSystem
5. Vendor Drawings
a. 108D408 Sh 2, Rev 6, Westinghouse, Process Control Block Diagram
b. 108D408 Sh 3, Rev 4, Westinghouse, Process Control Block Diagram
c. 108D408 Sh 4, Rev 4, Westinghouse, Process Control Block Diagram
d. 108D408 Sh 5, Rev 16, Westinghouse, Process Control BlockDiagram
C. Vendor Manuals
1. WBN-VTD-Wl20-0670, Rev 21, Westinghouse Instruction Book forReactor Coolant Pumps
D. Documents
1. 2-TSD-68-2A, Reactor Coolant System (RCS) Flow Measurements For HotFunctional Testing, Rev 1
3.0 PRECAUTIONS AND LIMITATIONS
A. Standard precautions shall be followed for working around energized electricalequipment in accordance with TVA Safety Procedure 1021.
B. Steps may be repeated if all components cannot be tested in a step. However,if the test has been exited, prerequisite steps must be re-verified and aChronological Test Log (CTL) entry made.
C. Discrepancies between component ID tags and the description in aprocedure/instruction do not require a Test Deficiency Notice, TDN, inaccordance with SMP-14.0, if the UNIDs match, exclusive of place-keepingzeros and train designators (e.g. 2-HS-31-468 vs. 2-HS-031-0468) and thenoun description is sufficient to identify the component. If the component labelneeds to be changed, a Tag Request Form (TR Card) should be processed inaccordance with TI-12.14. Make an entry in the CTL and continue testing.
D. All wires removed/lifted from a terminal shall be identified and taped or coveredwith an insulator to prevent personnel or equipment hazard and possiblespurious initiations. The wires should be grouped together and labeled with thework implementing document number that required them to be lifted if leftunattended.
E. All open problems are to be tracked by a corrective action document andentered on the appropriate system punchlist.
F. Problems identified during the test shall be annotated on the Chronological TestLog (CTL) from SMP-9.0 including a description of the problem, the procedurestep when/where the problem was identified, corrective action steps taken toresolve the problem, and the number of the corrective action document, if onewas required.
G. Observe all Radiation Protection (RP) requirements when working in or nearradiological areas.
H. Ensure there are no adverse effects to the operation of Unit 1 structures,systems, or components.
I. During the performance of this procedure visual observation of piping andcomponents is required. This includes steady state and transient operationswith visual confirmation that vibration is not excessive.
J. If the vibration is determined to be excessive the Test Engineer shall initiate aTest Deficiency Notice (TDN).
WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev. 0000
Page 9 of 33
3.0 PRECAUTIONS AND LIMITATIONS (continued)
K. The following Reactor Coolant Pump (RCP) maximum starting duty limitsshould be observed: (2-SOI-68-02)
1. After any period of running or after an attempted start, restart should not bemade until the motor has been idle for at least 30 minutes.
2. The number of RCP start attempts should be limited to three in anytwo hour period, with RCP idle at least 30 minutes prior to each startattempt. A fourth start should not be made until RCP motor has been idlefor at least I hour.
NOTE
Coordinate with the on duty Hot Functional Test Director prior to commencement ofeach test section.
L. The Sis referenced in this pre-op will be used as a guide by the I&C work planwriter, steps that are not required to accomplish the temporary settings may bedisregarded at the discretion of the work plan writer.
M. This pre-op is being performed to satisfy a temporary condition during HotFunctional Test (HFT) simulating the core being in place by adjusting ReactorCoolant flow instrumentation to indicate 110% (106-110) flow.
WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev. 0000
Page 10 of 33
Date
4.0 PREREQUISITE ACTIONSNOTE
Prerequisite steps may be performed in any order unless otherwise stated and should becompleted as close in time as practicable to the start of the instruction subsection to whichthey apply.
4.1 Preliminary Actions
[1] INFORM Preoperational Startup engineering personnel ofrequirement to monitor vibration data on rotating equipmentand piping during periods of testing.
[2) EVALUATE open items in Watts Bar Integrated TaskEquipment List (WITEL), AND
ENSURE they will NOT adversely affect the test performance
and results.
A. Subsection 6.1
B. Subsection 6.2
C. Subsection 6.3
D. Subsection 6.4
[3] ENSURE changes to the references listed on Appendix A,have been reviewed and determined NOT to adversely affectthe test performance.
[4] VERIFY current revisions and change paper for referenceddrawings has been reviewed and determined NOT toadversely affect the test performance, AND
ATTACH documentation of current drawing revision numbersand change paper that were reviewed to the data package.
[5] VERIFY the test/performance copy of this Preoperational TestInstruction (PTI) is the current revision and as needed, eachtest person assisting in this test has the current revision.
WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev. 0000
Page 11 of 33
Date
4.1 Preliminary Actions (continued)
[6] ENSURE outstanding Design Change Notices (DCN's),Engineering Document Construction Release (EDCR's) orTemporary Alterations (TA's) do NOT adversely impact testing,AND
ATTACH documentation of DCN's, EDCR's and TA's that
were reviewed to the data package.
A. Subsection 6.1
B. Subsection 6.2
C. Subsection 6.3
D. Subsection 6.4
[7] ENSURE required Component Testing has been completedprior to start of test.
A. Subsection 6.1
B. Subsection 6.2
C. Subsection 6.3
D. Subsection 6.4
[8] ENSURE the following Surveillance Procedures have beencompleted prior to the performance of this test:
A. 2-SI-68-12, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 1 CHANNEL I,LOOP 2-LPF-68-6A
B. 2-SI-68-13, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 1 CHANNEL IILOOP 2-LPF-68-6B
C. 2-SI-68-14, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 1 CHANNEL Ill,LOOP 2-LPF-68-6D
D. 2-SI-68-15, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 2 CHANNEL I,LOOP 2-LPF-68-29A
WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev. 0000
Page 12 of 33
Date
4.1 Preliminary Actions (continued)
E. 2-SI-68-16, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 2 CHANNEL II,LOOP 2-LPF-68-29B
F. 2-SI-68-17, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 2 CHANNEL Ill,LOOP 2-LPF-68-29D
G. 2-SI-68-18, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 3 CHANNEL I LOOP2-LPF-68-48A
H. 2-SI-68-19, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 3 CHANNEL II,LOOP 2-LPF-68-48B
I. 2-SI-68-20, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 3 CHANNEL IIILOOP 2-LPF-68-48D
J. 2-SI-68-21, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 4 CHANNEL I LOOP2-LPF-68-71A
K. 2-SI-68-22, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 4 CHANNEL IILOOP 2-LPF-68-71B
L. 2-SI-68-23, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 4 CHANNEL Ill,LOOP 2-LPF-68-71D
[9] ENSURE all piping supports required for Hot FunctionalTesting are installed and adjusted as required.
[10] CONDUCT a pretest briefing with Test and Operationspersonnel in accordance with SMP-9.0
Date
4.1 Preliminary Actions (continued)
NOTE
Final calibration of plant instruments listed in Appendix C will be performed for PowerAscension Testing.
[11] VERIFY plant instruments, listed on Appendix C, PermanentPlant Instrumentation Log, are placed in service and are withintheir calibration interval.
NOTE
Any Annunciator points associated with 2-MUX-55-12 and 2-MUX-55-13 ONLY havemaster switches at the bottom of each terminal strip.
All points associated with 2-TBK-55-25, 2-TBK-55-26, 2-TBK-55-27, and 2-TBK-55-28 willnot have individual switches or a master switch.
[12] VERIFY System 55, Annunciator and Sequential EventsRecording System, FTA switches (in Panel 2-M-21) associatedwith the following annunciator window inputs have beenverified to be in the ON position.
A. 2-XA-55-6B/120-B
B. 2-XA-55-6B/121-B
C. 2-XA-55-6B/122-B
D. 2-XA-55-6B/123-B
[13] ENSURE components contained within the boundaries of thistest are under the jurisdictional control of PreoperationalStartup Engineering (PSE) and/or Plant Operations.
[14] ENSURE a review of outstanding Clearances has beencoordinated with Operations for impact to the testperformance, AND
RECORD in Appendix B, Temporary Condition Log if required.
WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev.0000
Page 14 of 33
Date
4.1 Preliminary Actions (continued)
[15] OBTAIN copies of the applicable forms from the latest revisionof SMP-9.0, AND
ATTACH to this PTI for use during the performance of this PTI.
[161 PERFORM a pretest walkdown on equipment to be tested toensure no conditions exist that will impact-test performance.
A. Subsection 6.1
B. Subsection 6.2
C. Subsection 6.3
D. Subsection 6.4
[17] REVIEW preventive maintenance for system/componentscovered by this test, AND
VERIFY no conditions exist that will impact test performance.
A. Subsection 6.1
B. Subsection 6.2
C. Subsection 6.3
D. Subsection 6.4
4.2 Special Tools, Measuring and Test Equipment, Parts, and
Supplies
None
4.3 Field Preparations
[1] VERIFY that there is an I&C Maintenance work order in placeto calibrate RCS Flow Loops 1 thru 4. The setting will requireall RCS Flow instrument loops to be adjusted to a flow of110% (106-110) with all four Reactor Coolant Pumps running,this adjustment is to simulate the Core being in place AND
RECORD WO#
WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev. 0000
Page 15 of 33
Date
4.4 Approvals and Notifications
[1] OBTAIN permission of the Preoperational Startup Manager tostart the test.
Preoperational Startup ManagerSignature
Date
[2] OBTAIN the Unit 2 Supervisor's (US/SRO) or Shift Manager's(SM) authorization.
U2 US/SRO/SM Signature Date
WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev.0000
Page 16 of 33
5.0 ACCEPTANCE CRITERIA
[1] RCS flow loops instrumentation are indicating 110% (106-110) flow. (Steps6.1[5], 6.2[5], 6.3[5], 6.4[5])
WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev. 0000
Page 17 of 33
Date
6.0 PERFORMANCE
NOTES
1) Plant Maintenance I&C Department will recalibrate the RCS Flow InstrumentationLoops 1 thru 4, to indicate 110% (106-110) flow. Completion of all prerequisiteSection 4.0 will satisfy initial conditions for test Sections 6.1 thru 6.4, which may beperformed in any order.
2) RCP pump starts and stops shall be coordinated with the sequencing events of2-PTI-068-01, Hot Functional Test Procedure for checking Low Flow Alarms forSections 6.1 through 6.4
3) IF, THEN steps in the performance section can be NA'd if conditions are met.
6.1 Reactor Coolant System (RCS) Loop No. I Flow Adjustment and(RCS) Low Flow Alarm Verification.
[1] ENSURE Vibration Test Personnel are in place to monitorvibration of piping and equipment in support of this section.
[2] VERIFY prerequisites listed in Section 4.0 for Subsection 6.1
have been completed.
[31 ENSURE all 4 RCPs are running.
[4] COORDINATE with the on duty Hot Functional Test Director tocommence testing after the 557 OF plateau has been reached,AND
VERIFY RCP 2-MTR-68-8 is running.
WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev. 0000
Page 18 of 33
Date
6.1 Reactor Coolant System (RCS) Loop No. I Flow Adjustment and(RCS) Low Flow Alarm Verification. (continued)
[5] VERIFY the following (RCS) Loop 1 Flow indicators are reading 110% (106 to110) Flow, AND
RECORD:
A. 2-FI-68-6A, RCS LOOP I COOLANT FLOW, located at2-M-5 panel in Main Control Room.
% Flow (ACC CRIT)
B. 2-FI-68-6B, RCS LOOP 1 COOLANT FLOW, located at2-M-5 panel in Main Control Room.
% Flow (ACC CRIT)
C. 2-FI-68-6D, RCS LOOP 1 COOLANT FLOW, located at2-M-5 panel in Main Control Room.
% Flow (ACC CRIT)
[6] IF flow indicators do not read 110% (106-110), THEN
PERFORM WO to recalibrate loop flowinstrumentation AND
Repeat step 6.1[5].
[7] VERIFY Annunciator Window 120B, RCS LOOP 1 FLOW LO,at 2-M-6, 2-XA-55-6B is CLEAR.
[8] STOP Reactor Coolant Pump 2-PMP-68-8 using handswitch2-HS-68-8AA at panel 2-M-5.
[9] VERIFY Annunciator 120B, RCS LOOP 1 FLOW LO,ALARMS.
[10] VERIFY Trip Status Light Box 4, Loop I FLOW LO FS-68-6Aat 2-M-6, 2-XX-55-6A is lit.
WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev. 0000
Page 19 of 33
Date
6.1 Reactor Coolant System (RCS) Loop No. I Flow Adjustment and(RCS) Low Flow Alarm Verification. (continued)
[11] VERIFY Trip Status Light Box 24, Loop I FLOW LO FS-68-6Bat 2-M-6, 2-XX-55-6A is lit.
[12] VERIFY Trip Status Light Box 44, Loop I FLOW LO FS-68-6D
at 2-M-6, 2-XX-55-6A is lit.
[13] RECORD the following (RCS) Loop 1 Flow indications:
A. 2-FI-68-6A, RCS LOOP 1 COOLANT FLOW
% Flow
B. 2-FI-68-6B, RCS LOOP 1 COOLANT FLOW
% Flow
C. 2-FI-68-6D, RCS LOOP 1 COOLANT FLOW
% Flow
CAUTION
After any period of running or after an attempted start, restart should not be made until themotor has been idle for at least 30 minutes.
[14] START Reactor Coolant Pump 2-PMP-68-8 in accordancewith 2-SOI-68.02 Section 5.0 Startup.
[15] VERIFY Annunciator Window 120B, RCS LOOP 1 FLOW LO,is CLEAR.
[16] VERIFY Trip Status Light Box 4, Loop 1 FLOW LO FS-68-6Aat 2-M-6, 2-XX-55-6A is NOT lit.
[17] VERIFY Trip Status Light Box 24, Loop 1 FLOW LO FS-68-6Bat 2-M-6, 2-XX-55-6A is NOT lit.
[18] VERIFY Trip Status Light Box 44, Loop 1 FLOW LO FS-68-6Dat 2-M-6, 2-XX-55-6A is NOT lit.
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6.2 Reactor Coolant System (RCS) Loop No. 2 Flow Adjustment and(RCS) Low Flow Alarm Verification.
[1] ENSURE Vibration Test Personnel are in place to monitorvibration of piping and equipment in support of this section.
[2] VERIFY prerequisites listed in Section 4.0 for Subsection 6.2
have been completed.
[3] ENSURE all 4 RCPs are running.
[4] COORDINATE with the on duty Hot Functional Test Director tocommence testing after the 557 OF plateau has been reached,AND
VERIFY RCP 2-MTR-68-31 is running.
[5] VERIFY the following (RCS) Loop 2 Flow indicators are reading 110% (106 to110) flow, AND
RECORD:
A. 2-FI-68-29A, RCS LOOP 2 COOLANT FLOW, located at2-M-5 panel in Main Control Room
% Flow (ACC CRIT)
B. 2-FI-68-29B, RCS LOOP 2 COOLANT FLOW, located at2-M-5 panel in Main Control Room
% Flow (ACC CRIT)
C. 2-FI-68-29D, RCS LOOP 2 COOLANT FLOW, located at2-M-5 panel in Main Control Room
% Flow (ACC CRIT)
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6.2 Reactor Coolant System (RCS) Loop No. 2 Flow Adjustment and(RCS) Low Flow Alarm Verification. (continued)
[6] IF flow indicators do not read 110% (106-110), THEN
PERFORM WO to recalibrate loop flowinstrumentation AND
Repeat step 6.2[5].
[7] VERIFY Annunciator Window 121 B, RCS LOOP 2 FLOW LO,at 2-M-6, 2-XA-55-6B is CLEAR.
[8] STOP Reactor Coolant Pump 2-PMP-68-31 using handswitch2-HS-68-31AA at panel 2-M-5.
[9] VERIFY Annunciator Window 121B, RCS LOOP 2 FLOW LO,ALARMS.
[10] VERIFY Trip Status Light Box 5, Loop 2 FLOW LO FS-68-29Aat 2-M-6, 2-XX-55-6A is lit.
[11] VERIFY Trip Status Light Box 25, Loop 2 FLOW LOFS-68-29B at 2-M-6, 2-XX-55-6A is lit.
[12] VERIFY Trip Status Light Box 45, Loop 2 FLOW LOFS-68-29D at 2-M-6, 2-XX-55-6A is lit.
[13] RECORD the following (RCS) Loop 2 Flow indications.
A. 2-FI-68-29A, RCS LOOP 2 COOLANT FLOW
% Flow
B. 2-FI-68-29B, RCS LOOP 2 COOLANT FLOW
% Flow
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6.2 Reactor Coolant System (RCS) Loop No. 2 Flow Adjustment and(RCS) Low Flow Alarm Verification. (continued)
C. 2-FI-68-29D, RCS LOOP 2 COOLANT FLOW
% Flow
CAUTION
After any period of running or after an attempted start, restart should not be made until themotor has been idle for at least 30 minutes.
[14] START Reactor Coolant Pump 2-PMP-68-31 in accordancewith 2-SOI-68.02, Section 5.0 Startup.
[15] VERIFY Annunciator Window 121B, RCS LOOP 2 FLOW LO,is CLEAR.
[16] VERIFY Trip Status Light Box 5, Loop 2 FLOW LO FS-68-29Aat 2-M-6, 2-XX-55-6A is NOT lit.
[17] VERIFY Trip Status Light Box 25, Loop 2 FLOW LOFS-68-29B at 2-M-6, 2-XX-55-6A is NOT lit.
[181 VERIFY Trip Status Light Box 45, Loop 2 FLOW LOFS-68-29D at 2-M-6, 2-XX-55-6A is NOT lit.
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6.3 Reactor Coolant System (RCS) Loop No. 3 Flow Adjustment and(RCS) Low Flow Alarm Verification.
[1] ENSURE Vibration Test Personnel are in place to monitorvibration of piping and equipment in support of this section.
[2] VERIFY prerequisites listed in Section 4.0 for Subsection 6.3
have been completed.
[3] ENSURE all 4 RCPs are running.
[4] COORDINATE with the on duty Hot Functional Test Director tocommence testing after the 557 OF Plateau has been reached,AND
VERIFY RCP 2-MTR-68-50 is running.
[5] VERIFY the following (RCS) Loop 3 Flow indicators are reading 110% (106 to110) Flow, AND
RECORD:
A. 2-FI-68-48A, RCS LOOP 3 COOLANT FLOW, located at2-M-5 panel in Main Control Room
% Flow (ACC CRIT)
B. 2-FI-68-48B, RCS LOOP 3 COOLANT FLOW, located at2-M-5 panel in Main Control Room
% Flow (ACC CRIT)
C. 2-FI-68-48D, RCS LOOP 3 COOLANT FLOW, located at2-M-5 panel in Main Control Room
% Flow (ACC CRIT)
Date
6.3 Reactor Coolant System (RCS) Loop No. 3 Flow Adjustment and(RCS) Low Flow Alarm Verification. (continued)
[6] IF flow indicators do not read 110% (106-110), THEN
PERFORM WO to recalibrate loop flowinstrumentation AND
Repeat step 6.3[5].
[71 VERIFY Annunciator Window 122B, RCS LOOP 3 FLOW LO,at 2-M-6, 2-XA-55-6B is CLEAR.
[8] STOP Reactor Coolant Pump, 2-PMP-68-50 using handswitch2-HS-68-50AA at panel 2-M-5.
[9] VERIFY Annunciator Window 122B, RCS LOOP 3 FLOW LO,ALARMS.
[10] VERIFY Trip Status Light Box 6, Loop 3 FLOW LO FS-68-48Aat 2-M-6, 2-XX-55-6A is lit.
[11] VERIFY Trip Status Light Box 26, Loop 3 FLOW LOFS-68-48B at 2-M-6, 2-XX-55-6A is lit.
[12] VERIFY Trip Status Light Box 46, Loop 3 FLOW LO
FS-68-48D at 2-M-6, 2-XX-55-6A is lit.
[13] RECORD the following (RCS) Loop 3 Flow indications.
A. 2-FI-68-48A, RCS LOOP 3 COOLANT FLOW
% Flow
B. 2-FI-68-48B, RCS LOOP 3 COOLANT FLOW
% Flow
C. 2-FI-68-48D, RCS LOOP 3 COOLANT FLOW
% Flow
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6.3 Reactor Coolant System (RCS) Loop No. 3 Flow Adjustment and(RCS) Low Flow Alarm Verification. (continued)
CAUTION
After any period of running or after an attempted start, restart should not be made until themotor has been idle for at least 30 minutes.
[14] START Reactor Coolant Pump 2-PMP-68-50 in accordancewith 2-SOI-68.02, Section 5.0 Startup.
[15] VERIFY Annunciator Window 122B, RCS LOOP 3 Flow LO, isCLEAR.
[16] VERIFY Trip Status Light Box 6, Loop 3 FLOW LO FS-68-48Aat 2-M-6, 2-XX-55-6A is NOT lit.
[17] VERIFY Trip Status Light Box 26, Loop 3 FLOW LOFS-68-48B at 2-M-6, 2-XX-55-6A is NOT lit.
[18] VERIFY Trip Status Light Box 46, Loop 3 FLOW LOFS-68-48D at 2-M-6, 2-XX-55-6A is NOT lit.
Date
6.4 Reactor Coolant System (RCS) Loop 4 Flow Adjustment and(RCS) Low Flow Alarm Verification.
[1] ENSURE Vibration Test Personnel are in place to monitorvibration of piping and equipment in support of this section.
[2] VERIFY prerequisites listed in Section 4.0 for Subsection 6.4
have completed.
[3] ENSURE all 4 RCPs are running.
[4] COORDINATE with the on duty Hot Functional Test Director tocommence testing after the 557 OF plateau has been reached,AND
VERIFY RCP 2-MTR-68-73 is running.
[5] VERIFY the following (RCS) Loop 4 Flow indicators are reading 110% (106 to110) Flow, AND
RECORD:
A. 2-FI-68-71A, RCS LOOP 4 COOLANT FLOW, located at2-M-5 panel in Main Control Room
% Flow (ACC CRIT)
B. 2-FI-68-71B, RCS LOOP 4 COOLANT FLOW, located at2-M-5 panel in Main Control Room
% Flow (ACC CRIT)
C. 2-FI-68-71D, RCS LOOP 4 COOLANT FLOW, located at
2-M-5 panel in Main Control Room
% Flow (ACC CRIT)
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6.4 Reactor Coolant System (RCS) Loop 4 Flow Adjustment and(RCS) Low Flow Alarm Verification. (continued)
[6] IF flow indicators do not read 110% (106-110), THEN
PERFORM WO to recalibrate loop flowinstrumentation AND
Repeat step 6.4[5].
[7] VERIFY Annunciator Window 123B, RCS LOOP 4 FLOW LO,at 2-M-6, 2-XA-55-6B, is CLEAR.
[8] STOP Reactor Coolant Pump 2-PMP-68-73 using handswitch2-HS-68-73AA at panel 2-M-5.
[9] VERIFY Annunciator Window 123B, RCS LOOP 4 FLOW LO,ALARMS.
[10] VERIFY Trip Status Light Box 7, Loop 4 FLOW LO FS-68-71Aat 2-M-6, 2-XX-55-6A is lit.
[11] VERIFY Trip Status Light Box 27, Loop 4 FLOW LOFS-68-71 B at 2-M-6, 2-XX-55-6A is lit.
[12] VERIFY Trip Status Light Box 47, Loop 4 FLOW LOFS-68-71 D at 2-M-6, 2-XX-55-6A is lit. _
[13] RECORD the following (RCS) Loop 4 Flow indications.
A. 2-FI-68-71A, RCS LOOP 4 COOLANT FLOW
% Flow
B. 2-FI-68-71B, RCS LOOP 4 COOLANT FLOW
% Flow
C. 2-FI-68-71 D, RCS LOOP 4 COOLANT FLOW
% Flow
Date
6.4 Reactor Coolant System (RCS) Loop 4 Flow Adjustment and(RCS) Low Flow Alarm Verification. (continued)
CAUTION
After any period of running or after an attempted start, restart should not be made until themotor has been idle for at least 30 minutes.
[141 START Reactor Coolant Pump 2-PMP-68-73 in accordancewith 2-SOI-68.02 Section 5.0 Startup.
[15] VERIFY Annunciator Window 123B, RCS LOOP 4 FLOW LO,is CLEAR.
116] VERIFY Trip Status Light Box 7, Loop 4 FLOW LO FS-68-71Aat 2-M-6, 2-XX-55-6A is NOT lit.
[17] VERIFY Trip Status Light Box 27, Loop 4 FLOW LOFS-68-71 B at 2-M-6, 2-XX-55-6A is NOT lit.
[18] VERIFY Trip Status Light Box 47, Loop 4 FLOW LOFS-68-71 D at 2-M-6, 2-XX-55-6A is NOT lit.
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7.0 POST PERFORMANCE ACTIVITY
[1] NOTIFY the Unit 2 US/SRO of the test completion and systemalignment.
(2] VERIFY that Post-test calibration of permanent plantinstruments used to record quantitative acceptance criteria hasbeen satisfactorily performed, AND
RECORD the results on Appendix C, Permanent PlantInstrumentation Log.
[3] NOTIFY the I&C Maintenance Department that RCS Loops 1thru 4 flow transmitters may be left as-is in preparation forperformance of 2-SI-68-25, 2-SI-68-26, and 2-SI-68-27,which will establish baseline adjustments for Fuel Load.
[4] NOTIFY the on duty Hot Functional Test Director of the testcompletion.
8.0 RECORDS
A. QA Records
Completed Test Package (PTI)
B. Non-QA Records
None
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Appendix A(Page I of 1)
TEST PROCEDURESIINSTRUCTIONS REFERENCE REVIEW
NOTES
1) Additional copies of this table may be made as necessary.
2) Initial and date indicates review has been completed for impact.
PROCEDURE/ REVISION/CHANGES IMPACT INITIAL ANDINSTRUCTION YDATE. (NIA for no
CYes/No change)
Unit 2 FSAR -Amendment 107Section 5.0Chapter 14 Table 14.2-1Sheets 77-70 of 89
2-PTI-068-01 HFT Heatup& Cooldown
2-SI-68-25 Recalibrationof Channel I ReactorCoolant System, FlowLoops
2-S1-68-26 Recalibrationof Channel II ReactorCoolant System, FlowLoops
2-SI-68-27 Recalibrationof Channel III ReactorCoolant System, FlowLoops
2-TSD-68-2A, ReactorCoolant System (RCS)Flow Measurements ForHot Functional Testing
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Appendix B(Page 1 of 1)
TEMPORARY CONDITION LOG
Date
NOTE
These steps will be N/A'd if no temporary condition existed. Additional copies of this tablemay be made as necessary.
ITEM TEMPORARY CONDITION PERFORMED RETURNED TO NORMALNo. DESCRIPTION
Step Performed. By/Date Step Returned By/DateNo. CV By/Date No. CV By/Date
/ /
/ /
/ /
/ /
I /
/ /
/ I
/ /
/ /
/ /
/ /
/ /
/ /
I /
/ /
I /
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Appendix C(Page 1 of 2)
PERMANENT PLANT INSTRUMENTATION LOG
Date
INSTRUMENT PRELIM FILLED PLACED IN USED FOR POST-TEST POST-TESTOR CAL DUE AND SERVICE (1) QUANTITATIVE CAL DATE (2) CALIBRATIONINSTRUMENT DATE VENTED () ACC CRIT . ACCEPTABLE (2)
LOOP #INTDTINIT/DATE INIT/DATE YES NO INIT/DATE
2-FI-68-6A I I /
2-FI-68-6B I / /
2-FI-68-6D / / /
2-FI-68-29A / / I
2-FI-68-29B I / I
2-FI-68-29D / / /
2-FI-68-48A / / /
2-FI-68-48B /
2-FI-68-48D I I I
2-FI-68-71A I I
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Appendix C(Page 2 of 2)
PERMANENT PLANT INSTRUMENTATION LOG
Date
INSTRUMENT PRELIM FILLED PLACED IN USED FOR POST-TEST POST-TESTOR CAL DUE AND SERVICE (1) QUANTITATIVE CAL DATE (2) CALIBRATIONINSTRUMENT DATE VENTED (1) ACC CRIT ACCEPTABLE (2)
LOOP # INIT/DATEINIT/DATE INIT/DATE YES NO
2-FI-68-71B / / B
2-FI-68-71D / / D
/ / I
/ //
/ / I
These items may be initialed and dated by personnel performing the task. Instrumentation not required to be filledand vented may be identified as Not Applicable (NIA)
(2) May be identified as Not Applicable (N/A) if instrument was not used to verify/record quantitive acceptance
criteria data.