LaSalle County Station, Unit 2, Post-Outage 90-Day ...County Station Unit 2. It started February 7, 2005 and ended March 16, 2005. This refuel outage was the first scheduled for the

ExekeinSMExelon Generation Company, LLCLaSalle County Station2601 North 21"RoadMarseilles, IL 61341-9757

www.exelonCorp.Com1 Nuclear

RA05-48

June 10, 2005 10 CFR 50.55a(g)

United States Nuclear Regulatory CommissionAttention: Document Control DeskWashington, D.C. 20555

LaSalle County Station, Unit 2Facility Operating License No. NPF-18NRC Docket No. 50-374

Subject:

Reference:

Post-Outage 90-Day Inservice Inspection (ISI) SummaryReport

Milton H. Richter (ComEd) letter to Dr. Thomas E. Murley(NRC), "Structural Margin Evaluation for Reactor PressureVessel Head Studs," dated October 3, 1991

Enclosed is the Exelon Generation Company, LLC (EGC) LaSalle County StationUnit 2 Post-Outage 90-Day (ISI) Summary Report, submitted in accordance with10 CFR 50.55a, "Codes and Standards," and the American Society of MechanicalEngineers (ASME) Boiler and Pressure Vessel Code Section Xl, Article IWA-6200,Paragraph IWA-6230.

The enclosed Post-Outage 90-Day ISI Summary Report is for examinations,repair/replacement activities, and Containment Inservice Inspection (CISI)performed between the end of LaSalle County Station Unit 2 ninth refueling outageon February 21, 2003, through the end of the current, tenth refueling outage. Thisrefueling outage started February 7, 2005, and ended March 16, 2005. Thisrefueling outage was the first scheduled for the Third Inspection Period of theSecond Inspection Interval, effective from July 5, 2004, through July 4, 2007, forLaSalle County Station Unit 2.

Pressure boundary leakage was detected during examination of the reactor coolantpressure boundary. The leakage was reactor coolant from the weld joint betweenthe body of valve 2B21-F028D and drain line 2MS20AD-2". Issue Report # 311917was generated to document the leak. Work Order # 789955 was generated and aASME Section Xl Repair Plan was used to remove the entire defective weld and re-weld the connection. The repaired connection was subjected to System LeakageTest pressure and no leakage was detected. The components' materials of.construction being joined by the repair weld necessitated Post Weld Heat Treatment(PWHT) of the completed weld. To monitor PWHT, five temporary thermocoupleswere tack welded to the valve body and one thermocouple was tack welded to thedrain line pipe. The PWHT of the completed repair weld was successful and thetemporary attachments and their tack welds were removed from the components.

D447

June 10, 2005U.S. Nuclear Regulatory CommissionPage 2

The weld removal areas on the valve body and the drain pipe were not examined bythe Magnetic Particle (MT) or Liquid Penetrant (PT) methods as required by SubSubparagraph NB-4231.2 (g) of the ASME Boiler and Pressure Vessel CodeSection III, 1974 Edition. This ASME Code non-compliance was discoveredfollowing start-up from the refueling outage. Issue Report # 314183 was generatedto document the ASME Code non-compliance. Operability Evaluation # 05-002 wascompleted and determined that the valve and drain line would remain operable untilthe weld removal areas could be examined using MT or PT methods. ActionTracking Item # 314183-03 was created to track the completion of the requiredexaminations.

LaSalle County Station Unit 2 is owned and operated by EGC, whose address is:

200 Exelon WayKennett Square, PA 19348

LaSalle County Station Unit 2 has an authorized power level of 3489 MWt andbegan Commercial Operation on October 17, 1984.

We certify that, to the best of our knowledge and belief, the statements made in thisreport are correct, and the examinations and corrective measures, as applicable,conform to the rules of the ASME Boiler and Pressure Vessel Code, Section Xl.

Should you have any questions concerning this letter, please contactMr. Terrence Simpkin, Regulatory Assurance Manager, at (815) 415-2800.

Respectfully,

Susan R. LandhalSite Vice PresidentLaSalle County Station

Attachment

cc: NRC Senior Resident Inspector - LaSalle County Station

AttachmentPost-Outage 90-Day ISI Summary Report

INTRODUCTION

The Inservice Inspection (ISI) Summary Report addresses examinations,repair/replacement activities, and Containment Inservice Inspections (CISI) performedbetween the end of the previous refuel outage, (L2R09) February 21, 2003, through theend of the current refuel outage (L2R1 0). This refuel outage was the tenth for LaSalleCounty Station Unit 2. It started February 7, 2005 and ended March 16, 2005. Thisrefuel outage was the first scheduled for the Third Inspection Period of the SecondInspection Interval, effective from October 17,1994, through July 4, 2007, for LaSalleCounty Station Unit 2. Paragraph IWA-2430 (e) of the American Society of MechanicalEngineers (ASME) Code Section Xi allows an Inspection Interval to be extended for aperiod of time equivalent to the duration of a continuous outage that exceeds six months.The Second Inservice Inspection Interval is divided into three successive inspectionperiods as determined by calendar years of plant service within the inspection interval.Identified below are the period dates for the Second Inservice Inspection Interval asdefined by Inspection Program B. In accordance with IWB-2412 (b), the InspectionPeriods specified below may be decreased or extended by as much as one year toenable inspections to coincide with.LaSalle County Station's refuel outages.

Unit 2, Period 1 (October 17, 1994 through July 4, 2000**)Unit 2, Period 2 (July 5, 2000 through July 4, 2004)Unit 2, Period 3 (July 5, 2004 through July 4, 2007)** This date reflects a 932-day extension allowed by IWA-2430 (e) for L2R07.

Augmented Inservice Inspection (AISI) examinations, ISI and CISI, and PreserviceInspections (PSI) were completed prior to and during the refuel outage as required bythe Code of Federal Regulations, Technical Requirements Manual, ASME Boiler andPressure Vessel Code, Section Xi, 1989/1998 Edition, and the applicable requirementsof the Performance Demonstration Initiative (PDI).

Personnel from General Electric Nuclear Energy (GENE) Inspection Services andExelon Nondestructive Examination Services group (NDES) performed the Non-Destructive Examinations (NDE), Magnetic Particle (MT), Liquid Dye Penetrant (PT),and manual and/or automated Ultrasonic (UT) techniques that were used during theseinspections. All Intergranular Stress Corrosion Cracking (IGSCC) examinations werecompleted by personnel qualified for the detection and discrimination of IGSCC Crackingin accordance with the PDI. NDES provided necessary resolution of technical problems,reviewed all ISI personnel qualifications, and all visual, surface, and volumetricexamination results.

1

Visual examinations of reactor vessel internals, component supports, and pipingpressure tests were performed by GENE personnel, Exelon Generation Company, LLC(EGC) employees of the LaSalle County Station Programs Engineering Group andNDES personnel. These individuals were appropriately certified as ASME Code SectionXl Visual Examiners to EGC's written practice. An underwater camera was used for thevisual inspection of the reactor vessel internals. The camera was proven capable ofresolving 0.001" and 0.0005" stainless steel wires while underwater and, in the samelighting conditions found during the actual inspection.

The services of an Authorized Nuclear Inservice Concrete Inspector (ANIC) wereprovided by Hartford Steam Boiler Inspection & Insurance Co. of Connecticut, 2443Warrenville Road, Suite 500, Lisle, IL 60532.

Mr. Rocky W. White, ANIC, State of Illinois #1927, reviewed written NondestructiveExamination procedures, personnel qualifications, instrument and material certifications,ASME Code Section Xl examination results, Owner's Reports of Repair or Replacement(Form NIS-2), and the Owner's Data Report for Inservice Inspection (Form NIS-1).

II. SCOPE OF INSPECTIONS

The ISI Summary Report is provided with tables that consolidate the extent and resultsof inspections performed between the end of the previous refuel outage (L2R09),February 21, 2003, through the end of the current refuel outage (L2R1 0). Anexplanation of all abbreviations used is in Attachment 3 of the Summary Report.

Table A provides a listing of all completed ASME Code Section XI examinations for thisrefuel outage with the exception of component support examinations and pressuretesting which are addressed separately. Table A is divided by ASME Code Categorywith a description of the items examined, including the examination types, and theexamination results.

Table B provides a listing of all AISI. These are not ASME Code Section Xlrequirements, but are additional examination area requirements, increased frequencyrequirements, or combinations of these, which are requested by the Nuclear RegulatoryCommission (NRC). Others have been deemed prudent in view of EGC and industryexperience. Table B also gives a description of the items examined as well as theexamination types, and examination results. Table B includes the following categories:

BWRVIP-75 - These examinations are of austenitic stainless steel piping for thedetection of IGSCC.

REACTOR VESSEL INTERNALS AISI - These examinations include inspection ofreactor internal components required by the NRC such as core spray spargers andpiping. These have been adopted by EGC through its commitment to the Boiling WaterReactor Vessel and Intemals Project (BWRVIP). Other examinations, such as thesteam dryer and steam separator, were deemed prudent from industry experience.

MISCELLANEOUS AISI -

Pursuant to LaSalle County Station's commitment to the NRC (reference letter), the AISIexaminations included an augmented "End-Shot" UT examination of 100% (76 total) ofthe reactor pressure vessel closure studs. The "End Shot" UT examination wascompleted using procedures, calibration standards, and personnel which met allapplicable requirements of the 1989 Edition of ASME Code Section Xl, and the PDI.

2

Table C provides a listing of all completed ASME Code Section Xl Class I and 2component support examinations for this outage. Table C gives the support #(s),examination type, and examination results. Table C is divided by ASME Code Class.

Table D provides a listing of pressure testing of ASME Code Section Xl Class I & 2piping and components completed during the period between the L2R09 and L2R10refuel outages. As applicable, Code Case N-498-4, "Alternative Rules for 10-YearHydrostatic Testing for Class 1, 2, and 3 Systems Section Xl, Division 1," is utilizedduring the Third Inspection Period. ASME Code Class 1 components and piping wereexamined using the VT-2 method during the system leakage test conducted at 1035 psigprior to reactor start-up, within the nominal operating pressure range of the reactorpressure vessel associated with 100% rated reactor power. Pressure testing will beongoing throughout the remainder of the Third Inspection Period.

Table E is a listing of ASME Code Section Xl Class 1 and 2 repair/replacementscompleted since the previous refuel outage and those completed during the tenth refueloutage of Unit 2, in accordance with ASME Code Section Xl, Articles IWA-4000 andIWA-7000. This includes the Work Order # which served to implement the applicableactivity and a short description. The documentation packages are on file at LaSalleCounty Station. Each activity has been certified on the Owner's Report of Repair orReplacement, which will serve as documentation of these repair/replacements.

The name of each major component or appurtenance inspected during the tenth refueloutage is listed on Form NIS-1 (Attachment 1) in column #1. This includes the reactorpressure vessel and the Class 1 piping system. A detailed list of components orappurtenances inspected appears in the abstracts listed as items 13, 14, and 15 onForm NIS-1. The descriptions including size, capacity, material, location, and drawingsto aid in identification of the components or appurtenances have been previouslysubmitted, including the N-5 ASME Code Data Reports and the Second 10-Year ISIPlan. This information was not included in the ISI Summary Report. These documentsare on file at LaSalle County Station. This also applies to the PSI and ISI SummaryReports.

Ill. SUMMARY OF RESULTS AND CORRECTIVE ACTIONS

The ASME Code Section Xl ISI results obtained during this refuel outage werecompared with the Preservice and Inservice results. The following is a summary of theresults and corrective actions taken.'

1. ASME Code Section Xl Components

Recordable indications were detected in ASME Code Section Xl components and othernon-code components, during augmented examinations as discussed below or in theapplicable Tables. All indications detected in ASME Code Section Xl components wereevaluated against the applicable acceptance standards.

Examinations and tests of the Unit 2 ASME Code Section Xl Class CC post tensioningsystem were performed. The following conditions have been identified and are beingreported as required by 10 CFR 50.55(a):

3

During the examination of tendons, free water was identified in either the greasecan or anchorage of the following tendons:

Shop End H39GF 1.5 Ounce Field End H72F 1 Ounce

The difference between the amount of sheeting filler grease removed and theamount replaced exceeded 10% of the tendon net duct volume in the followingtendons:

V201A 20.29% V201A 14.88%V204A 10.82% V205A 15.45%V214A 10.77% V216A 14.04%V218A 21.06% V221A 13.09%V225A 11.50% V228A 12.20%V229A 13.93% V247C 38.67%

Examination of tendons identified degradation in the form of broken wires foundon the following:

V219A 1 of 90 wires brokenV228A 3 of 90 wires broken. This tendon was replaced.V229A 9 of 90 wires broken. This tendon was replaced.V247C 2 of 90 wires broken

Five "A" tendons and all thirty "B" tendons are inaccessible for examinationduring power operations. Degradation of the tendons is due to water-inducedcorrosion by failure of the water intrusion barriers and, aided by a loss of thecorrosion protection medium (grease) in the top region of the accessible "A"tendons. The design of the inaccessible tendons incorporates a welded coverthat prevents this type of degradation. To confirm this conclusion, a correctiveaction has been generated to inspect one inaccessible "A" and "B" tendon at thenext scheduled refueling outage. Action Tracking Item #157920, Assignment 33,tracks this inspection.

2. RH40-2877X Welded Attachments

During Magnetic Particle testing of the welded attachment lugs associated withcomponent support RH40-2877X, two linear indications were detected. The linearindications were located in the pipe base metal near the lug weldment. The indicationswere compared to the acceptance standards of ASME Section Xl, WB-3514-4 and didnot meet the acceptance standards. Issue Report #300094 was generated to dispositionthe indications. ASME Section Xl, IWC-3512.1(c), allows flaws exceeding the standardsof IWB-3514-4 to be examined by the volumetric method and compared to applicablestandards for the volumetric method (i.e., Table IWB-3514-1). Alternatively, controlledmechanical removal may be used to establish each indication's depth. This is supportedby ASME Code Interpretation XI-1-95-42, which allows a controlled mechanical removaltechnique (e.g., grinding) to be used to establish if the surface indication would havebeen acceptable to the volumetric acceptance standards of IWB-3500 or IWC-3500.Work Order #781039 was generated and a Section Xl Repair Plan was used toimplement controlled mechanical flaw removal using localized grinding. Ultrasonicthickness measurements were performed prior to grinding and after the indications werecompletely removed. The deepest measurement along each indication was recordedafter each of the indications was completely removed. The amount of metal removedrepresenting the initial depth of each indication was used to compare to the acceptance

4

standards of IWB-3514-1. Both indications were acceptable to the volumetric standardsand no sample expansion was performed.

3. Pressure Boundary Leakage of Pipe Line 2MS20AD-2-

Pressure boundary leakage was detected during examination of the Reactor CoolantPressure Boundary completed with the System Leakage Test. The leakage was reactorcoolant from the weld joint between the body of valve 2B21 -F028D and drain line2MS20AD-2". Issue Report # 311917 was generated to document the leak. Work Order# 789955 was generated and a ASME Section Xl Repair Plan was used to remove theentire defective weld and re-weld the connection. The repaired connection wassubjected to System Leakage Test pressure and no leakage was detected. Thematerials of construction of the components being joined by the repair weld necessitatedPWHT of the completed weld. To monitor PWHT, five temporary thermocouples weretack welded to the valve body and one thermocouple was tack welded to the drain linepipe. The PWHT of the completed repair weld was successful and the temporaryattachments and their tack welds were removed from the components. The weldremoval areas on the valve body and the drain pipe were not examined by the MT or PTmethods as required by Sub Subparagraph NB-4231.2 (g) of the ASME Boiler andPressure Vessel Code Section 111, 1974 Edition. This ASME Code non-compliance wasdiscovered after start-up from the refueling outage. Issue Report # 314183 wasgenerated to document the ASME Code non-compliance. Operability Evaluation # 05-002 was completed and determined that the valve and drain line remain operable untilthe weld removal areas can be examined using MT or PT methods. Action TrackingItem # 314183-03 was created to track the completion of the required examinations.

4. Steam Dryer

An augmented visual examination of the steam dryer is completed during each refueloutage. The steam dryer contains numerous indications that were recorded duringprevious examinations. Areas where historically indications were identified include the

- lifting eye bracket welds, upper dryer bank vertical welds, uppers support ring, drainchannel welds, and dryer bank panels. Specific inspections as recommended by SIL644 Revision 1 were performed and new indications were identified on tie bars 5 and 28,and on the upper strap associated with the lifting lug at 2150. The indications on the tiebars were evaluated as acceptable as-is with no repair required in accordance with EC#354310. The broken upper strap on the 2150 lifting lug was removed under EC#353949. Issue Reports #308912 and #309163 (tie bar indications) and #301422(broken upper strap) were generated to document these conditions. These examinationresults have been documented on the GENE examination data sheets.

5. Steam Separator

An augmented visual examination of the steam separator is completed during eachrefuel outage. No new indications were observed. The welds and separators around asteam separator tie bar removed in L2R09 were examined as recommended in theremoval design change, and no indications were observed. These examination resultshave been documented on the GENE examination data sheets.

6. Shroud Head Bolts

All shroud head bolts were examined, and pin wear was identified on three bolts andwindow wear was observed on one of these same bolts. Issue Report #309413 wasgenerated to document these indications. The indications were accepted as-is underdesign analysis EC 354310.

5

7. Jet Pumps

One hundred percent (20 total) of the jet pump inlet mixers were replaced with new inletmixers that had labyrinth seals machined in the slip joint area, with oversized non-stellitemain wedges. The changes in the inlet mixer were performed in accordance with EC348413. The existing 10 Auxiliary Wedges previously installed to eliminate gapsbetween the jet pumps and the inlet mixers were removed. Visual examinationsperformed after inlet mixer replacement revealed that no Auxiliary Wedges wererequired. During the inlet mixer replacements, 17 of the 20 hold down beams wereproactively replaced.

Examinations of areas made accessible below the core plate were performed when theinlet mixers were removed. Examinations included accessible portions of bottom headcladding in the vicinity of the jet pumps, surfaces/welds on Control Rod Drive (CRD) stubtubes and guide tubes, shroud to Reactor Pressure Vessel (RPV) weld H9 located belowthe shroud support plate, and a general overview of the bottom head. No recordableindications were noted. These examination results have been documented on theGENE examination data sheets.

8. Core Spray Piping

An augmented ultrasonic examination was completed on accessible core spray pipingwelds internal to the reactor vessel. An existing relevant indication on weld BP5 was re-sized with no noted growth after two cycles of operation. Issue Report #300599 wasgenerated to document this indication. The indication was accepted as-is for twoadditional cycles under design analysis L-002704.

9. Core Shroud

Four of the core shroud horizontal welds were ultrasonically examined in accordancewith BWRVIP-76, UBWR Vessel and Internals Project, BWR Core Shroud Inspection andFlaw Evaluation Guidelines". - No relevant indications were identified. Figure 2-2 ofBWRVIP-76 requires that the inspected length for each weld be greater than 50% of thelength of the weld or a plant specific evaluation is performed in accordance withAppendix D of BWRVIP-76. The length of weld examined was as follows:

H3: Looking-up: 73.1%H3: Looking-down: 0%H5: Looking-up: 40.5%H5: Looking-down: 71.0%H6: Looking-up: 0%H6: Looking-down: 74.5%H8: Looking-up: 73.7%H8: Looking-down: 0%

Greater than 50% coverage was not achieved on both sides of any of these welds, and aplant specific evaluation was required per Section 2.2 of BWRVIP-76 and is documentedin calculation L-003119. The calculation concluded that the Unit 2 core shroud has beenvery conservatively evaluated in accordance with BWRVIP-76 to maintain structuralintegrity for a minimum of 2 years, until the eleventh fuel cycle.

Note: LaSalle County Station weld nomenclature differs from the BWRVIP. The shroudcontains two beltline welds (H4 and H5), H6 is BWRVIP weld H5, and H8 is BWRVIPweld H7.

.6

10. ASME Code Section Xl Piping & Component Support Examinations

Piping and component supports were inspected (42 total) during thisrefuel outage. These were distributed between ASME Code Section XI Class 1 and2/D+ supports as follows:

* ASME Code Class 1 - 22 supports.* ASME Code Class 2/D+ - 20 supports.

One rejectable indication was detected during these examinations.

MS01-2005V had spring can settings outside of design tolerances. Issue Report #305584 was initiated to disposition the indication. The condition was evaluated underEngineering Change # 354132 and found to be acceptable.

As required by ASME Section XI Code Case N-491-1, "Alternative Rules for Examinationof Class 1, 2, 3, and MC Components Supports of Light-Water Cooled Power PlantsSection Xl, Division 1," sample expansion examinations were completed for therejectable indication. No further detrimental indications were detected.

7

LASALLE COUNTY STATION UNIT 2

TENTH REFUEL OUTAGE

ASME CODE SECTION XI SUMMARY REPORT

TABLE OF CONTENTS

1. INTRODUCTION

11. SCOPE OF INSPECTIONS

Table A - ASME Code Section XI Examinations

Table B - Augmented Inservice Inspections AISI

Table C - ASME Code Section XI Component Support Examinations

Table D - ASME Code Section XI Pressure Testing

Table E - Class 1 & 2 Repair/Replacements

III. SUMMARY OF RESULTS, EVALUATIONS, AND CORRECTIVE ACTIONS

IV. ATTACHMENTS

1. NIS-1 Form

2. NIS-2 Forms

3. Abbreviations

TABLE AASMIE CODE SECTION XI ISI INSPECTIONS

ASME CATEGORY B-A

ITEM #

1.2.3.4.5.6.7.

ITEM DESCRIPTION

LCS-2-AALCS-2-ADLCS-2-BMGEL-1061-DAGEL-1061 -DEGEL-1061-DFLCS-2-AE

EXAM TYPE RESULT

UTUTUTUTUTUTUT

NRINRINRINRI, 60% COVERAGE, REFERENCE CR-26NRI, 60% COVERAGE, REFERENCE CR-26NRI, 60% COVERAGE, REFERENCE CR-26NRI, 58.1%COVERAGE, REFERENCE CR-26

ASME CATEGORY B-D

1.2.3.4.5.6.7.8.9.10.I1.12.13.14.15.16.17.18.

LCS-2-N2BLCS-2-N2CLCS-2-N2FLCS-2-N2GLCS-2-N2HLCS-2-N2JLCS-2-N2KLCS-2-N3ALCS-2-N3B2-NIR-2B2-NIR-2C2-NIR-2F2-NIR-2G2-NIR-2H2-NIR-2J2-NIR-2K2-NIR-3A2-NIR-3B

UTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUT

NRI, 70%COVERAGE, REFERENCE CR-26NRI, 70% COVERAGE, REFERENCE CR-26NRI, 70% COVERAGE, REFERENCE CR-26NRI, 70% COVERAGE, REFERENCE CR-26NRI, 70% COVERAGE, REFERENCE CR-26NRI, 70% COVERAGE, REFERENCE CR-26NRI, 70% COVERAGE, REFERENCE CR-26NRI, 68% COVERAGE, REFERENCE CR-26NRI, 68% COVERAGE, REFERENCE CR-26NRINRINRINRINRINRINRINRINRI

ASME CATEGORY B-G-2

1.2.3.4.5.6.7.8.9.10.11.12.13.14.15.16.

MS-2001B-I IMS-2002B-22MS-2002B-26MS-2002B-30MS-2003B-12MS-2003B-16MS-2003B-20RI-2002B-22RT-2001B-18ART-2001B-18B2B21-F013M2B21-F028B2B21-F028D2B21-F032A2B33-F067B2E12-FO50A

VT-IVT-IVT-1VT-IVT-IVT-IVT-lVT-iVT-IVT-IVT-1VT-IVT-iVT-IVT-IVT-I

NRINRINRINRINRINRINRINRINRINRINRINRINRINRINRINRI

ASME CATEGORY B-K

1.2.3.4.5.

RPV-SS-2VS-IHP02-2812CRH40-2817CRH40-2818C

PT/VTMT/UT.MTMTMT

NRI, 52% COVERAGE, REFERENCE CR-25NRINRINRINRI

TABLE A (CONT'D.)ASME CODE SECTION XI ISI INSPECTIONS

ITEM # ITEM DESCRIPTION EXAM TYPE RESULT

6. RH53-2840C MT NRI7. R124-2853X MT NRI8. R124-2854X MT TWO INDICATIONS, ACCEPTABLE

ASME CATEGORY B-M-2

1. 2B21-F028B VT-3 NRI2. 2B21-F028D VT-3 NRI3. 2B21-F032A VT-3 NRI4. 2B33-F067B VT-3 NRI5. 2E12-F050A VT-3 NRI

ASME CATEGORY B-N-I

1. SURFACES ABOVE THE CORE VT-3 NRI2. SURFACES BELOW THE CORE VT-3 NRI3. GENERAL EXAM OF RPV

BOTTOM HEAD VT-3 NRI4. BOTTOM HEAD SURFACES

ATJETPUMPS#1-20 VT-3 NRI

ASME CATEGORY B-N-2

1. (3) CORE SPRAY PIPING ATT. EVT-I NRI2. (2) FEEDWATER SPAGER ATT. EVT-I NRI3. DRYER SUPPORT LUGS EVT-I NRI4. LOWER SURVEILLANCE LUGS VT-I NRI5. UPPER SURVEILLANCE LUGS VT-3 NRI6. ACCESSIBLE CRD STUB

.TUBE WELDS VT-3 NRI7. ACCESSIBLE CRD STUB

TUBE SURFACES VT-3 NRI8. ACCESSIBLE SHROUD SUPPORT

TO RPV WELD BOTTOM SIDE VT-3 NRI9. SUPPORT PLATE GUSSET TO

RPV WELDS EVT-1 NRI10. SUPPORT PLATE SURFACES VT-3 NRI11. SUPPORT PLATE TO SHROUD

CYLINDER WELD EVT-I NRI12. ACCESSIBLE SHROUD SUPPORT

LEGS TO RPV WELDS VT-3 NRI13. DRYER HOLD DOWN LUGS VT-3 NRI

ASME CATEGORY C-A

1. IRH-HX2B-05 UT NRI2. IRH-HX2B-06 UT NRI

ASME CATEGORY C-B

1. IRH-HX2B-07 NOZ TO SHELL UT NRI2. IRH-HX2B-07 INNER RADIUS UT NRI

ASME CATEGORY C-C

1. RH03-2853V MT NRI2. RH03-2884S MT NRI

TABLE A (CONT'D.)ASME CODE SECTION XI ISI INSPECTIONS


3.4.5.6.

RH03-2009VRH14-2807XRH40-2877XRH53-2826X

MTMTMT/UTMT

NRINRITWO INDICATIONS, SEE REPORT PG. 4NRI

ASME CATEGORY C-G

1.2.3.

IRH-PU2B-01IRH-PU2B-02IRH-PU2B-03

MTMTMT

NRINRINRI

ASME CATEGORY R-A

ITEM #

1.2.3.4.5.6.7.8.9.10.11.12.13.14.15.16.17.18.19.20.21.22.23.24.25.26.27.

ITEM DESCRIPTION

FW-2002-18FW-2002-27HP-2001-02LP-2001 -01LP-2001-23LP-2001-24MS-2003-02MS-2003-03MS-2004-02MS-2004-03MS-2051-17MS-2051-20MS-2052-15RH-2001-01RH-2077-26RH-2003-21RH-2004-02RH-2004-26RI-2002-18RR-2005-20RR-2005-21RR-2008-52RT-2001-03MS-2046-12MS-2046-13MS-2046-13BMS-2046-15

EXAM TYPE RESULT

UTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUTUT

NRINRINRINRINRINRINRINRINRINRINRINRINRINRINRINRINRINRIROOT GEOMETRYNRINRINRINRINRIIPSINRI/PSIROOT GEOMETRY/PSINRI/PSI

TABLE BAUGMENTED ISI INSPECTIONS

AISI CATEGORY BWVRVIP-75 IGSCC

ITEM #

I.2.3.4.5.6.7.8.

ITEM DESCRIPTION

RH-2001-21ARR-2006-07RR-2006-08RR-2006-09RR-2006-13RR-2006-14RR-2007-04RR-2007-09

EXAM TYPE RESULT

UT/PT NRIUT NRIUT NRIUT/PT NRIUT/PT NRIUT/PT NRIUT/PT NRIUT/PT NRI

AISI CATEGORY VESSEL INTERNALS

1.2.3.4.5.

6.7.

8.9.

10.

11.12.13.14.

STEAM DRYER VT-ISTEAM SEPARATOR VT-3CORE SPRAY PIPING UT/EVT-ICORE SPRAY SPARGERS VT-ICORE SPRAY PIPING & SPARGERBRACKETS EVT-IJET PUMP ASSY. WELDS EVT-I, VT-I & VT-3FEEDWATER SPARGERBRACKETS EVT-1LPCI COUPLINGS EVT-I, VT-I & VT-3ACCESSIBLE JET PUMPADAPTER WELDS VT-3SUPPORT PLATE TO SHROUDCYLINDER WELD EVT-ISHROUD HEAD BOLTS VT-3ACCESS HOLE COVERS VT-ITOP GUIDE C-CLAMP VT-3SHROUD UT

SEE REPORT PAGE 5NRI, SEE REPORT PAGE 5SEE REPORT PAGE 6 BWRVIP-18NRI, BWRVIP-18

NRI, BWRVIP-18SEE REPORT PAGE 6 BWRVIP-41

NRI, BWRVIP-48NRI, BWRVIP-42

NRI

NRISEE REPORT PAGE 5NRINRINRI, SEE REPORT PAGE 6

AISI CATEGORY MISC.


1. RPV STUDS (1-76) UT NRI, SEE REPORT PAGE 2

TABLE CASME CODE SECTION XI COMPONENT & SUPPORT EXAMINATIONS

ASME CLASS I


1.2.3.4.5.6.7.8.9.10.11.12.13.14.15.16.17.18.19.20.21.22.

RPV SkirtFW02-2837CFW02-2847XHP02-2801 C-MSOO-2039XMSOO-2046VMSOO-2056VMSOI-2005VMSOI-2006VMS06-2810CMS 14-2826XRH03-2891VRH03-2895CRH04-2859XRH04-2892CRH40-2817CRH40-2826XR124-2842XRROO-2038VRROO-2063VRR16-2800CRTOI-2885G

VTr-3 'VT-3VT-3 -VT-3VT-3VT-3VT-3VT-.3VT-3VT-3VT-3VT-3VT-3VT-3VT-3VT-3 -VT-3VT-3VT-3VT-3VT-3-VT-3

NRINRINRINRINRINRINRISETTINGS, ACCEPTEDNRINRINRINRINRINRINRINRINRINRINRINRINRINRI

1.2.3.4.5.6.7.8.9.10.11.12.13.14.15.16.17.18.19.20.

HGO5-2013XHGO5-2015XHP14-2803VHP14-2806XLP02-2826GLP02-2868XMS38-2808CRHO1-240IXRH02-2833VRH03-2838XRH03-2853VRH03-2898XRH03-2900VRH33-2401GRH40-2869XRH40-2877XRH53-2826XRH53-2835VRH58-2808X2C RHR PUMP

ASME CLASS 2

VT-3VT-3VT-3 .VT-3VT-3VT-3VT-3VT-3VT-3VT-3VT-3VT-3VT-3VT-3VT-3VT-3VT-3VT-3VT-3VT-3

NRINRI

... NRINRINRINRINRINRINRINRINRINRINRINRI

NRINRINRINRINRI

TABLE DASME CODE SECTION XI PRESSURE TESTING


1. 2-CM-03 VT-2 NRI2. 2-CM-04 VT-2 NRI3. 2-CM-05 VT-2 NRI4. 2-CM-14 VT-2 NRI5. 2-ES-01 VT-2 NRI6. 2-FC-09 VT-2 NRI7. 2-FC-10 VT-2 NRI8. 2-FW-01 VT-2 . NRI9. 2-HG-03 VT-2 NRI10. 2-HG-08 VT-2 NRI11. 2-HG-09 VT-2 NRI12. 2-IN-09 VT-2 NRI13. 2-IN-10 VT-2 NRI14. 2-IN-1 I VT-2 NRI15. 2-IN-12 VT-2 NRI16. 2-IN-13 VT-2 NRI17. 2-IN-14 VT-2 NRI18. 2-IN-15 VT-2 NRI19. 2-MC-01 VT-2 NRI20. 2-MS-01 VT-2 NRI21. 2-NB-01 VT-2 NRI22. 2-RR-01 VT-2 NRI23. 2-RR-02 VT-2 NRI24. 2-RR-04 VT-2 NRI25. 2-RR-05 VT-2 NRI26. 2-RR-06 VT-2 NRI27. 2-RR-08 VT-2 NRI28. 2-SA-01 VT-2 NRI29. 2-VP-01 VT-2 NRI30. 2-VP-02. VT-2 NRI31. 2-VQ-02 VT-2 NRI32. 2-VQ-03 VT-2 PACKING33. 2-VQ-05 VT-2 PACKING34. 2-WR-01 VT-2 NRI35. 2-RCPB VT-2 THROUGH WALL LEAK, SEE REPORT PAGE 5

TABLE EREPAIR/REPLACEMENT ACTIVITIES

CLASS-I

WORK PACKAGE # DESCRIPTION

1. 428318 Replace Main Steam SRV with Rebuilt Spare2. 428319 Replace Main Steam SRV with Rebuilt Spare3. 429584 Replace Main Steam SRV with Rebuilt Spare4. 515539 Replace Main Steam Isolation Valve Disc5. 515542 Replace Main Steam Isolation Valve Disc6. 544418 Replace Control Rod Drive & Cap Screws7. 544419 Replace Control Rod Drive & Cap Screws8. 544420 Replace Control Rod Drive & Cap Screws9. 544421 Replace Control Rod Drive & Cap Screws10. 554320 Repair RR Valve11. 554321 Replace Outboard MS Drain Isolation Valve12. 554322 Replace Inboard MS Drain Isolation Valve13. 585833 Replace Main Steam SRV with Rebuilt Spare14. 585834 Replace Main Steam SRV with Rebuilt Spare15. 585835 Replace Main Steam SRV with Rebuilt Spare16. 593839 Replace Main Steam SRV with Rebuilt Spare17. 605993 Replace Explosive Valve18. 620332 Replace RT Snubber19. 625682 Repair RH Check Valve20. 628869 Replace Control Rod Drive & Cap Screws21. 628870 Replace Control Rod Drive & Cap Screws22. 628871 Replace Control Rod Drive & Cap Screws23. 628888 Replace Control Rod Drive & Cap Screws24. 628889 Replace Control Rod Drive & Cap Screws25. 628891 Replace Control Rod Drive & Cap Screws26. 628893 Replace Control Rod Drive & Cap Screws27. 628895 Replace Control Rod Drive & Cap Screws28. 628897 Replace Control Rod Drive & Cap Screws29. 628898 Replace Control Rod Drive & Cap Screws30. 632225 Repair RPV Head Cladding31. 696096 Replace Control Rod Drive & Cap Screws32. 696097 Replace Control Rod Drive & Cap Screws33. 696098 Replace Control Rod Drive & Cap Screws34. 696099 Replace Control Rod Drive & Cap Screws35. 696100 Replace Control Rod Drive & Cap Screws36. 781368 Replace HP Pipe fitting37. 782779 Replace Control Rod Drive & Cap Screws38. 789955 Repair Weld on MS Drain Line

TABLE E (CONT'D)

REPAIR/REPLACEMENT ACTIVITIES

CLASS-2

'WORK PACKAGE # DESCRIPTION

1. 421977 Replace HP Water Leg Pump2. 437834 Replace RI Rupture Disc3. 437835 Replace RI Rupture Disc4. 541468 Replace SC Valve & Piping5. 552479 Replace Extension Tube on MS Strut6. 582162 Repair RH Valve7. 582163 Repair RH Valve8. 668477 Repair Heat Exchanger by Plugging Tubes9. 677752 Replace RI Valve Disc10. 781039 Repair Indications on RH Pipe11. 94060704 Replace Pump Seal Gland Plate

ATTACHMENT 3

ABBREVIATIONS

AD ADDENDA

ANIC AUTHORIZED NUCLEAR INSERVICE CONCRETE

AISI AUGMENTED INSERVICE INSPECTIONS

ASSY ASSEMBLY

ATT ATTACHMENT

ASME AMERICAN SOCIETY OF MECHANICAL ENGINEERS

AUTO UT AUTOMATED ULTRASONIC TEST

BOM BILL OF MATERIAL

BWR BOILING WATER REACTOR

BWROG BOILING WATER REACTOR OWNER'S GROUP

BWRVIP BOILING WATER REACTOR VESSEL AND INTERNALS PROJECT

CHRON TRACKING SYSTEM FOR ENGINEERING EVALUATIONS

CID CATALOG IDENTIFICATION

CM CONTAINMENT MONITERING

CISI CONTAINMENT INSERVICE INSPECTION

CR COMPONENT RELIEF REQUEST

CRD CONTROL ROD DRIVE

EC ENGINEERING CHANGE

ED EDITION

EGC EXELON GENERATION COMPANY

ES EXTRACTION STEAM

EVT ENHANCED VISUAL TEST

FC FUEL POOL COOLING

FW FEEDWATER

GENE GENERAL ELECTRIC NUCLEAR ENERGY

HG CONTAINMENT COMBUSTIBLE GAS CONTROL

HP HIGH PRESSURE CORE SPRAY

HSB-CT HARTFORD STEAM BOILER INSPECTION & INSURANCE CO. OF CONNECTICUT

HT# HEAT#

ATTACHMENT 3 (CONT'D)

ID/OD INSIDE DIAMETER/OUTSIDE DIAMETER

IGSCC INTERGRANULAR STRESS CORROSION CRACKING

IL ILLINOIS

IN INSTRUMENT NITROGEN

IRM INTERMEDIATE RANGE MONITOR

ISI INSERVICE INSPECTION

L2R07 LASALLE TWO REFUEL OUTAGE SEVEN

L2R08 LASALLE TWO REFUEL OUTAGE EIGHT

L2R09 LASALLE TWO REFUEL OUTAGE NINE

L2RIO LASALLE TWO REFUEL OUTAGE TEN

LLC LIMITED LIABILITY COMPANY

LPRM LOCAL POWER RANGE MONITOR

LP LOW PRESSURE CORE SPRAY

MIL MILLIMETER

MC CLEAN CONDENSATE STORAGE

MS MAIN STEAM

MSIV MAIN STEAM ISOLATION VALVE

MT MAGNETIC PARTICLE TEST'

MWt MEGAWATT THERMAL

N/A NOT APPLICABLE

NB NUCLEAR BOILER

NDE NON-DESTRUCTIVE EVALUATION

NDES NONDESTRUCTIVE EXAMINATION SERVICES

NIR NOZZLE INNER RADIUS

NR NUCLEAR INSTRUMENTATION

NRC NUCLEAR REGULATORY COMMISSION

NRI NON-RECORDABLE/NON-RELEVANT INDICATION

PA PENNSYLVANIA

PC PRIMARY CONTAINMENT

PCE PART CLASSIFICATION EVALUATION


PDI PERFORMANCE DEMONSTRATION INITIATIVE

PG PAGE

PO PURCHASE ORDER

PR PRESSURE TESTING RELIEF REQUEST

PSI PRESERVICE INSPECTION

PSIG POUNDS PER SQUARE INCH GAGE

PT LIQUID PENETRANT TEST

PTE PART TECHNICAL EVALUATION

PWHT POST WELD HEAT TREATMENT

QRI QUALITY RECEIPT INSPECTION

RC-PB REACTOR COOLANT PRESSURE BOUNDARY

RD ROD DRIVE

RE REACTOR BUILDING EQUIPMENT DRAINS

RF REACTOR BUILDING FLOOR DRAINS

RH RESIDUAL HEAT REMOVAL

RI REACTOR CORE ISOLATION COOLING

RIN RECEIPT INSPECTION #

RPV REACTOR PRESSURE VESSEL

RR REACTOR RECIRCULATION

RT REACTOR WATER CLEAN UP

SA SERVICE AIR

SAR SAFETY ANALYSIS REPORT

SC STANDBY LIQUID CONTROL

SDC SHUTDOWN COOLING

SEAG SITE ENGINEERING ADMIN GROUP

SIL SERVICES INFORMATION LETTER

SRM SOURCE RANGE MONITOR

SRV SAFETY RELIEF VALVE

STM STEAM

UT ULTRASONIC TEST


VG STANDBY GAS TREATMENT

VLV VALVE

VP PRIMARY CONTAINMENT CHILLED WATER

VQ PRIMARY CONTAINMENT VENT AND PURGE

VT VISUAL TEST

WO WORK ORDER

WR REACTOR BUILDING CLOSED COOLING WATER

ATTACHMENT I

NIS-1

OWNER'S REPORT FOR INSERVICE INSPECTION

1'UK?4 A1l-1 UVViAh('b kJKAUJK I UK' 11NbLKV ILI 11NbrhqYJUINbAs required by the Provisions of the ASME Code Rules

1. Owner Exelon Generation Company (EGC), LLC, 200 Exelon Way, Kennett Square, PA 19348(Name and Address of Owner)

2. Plant LaSalle County Station, 2601 North 21st Road Marseilles, IL 61341-9757(Name and Address of Owner)

3. Plant Unit Two 4. Owner Certificate of Authorization (if required) N/A

5. Commercial Service Date 10/17/84 6. National Board # for Unit 10

7. Components Inspected

Component or Manufacturer Manufacturer State or NationalAppurtenance Or Installer or Installer Province No. Board No.

Serial No.

Reactor Pressure Chicago Bridge & Iron T-37 B-243 19 0Vessel

Reactor Recirculation General Electric N/A N/A N/ACompany

Nuclear Boiler & CM B.F. Shaw N/A N/A N/ASystems

Residual Heat B.F. Shaw N/A N/A N/ARemoval

Feedwater, FC & VQ B.F. Shaw N/A N/A N/ASystems

High Pressure Core B.F. Shaw N/A N/A N/ASpray

Low Pressure Core B.F. Shaw N/A N/A N/ASpray

Main Steam, & IN GE/B.F. Shaw N/A N/A N/A

RI & RT Systems B.F. Shaw N/A N/A N/A

ES, MC, SA & WR B.F. Shaw N/A N/A N/ASystems

SC, HG & VP B.F. Shaw N/A N/A N/ASystems

Note: Supplemental sheets in torm ot lists, sketches, or drawings may De used, provided (1) size is zSi2 in. x I1i Y in., (2) informationn items I through 6 on this report is included on each sheet, and (3) each sheet is #ed and the # of sheets is recorded at the top of thi!1orm.

FORM NIS-1 (Back)

8. Examination Dates:

9. Inspection Period Identification:

10. Inspection Interval Identification:

11. Applicable Edition of Section XI

12. Date/Revision of Inspection Plan:

02/21/03 to 03/16/05

3rd Period - From 07/05/04 to 07/04/2007

2nd Interval - From 10/17/94 to 07/04/2007

1989/1998* Addenda N/A

11/20/2002 Rev.4

13. Abstract of Examination and Tests. Include a list of examinations and tests and a statement concerning status ofwork required for the Inspection Plan. See Summary Report for item 13.

14. Abstract of Results of Examinations and Tests. See Summary Report for item 14.

15. Abstract of Corrective Measures. See Summary Report for item 15.*Via Relief Request CR-32, the 1998 Edition of the ASME Code, Section XI applies to CISIAction Tracking Item # 314183-03 is tracking completion of NDE for Work Order # 789955.

We certify that a) the statement made in this report are correct, b) the examinations and tests meet Inspection Plan as required by theASME Code, Section XI, and c) corrective measures taken conform to the ASME Code, Section XI.

Certificate of Authorization No. (if applicable) N/A Expiration Date N/ADate Abuz /0. 20 05 Signed ExelonGenerationCompany,LLC By i ,~ C. -

Owner

CERTIFICATE OF INSERVICE INSPECTION

1, the under signed, holding a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of Illinois And employed by HSB-CT of

Hartford, Connecticut Have inspected the components described in the Owner's Report during the period02/21/2003 To 03/16/2005 , and state that to the best of my knowledge and belief, the

Owner has performed examinations and tests and taken corrective measures described in this Owner'sReport in accordance with the Inspection Plan and as required by the ASME Code, Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied,concerning the examinations, tests, and corrective measures described in this Owner's Report. Furthermore,neither the Inspector nor his employer shall be liable in any manner for any personal injury or propertydamage or a loss of any kind arising from or connected with this inspection.

/I Inspector's SignatureCommissions IIL. 1927

National Board, State, Province, and Endorsements

Date 6_-, _ _ _-__ _ _ 20 05

ATTACHMENT 2

NIS-2

OWNERS REPORT OF REPAIR OR REPLACEMENT

FORM NIS-2 OWNER'S REPORT OF REPAIRS OR REPLACEMENTSAs Required by the Provisions of ASME Code Section Xi

1. Owner Exelon Generation Company (EGC) LLC(Name)

200 Exelon Way. Kenneth Square. PA.. 19348

Date 05/14/05

AddressLaSalle County Nuclear Station2. Plant

Name2601 N. 21" Rd. Marseilles. 1I. 61341

Address

Sheet I of I

Unit 2

W.O. #428318Repair Organization, P.O. No., Job No., etc.

3. Work Performed b,v Morhanteal Unlnfanance(Name)

Mechanical Maintenance(Address)

Type Code Symbol Stamp N/AAuthorization No. N/AExpiration Date N/A

4.5.

Identification of System (MS) Main Steam(a) Applicable Construction Code Sect lii 19 71 Edition S172 Addenda, Code Cases 1567 and 1711(b) Applicable Edition of Section Xi Utilized for Repairs or Replacements-19 89, No Ad, Code Cases NoIdentification of Comnonents Renalred or Reolaced. and Replacement Comoonents6.

Name of Name of Mfrs. Ser. Nat'l Other Year Repaired ASME CodeComponent Mfr. No. Bd. Identification Built Replaced, or Stamped

No. Replacement (Yes or No)Safety Relief AG Crosby N63790-00-0073 N/A 2B21-F013E * Replaced NIA

V alve__ _ _ _ __ _ _ _ _ _ _ ___ _ _ _ _ _

Safety Reiief AG Crosby N63790-00-0004 N/A 2B21-F013E Replacement N/AValve or N63790-05- Receipt # 101593

0004 (Modified)_Nozzle AG Crosby N93184-49-0138 N/A Replaced N/A

Nozzle AG Crosby N97498-32-0009 N/A Receipt# 101593 2003 Replacement NIA

Disc Insert N93185-46-0170 N/A Replaced N/A

Disc Insert AG Crosby N97499-45-0113 N/A Receipt# 101593 2004 Replacement N/A

8.

9.

Description of Work Class I Repair & Replacement. * = Per N-5 Code Data Regort on file at LaSalle CountV Station.Tests Conducted: Hydrostatic i I Pneumatic I I Normal Operating Pressure I X I Other Visual

Pressure. 1035 esl Test Temp. 155 Deg. FRemarks Valve SN# N63790-05-0004 was refurbished at Wvle Labs with documentation provided under Quality

(Applicable Manufacturer's Data Report to be Attached )Recelot #101593 and installed as a replacement for SN# N63790-00-0073 under work order #428318. SRV nozzle

-I-- --- I - - - ... t.� �.. -I--- " emlywab sbU als ~dot:U WVIL11 Ic UV ne UDUV I smI. oVeIall Ilu it Was IJIUW 111111111JUl11 LUIUlI doIr . !- e Ia ;V

Serial No. was modified due to the Installation of a new flexi-disc seat design.

CERTIFICATION OF COMPLIANCEWe certify that the statements made In the report are correct and these Replacement conforms to the rulesof the ASME Code, Section XI. (repair or replacement)Type Code Symbol Stamp NONE

Certificate of Au orization No.s_

Rinned ZZcc

NIA .Expiration Date NIA

tRI r~nnrd~natnr Date Hi /; . 2005Owner or Owner's Designee, Title


I, The undersigned, holding a valid commission Issued by the National Board of Boller and Pressure VesselInspectors and the State or Province of Illinois and employed by The Hartford Steam Boiler Insp. & Ins. Co. ofConnecticut have inspected the components described in this Owner's Report during the period

L2R09 to L2R10and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures described In this Owner's Report In accordance with the requirements of the ASME Code, Section XI.C at rltfinn- 6h1--Artfif1"fa nnkitb-- #imInna^ nor hie amnnimsxr maile anu t Swrro .. l rAo a_____

- I

: : - 10159 3 Q.C.-434ASheet 1 of 2

FORM NVR-1 REPORT OF REPAIR MODIFICATION ], OR REPLACEMENT* OF NUCLEAR PRESSURE RELIEF DEVICES

1. Work performed by ANDERSON GREENWOOD CROSBY 00076601(name of organization) (P.O. no., job no., etc.)

43 Kendrick St., Wrentham, MA 02093(address)

2. Work performed for 'EXELON CORPORATION,LASALLE STATION,MARSEILLES,IL.(name and address)

3. Owner EXELON CORPORATION,LASALLE STATION,MARSEILLES,IL.(name)

(address)4. Name, address and identification of nuclear power plant EXELON CORPORATION,LASALLE STATION,

MARSEILLES, IL.

5. a. Repaired pressure relief device MAIN STEAM SAFETY RELIEF VALVE

b. Name of manufacturer ANDERSON GREENWOOD CROSBY

c. Identifying nos. HB-65-BP l"' N63790.05.0004 -0- STEAM 6 R 10 1981(type) (mfr's serial no.) (Nat'l Bd. No.) (service) (size) (year built)

d. Construction Code ASME III 1971 S1972 1567,1711 I(narne/section/division) ... (edition) (addenda) (Code Case(s)) (Code Class)

6. ASME Code Section Xl applicable for Inservice inspection 1989 NO -:' :edition) (addenda) (Code Case(s))

7.' ASME Code Section XI used for repairs, modifications," or replacements 1989 ' NO -- ' . (edition) (addenda) (Code Case(s))

8.. Construction Code used for repairs, modifications, or replacements 1971 S1972 1567,1711(edition) (addenda) (Code Case(s))

9. Design responsibilities ANDERSON GREENWOOD CROSBY

10. Opening pressure 1175 PSIG Blowdown (if applicable). 3 % Set pressure and blowdown adjustmentmade at WYLE LABORATORIES,HUNTSVILLE.AL. using STEAM

- (location) ' (test medium)11. Description of work: (include name and identifying number of replacement parts) FLEXIDISC MODIFICATION,

REPAIR AND TESTING MADE AT WYLE LABORATORIES, HUNTSVILLE,AL. USING STEAM.

12. Remarks THE DISC INSERT WAS REPLACED AND VARIOUS PARTS MODIFIED AS PART OF THEFLEXIDISC MODIFICATION.

.. i

Form NVR-1 (Back): 10 1593

Certificate Holder's Serial Nos. N63790-05-0004

- Q.C.-434A- Sheet 2 of 2 "

CERTIFICAE1OF COMPLIANCE

I, ))A dI < 3~-z certify that the statements made in this report are correct and the repair, modification oxreplacement of the pressure relief device described above conforms to Section XI of the ASME Code and the NationalBoard Inspection Code "VRW and "NR" rules..National Board Certificate of Authorization No. 75 to 84 to use the WVR' stamp expires JAN. 14,2007National Board Certificate of Authorization No. 68 to use the "NR* stamp expires DEC.11 ,2006

Date 7-14&P ,>o Signed Anderson Greenwood/Crosby Oi *- / QA MGR.(name of repair organization) (authorized representative) (title)

- | : - ~~~CER TIFICATE OF INSPECTIN .; ; .;:

l, ,holding a valid commission issued by The Nationial Boardof Boiler and ressuie VesselInspectors and Certificate of competency issued by the jurisdiction of . MASSACHUSETTS and employed by

-HSB-CT of HARTFORD - CT. have:inspected the repair, modification or replacement described in this report on &6 Oand state that to thebest of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XIof the ASME Codeand the National Board Inspection Code 'VRW and 'NR' rules.By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerningthe repair, modification or replacement described in this'report. . Furthermore, neither the undersigned nor my employer shallbe liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with thisInspection.

Date - ' 5 •.

Signed ____________' _ Commissions MA1420 A, N. I(Inspector) - (Nat'l. Bd. (inc. endorsements), and jurisdiction, and no.)

. ...

2. Jan. 8. 2005 10:26AM No.1163 P. 4/5

Q.C.-392Sheet 1 of 2

FORM N-2 CERT[CATE HOLDERS' DATA REPORT FOR IDENTICAL- '-NUCLEAR PARTS AND APpuRTENANCES*

As required by the Provisions of the ASME Code. SectioIf , Drvislon 1 - Not to Exceed One Day's Production1. Manufactured and certified by

2. Manufactured for

-

Anderson Greenwood Crosby, 43 Kendrick St., Wrentham, MA 02093-(Name axnd Address of N Certificate Holder)

EXELON GENER~AT1ON(Name and Address of Purchaser or Owner)

LASALLE COUNTY STATION3. Location of Installation(Name and Address)

4. Type DS-C-63790-5 REV.A ASME SA182 GR.F316 70,000 _ 2003(drawing no.) (mat'l. spec. no.) (tensile strength) (CRN) (year built)

5. ASME Code, Section III, Division 1: 1971 SLJMER 1972 1 _ _ _(edition) (addenda date) (class) (Code Case No.)

6. Fabricated in accordance with Const. Spec. (Div. 2 only) - Revision - Date -. - (no.)

7. Remarks 2,9

B. Nom. thickns (in.) Min. desigi thickness (in.) - -_ Dia. ID (ft & in.) - Length overall (ft & in.)9. 'When applicable, Certificate Holders' daa reports are attacedo each item of this report.

Part or AppurtenanceSerial Number

,(1)7N97498-32.0009 -j (2) N97498-32-0010

(3)(4)(5)(6)(7)(8)(9)(10)(11)(12)(13)(14)(15)(16)(17)(18)(19)(20)(21)_(22)(23)(24)(25)

National IBoard No.;:

in Numerical Order- (26)

*(27)

_(29)

*'_ (30)-_m:^. (3l)

*' > (32)-i 1 1(33)

* (3 5)~

- (37)(38)

- (39): (40)

(41)(42)

-_ - (43)- (44)

_ ,(45)

_ 146)

* (47)(48)(49)

_____________(50)_


NationalBoard No.

in Numerical Order

I

I

10. Design press e psi. Temp. . F Hydro. test pressure 2370 at temp. 70 p F

(when applicable)k/ceZl nformation ia tocmn ofrrisk setches, or dnwip rmay be tsedprovidcd (I) sizc b8-112 x21 (2) inbrmrion ia hoxt 2 and 3on tis DAa Rcport

is included on euch sheet. (3) each shaec is manbcmd and cie nwuber of sheets rCordeda e itop ofthi forn.

This form (E00040) nay be ohtad from d&C order DepL, ASME, 22 Law Drive. Box 2300, Fairtded, NJ 07007-230Q

.12n. A. M5 10:26AM No-1163 P. 5/5.bn R. 700 102A *o16 P. L 5/5

C)a / 0Q.C.-392Form N-2 (Back) Sheet 2 of 2

Certificate Holder's Serial No. N97498-32-0009

JCERTIFICAT ORDESIGN

Design specifications certified by C.T. NIEH P.E. State CA Reg. no. 15581(when applicable)

Design reporE* certified by - P.E. State Reg no.(when applicable)

CERTIFICATE OF COMPliANCE

We certify 2hat the statements made in this report are correct and that this (these) Nozzlesconforms to the rules of construction of the ASMB Code, Section Jr, Dii'iosa 1.

NPT Certificate of Authorization No. N-1877 Expires Sep. 30, 2004Anderson Greenwood Crosby

Date ZO -f8-O3 Signed Wrentha by mMA(NPT Certificate Holder) (Authorized Representative)

CERTICAOF SPECON

1, the umdersigned, holding a valid commission issued by the.National Board of Boiler and Pressure Vessel inspectors andtLe State or Province of Massachusetts and employedbby" Factory Muttial Tsuran=c Co.of Johnston, Rhode Island have inspected these items described in this Data Report on

_______ _ _ _a , 20 _2, 1 and state that to the best of my knowledge and belief, the Certificate Holderhas fabricated tse parts or appurtenances in accordaiceifh tlhe AivME Code, Section Em, Division 1. Each part listed has

becn authorized for stamping on the date shown above. ^ -By signing this certificate, neither the Inspector nor his employer makes arty warranty, expressed or implied, concerningthe equipment described in this Data Report. Firthermoire, neither the lospector nor his employer shall be liable in anymanner for any personal injury or property damage or loss5of any ktd arising from or connected with this inspection.

Date ;P d 20 O3

Signed Commissions /7, /(Authorized Inspector) . aT.Bd. (ioel. endbrsemes) and slate or proy. a&d no.)

.Jan. 8. 2005 10:26AM No.1163 P. 2/5

Q.C.-392* Sheet I of 2

FOJRM N-2 CERtlfICATE HOLDERS' DATA REFORT.FOR IDEIflCALNUCLEAR PARTS AND.APPURTENANCES;*

As requir-edb the Provisions of the ASME Code. Secton m. Division I - Not to Exceed One Day's Production

-

1. Manufactured and certified by Anderson Greenwood Crosby, 43 Kendrick St., Wrentbani, MA 02093. .

; (Name and Address of N Certificate Holder)EXELON GENERATION

. __ .

2 Manufactured for(Name and Address of Purchaser or Owner)

LASALLE STATION3. Location of Installation(Name and Address)

4. Type DS-A-63790-2 REV.- . ASME SA637 GR 718 185,000 _ 2004(drawing no.) (mat'l. spec. no.) (tensile strength) (CRN) (year built)

5. ASME Code, Section III, Division 1. 1971 SUMMER 1972 1(edition) (addenda date) (class) (Code Case No.)

6. Fabncated in accordance with Const. Spec. (Div. 2 only) - Revision - Date(no.)

7. Remarks

8 Nom thiclsaess (in.) - Min. design thickness (in.) - Dia. ID (t & in.) - Length overall (ft & in.)9 When aprplicable. Certificate Holders' data reports are attached for each item of this report.

Parn or ApputenaniceSerial Number

(1) N97499-45-0112(2) zN97499-45-1O 13

J(3) N97499-45-0114(4) N9g7499-45-0115(5) N97499-45-0116(6) N97499-45-0117(7)(8)(9)(10)(11)(12)(13)(14)(15)(16)(17)(18)(19)20)

(21)(22)(2)-(24)(25)

National :Board No .-

in Numerical Order

.~ I


(2(2(2(2-(31(3(3:(3:(36(3!(3f(31(38(39(40(41:(420(43;(44)(45)(46)(47)(48)(49)(5O)

.6_7)_8)_9)- -D)0)

Z)-

NationalBoard No.

in Numerical Order

4)-

1)))

?

II-

. .

II Design pressure -- psi. Temp. - F Hydro. test pressure 2370 psig at temp. 70 0 F(when applicable)

~1r tesnuJnformtzdon inathe foru of itrm. skehes. or drawSS nuy be Wed provded (1) se Is 8-Ml x 11. (2) Irormaxion In Items 2 and 3 on this Dat ReportIs includcd on eacb shle, (3) ezcA sheet Is numbered and the nr ober ofsheea As recorded ct the top of Ws form. _

This brn (E00O40) may be obtained frcm ihc Order Dept.. ASM E. 22 Law Drive. Box 2300. Fairfield. NJ 070t7-2300

.Jan. 8. 2005 10:26AM No.1163 P. 3/5

Q.C.-392

Form N-2 (Back) Sheet 2 of 2Certificate Holder's Serial No. N97499-45-0112 thru 0117

CERTIFICATE QF DESIGN

Design specifications certified by C T NIEH . P.E. State CA Reg. no 15587(when applicable)

Design report* certified by W.D. GREENLAW P.E. State MA Reg. no. 14784(when applicable)

CERTIFJCA ZE OF COMPLCk

We cerufy that the statements made in this report are correct and that this (these) Disc Insertsconforms to the rules of construction of the ASME Code, Section m, Division 1.

NPT Certificate of Authonzation No. N-1877 Expires Sep. 30, 2004Anderson Greenwood Crosby

Dam _ 5_ FE_ Zc Sgned _ Wrentham, MA by ____ID (NPT Certificate Holder) (Authorized Representative)

CERTIFICATE OF INSPECTION

1, the undersigned, holding a valid commmssion issued by the National Board of Boiler and Pressure Vessel Inspectors and

the State eor-Pre4neeof 45AS.# and employed by ABS Grout Inc.of Houston Tcxas have inspected these items described in ti5 Data Report on

,gR-, 20o.0 and state that to the best of my knowledge and belief, the Certificate Holderhas fabricated these parts or appurtenances in accordance with the ASMB Code, Section III, Division 1. Each part listed has

been authorized for stamping on the date shown above.

By igning tins certificate, neither the Inspector nor his employer makes any warranty, expremsed or implied, concerunwgthe equipment described in this Data Report. Furthermore7 neither the Inspector nor his employer shall be liable in any

manner for any personal Injury or property damage or loss of any kand arismg from or connected with thas inspection.

Date 5, 20OO

Signed_ __ _ __ _ _ __ _ _ Co ssions Lk ILJ - 4(Authorized Inspector) (Nat'l. Bd. (ncl. endorseniasts) and state or prov. and no)

FORM NIS-2 OWNER'S REPORT OF REPAIRS OR REPLACEMENTSAs Required by the Provisions of ASME Code Section XI

1. Owner Exelon Generation Company (EGCC LLC(Name)

200 Exelon Way, Kenneth Square, PA., 19348Address

2. Plant LaSalle County Nuclear StationName

2601 N. 2 1" Rd. Marseilles. II. 61341Address

Datp 051AI4/0

Sheet 1 of 1

Unit 2


3. Work Performed by

IJ"I{P+AN^ %- +f

Mechanical Maintenance(Name)


- lime "1"1 cheat

Type Code Symbol Stamp NJAAuthorization No. N/AExpiration Date N/A

4.5.

IUVIMllCILIUVII WI QYZLem IM4IJI OLUdII

(a) Applicable Construction Code Sect III 19 71 Edition S172 Addenda, Code Cases 1567 and 1711(b) Applicable Edition of Section Xl Utilized for Repairs or Replacements-19 89, No Ad, Code Cases NOIdentification of Components Renalred or Replaced, and Reolacement Comnonents6.

Name of Name of Mfrs. Ser.- Nat'l Other Year Repaired ASME CodeComponent Mfr. No. Bd. Identification Built Replaced, or Stamped

No. Replacement (Yes or No)Safety Relief Valve AG N63790-00-0065 N/A 2B21-F013R1 Replaced NIA

CrosbySafety Relief Valve AG N63790-00-0015 N/A 2B21-F013R a Replacement N/A

Crosby or N63790-05- Receipt # 1015930015 (Modifled)__

Disc Insert N93185-53-0214 N/A Replaced N/A

Disc Insert AG N97499-45-0115 N/A Recelpt# 101593 2004 Replacement N/ACrosby _

7.8.

9.

Description of Work Class 1 Repair & Replacement. * = Per N-5 Code Data Report on file at LaSalle County Station.Tests Conducted: Hydrostatic I I Pneumatic I I Normal Operating Pressure I X I Other Visual

Pressure .Q1035 psl Test Temp. 155 Deg. FRemarks Valve SN# N63790-05-0015 was refurbished at Wyle Labs with documentation provided under Quality

(Applicable Manufacturer's Data Report to be Attached )Receipt# 101593 and Installedas a replacementforSN# N63790-00-0065 underwork order#428319. Ail bolting

materials were reused. A visual examination VT-1 was performed on all Class 1 Inlet bolting.** Renlacement SRV Serial No. was modified due to the Installation of a new flexi-disc seat design.

CERTIFICATION OF COMPLIANCEWe certify that the statements made In the report are correct and this Replacement conforms to the rulesof the ASME Code, Section XI. (repair or replacement)Type Code Symbol Stamp NONE

Certificate of Auth rIzatIon No.

Signed

N/A -Expiratlon Date N/A

ISI Coordinator Date / = . 2005Owner or Owner's Designee, Title


I, The undersigned, holding a valid commission Issued by the National Board of Boller and Pressure VesselInspectors and the State or Province of Illinois' and employed by The Hartford Steam Boller Inso. & Ins. Co. ofConnecticut have Inspected the components described in this Owner's Report during the period

L2R09 to L2R10and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures described In this Owner's Report In accordance with the requirements of the ASME Code, Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty ,expressed or Implied,concerning the examinations and corrective measures described In this Owner's Report. Furthermore, neither theInspector nor his employer shall be liable In any manner for any personal Injury or property damage or a loss ofany kind arising from or connected with this Inspection.

i Commissions IL 1927In ctor's Signature National Board, State, Province, and Endorsements

Date _ _ __ 2005

101593- Q.C.-434ASheet I of 2

FORM NVR-1 REPORT OF REPAIR MODIFICATION [, OR REPLACEMENT IOF NUCLEAR PRESSURE RELIEF DEVICES


43 Kendrick St., Wrentham, MA 02093(address)

2. Work performed for EXELON CORPORATION,LASALLE STATIONMARSEILLES,IL.(name and address)

3. Owner EXELON CORPORATIONLASALLE STATION,MARSEILLES,IL.(name)

(address)4. Name, address and identification of nuclear power plant EXELON CORPORATION,LASALLE STATION,

MARSEILLES, IL.



c. Identifying nos. HB-65-BP N63790-05-0015 - STEAM 6 R 10 - 1981(type) (mfr's serial no.) (Nat'l Bd. No.) (service) (size) (year built)

d. Construction Code ASME III 1971 S1972 1567,1711 1- (name/section/division) (edition) (addenda) (Code Case(s)) (Code Class)

6. ASME Code Section XI applicable for Inservice inspection . 1989 NO -(edition) (addenda) (Code Case(s))

:7. ASME Code Section XI used for repairs, modifications, or replacements 1989 NO -(edition) (addenda) (Code Case(s))

8. Construction Code used for repairs, modifications, or replacements 1971 .S1972 1567,1711- (edition) (addenda) (Code Case(s))

* 9. Design responsibilities ANDERSON GREENWOOD CROSBY

10. Opening pressure 1205 PSIG Blowdown (if applicable) 3 % Set pressure and blowdown adjustmentmade at WYLE LABORATORIES,HUNTSVILLE,AL. using STEAM

(location) (test medium)I1. Description of work: (include name and identifying number of replacement parts) -FLEXIDISC MODIFICATION,

REPAIR AND TESTING MADE AT WYLE LABORATORIES, HUNTSVILLE,AL. USING STEAM. \

12. Remarks THE DISC INSERT WAS REPLACED AND VARIOUS PARTS MODIFIED AS PART OF THE

FLEXIDISC MODIFICATION.

: A 0 1 5 9 3 : Q.C.-434A ' .Form NVR-l (Back) . ;01Sheet523ofQ2

Certificate Holder's Serial Nos. N63790-05-0015

.CERTIFICATE OF COMPLIANCE.

I, Ap~t/ f3 -j-.s, 'certify that the statements made in this report are correct and the repair, modification ozreplacement of the pressure relief device described above conforms to Section XI of the ASME Code and the NationalBoard Inspection Code 'VR' and "NR' rules.National Board Certificate of Authorization No. 75 to 84 to use the 'VR' stamp expires JAN. 14,2007National Board Certificate of Authorization No. 68 to use the NRW' stamp expires DEC.11 ,2006

Date 7-SA , !O(Signed Anderson Greenwood/Crosby . .C / QAMGR.(name of repair organization) (authorized representative) (title)

'CER. . ,CA .TE F .N,,E. T .i2 j~-~,holinga vlidcomision isse by Th'le Nati onal Board of Boiler 'and Pressure Vessel

Insecorand er~ticate of competency issued by the jurisdiction of MASSACHUSETTS ' and employed by .'.HSB-CT of HARTFORD - CT. have

inspected the repair, modification or replacement described in this report on _ __________oj and state that to th,best of my knowledge and belief, this repair, modificatio or replacement has been completed in accordance

of the ASME Codeand the National Board Inspection Code 'VR. and '-N' rules.By signing this certificate,:neithr the undersigned nor my employer makes any warranty, expressed 'or implied, concerning'.:'the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall

-be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with thisInspection.

Date

Signed an e Commissions MA1420 A, N, I: (Inspector) (Nat'l. Bd. (incl. endorsements), and jurisdiction, and no.)

.Jan. 8. 2005 10:26AMNo.1163 P. 2/5

Q.C.-392Sheet I of 2

FOiRM N-2 CERIMFCATE HOLDERS DATA REPORT.FOA LWENICAL

NUCL}EAR PARTS ANDAPURTEINANCES*

As reuiired bV the Provisions of tbe ASME Code, Section IlI Division I - Not to Exceed One Day's Production

1. Manufactured and ceritified by

2 Manufactured for

Anderson Greenwood Crosby, 43 Kendriclk St., Wreniham, MA 02093

(Namc and Address of N Certificate Holder)

EXELON GENERATION

(Name and Address of Purchaser or Owner)

LASALLE STATION3.- Location of InstaUation (Name and Address)

4. Type DS-A-63790-2 REV.- . ASME SA637 GR 718 185,000

_ 2004

(drawing no.) (mat'l. spec. no.) -(tensile strength) (CRN)

(year built)

5. ASME Code, Section III. Division 1. 1971 SUMMER 1972

1

(edition) (addenda date) (class) (Code Case No.)

6. Fabricated in accordance with Const. Spec. (Div. 2 only) R Revision

- Date

(no.)

7. Remarks

8 Nom thickness (in.) - Mi. design thickness (in.) _ Dia. 1I) (ft & in,) - Lengt

overall (ft & in.)

9 When applicable, Certificate Holders' data reports amc attached for each item of this report.

Parn or AppurtenanceSerial Number

(1) N97499-45-0112(2) Nl97499-45-0113(3) N97499-45-0114(4) ,N97499-45-0115- w(5) N97499-45-0116(6) N9749945-0117

(8) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

(9) _(10)(11)(12)(13)(14)(15.)(16)(17)(18)(19)(20)(21)(22)523)'(24)(25)

NationalBoard No

in Numerical Order

. I

Part or AppurtenanceSenal Number

NationalBoard No.

in Numerical Order

("I

.(3(3(3(3~

(3~(3'(43(4)

(4(

!6)_17)_!8)-M'.90G)31)2)3)4)5)6)7)

I)

[)

(43)(44)(45)(46)(4'7)(48)(49)(50)

_

.

1A Design pressure -- psi. Temp. - F Hydro. rest pressure 2370 psig

at temp. 70

(when applicable)

"ipterntil mformidon In the form ot Ulsu. Iketchte. or dnmgS nuy be ued provd () Size s S.ISl

xl il. (2) hirormrtion In Items 2 and 3 on tbis Pata Report

is included on eacb shet, (3) mest sheet is numberd Ai tc nmber of shect is recorded et the top of

Ohh fornm.

- -- This orm (EOOd4O) may bc obtsined frem the Order Dept., ASME, 22 Lae Drive. Box

300. Fairfield. N1 07007-2300

Do F

.Jan. 8. 2005 10:26AM No.1163 P. 3/5

_'s -. o//N7

*e.fCe-ficate Holder's Serial No. N97'499-45-01 12 thru 01 17Form N-2 (Back)


CERTIFICATE OF COMPLIACi

We certify that the statements made in this report are correct and that this (these) DIsc Insertsconforms to the rules of construction of the ASfE Code,-Section m, Division 1.

NPT Certificate of Authorization No. N-1877 Expires Sep. 30, 2004Anderson Greenwood Crosby

Date 5 Fw Zcoq Signed Wrentham, MA by ,-(NPT Certificate Holder) Authorized Representative)

I CERNFCA QE OFISPECTIONi

1, the undersigned, holding a valid commission issued by the National Board of Bogler and Pressure Vessel Inspectors andthe State oe-Preyhw&.of A14 -5 and employed by ABS Grcm Inc.of Houston. Texas have inspected thece items described in this Data Report on

o_-_6_, 2003t1 and state that to the best of myi knowledge and belief, the Certificate Holderhas fabricated these parts or appurtenances in accordance vwith the ASME Code, Section III, Division 1. Each part listed hasbeen authorized for stamping on the date shown above.By sigaing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerningthe equipment described in this Data Report. Furthermore, neither the Inspector nor his employer shall be liable in anymanner for any personal injury or property damage or loss of aly kind arising from or connected with his dspection.

Date _ 2004~ .

Signed [.. < Commissions Itl- L-. AJ(Authorized Inspector) (Nat'). Bd. (ine. endorsenicats) and state or prov. and no)

I)

FORM NIS-2 OWNER'S REPORT OF REPAIRS OR REPLACEMENTSAs Required by the Provisions of ASME Code Section Xl


200 Exelon Way, Kenneth Sauare. PA.. 19348Address


2601 N. 21' Rd. Marseilles. II. 61341Address

Date 05/14/05

Sheet .I of 2

Unit 2


3. Work Performed bTV Maechannicl Malntannnra(Name)

Mechanical Maintenance

Type Code Symbol Stamp N/AAuthorization No. N/AExpiration Date N/A

(Address)4.5.

Identification of System (MS) Main Steam(a) Applicable Construction Code Sect 1i1 19 71 Edition S/72 Addenda, Code Cases 1567 and 1711(b) Applicable Edition of Section Xl Utilized for Repairs or Replacements-19p 89, No Ad, Code Cases N-496-1Identification of Comoonents Renaired or Renlaced. and Reolacement Comnonents6.

Name of Name of Mfrs. Ser. Nat'l Other Year Repaired ASME CodeComponent Mfr. No. Bd. Identification Built Replaced, or Stamped

No. Replacement (Yes or No)Safety Relief Valve AG N63790-00-0014 N/A 2B21-FO13L Replaced N/A

Crosby -Safety Relief Valve AG N63790-00-0013 N/A 2B21-FO13L * Replacement N/A

Crosby or N63790-05- Receipt # 1015930013 (Modified)'

Disc Insert N93185.33-0070 N/A Replaced N/A

Disc Insert AG N9749945-0114 N/A Receipt# 101593 2004 Replacement N/A_____ _____ _____ C rosb y

7.8.

9.

Description of Work Class 1 Repalr & Replacement. * = Per N-5 Code Data Renort on file at LaSalle County Station.Tests Conducted: Hydrostatic I I Pneumatic I _ I Normal Operating Pressure I X I Other Visual

Pressure 1035 psi Test Temp. 155 Deg. FRemarks Valve SN# N63790-05-0013 was refurbished at Wyle Labs with documentation provided under Quality

(Applicable Manufacturer's Data Report to be Attached )Recelot# 101593 and Installedas a replacementforSN# N63790-00-0014 underworkorder#429584. Forthe

remainder of the Repaired. Replaced and ReDlacement Items, see Form NIS-2 Supplemental Sheet on Pages 2 of 2.- Replacement SRV Serial No. was modified due to the Installation of a new flexl-disc seat design.

CERTIFICATION OF COMPLIANCEWe certify that the statements made in the report are correct and these Repalr and Replacement conforms to the rulesof the ASME Code, Section Xl. (repair or replacement)Type Code Symbol Stamp NONE

Certificate of Authorization No.

Signed C :2~Z.

&11A r r%~-. n -MP_ _ _ _____ dLIUI i LdaL N/A

ISI Coordinator Date,"% !; ; . 2005Owner or Owner's Designee, Title


I, Theundersigned, holding a valid commission Issuedby the National Board of Boller and Pressure VesselInspectors and the State or Province of Illinois and employed by The Hartford Steam Boller Insp. & Ins. Co. ofConnecticut have Inspected the components described In this Owner's Report during the period

L2R09 to L2R10and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures described In this Owner's Report In accordance with the requirements of the ASME Code, Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty , expressed or Implied,concerning the examinations and corrective measures described In this Owner's Report. Furthermore, neither theInspector nor his employer shall be liable In any manner foranypersonal Injury or property damage or a loss ofany kind arising from or connected with this Inspection.

Commissions IL 1927InspecXr's Signature National Board, State, Province, and Endorsements

Date __ _____ 2005

1. Owner:

2. Plant:

FORM NIS-2 SUPPLEMENTAL SHEET

Exelon Generation Company (EGC) LLC Sheet 2200 Exelon Way, Kenneth Square, Date 05114/05PA., 19348 Unit

LaSalle County Station2601 N. 21st. Rd.Marseilles, Illinois 61341 W.O. # 4295

of 2

2

584

3. Work Performed by: Mechanical Maint.Name

Mechanical Maintenance

P. 0. No., WR No., etc.

Type Code Symbol Stamp N/AAuthorization No. NIAExpiration Date N/A

4.

5a.

5b.

6.

Address

Identification of System MS (Main Steam)

Applicable Construction Code 71 Edition S72 Addenda

Applicable Edition of Section Xi utilized 89 Edition None Addenda

Identification of Components Repaired or Replaced and Replacement Components.

Name of Name of Manufacturer National Other Year Repaired, ASMEComponent Manufacturer Serial No. Board Identification Built Replaced Code

No. or StampedReplacement (Yes

or No)Valve Body AG Crosby N93183-31- NIA Receipt # Repaired NIA

0002 101593

(1) Hell-Coil AG Crosby N97823-0051 N/A Receipt # 2002 Repaired NIAInsert 101593

(Outlet)

1059 --:-- 1.0 1 5 9 3 :Q.C.-434A

- -Sheet I of2

FORM NVR-1 REPORT OF REPAIR Fx MODIFICATION F.TOR REPLACEMENT FOF NUCLEAR PRESSURE RELIEF DEVICES


43 Kendrick St., Wrentham, MA 02093-(address)

'2. Work performed for EXELON CORPORATION,LASALLE STATION,MARSEILLES,IL.(name and address)

3. Owner EXELON CORPORATION,LASALLE STATION,MARSEILLES,IL.(name)

(address)4. Name, address and identification of nuclear power plant EXELON CORPORATIONLASALLE STATION,

MARSEILLES, IL.



c. Identifying nos. HB-65-BP N63790-05-0013 . _- STEAM 6 R 10 1981(type) (mfr's serial no.) - (Nat'l Bd. No.) (service) (size) (year built)

d. Construction Code ASME III 1971 S1972 1567,1711 1; (name/section/division) (edition) (addenda) (Code Case(s)) (Code Class)

6. ASME Code Section XI applicable for Inservice inspection 1989 NO- . (edition) (addenda) (Code Case(s))

7. ASME Code Section XI used for repairs, modifications, or replacements 1989 NO.(edition) (addenda) (Code Case(s))

8. Construction Code used for repairs, modifications, or replacements 1971 S1972 1567,1711(edition) (addenda) (Code Case(s))

9. Design responsibilities ANDERSON GREENWOOD CROSBY

10. Opening pressure 1195 PSIG Blowdown (if applicable) 3 % Set pressure and blowdown adjustment

made at WYLE LABORATORIES,HUNTSVILLE,AL. using STEAM(location) - (test medium)

11. Description of work: (include name and identifying number of replacement parts) FLEXIDISC MODIFICATION,REPAIR AND TESTING MADE AT WYLE LABORATORIES, HUNTSVILLEAL. USING STEAM.

12. Remarks THE DISC INSERT WAS REPLACED AND VARIOUS PARTS MODIFIED AS PART OF THE

FLEXIDISC MODIFICATION.

Form NVR-1 (Back)Certificate Holder s Serial Nos. N63790-05-0013

I 3 - Q.C.-434ASheet 2 of 2

CERTIFICATE OF COMPLIANCE

1, Ad ,1L ' 7-- certify that the statements made in this report are correct and the repair, modification otreplacement of the pressure relief device described above conforms to Section XI of the ASME Code and the NationalBoard Inspection Code "VRW and 'NR" rules.National Board Certificate of Authorization No. 75 to 84 to use the 'VR' stamp expires JAN. 14,2007National Board Certificate of Authorization No. 68 to use the 'NR' stamp expires DEC.11 ,2006

Date 7-SEP ,ZOO4Signed Anderson Greenwood/Crosby I , r= A OQA MGR.(name of repair organization) (authorized representative) (title)

. . I . .::

'I- ;- .: .

1A I

. : . . : CERTIFICA TE OF INSPECTIN :

'I, '~ /C/6a_ .2 Hi ,holding a valid commission issued by The National Board of Boiler and Pressure Vessel:-.Inspectors and certificate of competency issued by the jurisdiction of - MASSACHUSETIS and employed by'

HSB-CT of ' HARTFORD- CT. have.;inspected the repair, modification or replacement described in this report on , etand state that to thebest of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI'of the ASME Codeand the National Board Inspection Code 'VR' and 'NRn rules.By signing this certificate, neither the undersigned nor my employer makes any warranty,"expressed or implied, concerningthe repair, modification or replacement described in this report.. Furthermore, neither the undersigned nor my employer shallbe liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this'Inspection. ' :

Date ' . S"v3 P

Signed I J PL

.. ep-TM-f -Commissions MA1420 A, N, I

(Nat'l. Bd. (incl. endorsements), and jurisdiction, and no.).,

_

1 '(Inspector)

.Jan. 8. 2005 10:26AM No.1163 P. 2/5


FORM N-. CE~RTCATE HOLDERS' DATA RPORT FOR IDENTICALNUCLEAR PARTS ANDAPPURENANCES*

As reouired bY the Provsion t he the ASME Code, Secton III. Division 1 - Not to Exceed One Day's Producton

1. Manufactured and ceritified by

2 Manrufactured for

Anderson Greenwood Crosby, 43 Kendrick St., Wreabam, MA 02093L(Naru and Address of N Certificate Holder)

EXELON GENJERA77ON(Name and Addres" of Purchaser or Owner)

LASALLE STATION

= _

3 Location of Installatjon(Name and Address)

4. Type DS-A-63790-2 REV.- . ASME SA637 GR 718 185,000 D_ 2004(drawing no.) (mat'l- spec. no.) (tensile streigth) (CRN) (year built)

5. ASME Code, Section III, Division 1. 1971 SUMMER 1972 1(edition) (addenda date) (class) (Code Case No.)

6. Fabncated in accordance with Const. Spec. (Div. 2 only) - Revision - Date(no.)

7. Remarks

8 Nom thiclaxesz (in.) - Min. design thickness (in.) - Dia. ID (ft & in.) - Length overall (ft & in.)9 When applicable, Certificate Holders' data reports are attached for each item of this report.


(1) N97499-45-1I12/ (2) N97499-45-0113

1(3)'-N97499-45-0114 1k(4) N97499-45-0115(5) N97499-45-0116(6) N97499-45-0117(7)(8)(9)(10)(11)(12)(13)(14)(15)(16)(17)(18)(19)(20)(21)(22)(2)'(24)(25)

DratiualBoard IYo

sn Numerical Order. .

__

. .

. . .

_

. . .

. .

_

. .

.

.

.

. . .

.

.

-

. .

. .


(26)_(27)_(28)(29)-(30)

C,(I(I(I

(I

13 1)32)33)

34)35)36)37)38)39)

'40)-tO)41)42)43)

NationalBoard No.

in Niumerical Order

(44)_(45)(46)_(4'7)_(48).(49)(50)_

VI Design pressure - psi. Temp. -__ F Hydro. test pressure 2370 psi9 at temp. 70

J (when applicable)

'. pltmetnn wnformardon in the form ot lsm. aketches. or draw-L5ts sny be Ustd providd (1) slze Is 8-1l2 x It. (2) Irorrnstion In Itewns 2 And 3 on this Data Report

1s included on eadch Aet, (3) each sheet is numbered Wd the numbet of sheets is recorded et the top of tWis form- This tobn (EOOAOd) may be obtained from die Ordef Dept.. ASM E 22 Low Drive. Box 2300. Fairfield. N] 070072300

a, F

Jan. 8. 2005 10:26AM No.1163 P. 3/5

IV77Y7 -9 o/l i Form N-2 (Back)

K)


_Certficate Holder's Serial No. N97499-45-0112 thru 0117

CERTIFICATE OF COLCE

We certify that the statemnents made in this report are correct and that this (these) Disc Insertsconforms to the rules of construction of the ASME Code, Section m, Division 1.

NPT Certificate of Authomzation No. N-1877 Expires Sep.30,2004Anderson Greenwood Crosby v

Date 5_ _ Zco Signed Wrentham, MA by _D (NPT Certificate Holder) Authorized Representative)

I . ..

I CER TFICWT QE INSPECTION

,/

1, the undersigned, holding a valid comml sion issued by the National Board of Boiler and Pressure Vessel Inspectors and

the State e r} of, A1 and employed by ABS Group Inc.of Houston Texas have inspected these items described in this Data Report on

_ _-6_, 200o and state that to the best of my knowledge and belief, the Certificate Holderhas fabricated these parts or appurtenances in accordance with the ASME Code, Section m, Division 1. Each part listed hasbeen authonzed for stamping on the date shown above.

By swgng this certificate, neither the Inspector nor his omployer makes any warranty, expressed or implied, concernn

the equipment described in this Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any

manner for any personal injury or property damage or loss of any kand arisrug from or connected with this inspection.

Date , ,, 0O .

Signed | _ Commissions AiL ,LAC>_ AJ(Authorized Inspector) (Nat'l. Bd. (ind. endorseiants) and state or proa. and no)

FORM NIS-2 OWNER'S REPORT OF REPAIRS OR REPLACEMENTSAs Required by the Provisions of ASME Code Section XI


200 Exelon Way. Kenneth Square. PA.. 19348Address


2601 N. 2111 Rd. Marseilles. II. 61341Address

Date 05/23/05

Sheet 1 of 1

Unit 2


3. Work Performed by_ Mechanical Maintenance Type Code Symbol Stamp N/AAuthorization No. N/A(Name)


Expiration Date_ N/A

4.5.

Identification of System (MS) Main Steam(a) Applicable Construction Code Sect ill 19 71 Edition W'71 Addenda, Code Cases NO(b) Appilcable Edition of Section XI Utilized for Repairs or Replacements-19 89, No Ad, Code Cases NO. _ - . .- n_ _--- _- _s _____ -s__ __ ____ _-t_|___ - - _

b.Identification oT Gom )onenms Repairea or Keplacea, ana Kepiacement Components ______Name of Name of Mfrs. Ser. Nat'l Other Year Repaired ASME Code

Component Mfr. No. Bd. Identification Built Replaced, or StampedNo. Replacement (Yes or No)

MSIV Stem/Stem- Rockwell N/A 2B21-F028D Replaced N/ADisk Assy. Corp

MSIV Stem/Stem- Flowserve 76366-3 N/A Size 26 Figure 2004 Replacement N/ADisk Assy. Corp 1612JMMNTY

ValveW.O. # 659252

7.8.

Description of Work: Class 1 Replacement. * = Per N-5 Code Data Report on file at LaSalle County Station.Tests Conducted: Hydrostatic I I Pneumatic IlI Normal Operating Pressure I X I Other Visual

Pressure 1035 asI Test Temp. _155 Deg. FRemarks: The old Main Steam Isolation Valve (MSIV) main disk assembly removed from MSIV 1B21-F028D

(Appilcable Manufacturer's Data Report to be Attached )was refurbished with a new style Stem/Stem-DIsk Assembly with SN# 76366-3 under work order # 659252. This

9.

niwv refurbished disk assemblv was Installed and tested In MSIV2B21-F028D under Work Order# 515539.

CERTIFICATION OF COMPLIANCEWe certify that the statements made In the report are correct and this Replacementof the ASME Code, Section XI. (repair or replaType Code Symbol Stamp NONE

~conforms to the rulescement)

Criiaeof Au NoSegneorizado

Signedf

N/A _Expiration Date N/A

ISI Coordinator Date ? it . 2005Owner or Owner's Designee, Title


I, The undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of Ilinols - and employed by The Hartford Steam Boiler Inso. & Ins. Co. ofConnecticut have Inspected the components described in this Owner's Report during the period

L2R09 to L2R10and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures described In this Owner's Report In accordance with the requirements of the ASME Code, Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty , expressed or Implied,concerning the examinations and corrective measures described In this Owner's Report. Furthermore, neither theInspector nor his employer shall be liable In any -manner for any personal Injury or property damage or a loss ofany kind arl rom or connected with this spectlon.

API .0 ommiss ions IL 1927lnspectorfignature National Board, State, Province, and Endorsements

Date_ _ _ _ _ 205



200 Exelon Way, Kenneth Sauare. PA., 19348

Date 05123105

Address2. Plant LaSalle Countv Nuclear Station

Sheet 1 of I

Unit 2


Name2601 N. 21" Rd. Marseilles. II. 61341

Address

3. Work Performed by_

IrI -+IIPTIA- So C

Mechanical Maintenance(Name)


s~oe mmURS Susn CA-

Type Code Symbol Stamp NIAAuthorization No. NIAExpiration Date NIA

4.5.

IUVIR111IIL0d&UH I UI QYILVI II IffK11 iRi0lil .~LVdI I

(a) Applicable Construction Code Sect 111.19 71 Edition W'71 Addenda, Code Cases NO(b) Applicable Edition of Section XI Utilized for Repairs or Replacements-19 89, No Ad, Code Cases NO

6. Identification of Com onents Repalred or Replaced, and Replacement ComponentsName of Name of Mfrs. Ser. Nat'l Other Year Repaired ASME Code

Component Mfr. No. Bd. Identification Built Replaced, or StampedNo. _ Replacement (Yes or No)

MSIV Stem/Stem- Rockwell N/A 2B21-FO28B * Replaced N/ADisk Assy. Corp

MSIV Stem/Stem- Flowserve 76366-5 N/A Size 26 Figure 2004 Replacement N/ADisk Assy. Corp 1612JMMNTY

ValveW.O. # 659253

8.

9.

Description of Work: Class I Replacement. * = Per N-5 Code Data Renort on file at LaSalle County Station.Tests Conducted: Hydrostatic I I Pneumatic I I Normal Operating Pressure l X I Other Visual

Pressure 1035 osi Test Temp. _155 Deg. FRemarks: The old Main Steam Isolation Valve WMSIV) main disk assembly removed from MSIV 1 B21 .F028C

(Applicable Manufacturer's Data Report to be Attached )was refurbished with a new style Stem/Stem-Disk Assembly with SN# 76366-5 under work order # 659253. Thisnewly refurbished disk assembly was Installed and tested In MSIV 2B21 -F028B under Work Order # 515542.

CERTIFICATION OF COMPLIANCEWe certify that the statements made In the report are correct and this Replacement conforms to the rulesof the ASME Code, Section Xl. (repair or replacement)Type Code Symbol Stamp NONE

Certificate of Authorization No. - N/A -Expiration Date NIA

ISI Coonrdinator Date A f 0 le 'Z . 2005Owner or Owner's Designee, Title


I, The undersigned, holding a valid commission Issued by the National Board of Boller and Pressure VesselInspectors and the State or Province of Ilinols and employed by The Hartford Steam Boller Insp. & Ins. Co. ofConnecticut have inspected the components described In this Owner's Report during the period

L2R09 to L2R10and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correctivemeasures described In this Owners Report In accordance with the requirements of the ASME Code, Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or Implied,concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither theInspector nor his employer shall be liable In any manner for any personal Injury or property damage or a loss ofany kind arl g from or connected with th Inspection.

AO" "& Commissions IL 1927InspersSnature National Board, State, Province, and Endorsements

Date _____ 0 2005



200 Exelon Way. Kenneth Square. PA., 19348Address

Plant LaSalle County Nuclear Station

Date 04118105

Sheet 1 of I

Unit 22.Name

2601 N. 211" Rd. Marseilles, II. 61341(Address)

W.O. # 544418Repair Organization, P.O. No., Job No., etc.

Type Code Symbol Stamp NIAAiuthnrizatinn N. NIA

3. Work Performed blV Uaehannc.l antn.ance-(Name)


Expiration Date_ NIA

4.S.

Identification of System I(RD) Control Rod Drive(a) Applicable Construction Code.ASME Sect liI 19 71 Edition No Addenda, Code Cases 1361-1. & 1361-2(b) Applicable Edition of Section XI Utilized for Repairs or Replacements-1989 , No Ad, Code Cases NoneIde

Documents

LaSalle County Station, Unit 2, Post-Outage 90-Day ...County Station Unit 2. It started February 7, 2005 and ended March 16, 2005. This refuel outage was the first scheduled for the