Crystal River, Unit 3 - Inservice Inspection Program Plan ... · Document No.: PENO1.G03 Crystal River Unit 3 ISI Program Document No.: PEN01.G03 PrgrssEnergykf CRYSTAL RIVER NUCLEAR

OProgress EnergyCrystal River Nuclear PlantDocket No. 50-302Operating License No. DPR-72

Ref: 10 CFR 50.55a

December 21, 20073F 1207-04

U.S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, DC 20555

Subject: Crystal River Unit 3 - Inservice Inspection Program Plan, Ten Year Update

Dear Sir:

Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc., is hereby submitting theCrystal River Unit 3 (CR-3) Inservice Inspection (ISI) Program Plan for the fourth ten year interval. TheISI Program Plan has been updated to meet the requirements of the 2001 Edition through the 2003 Addendaof the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, inaccordance with ASME Section XI Article IWA-2400, except where specific relief from the B&PV Codehas been requested, pursuant to 1OCFR50.55a(3). The third ten year interval will end on August 13, 2008,and the fourth ten year interval will begin on August 14, 2008.

ASME Code Cases approved by the NRC, as identified in Regulatory Guide 1.147, and which areapplicable to CR-3, along with the specific Relief Requests are identified in the ISI Program Plan.

No regulatory commitments are being made in this submittal.

If you should have any questions regarding this submittal, please contact Mr. Dennis Herrin, ActingSupervisor, Licensing & Regulatory Programs, at (352) 563-4633.

Sincerely,

Stephen J. Cahill

Engineering Manager

SJC/seb

Attachment: Crystal River Unit 3 Inservice Inspection Program Plan - Fourth Ten Year Interval

xc: NRR Project ManagerRegional Administrator, Region IISenior Resident Inspector

Progress Energy Florida, Inc. -7Crystal River Nuclear Plant15760 W Powerline StreetCrystal River, FL 34428 ' b

PROGRESS ENERGY FLORIDA, INC.

CRYSTAL RIVER - UNIT 3

DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72

ATTACHMENT

CRYSTAL RIVER UNIT 3 INSERVICE INSPECTION PROGRAM PLAN

FOURTH TEN YEAR INTERVAL

Crystal River Unit 3 151 Program Document No.: PENO1.G03Crystal River Unit 3 ISI Program Document No.: PEN01.G03

PrgrssEnergykf

CRYSTAL RIVER NUCLEAR PLANT UNIT 3

ISI PROGRAM PLANFOURTH TEN-YEAR INSPECTION INTERVAL

Commercial Service Date:

Unit 3 - 03/13/77

Crystal River Nuclear Plant Unit 315760 West Power Line StreetCrystal River, FL 34428-6708

Progress Energy Service Company, LLC410 South Wilmington Street

Raleigh, NC 27601-1748

Prepared By:Alion Science and Technology Corporation

Engineering and Technical Programs DivisionWarrenville, Illinois

ALIONSCIENCE AND TECHNOLOGY

i

ISI Program PlanCrystal River Unit 3, Fourth Interval

REVISION CONTROL SHEET

Major changes should be outlined within the table below. Minor editorial and formattingrevisions are not required to be logged.

REVISION DATE REVISION SUMMARY

0 09/26/07 Initial issuance. (This ISI Program Plan was developed by AlionScience and Technology Corporation as part of the Fourth Interval ISIProgram update.)

Prepared: S. Coleman Reviewed: K. Johnson Approved: D. Lamond

Notes: 1. This ISI Program Plan (Sections 1 - 9 inclusive) is controlled by the Crystal RiverUnit 3 Engineering Programs Group.

2. Revision 0 of this document was issued as the Fourth Interval ISI Program Plan andwas submitted to the USNRC for review, including approval of the initial Fourth ISIInterval Relief Requests. Future revisions of this document made within the FourthISI Interval will be maintained and controlled at Crystal River Unit 3; however, theyare not required to be and will not be submitted to the USNRC for approval. Theexception to this is that new or revised Relief Requests shall be submitted to theUSNRC for safety evaluation and approval.

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REVISION SUMMARY

SECTION EFFECTIVE PAGES REVISION DATE

Preface i to v 0 09/26/07

1.0 1-1 to 1-18 0 09/26/07

2.0 2-1 to 2-43 0 09/26/07

3.0 3-1 to 3-2 0 09/26/07

4.0 4-1 to 4-2 0 09/26/07

5.0 5-1 0 09/26/07

6.0 6-1 to 6-2 0 09/26/07

7.0 7-1 to 7-20 0 09/26/07

8.0 8-1 to 8-2 0 09/26/07

9.0 9-1 to 9-4 0 09/26/07

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TABLE OF CONTENTS

SECTION DES CRIPTION PAGE

1.0 INTRODUCTION AND BACKGROUND ..................................................................... 1-11.1 Introduction1.2 Background1.3 First Interval ISI Program1.4 Second Interval ISI Program1.5 Third Interval ISI Program1.6 Fourth Interval ISI Program1.7 First Interval CISI Program1.8 Second Interval CISI Program1.9 Code of Federal Regulations 10CFR50.55a Requirements1.10 Code Cases1.11 Relief Requests

2.0 BASIS FOR INSERVICE INSPECTION PROGRAM ................................................... 2-12.1 ASME Section XI Examination Requirements2.2 Augmented Examination Requirements2.3 System Classifications and P&ID Boundary Drawings2.4 ISI Isometric and Component Drawings for Nonexempt ISI Class Components

and Supports2.5 Technical Approach and Positions

3.0 CO M PO NEN T ISI PLA N ................................................................................................. 3-13.1 Nonexempt ISI Class Components3.2 Risk-Informed Examination Requirements

4.0 SU PPO R T ISI PL A N ....................................................................................................... 4-14.1 Nonexempt ISI Class Supports4.2 Snubber Examination and Testing Requirements

5.0 SYSTEM PRESSURE TESTING ISI PLAN ................................................................. 5-15.1 ISI Class Systems5.2 Risk-Informed Examination of Socket Welds

6.0 CO N TA IN M EN T ISI PLA N ........................................................................................... 6-16.1 Nonexempt CISI Class Components6.2 Augmented Examination Areas6.3 Component Accessibility6.4 Responsible Individual and Engineer

7.0 COM PONENT SUM M ARY TABLES ........................................................................... 7-17.1 Inservice Inspection Summary Tables

8.0 RELIEF REQUESTS FROM ASME SECTION XI ........................................................ 8-19.0 R E FE R E N C E S ................................................................................................................ 9-1

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ISI Program Plan

Crystal River Unit 3, Fourth Interval

TABLE OF CONTENTS

TABLES DESCRIPTION PAGE

1.1-1 FOURTH ISI INTERVAL/PERIOD/OUTAGE MATRIX (FOR ISI CLASS 1, 2, AND 3COMPONENT EXAMINATIONS) ................................................................................ 1-2

1.1-2 SECOND CISI INTERVAL/PERIOD/OUTAGE MATRIX (FOR CISI CLASS MCCOMPONENT EXAMINATIONS) ................................................................................ 1-3

1.1-3 SECOND CISI INTERVAIJPERIOD/OUTAGE MATRIX (FOR CISI CLASS CCCOMPONENT EXAMINATIONS) ................................................................................ 1-4

1.9-1 CODE OF FEDERAL REGULATIONS 10CFR50.55a REQUIREMENTS .................. 1-92.3-1 P&ID BOUNDARY DRAWINGS ................................................................................ 2-152.4-1 ISI COMPONENT DRAWINGS .................................................................................. 2-182.4-2 CLASS 1 ISI ISOMETRIC PIPING DRAWINGS ........................................................ 2-192.4-3 CLASS I ISI ISOMETRIC HANGER DRAWINGS .................................................... 2-212.4-4 CLASS 2 ISI ISOMETRIC PIPING DRAWINGS ........................................................ 2-222.4-5 CLASS 2 ISI ISOMETRIC HANGER DRAWINGS .................................................... 2-262.4-6 CLASS 3 ISI ISOMETRIC HANGER DRAWINGS .................................................... 2-302.4-7 CISI REFERENCE DRAWINGS .................................................................................. 2-322.4-8 ASME SECTION XI UT CALIBRATION BLOCKS ................................................... 2-352.5-1 TECHNICAL APPROACH AND POSITIONS INDEX .............................................. 2-417.1-1 INSERVICE INSPECTION SUMMARY TABLE ......................................................... 7-47.1-2 INSERVICE INSPECTION SUMMARY TABLE PROGRAM NOTES ..................... 7-208.0-1 RELIEF REQ UEST IN D EX ............................................................................................ 8-2

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1.0 INTRODUCTION AND BACKGROUND

1.1 Introduction

This Inservice Inspection (ISI) Program Plan details the requirements for theexamination and testing of ISI Class 1, 2, 3, MC, and CC pressure retainingcomponents, supports, containment structures, and post-tensioning systems atCrystal River Unit 3 (CR3). This ISI Program Plan also includes ContainmentInservice Inspection (CISI), Risk-Informed Inservice Inspection (RISI),Augmented Inservice Inspections (AUG), and System Pressure Testing (SPT)requirements imposed on or committed to by CR3. At CR3, the Inservice Testing(IST) Program is maintained and implemented separately from the ISI Program.The IST Basis Document and Program Plan contain all applicable inservicetesting requirements.

The Fourth ISI Interval is effective from August 14, 2008 through August 13,2018 for CR3. With the update to the ISI Program for the Fourth ISI Interval forClass 1, 2, and 3 components, including their supports, the CISI Program is alsobeing updated to its Second Interval for Class MC and CC components. Thisupdate will enable all of the ISI and CISI Program components / elements to bebased on the same effective Edition and Addenda of the American Society ofMechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, aswell as share a common interval start and end date. The common ASME Code ofRecord for the Fourth ISI Interval and the Second CISI Interval is the 2001Edition through the 2003 Addenda.

Paragraph IWA-2430(d)(1) of ASME Section XI allows an inspection interval tobe extended or decreased by as much as one year, and Paragraph IWA-2430(e)allows an inspection interval to be extended when a unit is out of servicecontinuously for six months or more. The extension may be taken for a period oftime not to exceed the duration of the outage. See Tables 1.1-1, 1.1-2, and 1.1-3for intervals, periods, and extensions that apply to CR3's Fourth ISI Interval andSecond CISI Interval.

The Fourth ISI Interval and Second CISI Interval are divided into two or threeinspection periods as determined by calendar years within the intervals. Tables1.1-1, 1.1-2, and 1.1-3 identify the period start and end dates for the Fourth ISIInterval and the Second CISI Interval as defined by Inspection Program B. Inaccordance with Paragraph IWA-2430(d)(3), the inspection periods specified inthese Tables may be decreased or extended by as much as 1 year to enableinspections to coincide with CR3's refueling outages.

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TABLE 1.1-1

FOURTH ISI INTERVAL/PERIOD/OUTAGE MATRIX(FOR ISI CLASS 1, 2, AND 3 COMPONENT EXAMINATIONS)

Interval Period OutagesStart Date to Start Date to End Date Projected Outage Outage

End Date1 Start Date.or NumberOutage Duration

Scheduled R16ist 11/09

4 th 08/14/08 to 08/13/1108/14/08 to 08/13/18

Scheduled R172 nd 11/11

08/14/11 to 08/13/15 Scheduled R1811/13

Scheduled R193 rd 11/15

08/14/15 to 08/13/18 Scheduled R2011/17

Note 1: The end of the CR3 Second ISI Interval was extended from March 13, 1997 toAugust 13, 1998 due to an extended outage (see Section 1.4). As required byIWA-2430(e), the original pattern of intervals was extended accordingly, thusaffecting the start date of the Fourth ISI Interval.

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TABLE 1.1-2

SECOND CISI INTERVAL/PERIOD/OUTAGE MATRIX(FOR CISI CLASS MC COMPONENT EXAMINATIONS)

Interval Period OutagesStart Date to Start Date to End Date Projected Outage Outage

End Date1 Start Date or NumberOutage Duration

Scheduled R16S1st 11/09

2 nd 08/14/08 to 08/13/11

08/14/08 to 08/13/18

Scheduled R172 nd 11/11

08/14/11 to 08/13/15 Scheduled R1811/13

Scheduled R193 rd 11/15

08/14/15 to 08/13/18 Scheduled R20L 11/17

Note 1: The CR3 First CISI Interval was scheduled to end September 8, 2008. In order tofacilitate the CISI Program sharing a common interyal start and end date with the ISIProgram, the Second CISI Interval is adjusted by starting the interval 26 days earlyas allowed by IWA-2430(d)(1). This means that for the remainder of the SecondCISI Interval, 339 days are available to use under the IWA-2430(d) extension.

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1Sf Program PlanCrystal River Unit 3, Fourth Interval

TABLE 1.1-3

SECOND CISI INTERVAL/PERIOD/OUTAGE MATRIX(FOR CISI CLASS CC COMPONENT EXAMINATIONS)

Interval 5-Year Period OutagesStart Date to Rolling Exam # - Date Projected Outage

End Date1 (2 Year Window) Outage Start NumberDate orOutage

Duration

x xScheduled R16

2 nd 3rd Concrete Insp. - 09/07/11 (Cat. L-A) Scheduled R1708/14/08 to08/13/18 (09/07/10 to 09/06/12)2 11/11

9th Tendon Surv. - 12/07/11 (Cat. L-13)(12/07/10 to 12/07/12)3

Scheduled R18

4th Concrete Insp. - 09/07/16 (Cat. L-A) Scheduled R19(09/07/15 to 09/06/17)2 11/15

10tb Tendon Surv. - 12/07/16 (Cat. L-B) Scheduled R20(12/07/15 to 12/07/17)3 11/17

Note 1: The CR3 First CISI Interval was scheduled to end September 8, 2008. In order tofacilitate the CISI Program sharing a common interval start and end date with the ISIProgram, the Second CISI Interval is adjusted by starting the interval 26 days early asallowed by IWA-2430(d)(1). This means that for the remainder of the Second CISIInterval, 339 days are available to use under the IWA-2430(d) extension.

Note 2: The CISI Interval for Class CC, Examination Category L-A, Concrete Componentsparallels the CISI Interval for Class MC Components, as well as the ISI interval, forthe purpose of establishing the ten-year start and end dates and the applicable Codeof Record. The actual inspection schedule however is based on a rolling 5 yearfrequency (+/- 1 year) from the date of completion of the original examinations(09/07/01) performed during the initial September 9, 1996 - September 8, 2001Rulemaking implementation period. The rolling 5 year inspection schedule forcontainment concrete systems is in accordance with the Inservice InspectionSchedule specified in IWL-2400 as modified by the initial regulatory rulemaking.

Note 3: The CISI Interval for Class CC components, Examination Category L-B, Unbonded Post-Tensioning Components, schedule for inspection and testing is based on a rolling 5 yearfrequency (+/- 1 year) from the date of completion of the original Containment StructuralIntegrity Test. The initial Containment Structural Integrity Test was completed December 7,1976. The rolling 5 year inspection schedule for post-tensioning systems is in accordance withthe Inservice Inspection Schedule specified in IWL-2400 as modified by the initial regulatoryrulemaking

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1.2 Background

The Florida Power Corporation (FPC), now known commercially as ProgressEnergy Service Company, LLC, obtained Construction Permits to build CrystalRiver Unit 3 on September 25, 1968. The Docket Number assigned to CR3 is50-302. After satisfactory plant construction and preoperational testing wascompleted, CR3 was granted a full power operating license on January 28, 1977,DPR-72, and subsequently commenced commercial operation on March 13, 1977.

CR3's Reactor Coolant piping was designed, fabricated, and erected inaccordance with USAS B31.7, 1968 Draft Edition as documented in FSARSection 1.3.2.8. CR3's power piping was designed in accordance with USASB31.1, 1967 Edition and fabricated/erected in accordance with B31.7-1969Edition as documented in FSAR Section 1.3.2.12. The Nuclear Steam SupplySystem (NSSS) was furnished by Babcock & Wilcox (B&W) and has two ReactorCoolant loops. The Architect Engineer for CR3 during construction was GilbertCommonwealth. The reactor vessel, steam generators and pressurizer weredesigned to meet the requirements of ASME Section II, 1965 Edition through theSummer 1967 Addenda. FPC's Nuclear Engineering Organization used UnitedStates Nuclear Regulatory Commission (USNRC) Regulatory Guide 1.26 todetermine the ASME Code classification for Class 2 and 3 Systems, Structures,and Components.

Certain limitations are likely to occur due to conditions such as accessibility,geometric configuration, and/or metallurgical characteristics. For some inspectioncategories, an alternate component may be selected for examination and the codestatistical and distribution requirements can still be maintained. If Code requiredexamination criteria cannot be met, a relief request will be submitted inaccordance with 10CFR50.55a.

1.3 First Interval ISI Program

Pursuant to the Code Of Federal Regulations (CFR), Title 10, Part 50, Section55a, Codes and standards, (10CFR50.55a), CR3 was required to meet therequirements of Paragraph (g), Inservice inspection requirements; of that section.

Specifically, Paragraph 1OCFR50.55a(g)(4)(i) calls for the inservice inspectionrequirements of the initial 120 month inspection interval to comply with therequirements of the latest Edition and Addenda of ASME Section XI referenced inParagraph (b) of 10CFR50.55a on the date 12 months prior the date of issuance ofthe operating license, subject to the limitations and modifications listed in10CFR50.55a(b).

CR3 was issued an operating license on January 28, 1977. The version of10CFR50.55a in effect 12 months prior to this date referenced Section XI, 1974Edition with Addenda through the Summer 1975 (74S75) of the ASME Boiler

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and Pressure Vessel (B&PV) Code, ASME Section XI, titled Rules for InserviceInspection of Nuclear Power Plant Components. The inservice inspectionrequirements applicable to nondestructive examination and system pressuretesting for the First Inservice Inspection Program were based on these rules.

The CR3 First ISI Interval was effective from March 13, 1977 to March 13, 1987.

1.4 Second Interval ISI Program

Pursuant to 1OCFR50.55a(g), CR3 was required to update the ISI Program at theend of the first ten-year inspection interval. The ISI Program was required tocomply with the latest Edition and Addenda of ASME Section XI incorporated byreference in 1OCFR50.55a twelve months prior to the start of the Second Intervalper 1OCFR50.55a(g)(4)(ii).

This ISI Program Plan was developed in accordance with the requirements of1OCFR50.55a and the 1983 Edition through the Summer 1983 Addenda of ASMESection XI. This ISI Program Plan addressed Subsections IWA, lWB, IWC, IWD,and LWF of ASME Section XI, and utilized Inspection Program B as definedtherein.

The CR3 Second ISI Interval started March 14, 1987 and was scheduled to endMarch 13, 1997. Due to an extended outage which occurred from September 4,1996 until February 5, 1998, the Second ISI Interval end date was extended toAugust 13, 1998 in accordance with the 83S83 Edition of ASME Section XI,subarticle IWA-2400(c).

1.5 Third Interval ISI Program

Pursuant to 1OCFR50.55a(g), CR3 was required to update the ISI Program at theend of the second ten-year inspection interval. The ISI Program was required tocomply with the latest Edition and Addenda of ASME Section XI incorporated byreference in 1OCFR50.55a twelve months prior to the start of the Third ISIInterval per 1OCFR50.55a(g)(4)(ii).

This ISI Program Plan was developed in accordance with the requirements of10CFR50.55a and the 1989 Edition, No Addenda of ASME Section XI. This ISIProgram Plan addressed Subsections IWA, IWB, IWC, TWD, and IWF of ASMESection XI, and utilized Inspection Program B as defined therein.

The CR3 Third ISI Interval was effective from August 14, 1998 through August13, 2008.

1.6 Fourth Interval ISI Program

Pursuant to 1OCFR50.55a(g), licensees are required to update their ISI Programsto meet the requirements of ASME Section XI once every ten years or inspection

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interval. The ISI Program is required to comply with the latest Edition andAddenda of the Code incorporated by reference in 1OCFR50.55a twelve (12)months prior to the start of the interval per 10CFR50.55a(g)(4)(ii). The start ofthe Fourth ISI Interval is August 14, 2008 for CR3. Based on this date, the latestEdition and Addenda of the Code referenced in 1OCFR50.55a(b)(2) twelvemonths prior was the 2001 Edition through the 2003 Addenda.

The CR3 Fourth Interval ISI Program Plan was developed in accordance with therequirements of 10CFR50.55a and the 2001 Edition through the 2003 Addenda ofASME Section XI, subject to the limitations and modifications contained withinParagraph (b) of the regulation. These limitations and modifications are detailedin Table 1.9-1 of this section. This ISI Program Plan addresses Subsections IWA,IWB, IWC, IWD, IWF, Mandatory Appendices, approved ASME Code Cases,approved alternatives through relief requests and Safety Evaluation Reports(SER's), and utilizes Inspection Program B as defined therein.

CR3 previously adopted the EPRI Topical Report TR- 112657, Rev. B-Amethodology, which was supplemented by Code Case N-578-1, for implementingrisk-informed inservice inspections. The RISI Program will be in effect for theentire Fourth ISI Interval. This approach replaces the categorization, selection,and examination volume requirements for portions of ASME Section XIExamination Categories B-F and B-J applicable to CR3 with ExaminationCategory R-A as defined in Code Case N-578-1. Implementation of the RISIProgram is in accordance with Relief Request 07-001-I.

1.7 First Interval CISI Program

CISI examinations were originally invoked by amended regulations containedwithin a Final Rule issued by the USNRC. The amended regulation incorporatedthe requirements of the 1992 Edition through the 1992 Addenda of the ASMESection XI, Subsections IWE and 1WL, subject to specific modifications that wereincluded in Paragraphs 1OCFR50.55a(b)(2)(ix) and 1OCFR50.55a(b)(2)(x).

The final rulemaking was published in the Federal Register on August 8, 1996 andspecified an effective date of September 9, 1996. Implementation of theSubsection IWE and IWL Program from a scheduling standpoint was driven bythe five year expedited implementation period per 1OCFR50.55a(g)(6)(ii)(B),which specified that the examinations required to be completed by the end of thefirst period of the First Inspection Interval (per Table IWE-2412-1) be completedby the effective date (by September 9, 2001).

ASME Section XI Subsections IWE, IWL, Mandatory Appendices, approvedASME Code Cases, and approved alternatives through relief requests and SER'swere developed to implement these requirements. The First CISI Interval for CR3was effective from September 9, 1996 through September 8, 2008.

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1.8 Second Interval CISI Program

Pursuant to 1OCFR50.55a(g), licensees are required to update their CISI Programsto meet the requirements of ASME Section XI once every ten years or inspectioninterval. The CISI Program is required to comply with the latest Edition andAddenda of the Code incorporated by reference in 10CFR50.55a twelve (12)months prior to the start of the interval per 1OCFR50.55a(g)(4)(ii). The start ofthe Second CISI Interval is August 14, 2008. Based on this date, the latest Editionand Addenda of the Code referenced in 10CFR50.55a(b)(2) twelve months priorwas the 2001 Edition through the 2003 Addenda.

The First CISI Interval was scheduled to end on September 8, 2008. The SecondInterval CISI Program will commence 26 days early to allow for common intervalstart/end dates and a common Code of record between the ISI and CISI Programs.ASME Section XI Paragraph IWA-2430(d) allows each inspection interval to bereduced or extended by as much as one year so long as adjustments do not causesuccessive intervals to be altered by more than one year from their originalpattern.

Since the provisions of Paragraph JIWA-2430(d) have been adhered to as required,a relief request under the provision of 1OCFR50.55a(a)(3)(i) is not required. Assuch, the CR3 Second CISI Interval will be effective from August 14, 2008through August 13, 2018, which directly coincides with the Fourth ISI Intervalstart and end dates.

The CR3 Second Interval CISI Program Plan was developed in accordance withthe requirements of 10CFR50.55a and the 2001 Edition through the 2003Addenda of ASME Section XI, subject to the limitations and modificationscontained within Paragraph (b) of the regulation. These limitations andmodifications are detailed in Table 1.9-1 of this section.

This CISI Program Plan addresses Subsections IWE, IWL, MandatoryAppendices, approved ASME Code Cases, approved alternatives through reliefrequests and SER's, and utilizes Inspection Program B as defined therein.

1.9 Code of Federal Regulations 1OCFR50.55a Requirements

There are certain Paragraphs in 10CFR50.55a that list the limitations,modifications, and/or clarifications to the implementation requirements of ASMESection XI. These Paragraphs in 1OCFR5O.55athat are applicable to CR3 aredetailed in Table 1.9-1.

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TABLE 1.9-1CODE OF FEDERAL REGULATIONS 10CFR50.55a REQUIREMENTS

10CFR50.55a Paragraphs Limitations, Modifications, and Clarifications

1OCFR50.55a(b)(2)(viii)(E) (CISI) Examination of concrete containm ents: For Class CCapplications, the licensee shall evaluate the acceptability ofinaccessible areas when conditions exist in accessible areasthat could indicate the presence of or result in degradation tosuch inaccessible areas. For each inaccessible area identified,the licensee shall provide the following in the ISI SummaryReport required by IWA-6000:(1) A description of the type and estimated extent of

degradation, and the conditions that led to thedegradation;

(2) An evaluation of each area, and the result of theevaluation, and;

(3) A description of necessary corrective actions.10CFR50.55a(b)(2)(viii)(F) (CISI) Examination of concrete containments: Personnel that

examine containment concrete surfaces and tendon hardware,wires, or strands must meet the qualification provisions inIWA-2300. The "owner-defined" personnel qualificationprovisions in IWL-2310(d) are not approved for use.

1OCFR50.55a(b)(2)(viii)(G) (CISI) Examination of concrete containments: Corrosionprotection material must be restored following concretecontainment post-tensioning system repair and replacementactivities in accordance with the quality assurance programrequirements specified in IWA-1400.

10CFR50.55a(b)(2)(ix)(A) (CISI) Examination of metal containments and the liners ofconcrete containments: For Class MC applications, thelicensee shall evaluate the acceptability of inaccessible areaswhen conditions exist in accessible areas that could indicatethe presence of or result in degradation to such inaccessibleareas. For each inaccessible area identified, the licensee shallprovide the following in the ISI Summary Report as requiredby IWA-6000:(1) A description of the type and estimated extent of

degradation, and the conditions that led to thedegradation;

(2) An evaluation of each area, and the result of theevaluation, and;

1 (3) A description of necessary corrective actions.

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1OCFR50.55a(b)(2)(ix)(B) (CISI) Examination of metal containments and the liners ofconcrete containments: When performing remotely the visualexaminations required by Subsection IWE, the maximumdirect examination distance specified in Table IWA-2210-1may be extended and the minimum illumination requirementsspecified in Table IWA-2210-1 may be decreased providedthat the conditions or indications for which the visualexamination is performed can be detected at the chosendistance and illumination.

IOCFR5O.55a(b)(2)(ix)(F) (CISI) Examination of metal containments and the liners ofconcrete containments: VT-1 and VT-3 examinations must beconducted in accordance with IWA-2200. Personnelconducting examinations in accordance with the VT-1 or VT-3examination method shall be qualified in accordance withIWA-2300. The "owner-defined" personnel qualificationprovisions in 1WE-2330(a) for personnel that conduct VT-1and VT-3 examinations are not approved for use.

1OCFR5O.55a(b)(2)(ix)(G) (CISI) Examination of metal containments and the liners ofconcrete containments: The VT-3 examination method mustbe used to conduct the examinations in Items El.12 and El.20of Table IWE-2500-1 and the VT-1 examination method mustbe used to conduct the examination in Item E4.1 I of TableIWE-2500-1. An examination of the pressure-retaining boltedconnections in Item El. 11 of Table IWE-2500-1 using theVT-3 examination method must be conducted once eachinterval. The "owner-defined" visual examination provisionsin IWE-2310(a) are not approved for use for VT-I and VT-3examinations.

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10CFR50.55a(b)(2)(ix)(H) (CISI) Examination of metal containments and the liners ofconcrete containments: Containment bolted connections thatare disassembled during the scheduled performance of theexaminations in Item E1. 11 of Table IWE-2500-1 must beexamined using the VT-3 examination method. Flaws ordegradation identified during the performance of a VT-3examination must be examined in accordance with the VT-Iexamination method. The criteria in the material specificationor IWB-3517.1 must be used to evaluate containment boltingflaws or degradation. As an alternative to performing VT-3examinations of containment bolted connections that aredisassembled during the scheduled performance of Item El. 11,VT-3 examinations of containment bolted connections may beconducted whenever containment bolted connections aredisassembled for any reason.

10CFR50.55a(b)(2)(ix)(I) (CISI) Examination of metal containments and the liners ofconcrete containments: The ultrasonic examinationacceptance standard specified in IWE-3511.3 for Class MCpressure-retaining components must also be applied to metallicliners of Class CC pressure-retaining components.

10CFR50.55a(b)(2)(xi) (ISI) Class 1 piping: Licensees may not apply IWB-1220,"Components Exempt from Examination," of Section XI, 1989Addenda through the latest Edition and Addenda incorporatedby reference in Paragraph (b)(2) of this section, and shall applyIWB-1220, 1989 Edition.

1OCFR50.55a(b)(2)(xii) (ISI) Underwater Welding: The provisions in IWA-4660,"Underwater Welding," of Section XI, 1997 Addenda throughthe latest Edition and Addenda incorporated by reference inParagraph (b)(2) of this section, are not approved for use onirradiated material.

1OCFR50.55a(b)(2)(xviii)(A) (ISI) Certification of NDEpersonnel: Level I and IInondestructive examination personnel shall be recertified on a3-year interval in lieu of the 5-year interval specified in the1997 Addenda and 1998 Edition of IWA-2314, andIWA-2314(a) and IWA-2314(b) of the 1999 Addenda throughthe latest Edition and Addenda incorporated by reference in

I Paragraph (b)(2) of this section.

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10CFR50.55a(b)(2)(xviii)(B) (ISI) Certification of NDE personnel: Paragraph IWA-2316of the 1998 Edition through the latest Edition and Addendaincorporated by reference in Paragraph (b)(2) of this section,may only be used to qualify personnel that observe for leakageduring system leakage and hydrostatic tests conducted inaccordance with IWA-521 1(a) and (b), 1998 Edition throughthe latest Edition and Addenda incorporated by reference inParagraph (b)(2) of this section.

1OCFR50.55a(b)(2)(xviii)(C) (ISI) Certification of NDEpersonnel: When qualifying visualexamination personnel for VT-3 visual examinations underParagraph IWA-2317 of the 1998 Edition through the latestEdition and Addenda incorporated by reference in Paragraph(b)(2) of this section, the proficiency of the training must bedemonstrated by administering an initial qualificationexamination and administering subsequent examinations on a3-year interval.

10CFR50.55a(b)(2)(xix) (ISI) Substitution of alternative methods: The provisions forthe substitution of alternative examination methods, acombination of methods, or newly developed techniques in the1997 Addenda of IWA-2240 must be applied. The provisionsin IWA-2240, 1998 Edition through the latest Edition andAddenda incorporated by reference in Paragraph (b)(2) of thissection, are not approved for use. The provisions inIWA-4520(c), 1997 Addenda through the latest Edition andAddenda incorporated by reference in Paragraph (b)(2) of thissection, allowing the substitution of alternative examinationmethods, a combination of methods, or newly developedtechniques for the methods specified in the Construction Codeare not approved for use.

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10CFR50.55a(b)(2)(xxi)(A) (ISI) Table IWB-2500-1 examination requirements: Theprovisions of Table 1WB-2500-1, Examination Category B-D,Full Penetration Welded Nozzles in Vessels, Items B3.120 andB3.140 (Inspection Program B) in the 1998 Edition must beapplied when using the 1999 Addenda through the latestEdition and Addenda incorporated by reference in Paragraph(b)(2) of this section. A visual examination with enhancedmagnification that has a resolution sensitivity to detect a 1-milwidth wire or crack, utilizing the allowable flaw length criteriain Table IWB-3512-1, 1997 Addenda through the latestEdition and Addenda incorporated by reference in Paragraph(b)(2) of this section, may be performed in place of anultrasonic examination.

10CFR50.55a(b)(2)(xxi)(B) (ISI) Table IWB-2500-1 examination requirements: Theprovisions of Table IWB-2500-1, Examination CategoryB-G-2, Item B7.80, that are in the 1995 Edition are applicableonly to reused bolting when using the 1997 Addenda throughthe latest Edition and Addenda incorporated by reference inparagraph (b)(2) of this section.

10CFR50.55a(b)(2)(xxii) (ISI) Surface Examination: The use of the provision inIWA-2220, "Surface Examination," of Section XI, 2001Edition through the latest Edition and Addenda incorporatedby reference in Paragraph (b)(2) of this section, that allow useof an ultrasonic examination method is prohibited.

1OCFR50.55a(b)(2)(xxiii) (ISI) Evaluation of Thermally Cut Surfaces: The use of theprovisions for eliminating mechanical processing of thermallycut surfaces in IWA-4461.4.2 of Section XI, 2001 Editionthrough the latest Edition and Addenda incorporated byreference in Paragraph (b)(2) of this section are prohibited.

10CFR50.55a(b)(2)(xxiv) (PDI) Incorporation of the Performance DemonstrationInitiative and Addition of Ultrasonic Examination Criteria:The use of Appendix VIII and the supplements to AppendixVIII and Article 1-3000 of Section XI of the ASME BPV Code,2002 Addenda through the latest Edition and Addendaincorporated by reference in Paragraph (b)(2) of this section, is

I prohibited.

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TABLE 1.9-1CODE OF FEDERAL REGULATIONS 1OCFR50.55a REQUIREMENTS

1OCFR50.55a Paragraphs Limitations, Modifications, and Clarifications

10CFR50.55a(b)(2)(xxv) (ISI) Mitigation of Defects by Modification: The use of theprovisions in IWA-4340, "Mitigation of Defects byModification," Section XI, 2001 Edition through the latestEdition and Addenda incorporated by reference in Paragraph(b)(2) of this section are prohibited.

10CFR50.55a(b)(2)(xxvi) (SPT) Pressure Testing Class 1, 2, and 3 Mechanical Joints:The repair and replacement activity provisions in LWA-4540(c)of the 1998 Edition of Section XI for pressure testing Class 1,2, and 3 mechanical joints must be applied when using the2001 Edition through the latest Edition and Addendaincorporated by reference in Paragraph (b)(2) of this section.

10CFR50.55a(b)(2)(xxvii) (SPT) Removal of Insulation: When performing visualexaminations in accordance with IWA-5242 of Section XI,2003 Addenda through the latest Edition and Addendaincorporated by reference in Paragraph (b)(2) of the section,insulation must be removed from 17-4 PH or 410 stainlesssteel studs or bolts aged at a temperature below 1100 'F orhaving a Rockwell Method C hardness value above 30, andfrom A-286 stainless steel studs or bolts preloaded to 100,000pounds per square inch or higher.

10CFR50.55a(b)(3)(v) (ISI) Subsection ISTD: Article 1WF-5000, "InserviceInspection Requirements for Snubbers," of the ASME BPVCode, Section XI, provides inservice inspection requirementsfor examinations and tests of snubbers at nuclear power plants.Licensees may use Subsection ISTD, "Inservice Testing ofDynamic Restraints (Snubbers) in Light-Water Reactor PowerPlants," ASME OM Code, 1995 Edition through the latestEdition and Addenda incorporated by reference in paragraph(b)(3) of this section, in place of the requirements for snubbersin Section XI, TWF-5200(a) and (b) and IWF-5300(a) and (b),by making appropriate changes to their technical specificationsor licensee-controlled documents. Preservice and inserviceexaminations must be performed using the VT-3 visualexamination method described in TWA-2213.

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10CFR50.55a(b)(5) (ISI) Inservice Inspection Code Cases: Licensees may applythe ASME Boiler and Pressure Vessel Code Cases listed inRegulatory Guide 1.147 through Revision 15, without priorUSNRC approval subject to the following:(i) When a licensee initially applies a listed Code Case, thelicensee shall apply the most recent version of that Code Caseincorporated by reference in this paragraph.(ii) If a licensee has previously applied a Code Case and a laterversion of the Code Case is incorporated by reference in thisparagraph, the licensee may continue to apply, to the end of thecurrent 120-month interval, the previous version of the CodeCase as authorized or may apply the later version of the CodeCase, including any USNRC-specified conditions placed on itsuse.(iii) Application of an annulled Code Case is prohibited unlessa licensee previously applied the listed Code Case prior to itbeing listed as annulled in Regulatory Guide 1.147. Any CodeCase listed as annulled in any Revision of Regulatory Guide1.147 which a licensee has applied prior to it being listed asannulled, may continue to be applied by that licensee to theend of the 120-month interval in which the Code Case wasimplemented.

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TABLE 1.9-1CODE OF FEDERAL REGULATIONS 1OCFR50.55a REQUIREMENTS

1OCFR50.55a Paragraphs Limitations, Modifications, and Clarifications

IOCFR5O.55a(b)(6) (ISI) Operation and Maintenance of Nuclear Power PlantsCode Cases: Licensees may apply the ASME Operation andMaintenance Nuclear Power Plants Code Cases listed inRegulatory Guide 1.192 without prior NRC approval subject tothe following:(i) When a licensee initially applies a listed Code Case, thelicensee shall apply the most recent version of that Code Caseincorporated by reference in this paragraph.(ii) If a licensee has previously applied a Code Case and a laterversion of the Code Case is incorporated by reference in thisparagraph, the licensee may continue to apply, to the end of thecurrent 120-month interval, the previous version of the CodeCase as authorized or may apply the later version of the CodeCase, including any NRC-specified conditions placed on itsuse.(iii) Application of an annulled Code Case is prohibited unlessa licensee previously applied the listed Code Case prior to itbeing listed as annulled in Regulatory Guide 1.192. If alicensee has applied a listed Code Case that is later listed asannulled in Regulatory Guide 1.192, the licensee may continueto apply the Code Case to the end of the current 120-monthinterval.

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1.10 Code Cases

Per 1OCFR50.55a(b)(5) and (b)(6), ASME Code Cases that have been determinedto be suitable for use in ISI Program Plans by the USNRC are listed in RegulatoryGuide 1.147, "Inservice Inspection Code Case Acceptability-ASME Section XI,Division 1". The approved Code Cases in Regulatory Guide 1.147, which arebeing utilized by CR3, are included in Section 2.1.1. The most recent version of agiven Code Case incorporated in the revision of Regulatory Guide 1.147referenced in 1OCFR50.55a(b)(5)(i) at the time it is applied within the ISIProgram shall be used. The latest version of Regulatory Guide 1.147 incorporatedinto this document is Revision 15. As this guide is revised, newly approved CodeCases should be assessed for plan implementation at CR3.

The use of other Code Cases (other than those listed in Regulatory Guide 1.147)may be authorized by the Director of the office of Nuclear Reactor Regulationupon request pursuant to 10CFR50.55a(a)(3). Code Cases not approved for use inRegulatory Guide 1.147, which are being utilized by CR3 through associatedrelief requests, are included in Section 8.0.

This ISI Program Plan will initially utilize the Draft Regulatory Guide DG-1 134(Proposed Revision 15 of Regulatory Guide 1.147) with the anticipation that theFinal Revision 15 of Regulatory Guide 1.147 will be approved prior to the start ofthe Fourth Inspection Interval. CR3 will review the Final Revision 15 ofRegulatory Guide 1.147 for ISI Program impact at which time it is published.

This ISI Program Plan will also utilize Regulatory Guide 1.192, "Operation andMaintenance Code Case Acceptability, ASME OM Code". The approved CodeCases in Regulatory Guide 1.192, which are being utilized by CR3, are includedin Section 2.1.2. The latest version of Regulatory Guide 1.192 incorporated intothis document is Revision 0. As this guide is revised, newly approved Code Casesshould be assessed for plan implementation at CR3.

1.11 Relief Requests

In accordance with 10CFR50.55a, when a licensee either proposes alternatives toASME Section XI requirements which provide an acceptable level of quality andsafety, determines compliance with ASME Section XI requirements would resultin hardship or unusual difficulty without a compensating increase in the level ofquality and safety,. or determines that specific ASME Section XI requirements forinservice inspection are impractical, the licensee shall notify the USNRC andsubmit information to support the determination.

The submittal of this information.will be referred to in this document as a "ReliefRequest". Relief requests for the Fourth ISI Interval and the Second CISI Intervalare included in Section 8.0 of this document. The text of the relief requestscontained in Section 8.0 will demonstrate one of the following: the proposed

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alternatives provide an acceptable level of quality and safety per10CFR50.55a(a)(3)(i), compliance with the specified requirements would result inhardship or unusual difficulty without a compensating increase in the level ofquality and safety per 10CFR50.55a(a)(3)(ii), or the code requirements areconsidered impractical per 1OCFR50.55a(g)(5)(iii).

Per 10CFR50.55a Paragraphs (a)(3) and (g)(6)(i), the Director of the Office ofNuclear Reactor Regulation will evaluate relief requests and "may grant suchrelief and may impose such alternative requirements as it determines is authorizedby law and will not endanger life or property or the common defense and securityand is otherwise in the public interest giving due consideration to the burden uponthe licensee that could result if the requirements were imposed on the facility".

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2.0 BASIS FOR INSERVICE INSPECTION PROGRAM

2.1 ASME Section XI Examination Requirements

As required by the Code Of Federal Regulations, Title 10, Part 50, Section 55a,(1OCFR50.55a), this Program was developed in accordance with the requirementsdetailed in the 2001 Edition through the 2003 Addenda, of the ASME Boiler andPressure Vessel Code, Section XI, Division 1, Subsections IWA, IWB, IWC,IWD, IWE, IWF, IWL, Mandatory Appendices, and Inspection Program B ofIWA-2432, approved ASME Code Cases, and approved alternatives through reliefrequests and SER's.

The ISI Program implements Appendix VIII "Performance Demonstration forUltrasonic Examination Systems," ASME Section XI 2001 Edition, No Addendaas required by 10CFR50.55a(b)(2)(xxiv). Appendix VIII requires qualification ofthe procedures, personnel, and equipment used to detect and size flaws in piping,bolting, and the reactor pressure vessel (RPV). Each organization (e.g., owner orvendor) will be required to have a written program to ensure compliance with therequirements. These requirements were initially implemented through thePerformance Demonstration Initiative (PDI) Program according to the scheduledefined in 10CFR50.55a(g)(6)(ii)(C).

For the Fourth Inspection Interval, CR3's inspection program for ASME Section XIExamination Categories B-F and B-J will be governed by risk-informed regulations.The RISI program methodology is described in the EPRI Topical ReportTR-1 12657, Rev. B-A. To supplement the EPRI Topical Report, Code CaseN-578-1 (as applicable per Relief Request 07-001-11) is also being used for theclassification of piping structural elements under the RISI program. The RISIprogram scope has been implemented as an alternative to the ASME Section XICode examination program for the Class 1 B-F and B-J Welds in accordance with1OCFR50.55a(a)(3)(i). The basis for the resulting Risk Categorizations of thepiping within the RISI Program is defined and maintained in the RISI ProgramEvaluation Documents as referenced in Section 9.0.

2.1.1 ASME Section XI Code Cases

As referenced by 1OCFR50.55a(b)(5) and allowed by USNRC RegulatoryGuide 1.147, Revision 15, the following Code Cases are beingincorporated into the CR3 ISI Program.

N-432-1 Repair Welding Using Automatic or Machine GasTungsten-Arc Welding (GTAW) Temper Bead Technique

N-460 Alternative Examination Coverage for Class 1 and Class 2Welds

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N-504-2 Alternative Rules for Repair of Class 1, 2, and 3 AusteniticStainless Steel Piping

Code Case N-504-2 is acceptable subject to the followingcondition specified in Regulatory Guide 1.147, Revision15:

The provisions of Section XI, Nonmandatory AppendixQ, "Weld Overlay Repair of Class 1, 2, and 3 AusteniticStainless Steel Piping Weldments," must also be met.

N-508-3 Rotation of Serviced Snubbers and Pressure Relief Valvesfor the Purpose of Testing

N-513-2 Evaluation Criteria for Temporary Acceptance of Flaws in

Moderate Energy Class 2 or 3 Piping

N-516-3 Underwater Welding


Licensee must obtain USNRC approval in accordancewith 1OCFR50.55a(a)(3) regarding the technique to beused in the weld repair or replacement of irradiatedmaterial underwater.

N-517-1 Quality Assurance Program Requirements for Owners


The Owner's Quality Assurance (QA) Program that isapproved under Appendix B to 10CFRPart 50 mustaddress the use of this Code Case and any unique QArequirements identified by the Code Case that are notcontained in the owner's QA Program description. Thiswould include the activities performed in accordancewith this Code Case that are subject to monitoring bythe Authorized Nuclear Inspector.

N-526 Alternative Requirements for Successive Inspections ofClass 1 and 2 Vessels

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N-528-1 Purchase, Exchange, or Transfer of Material BetweenNuclear Plant Sites


The requirements of 10CFRPart 21 are to be applied tothe nuclear plant site supplying the material as well asto the nuclear plant site receiving the material that hasbeen purchased, exchanged, or transferred betweensites.

N-532-3 Alternative Requirements to Repair and ReplacementDocumentation Requirements and Inservice SummaryReport Preparation and Submission as Required byIWA-4000 and IWA-6000

Code Case N-532-3 is acceptable subject to the followingconditions specified in Regulatory Guide 1.147, Revision15:

Code Case N-532-3 requires an Owner's ActivityReport Form OAR-i to be prepared and certified uponcompletion of each refueling outage. The OAR-I formsmust be submitted to the USNRC within 90 days of thecompletion of the refueling outage.

N-545 Alternative Requirements for Conduct of PerformanceDemonstration Detection Test of Reactor Vessel

N-552 Alternative Methods - Qualification for Nozzle InsideRadius Section from the Outside Surface

Code Case N-552 is acceptable subject to the followingconditions specified in Regulatory Guide 1.147, Revision15:

To achieve consistency with the 10CFR50.55a rulechange published September 22, 1-999 (64 FR 51370),incorporating Appendix VIII, "PerformanceDemonstration for Ultrasonic Examination Systems," toASME Section XI, add the. following to the specimenrequirements:

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"At least 50 percent of the flaws in the demonstrationtest set must be cracks and the maximum misorientationmust be demonstrated with cracks. Flaws in nozzleswith bore diameters equal to or less than 4 inches maybe notches."

Add to detection criteria, "The number of false callsmust not exceed three."

N-566-2 Corrective Action for Leakage Identified at BoltedConnections

N-569-1 Alternative Rules for Repair by Electrochemical Depositionof Class 1 and 2 Steam Generator Tubing


Note: Steam Generator tube repair methods require priorUSNRC approval through the Technical Specifications.This Code Case does not address certain aspects of thisrepair, e.g., the qualification of inspection and pluggingcriteria necessary for staff approval of the repair method.In addition, if the user plans to "reconcile," as described inthe footnote, the reconciliation is to be performed inaccordance with IWA-4200 in the 1995 Edition through the1996 Addenda of ASMIE Section XI.

N-576-1 Repair of Class 1 and 2 SB-163, UNS N06600 SteamGenerator Tubing


Note: Steam Generator tube repair methods require priorUSNRC approval through the Technical Specifications.This Code Case does not address certain aspects of thisrepair, e.g., the qualification of inspection and pluggingcriteria necessary for staff approval of the repair method.In addition, if the user plans to "reconcile," as described inthe footnote, the reconciliation is to be performed inaccordance with IWA-4200 in the 1995 Edition through the1996 Addenda of ASME Section XI.

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N-586-1 Alternative Additional Examination Requirements forClasses 1, 2, and 3 Piping, Components, and Supports

N-593 Alternative Examination Requirements for SteamGenerator Nozzle to Vessel Welds


Essentially 100 percent (not less than 90 percent) of theexamination volume A-B-C-E-F-G-H must be inspected.

N-597-2 Requirements for Analytical Evaluation of Pipe WallThinning


(1) Code Case must be supplemented by the provisionsof EPRI Nuclear Safety Analysis Center Report202L-R2, April 1999, "Recommendations for anEffective Flow Accelerated Corrosion Program," fordeveloping the inspection requirements, the methodof predicting the rate of wall thickness loss, and thevalue of the predicted remaining wall thickness. Asused in NSAC-202L-R2, the terms "should" and"shall" have the same expectation of beingcompleted.

(2) Components affected by flow-accelerated corrosionto which this Code Case are applied must berepaired or replaced in accordance with theconstruction code of record and Owner'srequirements or a later USNRC approved edition ofSection EI of the ASME Code prior to the value oftp reaching the allowable minimum wall thickness,train, as specified in -3622.1 (a)(1) of this Code Case.Alternatively, use .of the Code Case is subject toUSNRC review and approval.

(3) For Class 1 piping not meeting the criteria of -3221,the use of evaluation methods and criteria is subjectto USNRC review and approval.

(4) For those components that do not require immediaterepair or replacement, the rate of wall thickness lossis to be used to determine a suitable inspection

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frequency so that repair or replacement occurs priorto reaching allowable minimum wall thickness, train.

(5) For corrosion phenomenon other than flowaccelerated corrosion, use of the Code Case issubject to USNRC review and approval. Inspectionplans and wall thinning rates may be difficult tojustify for certain degradation mechanisms such asMIC and pitting.

N-600 Transfer of Welder, Welding Operator, Brazer, and BrazingOperator Qualifications Between Owners

N-613-1 Ultrasonic Examination of Full Penetration Nozzles inVessels, Examination Category B-D, Item Nos. B3.10 andB3.90, Reactor Nozzle-to-Vessel Welds, Figs.IWB-2500-7(a), (b), and (c)

N-624 Successive Inspections

N-629 Use of Fracture Toughness Test Data to EstablishReference Temperature for Pressure Retaining Materials

N-638-1 Similar and Dissimilar Metal Welding Using AmbientTemperature Machine GTAW Temper Bead Technique


UT examinations shall be demonstrated for the repairedvolume using representative samples, which containconstruction type flaws. The acceptance criteria ofNB-5330 of Section III edition and addenda approved in10CFR50.55a apply to all flaws identified within therepaired volume.

N-639 Alternative Calibration Block Material


Chemical ranges of the calibration block may vary fromthe materials specification if (1) it is within thechemical range of the component specification to beinspected, and (2) the phase and grain shape are

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maintained in the same ranges produced by the thermalprocess required by the material specification.

N-641 Alternative Pressure-Temperature Relationship and LowTemperature Overpressure Protection System Requirements

N-643-2 Fatigue Crack Growth Rate Curves for Ferritic Steels inPWR Water Environment

N-648-1 Alternative Requirements for Inner Radius Examination ofClass 1 Reactor Vessel Nozzles


In place of a UT examination, licensees may perform avisual examination with enhanced magnification thathas a resolution sensitivity to detect a 1-mil width wireor crack, utilizing the allowable flaw length criteria ofTable IWB-3512-1 with limiting assumptions on theflaw aspect ratio. The provisions of Table IWB-2500-1,Examination Category B-D, continue to apply exceptthat, in place of examination volumes, the surfaces to beexamined are the external surfaces shown in the figuresapplicable to this table.

N-649 Alternative Requirements for IWE-5240 VisualExamination

N-651 Ferritic and Dissimilar Metal Welding Using SMAWTemper Bead Technique Without Removing the Weld BeadCrown of the First Layer

N-661 Alternative Requirements for Wall Thickness Restorationof Classes 2 and 3 Carbon Steel Piping for Raw WaterService


(a) If the root cause of the degradation has not beendetermined, the repair is only acceptable for one cycle.

(b) Weld overlay repair of an area can only be performedonce in the same location.

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(c) When through-wall repairs are made by welding onsurfaces that are wet or exposed to water, the weldoverlay repair is only acceptable until the next refuelingoutage.

N-663 Alternative Requirements for Classes 1 and 2 SurfaceExaminations

N-664 Performance Demonstration Requirements for Examinationof Unclad Reactor Pressure Vessel Welds, ExcludingFlange Welds

N-686 Alternative Requirements for Visual Examinations, VT-1,VT-2, and VT-3

N-695 Qualification Requirements for Dissimilar Metal PipingWelds

N-696 Qualification Requirements for Appendix VIII PipingExaminations Conducted from the Inside Surface

N-697 Pressurized Water Reactor (PWR) ExaminationRequirements for Pressure Retaining Welds in Control RodDrive and Instrument Nozzle Housings

N-700 Alternative Rules for Selection of Classes 1, 2, and 3Vessel Welded Attachments for Examination

Additional Code Cases invoked in the future shall be in accordance withthose approved for use in the latest published revision of Regulatory Guide1.147 at that time.

2.1.2 OM Code Cases

As referenced by 1OCFR50.55a(b)(6) and allowed by USNRC RegulatoryGuide 1.192, Revision 0, the following Code Cases are being incorporatedinto the CR3 ISI Program:

None currently utilized in accordance with the OM Code

Additional Code Cases invoked in the future shall be in accordance withthose approved for use in the latest published revision of Regulatory Guide1.192 at that time.

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ISI Program Plan


2.2 Augmented Examination Requirements

Augmented examination requirements are those examinations that are performedabove and beyond the requirements of ASME Section XI. Below is a summary ofthose examinations performed by CR3 that are not specifically addressed byASME Section XI, or the examinations that will be performed in addition to therequirements of ASME Section XI on a routine basis during the Fourth InspectionInterval.

2.2.1 Thin Wall Class 2 (C-F-i) Austenitic Piping

The 2001 Edition through the 2003 Addenda of ASME Section XI doesnot require examination of Class 2 piping welds > 4" NPS and a wallthickness < 3/8". There is a significant amount of Class 2 austeniticstainless steel piping in safety systems at CR3 that is not required to beexamined under the requirements of ASME Section XI.

To assure the integrity of piping not required to be examined under the2001 Edition through the 2003 Addenda of ASME Section XI, anadditional sample of 7.5% of Category C-F-1 piping welds that are > 4"NPS and < 3/8" wall thickness will be volumetrically examined. WhileASMIE Section XI does not require these examinations and CR3 does nothave any specific augmented commitments to examine this thin wallpiping, the plant plans to examine 7.5% of these locations as aconservative practice in addition to the ASME Section XI requirements.

2.2.2 High Pressure Injection (HPI) Thermal Sleeve

An Augmented Inspection Plan schedule will be conducted on the HighPressure Injection and Normal Makeup nozzle areas as recommended inthe Babcock & Wilcox 177 Fuel Assembly Owner's Group report,Document Number 77-1140611-00. As of Refueling Outage 10, all four(4) of the thermal sleeves have been replaced with the new design sleeveand as such, the inspection schedule for a repaired nozzle of new designwill be followed. This schedule entails the following:

MAKE UP NOZZLES

RT during the first refueling outage after repair to ensure that thethermal sleeve is in the proper location and no gap has formed.

L UT safe end, cold leg ID nozzle knuckle transition inner radius,and adjacent piping/valve during the first refueling outage afterrepair to ensure no cracking exists. In addition, the nozzle innerradius should be examined once every ten years due to thermal

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sleeve cracking discovered during Refueling Outage 13 (Reference28).

* VT of the ID (or RT) and UT again at the third and fifth refuelingoutages after repair and every fifth outage thereafter.

HPI NOZZLES

* RT during the first refueling outage after repair to ensure that thethermal sleeve is in the proper location and no gap has formed.

RT / VT of the ID during third and fifth refueling outages andevery fifth refueling outage thereafter.

UT the ID nozzle/cold leg transition knuckle area during the firstrefueling outage after repair to ensure that no cracking is present.UT during the third and fifth refueling outages thereafter.

The thermal sleeves associated with the A2 and B 1 loops were replacedwith the new design thermal sleeve during the Refueling Outage 10(1996). The A1 nozzle thermal sleeve was replaced in 1982 and 2003.The B2 thermal sleeve was replaced in 1994.

EC 54002 provides justification for changing the RT frequency to onceevery 10 years. The UT schedule does not change:

Memo NPTS03-0022 provides justification for visual of the ID in lieu ofRT for thermal sleeve location and gap verification;

2.2.3 Augmented Examination of Inconel 600

In response to an industry wide concern with Inconel 600 cracking in PWRapplications (Information Notice 90-10 Primary Water Stress CorrosionCracking of Inconel 600), Progress Energy has included within theAugmented Inspection Plan, those locations within the reactor coolantsystem that are most prone to Primary Water Stress Corrosion Cracking(PWSCC). The identification of Inconel 600 locations and application ofthe risk factors was performed by the Babcock & Wilcox Owners Group.The report limited the areas of concern to only the pressurizer and the hotlegs.

As an additional conservatism, Progress Energy elected to include the coldleg drain nozzles.

The ISI Program Plan originally scheduled twelve (12) examinationlocations. Five (5) more locations have been added due to increasedIndustry Issues concerning Alloy 600 PWSCC. These locations are the

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RTD Mounting Bosses, Temperature Connections, and Pressure Taps onthe RCS system.

The Inconel 600 locations are scheduled to receive a bare metal VT-2visual examination. During the original Ten-Year Schedule, an equalnumber of locations were scheduled for examination each period of theThird Inspection Interval to coincide with ASME Section XIexaminations. However, with increased industry concerns with 1-600PWSCC, the schedule was accelerated based on Risk Impact. As such, allpressurizer nozzles and reactor coolant partial-penetration nozzles wereexamined during Refueling Outage 13. These examinations identifiedthru-wall leaks in the three (3) pressurizer upper level tap nozzles. Theywere repaired with 1-690 materials. NCR 106443-09 Corrective Actionrequires examination of all Alloy 600 Pressurizer penetrations and steamspace piping (Reference 17 and 24) each refueling outage. The Alloy 690replacement nozzles will receive a bare metal visual examination duringthe first refueling outage following repair and then once every 10 years. AVT-3 visual examination of the pressurizer spray nozzle extension pininternal 1-600 components will be performed only when the pressurizermanway is opened for scheduled maintenance.

USNRC Bulletin 2004-01 requires CR3 to submit a statement within 60days of plant restart for pressurizer steam space Alloy 600 examinationswith the following information:

(a) a statement indicating that the Alloy 82/182/600 pressurizerpenetrations and steam space piping connection inspections werecomplete with a description of the as-found condition of thepressurizer shell, any findings of relevant indications of through-wall leakage, following NDE performed to characterize flaws inleaking penetrations or steam space piping connections, a summaryof the disposition of any findings of boric acid, and any correctiveactions taken and/or repairs as a result of the indications found, or

(b) if the licensee was unable to complete the pressurizer steam spaceinspections described in response the bulletin, submit to theUSNRC a summary of the inspections performed, the extent of theinspections, the methods used, a description of the as-foundcondition of the pressurizer shell, any findings of relevantindications of through-wall leakage, follow-up NDE performed tocharacterize flaws in leaking penetrations or steam space pipingconnections, a summary of all relevant indications found by NDE,a summary of the disposition of any findings of boric acid, and anycorrective actions taken and/or repairs made as a result of theindications found. In addition, supplement the answer which you

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provided to item (1)(d) of the bulletin to explain why theinspections that CR3 completed were adequate for the purpose ofmaintaining the integrity of your facility's RCPB and for meetingall applicable regulatory requirements which pertain to CR3.

For lines attached directly to the pressurizer, with the exception of thesurge line, the information requested in (1) and (2) above should beprovided for any locations, including those remote from the pressurizershell, which contain Alloy 82/182/600 materials which are exposed toconditions similar to those of the pressurizer environment.

2.2.4 Reactor Coolant Pump Motor Flywheel Inspections

The Reactor Coolant Pump Motor flywheels will be inspected as requiredby CR3 Improved Technical Specifications Section 5.6.2.8 c. Inserviceinspection of each reactor coolant pump flywheel shall be performed atleast once every 20 years. The inservice inspection shall be either anultrasonic examination of the volume from the inner bore of the flywheelto the circle of one-half the outer radius or a surface examination forexposed surfaces of the disassembled flywheels (Reference 29).

2.2.5 USNRC EA-03-009, Issuance Of First Revised Order Establishing InterimInspection Requirements For Reactor Pressure Vessel Heads AtPressurized Water Reactors

Section IV-B requires each licensee to determine the susceptibilitycategory of their reactor vessel head (RVH). Because CR3 replaced theRVH with alloy 690 base and weld material, CR3's RVH is consideredcategory "Replaced".

Section IV-C-(5)(a) of the Order requires bare metal visual examination of100% of the RPV head surface (including 3600 around each RPV headpenetration nozzle) at least every third refueling outage or every 5 years(whichever comes first).

Section IV-C-(5)(b) of the Order requires either of the following NDEmethod be performed at least every four (4) refueling outages or everyseven (7) years (whichever comes first):

(i) Ultrasonic testing of each RPV head penetration nozzle (i.e.,nozzle base material) from two (2) inches above the J-groove weldto two (2) inches below the J-groove weld (or bottom) and anassessment to determine if leakage has occurred into theinterference fit zone, or

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(ii) Eddy current testing or dye penetrant testing of the entire wettedsurface of each J-Groove weld and RPV head penetration nozzlebase material to at least two (2) inches above the J-groove weld totwo (2) inches below the J-groove weld (or bottom)

Section IV-D of the Order requires that during each refueling outage,visual inspections to identify potential boric acid leaks from pressure-retaining components above the RPV head. This examination isperformed by the Boric Acid Control Program.

Section IV-E of the Order requires, for each inspection required in SectionIV-C, of the Order, the submittal of a report detailing the inspection resultswithin sixty (60) days after returning the plant to operation. Section IV-Ealso requires, for each inspection required in Section IV-D, the submittalof a report detailing the inspection results within sixty (60) days afterreturning the plant to operation if a leak or boron deposit was found duringthe inspection.

2.2.6 USNRC NUREG-0737, dated November 1980

This document discusses TMI Action Plan Requirements, and includesrequirements in Item I.D. 1.1 for leak testing and periodic visualexaminations of systems outside of primary containment which couldcontain highly radioactive fluids during a serious transient or accident.

2.3 System Classifications and P&ID Boundary Drawings

The ISI Classification Basis Document details those systems that are ISI Class 1,2, 3, or MC that fall within the ISI scope of examinations. The concretecontainment structure and post-tensioning system are ISI Class CC and are shownon the CISI Reference Drawings. Below is a summary of the classificationcriteria used within the ISI Classification Basis Document.

Each safety related, fluid system containing water, steam, air, oil, etc. included inthe CR3 FSAR was reviewed to determine which safety functions they performduring all modes of system and plant operation. Based on these safety functions,the systems and components were evaluated per classification documents. Thesystems were then designated as ISI Class 1, 2, 3, or non-classed accordingly.

When a particular group of components is identified as performing an ISI Class 1,2, or 3 safety function, the components are further reviewed to assure theinterfaces (boundary valves and boundary barriers) meet the criteria set by10CFR50.2, 1OCFR50.55a(c)(1), 1OCFR50.55a(c)(2), and Regulatory Guide 1.26,Revision 3. SRP 3.2.2 and ANSI/ANS-58.14-1993 (CR3 is not committed to orlicensed in accordance with these documents) were also used for guidance in

2-13Revision 0


determining the classification boundaries where 1OCFR and the Regulatory Guidedid not address a given situation.

According to 10CFR50.55a, Paragraph (g)(4), the ISI requirements of ASMESection XI are assigned to these components, within the constraints of existingplant design. The CR3 ISI Class 1, 2, and 3 components that are exempt fromexamination are those which meet the criteria of ASME Section XI, SubarticlesIWB-1220, IWC-1220, and IWD-1220. Supports which meet the criteria ofSubarticle IWF-1230 are also exempt from examination. For Containment, ClassMC components which meet IWE-1220 are exempt from examination, and ClassCC components which meet IWL-1220 are exempt from examination. CR3's ISIProgram, including the ISI Database, basis document, selection document, andschedule, addresses those components which may require examination and testing.These components are referred to throughout this document as "Nonexempt",meaning they are potentially subject to examination and testing in accordancewith ASME Section XI.

The systems and components (piping, pumps, valves, vessels, etc.), which are ISIClass 1, 2, or 3 are identified on the P&IDs listed in Table 2.3-1. Theclassification boundaries are identified with triangular flags containing a 1, 2, or 3.Transitions to non-classed components are identified with a 4 in the boundaryflag. The ISI Class 1, 2, and 3 identifiers are shown regardless of the ASMESection XI examination exemptions.

2-14Revision 0


TABLE 2.3-1P&ID BOUNDARY DRAWINGS

Number Title

FD-302-011 Shts. 1, 2, 4 Main and Reheat Steam (MS, RH)

FD-302-051 Sht. 1 Auxiliary Steam (AS)

FD-302-081 Shts. 1, 3, 4 Feedwater (FW)

FD-302-082 Shts. 1, 2, 3 Emergency Feedwater (EF)

FD-302-192 Sht. 1 Chemical Cleaning Steam Generators (CG)

FD-302-182 Sht. 2 Condensate and Demineralized Water (DW)

FD-302-211 Sht. 1 Domestic (DO)

FD-302-281 Sht. 1 Emergency Diesel Generator Fuel-Oil Transfer (DF)

FD-302-231 Sht. 1 Fire Service Water (FS)

FD-302-601 Shts. 1, 2, 3, 4, 5 Nuclear Services Closed Cycle Cooling (SW)

FD-302-271 Shts. 2, 4 Service Air (SA) & Instrument Air (IA)

FD-302-611 Shts. 1, 2, 3 Nuclear Services and Decay Heat Sea Water (RW)

FD-302-621 Shts. 1, 3 Spent Fuel Cooling (SF)

FD-302-631 Shts. 1, 2, 3 Decay Heat Closed Cycle Cooling (DC)

FD-302-641 Shts. 1, 2, 3 Decay Heat Removal (DH)

FD-302-65 1, Shts. 1, 2, 3 Reactor Coolant (RC)

FD-302-661 Shts. 1, 2, 3, 4, 5 Make-Up and Purification (MU)

FD-302-671 Sht. 1 Chemical Addition (CA)

FD-302-673 Sht. 2 Nitrogen Supply to RCS Primary, Nitrogen Supply to OTSG Secondary, &Nitrogen Supply to Reactor Coolant Drain Tank (NG, HY)

FD-302-681 Sht. I Reactor Building Sump to MWST & Reactor Coolant Drain Tank to MWST(WD)

FD-302-691 Shts. 1, 2, 3 Gas Waste Disposal & RC Equipment Vents to Waste Gas (WD)

FD-302-693 Sht. 1 Reactor Building Air Sample, Reactor Building Air Sample Return, &Containment Monitoring Sample Return (WS)

FD-302-700 Sht. 1 Post Accident Sampling & Post Accident Sampling Return (CA)

FD-302-702 Sht. 1 Core Flooding (CF)

FD-302-711 Sht. 1 Reactor Building Spray (BS)

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TABLE 2.3-1P&ID BOUNDARY DRAWINGS

Number Title

FD-302-712 Sht. I Reactor Building Pressure Sensing and Testing (BS)

FD-302-722 Sht. 1 Reactor Building Leak Rate Test, H2 Recombiner & H2 Recombiner Return(LR)

FD-302-723 Sht. 1 Post Accident Venting (LR)

FD-302-751 Sht. 1 Reactor Building Purge & Reactor Building Purge Exhaust (AH)

FD-302-756 Sht. 1 Chilled Water (CW)

FD-302-762 Sht. 1 Industrial Cooling Water Supply & Industrial Cooling Water Return (CI)

FD-302-765 Sht. 1 Chilled Water (CW)

FD-302-772 Sht. 1 Reactor Building Air Locks (RA)

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2.4 ISI Isometric and Component Drawings for Nonexempt ISI Class Componentsand Supports

ISI Isometric and Component Drawings were developed to detail the ISI Class 1,2, and 3 components (welds, bolting, etc.) and support locations at CR3. TheseISI component and support locations are identified on the ISI Isometric andComponent Drawings listed in Tables 2.4-1, 2.4-2, 2.4-3, 2.4-4, 2.4-5, and 2.4-6.The CISI Class MC and CC components are identified on the CISI ReferenceDrawings listed in Table 2.4-7. Calibration Block Drawings are identified on theASME Section XI UT Calibration Block Drawings listed in Table 2.4-8.

CR3's ISI Program, including the ISI Database, ISI Classification BasisDocument, and ISI Selection Document, addresses the nonexempt components,which require examination and testing.

A summary of CR3 ASMIE Section XI nonexempt components and supports isincluded in Section 7.0.

2-17Revision 0


TABLE 2.4-1ISI COMPONENT DRAWINGS

Number Title

CR3-P-SK-1AC.1 Reactor Pressure Vessel (layout)

CR3-P-SK-1AC.2 Reactor Pressure Vessel (section)

CR3-P-SK-1AC.3 Reactor Top Head (closure hardware)

CR3-P-SK-1AC.4 Reactor Top head (CRDM & hardware)

CR3-P-SK-IAC.5 RCP Seal Cooler Welds

CR3-P-SK- 1AC.6 Steam Generator "A"

CR3-P-SK- IAC.7 Steam Generator "B"

CR3-P-SK-1AC.8 Pressurizer (section)

CR3-P-SK-IAC.9 Pressurizer (closure hardware)

CR3-P-SK-1AC.10 Feedwater Header to Steam Generators (RCSG- 1A/1B)

CR3-P-SK-IAC.11 Decay Heat Cooler A & B

CR3-P-SK-1AC.12 Reactor Coolant Pump (section)

CR3-P-SK-1AC.13 Reactor Vessel Head Stand Pipe Assembly

CR3-P-SK- 1AC. 14 Letdown Coolers

CR3-P-SK-1AC.15 Main Steam Isolation Valves

CR3-P-SK-1AC.16 Integral Attachments (SWHE-IA, 1B, 1C, 1D)

CR3-P-SK-1AC.17 Integral Attachments (DCHE-IA, 1B)

CR3-P-SK-1AC.18 Integral Attachments (DHIE-1A, 1B)

CR3-P-SK- 1AC. 19 Integral Attachments (DCT- 1 A)

CR3-P-SK-1AC.20 Integral Attachments (DCT-1B)

CR3-P-SK-1AC.21 Integral Attachments (SWT-1)

CR3-P-SK-1AC.22 Integral Attachments (EFT-1)

CR3-P-SK-1AC.23 Integral Attachment (DCP- I A, l B, SWP- 1 A, 1 B, I C)

CR3-P-SK-1AC.24 Integral Attachment (RWP-1, 2A, 2B, 3A, 3B)

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TABLE 2.4-2CLASS 1 ISI ISOMETRIC PIPING DRAWINGS

Number Title

CR3-P-SK- 1.1 12" Decay Heat

CR3-P-SK-3.1 10" & 14" Core Flood (A Train)

CR3-P-SK-3.2 10" & 14" Core Flood (B Train)

CR3-P-SK-4.1 2 1/2" High Pressure Injection (RCP- 1 A)

CR3-P-SK-5.1 2 1/2" High Pressure Injection (RCP-1B)

CR3-P-SK-5.2 2 1/2" High Pressure Injection (RCP-1B)

CR3-P-SK-6.1 2 1/2" High Pressure Injection (RCP-1 C)

CR3-P-SK-6.2 2 1/2" High Pressure Injection (RCP-IC)

CR3-P-SK-7.1 2 1/2" High Pressure Injection (RCP-1D)

CR3-P-SK-7.2 2 1/2" High Pressure Injection (RCP-1D)

CR3-P-SK-8.1 Pressurizer Valves (PORV & Code Safety)

CR3-P-SK-9.1 2 1/2" Conn. Pump 2B Suction to Letdown Coolers



CR3-P-SK- 10.1 MUHE-1A/1B Outlet

CR3-P-SK-10.2 MUHE-IC

CR3-P-SK-10.3 MUHE-IA, IB, 1C Outlet

CR3-P-SK-11.1 28" Reactor Coolant Cold Leg (Loop Al)

CR3-P-SK-12.1 28" Reactor Coolant Cold Leg (Loop A2)

CR3-P-SK-13.1 28" Reactor Coolant Cold Leg (Loop B 1)

CR3-P-SK-14.1 28" Reactor Coolant Cold Leg (Loop B2)

CR3-P-SK-15.1 Reactor Coolant to Steam Generator "A"

CR3-P-SK-15.2 Reactor Coolant to Steam Generator "B"

CR3-P-SK-15.3 Reactor Coolant to Steam Generators (Details)

CR3-P-SK-16.1 Cold Leg Crossover From OTSG "B" to Pump B 1

CR3-P-SK-16.2 Cold Leg Crossover From OTSG "B" to Pump B2

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Number Title

CR3-P-SK-17.1 Cold Leg Crossover From OTSG "A" to Pump Al

CR3-P-SK-17.2 Cold Leg Crossover From OTSG "A" to Pump A2

CR3-P-SK- 18.1 10" Surge Line

CR3-P-SK- 19.1 2 1/2" Pressurizer Spray Line

CR3-P-SK-20.1 Reactor Coolant Drain From RCP-1A

CR3-P-SK-20.2 Reactor Coolant Drain From RCP-IB

CR3-P-SK-20.3 Reactor Coolant Drain From RCP-1C

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TABLE 2.4-3CLASS 1 ISI ISOMETRIC HANGER DRAWINGS

Number Title

CR3-P-SK-TYPICAL-1 IWF Examination Boundary Drawing

CR3-P-SKH- 1.1 12" Decay Heat

CR3-P-SKH-3.1 10" & 14" Core Flood (A Train)

CR3-P-SKH-3.2 10" & 14" Core Flood (B Train)

CR3-P-SKH-4.1 2 1/2" High Pressure Injection (RCP-1A)

CR3-P-SKH-5.1 2 1/2" High Pressure Injection (RCP-1B)

CR3-P-SKH-5.2 2 1/2" High Pressure Injection (RCP-IB)

CR3-P-SKH-6.1 2 1/2" High Pressure Injection (RCP-1C)

CR3-P-SKH-6.2 2 1/2" High Pressure Injection (RCP-1C)

CR3-P-SKH-7.1 2 1/2" High Pressure Injection (RCP-1D)

CR3-P-SKH-7.2 2 1/2" High Pressure Injection (RCP-1D)

CR3-P-SKH-9.1 2 1/2" Conn. Pump 2B Suction to Letdown Coolers



CR3-P-SKH- 10.1 MUHE- I A/1B Outlet

CR3-P-SKH- 10.2 MUHE-1C

CR3-P-SKH-10.3 MUHE-lA, 1B, 1C Outlet

CR3-P-SKH- 18.1 10" Surge Line

CR3-P-SKH-19.1 2 1/2" Pressurizer Spray Line

CR3-P-SKH-20.1 Reactor Coolant Drain From RCP- 1A

CR3-P-SKH-20.2 Reactor Coolant Drain From RCP-1B

CR3-P-SKH-20.3 Reactor Coolant Drain From RCP-1C

CR3-P-SK-IAH.12 Reactor Coolant Pump Constant Support

2-21ReviWion 0



Number Title

CR3-P-SK-101.1 24" Main Steam From OTSG "A" to Pen. # 106

CR3-P-SK-101.2 24" Main Steam From Pen. # 106 to MSV-412

CR3-P-SK-102.1 24" Main Steam From OTSG "A" to Pen. # 105

CR3-P-SK-102.2 24" Main Steam From Pen # 105 to MSV-411

CR3-P-SK-103.1 24" Main Steam From OTSG "B" to Pen # 107


CR3-P-SK-104.1 24" Main Steam From OTSG "B" to Pen # 201


CR3-P-SK- 105.1 Feedwater to OTSG "A"

CR3-P-SK-105.2 Feedwater to OTSG "A"

CR3-P-SK- 105.3 Feedwater to OTSG "A"

CR3-P-SK-106.1 Feedwater to OTSG "B"

CR3-P-SK- 106.2 Feedwater to OTSG "B"

CR3-P-SK- 106.3 Feedwater to OTSG "B"

CR3-P-SK- 107.1 Emergency Feedwater to OTSG "A"

CR3-P-SK- 107.2 Emergency Feedwater to OTSG "A"

CR3-P-SK-107.3 Emergency Feedwater to OTSG "A"

CR3-P-SK-108.1 Emergency Feedwater to OTSG "B"

CR3-P-SK- 108.2 Emergency Feedwater to OTSG "B"

CR3-P-SK-108.3 Emergency Feedwater to OTSG "B"

CR3-P-SK-109.1 14" Decay Heat (A Train)

CR3-P-SK-109.2 14" Decay Heat (A Train)

CR3-P-SK- 110.1 14" Decay Heat (B Train)

CR3-P-SK- 110.2 14" Decay Heat (B Train)

CR3-P-SK-111.1 8" Decay Heat

CR3-P-SK- 111.2 14" Decay Heat

2-22Revision 0



Number Title

CR3-P-SK- 112.1 10" Decay Heat (A Train)

CR3-P-SK- 112.2 10" Decay Heat (A Train)

CR3-P-SK-112.3 10" Decay Heat Inside Reactor Building (A Train)

CR3-P-SK-113.1 10" Decay Heat From DHV- 111 To Pump 3B (B Train)

CR3-P-SK- 113.2 10" Decay Heat From DHV- 111 To Pen. #342 (B Train)

CR3-P-SK- 113.3 10" Decay Heat Inside Reactor Building (B Train)

CR3-P-SK- 114.1 8" Decay Heat (A/B Train)

CR3-P-SK-115.1 6" Makeup

CR3-P-SK- 115.2 6" Makeup

CR3-P-SK-115.3 4" Decay Heat to DHV-11 (Piggy Back mode)

CR3-P-SK- 115.4 4" Makeup Suction to MUV-65



CR3-P-SK- 116.3 4" Decay Heat to DHV-12 (Piggy Back mode)

CR3-P-SK-117.1 14" Core Flood

CR3-P-SK-118.1 14" Core Flood


CR3-P-SK-120.1 10" Building Spray to BSP-1A

CR3-P-SK7120.2 10" Building Spray From BSP-1A to Pen # 340

CR3-P-SK-121.1 10" Building Spray to BSP-1B

CR3-P-SK-121.2 10" Building Spray From BSP-1B to Pen # 341

CR3-P-SK-122.1 14" Decay Heat From BWST "A" Train

CR3-P-SK-122.2 6" MU Pump Suction From BWST "A" Train

CR3-P-SK-122.3 14" Decay Heat From BWST "B" Train

CR3-P-SK-122.4 6" MU Pump Suction From BWST "B" Train

CR3-P-SK-123.1 4" Makeup Recirc Line

CR3-P-SK-123.2 4" Makeup Recirc Line

2-23Revision 0



Number Title

CR3-P-SK-124.1 2" Makeup Recirc Line From MUP-1A

CR3-P-SK-125.1 2" Makeup Recirc Line From MUP-IB

CR3-P-SK-126.1 2" Makeup Recirc Line From MUP-1C

CR3-P-SK-127.1 10" Decay Heat From BWST to SFV-13

CR3-P-SK- 127.2 10" Decay Heat From BWST to SFV- 13

CR3-P-SK-128.1 2 1/2" Makeup to RCS




CR3-P-SK-129.1 4" Makeup to MUV-18

CR3-P-SK-129.2 2 1/2" Makeup to MUV-18

CR3-P-SK-129.3 4" Makeup to MUV- 18

CR3-P-SK-129.4 4" Makeup to MUV-18

CR3-P-SK-129.5 2 1/2" Makeup Bypass for MUV-452

CR3-P-SK-129.6 2 1/2" Makeup Bypass for MUV-452

CR3-P-SK-130.1 4" Makeup Discharge Header

CR3-P-SK-130.2 3" Makeup From MUP-IC Discharge

CR3-P-SK- 130.3 4" High Pressure Injection

CR3-P-SK-130.4 3" Makeup to RC Injection


CR3-P-SK- 131.1 4" Makeup Header

CR3-P-SK-131.2 3" Makeup From MUP-IB Discharge

CR3-P-SK-131.3 3" Makeup From MUP-IA Discharge

CR3-P-SK- 131.4 4" High Pressure Injection


CR3-P-SK- 131.6 3" Makeup to RC Injection


2-24Revision 0



Number Title



CR3-P-SK- 131.10 2 1/2" Makeup to RCS



CR3-P-SK-132.1 3" Makeup Recirc to RB Sump




CR3-P-SK-133.1 Nuclear Services (SW) to RB Fan 3A



CR3-P-SK-134.1 Nuclear Services (SW) from RB Fan 3A



CR3-P-SK-135.1 Nuclear Services (SW) to RB Fan 3B

CR3-P-SK-135.2 Nuclear Services (SW) to RB Fan 3B

CR3-P-SK-136.1 Nuclear Services (SW) from RB Fan 3B

CR3-P-SK-136.2 Nuclear Services (SW) from RB Fan 3B

CR3-P-SK-137.1 Nuclear Services (SW) to RB Fan 3C



CR3-P-SK-138.1 Nuclear Services (SW) from RB Fan 3C



2-25Revision 0



Number Title

CR3-P-SKH-101.1 24" Main Steam From OTSG "A" to Pen. # 106

CR3-P-SKH-101.2 24" Main Steam From Pen. # 106 to MSV-412

CR3-P-SKH-101.3 24" Main Steam From Pen. # 427 to MSh-559

CR3-P-SKH-102.1 24" Main Steam From OTSG "A" to Pen. # 105

CR3-P-SKH-102.2 24" Main Steam From Pen # 105 to MSV-411

CR3-P-SKH-103.1 24" Main Steam From OTSG "B" to Pen # 107


CR3-P-SKH-104.1 24" Main Steam From OTSG "B" to Pen # 201


CR3-P-SKH-104.3 24" Main Steam From MSH-559 to MSV-128

CR3-P-SKH-105.1 Feedwater to OTSG "A"

CR3-P-SKH- 105.2 Feedwater to OTSG "A"

CR3-P-SKH-105.3 Feedwater to OTSG "A"

CR3-P-SKH-106.1 Feedwater to OTSG "B"



CR3-P-SKH-107.1 Emergency Feedwater to OTSG "A"



CR3-P-SKH-108.1 Emergency Feedwater to OTSG "B"




CR3-P-SKH-109.1 14" Decay Heat (A Train)


CR3-P-SKH-110.1 14" Decay Heat (B Train)

2-26Revision 0



Number Title

CR3-P-SKH- 110.2 14" Decay Heat (B Train)

CR3-P-SKH-111.1 8" Decay Heat


CR3-P-SKH- 112.1 10" Decay Heat (A Train)


CR3-P-SKH-112.3 10" Decay Heat Inside Reactor Building (A Train)

CR3-P-SKH- 113.1 10" Decay Heat From DHV- 111 To Pump 3B (B Train)

CR3-P-SKH- 113.2 10" Decay Heat from DHV- 111 to Pen. #342 (B Train)

CR3-P-SKH-113.3 10" Decay Heat Inside Reactor Building (B Train)

CR3-P-SKH- 114.1 8" Decay Heat (A/B Train)

CR3-P-SKH- 115.1 6" Makeup


CR3-P-SKH-115.3 4" Decay Heat to DHV- 11 (Piggy Back mode)

CR3-P-SKH-115.4 4" Makeup Suction to MUV-65



CR3-P-SKH-116.3 4" Decay Heat to DHV-12 (Piggy Back mode)

CR3-P-SKH-117.1 14" Core Flood

CR3-P-SKH- 118.1 14" Core Flood

CR3-P-SKH-119.1 5" Makeup

CR3-P-SKH-120.1 10" Building Spray to BSP-IA

CR3-P-SKH-120.2 10" Building Spray From BSP-1A to Pen # 340

CR3-P-SKH-121.1 10" Building Spray to BSP-IB

CR3-P-SKH-121.2 10" Building Spray From BSP-1B to Pen # 341

CR3-P-SKH-122.1 14" Decay Heat From BWST "A" Train

CR3-P-SKH-122.2 6" MU Pump Suction From BWST "A" Train

CR3-P-SKH-122.3 14" Decay Heat from BWST "B" Train

2-27Revision 0



Number Title

CR3-P-SKH-122.4 6" MU Pump Suction From BWST "B" Train

CR3-P-SKH-123.1 4" Makeup Recirc Line

CR3-P-SKH-123.2 4" Makeup Recirc Line

CR3-P-SKH-124.1 2" Makeup Recirc Line From MUP-1A

CR3-P-SKH-125.1 2" Makeup Recirc Line From MUP- IB

CR3-P-SKH-126.1 2" Makeup Recirc Line From MUP- IC

CR3-P-SKH-127.1 10" Decay Heat from BWST to SFV-13

CR3-P-SKH-127.2 10" Decay Heat from BWST to SFV-13

CR3-P-SKH-128.1 2 1/2" Makeup to RCS




CR3-P-SKH- 129.1 4" Makeup to MUV- 18

CR3-P-SKH-129.2 2 1/2" Makeup to MUV-18

CR3-P-SKH-129.3 4" Makeup to MUV- 18

CR3-P-SKH-129.4 4" Makeup to MUV-18

CR3-P-SKH-129.5 2 1/2" Makeup Bypass for MUV-452

CR3-P-SKH-129.6 2 1/2" Makeup Bypass for MUV-452

CR3-P-SKH-130.1 4" Makeup Discharge Header

CR3-P-SKH-130.2 3" Makeup From MUP-IC Discharge

CR3-P-SKH- 130.3 4" High Pressure Injection

CR3-P-SKH-130.4 3" Makeup to RC Injection


CR3-P-SKH- 131.1 4" Makeup Header

CR3-P-SKH-131.2 3" Makeup From MUP-1B Discharge

CR3-P-SKH- 131.3 3" Makeup From MUP- lA Discharge

CR3-P-SKH- 131.4 4" High Pressure Injection

2-28Revision 0



Number Title

CR3-P-SKH- 131.5 3" Makeup to RC Injection


CR3-P-SKH-132.1 3" Makeup Recirc to RB Sump




CR3-P-SKH-133.1 Nuclear Services (SW) to RB Fan 3A



CR3-P-SKH-134.1 Nuclear Services (SW) from RB Fan 3A



CR3-P-SKH-135.1 Nuclear Services (SW) to RB Fan 3B

CR3-P-SKH-135.2 Nuclear Services (SW) to RB Fan 3B

CR3-P-SKH-136.1 Nuclear Services (SW) from RB Fan 3B

CR3-P-SKH-136.2 Nuclear Services (SW) from RB Fan 3B

CR3-P-SKH-137.1 Nuclear Services (SW) to RB Fan 3C



CR3-P-SKH-138.1 Nuclear Services (SW) from RB Fan 3C



2-29Revision 0



Number Title

CR3-P-SKH-201.1 8 & 12" Decay Heat

CR3-P-SKH-201.2 Decay Heat Closed Cycle Cooling

CR3-P-SKH-202.1 Nuclear Services Closed Cycle Cooling














CR3-P-SKH-2 11.1 Nuclear Services Closed Cycle Cooling


CR3-P-SKH-212.1 Chilled Water

CR3-P-SKH-213.1 Nuclear Services Sea Water




CR3-P-SKH-216.1 Spent Fuel Cooling

CR3-P-SKH-217.1 .6" Main Steam to Emergency FW Pump

CR3-P-SKH-217.2 6" Main Steam to Emergency FW Pump

2-30Revision 0

ISf Program PlanCrystal River Unit 3, Fourth Interval


Number J Title


CR3-P-SKH-219.1 Nuclear Services Decay Heat Sea Water







CR3-P-SKH-225.1 Spent Fuel Cooling





CR3-P-SKH-228.1 Spent Fuel to Spent Fuel Pumps

CR3-P-SKH-228.2 Spent Fuel to Spent Fuel Pumps



2-31Revision 0


TABLE 2.4-7CISI REFERENCE DRAWINGS

Number Title

S425-001 IWE / IWL Inspection Concrete Layout 0' to 1800

S425-002 IWE / IWL Inspection Concrete Layout 1800 to 3600

S425-003 IWE I IWL Inspection Exterior Dome Layout

S425-004 IWE / IWL Inspection Vertical Tendon Layout

S425-005 IWE / IWL Inspection Hoop Tendon "13" Layout






S425-011 IWE / IWL Inspection Dome Tendons Layout - Plan

S425-012 IWE / IWL Inspection Dome Tendons Layout -Elevation

S425-020 IWE / IWL Inspection Sheet Tendon Detail

S525-001 IWE/ IWL Inspection Bottom Liner Layout

S525-002 IWE / IWL Inspection Reactor Building Liner Plate Layout 0' to 900

S525-003 IWE / IWL Inspection Reactor Building Liner Plate Layout 900 to 1800



S525-006 IWE / IWL Inspection Dome Liner Layout 00 to 900

8525-007 IWE/ IWL Inspection Dome Liner Layout 90" to 1800



8525-020 Sht. I IWE / IWL Inspection Sheet Penetration Detail

8525-020 Sht. 2 IWE / IWL Inspection Sheet Penetration Detail

S525-021 Sht. 1 IWE / IWL Inspection Sheet Penetration Detail


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1Sf Program PlanCrystal River Unit 3, -Fourth Interval


Number Title



S525-023 IWE / IWL Inspection Sheet Penetration Detail






S525-029 Sht. 1 IWE / IWL Inspection Sheet Fuel Transfer Tube

S525-029 Sht. 2 IWE / IWL Inspection Sheet Fuel Transfer Tube

S525-030 Sht. 1 IWE / IWL Inspection Sheet Equipment Hatch Detail









S525-031 Sht. 1 IWE / IWL Inspection Sheet Personnel Hatch Detail








2-33Revision 0



Number Title






2-34Revision 0


TABLE 2.4-8ASME SECTION XI UT CALIBRATION BLOCKS

Cal. Block Type Description Material Thick. J Dia. Size DrawingNumber I I I 1

1205267 PIPING NOZZLE PIPING SA479 0.75 4 4" SCH XX CR3-M100-ATP304

40701 VESSEL ARIS CAL STD SA516 Grade 3 0 12"L X 8"W CR3-M-38-B#0001 70

40702 VESSEL ARIS CAL STD SA 533-65 Gr 12 0 23"L X 12"W CR3-M39-B#0002 B Cl1

ARIS CAL STD SA 533-65 Gr40703 VESSEL #00S Cl 1 12 0 25"L X 8"W CR3-M40-B#0003 B CI 1

40704 VESSEL ARIS CAL STD SA533-65Gr 9 0 21"L x 8"W CR3-M41-B#0004 B CI I

ARIS CAL STD SA 533-65 Gr 10½"L X -M42-B40705 VESSEL #00 l1 12 0 1 V W CR3-4B#0005 B C1 1 ___ 1 1½"W ______

40706 VESSEL ARIS CAL STD SA 533-65 Gr 5 0 16"L X 8"W CR3-M43-B#0006 B C1 1

40707 VESSEL PRESSURIZER SA533Gr3 7 0 21 "L X 7"W CR3-M26-BVESSEL STD Cl 1

40708 VESSEL IST INT.- OTSG SA 533 Gr B 8 0 18 5/8"L X CR3-M28-BPRIMARY CL 1 4"W

40709 VESSEL 1ST INT.- OTSG SA 533 Gr B 0 18"L X 4W" CR3-M29-BPRIMARY Cl1

40710A/B PIPING 1.5" AUX. ASTM A-312 0.281 1.5 1½" SCH 160 CR3-P30-ASPRAY TP 304

2" SPRAY ASTM A-40711A/B PIPING 2SPRAY A12M3A- 0.344 2 2" SCH 160 CR3-P31-A_________PIPING 312/316 __ _____

IST INT.-2.5" ASTMA-40712 PIPING 312/376 TP 0.375 2.5 2½" SCH 160 CR3-P32-AH-PI PIPING

30440713 ST INT.- - 3" ASTM A-376 0.438 3 3" SCH 160 CR3-P33-A

HPI PIPING TP 304

Replaced by40714 PIPING block S/N N/A N/A 0 N/A CR3-P34-A

1205267

1ST INT.- 6" ASTM A-40715 PIPING 376-71 TP 0.28 6 6" SCH 40 CR3-P35-ASCH 40O0

304

40716 PIPING 1ST INT.- 8" ASTM A-312 0.322 8 8" SCH 40 CR3-P36-ASCH 40 TP 304

40717 PIPING 10" SURGE ASTM A-376 1 10 10" SCH 140 CR3-P37-ALINE TP 304

40718 PIPING 1ST INT.- BS ASTM A-376 0.365" 10 10" SCH 40 CR3-P38-APIPING TP 304

1ST INT.- DH ASME SA-40719 PIPING IPING 37 TP 304 0.375 12 12" SCH 40 CR3-P39-APIPING 376 TP 304

40720 PIPING 12" DECAY ASTM A-376 1.312 12 12" SCH 160 CR3-P40-AHEAT TP 316

2-35Revision 0



Cal. Block Type Description Material I Thick. Dia. Size DrawingNumber j I I I I I 1 I

40721 PIPING 14" CORE ASTM A-376 1.406 14 14" SCH 160 CR3-P41-AFLOOD TP 304

1ST INT.- MS ASTM40722 PIPING IPING A5/0 0.28 6 6" SCH 40 CR3-P42-APIPING A53/106

40723 PIPING 1ST INT.- MS ASTM A106 0.432 6 6" SCH 80 CR3-P43-APIPING

40724 PIPING 1ST INT.- F SA106 GR. B 0.5 10 10" SCH 80 CR3-P44-APIPING

40725 PIPING IST INT.- SA106 GR. B 0.719 10 10" SCH 100 CR3-P45-A

40726 PIPING 1ST INT.- 18" ASME 0.938 18 18" SCH 80 CR3-P46-A

FW PIPING SA106B1ST INT.- 18" ASTM A 106-

40727 PIPING 1S INT 67 1.156 18 18" SCH 140 CR3-P47-AMS PIPING 67 ___ __________

40728 PIPING 24" MS PIPING ASTM A 106- 0.969 24 24" SCH 60 CR3-P48-A68

40729 PIPING 1ST INT.- 14" ASTM A312 0.25 14 14" SCH 10 CR3-P49-ABS PIPING TP304

40730 VESSEL 3/4" THICK CS SA-306 0.75 0 7"L X I"W CR3-M21-BBLOCK GR.50

40731 VESSEL 1.5" CS BLOCK SA-306 GR. 1.5 0 12"L X CR3-M18-B50 1½2"W

40732 STUD 1ST INT.- RPV SA-540 GR. 30 5.75 5.75"DIA x CR3-M23-BSTUD CAL STD B-23 30"L

"A"40733 NUT 1ST INT.- RPV SA-540 GR. 7.875 8.5 7.875"L X CR3-M22-B

CASTELLATED B-23 8.5"WNUT 1

40734 PIPING SS RC PIPING SA-479 3 0 12"L X 3"W CR3-M27-BTP304

40735 VESSEL 3/4" THICK SS A-316 0.75 0 7"L X I"W CR3-M19-BBLOCK

40736 VESSEL DH COOLER ASTM A-316 1.5 0 8"L X 1½"W CR3-M20-B

40737 PIPING DH PIPING SA-312 0.375 14 14" SCH CR3-P50-ATP340 STD

40738 STUD 1ST INT.- 5" SA 540 Gr. 5 5.75 5.75"Dia X CR3-M23-BRPV STUD STD B-23 30"L

"B"40739 PIPING 1ST INT.- 14" SA106 0.75 14 14" SCH 80 CR3-M30-A

SCH 80 PIPING40740 PIPING 18" DH COOLER SA376 TP 0.75 18 18" SCH 60 CR3-M31-A

PIPING 304 140741 PIPING 5" FW HEADER SA106 GR. A 0.75 5 5" SCH XX CR3-M32-A

BRANCH PIPE40742 PIPING 6" SCH-160 MS SA106 GR. B 0.75 6 6" SCH 160 CR3-M33-A

PIPING

2-36Revision 0


TABLE 2.4-8

ASME SECTION XI UT CALIBRATION BLOCKS

Cal. Block Type Description Material Thick. Dia. Size DrawingNumber l

40743 COMP. RCP MOTOR SA7283-D 7.5 65 65" DIA. CR3-M37-AFLYWHEEL _

40744 PIPING 2.8" SS SA-312 0.75 2.8 2½" XX CR3-M34-AWELDOLETS TP316ON DRAINS

40745 PIPING 1ST INT.- 14" SA-312 0.75 14 14" SCH 60. CR3-M35-ASCH-80 SS STD. TP316

40746 STUD 1ST INT.- MSIV SA-193 GR- 13.75 2 2 DIA. x NOT USEDBONNET STUD 87 13.75"L

40747 PIPING 6" SCH-160 CS SA-106 GR-B 1.5 6 6" SCH XX CR3-M36-ASTD

40748 COMP. IST INT.- CS CLAD 0.56 4 4" SCH XX CR3-M44-BCRDM FLANGE TO SSTO TUBE WELD

40749 COMP. 1ST INT.- - CS CLAD 0.325 4 4" SCH 80 CR3-M46-ACRDM CENTER TO SS

WELD40750 COMP. 1ST INT.- SS 0.375 4 4" SCH 80 CR3-M45-A

CRDM ENDCAP WELD

40751 COMP. 1ST INT.- CRD 304SS 0.625 4 4" SCH XX CR3-M49-CSTANDARD

40752 VESSEL 3" CS CAL STD SA-306 3 0 8" L x 4.3"W CR3-M25-B

40753 PIPING 3" RCS PIPING SA-515 GR. 3 0 12"L x 6" W CR3-M24-B60

W/CLADDING

40754 VESSEL OTSG SHELL SA-516 GR 7 0 21 "L x 7"W CR3-M59-BTO TUBESHEET 70 _ _o

40754-A VESSEL OTSG SHELL SA-516 GR 7 0 21"L x 7"W B&WTO TUBESHEET 70 1230624

40755 VESSEL OTSG SHELL SA-516 GR 5 0 15"L x 6"W CR3-M60-BTO SHELL 70

40756 VESSEL ARIS NOZZLE A-508-64 12 0 36"L x 8"W CR3-M92-ATO VESSEL / CL2FLANGE TO

VESSEL

40757 VESSEL ARIS NOZZLE A-508-64 18 0 45"L x 8"W CR3-M93-ATO VESSEL / CL2FLANGE TO

VESSEL

40758 STUD 1ST INT.- OTSG, SA-320 GR 13.5. 2 2"DIA x B&WPRIMARY 643 13.5"L 1120120MANWAY

STUD I

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Cal. Block Type Description Material Thick.I Dia. Size DrawingNumber I I I I I

40760 STUD 1STINT.- OTSG SA-320 GR 7.5 1.25 1.25"DIA x B&W 10122SECONDARY L43 7.5"L

MANWAYSTUD

40761 STUD 1ST INT.- RCP A540 GR. 0 N/A B&WSTUD- B23 CL.1 1123041

REPLACED

40762 VESSEL NEAR SA-533 GR B 4 0 14"L x 6"W CR3-M98-ASURFACE CAL

STD 5" - 9"THICK

40763 VESSEL NEAR SA-508 CL2 4 0 14"L x 6"W CR3-M99-ASURFACE CALSTD 12" THICK

40764 STUD 1ST INT.- PZR SA-320 GR 14.95 2.75 2.75"DIA. X CR3-T-517MANWAY L43' 14.95"L

STUD

40765 STUD 1ST INT.- 2 IN. SA-320 GR 16.375 2 2"DIA. X NOT USEDPZR HEATER L43 16.375"L

BUNDLE STUD I40765A STUD THERMAL A-453 GR 5.125 1.3 1.3"DIA. X B&W

SHIELD BOLT 660 5.125"L 114146340765B STUD THERMAL A-453 GR 5.125 1.3 1.3" DIA x B&W

SHIELD BOLT 660 5.125"L 114146440770 PIPING 4" SPRAY A376 TP 316 0.438 4 4" SCHI20 CR3-M94-A

PIPING40771 PIPING 5" MU PIPING A312 TP 304 0.625 5 5" SCH 160 CR3-M95-A

40772 PIPING 14" FW PIPING A106 GR. B 0.75 14 14" SCH 80 CR3-M96-A

40773 PIPING 18" FW PIPING A106 GR. B 0.938 18 18" SCH 80 CR3-M97-A

41502 VESSEL Pressurizer Spray CLAD A 508 0.64 4 6 5/8" dia. x B&W 415021BWOG #1 Nozzle CL. 1A 13.4"L

41502 VESSEL Pressurizer Spray CLAD A 508 0.64 4 6 5/8" dia. x B&W 415022BWOG #2 Nozzle CL. IA 13.4"L

41503 VESSEL Pressurizer Relief CLAD A 508 2 2.5. 7 1/8" dia. x B&W 415031BWOG#1 Nozzle CL. 1A 17.5"L

41503 VESSEL Pressurizer Relief CLAD A 508 2 2.5 7 1/8" dia. x B&W 415032BWOG #2 Nozzle CL. IA 17.5"L

41504 VESSEL Pressurizer Surge CLAD A 508 3 10 15.25" dia. x B&W 415041BWOG #1 Nozzle CL. IA 12.5"L

41504 VESSEL Pressurizer Surge CLAD A 508 3 10 15.25" dia. x B&W 415042BWOG #2 Nozzle CL. IA 12.5"L

500-1 (SS) PIPING 3" HPI PIPING SA 312 TP 0.438 3 3" Sch 160 CR3-T-500304 SS

501-1 (CS) FLAT CS SURFACE 1018 Carbon 0.73 0 9"L x 4"W CR3-T-501ET STD Steel

2-38Revision 0



Cal. Block Type Description Material Thick. Dia. Size DrawingNumber I D Mt I 1 I a i 1

502-1 STUD MS STEPPED SA-193 GR. 14.5 2.25 2.25"DIA x CR3-T-502STUD - DEMO B7 14.5"L SHT1

ONLY502-2 STUD MS STEPPED SA-193 GR. 14.5 2.25 2.25"DIA x CR3-T-502

CAL STUD B7 14.5"L SHT2502-3 STUD MS STEPPED SA-193 GR. 14.5 2.25 2.25"DIA x CR3-T-502

QUAL STUD B7 14.5"L SHT3503-1 (SS) PIPE 2.5" BPI PIPING SA 312 TP 0.375 2.5 2 1/2" SCH. CR3-T-503

304SS 160504-1 STUD RPV CLOSURE A540 GR. 23 57.575 6.25 6.25"DIA x CR3-T-504

STUD 57.575"L505-1 (CS) PIPING ALT ASME CAL A516-70 0.5 - 0 2"W x 10"L CR3-T-505

BLOCK - A516 2.0 SHT3

505-2 (SS) PIPING ALT ASME CAL 304 SS 0.5 - 0 2"W x 10"L CR3-T-505BLOCK - T304 2.0 SHT1

505-3 (SS) PIPING ALT ASME CAL 316 SS 0.5 - 0 2"W x 10"L CR3-T-505BLOCK - T316 2.0 SHT2

506-1 (SS) FLAT SS SURFACE ET 304 SS 0.73 0 9"L x 4"W CR3-T-506STD

508-1 PIPING 10" SURGE CLAD ASTM 1 10 10" SCH 140 CR3-T-508LINE NOZZLE A106 GR. B

509-1 PIPING 12" DH DROP CLAD ASTM 1.312 12 12" SCH 160 CR3-T-509LINE NOZZLE A106 GR. B

510-1 PIPING 2.5" HPI SAFE SA 336, F316 0.75 2.5 2 1/2" SCH CR3-T-510END _ XX

511-1 PIPING 4" SPRAY LINE SB166 0.438 4 4" SCH 120 CR3-T-511NOZZLE ALLOY 600

512-1 STUD PZR MANWAY A540 GR. 23 14.875 2.75 2.75" DIA. x CR3-T-512STUD 14.875"L

513-1 STUD RCP STUD A540 GR. 37 4.8 4.8"DIA. x CR3-T-513B23 CL.1 371"

CSS- FLAT CSS SURFACE CAST SS CF- 1 0 11.5"L x CR3-T-516970910 ET STD 3 4.5"W

UTLW-I SIZING SS SIZING 304 SS 3 0 30"L x I"W CR3-T-514BLOCK

UTLW-6 SIZING CS SIZING 1018 2 0 15"L x 2"W CR3-T-515BLOCK

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2.5 Technical Approach and Positions

When the requirements of ASME Section XI are not easily interpreted, CR3 hasreviewed general licensing/regulatory requirements and industry practice todetermine a practical method of implementing the Code requirements. TheTechnical Approach and Position (TAP) documents contained in this section havebeen provided to clarify CR3's implementation of ASME Section XI requirements.An index which summarizes each technical approach and position is included inTable 2.5-1. The "07-XXX-TA" format for technical approach and positionsshould be numbered starting with the last 2 digits of the year written andnumbered consecutively beginning with 001. This section is reserved for sitespecific issues. Corporate Policy statements will be tracked and maintained by theCorporate Staff.

2-40Revision 0


TABLE 2.5-1TECHNICAL APPROACH AND POSITIONS INDEX

Position Revision Status1 (Program) Description of TechnicalNumber Date2 Approach and Position

0 (SPT) System Leakage Testing of Non-Isolable07-001-TA Active Bre opnns09/26/07 Buried Components.

0 (SPT) Valve Seats as Pressurization07-002-TA Active Bonais09/26/07 Boundaries.

Note 1: Technical Approach and Position Status Options: Active - Current ISI Program technical approach andposition is being utilized at CR3; Deleted - Technical approach and position is no longer being utilized atCR3.

Note 2: The revision listed is the latest revision of the subject technical approach and position. The date noted inthe second column is the date of the ISI Program Plan revision when the technical approach and positionwas incorporated into the document.

2-41Revision 0


TECHNICAL APPROACH AND POSITION NUMBER 07-001-TARevision 0

COMPONENT IDENTIFICATION:

Code Class: 2 and 3Reference: IWA-5244(b)(2)Examination Category: C-H, D-BItem Number: C7.10, D2.10Description: System Leakage Testing of Non-Isolable Buried ComponentsComponent Number: Non-Isolable Buried Pressure Retaining Components

CODE REQUIREMENT:

IWA-5244(b)(2) requires non-isolable buried components be tested to confirm that flow duringoperation is not impaired.

POSITION:

Article IWA-5000 provides no guidance in setting acceptance criteria for what can be considered"adequate flow". In lieu of any formal guidance provided by the Code, CR3 has established thefollowing acceptance criteria:

For opened ended lines on systems that require Inservice Testing (IST) of pumps,adherence to IST acceptance criteria is considered as reasonable proof of adequateflow through the lines.

For lines in which the open end is accessible to visual examination while the systemis in operation, visual evidence of flow discharging the line is considered asreasonable proof of adequate flow through the open ended line.

For open ended portions of systems where the process fluid is pneumatic, evidenceof gaseous discharge shall be considered reasonable proof of adequate flow throughthe open ended line. Such test may include passing smoke through the 'line, hangingballoons or streamers, using a remotely operated blimp, using thermography todetect hot air, etc.

This acceptance criteria will be utilized in order to meet the requirements of IWA-5244(b)(2).

CR3's position is that proof of adequate flow is all that is required for testing these open endedlines and that no further visual examination is necessary. This is consistent with the requirementsfor buried piping, which is not subject to visual examination.

2-42


TECHNICAL APPROACH AND POSITION NUMBER 07-002-TARevision 0

COMPONENT IDENTIFICATION:

Code Class:Reference:

Examination Category:Item Number:Description:Component Number:

CODE REQUIREMENT:

1, 2, and 3IWA-5221IWA-5222B-P, C-H, D-BB15.10, C7.10, D2.10Valve Seats as Pressurization BoundariesAll Pressure Testing Boundary Valves

IWA-5221 requires the pressurization boundary for system leakage testing extend to those pressureretaining components under operating pressures during normal system service.

POSITION:

CR3's position is that the pressurization boundary extends up to the valve seat of the valve utilizedfor isolation. For example, in order to pressure test the Class 1 components, the valve that providesthe Class break would be utilized as the isolation point. In this case the true pressurizationboundary, and Class break, is actually at the valve seat.

Any requirement to test beyond the valve seat is dependent only on whether or not the piping on theother side of the valve seat is ISI Class 1, 2, or 3.

In order to simplify examination of classed components, CR3 will perform a VT-2 visualexamination of the entire boundary valve body and bonnet (during pressurization up to the valveseat).

.2-43


3.0 COMPONENT ISI PLAN

The CR3 Component ISI Plan includes ASMIE Section XI nonexempt pressure retainingwelds, piping structural elements, pressure retaining bolting, attachment welds, pumpcasings, valve bodies, reactor pressure vessel interior, reactor pressure vessel welded coresupport structures, and reactor pressure vessel interior attachments of ISI Class 1, 2, and 3components that meet the criteria of IWA-1300. The term "Nonexempt" is used here tomean components which are not exempt per ASME Section XI Articles IWB(C)(D)-1220. All Class 1, 2, and 3 components are identified on the P&IDs listed in Section 2.3,Table 2.3-1. This Component ISI Plan also includes component augmented inserviceinspection program information specified by documents other than ASME Section XI.

3.1 Nonexempt ISI Class Components

The CR3 ISI Class 1 components subject to examination are those which are notexempted under the criteria of Subarticle IWB-1220 in the 1989 Edition, NoAddenda of ASME Section XI (see Section 3.1.2 below). The ISI Class 2 and 3components identified on ISI Isometrics and Component Drawings are those notexempted under the criteria of Subarticles IWC-1220 and IWD-1220 of ASvIESection XI. A summary of CR3 ASME Section XI nonexempt components isincluded in Section 7.0.

3.1.1 Identification of ISI Class 1, 2, and 3 Nonexempt Components

ISI Class 1, 2, and 3 components arie identified on the ISI Isometrics andComponent Drawings listed in Section 2.4, Tables 2.4-1, 2.4-2, 2.4-3,2.4-4, 2.4-5, and 2.4-6. Welded attachments are also identified bycontrolled CR3 support drawings.

3.1.2 10CFR50.55a(b)(2)(xi) specifies that the 1989 Edition, No Addenda ofASME Section XI, Subarticle IWB-1220 shall be used in lieu of the 2001Edition through the 2003 Addenda of ASME Section XI, SubarticleIWB-1220.

IWB-1220, Components Exempt from Examination - The followingcomponents (or parts of components) are exempted from the volumetricand surface examination requirements of IWB-2500 per the Codeparagraph referenced:

(a) Components that are connected to the reactor coolant system andpart of the reactor coolant pressure boundary, and that are of sucha size and shape so that upon postulated rupture the resultingflowof coolant from the reactor coolant system under normal plantoperating conditions is within the capacity of makeup systemswhich are operable from on-site emergency power;

3-1Revision 0


(b)(1) piping of Nominal Pipe Size (NPS) 1 and smaller, except for steamgenerator tubing;

(b)(2) components and their connections in piping of NPS 1 and smaller;

(c) reactor pressure vessel head connections and associated piping,NPS 2 and smaller, made inaccessible by control rod drivepenetrations.

3.2 Risk-Informed Examination Requirements

Piping structural elements that fall under RISI Examination Category R-A are riskranked as High (1, 2, and 3), Medium (4 and 5), and Low (6 and 7). Per the EPRITopical Report TR-1 12657, Rev. B-A and Code Case N-578-1, piping structuralelements ranked as High or Medium Risk are subject to examination while pipingstructural elements ranked as Low Risk are not subject to examinations (exceptfor pressure testing). Thin wall welds that were excluded from volumetricexamination under ASME Section XI rules per Table IWC-2500-1 are included inthe element scope that is potentially subject to RISI examination at CR3.

Piping structural elements may be excluded from examination (other than pressuretesting) under the RISI Program if the only degradation mechanism present for agiven location is inspected for under certain other CR3 programs such as the FlowAccelerated Corrosion (FAC) program. These piping structural elements willremain part of the FAC program which already perform "for cause" inspections todetect these degradation mechanisms. Piping structural elements susceptible toFAC along with another degradation mechanism (e.g., thermal fatigue) areretained as part of the RISI scope and are included in the element selection for thepurpose of performing exams to detect the additional degradation mechanism.The RISI Program element examinations are performed in accordance with ReliefRequest 07-001-11.

3-2Revision 0


4.0 SUPPORT ISI PLAN

The CR3 Support ISI Plan includes the supports of ASME Section XI nonexempt ISIClass 1, 2, and 3 components as described in Section 3.0. The term "Nonexempt" is usedhere to mean components which are not exempt per ASME Section XI articles IWF-1230.

4.1 Nonexempt ISI Class Supports

The CR3 ISI Class 1, 2, and 3 nonexempt supports are those which do not meetthe exemption criteria of Subarticle IWF-1230 of ASME Section XI. A summaryof CR3 ASME Section XI nonexempt supports is included in Section 7.0.

4.1.1 Identification of ISI Class 1, 2, and 3 Nonexempt Supports

ISI Class 1, 2, and 3 supports are identified on the ISI Isometrics andComponent Drawings listed in Section 2.4, Tables 2.4-3, 2.4-5, and 2.4-6.Supports are identified by controlled CR3 individual support detaildrawings.

4.2 Snubber Examination and Testing Requirements

4.2.1 ASME Section XI Paragraphs IWF-5200(a) and (b) and IWF-5300(a) and(b) require VT-3 Visual Examination and Inservice Tests of snubbers to beperformed in accordance with the Operation and Maintenance of NuclearPower Plants (OM), Standard ASME/ANSI OM, Part 4. As allowed by10CFR50.55a(b)(3)(v), CR3 will use Subsection ISTD, "Inservice Testingof Dynamic Restraints (Snubbers) In Light Water Reactor Power Plants,"ASME OM Code, 2001 Edition through the 2003 Addenda, to meet therequirements in ASME Section XI Paragraphs IWF-5200(a) and (b) andIWF-5300(a) and (b).

The ASME Section XI ISI Program uses Subsection IWF to definesupport inspection requirements. The ISI Program maintains the CodeClass snubbers in the populations subject to inspection per SubsectionIWF. This is done to accommodate scheduling and inspectionrequirements of the related attachment hardware per Paragraphs IWF-5200(c) and IWF-5300(c). (See Section 4.2.2 below.)

4.2.2 ASME Section XI Paragraphs IWF-5200(c) and IWF-5300(c) requireintegral and non-integral attachments for snubbers to be examined inaccordance with Subsection IWF of ASME Section XI. This results inVT-3 visual examination of the snubber attachment hardware includingthe bolting, pins, and their interface to the clamp, but does not include thecomponent-to-clamp interface.

4-1Revision 0


The ASME Section XI ISI Program uses Subsection IWF to define theinspection requirements for all Class 1, Class 2, and Class 3 supports,regardless of type. The ISI Program maintains the Code Class snubbers inthe support populations subject to inspection per Subsection IWF. This isdone to facilitate scheduling and inspection requirements of the snubberattachment hardware (e.g., bolting and pins) per IWF-5200(c) andIWF-5300(c).

It should be noted that the examination of snubber welded attachmentswill be performed in accordance with the ASME Section XI SubsectionsIWB, IWC, and IWD welded attachment examination requirements (e.g.;Examination Categories B-K, C-C, and D-A).

4-2Revision 0

ISI Program Plan


5.0 SYSTEM PRESSURE TESTING ISI PLAN

The CR3 System Pressure Testing (SPT) ISI Plan includes all pressure retaining ASMIESection XI ISI Class 1, 2, and 3 components, with the exception of those specificallyexempted by Paragraphs IWA-51 10(c), IWC-5222(b), and IWD-5240(b). All RISI pipingstructural elements, regardless of risk classification, are subject to pressure testing as part ofthe current ASME Section XI program.

The SPT ISI Plan performs system pressure tests and visual inspections on the ISI Class1, 2, and 3 pressure retaining components to verify system and component structuralintegrity. This program conducts both Periodic and Interval (10-Year frequency) pressuretests as defined in ASME Section XI Inspection Program B. In addition to the ASMIESection XI requirements, CR3's SPT ISI Plan also includes augmented examinationcommitments.

5.1 ISI Class Systems

All Class 1 pressure retaining components, typically defined as the reactor coolantpressure boundary, are required to be tested. Those portions of Class 2 and 3systems that are required to be tested include the pressure retaining boundaries ofcomponents required to operate or support the system safety functions. Class 2and 3 open ended discharge piping and components are excluded from theexamination requirements per IWC-5222(b) and IWD-5240(b).

5.1.1 Identification of Class 1, 2, and 3 Components

All components subject to ASME Section XI System Pressure Testing andaugmented pressure testing are shown on the P&IDs listed in Section 2.3,Table 2.3-1.

5.1.2 Identification of System Pressure Tests

Individual tests and test segments are identified and maintainedin the CR3ISI Database.

5.2 Risk-Informed Examinations of Socket Welds

Socket welds selected for examination under the RISI program are to be inspectedwith a VT-2 visual examination each refueling outage per ASME Code CaseN-578-1 (see footnote 12 in Table 1 of the Code Case). To facilitate this, socketwelds selected for inspection under the RISI program shall be pressurized eachrefueling outage in accordance with Paragraph IWA-521 1(a).

5-1Revision 0

ISI Program Plan


6.0 CONTAINMENT ISI PLAN

The CR3 Containment ISI Plan includes nonexempt ASME Section XI CISI Class MCpressure retaining components and their integral attachments, and Class CC componentsand structures, and post-tensioning systems that meet the criteria of Subarticle IWA-1300.The term "Nonexempt" is used here to mean components which are not exempt perASME Section XI articles TWE(L)-1220. This Containment ISI Plan also includesinformation related to augmented examination areas, component accessibility, andexamination review.

6.1 Nonexempt CISI Class Components

The CR3 CISI Class MC and CC components identified on the CISI ReferenceDrawings are those not exempted under the criteria of Subarticles IWE-1220 andIWL-1220 in the 2001 Edition through the 2003 Addenda of ASME Section XI.A summary of CR3's ASME Section XI nonexempt CISI components is includedin Section 7.0.

The process for scoping CR3 components for inclusion in the Containment ISIPlan is included in the containment sections of the ISI Classification BasisDocument. These sections include a listing and detailed basis for inclusion ofcontainment components.

Components that are classified as Class MC and CC must meet the requirementsof ASME Section XI in accordance with 1OCFR50.55a(g)(4). Supports of IWEcomponents are not required to be examined in accordance with10CFR50.55a(g)(4).

6.1.1 Identification of ISI Class MC and CC Nonexempt Components

ISI Class MC and CC components are identified on the CISI ReferenceDrawings listed in Section 2.4, Table 2.4-7.

6.1.2 Identification of ISI Class MC and CC Exempt Components

Certain containment components or parts of components may be exemptedfrom examination based on design and accessibility per the requirementsof TWE-1220 and IWL-1220.

6.2 Augmented Examinations Areas

Metal containment components potentially subject to augmented examination perIWE-1240 have been evaluated in the containment sections of the ISIClassification Basis Document. These sections define the areas that are subjectedto augmented examination.

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ISI Program Plan


Similarly, concrete surfaces may be subject to Detailed Visual examination inaccordance with 1WL-2310, if declared to be 'Suspect Areas' by the examiner orthe Responsible Engineer.

No significant conditions were identified in the First CISI Interval and nosignificant conditions are currently identified in the Second Interval as requiringapplication of additional augmented examination requirements under FWE-1240or IWL-23 10.

6.3 Component Accessibility

Class MC pressure retaining components subject to examination shall remainaccessible for either direct or remote visual examination from at least one side perthe requirements of ASME Section XI, Subarticle IWE-1230.

6.4 Responsible Individual and Engineer

ASME Section XI Subsection IWE requires the Responsible Individual to beinvolved in the development, performance, and review of the CISI examinations.The Responsible Individual shall meet the requirements of ASME Section XI,Subarticle IWE-2320.

ASME Section XI Subsection JWL requires the Responsible Engineer to beinvolved in the development, approval, and review of the CISI examinations. TheResponsible Engineer shall meet the requirements of ASME Section XI,Subarticle IWL-2320.

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7.0 COMPONENT SUMMARY TABLES

7.1 Inservice Inspection Summary Tables

The following Table 7.1 provides a summary of the ASME Section XI pressureretaining components, supports, containment structures, post-tensioning systems,system pressure testing, and augmented program components for the FourthInservice Inspection Interval and the Second Containment Inservice InspectionInterval at CR3.

The format of the Inservice Inspection Summary Tables is as depicted below andprovides the following information:

Examination Item Number (or Description Exam Total Number of Relief Request/ NotesCategory (with Risk Category Requirements Components by TAP NumberExamination Number or System

Category AugmentedDescription) Number)

(1) (2) I (3) I (4) J (5) (6) (7)

(1) Examination Category (with Examination Category Description):

Provides the Examination Category and description as identified in ASMESection XI, Tables IWB-2500-1, IWC-2500-1, IWD-2500-1, IWE-2500-1,IWF-2500-1, and IWL-2500-1.

Examination Category "R-A" from Code Case N-578-1 is used in lieu of ASMESection XI Examination Categories B-F and B-J to identify Class 1 pipingstructural elements for the RISI program. Only those Examination Categoriesapplicable to CR3 are identified.

Examination Category "AUG" is used to identify Augmented ISI examinationsand other CR3 commitments.

(2) Item Number (or Risk Category Number or Augmented Number):

Provides the Item Number as identified in ASME Section XI, TablesIWB-2500-1, IWC-2500-1, IWD-2500-1, IWE-2500-1, IWF-2500-1, andIWL-2500-1. Only those Item Numbers applicable to CR3 are identified.

For piping structural elements under the RISI program, the Risk Category Number(1-5) is used in place of the Item Number.

Specific abbreviations such as AUG7.3, AUG7.5, AUG7.6, AUG7.7, andMRP200405 have been developed to identify Augmented ISI examinations andother CR3 commitments.

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(3) Item Number (or Risk Category Number or Augmented Number) Description:

Provides the description as identified in ASME Section XI, Tables IWB-2500-1,1WC-2500-1, IWD-2500-1, JWE-2500-1, IWF-2500-1 and IWL-2500-1.

For Risk-Informed piping examinations, a description of the Risk CategoryNumber is provided.

For augmented inspection commitments, a description of the augmentedrequirement is provided.

(4) Examination Requirements:

Provides the examination methods required by ASME Section XI, TablesIWB-2500-1, IWC-2500-1, IWD-2500-1, LWE-2500-1, IWF-2500-1, andIWL-2500-1.

Provides the examination requirements for piping structural elements under theRISI Program that are in accordance with the EPRI Topical Report TR- 112657,Rev. B-A and Code Case N-578-1.

Provides the examination requirements for augmented components from CR3commitments or relief requests.

(5) Total Number Of Components by System

Provides the system designator (abbreviations). See Section 2.3, Table 2.3-1 for alist of these systems.

This column also provides the number of components within a particular systemfor that ASME Section XI Item Number, Risk Category Number, or AugmentedNumber.

Note that the total number of components by system are subject to change aftercompletion of plant modifications, design changes, and ISI system classificationupdates.

(6) Relief Request/Technical Approach & Position Number

Provides a listing of Relief Request/TAP Numbers applicable to specificcomponents, the ASME Section XI Item Number, Risk Category Number, orAugmented Number. Relief Requests and TAPs that generically apply to allcomponents, or an entire class are not listed. If a Relief Request/TAP Number isidentified, see the corresponding relief request in Section 8.0 or the TAP Numberin Section 2.5.

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(7) Notes

Provides a listing of program notes applicable to the ASME Section XI ItemNumber, Risk Category Number, or Augmented Number. If a program notenumber is identified, see the corresponding program note in Table 7.1-2.

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TABLE 7.1-1INSERVICE INSPECTION SUMMARY TABLE

Examination Category Item Description Exam Total Number of Relief Request/ Notes(with Examination Category Number Requirements Components by TAP Number

Description) SystemB-A B 1.11 Circumferential Shell Welds (Reactor Vessel) Volumetric RC: 4

Pressure Retaining Welds B 1.12 Longitudinal Shell Welds (Reactor Vessel) Volumetric RC: 4in Reactor Vessel B 1.21 Circumferential Head Welds (Reactor Vessel) Volumetric RC: 1

B 1.30 Shell-to-Flange Weld (Reactor Vessel) Volumetric RC: 1B-B B2.11 Circumferential Shell-To-Head Welds (Pressurizer) Volumetric RC: 2

Pressure Retaining Welds in B2.12 Longitudinal Shell-To-Head Welds (Pressurizer) Volumetric RC: 3Vessels Other Than 1B2.40 Tube Sheet-To-Head Weld (Steam Generator) Volumetric RC: 4

Reactor VesselsB-D B3.90 Nozzle-to-Vessel Welds (Reactor Vessel) Volumetric RC: 8

Full Penetration Welds B3.100 Nozzle Inside Radius Section (Reactor Vessel) Volumetric RC: 8of Nozzles in Vessels B3.1 10 Nozzle-to-Vessel Welds (Pressurizer) Volumetric RC: 5

B3.120 Nozzle Inside Radius Section (Pressurizer) Volumetric RC: 5 9B3.130 Nozzle-to-Vessel Welds (Steam Generator) Volumetric RC: 6B3.140 Nozzle Inside Radius Section (Steam Generator) Volumetric RC: 6 9

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Description) System

B-G-1 B6.10 Closure Head Nuts (Reactor Vessel) Visual, VT-1 RC: 60Pressure Retaining B6.20 Closure Studs (Reactor Vessel) Volumetric RC: 60

Bolting, Greater Than B6.40 Threads in Flange (Reactor Vessel) Volumetric RC: 602 in. In Diameter B6.50 Closure Washers (Reactor Vessel) Visual, VT-I RC: 60

B6.60 Bolts & Studs (Pressurizer) Volumetric RC: 1B6.70 Flange Surface, when connection disassembled (Pressurizer) Visual, VT-i RC: 1B6.80 Nuts, Bushings, and Washers (Pressurizer) Visual, VT-I RC: 1B6.180 Bolts & Studs.(Pumps) Volumetric RC: 4B6.190 Flange Surface, when connection disassembled (Pumps) Visual, VT-I RC: 4B6.200 Nuts, Bushings, and Washers (Pumps) Visual, VT-1 RC: 4

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Description) SystemB-G-2 B7.20 Bolts, Studs, & Nuts (Pressurizer) Visual, VT-1 RC: 3

Pressure Retaining B7.30 Bolts, Studs, & Nuts (Steam Generator) Visual, VT-I RC: 8Bolting, 2 in. and Less B7.50 Bolts, Studs, & Nuts (Piping) Visual, VT-1 MU: 4

In Diameter B7.60 Bolts, Studs, & Nuts (Pumps) Visual, VT-1 RC: 4B7.70 Bolts, Studs, & Nuts (Valves) Visual, VT-1 MU: 13

1 _ I_ RC: 6I B7.80 Bolts, Studs, & Nuts in CRD Housing (Reactor Vessel) Visual, VT-1 RC: 69 8

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Description) SystemB-K B 10.10 Welded Attachments (Pressure Vessels) Surface or RC (PZR): 8

Welded Attachments Volumetric RC (SG): 2for Vessels, Piping, B 10.20 Welded Attachments (Piping) Surface CF: 4Pumps, and Valves DH: 2

MU: 14RC: 5

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Description) SystemB-L-1 B 12.10 Pump Casing welds (Pumps) Visual, VT-I RC: 8

Pressure Retaining Welds

In Pump CasingsB-L-2 B12.20 Pump Casings (Pumps) Visual, VT-3 RC: 8

Pump Casings _ I I IB-M-1 B 12.30 Valve Body Welds (less than NPS 4) (Valves) Surface RC: 6

Pressure Retaining Welds B 12.40 Valve Body Welds (NPS 4 or larger) (Valves) Volumetric DH: nE P In Valve BodiestIB-M-2 B 12.50 Valve Bodies (Exceeding NPS 4) (Valves) Visual, VT-3 CF: 4

Valve Bodies I T DH: 4B-N-i B13.10 Vessel Interior (Reactor Vessel) Visual, VT-3 RC: o

Interior of Reactor Vessel II

B-N-2 B 13.60 Interior Attachments Beyond Beltline Region (Reactor Visual, VT-3 RC: 1Welded Core Vessel)

Support Structures and InteriorAttachments toReactor Vessels

B-N-3 B13.70 Core Support Structure (Reactor Vessel) Visual, VT-3 RC: 1Removable Core Support

Structures

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ISI Program PlanCrystal River Unit 3, -Fourth Interval



Description) _ __System -B-O B 14.10 Welds in CRD Housing (Reactor Vessel) Volumetric or RC: 342

Pressuo Retaining Welds in (10% of Peripheral CRD Housings) SurfaceControl Rod Housings

B-P B115.10 System Leakage Test (IWB-5220) Visual, VT-2 RC: 16 07-001-PTAll Pressure DH: 1 07-002-TA

Retaining Components

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Description) System

C-A C1.10 Shell Circumferential Welds (Pressure Vessels) Volumetric DH: 2Pressure Retaining Welds MS: 8

in Pressure Vessels C 1.20 Head Circumferential Welds (Pressure Vessels) Volumetric DH: 2

C1.30 Tubesheet-to-Shell-Weld Welds (Pressure Vessels) Volumetric MS: 4C-B C2.21 Nozzle-to-Shell (Nozzle to Head or Nozzle to Nozzle) Volumetric & DH: 4

Pressure Retaining Welds Without Reinforcing Plate, Greater Than 1/2" Surface MS: 4Nozzle Welds in Nominal Thickness (Pressure Vessels)

Vessels C2.22 Nozzle Inside Radius Section Without Reinforcing Plate, Volumetric DH: 4

Greater Than 1/2" Nominal Thickness (Pressure Vessels) MS: 4C-C C3.10 Welded Attachments (Pressure Vessels) Surface FW: 16

Welded Attachments C3.20 Welded Attachments (Piping) Surface DH: 8for Vessels, Piping, EF: 19Pumps, and Valves FW: 26

MS: 25MU: 4SW: 12

C-D C4.40 Bolts and Studs (Valves) Volumetric MS: 10Pressure Retaining Bolting

Greater Than 2 in. in Diameter

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Examination Category Item Description Exam Total Number of Relief Request/ Notes(with Examination Category Number Requirements Components by TAP NumberDescription) System

C-F-I C5.11 Circumferential Weld (Piping Welds > 3/8 in. nominal Surface & DH: 196Pressure Retaining Welds in Wall thickness for Piping > NPS 4) (DN 100) Volumetric MU: 4

Austenetic Stainless Steel C5.21 Circumferential Weld (Piping Welds >_ 1/5 in. nominal Surface & DH: 21Or High Alloy Piping Wall thickness for Piping >_ NPS 2 and _ NPS 4) (DN 100) Volumetric MU: 690

C5.30 Socket Welds Surface MU: 61C5.41 Circumferential Weld (Pipe Branch Connections of Surface MU: 3

Branch Piping _> NPS 2) (DN 50)NA Circumferential Welds < 3/8 in. nominal Not Required BS: 75 10

Wall thickness for Piping > NPS 4 (DN 100) DH: 198MU: 103

C-F-2 C5.51 Circumferential Weld (Piping Welds ? 3/8 in. nominal Surface & EF: 148Pressure Retaining Welds in Wall thickness for Piping > NPS 4) (DN 100) Volumetric FW: 142

Carbon or Low Alloy Steel Piping MS: 127C5.81 Circumferential Weld (Pipe Branch Connections of Surface FW: 2

Branch Piping ? NPS 2) (DN 50) MS: 24NA Circumferential Welds < 3/8 in. nominal Not Required SW: 378 10

Wall thickness for Piping > NPS 4 (DN 100) - I I I

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Description) SystemC-H C7.10 System Leakage Test (IWC-5220) Visual, VT-2 BS: 2 07-001-TA

All Pressure CF: 2 07-002-TARetaining Components DH: 9

EF: 6FW: 2MS: 3MU: 6RC: 1SW: 9

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Description) SystemD-A DI.10 Welded Attachments (Pressure Vessels) Visual, VT-I DC: 6

Welded Attachments DH: 2for Vessels, Piping, EF: 1Pumps, and Valves RW: 8

SW: 4D1.20 Welded Attachments (Piping) Visual, VT-I CH: 4

DC: 4EF: 26MS: 14RW: 22SW: 22

D-B D2.10 System Leakage Test (IWD-5221) Visual, VT-2 AS: 1 07-001-TAAll Pressure CA: 1 07-002-TA

Retaining Components CH: 2DC: 2DH: 1DO: 1DJ: 3EF: 7MS: 2MU: 4RC: 2RW: 6SF: 4

SW: 12

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Examination Category Item Description Exam Total Number of Relief Request/ Notes(with Examination Category Number Requirements Components TAP Number

Description)

E-A El. 11 Containment Vessel Pressure Retaining Boundary - General Visual Liner Plates: 26 4Containment Surfaces Accessible Surface Areas Penetrations: 155

Attachments: 867EL .11 Containment Vessel Pressure Retaining Boundary - Visual, VT-3 7 4

Bolted Connections, Surfaces

E1.12 Containment Vessel Pressure Retaining Boundary - Visual, VT-3 Sump: 1 5Wetted Surfaces of Submerged Areas Penetrations: 2

Attachments: 0E-C E4.11 Containment Surface Areas - Visible Surfaces Visual, VT-1 0 6

Containment Surfaces Requiring E4.12 Containment Surface Areas - Surface Area Grid Volumetric 0 7Augmented Examination Grid Line Intersections and Minimum (Thickness)

Wall Thickness Locations

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Examination Category Item Description Exam Total Number of Components by Relief Request/ Notes(with Examination Category Number Requirements System TAP Number

Description) A B CAnchor/Rod Restraint Spring/

SnubberF-A F7.10 Class I Piping Supports Visual, VT-3 CF: 0 CF: 0 CF: 13 1

Supports DH: 0 DH: 1 DH: 14MU: 27 MU: 24 MU: 47RC: 0 RC: 5 RC: 27SW: 0 SW: 1 SW: 0

F1.20 Class 2 Piping Supports Visual, VT-3 BS: 8 BS: 0 BS: 7 1CF: 0 CF: 0 CF: 6

DH: 96 DH: 9 DH: 53EF: 32 EF: 11 EF: 29FW: 7 FW: 0 FW: 68MS: 14 MS: 7 MS: 35

MU: 161 MU: 72 MU: 9SW: 61. SW: 20 SW: 2

F1.30 Class 3 Piping Supports Visual, VT-3 CH: 25 CH: 4 CH: 0 1DC: 48 DC: 5 DC: 15DH: 15 DH: 2 DH: 4

DJ: 0 DJ: 2 DJ: 0EF: 33 EF: 77 EF: 16MS: 2 MS: 4 MS: 29RC: 20 RC: 0 RC: I

RW: 104 RW: 16 RW: 0SW: 215 SW: 43 SW: 25

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Description)F-A F1.40 Supports Other Than Piping Supports Visual, VT-3 DC: 6 07-001-SS

Supports (Class 1, 2, or 3) DH: 5(Continued) EF: 4

MU: 9RC: 19RW: 5SF: 2

SW: 10

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Description)

L-A LI.11 Concrete Surfaces - General Visual 16Concrete Surfaces All Accessible Surface Areas

L1.12 Concrete Surfaces - Detailed Visual -Suspect Areas

L-B L2.10 Tendon IWL-2522 Vertical: 144Unbonded Post-Tensioning System Horizontal: 282

Dome: 123L2.20 Tendon- IWL-2523.2 Vertical: 144

Wire or Strand Horizontal: 282Dome: 123

L2.30 Tendon- Detailed Visual Vertical: 144Anchorage Hardware and Surrounding Concrete Horizontal: 282

Dome: 123L2.40 Tendon- IWL-2525.2(a) Vertical: 144

Corrosion Protection Medium Horizontal: 282Dome: 123

L2.50 Tendon- IWL-2525.2(b) Vertical: 144Free Water Horizontal: 282

I__I _ I_ Dome: 123

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Examination Category Risk Description Exam Total Number of Relief Request/ Notes(with Examination Category Category Requirements Components by TAP Number

Description) Number SystemR-A 2 Risk Category 2 Elements See Notes CF: 4 07-001-I1 2

Risk-Informed Piping DH: 3 3Examinations MU: 13

RC: 414 Risk Category 4 Elements See Notes CF: 11 07-001-Il 2

DH: 7 3MU: 140RC: 183

5 Risk Category 5 Elements See Notes MU: 13 07-001-II 23

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Examination Category Aug Description Exam Total Number of Relief Request/ Notes(with Examination Category Number Requirements Components by TA&P Number

Description) SystemAUG AUG7.3 HPI Thermal Sleeves Volumetric MU: 4

Augmented AUG7.3 MU Nozzles Inner Radius Region (MUV-43) Volumetric MU: 1Components AUG7.5 Inconel 600 components in the Reactor Coolant System Bare Metal RC: 39

Visual (BMV),VT-2

AUG7.5 Inconel 600 Components in the Pressurizer BMV, VT-2 RC: 7AUG7.5 Pressurizer Spray Nozzle Connection Inside Pressurizer Visual, VT-2 RC: 1AUG7.6 Reactor Coolant Pump Flywheels Volumetric or RC: 5

SurfaceAUG7.7 NRC Order E-03-009 Bare Metal RC: 69

VisualAUG7.7 NRC Order E-03-009 Volumetric or RC: 69

SurfaceMRP200405 MRP 200405 Components Visual DH: 1

RC: 16

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TABLE 7.1-2INSERVICE INSPECTION SUMMARY TABLE PROGRAM NOTES

Note # Note Summary1 ISI snubber visual examinations and functional testing are performed in accordance with the ASME OM Code, Subsection ISTD Program. The number of

CR3 supports identified, include snubbers for the visual examination and functional testing of the integral and nonintegral attachments per ParagraphsIWF-5200(c), IWF-5300(c), and IWF-2500(a). The snubbers are scheduled and administratively tracked in the ISI Program; however, the ASME OM Code,Subsection ISTD Program will be the mechanism for actually performing the visual examinations and functional testing scheduled within the ISI Program. Fora detailed discussion of the snubber program, see Section 4.2.

2 For the Fourth Inspection Interval, CR3's Class 1 piping inspection program will be governed by risk-informed regulations. The RISI Program methodology isdescribed in the EPRI Topical Report TR-112657, Rev. B-A and Code Case N-578-1. The RISI Program scope has been implemented as an alternative to the 2001Edition through the 2003 Addenda of the ASME Section XI examination program for Class 1 Examination Category B-F and B-J welds in accordance with10CFR50.55a(a)(3)(i).

3 Examination requirements within the RISI Program are determined by the various degradation mechanisms present at each individual piping structural element. SeeEPRI Topical Report TR- 112657, Rev. B-A and Code Case N-578-1 for specific exam method requirements.

4 Bolted connections examined per Item Number El. 11 require a VT-3 visual examination once per interval and each time the connection is disassembled duringa scheduled Item Number El. 11 exam. Additionally, a VT-1 visual examination shall be performed if degradation or flaws are identified during the VT-3visual examination. These modifications are required by toCFR50.55a(b)(2)(ix)(G) and siCFR50.55a(b)(2)(ix)(H).

5 Item Number El. 12 requires VT-3 visual examination in lieu of General Visual examination, as modified by 10CFR50.55a(b)(2)(ix)(G).6 Item Number E4.11 requires VT- I visual examination in lieu of Detailed Visual examination, as modified by 10CFR50.55a(b)(2)(ix)(G).7 The ultrasonic examination acceptance standard specified in IWE-3511.3 for Class MC pressure-retaining components must also be applied to metallic liners

of Class CC pressure-retaining components, as modified by 10CFR50.55a(b)(2)(ix)(I).

9 Per 1OCFR50.55a(b)(2)(xxi)(B), Table IWB-2500-1 examination requirements, the provisions of Table IWB-2500-1, Examination Category B-G-2, ItemNumber B7.80, that are in the 1995 Edition are applicable only to reused bolting when using the 1997 Addenda through the latest Edition and Addendaincorporated by reference in paragraph (b)(2) of this section.

9 Per 10CFR50.55a(b)(2)(xxi)(A), Table IWB-2500-1 examination requi .rements, the provisions of Table IWB-2500-1, Examination Category B-D, Items

B3.120 and B3.140 in the 1998 Edition must be applied when using the 1999 Addenda through the latest Edition and Addenda, and requires that a visualexamination with enhanced magnification may be performed on the inside radius section in place of an ultrasonic examination.

10 Thin Wall Class 2 (C-F-I and C-F-2) Austenitic Piping: The 2001 Edition through the 2003 Addenda of ASME Section XI requires that Class 2 piping welds> 4" NPS and a wall thickness < 3/8" be included in the population to which the 7.5% examination requirement apply; however, none of these "thin wall"

I welds are required to be examined per C-F-I and C-F-2. The 7.5% is to be comprised of welds > 4" NPS and > 3/8" wall thickness.

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8.0 RELIEF REQUESTS FROM ASME SECTION XI

This section contains relief requests written per 1OCFR50.55a(a)(3)(i) for situationswhere alternatives to ASME Section XI requirements provide an acceptable level ofquality and safety; per 1OCFR50.55a(a)(3)(ii) for situations where compliance withASMESection XI requirements results in a hardship or an unusual difficulty without acompensating increase in the level of quality and safety; and per 1OCFR50.55a(g)(5)(iii)for situations where ASME Section XI requirements are considered impractical.

The following USNRC guidance was utilized to determine the correct 10CFR50.55aparagraph citing for CR3 relief requests. 1OCFR50.55a(a)(3)(i) and1OCFR50.55a(a)(3)(ii) provide alternatives to the requirements of ASME Section XI,while 1OCFR50.55a(g)(5)(iii) recognizes situational impracticalities.

.10CFR50.55a(a)(3)(i):

10CFR50.55a(a)(3)(fi):

Cited in relief requests when alternatives to the ASMESection XI requirements which provide an acceptable levelof quality and safety are proposed. Examples are reliefrequests which propose alternative NDE methods and/orexamination frequency.

Cited in relief requests when compliance with the ASMESection XI requirements is deemed to be a hardship orunusual difficulty without a compensating increase in thelevel of quality and safety. Examples of hardship and/orunusual difficulty include, but are not limited to, excessiveradiation exposure, disassembly of components solely toprovide access for examinations, and development ofsophisticated tooling that would result in only minimalincreases in examination coverage.

Cited in relief requests when conformance with ASMESection XI requirements is deemed impractical. Examplesof impractical requirements are situations where thecomponent would have to be redesigned, or replaced toenable the required inspection to be performed.

10CFR50.55a6!)(5)(ii):

An index for CR3 relief requests is included in Table 8.0-1. The "07-XXX-XX" formatfor relief requests should be numbered starting with the last 2 digits of the year writtenand numbered consecutively beginning with 001 for each of the applicable categories:Pressure Test (PT), ISI and NDE (1I), Steam Generator (SG), Snubbers and Supports(SS), Repair and Replacement (RR), and Miscellaneous (MX).

The following relief requests are subject to change throughout the inspection interval.

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TABLE 8.0-1RELIEF REQUEST INDEX

Relief Revision Status2 (Program) Description/Request Date3 Approval Summary1

(ISI) Alternate Risk-Informed Selection and0 Examination Criteria for Examination Category

09/26/07 B-F and B-J Pressure Retaining Piping Welds.

Revision 0 Submitted.

(ISI) Alternate Examination Criteria for the0 Reactor Vessel Support Skirt to Perform Limited

09/26/07 VT-3 Visual Examination on 3 Areas 1200 Apart

on the Inside Surface. Revision 0 Submitted.

07-001-PT 0 Submitted (SPT) System Pressure Testing Boundary.09/26/07 Revision 0 Submitted.

Note 1: The USNRC grants relief requests pursuant to 1OCFR50.55a(g)(6)(i) when Code requirements cannot bemet and proposed alternatives do not meet the criteria of 1OCFR50.55(a)(3). The USNRC authorizes reliefrequests pursuant to lOCFR50.55a(a)(3)(i) if the proposed alternatives would provide an acceptable level ofquality and safety or under (3)(ii) if compliance with the specified requirements would result in hardship orunusual difficulties without a compensating increase in the level of safety.

Note 2: This column represents the status of the latest revision. Relief Request Status Options: Authorized -Approved for use in an USNRC SER (See Note 1); Granted - Approved for use in an USNRC SER (SeeNote 1); Authorized Conditionally - Approved for use in an USNRC SER which imposes certainconditions; Denied - Use denied in an USNRC SER; Expired - Approval for relief has expired; Withdrawn -Relief has been withdrawn by Crystal River; Not Required - The USNRC has deemed the relief unnecessaryin an SER or RAI; Cancelled - Relief has been cancelled by Crystal River prior to issue; Submitted - Reliefhas been submitted to the USNRC by the station and is awaiting approval.

Note 3: The revision listed is the latest revision of the subject relief request. The date this revision became effectiveis the date of the approving SER which is listed in the fourth column of the table. The date noted in thesecond column is.the date of the ISI Program Plan revision when the relief request was incorporated into thedocument.

8-2Revision 0


1OCFR50.55a RELIEF REQUEST: 07-001-IIRevision 0

(Page 1 of 5)

Request for Relief for Alternate Risk-Informed Selection and Examination Criteria forExamination Category B-F and B-J Pressure Retaining Piping Welds

In Accordance with 10CFR50.55a(a)(3)(i)

1.0 ASME CODE COMPONENTS AFFECTED:

Code Class: 1Examination Category: B-F and B-JItem Number: B5.10, B5.40, B9.11, B9.21, B9.22, B9.31, B9.32, and

B9.40Description: Alternate Risk-Informed Selection and Examination

Criteria for Examination Category B-F and B-J PressureRetaining Piping Welds

Component Number: Pressure Retaining Piping

2.0 APPLICABLE CODE EDITION AND ADDENDA:

The Inservice Inspection program is based on the American Society of MechanicalEngineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, 2001 Editionthrough the 2003 Addenda.

3.0 APPLICABLE CODE REQUIREMENT:

Table TWB-2500-1, Examination Category B-F, requires volumetric and surfaceexaminations on all welds for Item Numbers B5.10 and B5.40.

Table IWB-2500-1, Examination Category B-J, requires volumetric and surfaceexaminations on a sample of welds for Item Numbers B9.11 and B9.31, volumetricexaminations on a sample of welds for Item Number B9.22, and surface examinations ona sample of welds for Item Numbers B9.21, B9.32, and B9.40. The weld populationselected for inspection includes the following:

1. All terminal ends in each pipe or branch run connected to vessels.

2. All terminal ends and joints in each pipe or branch run connected to othercomponents where the stress levels exceed either of the following limits underloads associated with specific seismic events and operational conditions:

a. primary plus secondary stress intensity range of 2.4Sm for ferritic steel andaustenitic steel.


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b. cumulative usage factor U of 0.4.

3. All dissimilar metal welds not covered under Examination Category B-F.

4. Additional piping welds so that the total number of circumferential butt welds,branch connections, or socket welds selected for examination equals 25% of thecircumferential butt welds, branch connection, or socket welds in the reactorcoolant piping system. This total does not include welds exempted by IWB-1220or welds in Item Number B9.22.

5. A 10% sample of PWR high pressure safety injection system circumferentialwelds in piping >_ NPS 1½ and < NPS 4 shall be selected for examination. Thissample shall be selected from locations determined by the Owner as most likely tobe subject to thermal fatigue.

4.0 REASON FOR REQUEST:

Pursuant to 10CFR50.55a(a)(3)(i), relief is requested on the basis that the proposedalternative utilizing Reference 1 along with two enhancements from Reference 4 willprovide an acceptable level of quality and safety.

As stated in "Safety Evaluation Report Related to EPRI Risk-Informed InserviceInspection Evaluation Procedure (EPRI TR-1 12657, Revision B, July 1999)" (Reference2):

"The staff concludes that the proposed RISI program as describedin EPRI TR-1 12657, Revision B, is a sound technical approach andwill provide an acceptable level of quality and safety pursuant to10CFR50.55a for the proposed alternative to the piping ISIrequirements with regard to the number of locations, locations ofinspections, and methods of inspection."

The initial Crystal River RISI Program was submitted during the Second Period of theThird Inspection Interval. This initial RISI program was developed in accordance withEPRI TR-1 12657, Revision B-A, as supplemented by Code Case N-578. The programwas approved for use by the NRC via a Safety Evaluation as transmitted to ProgressEnergy on September 20, 2005 (Reference 5).

The transition from the 1989 Edition to the 2001 Edition through the 2003 Addenda ofASME Section XI for Crystal River's Fourth Inspection Interval does not impact thecurrently approved Risk-Informed ISI evaluation process used in the Third Inspection


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Interval, and the requirements of the new Code edition/addenda will be implemented asdetailed in the Crystal River Unit 3 ISI Program Plan.

The Risk Impact Assessment completed as part of the original baseline RISI Program wasan implementation/transition check on the initial impact of converting from a traditionalASME Section XI program to the new RISI methodology. For the Fourth Interval ISIupdate, there is no transition occurring between two different methodologies, but rather,the currently approved RISI methodology and evaluation will be maintained for the newinterval. As such, the original risk impact assessment process is not impacted by the newinterval and does not require update.

As an added measure of assurance, any new systems, portions of systems, or componentsbeing included in the RISI Program for the Fourth Inspection Interval will be added to theRisk Impact Assessment performed during the previous interval. These components willbe addressed within the evaluation at the start of the new interval to assure that the newFourth Inspection Interval RISI element selection provides an acceptable overall change-in-risk when compared to the old ASME Section XI population of exams which existedprior to the implementation of the first RISI Program.

The actual "evaluation and ranking procedure" including the Consequence Evaluationand Degradation Mechanism Assessment processes of the currently approved (Reference5) RISI Program remain unchanged and are continually applied to maintain the RiskCategorization and Element Selection methods of EPRI TR-1 12657, Revision B-A.These portions of the RISI Program have been and will continue to be reevaluated andrevised as major revisions of the site PRA occur and modifications to plant configurationare made. The Consequence Evaluation, Degradation Mechanism Assessment, RiskRanking, and Element Selection steps encompass the complete living program processapplied under the Crystal River Unit 3 RISI Program.

5.0 PROPOSED ALTERNATIVE AND BASIS FOR USE:

The proposed alternative originally implemented in the "Initial Risk-Informed InserviceInspection Evaluation Submittal, Crystal River Unit 3 (Reference 3), along with the twoenhancements noted below, provide an acceptable level of quality and safety as requiredby 1OCFR50.55a(a)(3)(i). This original program along with these same twoenhancements is currently approved for the Crystal River Unit 3 Third Inspection Intervalas documented in Reference 5.

The Fourth Inspection Interval RISI Program will be a continuation of the currentapplication and will continue to be a living program as described in the Reason ForRequest section of this relief request. No changes to the evaluation methodology as



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currently implemented under EPRI TR- 112657, Revision B-A, are required as part of thisinterval update. The following two enhancements will continue to be implemented.

In lieu of the evaluation and sample expansion requirements in Section 3.6.6.2,"RISI Selected Examinations" of EPRI TR- 112657, Crystal River will utilize therequirements of Subarticle -2430, "Additional Examinations" contained in CodeCase N-578-1 (Reference 4). The alternative criteria for additional examinationscontained in Code Case N-578-1 provides a more refined methodology forimplementing necessary additional examinations.

To supplement the requirements listed in Table 4-1, "Summary of Degradation-Specific Inspection Requirements and Examination Methods" of EPRITR-1 12657, Crystal River will utilize the provisions listed in Table 1,Examination Category R-A, "Risk-Informed Piping Examinations" contained inCode Case N-578-1 (Reference 4). To implement Note 10 of this table,paragraphs and figures from the 2001 Edition through the 2003 Addenda ofASME Section XI (Crystal River Unit 3 code of record for the Fourth InspectionInterval) will be utilized which parallel those referenced in the Code Case for the1989 Edition. Table 1 of Code Case N-578-1 will be used as it provides a detailedbreakdown for examination method and categorization of parts to be examined.

The Crystal River Unit 3 RISI Program, as developed in accordance with EPRITR-1 12657, Rev. B-A (Reference 1), requires that 25% of the elements that arecategorized as "High" risk (i.e., Risk Category 1, 2, and 3) and 10% of the elements thatare categorized as "Medium" risk (i.e., Risk Categories 4 and 5) be selected forinspection. For this application, the guidance for the examination volume for agivendegradation mechanism is provided by the EPRI TR- 112657 while the guidance for theexamination method and categorization of parts to be examined are provided by the EPRITR-112657 as supplemented by Code Case N-578-1.

In addition to this risk-informed evaluation, selection, and examination procedure, allASME Section XI piping components, regardless of risk classification, will continue toreceive Code required pressure testing as part of the current ASME Section XI program.VT-2 visual examinations are scheduled in accordance with the Crystal River Unit 3pressure testing program, which remains unaffected by the RISI program.

6.0 DURATION OF PROPOSED ALTERNATIVE:

Relief is requested for the Fourth Ten-Year Inspection Interval for Crystal River Unit 3.



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7.0 PRECEDENTS:

Similar relief requests have been approved for:

Crystal River Unit 3 Third Inspection Interval Relief Request (Letter 3F1 104-02) wasauthorized per SER dated September 20, 2005. The Fourth Inspection Interval ReliefRequest utilizes an identical RISI methodology as was previously approved.

Susquehanna Steam Electric Station Third Inspection Interval Relief Request 3RR-01was authorized per SER dated July 28, 2005.

Dresden Station Fourth Inspection Interval Relief Request 14R-02 was authorized perSER dated September 4,-2003.

Quad Cities Station Fourth Inspection Interval Relief Request 14R-02 was authorized perSER dated January 28, 2004.

8.0 REFERENCES:

1) Electric Power Research Institute (EPRI) Topical Report (TR) 112657 Rev. B-A,"Revised Risk-Informed Inservice Inspection Evaluation Procedure", December1999

2) W. H. Bateman (NRC) to G. L. Vine (EPRI) letter dated October 28, 1999transmitting "Safety Evaluation Report Related to EPRI Risk-Informed InserviceInspection Evaluation Procedure (EPRI TR- 112657, Revision B, July 1999)"

3) Initial Risk-Informed Inservice Inspection Evaluation Submittal - Crystal RiverUnit 3 (Letter 3F1 104-02, dated November 10, 2004)

4) American Society of Mechanical Engineers (ASME) Code Case N-578-1, "Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B"

5) USNRC Safety Evaluation Report for CR3 RISI Relief Request dated September20, 2005


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Alternate Examination Criteria for the Reactor Vessel Support Skirt to Perform LimitedVT-3 Visual Examination on 3 Areas 1200 Apart on the Inside Surface

In Accordance with 10CFR50.55a(a)(3)(i)


Code Class: 1Examination Category: F-AItem Number: F1.40Description: Alternate Examination Criteria for the Reactor Vessel

Support Skirt to Perform Limited VT-3 Visual Examinationon 3 Areas 120O Apart on the Inside Surface, ExaminationID B1.12.1

Component Number: MK36 to 37




ASME Section XI, Table IWF-2500-1, Examination Category F1.40, requires a VT-3Visual Examination of 100% of the component support.


Pursuant to 1OCFR50.55a(a)(3)(i), relief is requested on the basis that the proposedalternative will provide an acceptable level of quality and safety.

Relief is requested based on the radiation conditions below the reactor vessel whichwould result in significant radiation exposure to inspection and support personnel. Inorder to perform a 100% visual examination, significant preparatory work including theinstallation of temporary lighting, erection of scaffolding, weld preparation, etc. would benecessary. These activities would be carried out around the full circumference of thereactor vessel support skirt interior. Based on previous exposure levels, it is estimatedthat personnel involved in this activity would be exposed to a total dose exceeding 16Rem.


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A VT-3 visual examination will be performed on 10% of the interior of the reactor vesselsupport at 3 positions along the circumference of the reactor vessel support. The samesegments of the support skirt, located 120 degrees apart, that were examined during theFirst, Second, and Third Inspection Intervals, will be examined in the Fourth InspectionInterval.

Previous visual examinations performed during the First, Second, and Third InspectionIntervals indicated that there was no degradation to the vessel support skirt. The locationsselected are the least restrictive in providing access to the support skirt weld area withoutcreating a potential for damage to the incore guide tubes. Examinations performed atthese locations will adequately reveal the condition of the reactor vessel support skirtwithout subjecting personnel to unnecessary radiation exposure.

The proposed alternative examination provides an acceptable level of quality and safetyas defined by 1OCFR50.55a(a)(3)(i).



7.0 PRECEDENTS:

Crystal River Unit 3 Third Inspection Interval Relief Request 98-003-11 was authorizedper SER dated August 5, 1999. The Fourth Inspection Interval Relief Request utilizes anidentical approach as was previously approved.


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Request for Relief for Hardship Or Unusual Difficulty Without Compensating Increase InLevel Of Quality Or Safety for Pressure Testing Boundary

In Accordance with 1OCFR50.55a(a)(3)(ii)


Code Class: 1Reference: IWB-2500, Table IWB-2500-1Examination Category: B-PItem Number: B 15.10Description: Pressure Testing BoundaryComponent Number: Class 1 Pressure Retaining ComponentsDrawing Number: Various




Table TWB-2500-1, Examination Category B-P, Item Number B 15.10, requires all Class1 pressure retaining components be subject to a system leakage test with a VT-2 visualexamination in accordance with IWB-5220. This pressure test is to be conducted prior toplant startup following each reactor refueling outage. The pressure retaining boundary forthe test conducted at or near the end of each inspection interval shall be extended to allClass 1 pressure retaining components per IWB-5222(b).


Pursuant to 10CFR50.55a(a)(3)(ii), relief is requested on the basis that compliance withthe specified requirements would result in hardship or unusual difficulty without acompensating increase in the level of quality and safety.

The many vent, drain, and branch (VTDB) connections 1-inch nominal pipe size (NPS)and smaller off the reactor coolant pressure boundary have double manual isolationvalves. The requirement to extend the system leakage test boundary for the leakage testconducted at or near the end of each inspection interval to the outboard valve on theseVTDB connections result in a hardship without a compensating increase in the level of


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quality and safety. Repositioning the inboard manual valves before and after the test willtake considerable time and will result in an unnecessary increase in dose to plantpersonnel. Manual operation (opening and closing) of the VTDB valves is estimated toexpose plant personnel to 0.5 man-rem per test.


Reactor coolant pressure boundary VTDB connections 1-inch NPS and smaller will bevisually examined for leakage with the inboard isolation valve in the normally closedposition during the system leakage test conducted at the end or near the end of eachinspection interval per 1WB-5222(b). This test provides reasonable assurance ofstructural integrity.

The 1-inch NPS and smaller VTDB connections are normally closed during plantoperation. The outboard valves would only see pressure if the inboard valve is open orleaks by the seat. Seat leakage, although undesirable, is not indicative of a flaw in thepressure boundary. Furthermore, these valves are in close proximity to the main runs ofpipe. The nonisolable portion of these VTDB connections is pressurized and VT-2visually examined during the test. The VT-2 visual examination performed eachrefueling outage extends to the outboard valve, even though it is not pressurized.

The Crystal River Unit 3 technical specifications for reactor coolant pressure boundaryleakage monitoring requires appropriate actions, including plant shutdown if leakageexceeded specified limits. Based on the above criteria, Crystal River Unit 3 requestsauthorization to use the proposed alternative in lieu of the ASME Section XI,IWB-5222(b) requirements.



7.0 PRECEDENTS:

Similar relief requests have been approved for:

Harris Nuclear Plant Second Inspection Interval Relief Request 2R1-015 was authorizedper SER dated April 17, 2006.

Cooper Nuclear Station Fourth Inspection Interval Relief Request PR-1I was authorizedper SER dated October 2, 2006.

ISI Program Plan


9.0 REFERENCES

The references used to develop this Inservice Inspection Program Plan include:

1) Code of Federal Regulations, Title 10, Energy.- Part 50, Paragraph 2, "Definitions", the definition of "Reactor Coolant PressureBoundary".- Part 50, Paragraph 50.55a, "Codes and Standards".- Part 50, Appendix J, Primary Reactor Containment Testing for Water CooledPower Reactors.

USNRC SECY-96-080, Issuance of Final Amendment To 1OCFR50.55a ToIncorporate By Reference The ASME Boiler And Pressure Vessel Code (ASMECode), Section XI, Division 1, Subsection IWE and IWL.

2) ASME Boiler and Pressure Vessel Code, Section XI, Division 1, "InserviceInspection of Nuclear Power Plant Components."- 1974 Edition through the Summer 1975 Addenda.- 1983 Edition through the Summer 1983 Addenda.- 1989 Edition, No Addenda.- 1992 Edition through the 1992 Addenda.- 1995 Edition through the 1996 Addenda.- 1995 Edition through the 1997 Addenda.- 1998 Edition through the 2000 Addenda.- 2001 Edition through the 2001 Addenda.- 2001 Edition through the 2003 Addenda.

3) ASME Boiler and Pressure Vessel Code, Section IIn, Division 1, "Rules ForConstruction of Nuclear Power Plant Components", the 2001 Edition through the2003 Addenda.

4) ASME OM Code, Code For Operation and Maintenance of Nuclear Power Plants,2001 Edition through the 2003 Addenda.

5) USAS B31.1.0-1967, "Power Piping".

6) Regulatory Guide 1.26, Revision 3, "Quality Group Classifications and Standardsfor Water-, Steam-, and Radioactive Waste- Containing Components of NuclearPower Plants".

7) Regulatory Guide 1.14, Revision 1, "Reactor Coolant Pump Flywheel Integrity".

8) Regulatory Guide 1.147 "Inservice Inspection Code Case Acceptability, ASMESection XI, Division 1".

9) Regulatory Guide 1.150, "Reactor Pressure Vessel Ultrasonic Inspection".

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10) Regulatory Guide 1.192, "Operation and Maintenance Code Case Acceptability,ASME OM Code".

11) Regulatory Guide 1.193, "ASME Code Cases Not Approved For Use".

12) USNRC Information Notice IN 90-10, "Primary Water Stress Corrosion Cracking(PWSCC) of Inconel 600".

13) USNRC Information Notice IN 96-11, "Ingress of Demineralizer Resins IncreasesPotential for Stress Corrosion Cracking of Control Rod Drive MechanismPenetrations".

14) USNRC Information Notice IN 97-46, "Unisolable Crack in High PressureInjection Piping".

15) USNRC Bulletin 2002-01, "Reactor Pressure Vessel Head Degradation andReactor Coolant Pressure Boundary Integrity".

16) USNRC Bulletin 2003-02, "Leakage from Reactor Pressure Vessel Lower HeadPenetrations and Reactor Coolant Pressure Boundary Integrity".

17) USNRC Bulletin 2004-01 dated May 28, 2004, "Inspection of Alloy 82/182/600Materials Used in the Fabrication of Pressurizer Penetrations and Steam SpacePiping Connections at Pressurized-Water Reactors".

18) B&W Document 77-1140611-00, "Generic Investigation of HPI/MU NozzleComponent Cracking".

19) Calc 1-91-0023, "Narrow Range RC Pressure (PIR) Instrument Loop Accuracy".

20) USNRC EA-03-009, dated February 20, 2004, "Issuance Of First Revised OrderEstablishing Interim Inspection Requirements For Reactor Pressure Vessel HeadsAt Pressurized Water Reactors".

21) PE to NRC Letter 3F0903-02, 30-Day Response to Bulletin 2003-02, "Leakagefrom Reactor Pressure Vessel Lower Head Penetrations and Reactor CoolantPressure Boundary Integrity".

22) EC 54002, "Justification for HPI Thermal Sleeve Inspection Date Change".

23) NPTS03-0022, "Commitment Change Request".

24) PE Letter to NRC 3F0704-1 1, "60-day Response to NRC Bulletin 2004-01,Inspection of Alloy 82/182/600/ Materials Used in the Fabrication of PressurizerPenetrations and Steam Space Piping Connections at Pressurized-WaterReactors".

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25) Letter, Leslie Hartz to Distribution MRP 2003-039, dated January 20, 2004,"Recommendations for Inspection of Alloy 600/82/182 Pressure BoundaryComponents".

26) MRP 2004-05, dated April 2, 2004, "Needed action for Visual Inspection of Alloy82/182 Butt Welds and Good Practice Recommendations for Weld JointConfigurations".

27) EC 62378 "Code Case N-663 Service History and Susceptibility Review forClass 2 Piping".

28) NCR 108826-19, "Cracking Discovered in MUV-43 Thermal Sleeve".

29) License Amendment No. 218, Reactor Coolant Pump Flywheel Surveillance.

30) Crystal River Unit 3 Final Safety Analysis Report (FSAR).

31) Crystal River Unit 3 Improved Technical Specifications (TS).

32) Crystal River Unit 3 Procedures RDC-NGGC-002, "Document Control Program",NEP-301, "Control of ASME Section XI Examination Program Plans, Manuals,and Reports", NEP-303, "Retention and Control of Calibration Blocks",NEP-304, "Control of Crystal River Unit 3 Section XI NDE Procedures",NEP-305, "Control of Relief Requests", NEP-306, "Control of PlantModifications for PSI and ISI Requirements", NEP-307, "ANII InterfaceRequirements", AI-701, Administration of the ASME Section XI InserviceInspection and Inservice Testing Programs", OP-202, "Plant Heatup", CP-213,"Administrative Procedure for 10CFR50.59 Reviews".

33) Progress Energy Corporate Procedure NDEP-A, "Nuclear NDE Program andPersonnel Process".

34) Crystal River Unit 3 ISI Classification Basis Document (PENO1.G04), FourthTen-Year Inspection Interval.

35) Crystal River Unit 3 ISI Selection Document (PENO1.G05), Fourth Ten-YearInspection Interval.

36) USNRC NUREG-0737, dated November 1980, "TMI Action Plan Requirements".

37) EPRI Topical Report TR-1 12657, Rev. B-A, Final Report, "Revised Risk-Informed Inservice Inspection Evaluation Procedure", December 1999.

38) USNRC SER related to EPRI Topical Report TR-1 12657, Rev. B, Final Report,"Revised Risk-Informed Inservice Inspection Evaluation Procedure, July 1999",dated October 28, 1999.

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39) Calc M04-0015, EPRI-156-340, Degradation Mechanism Evaluation for the Class1 (Category B-J/B-F) Piping at Crystal River Unit 3.

40) Risk-Informed Inservice Inspection Consequence Evaluation of Class 1 CrystalRiver 3, Revision 2 (RMS #3169713).

41) Evaluation of the Impact of the CR3 PRA Update on the RI-ISI Program,Revision 0 (RMS #3169713).

42) ASME Code Case N-578-1, "Risk-Informed Requirements for Class 1, 2, and 3Piping, Method B, Section XI, Division 1".

43) Engineering Change 55725R0, CR3 Service History and Susceptibility Review(RMS #3149040).

44) EPRI-156-341, Crystal River Unit 3 Risk Ranking, Revision 0 (RMS #3169685).

45) EPRI-156-342, Minutes of the Element Selection Meeting for the RI-ISI Project atCrystal River Unit 3 (CR3), Revision 0 (RMS #3169682).

46) Crystal River Unit 3, RI-ISI Risk Impact Analysis, Revision 0 (RMS #3169703).

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