Text

Limerick, Units 1 and 2, Submittal of Third Inservice Inspection (ISI) Interval Program Plan
	ML070800741
Person / Time
Site:	Limerick
Issue date:	03/06/2007
From:	Cowan P B; Exelon Generation Co, Exelon Nuclear
To:	; Document Control Desk, NRC/NRR/ADRO
References
	Download: ML070800741 (131)
	v • d • e

Exeltn.Exelon Nuclear 200 Exelon Way Kennett Square, PA 19348 www.exe]OICOTP.COM Nuclear 10 CFR 50.55a March 6, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353

Subject:

Submittal of Third Inservice Inspection (ISI) Interval Program Plan In accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section Xl, IWA-1400(c), "Owner's Responsibility," attached for your information is a copy of the Third Ten-Year Interval Inservice Inspection (ISI) Program for Limerick Generating Station (LGS), Units 1 and 2, not including relief requests.

Relief requests associated with the program are being submitted separately.

The third interval of the LGS, Units 1 and 2 ISI Program complies with the 2001 Edition through 2003 Addenda of the ASME B&PV Code.Should you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510.Sincerely, Pamela B. owan Director -Licensing

& Regulatory Affairs Exelon Generation Company, LLC

Attachment:

Limerick Generating Station (LGS), Units 1 and 2 Third Inservice Inspection (ISI) Interval Program Plan cc: S. J. Collins, Regional Administrator, Region I, USNRC S. Hansell, USNRC Senior Resident Inspector, LGS J. Shea, Project Manager [LGS] USNRC-404-7 Limerick Generating Station (LGS)Units 1 and 2 Third Inservice Inspection (ISI) Interval Program Plan NUCLEAR SAFETY RELATED SPECIFICATION FOR LIMERICK GENERATING STATION UNIT 1& 2 INSERVICE INSPECTION PROGRAM System/Topic No. 101 Use of this Specification is not limited to the Systems/Topics listed above.Responsible Organization LEDX Branch 1, 0o Issued per LG ECR 06-00481 0 R I G I N A T 0 R R E V'I E w E R A P P R 0 V A L A P P R 0 V A L A P P R 0 V A L A P P R 0 V A L+ 4 4.REV NO DATE REASON FOR ISSUE LEAD NON- LEAD NO. NE-328 REV. NO 0 PECO SPECIFICATION FOR LIMERICK GENERATING PAGE 1 OF NUCLEAR STATION UNIT 1 & 2 INSERVICE INSPECTION

_PROGPAM I Limerick Generating Station 151 Program Document No.: LJMO2.G03 Limerick Generating Station IS] Program Document No.: LIM02.GO3 LIMERICK GENERATING STATION UNITS 1 & 2 ISI PROGRAM PLAN THIRD TEN-YEAR INSPECTION INTERVAL Commercial Service Dates: Unit 1 -02/01/86 Unit 2 -01/08/90 Limerick Generating Station 3146 Sanatoga Road Pottstown, Pennsylvania 19464 Exelon Generation Company (EGC), LLC 200 Exelon Way Kennett Square, Pennsylvania 19348 Prepared By: Alion Science and Technology Corporation Engineering and Technical Programs Division Warrenville, Illinois St(lIft APND TCCINOI.O1,Y LylIprogram Plan.Limyerick Generating Staton Units 1 & 2, 7Third interval REVISION APPROVAL SHEET TITLE: ISI Program Plan Third Ten-Year Inspection Interval Limerick Generating Station, Units 1 & 2 DOCUMENT: LIM02.G03 REVISION: 0 PREPARED TRANSMITTAL PREPARED: REVIEWED: APPROVED: e .eoleman ..-Alion Project Engineer 12-107 Kevin M. Jof-mson Alion Programs Technical Specialist Daniel W. Lamond Alion Project Manager EXELON ACCEPTANCE APPROVED: Michelle A. Karasek Project Manager A lialt Scie~llee

& Tedillology i LIMO2. G03.Revisio,, 0 151 Program Plan Lint rickr Generating Station Units I & 2, Thtird Interval REVISION APPROVAL SHEET TITLE: ISI Program Plan Third Ten-Year Inspection Interval Limerick Generating Station, Units 1 & 2 DOCUMENT: LIM02.G03 REVISION: 0 PROGRAM ACCEPTANCE REVIEWED: REVIEWED: APPROVED: APPROVED: REVIEWED: Michelle Karasek Project Manager 147 Projecvlanager George P. -udock ISI Program Engineer Program Owner Steve Bobyock Engineering Programs Manager__ 2//- o.Paul Lenair Authori7ed Nuclear Inservice Inspector Each time this document is revised, the Revision Approval Sheet will be signed and the following Revision Control Sheet should be completed io provide a detailed record of the revision history. The signatures above apply only to the changes made in the revision noted. If historical signatures are required, Limerick Generating Station archives should be retrieved.

4lion Science & Technolot:g; ii LJMD-12. 603 Rev.ision 0

ISI Program Plan Limerick Generating Station Units I & 2, Third Interval REVISION CONTROL SHEET Major changes to this document should be outlined within the table below. Editorial and formatting revisions are not required to be logged.REVISION.

DATE REVISION

SUMMARY

0 02/01/07 Initial issuance. (This 1SI Program Plan was developed by Alion Science and Technology Corporation as part of the Third Interval IS]Program update.)Prepared:

S. Coleman Reviewed:

K. Johnson Approved:

D. Lamond Notes: 1. This IS1 Program Plan (Sections I -9 inclusive) is controlled by the Limerick Generating Station, Engineering Programs Group.2. Revision 0 of this document was issued as the Third Interval ISI Program Plan and was submitted to the NRC for review, including approval of the initial Third ISI Interval Relief Requests.

Future revisions of this document made within the Third IS1 Interval will be maintained and controlled at the station; however, they are not required to be and will not be submitted to the NRC for approval.

The exception to this is that new or revised Relief Requests shall be submitted to the NRC for safety evaluation and approval..4lion Science & Technology iii L 603 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval REVISION

SUMMARY

SECTION EFFECTIVE PAGES REVISION DATE Preface i to v 0 02/01/07 1.0 1-1 to 1-15 0 02/01/07 2.0 2-1 to 2-69 0 02/01/07 3.0 3-1 to 3-3 0 02/01/07 4.0 4-1 to 4-2 0 02/01/07 5.0 5-1 0 02/01/07 6.0 6-1 to 6-2 0 02/01/07 7.0 7-1 to 7-32 0 02/01/07 8.0 8-1 to 13R- 14-19 0 02/01/07 9.0 9-1 to 9-3 0 02101/07 A lion Science ~' Technology LJ.Wi2. G03 Alien Science & Technalogy L.Ii02. GO3 Revision 0 ISi Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE OF CONTENTS SECTION .DESCRIPTION PAGE

1.0 INTRODUCTION

AND BACKGROUND

..... ...............................

1-1 1.1 Introduction

1.2 Background

1.3 First

Interval ISI Program 1.4 Second Interval IS] Program 1.5 Third Interval ISI Program 1.6 First Interval CISI Program 1.7 Second Interval CISI Program 1.8 Code of Federal Regulations IOCFR50.55a Requirements 1.9 Code Cases 1.10 Relief Requests 2.0 BASIS FOR INSERVICE INSPECTION PROGRAM ...............................................

2-1 2.1 ASME Section XI Examination Requirements

2.2 Augmented

Inspection Requirements

2.3 System

Classifications and ISI Boundary Drawings 2.4 IS Isometric and Component Drawings for Nonexempt 1SI Class Components and Supports 2.5 Technical Approach and Positions 3.0 CO M PON EN T IS1 PLAN ............................................................................................

3-1 3.1 Nonexempt ISI Class Components 3.2 Risk-informed Examination Requirements 3.3 IS Class I Piping Size Exemption for Water and Steam 4.0 SUPPORT IS] PLAN ................................................

4-1 4.1 Nonexempt IS] Class Supports 4.2 Snubber Examination and Testing Requirements

5.0 SYSTEM

PRESSURE TESTING ISI PLAN ..................................................................

5-1 5.1 ISI Class Systems 5.2 Risk-Informed Examination of Socket Welds 6.0 C O N TA IN M EN T ISI PLA N ..........................................................................................

6-1 6.1 Nonexempt CISI Class Components

6.2 Augmented

Examination Areas 6.3 Component Accessibility

6.4 Responsible

Individual and Engineer 7.0 COMIPONENT

SUMMARY

TABLES........................................................

7-I S.0 RELIEF REQUESTS FROM ASME SECTION XI .... ............................

8-1 9.0 R E FE R E N C E S ..........................................................................................................

..9-I APPENDICES A AUGMENTED IS1 PROGRAMS B ISI PROGRAM COMPONENT TABLES.fjion Science & Technolqxr.1 0 / .11'02. 603

ISI Program Plan Limerick Generating Station Units ) & 2, Third Interval

1.0 INTRODUCTION

AND BACKGROUND

1.1 Introduction

This Inservice Inspection (ISI) Program Plan details the requirements for the examination and testing of 1S1 Class 1, 2, 3, MC, and CC pressure retaining components, supports, and containment structures at Limerick Generating Station (LGS), Units 1, 2, and Common. Common (Unit Common) components are included in the Unit I sections, reports, and tables. This ISI Program Plan also includes Containment Inservice Inspection (CISI), Risk-Informed Inservice Inspections (RISI), Augmented Inservice Inspections (AUG), and pressure testing requirements imposed on or committed to by LGS. At LGS, the Inservice Testing (IST) Program is maintained and implemented separately from the ISI Program.The IST Basis Document and Program Plan contain all applicable inservice testing requirements.

The Third ISI Interval is effective from February 1, 2007 through January 31, 2017 for both LGS Units I and 2. With the update to the ISI Program for the Third IST Interval for Class 1, 2, and 3 components, including their supports, Exelon Generation Company, LLC'(Exelon) has also elected to update the CISI Program to its Second CISI Interval for Class MC and CC components at the same time (Relief Request 13R-01). This update will enable all of the ISI and CISI Program components

/ elements to be based on the same effective Edition and Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI, as well as share a common interval start and end date. The common ASME Code of Record for the Third ISI Interval and the Second CISI Interval is the 2001 Edition through the 2003 Addenda.Paragraph IWA-2430(d)(1) of ASME Section X] allows an inspection interval to be 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 service continuously for six months or more. The extension may be taken for a period of time not to exceed the duration of the outage. See Tables 1.1-1, 1.1-2. and 1.1-3 for intervals, periods, and extensions that apply to LGS's Third IS] Interval and Second CISI Interval.The Third ISI Interval and the Second CISI Interval are divided into two or three inspection periods as determined by calendar years within the intervals.

Tables 1.1-I. 1.1-2. and 1.1-3 identify the period start and end dates for the Third IS1 Interval and the Second CIS] Interval as defined by Inspection Program B. In accordance with Paragraph IWA-2430(d)(3).

the inspection periods specified in these Tables may be decreased or extended b, as much as I year to enable inspection to coincide with LGS's refueling outages..41i4,n Scienc t, Technoth~g.

i-1 L.11B2.G03 Revishien

)

IS! Progrqrn Plan Lionuric1k Generating Station Units I &. 2, Third Interval Table 1.1-1 LGS UNIT I AND UNIT 2 ISI INTERVAL/PERIOD/OUTAGE MATRIX (FOR ISI CLASS 1, 2, AND 3 COMPONENT EXAMINATIONS)

........ Unit I Period Interval Period Unit 2 Outage Projected Outage Start Date to End Date Start Date to Start Date to End Date Projected Outage Outage Number Start Date or End Date Start Date or Number Outag.e Duration ....._Outage Duration I R 12 Scheduled Scheduled 2R09 3/09 3/07 IR 13 Scheduled 211/07 to 1/31/l/ 3'd (Unit 1) 2/1/07 to 1/31/10 Scheduled 2R10 1/1O 2/1/07 to 1131/17 : 3/09 R 14 Scheduled 2nd (Note I and 2) 2 nd Scheduled 2R1 11 3/12 2/1/11 to 1/311/14 2/1/10 to 1/31/13 3/11 IRIS Scheduled 2/1 Un7t 1) Scheduled 2R.12 3114 3J 2/1/07 to 1/31/17 _____*_14 _3_d (Note and 3) 3rd,_ 3/13 1 R 16 Scheduled 2/1114 to 1/31/17 2/1/13 to 1/31/17 Scheduled 2Ri3 3/16 L 3/15 _* Notc I: A request to sharc a common interval start and end date between LGS Units I and 2 was submitted in accordance with Relief Request 13R-01.Note 2: The LGS I Jnit I and Common Second Period was reduced by one year and the First Period was extended by one year as permitted by IWA-2430(d)(3) in order to coincide with the plant refueling outage schedule.Note 3: The LGS U)nit 2 Second Period was reduced by one year and the Third Period was extended by one year as permitted by IWA-2430(dX3) in order to coincide with the plant refueling outage schedule.,1lion Science & Technolohgr 1-2 LIMO2.G03 Revision 0 IS! Program Plan Limerick Generating Station Units I & 2. Third Interval Table 1.1-2 LGS UNIT I AND UNIT 2 CISI INTERVAL/PERIOD/OUTAGE MATRIX (FOR ISI CLASS MC COMPONENT EXAMINATIONS)

Unit I Period Interval Period Unit 2 Outage Projected Outage Start Date to End Date Start Date to Start Date to End Date Projected Outage Outage Number Start Date or End Date Start Date or Number Outage Iuration Outage Duration I R 12 Scheduled Scheduled 2R09 3/OX l8 Si 3/07 IR13 Scheduled 2/1/07 to 1/31/1 1 2 n" (Unit 1) 2/1/07 to 1/3 1/10 Scheduled 2R10 3/11) 2/1/07 to 1/31/17 " 3/09 R14 Scheduled 2 nd (Nivc I and 2 nd Scheduled 2R111 3/I2 V 2/1111 to 1131/14 2/110 to 1/31/13 3/11 IR15 Scheduled 2 nd (Unit 2) Scheduled 2R12 3/14 ___ j2/1/07 to 1/31/17 3 dJ/13____M(! I and 33 I R16 Schcdilled 2/111.4 to 1/31/17 211/13 to 1/3 1/17 Scheduled 2Rl3/116 3/t5 Note I: A request for use of subsequent ASME Section XI Code Edition and Addenda was submitted in accordance with Relief Request 13R-O! which implements the 2001 Edition through the 2003 Addenda of ASME Section X1 for the CIS] Programs as well as to share a common interval start and end date with the ISI Program.Note 2: The I. XS Units I and Common Second Period was reduced by one year and the First Period was extended by one year as permitted by IWA-2430(d)(3) in order to coincide with the plant refueling outage schedule.Note 3: The l,6S Unit 2 Second Period was reduced by one year and the Third Period was extended by one year as permitted by IWA-2430(d)(3) in order to coincide wmith the plant refueling outage schedule..lion Science & Technohigi,...-3 LI..-.oG03.onO0 IMi Program Pl'an inimericA Generating Station Units I & 2, Third Interval Table 1.1-3 LGS UNIT I AND UNIT 2 CISI INTERVAL/PERIOD/OUTAGE MATRIX (FOR ISI CLASS CC COMPONENT EXAMINATIONS)

_ Unit I 5-Year Period Interval 5-Year Period Unit 2 Outage Projected Outage Start Date to End Date Start Date to Start Date to End Date Projected Outage Outage Numher Start Date or End Date Start Date or Number Outage Duration ,,_,_Outage Duration 1 R 12 Scheduled Scheduled 2R09_ _ 3/10 _ I' 3107 ......IRI3 Scheduled 2/1/07 to 1/31/12 2n" (Unit I) lA Scheduled 2R10 2/1/07 to 1/31/17' 1 I -3/110* 2/1f07 to 1/31t!2 3/09 _____I R 14 Scheduled Scheduled 2R11 3/12 2"' (Unit 2) 3/11 1R 15 Scheduled 2nd 2/1/07 to 1/31/17' Scheduled 2R12 3/14 2/1/12 to 1/31/17 3n' 3/13 I R 16 Scheduled 2/1/12 to 1/31/17 Scheduled.

2R13 3116 3/15 Note 1: A request for use of subsequent ASME Section XI Code Edition and Addenda was submitted in accordance with Relief Request 13R-01 which implemcnis the 2001 Edition through the 2003 Addenda of ASME Section Xl for the CISI Program as well as share a common interval start and end (late with the ISI Program.Aliaii Science & Techknologlp 1-4 LIM02. G03 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval 1.2 Background The Philadelphia Electric Company, now known commercially as Exelon Generation Company or Exelon, obtained construction permits CPPR- 106 for Unit I and CPPR-107 for Unit 2 to build LGS on June 19, 1974. The docket numbers assigned to LGS are 50-352 for Unit I and 50-353 for Unit 2. After satisfactory plant construction and preoperational testing was completed, LGS was granted a full power operating license for Unit 1, NPF-39, and subsequently commenced commercial operation on February 1, 1986; the full power operating license for Unit 2, NPF-85, was granted and commercial operation commenced on January 8, 1990.LGS's piping systems and associated components were designed and fabricated to the examination requirements of ASME Section XI. Although this plant was specifically designed to meetthe requirements of ASME Section XI, literal compliance may not be feasible or practical within the limits of the current plant design. Certain limitations are likely to occur due to conditions such as accessibility, geometric configuration, and/or metallurgical characteristics.

For some inspection categories, an alternate component may be selected for examination and the code statistical and distribution requirements can still be maintained.

If Code required examination criteria cannot be met, a relief request will be submitted in accordance with I OCFR50.55a.

1.3 First

Interval IS Program On February 1, 1986, LGS Unit I began commercial operation, which marked the beginning of the Unit I First Inspection Interval.

IS! and Repair and Replacement Programs were developed to implement the requirements of the ASME Boiler and Pressure Vessel (B&PV) Code, Section XL. At the time these programs were implemented, ASME Section XI, 1980 Edition, including Addenda through Winter 1981, were used to develop the 151 and Repair and Replacement Programs, as required by IOCFR50.55a(g)(4)(i).

By letter dated January 24, 1992, LGS notified the United States Nuclear Regulatory Commission (USNRC) that the LGS Unit I and Common ISI and Repair and Replacement Programs had been voluntarily upgraded to meet the requirements of the latest USNRC-approved version of ASME Section XI (i.e., 1986 Edition, no Addenda).

This voluntary upgrade was adopted following the completion of the LGS Unit I third refueling outage, IR03, and was used for the remainder of the First Inspection Interval.

The voluntary upgrade was initiated to allow LGS Unit I to use the same ASME Section XI Edition as that required for LGS Unit 2 (ie., 1986 Edition).

This alignment of applicable Code Editions was developed to provide a uniform set of requirements for both units at LGS. and to preclude any confusion that could result from the use of different requirements for each unit.41ion Science & Technoiogn.

1-5 LI1MI2. G03 Revision O IS] Program Plan Limerick Generating Station Units I A 2, Third Interval The First Inspection Interval for LGS Unit I was scheduled to end on February 1, 1996. However, by letter dated April 6, 1995, LGS notified the USNRC that the inspection interval would be extended until March 1, 1996, to accommodate the sixth refueling outage (I R06) schedule..

Additionally, by letter dated January 5, 1996, LGS notified the USNRC that the inspection interval would be further extended until February 1, 1997, to accommodate the preparation and implementation of ASME Code pressure tests that were now required as a result of the USNRC's conditional approval of Relief Request RR-13. The LGS Unit I First Inspection Interval began on February 1, 1986 and ended on January 31, 1997. This one-year extension has not been recovered to date for LGS Unit 1.The LGS Unit 2 First Inspection Interval began on January 8, 1990 and ended on January 7, 2000. IS1 and Repair and Replacement Programs were developed to implement the requirements of the ASME B&PV Code,Section XI, 1986 Edition, No Addenda.1.4 Second Interval ISI Program Pursuant to the Code Of Federal Regulations, Title 10, Part 50, Section 55a, Codes and standards, (I OCFR50.55a), Paragraph (g), Inservice inspection requirements, licensees were required to update their IS1 Programs to meet the requirements of ASME Section XI once every ten years or inspection interval.The ISI Program was required to comply with the latest Edition and Addenda of the Code incorporated by reference in I OCFR50.55a twelve (12) months prior to the start of the interval per I OCFR50.55a(g)(4)(ii).

As stated above, the end of the LGS Unit I First Inspection lnterval was January 31, 1997 and the end of the LGS Unit 2 First Inspection Interval was January 7, 2000. In order to avoid the inherent misalignment of the LGS ASME Section XI Programs, LGS obtained approval from the USNRC to begin the LGS Unit I and Common Second Inspection Interval, as normally scheduled, using the existing Code requirements (i.e., First Inspection Interval requirements), as described in ASME Section X1, 1986 Edition. Then. in approximately three (3) to four (4)years following the start of the LGS Unit I Second Inspection Interval, when LGS Unit 2 completed its First Inspection Interval, both Unit I and Unit 2 ISI Programs were simultaneously updated to the latest approved Edition and Addenda of the ASMME Section XI, which was the Code requirements in effect 12 months prior to the start of LGS Unit 2 Second Inspection Interval (i.e., 1989 Edition, No Addenda).The LGS Second Interval IS] Proaram Plans addressed Subsections IWA, IWB, JWC. IWDA, WF, M andator Appendices, approved ASME Code Cases, approved alternatives through relief requests and SER's, and utilized Inspection Program B as defined therein.Alion Science & Technllirt 1-6 1IM02. 603.............

o..Revision 0 IS] Program Plan Limerick Generating Station Units I & 2, Third Interval As an alternative to the full ten-year interval duration requirements of IWA-2430(b) and (d) and IWA-2432 for the Unit 2 Second Interval ISI Program and the Unit 2 First Interval CISI Program, LGS has proposed Relief Request 13R-01 to modify the interval dates of the Unit 2 Second Interval 1S Program and the Unit 2 First Interval CISI Program. This will permit the subsequent ISI and CIS] Programs to share a common inspection interval start and end date and to implement common Code Editions for Class 1, 2, 3, MC, and CC components.

As such, the Second ISI Interval was effective from February 1, 1997 through January 31, 2007 for LGS Unit 1 and from January 8, 2000 through January 31, 2007 for LGS Unit 2.1.5 Third Interval IS Program Pursuant to 1 OCFR50.55a(g), licensees are required to update their ISI Programs to meet the requirements of ASME Section XI once every ten years or inspection interval.

The ISI Program is required to comply with the latest Edition and Addenda of the Code incorporated by reference in 1 OCFR50.55a twelve (12)months prior to the start of the interval per I OCFR50.55a(g)(4)(ii).

As discussed in Section 1.4 above, the start of the Third ISI Interval will be on February 1, 2007 for LGS Units I and 2. Based on this date, the latest Edition and Addenda of the Code referenced in I OCFR50.55a(b)(2) twelve months prior was the 2001 Edition through the 2003 Addenda.The LGS Third Interval ISI Program Plan was developed in accordance with the requirements of I OCFR50.55a including all published changes through January 31, 2006, and the 2001 Edition through the 2003 Addenda of ASME Section XI, subject to the limitations and modifications contained within Paragraph (b) of the regulation.

These limitations and modifications are detailed in Table 1.8-1 of this section. This IS Program Plan addresses Subsections IWA, IWB, IWC, IWD, IWF, Mandatory Appendices, approved ASME Code Cases, approved alternatives through relief requests and SER's, and utilizes Inspection Program B1 as defined therein.LGS has adopted the EPRI Topical Report TR- 1 12657, Rev. B-A methodology.

which was supplemented by Code Case N-578-1. for implementing risk-informed inservice inspections.

The RISI Program will be in effect for the entire Third Inspection Interval.

This approach replaces the categorization, selection, and examination volume requirements of ASME Section XI Examination Categories B-F, B-J, C-F-I, and C-F-2 applicable to LGS with Examination Category R-A as defined in Code Case N-578-1. Implementation of RISi Program is in accordance with Relief Request 13R-02.LGS has also adopted the EPRI Topical Report TR-1006937.

Rev. 0-A.methodology for additional guidance for adaptation of the RISI evaluation process to Break Exclusion Region (BER) piping, also referred to as the High Energy Line Break (HE1..B) region. This change to ihe BER program was made under.Alion St'ience A Technology 1-7 LIM02. GO3 Revixion 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval 1 0CFR50.59 evaluation criteria.

The BER program will be in effect for the entire Third Inspection Interval.1.6 First Interval CISI Program CISI examinations were originally invoked by amended regulations contained within a Final Rule issued by the USNRC. The amended regulation incorporated the requirements of the 1992 Edition with the 1992 Addenda of the ASME Section XI, Subsections IWE and IWL, subject to specific modifications that were included in Paragraphs I0CFR50.55a(b)(2)(ix) and 10CFR50.55a(b)(2)(x).

The final rulemaking was published in the Federal Register on August 8, 1996 and specified an effective date of September 9, 1996. Implementation of the Subsection IWE and IWL Program from a scheduling standpoint was driven by the five year expedited implementation period per I OCFR50.55a(g)(6)(ii)(B), which specified that the examinations required to be completed by the end of the first period of the First Inspection Interval (per Table 1WE-2412-1) be completed by the effective date (by September 9, 2001).ASME Section XI Subsections IWE, JWL, Mandatory Appendices, approved ASME Code Cases, and approved alternatives through relief requests and SER's were added to the ISI Program midway through the Second ISI Interval to address CISI. The First CISI Interval for the LGS CISI Programs was aligned with the Unit I and Unit 2 ISI Programs and was effective from February 1, 1997 through January 31, 2007 for Unit I and January 8, 2000 through January 7, 2010 for Unit 2, respectively.

The CISI Program Plan was developed and implemented prior to the required date, and examinations for the first, second, and third periods were performed in accordance with the First CISI Interval schedule for Unit 1. Only the first and second periods were in accordance with the First CISI Interval schedule for Unit 2. As detailed in the submittal of the Third Interval ISI Program, the transition from the First to Second Interval CIS] Program occurred approximately three years early for Unit 2 to allow for a common interval start and end date and Code of record between the IS1 and CISI Programs.

No siwmificant examination issues were identified in this shortened First CIS] Interval requiring application of additional augmented examination requirements as detailed within IWE- 1240.As an alternative to the full ten-year interval duration requirements of IWA-2430(b) and (d) and JWA-2432 for the Unit 2 Second Interval ISI Program and the Unit 2 First Interval CISI Program LGS has proposed Relief Request 13R-01 to modif, the interval dales of the Unit 2 Second Interval ISI Prowram and the Unit 2 First Interval CISI Program. This will permit the subsequent IS] and CISI Programs to share a common inspection interval start and end date and to implement common Code Editions for Class 1. 2, 3. MC, and CC components.

As such, the Unit I First CISI Interval was effective from February 1. 1997 A1ion Science & Technologp, 1-8 L 1MOZ G03 Revision 0 IS] Program Plan Limerick Generating Station Units I A 2, Third Interval through January 31, 2007 and the Unit 2 First CISI Interval was effective from January 8, 2000 through January 31, 2007 (approximately 3 years early) for LGS Unit 2..1.7 Second Interval CISI Program Pursuant to I OCFR50.55a(g), licensees are required to update their CIS] Programs to meet the requirements of ASME Section XI once every ten years or inspection interval.

The CISIlProgram is required to comply with the latest Edition and Addenda of the Code incorporated by reference in I OCFR50.55a twelve (12)months prior to the start of the interval per IOCFR50.55a(g)(4)(ii).

As discussed in Section 1.6 above, the start of the Second CISI Interval will be on February 1, 2007 for LGS Units I and 2. Based on this date, the latest Edition and Addenda of the Code referenced in IOCFR50.55a(b)(2) twelve months prior was the 2001 Edition through the 2003 Addenda.The LGS Second Interval CISI Program Plan was developed in accordance with the requirements of I OCFR50.55a including all published changes through February 1. 2006, and the 2001 Edition through the 2003 Addenda of ASME Section XI, subject to the limitations and modifications contained within Paragraph (b) of the regulation.

These limitations and modifications are detailed in Table 1.8-1 of this section.This CIS] Program Plan addresses Subsections IWE, IWL. Mandatory Appendices, approved ASME Code Cases, approved alternatives through relief requests and SER's, and utilizes Inspection Program B as defined therein.1.8 Code of Federal Regulations I OCFR50.55a Requirements There are certain paragraphs in I OCFR50.55a that list the limitations, modifications, and/or clarifications to the implementation requirements of ASME Section XL. These paragraphs in 10CFR50.55ý-that are applicable to LGS are detailed in Table 1.8-1..4lion Science A. Technology 1-9 LIMO2.G03 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 1.8-1 CODE OF FEDERAL REGULATIONS IOCFR50.55a REQUIREMENTS IoCFR50.55a Paragraphs Limitations; Modifications, and Clarifications I OCFR50.55a(b)(2)(viii)(E) (CISI) Examination of concrete containments:

For Class CC applications, the licensee shall evaluate the acceptability of inaccessible areas when conditions exist in accessible areas that could indicate the presence of or result in degradation to such inaccessible areas. For each inaccessible area identified, the licensee shall provide the following in the IS] Summary Report required by IWA-6000: (1) A description of the type and estimated extent of degradation, and the conditions that led to the degradation; (2) An evaluation of each area, and the result of the evaluation, and;(3) A description of necessary corrective actions.I OCFR5O.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 in IWA-2300.

The "owner-defined" personnel qualification provisions in IWL-23 10(d) are not approved for use.I OCFR50.55a(b)(2)(ix)(A) (CISI)- Examination of metal containments and the liners of concrete containments:

For Class MC applications, the licensee shall evaluate the acceptability of inaccessible areas when conditions exist in accessible areas that could indicate the presence of or result in degradation to such inaccessible areas. For each inaccessible area identified, the licensee shall provide the following in the ISI Summary Report as required by IWA-6000: (1) A description of the type and estimated extent of degradation, and the conditions that led to the degradation; (2) An evaluation of each area. and the result of the evaluation, and;(3) A description of necessary corrective actions. I Alion Science & Technology 1-10 LJM0'2. GO3 Revision 0 IS] Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 1.8-1 CODE OF FEDERAL REGULATIONS IOCFR50.55a REQUIREMENTS

.0CFR50.55a Paragraphs Limitations, Modifications, and Clarifications I OCFR50.55a(b)(2)(ix)(B) (CISI) Examination of metal containments and the liners of concrete containments:

When performing remotely the visual examinations required by Subsection IWE, the maximum direct examination distance specified in Table IWA-22 10-1 may be extended and the minimum illumination requirements specified in Table IWA-2210-1 may be decreased provided that the conditions or indications for which the visual examination is performed can be detected at the chosen distance and illumination.

I OCFR50.55a(b)(2)(ix)(F) (CISI) Examination of metal containments and the liners of concrete containments:

VT-I and VT-3 examinations must be conducted in accordance with IWA-2200.

Personnel conducting examinations in accordance with the VT-I or VT-3 examination method shall be qualified in accordance with IWA-2300.

The "owner-defined" personnel qualification provisions in IWE-2330(a) for personnel that conduct VT-I and VT-3 examinations are not approved for use.I 0CFR5055a(b)(2)(ix)(G) (CISI) Examination of metal containments and the liners of concrete containments:

The VT-3 examination method must be used to conduct the examinations in Items El. 12 and El .20 of Table IWE-2500-1, and the VT- I examination method must be used to conduct the examination in Item E4.11 of Table IWE-2500-1.

An examination of the pressure-retaining bolted connections in Item El .1I of Table IWE-2500-1 using the VT-3 examination method must be conducted once each interval.

The "owner-defined" visual examination provisions in IWE-23 10(a) are not approved for use for VT- 1 and VT-3 examinations.

.4tion Science & Technuokv, 141 L14102.GV3 Rev'ision 0

ISI Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 1.8-1 CODE OF FEDERAL REGULATIONS I OCFR50.55a REQUIREMENTS IOCFR50.55a Paragraphs Limitations, Modifications, and Clarifications I OCFR50.55a(b)(2)(ix)(H)(CISI) Examination of metal containments and the liners of concrete containments:

Containment bolted connections that are disassembled during the scheduled performance of the examinations in Item El .11 of Table IWE-2500-1 must be examined using the VT-3 examination method. Flaws or degradation identified during the performance of a VT-3 examination must be examined in accordance with the VT-I examination method. The criteria in the material specification or IWB-3517.1 must be used to evaluate containment bolting, flaws or degradation.

As an alternative to performing VT-3 examinations of containment bolted connections that are disassembled during the scheduled performance of Item El 11, VT-3 examinations of containment bolted connections may be conducted whenever containment bolted connections are disassembled for any reason.I OCFR50.55a(b)(2)(ix)(1) (CISI) Examination of metal containments and the liners of concrete containments:

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.

I 0CFR50.55a(b)(2)(xi) (ISI) Class I piping. Licensees may not apply IWB- 1220,"Components Exempt from Examination," of Section XI, 1989 Addenda through the latest Edition and Addenda incorporated by reference in paragraph (b)(2) of this section, , __and shall apply IW'B- 1220, 1989 Edition.IOCFR50.55a(b)(2)(xviii)(A) (ISI) Certfication ofNDE personnel:

Level I and II nondestructive examination personnel shall be recertified on a 3-year interval in lieu of the 5-year interval specified in the 1997 Addenda and 1998 Edition of IWA-2314, and IWA-2314(a) and IWA-23 14(b) of the 1999 Addenda through the latest Edition and Addenda incorporated by reference in paragraph (b)(2) of this section.A4ion Stience & Technologi, 1-12 LJM02. G03 Re'vision 0

ISI Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 1.8-1 CODE OF FEDERAL REGULATIONS IOCFR50.55a REQUIREMENTS I0CFR50.55a Paragraphs Limitations, Modifications, and Clarifications I OCFR50.55a(b)(2)(xviii)(B)

(1SI) Certification ofNDEpersonnel:

Paragraph IWA-2316 of the 1998 Edition through the latest Edition and Addenda incorporated by reference in paragraph (b)(2) of this section, may only be used to qualify personnel that observe for leakage during system leakage and hydrostatic tests conducted in accordance with IWA-521 I(a) and (b), 1998 Edition through the latest Edition and Addenda incorporated by reference in paragraph (b)(2) of this section.I OCFR50.55a(b)(2)(xviii)(C) (IS) Certification of NDEpersonnel:

When qualifying visual examination personnel for VT-3 visual examinations under paragraph JWA-231 7 of the 1998 Edition through the latest Edition and Addenda incorporated by reference in paragraph (b)(2) of this section, the proficiency of the training must be demonstrated by administering an initial qualification examination and administering subsequent examinations on a 3-year interval.I OCFR50.55a(b)(2)(xix)

(1S1), Substitution ofalhernative methods: The provisions for the substitution of alternative examination methods, a combination of methods, or newly developed techniques in the 1997 Addenda of IWA-2240 must be applied. The provisions in IWA-2240, 1 998 Edition through the latest Edition and Addenda incorporated by reference in paragraph (b)(2) of this section. are not approved for use. The provisions in IWA-4520(c), 1997 Addenda through the latest Edition and Addenda incorporated by reference in paragraph (b)(2) of this section, allowing the substitution of alternative examination methods. a combination of methods, or newly developed techniques for the methods specified in the Construction Code are not approved for use.IOCFR50.55a(b)(2)(xxi)(B) (IS1) Table IWB-2500-1 examination requirements:

The provisions of Table IWB-2500-1, Examination Category B-G-2, Item B7.80. that are in the 1995 Edition are applicable only to reused bolting when using the 1997 Addenda.through the latest Edition and Addenda incorporated by reference in paragraph (b)(2) of this section.Alion Science & Technolog)y 1-13 L1.1112. G03 Revishion 0

ISI Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 1.8-1 CODE OF FEDERAL REGULATIONS IOCFR50.55a REQUIREMENTS 10CFRS0.55a Paragraphs Limitations, Modifications, and Clarifications I1OCFR50.55a(b)(2)(xxii) (ISI) Surface Examination:

The use of the provision in IWA-2220, "Surface Examination," of Section Xl, 2001 Edition through the latest Edition and Addenda incorporated by reference in paragraph (b)(2) of this section, that allow use_of an ultrasonic examination method is prohibited.

I OCFR50.55a(b)(2)(xxvii) (ISI) Removal of Insulation:

When performing visual examinations in accordance with IWA-5242 of Section X1, 2003 Addenda through the latest Edition and Addenda incorporated by reference in paragraph (b)(2) of the section, insulation must be removed from 17-4 PH or 410 stainless steel studs or bolts aged at a temperature below 1100 'F or having. a Rockwell Method C hardness value above 30, and from A-286 stainless steel situds or bolts preloaded to 100,000 pounds per square inch or higher.I OCFR50.55a(b)(5) (ISI) Inservice Inspection Code Cases: Licensees may apply the ASME Boiler and Pressure Vessel Code Cases listed in Regulatory Guide 1. 147 through Revision 1.4, without prior USNRC approval subject to the following: (i) When a licensee initially applies a listed Code Case, the licensee shall apply the most recent version of that Code Case incorporated by reference in this paragraph.(ii) If a licensee has previously applied a Code Case and a later version of the Code Case is incorporated by reference in this paragraph.

the licensee may continue to apply, to the end of the current 120-month interval, the previous version of the Code Case as authorized or may apply the later version of the Code Case, including any USNRC-specified conditions placed on its use.(iii) Application of an annulled Code Case is prohibited unless a licensee previously applied the listed Code Case prior to it being listed as annulled in Regulatory Guide 1.147. Any Code Case listed as annulled in any Revision of Regulatory Guide 1.147 which a licensee has applied prior to it being listed as annulled, may continue to be applied by that licensee to the end of the 120-month interval in which the Code Case* was implemented.

... * ..... .H A (ion Science Tech ntdi,,gv 1-14 LIMO2. G63 Revision 0 ISI Program Plan Limerick Generating.Station Units I & 2, Third Interval 1.9 Code Cases Per I OCFR50.55a(b)(5), ASME Code Cases that have been determined to be suitable for use in ISI Program Plans by the USNRC are listed in Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability-ASME Section X!, Division I ". The approved Code Cases in Regulatory Guide 1.147, which are being utilized by LGS, are included in Section 2.1.1. The most recent version of a given Code Case incorporated in the revision of Regulatory Guide 1.147 referenced in I OCFR50.55a(b)(5)(i) at the time it is applied within the ISI Program shall be used. The latest version of Regulatory Guide 1.147 incorporated into this document is Revision 14. As this guide is revised, newly approved Code Cases should be assessed for plan implementation at LGS.The use of other Code Cases (than those listed in Regulatory Guide 1.147) maybe authorized by the Director of the office of Nuclear Reactor Regulation upon request pursuant to I 0CFR50.55a(a)(3).

Code Cases not approved for use in Regulatory Guide 1. 147, which are being utilized by LGS through associated relief requests, are included in Section 8.0.1.10 Relief Requests In accordance with IOCFR50.55a, when a licensee either proposes alternatives to ASME Section XI requirements which provide an acceptable level of quality and safety, determines compliance with ASME Section XI requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety, or determines that specific ASME Section XI requirements for inservice inspection are impractical, the licensee shall notify the USNRC and submit information to support the determination:

The submittal of this information will be referred to in this document as a "relief request." Relief requests for the Third IS] Interval are included in Section 8.0 of this document.

The text of the relief requests contained in Section 8.0 will demonstrate one of the following; the proposed alternatives provide an acceptable level of quality and safety per 1 OCFR50.55a(a)(3)(i).

compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety per IOCFR50.55a(a)(3)(ii), or the code requirements are considered impractical per I OCFR50.55a(g)(5)(iii).

Per IOCFR50.55a Paragraphs (a)(3) and (g)(6)(i), the Director of the Office of Nuclear Reactor Regulation will evaluate relief requests and "may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.".4lion Svience & 7ec'hnology 1-15 LIMO2.G03 Reviisio, 0 IS) Program Plan Limerick Generating Station Units I & 2, Third Interval 2.0 BASIS FOR INSERVICE INSPECTION PROGRAM 2.1 ASME Section XI Examination Requirements As required by the I OCFR50.55a, this program was developed in accordance with the requirements detailed in the 2001 Edition through the 2003 Addenda, of the ASME Boiler and Pressure Vessel Code, Section X1, Division 1, Subsections IWA, IWB, IWC, IWD, IWE, JWF, IWL, Mandatory Appendices, Inspection Program B of IWA-2432, approved ASME Code Cases, and approved alternatives through relief requests and Safety Evaluation Reports (SER's).The IS] Program implements Appendix ViII "Performance Demonstration for Ultrasonic Examination Systems," ASME Section XI 2001 Edition, No Addenda as required by I OCFR50.55a(b)(2).

Appendix VIIl requires qualification of the procedures, personnel, and equipment used to detect and size flaws in piping, bolting, and the reactor pressure vessel (RPV). Each organization (e.g., owner or vendor) will be required to have a written program to ensure compliance with the requirements.

These requirements were initially implemented through the Performance Demonstration Initiative (PD1) Program according to the schedule defined in l0CFR50.55a(g)(6)(ii)(C).

For the Third Inspection Interval, LGS's inspection program for ASME Section XI Examination Categories B-F, B-J, C-F-], and C-F-2 will be governed by risk-informed requirements.

The RISI Program methodology is described in the EPRI Topical Report TR-l 12657, Rev. B-A. To supplement the EPRI Topical Report, Code Case N-578-1 (as applicable per Relief Request 13R-02) is also being used for the classification of piping structural elements under the RISI Program. The RISI Program scope has been implemented as an alternative to the 2001 Edition through the 2003 Addenda, ASME Section XI examination program for Class I B-F and B-J welds and Class 2 C-F-I and C-F-2 welds in accordance with I0CFR50.55a(a)(3)(i).

The basis for the resulting risk categorizations of the non-exempt Class I and 2 piping systems at LGS is defined and maintained in the Final Report, "Risk Informed Inservice Inspection Evaluation," as referenced in Section 9.0 of this document.For the Third Inspection Interval, the: RISI program scope has been expanded to include welds in the BER piping, also referred to as the HELB region, which includes several non-class welds that fall within the BER augmented inspection program. The BER program methodology is described in EPRI Topical Report TR- 1006937. Rev. 0-A, which has been used to define the inspection scope in lieu of the J00% examination of all piping welds in the previous BER augmented program. Therefore, all welds in the original augmented program for BER were evaluated under the RIS] program using an integrated risk-informed approach.Alion i,, £ Technoloy 2-1 LIMO2.G03 Alion Scietice & Techtiolog11 Revision 0 ISI Program Plan Limerick Generating Station Units 1 & 2, Third Interval 2. 1.1 ASME Section X1 Code Cases As referenced by IOCFRS0.55a(bX5) and allowed by USNRC Regulatory Guide 1.147, Revision 14, the following Code Cases are being incorporated into the LGS 1SI Program. Several of these Code Cases are included as contingencies, to ensure that they are available for future repair/replacement activities.

N-432-1 Repair Welding Using Automatic or Machine Gas Tungsten-Arc Welding (GTAW) Temper Bead Technique N-460 Alternative Examination Coverage for Class I and Class 2 Welds N-504-2 Alternative Rules for Repair of Class 1, 2, and 3 Austenitic Stainless Steel Piping Code Case N-504-2 is acceptable subject to the following condition specified in Regulatory Guide 1.147, Revision 14: The provisions of ASME Section X1, Nonmandatory Appendix Q, "Weld Overlay Repair of Class 1, 2, and 3 Austenitic Stainless Steel Piping Weldments," must also be met.N-508-2 Rotation of Serviced Snubbers and Pressure Relief Valves for the Purpose of Testing N-513-1 Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Code Case N-513-1 is acceptable subject to the following conditions specified in Regulatory Guide 1. 147, Revision 14: (1) The specific safety factors in paragraph 4.0 must be satisfied.

(2) and the Code Case may not be applied to: (a) Components other than pipe and tubing.(b) Leakage through a gasket.(c) Threaded connections employing nonstrucrural seal w elds for leakage prevention (through seal weld leakage is not a structural flaw; thread integrity must be maintained).(d) Degraded socket welds.Alhin Science & Technology, 2-2 LI.1I02. G03 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval N-516-3 Underwater Welding Code Case N-516-3 is acceptable subject to the following condition specified in Regulatory Guide 1.147, Revision 14: Licensee must obtain USNRC approval in accordance with I OCFR50.55a(a)(3) regarding the technique to be used in the weld repair or replacement of irradiated material underwater.

N-517-1 Quality Assurance Program Requirements for Owners Code Case N-517-1 is acceptable subject to the following condition specified in Regulatory Guide 1.147, Revision 14: The Owner's Quality Assurance (QA) Program that is approved under Appendix B to I OCFR Part 50 must address the use of this Code Case and any unique QA requirements identified by the Code Case that are not contained in the owner's QA Program description.

This would include the activities performed in accordance with this Code Case that are subject to monitoring by the Authorized Nuclear Inspector.

N-526 Alternative Requirements for Successive Inspections of Class I and 2 Vessels N-528-1 Purchase, Exchange, or Transfer of Material Between Nuclear Plant Sites Code Case N-528-1 is acceptable subject to the following condition specified in Regulatory Guide 1.1 47. Revision 14: The requirements of I OCFR Part 2] are to be applied to the nuclear plant site supplying the material as well as to the nuclear plani site receiving the material that has been purchased, exchanged.

or transferred between sites.N-532-1 Alternative Requirements to Repair and Replacement Documentation Requirements and lnsern'ice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000 Alion Science Tevhnology 2-3 L1102. 6,03 0

IS] Program Plan Limerick Generating Station Units I & 2, Third Interval Code Case N-532-1 is acceptable subject to the following conditions specified in Regulatory Guide 1.147, Revision 14: Code Case N-532-1 requires an Owner's Activity Report Form OAR-I to be prepared and certified upon completion of each refueling outage. The OAR-I forms must be submitted to the USNRC within 90 days of the completion of the refueling outage.N-552 Alternative Methods -Qualification for Nozzle Inside Radius Section from the Outside Surface Code Case N-552 is acceptable subject to the following conditions specified in Regulatory Guide 1.147, Revision 14: To achieve consistency with the I OCFR50.55a rule change published September 22, 1999 (64 FR 51370), incorporating Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," to ASME Section XI, add the following to the specimen requirements: "At least 50 percent of the flaws in the demonstration test set must be cracks and the maximum misorientation must be demonstrated with cracks. Flaws in nozzles with bore diameters equal to or less than 4 inches may be notches." Add to detection criteria, "The number of false calls must not exceed three." N-566-2 Corrective Action for Leakage Identified at Bolted Connections N-586 Alternative Additional Examination Requirements for Class 1, 2, and 3 Piping, Components.

and Supports Code Case N-586 is acceptable subject to the following conditions specified in Regulatory Guide 1.147, Revision 14: The engineering evaluations addressed under Item (a)and the additional examinations addressed under Item (b) shall be performed during this outage. If the Alien Science A Technology 2-4 LIM02. G03 Reviion 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval additional examinations performed under Item (b)reveal indications exceeding the applicable acceptance criteria of ASME Section XI, the engineering evaluations and the examinations shall be further extended to included additional evaluations and examinations at this outage.N-597-1 Requirements for Analytical Evaluation of Pipe Wall Thinning Code Case N-597-1 is acceptable subject to the following conditions specified in Regulatory Guide 1.147, Revision 14: (I) Code Case must be supplemented by the provisions of EPRI Nuclear Safety Analysis Center Report 202L-R2, April 1999, "Recommendations for an Effective Flow Accelerated Corrosion Program," for developing the inspection requirements, the method of predicting the rate of wall thickness loss, and the value of the predicted remaining wall thickness.

As used in NSAC-202L-R2, the terms "should" and"shall" have the same expectation of being completed.

(2) Components affected by flow-accelerated corrosion to which this Code Case are applied must be repaired or replaced in accordance with. the construction code of record and Owner's requirements or a later USNRC approved edition of Section III of the ASME Code prior to the value of t, reaching the allowable minimum wall thickness, , as specified in -3622.1(a)(])

of this Code Case.Alternatively, use of the Code Case is subject to USNRC review and approval.(3) For Class I piping not meeting the criteria of-3221.the use of evaluation methods and criteria is subject to USNRC review and approval.(4) For those components that do not require immediate repair or replacement, the rate of wall thickness loss is to be used to determine a suitable inspection frequency so that repair or replacement occurs prior to reaching allowable minimum wall thickness.

r,,,,,.(5) For corrosion phenomenon other than flow accelerated corrosion, use of the Code Case is subject to USNRC review and approval.

Inspection A1ian Science i, Technology 2-5 L IW402.G03 Revision 0 ISi Program Plan Limerick Generating Station Units I A 2, Third Interval plans and wall thinning rates may be difficult to justify for certain degradation mechanisms such as MIC and pitting.N-600 Transfer of Welder, Welding Operator, Brazer, and Brazing Operator Qualifications Between Owners N-606-1 Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique for BWR CRD Housing/Stud Tube Repairs Code Case N-606-1 is acceptable subject to the following conditions specified in Regulatory Guide 1.147, Revision 14: Prior to welding, an examination or verification must be performed to ensure proper preparation of the base metal, and that the surface is properly contoured so that an acceptable weld can be produced.

The surfaces to be welded, and surfaces adjacent to the weld, are to be free from contaminants, such as, rust, moisture, grease, and other foreign material or any other condition that would prevent proper welding and adversely affect the quality or strength of the weld. This verification is to be required.in the welding procedures.

N-613-1 Ultrasonic Examination of Full Penetration Nozzles in Vessels, Examination Category B-D, Item No's. B3. !0 and B3.90, Reactor Nozzle-to-Vessel Welds, Figs.IWB-2500-7(a), (b), and (c)N-624 Successive Inspections N-638-1 Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique Code Case N-638-1 is acceptable subject to the following conditions specified in Regulalory Guide 1.147, Revision 14: UT examinations shall be demonstrated for the repaired volume using representative samples, which contain construction type flaws. The acceptance criteria of NB-5330 of Section III edition and addenda approved in I OCFR50.55a apply to all flaws identified within the repaired volume..4lion Science & Techn olhtgr 2-6 Li]302. 603 Revisjion 0

ISI Program Plan Limerick Generating Station Units I & 2, Third Interval N-639 Alternative Calibration Block Material Code Case N-639 is acceptable subject to the following conditions specified in Regulatory Guide 1.147, Revision 14: Chemical ranges of the calibration block may vary from the materials specification if(1) it is within the chemical range of the component specification to be inspected, and (2) the phase and grain shape are maintained in the same ranges produced by the thermal process required by the material specification.

N-648-1 Alternative Requirements for Inner Radius Examination of Class I Reactor Vessel Nozzles Code Case N-648- lis acceptable subject to the following conditions specified in Regulatory Guide 1.147, Revision 14: In place of a UT examination, licensees may perform a visual examination with enhanced magnification that has a resolution sensitivity to detect a I -mil width wire or crack, utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio. The provisions of Table IWB-2500-1, Examination Category B-D, continue to apply except that, in place of examination volumes, the surfaces to be examined are the external surfaces shown in the figures applicable to this table.N-649 Alternative Requirements for IWE-5240 Visual Examination N-651 Ferritic and Dissimilar Metal Welding Using SMAW Temper Bead Technique Without Removing the Weld Bead Crown of the First Layer N-661 Alternative Requirements for Wall Thickness Restoration of Classes 2 and 3 Carbon Steel Piping for Raw Water Service Code Case N-661 is acceptable subject to the following conditions specified in Regulator, Guide 1. 147. Revision 14: Alion Science A Techlhologr LIM02.G03.

Revision 0 IS] Program Plan Limerick Generating Station Units I& 2, Third Interval (a) If the root cause of the degradation has not been determined, the repair is only acceptable for one cycle.(b) Weld overlay repair of an area can only be performed once in the same location.(c) When through-wall repairs are made by welding on surfaces that are wet or exposed to water, the weld overlay repair is only acceptable until the next refueling outage.N-664 Performance Demonstration Requirements for Examination of Unclad Reactor Pressure Vessel Welds, Excluding Flange Welds N-695 Qualification Requirements for Dissimilar Metal Piping Welds Additional Code Cases invoked in the future shall be in accordance with those approved for use in the latest published revision of Regulatory Guide 1.147 at that time.2.2 Augmented Inspection Requirements Augmented Inspection Program requirements are those inspections that are performed above and beyond the requirements of ASME Section XI. Below is a summary of those examinations performed by LGS that are not specifically addressed by ASME Section XI, or the inspections that will be performed in addition to the requirements of ASME Section XI on a routine basis during the Third Inspection Interval.

Implementation of the examination commitments is included in Section 7.0 of this ISI Program Plan and the associated ISI Database.See the Augmented, Inspection Program for details on these additional examination requirements and references.

2.2.1 (AUG-01), Generic Letter 88-01, USNRC Position on 1GSCC in BWR Austenitic Stainless Steel Piping, Revision 2 / Supplement I to Generic Letter 88-01, NUREG 0313, Technical Report on Material Selection and Process Guidelines for BWR Coolant Pressure Boundary Piping, Revision 2, and EPRI Report TR-] 13932, BWR Vessel and Internals Project Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules (BWRVIP-75) 2.2.2 (AUG-02).

Boiling Water Reactor Owners' Group (BWROG) Report GE-NE-523-A71-0594.

Revision I, Alternate BWR Feedwater Nozzle Inspection Requirements.

and NUREG 0619. BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking Alion Science A Technology 2-8 LIM02. G03 Rei-ision 0

ISI Program Plan Limerick Generating Station Units I A 2, Third Interval Note: Augmented examination of the Feedwater Spargers has been transferred to procedure ER-LG-33 1, "Reactor Internals Program Bases and Implementation at LGS", whereas augmented examination of the Feedwater Nozzles remains with this section.2.2.3 (AUG-05), USNRC Mechanical Engineering Branch (MEB) Technical Position MEB 3-1, NUREG-0800, No Break Boundaries 2.2.4 (AUG-07), SIL No. 455, Recommendation for Additional IS1 of Alloy 182 Nozzle Weldments 2.2.5 (AUG-09), Examination of the RPV Closure Head Lifting Lugs 2.2.6 (AUG- 10), UFSAR Table 3.2-1, Non-Q Reactor Pressure Vessel Internal Components 2.2.7 (AUG-13), Technical Specification 3/4.7.4, Snubber Examination and Testing Program 2.2.8 (AUG-14), Balance of Plant Snubber Examination Program 2.2.9 (AUG-19), Weld Centerline Marking 2.2.10 (AUG-22), USNRC IEB Nos. 95-02 and 96-03, RHR and CS Suction Strainers 2.2.11 (AUG-30), BWRVIP-05, BWR Reactor Pressure Vessel Shell Welds 2.2.12 Augmented inspection programs associated with the BWRVIP and the LGS Vessel Internals Program have been transferred to procedure ER-LG-33 1. "'Reactor Internals Program Bases and Implementation at LGS." The LGS Vessel Internals Program procedure now includes the following:

AUG-02 Boiling Water Reactor Owners' Group (BWROG) Report GE-NE-523-A71-0594.

Revision 1, Alternate BWR Feedwater Nozzle Inspection Requirements, and N1JREG-0619, BWR Feedwater Nozzle and Control Rod Drive Return. Line Nozzle Cracking (See Note in Section 2.2.2 for augmented examination details for Feedwater Spargers)AUG-03 IE Bulletin No. 80-13. Cracking in Core Spray Spargers, and BWR VIP-I 8. BWR Core Spray Internals AUG-04 NUREG;CR-3052.

Closeout of IE Bulletin 80-07, BWR Jet Pump Assembly Failure, and BWRVIP-41, BWR Jet Pump Assembly AUG-I I SIL No. 409, Incore Dry Tube Cracks Lines Alion Science & Technology 2-9 L1.41112.

G03 Re'i'ion,, #

ISI Program Plan Limerick Generating Station Unit, 1 & 2, Third Interval AUG-15 SIL No. 433, Shroud Head Bolt Cracks AUG- 16 SIL No. 462, Shroud Support Access Hole Cover Cracks AUG-17 SIL No. 474, Steam Dryer Drain Channel Cracking AUG-20 BWRVIP-76, BWR Core Shroud AUG-21 BWRVIP-26, BWR Top Guide AUG-23 BWRVIP-25, BWR Core Plate AUG-24 BWRVIP-27, BWR Standby Liquid Control and Core Plate AP Nozzle AUG-25 BWRVIP-38, BWR Core Shroud Support Structure AUG-26 BWRVIP-42, BWR LPC1 Coupling AUG-27 BWRVIP-47, BWR Lower Plenum AUG-28 BWRVIP-48, BWR Reactor Pressure Vessel ID Attachment Welds AUG-29 BWRVIP-49, BWR Instrument Penetrations

2.3 System

Classifications and IS] Boundary Drawings The ISI Classification Basis Document details those systems that are IS] Class 1, 2. 3, or MC that fall within the ISI scope of examinations.

The concrete containment structure is ISI Class CC and is shown on the Containment Roll-Out Drawings.

Below is a summary of the classification criteria used within the ISI Classification Basis Document.Each safety related, fluid system containing water, steam, air, oil, etc. included in the LGS UFSAR was reviewed to determine which safety functions they perform during all modes of system and plant operation.

Based on these safety functions, the systems and components were evaluated per classification documents.

The systems were then designated as ISI Class 1. 2, 3, MC, or non-classed accordingly.

This evaluation followed the guidelines of UFSAR Sections 5.2.4 and 6.6.When a particular group of components is identified as performing a ISI Class 1, 2, or 3 safety function, the components are further reviewed to assure the interfaces (boundary valves and boundary barriers) meet the criteria set by I OCFR50.2,, IOCFR50.55a(c)( 1). IOCFR50.55a(c)(2), and Regulatory Guide 1.26.The valve positions shown on the system flow diagrams are assumed to be the normal positions during system operation unless otherwise noted.Components within the reactor coolant pressure boundary, as defined by I OCFR50.2, are typically designated as IS] Class I while the other safety related components are evaluated for IS] Class 2 or 3 designation in accordance with the guidelines of Regulatory Guide 1.26. Per Regulatory Guide 1.26 Paragraphs A andB. the ISI Class 2 and 3 boundaries are limited to safety related systems and components (reference UFSAR Section 6.6). Where sufficient classification criteria is not provided within IOCFRSO or Regulatory Guide 1.26, other industry documents such as NUREG-0800 and ANSI. ANS standards are consulted "for Alion Science & Technology 2-10 UJI02. G63 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval guidance".

LGS is only committed to and licensed in accordance with the rules and regulations of IOCFR50 and Regulatory Guide 1.26.ISI classification boundaries are defined by the ISI Boundary Drawings with a classification line color code. A legend appears on each of the ISI Boundary Drawings defining the IS] classification and exempt/non-exempt status for each of the color coded lines. These drawings are identified with a special prefix of "IST" for the color-coded P&IDs (e.g.; ISI-M-01).

The systems and components (piping, pumps, Valves, vessels, etc.). which are subject to the examinations of Articles IWB-2000, IWC-2000, IWD-2000, IWE-2000, IWF-2000, and IWL-2000 are identified on the 1SI Boundary Drawings as detailed in Table 2.3-1.Alion Science & Technology 2-li LIM02.G03 Revision 0 ISI Program Plan Limerick Generating Station Units 1 & Z Third Interval TABLE 2.3-1 LGS ISI CLASSIFICATION BOUNDARY DRAWINGS UNIT I & Common UNIT 2 TITLE ISI-M-01, Sh. 1 ISI-M-01, Sh. 3 Main Steam (MS)IS1-M-08, Sh. I ISI-M-08, Sh. 3 Condensate

& Refueling Water Storage (CONDSTE)ISi:-M- 1, Sh. 1,I A,2,3 4 ISI-M-I 1, Sh. 1,4,5 Emergency Service Water (ESW)ISI-M-12 iSI-M-12 RHR Service Water (RHRSW)ISI-M- 13. Sh. I ISI-M-1 3, Sh. 2 Reactor Enclosure Cooling Water (RECW)IS -M-15, Sh. 1.15,16 IS1-M-15, Sh. 29,30 Compressed Air (Service Air)ISI-M-20.

Sh. ISI-M-20, Sh.3.4,4A,5,6,7,8 9,10.11,12,13.14 Fuel & Diesel Oil Storage and Transfer (DIESEL)ISI-M-26.

Sh. 1.2,4 ISI-M-26.

Sh. 7,8 Plant Process Radiation Monitoring (RADMON)MSJV Leakage Control System (Abandoned in Place ISI-M-40, Sh. I ISI-M-40, Sh.2 pe2O OO1-1_________________per MOD P00017-I)ISI-M-41.

Sh. 1,2 ISI-M-41.

Sh. 4,5 Nuclear Boiler (NB or RPV)1SI-M-42.

Sh. 1.2.5 ISI-M-42.

Sh. 3 Nuclear Boiler Vessel Instrumentation (NB or RPV)lSI-M-43, Sh. 1,2 IS-M-43, Sh. 3,4 Reactor Recirculation Pump (RR)ISI-M-44, Sh. 1.2 IS1-M-44, Sh. 3,4 Reactor Water Clean-up (RWCU)ISI-M-45.

Sh. 1 ISI-M-45, Sh. 2 Clean Up Filter Demineralizer (DEMIN)1Sl-M-46.

Sh. I ISI-M-46, Sh. 2 Control Rod Drive Hydraulic (Part A) (CRD)ISI-M-47.

Sh. I lS]-M-47.

Sh. _2 Control Rod Drive Hydraulic (Part B) (CRD)ISI-M-48.

Sh. I ISI-M-48, Sh. 2 Standby Liquid Control (SLC)ISI-M-49.

Sh. 1 ISI-M-49, Sh. 2 Reactor Core Isolation Cooling (RCIC)I SI-M-50. Sh. 1 ISJ-M-50.

Sh. 2 RCIC Pump Turbine (RCIC)IS]-M-51.

Sh. 1.2.3.4 ISI-M-51.

Sh. 5,6.7.8 Residual Heat Removal (RHR)lS1-M-52.

Sh. l.2.2A ISI-M-52.

Sh. 3.4 Core Spray (CS)ISI-M-53.

Sh. 1.2 ISI-M-53, Sh. 3.4 Fuel Pool Cooling and Clean-up (FPC)ISI-M-55.

Sh. 1 ISI-M-55, Sh. 2 High Pressure Coolant Inecrion (HPCI)ISI-M-56.

Sb_ I tS-4M-56.

Sh. 2 HPCI Pump Turbine (I-ICPI)ISI-M-57.

sh, 1.2.3 ISI-M-57.

SK. 4.5.6 Containment Atmospheric Control ]CAC)

Sh. 1.2 ISI-M-58.

Sh. .4 Hydrogen Recombiner (HYD REC).4lion Science& T echnologvy 2-12 LIM02. Gt3 Rev'ision 0

IS] Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 2.3-1 LGS IS] CLASSIFICATION BOUNDARY DRAWINGS UNIT I & Common UNIT 2 TITLE ISI-M-59, Sh. 1,2 ISl-M-59, Sh. 3,4 Primary Containment Instrument Gas,(PCIG)

ISI-M-60, Sh. I ISI-M-60, Sh. 2 Primary Containment Leak Testing (PCTL)ISI-M-61, Sh. I ISI-M-61, Sh. 4 Liquid Radwaste Collection (LRW)ISI-M-87, Sh. 4,5 IS1-M-87,.

Sh. 9,10 Drywell: Chilled Water (DWCW)ISI-M-90, Sh. 1,2 -Control Structure Chilled Water (CSCW)/.Alion Science & Technology 2-13 LJA'02. G03 Rei',ixion 0

ISI Program Plan Limerick Generating Station Units 1 2, Third Interval 2.4 ISI Isometric and Component Drawings for Nonexempt ISI Class Components and Supports IS Isometric and Component Drawings were developed to detail the IS] Code classified 1, 2, and 3 components (welds, bolting, etc.) and support locations at LGS. These IS] components and supports are identified on the ISI Isometric and Component Drawings listed in Tables 2.4-1, 2.4-2, 2.4-3, 2.4-4, 2.4-5, and 2.4-6.The Class I and 2 Isometric Drawings are identified with a special prefix of "FIG" for Unit I and "XI" for Unit 2 (e.g.; FIG-01 -01 or XI-DCA-204-l).

The CISI Class MC and CC components are identified on the CISI Reference Drawings listed in Table 2.4-7. Calibration Block Drawings are identified on the ASME Section X] UT Calibration Block Drawings listed in Tables 2.4-8 and 2.4-9.LGS's IS Program, including the ISI Database, ISI Classification Basis Document, and IS] Selection Document, addresses the non-exempt components, which require examination and testing.A summary of LGS Units I and 2 ASME Section XI nonexempt components and supports is included in Section 7.0.Aiion Science A Technolo'9., 2-14 _LJ.V02. GO3 Revision 0 IS] Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 2.4-1 LGS UNIT 1 ISI CLASS I AND 2 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

UNIT I & Common UNIT I & Common TITLE (Class 1) (Class 2)FIG-0 1-01 FIG-0 1-02 Residual Heat Removal FIG-01 -!01 FIG-01-102 Residual Heat Removal FIG-O1-04 FIG-01-03 Residual Heat Removal FIG-01-104 FIG-01-103 Residual Heat Removal FIG-01-07A FIG-01-03A Residual Heat Removal FIG-01-107A FIG-O1-1O3A Residual Heat Removal FIG-01-09A FIG-01-05 Residual Heat Removal FIG-0i-109A FIG-0] -105 Residual Heal Removal FIG-01-1 I FIG-01-06 ResidualHeat Removal FIG-01-1 I1 FIG-01-106 Residual Heat Removal FIG-0]-06A Residual Heat Removal FIG-01-106A Residual Htai Removal FIG-0 1-007 Residual Heat Removal FIG-01-107 Residual Heat Removal FIG-01-08 Residual Heat Removal FIG-01-108 Residual Heat Removal FIG-0 1-09 Residual.

Heai Removal FIG-0t-109 Residual Heat Removal FIG-0 1-10 Reactor Recirculation FIG-01-1 10 Reactor Recirculation FIG-01-120 Residual Heat Removal FIG-01-112 Residual Heat Removal FIG-01I- 13 Residual Heat Removal FIG-U1-1 13 Residual Heat Removal FIG-01-14 Residual Heat Removal FIG-0l-1 14 Residual Heat Removal Alion Science A TechwhlogY 2-15 LIM02. G03 Revi.sion 0

IS] Program Plan Limerick Generating Station Units I A 2, Third Interval TABLE 2.4-1 LGS UNIT I ISI CLASS 1 AND 2 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

UNIT I &Common UNIT I & Common I TITLE (Class 1) (Class 2) 1__________________

UNIT I & Common UNIT I & Common TITLE (Class 1) (Class 2)FIG-02-07 High Pressure Coolant Injection FIG-02-107 High Pressure Coolant Injection FIG-02-08 High Pressure Coolant Injection FIG-02-108 High Pressure Coolant Injection FIG-02-09 High Pressure Coolant Injection FIG-02-108 High Pressure Coolant Injection FIG-03-01 FIG-03-03 Main Steam FIG-03-1O1 FIG-03-103 Main Steam FIG-03-02 FIG-03-.5 Main Steam FIG-03-04 FIG-03-105 Main Steam FIG-03-104 FIG-03-06 Main Steam FIG-03-106 Main Steam FIG-04-01 FIG-04-062 Core Spray FIG-04-1 1 FIG-04-102 Core Spray FIG-04-04 FIG-04-03 Core Spray FIG-04-104 FIG-04-103 Core Spray FIG-04-05 Core Spray FIG-04-105 Core Spray FIG-04-06 Core Spray FIG-04-106 Core Spray FIG-04-07 Core Spray FIG-04-1067 Core Spray-FIG-04-07 Core Spray FIG-04-108 Core Spray FIG-04-109 Core Spray FIG-04-110 Core Spray Alion Science & Technology 2-17 Lvio2. G03 Revision 0 IS] Program Plan Limerick Generating Station Units) I 2, Thir Interval TABLE 2.4-1 LGS UNIT 1 IS1 CLASS I AND 2 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

UNIT I & Common UNIT I & Common TITLE ,,(Class 1) f Class 2)FIG-04-1 1i Core Spray FIG-05-01 FIG-05-02 Feedwater FIG-05-1 01 FIG-05-102 Feedwater FIG-05-03 FIG-05-04 Feedwater FIG-05-103 FIG-05-104 Feedwater FIG-05-05 Feedwater (Class 4 Augmented only)FIG-05-06 Feedwater (Class 4 Augmented only)FIG......

FIG-06-02Reactor Core Isolation Cooling (06-02 includes a ,,,F--portion of Non-Classed piping)FIG-06-1 01 FIG-06-102 Reactor Core Isolation Cooling FIG-06-03 Reactor Core Isolation Cooling FIG-06-103 Reactor Core Isolation Cooling FIG-06-04 Reactor Core Isolation Cooling FIG-07-01 Reactor Recirculation FIG-07-101 Reactor Recirculation FIG-07-02 .Reactor Recirculaion FIG-07-102

-Reactor Recirculation FIG-07-03 Reactor Recirculation FIG-07-103 Reactor Recirculation FIG-07-04 Reactor Recirculation FIG-07-104 Reactor Recirculation FIG-08-O Reactor Water Clean Up FIG-08-101 Reactor Water Clean Up FIG-08-02 Reactor Water Clean Up (Includes a portion of Non-Classed piping)F16-08-10-1 Reactor Water Clean Up FIG-08-03 Reactor Water Clean Up FIG-08-103 Reactor Water Clean Up..... .L IM,,, ,,, , 2 , , Alion Science & Technohogr 2-18 LIRVi02. 603 Revision 0 ISI Program Plan Limerick Generating Station Units. I. & 2, Third Interval TABLE 2.4-1 LGS UNIT I 1S1 CLASS 1 AND 2 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

UNIT 1 & Common UNIT 1 & Common TITLE (Class 1) (Class 2)FIG-08-04 Reactor Water Clean Up FIG-08-104 Reactor Water Clean Up FIG-08-05 Reactor Water Clean Up (Augmented only)FIG-08-06 Reactor Water Clean Up (Augmented only)FIG-08-07 Reactor Water Clean Up (Augmented only)FIG-08-08 Reactor Water Clean Up (Augmented only)FIG-09-01 Control Rod Drive FIG-09-101 Control Rod Drive FIG-09-02 Control Rod Drive FIG-09-102 Control Rod Drive FIG-1 1-01 Standby Liquid Control FIG-1 1-101 Standby Liquid Control FIG- 11-02 Standby Liquid Control FIG-I 1- 102 Standby Liquid Control FIG- 11-03 Standby Liquid Control FIG- 11-103 Standby Liquid Control FIG- 12-01 RPV Vent Alion Science & Technology, 2-19 LIM02. G03 Revision 0 IS) Program Plan Limjerick Generating Station Units) I 2, Third Interval TABLE 2.4-2 LGS UNIT 2 IST CLASS I AND 2 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

UNIT 2 UNIT 2 TITLE (Class J) .(ass 2)XI-DCA-204-1 XI-EBB-221

-1 Residual Heat Removal XI-DCA-204-2 XI-EBB-221-2 Residual Heat Removal XI-DCA-204-3 XI-GBB-201-1 Residual Heat Removal XI-DCA-204-4 XI-GBB-201-2 Residual Heat Removal XI-DCA-205-1 XI-GBB-202-1 Residual Heat Removal XI-DCA-205-3 XI-GBB-202-2 Residual Heat Removal XI-DCA-4 18-1 XI-GBB-202-3 Residual Heat Removal XI-DCA-418-2 XI-GBB-203-1 Residual Heat Removal XI-DCA-418-3 XI-GBB-203-2 Residual Heat Removal XI-DCA-418-4 XI-GBB-205-1 Residual Heat Removal XI-DLA-212-I XI-GBB-205-2 Residual Heat Removal XI-DLA-212-2 XI-GBB-207.-1 Residual Heat Removal Xl-DLA-212-3 XI-GBB-207-2 Residual Heat Removal XI-DLA-212-4 XI-GBB-208-1 Residual Heat Removal XI-GBB-208-2 Residual Heat Removal XI-GBB-210-1 Residual Heat Removal XI-GBB-2 11-I Residual Heat Removal XI-GBB-217-1 Residual Heat Removal XI-GBB-2 17-2 Residual Heat Removal XI-GBB-218-1 Residual Heat Removal XI-GBB-2 18-2 Residual Heat Removal X.I-GBB-218-3 Residual Heat Removal X1-GBB-218-4 Residual Heal Removal XI-GBB-2 19-1 Residual Heat Remoial Xl-GBB-2]3

!9-2 Residual Heat Removal XI-GBB-219-3 Residual Heat Removal.....__ _..... .... _ _ _ ... ,-,, ,_, .,_,_,,,_ , , _ _ __. ..._.-lion Science &, 7echnolohgv, 2-20 L1MO2.G03 Revision 0 IS] Program Plan Limerick Generating Station Units)I & 2, Third Interval.TABLE 2.4-2 LGS UNIT 2 IS CLASS I AND 2 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

UNIT2 UNIT 2 TITLE (C lass 1) ..(C lass 2) ........_._.........

XI-GBB-219-4 Residual Heat Removal SX,-GBB-219-5 Residual Heat Removal XI-GBB-219-6 Residual Heat Removal XI-GBB-219-9 Residual Heat Removal XI-GBB-220-9 Residual Heat Removal XI-GBB-220-2 Residual Heat Removal XI-HBB-2217-Residual Heat Removal XI-HBB-217-IA Residual Heal Removal XI-HBB-217-2 Residual Heal Removal Xl-HBB-217-2A Residual Heat Removal XI-HBB-217-3 Residual Heat Removal XI-HBB-217-3A Residual Heat Removal XI-H.BB-217-4 Residual Heat Removal XI-HBB-217-4A Residual Heat Removal XI-HBB-2 18-4 Residual Heat Removal XI-HBB-218-2 Residual Heat Removal XI-HBB-21 8-3 Residual Heal Removal XI-HBB-218-4 Residual Heat Removal XJ-HBB-2 18-5 Residual Heat Removal XI-HBB-218-6 Residual Heat Removal XI-HBB-218-7 Residual Heal Removal Xl-H.BB-219-1 Residual Heal Removal XI-HBB-260-I Residual Heal Removal Feedwater (XI-DBB-203-I includes "'no-break""0ortions of DBD-203-1 and DBD-205-1)

XI-DLA-206-1 Feedwater Xl-DLA-207-I XI-DBB-203-2 Feedwater Alion Science A 7Tchnohogi 2-21 L102.GO03 Revision 0 IS] Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 2.4-2 LGS UNIT 2 ISI CLASS 1 AND 2 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

UNIT'2 UNIT 2 TITLE (Class 1) (Class 2) _______________________

XrDL 8 X- Feedwater (XI-.DBB-204-1 includes "no-break".............

portions of DBD-204-1 and DBD-205-1)

XI-APE-2M.S-LA XI-EBB-201-1 Main Stream XI-APE-2MS-LB XI-EBB-201-2 Main Stream XI-APE-2MS-LC XI-EBB-202-1 Main Stream XI-APE-2MS-LD XI-EBB-203-1 Main Stream XI-EBB-204-1 Main Stream XI-EBB-204-3 Main Stream.XI-E.B-206-.

Main Stream XI-EBB-207-1 Main Stream XI-EBB-207-2 Main Stream XI-DCA-277-E1 None Reactor Recirculation XI-DCA-285-E2 Reactor Recirculation XI-VRR-2RS-2A Reactor Recirculation XI-VRR-2RS-2B Reactor Recirculation XI-VRR-2RD-2A Reactor Recirculation XI-VRR-2-B

-Reactor Recirculatintion XI-DBA-206-1 XI-EBB-208-1 High Pressure Coolant Injection XI-13A-206-2 XI-EBB-208-2 High Pressure Coolant Injection XI-EBB-229-1 High Pressure Coolant Injection XI-EBB-229-2 High Pressure Coolant Injection SXI-EBB-229-3 High Pressure Coolant Injection XI-EBB-2384-1 High Pressure Coolant Injection-XI-HBB-208-1 High Pressure Coolant Injection XI-H.BB1-208-2 High Pressure Coolant Injection XI-HBB-2109-1 High Pressure Coolant Injection XI-2-B-2120-I High Pressure Coolanw Injection Alion Science & Technology 2-22 Rev'ision 0

is/ Program Plan L im~erik Generating Station Units I &4 2, Third Interval TABLE 2.4-2 LGS UNIT 2 ISI CLASS I AND 2 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

UNIT 2 UNIT 2 TITLE (Class 1) (Class 2)XI-HPP-IP High Pressure Coolant Injection XI-DBA-207-1 XI-DBB-201

-1 Reactor Core Isolation Cooling XI-.EBB3209-I Reactor Core Isolation Cooling XI-EBB-209-2 Reactor Core Isolation Cooling XI-EBB-226-I Reactor Core Isolation Cooling XI-EBB-235-1 Reactor Core Isolation Cooling-XI-EBB-235-2 Reactor Core Isolation Cooling..X.-HBB-201

-1 Reactor Core Isolation Cooling-XI-HBB-201-2 Reactor Core Isolation Cooling XI-DCA-4 19-1 XI-EBB-231 -I Core Spray XI-DCA-420-1 XI-EBB-232-1 Core Spray XI-DLA-210-1 XI-GBB-212-I Core Spray X)-DLA-21 1 -1 XI-GBB-2 12-2 Core Spray XI-GBB-212-3 Core Spray XI-GBB-213-1 Core Spray XI-GBB-213-2 Core Spray XI-GBB-213-3 Core Spray XI-GBB-214-1 Core Spray XI-GBB-2 15-I Core Spray XI-HBB-220-I Core Spray XI-lILBB-220-I A Core Spray XI-HBB-220-2 Core Spray XI-HBB-.120-7A Core Spray XI-H-BB-2120-3.

Core Spray X1-H1BB-202)-3A Core Spray XI-HBB-220-4 Core Spray.4lion Science & 7echnolagk 2-23 LIMO2. Gi3 Revision 0 IS! Program Plant Limerick Generating Station Units I & 2, Third interval TABLE 2.4-2 LGS UNIT 2 ISI CLASS I AND 2 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

UNIT 2 UNIT 2 TITLE (Class 1) j Clsss2)_______________________

XI-HBB-220-4A Core Spray XI-HBB-234-1 Core Spray XI-DBA-2]2-1 XI-DCB-202-1 Reactor Water Clean Up (XI-DCB-202-1 includes.. .................

____ ."no-break" portion of DCC-203- I)XI-DCA-20 I-i Reactor Water Clean Up XI-DCA-201-2 Reactor Water Clean Up XI-DCA-201-3 Reactor Water Clean Up XI-DCA-20 1-4 Reactor Water Clean Up XI-DCA-201 -E2 Reactor Water Clean Up XI-DCA-202-EI None Standby Liquid Control XI-DCA-202-E2 Standby Liquid Control XI-DCA-212-El Standby Liquid Control XI-DCA-212-E2 Standby Liquid Control None XI-EBB-242-IES Control Rod Drive Hydraulics XI-EBB-242-I WS Control Rod Drive Hydraulics XI-DBA-210-1 None RPV Vent Nuclear Boiler Instrumentation and Miscellaneous X1-DCA-21i3-1 None (Includes non-exempi portions of the following lines XI-DCA-213-E2 Nuclear Boiler Instrumentation and Miscellaneous XI-DCA-213-E3 Nuclear Boiler Instrumentation and Miscellaneous Nuclear Boiler Instrumentation and Miscellaneous (Includes non-exempt portions of the following XI-RPV-21N lines: DCA-293-EI.

DCA-294-E2.

DCA-295-E1, DCA-296-E2.

DCA-297-E1, DCA-401-E2.

DCA-404-E 1. DCA-405-E I. DCA-406-E I. DCA-407-E 1.and DCA-408-E I)Alion Science & Technology 2-24 LI.-V#2.G03 Revision 0 IS] Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 2.4-3 LGS UNIT 1 ISi CLASS I AND 2 COMPONENT DETAIL DRAWINGS UNIT I'& Common UNIT 1 & Common TITLE (Class 1) ..(Class 2)..XI-IP-201 Recirculation Pumps Xl- I P-202 RHR Pumps XI-l E-205 -Page I RHR Heat Exchangers XI-IOP-203 RCIC Pump XI-IOP-204 HPCI Pumps Xl-lP-206 Core Spray Pumps XI-BA-I- Page 1 Reactor Pressure Vessel XI-BA-2 -Page I.. Reactor Pressure Vessel XI-BA Page I -Reactor Pressure Vessel XI-BA-4 -Page I Reactor Pressure Vessel XI-BA-4 -Page I Reactor Pressure Vessel XI-BA-6 -Page I Reactor Pressure Vessel XI-BA-7 -Page I -Reactor Pressure Vessel X1-BD-7 -Page I Reactor Pressure Vessel XI-BD-2 -Page 1 Reactor Pressure Vessel XI-BD-3 -Page 1 Reactor Pressure Vessel XI-BE-3 -Page I Reactor Pressure Vessel XI-BE-2 -Page I Reactor Pressure Vessel XI-BE-3 -Page I Reactor Pressure Vessel Xl-BE- -Page I -Reactor Pressure Vessel X1-BE-4 -Page I Reactor Pressure Vessel Xl-BF -Page I Reactor Pressure Vessel XI-BF-1 -Page I Reactor Pressure Vessel XI-BF- -Page 1 Reactor Pressure Vessel XI-BF-3 -Page 1 Reactor Pressure Vessel Xl-BF-4 -Page I Reactor Pressure Vessel.41ion Science & Tech nologr 2-25 LIMO2.G03 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 2.4-3 LGS UNIT I IS! CLASS I AND 2 COMPONENT DETAIL DRAWINGS XI-BF-5 -Page 1 Reactor Pressure Vessel XI-BF-6 -Page I Reactor Pressure Vessel XI-BF-7 -Page I Reactor Pressure Vessel XI-BF-8 -Page I Reactor Pressure Vessel XI-BF-9 -Page I Reactor Pressure Vessel XI-BF-1 7 -Page 1 Reactor Pressure Vessel XI-BG -Page I Reactor Pressure Vessel XI-BH-I -Page 1 Reactor Pressure Vessel XI-BH- I -Page 2 Reactor Pressure Vessel XI-BH-2 -Page I Reactor Pressure Vessel XI-BH-3 -Page I Reactor Pressure Vessel XI-BH-4 -Page 1 Reactor Pressure Vessel XJ-BN -Page 1 Reactor Pressure Vessel XI-BN-1 -Page I Reactor Pressure Vessel XI-BN-1 -Page 2 -Reactor Pressure Vessel X1-BN-I -Page 3 Reactor Pressure Vessel XI-BN-12 -Page I Reactor Pressure Vessel-Page 2 Reactor Pressure Vessel X]-BN-2 -Page 3 Reactor Pressure Vessel XJ-BN-3 -Page 1 Reactor Pressure Vessel XI-BN-3 -Page 2 Reactor Pressure Vessel XI-BN4 -Page I Reactor Pressure Vessel XI-BN-4 -Page 2 Reactor Pressure Vessel Xl-BN-4 -Page 3 -Reactor Pressure Vessel XI-BN-4 -PaNet 4 Reactor Pressure Vessel XI.-BN4 -Page 5 Reactor Pressure Vessel XI-BN-4 -Page 6 Reactor Pressure Vessel XI-BN-4 -Page 7 Reactor Pressure Vessel Alion Science & Technology 2-26 LIMO2.G03 Revision #/

ISI Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 2.4-3 LGS UNIT I IS1 CLASS I AND 2 COMPONENT DETAIL DRAWINGS XI-BN-5 -Page I Reactor Pressure Vessel Xl-BN-5 -Page 2 Reactor Pressure Vessel X1-BN-6 -Page 1 Reactor Pressure Vessel XI-BN-6 -Page 2 Reactor Pressure Vessel XI-BN-6 -Page 3 Reactor Pressure Vessel XI-B3N-7 -Page 1 Reactor Pressure Vessel XI-BN-7 -Page 2 Reactor Pressure Vessel XI-BN-7 -Page 3 Reactor Pressure Vessel X,-BN-7 -Page 4 Reactor Pressure Vessel XI-13N-8 -PageI -Reactor Pressure Vessel XI-BN-8 -Page 2 Reactor Pressure Vessel XJ-BN-8 -Page 3 -Reactor Pressure Vessel XJ-BN-8 -Page 4 -Reactor Pressure Vessel XI-BN-8 -Page 3 Reactor Pressure Vessel XI-BN-8 -Page 6 Reactor Pressure Vessel XI-BN-8 -Page 7 , Reactor Pressure Vessel XI-BN-9 -Page 6 Reactor Pressure Vessel X1-BN-9 -Page 2 Reactor Pressure Vessel XI-BN-1 -Page I Reactor Pressure Vessel XI-BN-9 I -Page 2 Reactor Pressure Vessel XI-BN-II-Page 2 Reactor Pressure Vessel XI-BN-12 -Page I Reactor Pressure Vessel XI-BN-12 -Page 2 Reactor Pressure Vessel XI-BN- 13 -Page I Reactor Pressure Vessel XI-BN-14 -Page I.. Reactor PresSUr Vesse XI-BNN -Page I Reactor Pressure Vessel XI-FA-13 -Page I Reactor Pressure Vessel XI-FA-4 -Page 3 Reactor Pressure Vessel I ________ B____________

-_____Pa________e

________ Reactor Pressure ______________________'e_____sel___

Alion Science A Technology 2-27 L03102. G63 Revision 0 IS) Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 2.4-3 LGS UNIT I ISI CLASS I AND 2 COMPONENT DETAIL DRAWINGS XI-FA-2 -Page I Reactor Pressure Vessel XI-FA-2 -Page 2 Reactor Pressure Vessel XJ-FA-2 -Page 3 Reactor Pressure Vessel XI-RPV-l -Page 1 Reactor Pressure Vessel Xl-RPV-l -Page 2 Reactor Pressure Vessel XJ-RPV-1 -Page 3 Reactor Pressure Vessel X1-RPV-l -Page 4 Reactor Pressure Vessel XI-RPV-11N RPV App Alion Science & Technwhgs?

2-28 LI M02. G03 Revision 0 IS] Program Plan Limerick Generating Station Units ) & 2, Third Interval TABLE 2.4-4 LGS UNIT 2 IS] CLASS ] AND 2 COMPONENT DETAIL DRAWINGS UNIT 2 UNIT 2 TITLE (C lass 1) j (Class 2) .. .. .. ..... ...XI-2P-201 Recirculation Pumps XI-2P-202 RHR Pumps XI-2E-205 RHR Heat Exchangers XI-20P-203 RCIC Pump XI-20P-204 HPCI Pump XI-2P-206 Core Spray Pumps XI-RPV-2 -Page I Reactor Pressure Vessel XI-RPV-2 -Page 2 Reactor Pressure Vessel XI-RPV-2 -Page 3 Reactor Pressure Vessel XI-RPV-2 -Page 4 Reactor Pressure Vessel XI-BA-1 -Page I Reactor Pressure Vessel X]-BA-2 -Page I -Reactor Pressure Vessel XI-BA-3 -Page 1 -Reactor Pressure Vessel Xl-BA-4 -Page 1 Reactor Pressure Vessel XI-BA-5 -Page I Reactor Pressure Vessel XI-BA-8 -Page 1 Reactor Pressure Vessel XI-BA-9 -Page I. Reactor Pressure Vessel XJ-BD- I -Page 1 Reactor Pressure Vessel XI-BDJ-2 -Page I Reactor Pressure Vessel XI-BD-3 -Page I Reactor Pressure Vessel XI-BE -I- Page 1 -Reactor Pressure Vessel XI-BE-2 -Page 1 Reactor Pressure Vessel XI-BE-3 -Page I Reactor Pressure Vessel XI-BE-4 -Pave I Reactor Pressure Vessel XI-BE-5 -Page 1 Reactor Pressure Vessel Xl-BF -Pace I Reactor Pressure Vessel Alion Science & Technology 2-29 LIMi02. GO3 Revision 0 IS! Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 2.4-4 LGS UNIT 2 ISI CLASS I AND 2 COMPONENT DETAIL DRAWINGS XI-BF-I -Page 2 Reactor Pressure Vessel X1-BF-2 -Page 2 Reactor Pressure Vessel XI-BF-3 -Page 2 Reactor Pressure Vessel XI-BF-4 -Page 2 Reactor Pressure Vessel XI-BF-5 -Page 2 -Reactor Pressure Vessel x1-1317-6

-Page 2 Reactor Pressure Vessel XI-BF-7 -Page 2 Reactor Pressure Vessel XI-BF-8 -Page 2 Reactor Pressure Vessel XI-BF-9 -Page 2 Reactor Pressure Vessel Xl-BF-l 7 -Page 2 -Reactor Pressure Vessel XI-BG -Page 1 -Reactor Pressure Vessel XI-BH-1 -Page 1 -Reactor Pressure Vessel XI-BH-1 -Page 2 -Reactor Pressure Vessel XI-BH-2 -Page I -Reactor Pressure Vessel X1-11-3 -Page .Reactor Pressure Vessel XI-BH-4 -Page 1 -Reactor Pressure Vessel X]-BN -Page 1 Reactor Pressure Vessel XI-BNN -Page 1 Reactor Pressure Vessel XI-BN-1 -Page I Reactor Pressure Vessel XI-BN-I -Page 2 Reactor Pressure Vessel XI-BN-1 -Page 3 Reactor Pressure Vessel XI-BN-2 -Page 1 Reactor Pressure Vessel XI-BN-2 -Page 2 Reactor Pressure Vessel XI-BN-2 -Page 4 Reactor Pressure Vessel Xl-BN-3 -Page 1 Reactor Pressure Vessel Xl-RN-3 -Page 2 Reactor Pressure Vessel Xl-BN-3 -Page I Reactor Pressure Vessel XI-BN34 -Page 2 Reactor Pressure Vessel Ajien Science A Technohnkjy 2-30 e:102iGOi3i Revision 0 IS] Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 2.4-4 LGS UNIT 2 ISI CLASS 1 AND 2 COMPONENT DETAIL DRAWINGS XI-BN-4 -Page 3 Reactor Pressure Vessel X.-.-4 -Page 4 Reactor Pressure Vessel XI-BN-4 -Page 5 Reactor Pressure Vessel XI-BN-4 -Page 6 Reactor Pressure Vessel XI-BN-4 -Page 7 Reactor Pressure Vessel XI-BN-5 -Page I -Reactor Pressure Vessel XI-BN-5 -Page 2 -Reactor Pressure Vessel X1-BN-6 -Page 1 Reactor Pressure Vessel XI-BN-6 -Page 2 -Reactor Pressure Vessel XI-BN-6 -Page 3 -Reactor Pressure Vessel Xl-BN-7 -Page 1 -Reactor Pressure Vessel XI-BN-7 -Page 2 -Reactor Pressure Vessel XI-BN-7 -Page 3 Reactor Pressure Vessel XJ-BN-7 -Page 4 Reactor Pressure Vessel XI-.N-8 -Page I Reactor Pressure Vessel XI-BN-8 -Page 2 Reactor Pressure Vessel XI-BN-8 -Page 3 Reactor Pressure Vessel XI-BN-8 -Page 4 Reactor Pressure Vessel XJ-B3N-8 -Page 5 Seco rsueVse X1-BN-8 -Page 6 Reactor Pressure Vessel X,-,N-8 -Paie 7 Reactor Pressure Vessel XI-BN-9 -Page 1 Reactor Pressure Vessel X1-BN-8 -Page 2 Reactor Pressure Vessel XI-BN-8 -Page I Reactor Pressure Vessel X1-BN- II -Pae I Reactor Pressure Vessel XI-BN-9 -Page 21 Reactor Pressure Vessel XI-BN-9 -Paee I Reactor Pressure Vessel X-BN- 0 Page Reactor Pressure Vessel , ,,P,,,, Alion Science & Technology 2-31 LIM02. G03 Revision 0 IS] Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 2.4-4 LGS UNIT 2 ISI CLASS 1 AND 2 COMPONENT DETAIL DRAWINGS XI-BN- 13 -Page 1 -Reactor Pressure Vessel XI-BN-14 -Page I Reactor Pressure Vessel XI-FA-t -Page 1 -Reactor Pressure Vessel XI-FA-I -Page 3 -Reactor Pressure Vessel X1-FA-2 -Page I -Reactor Pressure Vessel XI-FA-2 -Page 2 Reactor Pressure Vessel Xl-FA-2 -Page 3 Reactor Pressure Vessel Alioti Science (- Tech nology 2-32 LIA'10. 60 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 2.4-5 LGS UNIT I ISI CLASS 3 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

UNIT 1 & Common TITLE (Class 3),, HBC-08 1-01 Emergency Service Water HBC-081-02 Emergency Service Water HBC-082-01 Emergency Service Water HBC-082-02 Emergency Service Water HBC-082-03 Emergency Service Water HBC-083-01 Emergency Service Water HBC-083-02 Emergency Service Water HBC-084-01 Emergency Service Water HBC-084-02 Emergency Service Water HBC-138-01 Emergency Service Water HBC-138-02 Emergency Service Water HBC-138-03 Emergency Service Water HBC- 143-01 Emergency Service Water HBC- 143-02 Emergency Service Water HBC-143-03 Emergency Service Water H.BC- 147-01 Emergency Service Water HBC- 147-02 Emergency Service Water HBC-147-03 Emergency Service Water HBC-152-01 Emergency Service Water HBC-152-02 Emergency Service Water HBC-152-03 Emergency Service Water HBC-1 58-01 Emergency Service Water HBC-159-01 Emergency Service Water HBC- 166-01 Emereency Service Water HBC-192.1-01 Emergency Service Water uHBC- 192-0, Emergency Service VVater Alion Science & Technology 2-33 LlI402.G03 Revision 0 ISI.Program, Plan Limnerick; Geneýrqting, Station Units I & 2, Third Interval TABLE 2.4.5 LGS UNIT 1 ISI CLASS 3 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

HBC- 192-03 Emergency Service Water HBC-1.92-04 Emergncy.

Service Water HBC-1.93-01 Emergency Service Water HBC- 1 93-02 Emergency Servic Water HBC-193-03 Emergency Service Water HBC-193-04i Emergency Service Water HBC- 194-01 Emergency Service Water HBC- I194-Q2 Emergency Service Water HBC- 194-03 Emergency Service Water HBC-194-04 Emergency Service Water HBC-195-01 Emergency Service Water HBC- 195-02 Emergency Service Water HBC-195-03 Emergency Service. Water HBC-195-04 Emergency Service Water HB.238-01 Emergency Service Water (Ends at Unit 2 Boundary)HBC-241-01 Emergency Service Water (Except from FW5 1Ito. FW3)HBC-247-02 Emergency Service Water HBC-25-2-O I Emergency Service Water (Except from FW50 to Unit I/"Unit 2 tie-in)HBC-.266-0 Emergency Service Water HBC-270-0l Emergency Service Water HBC-292-01 Emergency Service Water (Ends at Unit 2 N-, Boundary)

(2 Shts)HBC-292-02 Emergency.

S ervice. Water (Ends at Unit 2 N-5 Boundary)

(2 Shts)HBC-2922-03 Emergency.

Service Water (Ends at Unit 2 N-5 Boundary)

(2 Shts)HBC-292-04 Emergency Service Water (Ends at Unit 2 N-5 Boundary)

(2 Shts)HBC-293-01 Emergency Service Water (Ends at Unit 2 N-S Boundan)HBC-293-02 Emereency Service Water (Ends at Unit 2 N-5 Boundary)HBC-293-03 Emergenc\

Service Water (Ends at Unit 2 N-5 Boundary)HBC-238-01

.Emerg~ency Service Water (Ends at Unit 2 N-S Boundary).......___,,,,__

__... ..____.,_. ....... ..__._,_,,.__...

..........e Alion Science S Technluogv 2-34 LIMO2.GO3 Revision 0 IS! Program Plan Linmerick Generating Station Units I & 2, Third Interval TABLE 2.4-5 LGS UNIT I ISI CLASS 3 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

HBC- 18 1-01 RHR Service Water HBC- 182-01 RHR Service Water HBC-183-01 RHR Service Water HBC-280-01 RHR Service Water (Except from FWI to Unit I/Unit 2 tie-in)HBC-282-01 RHR Service Water(Except from Unit I/Unit 2 tie-in)HBC-282-02 RHR Service Water HBC-507-0 i RHR Service Water HBC-507-02 RHR Service Water HBC-507-03 RHR Service Water HBC-507-04 RHR Service Water HBC-507-05 RHR Service Water HBC-507-06 RHR Service Water HBC-507-07 RHR Service Water HBC-507-08 RFHR Service Water HBC-507-09 RHR Service Water HBC-507-10 RHR Service Water HBC-507-1 I RHR Service Water HBC-507-12 RHR Service Water HB3C-507-13 RHR Service Water HBC-507-14 RHR Service Water HBC-507-1 5 RHR Service Water HBC-507-16 RHR Service Water HBC-507-17 RHR Service Water HBC-507-18 RHR Service Water ,4BC-508-01.

RHR Service Water HBC-508-021 RHR Service Water HBC-509-01 RHR Service Water HBC-509-021 RHR Service Water.4lion Science & Technology 2-37 LIM02. G03 Revision 0 ISi Program Plan Limerick Generating Station Units I & 2, Third Interval/TABLE 2.4-5 LGS UNIT 1 ISI CLASS 3 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

HBC-537-01 RHR Service Water HBC-563-01 RHR Service Water Aliom, sc'ience 9- Technologi', 2-38 L1,4102.(603 Re'visiojnf

(

.St Progrool Plan Limerick Generating Stalun- Unils I & 2, Third 1njervaI TABLE 2.4-6 LGS UNIT 2 ISI CLASS 3 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

UNIT 2 TITLE (Class 3)HBC-238-1 Emergency Service Water (Starts at Unit 2 Boundary)HBC-243-1 Emergency Service Water (From FW51 to FW3)HBC-243-2 Emergency Service Water HBC-243-3 Emergency Service Water (From FW I to 6"A4" conc. reducer)HBC-247-)

Emergency Service Water (From FW6, FW7, and FW8 to 6"x3" cone. reducer)HBC-252-1 Emergency Service Water (From. FWS0 to Unit 1/Unit 2 tie-in)HBC-252-2 Emergency Service Water HBC-252-3 Emergency Service Water (From 6"x4" conc. Reducer to HBC-252-2)

HBC.258-1 Emergency Service Water HBC-259-1 Emergency Service Water HBC-268-1 Emergency Service Water HBC-292-1 Emergency Service Water (Starts at Unit 2 N-5 Boundary)HBC-292-2 Emergency Service Water (Starts at Unit 2 N-5 Boundary)HBC-292-3 Emergency Service Water (Starts at Unit 2 N-5 Boundary)HBC-292-4 Emergency Service Water (Starts at Unit 2 N-5 Boundary)HBC-293-4 Emergency Service Water (Starts at Unit 2 N-5 Boundary)HBC-293-2 Emergency Service Water (Starts at Unit 2 N-5 Boundary)HBC-293-3 Emergency Service Water (Starts at Unit 2 N-5 Boundary)HBC-293-4 Emergency Service Water (Starts at Unit 2 N-5 Boundary)HBC-294-4 Emergency Service Water (Starts at Unit 2 N-5 Boundary)HBC-294-2 Emergency Service Water (Starts at Unit 2 Boundary)HBC-294-3 Emergency Service Water (Starts at Unit 2 Boundary)HBC-294-4 Emergency' Serv ice Water (Starts at Unit 2 Boundary)HBC-294-4 Emergency Service Water (Starts at Unit 2N-5 Boundary)HBC-295-2 Emergency Service Water (Starts at Unit 2 N-5 Boundary).1aion Science A Technollhg." 2-39 LIMO2.G03 Revision 0 IS] Program Plan Limerick Generating Station Units I A 2, Third Interval TABLE 2.4-6 LGS UNIT 2 IS CLASS 3 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

HBC-295-3 Emergency Service Water (Starts at Unit 2 N-5 Boundary)HBC-295-4 Emergency Service Water (Starts at Unit 2 N-5 Boundary)GBC-202-I RHR Service Water GBC-203-I RHR Service Water GBC-204-I RHR Service Water GBC-206-1 RHR Service Water GBC-210-1 RHR Service Water HBC-280-1 RHR Service Water (From FWI to Unit 1/Unit 2 tie-in)HBC-280-2 RHR Service Water HBC-281-I RHR Senice Water (From FWI to Unit I/Unit 2 tie-in)HBC-282-I RHR Service Water (From Unit I/Unit 2 tie-in to HBC-282-2)

HBC-282-2 RHR Service Water HBC-283-1 RHR Service Water (From Unit I,/Unit 2 tie-in to FW1)GBC-201-1 Main Stream GBC-201-2 Main Stream GBC-201-3 Main Stream GBC-2014 Main Stream GBC-201-5 Main Stream GBC-201-6 Main Stream GBC-201-7 Main Stream GBC-201-8 Main Stream GBC-201-9 Main Stream GBC-201- 10 Main Stream GBC-201-I 1 Main Stream GBC-203-12 Main Stream GBC-20 I- 13 Main Stream GBC-201I-14 Main Stream GBC-216-14 Main Stream GB-t-IMi Sra A4ion Science & Teuhnology 2-40 L IM 02'. GO3 Revision 0 ISI Program. Plan Limerick Generating Station Units 1 & 2Z Third Interval TABLE 2.4-6 LGS UNIT 2 ISI CLASS 3 ISOMETRIC DRAWINGS (WELD AND HANGER IDENTIFICATION)

GBC-216-2 Main Stream GBC-216-3 Main Stream GBC-216-4 Main Stream GBC-216-5 Main Stream GBC-216-6 Main Stream GBC-216-7 Main Stream GBC-2 16-8 Main Stream GBC-216-9 Main Stream GBC-216-10 Main Stream GBC-216-11 Main Stream GBV-216-12 Main Stream GBC-216-13 Main Stream GBC-216-14 Main Stream t 4Iin.n Science & Technology 2-41 L 1,102. G03 Revision 0 ISI Program Plan Limerick Generating Station Unitss I & 2, Third Interval TABLE 2.4-7 LGS CONTAINMENT ISI REFERENCE DRAWINGS UNIT I & Common UNIT 2 TITLE Exterior Bulkhead Assembly 2'-6" x 6'-0" C-002-00096 C-002-00096 PronlLc______________________________________Personnel Lock C-002-00139 C-002-00139 12'-0" 1.D. Equipment Door for Personnel Lock C-002-00243 C-002-00243 Top Head, Flange, Bolting Rings and Seal Plate Assembly C-002-00247 C-002-00247 Top Head Dollar Plates and Access Manhole Sihop Assemblies C-0247 C-0247 Reactor Building Units I & 2, Primary Containment General Arrangement C-0262 C-0262 Reactor Building Primary Containment Downcomer Arrangement Reactor Building.

Units 1 & 2 Primary C-0270 C-0270 Containment MSRV Discharge Pipe and Downcomer Bracing C-0276 C-0276 Liner Plate Requirements General Outline C-0279 C-0280 Liner Plate Requirements Penetration Schedule C-0283 C-0283 Reactor Building Units I & 2, Liner Plate Requirements, Suppression Pool Details Reactor Building Units I & 2, Liner Plate C-0287 C-0287 Requirements, Drywell Penetration Sections and Details.C-0288 C-0288 Reactor Building Units I & 2, Liner Plate....... .... .. Requirements Drywell Penetration Details Reactor Building, Primary Containment Downcomer Details C-0294 C-0294 Diaphragm Floor Plan and Details C-0776 C-0776 Liner Plate Attachment Acceptance Criteria C-0867 C-0867 Drywell Wall Sections -Details Units I & 2 C-0936 C-0936 Seismic Stabilizer Plan and Details C-0943 C-0943 "Drywell Interior Structural Steel Beam Connection Details M-0057 M-0057 P&ID Containment Atmospheric Control M-0060 M-0060 P&ID Primary Containment Leak Testing M-0061 M-0061 P&ID Liquid Radwaste Collection M-0391 M-0391 Flued Head Details Alion Science & Technology 2-42 LIM02. G03 Revision 0 IS Program Plan Limerick Generating Station Lnits I & 2, Third nrl TABLE 2.4-8 LGS UNIT 1 ASME SECTION XI UT CALIBRATION BLOCKS UNIT I & Common UNIT I & Common UNIT I & Common Cal. Block No. Material Drawin No. (03-) ..LIM-30-.625-CS SA333Gr6 M-246A-258 LOM-30-.375-CS SA155GrKC70 M-246A-61 LIM-28-SS-O'LAY SA3 ! 2Gr3O04 M-246A-275 LIM-22-SS-O'LAY SA312Gr304 M-246A-275 LIM-20-SS-O'LAY SA312Gr304 M-246A-275 LIM-28-2.72-SS316 SA358T316L M-246A-256 LIM-28-1.285-SS316 SA403WP31 6 M-246A-256 LIM-28-1.076-SS316 SA358T316 M-246A-256 LIM 1.013-CS SA1 06GrC M-246A-256 LIM-26-.928-CS SA I06GrC M-246A-60 LIM-24-1.812-CS-F SA350LF2 M-246A-256 LIM-24-1.812-CS SA106GrB M-246A-60 LIM-24-.375CS SA106GrB M-246A-61I LIM-22-1.22-CS SA234WPB M-246A-256 L1M 1.009-SS3 16 SA358T316 M-246A-207 LIM-20-1.031-CS SA333Gr6 M-246A-60 LIM 1.031-SS SA403WP304-W M-246A-256 LIM-20-.903-SS316 SA358T316L M-246A-258 LIM-20-. 733-SS SA376T304 M-246A-260 LIM-20-.375-CS SA106GrB M-246A-61 LIM-20-.500-CS SA 1I6GrB M-246A-260 LIM-18-.500-CS SA106GrB M-246A-258 L1M-18-.938.-CS SA106GrB M-246A-260 LIM-148-375CS SA106GrB .*M-246A-61 LJM- 16-1,219-CS SA 106GrC M-246A-60 LIM-16-,500-CS SA333IGr6 M-246A-258

-,lion Science S& Technhlogy 2-43 LI1102.G03 Revision 0 IS! Program Plan Limerick Generating Station Units I A 2, Third Interval TABLE 2.4-8 LGS UNIT 1 ASME SECTION XI UT CALIBRATION BLOCKS UNIT 1 & Common UNIT I & Common UNIT I & Common Cal. Block No. Material Drawing No..(8031-)

LIM-16-.375-CS SA106GrB M-246A-61 LIM-14-1.093-CS SA106GrB M-246A-256 LIM- 14-.937-CS SA106GrB M-246A-258 LIM-14-.750-CS SAI06GrB M-246A-260 LiM-14-375-CS SA106GrB M-246A-61 LIM-12-.843-CS SAI O6GrB M-246A-258 LIM-12-.843-SS316 SA358T316L LIM-12-.688-CS SA333Gr6 M-246A-258 LIM- 12-.688-SS SA312T304 M-246A-260 LIM-12-.688-SS316 SA358T316L M-246A-258 LINM-=12-.586SS SA358Tp3O4 M-246A-260 LIM- 1 2-.375-CS SA 106GrB M-246A-6 1 LIM-10-.843-CS SA106GrB M-246A-258 LIM-10-.718-CS SA106GrB M-246A-258 UAM- 10.593-CS SA 106GrB M-246A-258 LIM-10-.593-SS316 SA358T316L M-246A-258 LIM-10-.365-CS SA106GrB M-246A-61 LIM-8-.906-CS SA106GrB M-246A-258 LIM-8-.719-CS SA106GrB M-246A-246 L1M .594-CS SA!06GrB M-246A-246 LIM-8-.500-CS SA106GrB M-2-46A-258 LINM-6-.562-CS SA106GrB M-246A-258 LIM-6-A32-CS SA 106GrB M-246A-6 I LIM-6-.432-SS SA376T304 M-246A-6 1..LIM--.280S .SA106Gr.

M-246A-6i ItM-6-.432-SS.

16 SA312T316L M-246A-2) 76 L IM-4-A37-CS SAlO6GrB M-46A-246 A -17 6 3. ...... ... ..... .. ,. .,,_A lion Science & Technologeyi 2-44 L.,102. GO3 Revi.sion 0

ISI Program Plan Limerick Generating Station Units l & 2, Third Interval TABLE 2.4-8 LGS UNIT I ASME SECTION XI UT CALIBRATION BLOCKS UNIT I & Common UNIT I & Common UNIT I & Common Cal. Block No. Material .Drawing No. (8031-)LIM-4-.337-CS SA1 06GrB M-246A-6 I LIM-4-.337-SS304 SA312T304 M-246A-208 LIM-3-.438-CS SAI!06GrB M-246A-230 LIM-SP-515-CS SA515Gr7O M-246A- 194 LIM-SP-350-CS SA35OLF2 M-246A-194 LIM-SP-333-CS SA333Gr6 M-246A-194 LIM-SP- 182-SS316 SA 1 82F316 M-246A-232 LIM-SP- 181-CS SA 81Gr2 M-246A-194 LIM-SP-105-CS SAI05Gr2 M-246A- 194 LIM-3-STUD-CS SA540 B-24CL2 M-246A-218 LIM-3-STUD-I1-CS SA540 B-24CL2 M-246A-278 IUM-1.00-P SA516-Gr70 M-246A-277 LIM-F- 1.8-CS SA5 1 6-Gr70 M-246A-2 11 LIM-F-.8 12-CS SA5]6-Gr70 M-246A-277 LIM-RHR-HT-EX-IR SA105-CL2 XI- I E-205 RPV STD. No. IA SA533 M-246B- 184 RPV STD. No., 2 SA533 M-246B-39 RPV STD. No. 3 SA533 M-246B-127 PRV STD. No. 4 SA533 M-246B-128 RPV FLANGE SEAL A36 M-246B-254 MAIN STEAM ZONE 3 A285 M-246B-188 RECIRC OUT ZONE 3 A285 M-246B-188 FEEDWATER ZONE 3 A285 M-246B-188 PART NO. I THRU 21 SA508 M-246B-2-(I)-8 S)S NO. 4 SA508 M-246B-157 RPV CLOSURE STUD SA540 M-2461B-1 15 NUT NO. B61 SA540 M-246B-37.41ion Science & Technology 2-45 1. M02. G03 Revisi.on 0

I.SI Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 2.4-8 LGS UNIT I ASME SECTION X! UT CALIBRATION BLOCKS UNIT I & Common UNIT I & Common UNIT I & Common Cal. Block No. Material Drawing No. (8031-)LIM-2-.218SS SA312TP3 1 6L M-246A-276 LIM-1 .5-.200-SS SA312TP316L M-246A-276 BF-9-CB- I SA508 M-246B-163 LIM-2 M-246B- 188 A lion Science & Tech~nology' 2-46 I.13102.G03 Rer'ision 0

15S1 Program Plan Limerick Generating Station Units I & 2, Third Interval.TABLE 2.4-9 LGS UNIT 2 ASME SECTION XI UT CALIBRATION BLOCKS UNIT 2 -....... UNIT2 2 Cal. Block No. Material Bechtel Drawing No.LIM-28-2.72-SS316 SA358T31 6L M-246A-256 LIM 1.285-SS316 SA403WP316 M-246A-256 LIM 1.076-SS316 SA358T3 16 M-246A-256 L]M-26-1 .013-CS SA 106GrC M-246A-256 LIM-26-.928-CS SAi06GrC M-246A-60 LIM-24-1.812-CS-F SA350LF2 M-246A-256 LI M-24-1.812-CS SAI 06GrB M-246A-60 LIM-22-1.22-CS SA234-WPB M-246A-256 IAM-22-1.009-SS316 SA358T316 M-246A-207 LIM-20-1.031-CS SA33Gr6 M-246A-60 LIM-20-1.031-SS SA403WP304-W M-246A-256 lIM-20-.903-SS316 SA358T316L M-245A-258 LIM-20-.840-SS316NG SA376T316NG P- 151-54 LIM-20-,733-SS SA376T304 M-246-A-260 LIM-20-.375-CS SA106GrB M-246A-61 LIM-18-,938-CS SA106GrB M-246A-260 LIM-16-1.219-CS SA106GrC M-246A-60 LIM 1.093-CS SA106GrB M-246A-256 LIM- 14-.937-CS SA106GrB M-246A-258 LIM- 14-.750-CS SA106GrB M-246A-260 LIM-12-.843-CS SAI06GrB M-246A-258 LIM- 12-.843-SS316 SA358T316L M-246A-258 LIM-12-688-CS SA333Gr6 M-246A-258 LIM-!24.688-SS SA312T304

%4-246A-260 LIM- 12-.688-SS316 SA358T316L M-2-6A-258 LIM-] 2-688-SS316NG SA376T316NG P-I 51-54 Ati*on Science A 7Technvn'ogi' 2-47 LIM02. G03 Revisiion 0

IS] Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 2.4-9 LGS UNIT 2 ASME SECTION XI UT CALIBRATION BLOCKS LIM-10-.843-CS SA!06GrB M-246A.-258 LIM-10-.718-CS SAI06GrB M-246A-258 LIM-10-.593-CS SAI06GrB M-246A-258 LIM-10-.593-SS316 SA358T316L M-246A-258 LIM-8-.906-CS SA106GrB M-246A-258 LIM-8-.719-CS SA106GrB M-246A-246 LIM-8-.594-CS SA1 06GrB M-246A-246 LIM-6-.562-CS SA106GrB M-246A-258 LIM-6-.432-CS SA1O6GrB M-246A-61 LIM-6-.432-SS SA376T304 M-246A-61 LIM-6-.432-SS316 SA312T316L M-246A-276 LIM-4-.437-CS SA106GrB M-246A-276 LIM-4-.337-CS SA I06GrB M-246A-61 LIM-4-.337-SS304 SA312T304 M-246A-208 LIM-3-.438-CS SA106GrB M-246A-230 LIM-SP-515-CS SA5I5Gr7O M-246A-194 LIM-SP-350-CS SA350LF2 M-246A- 194 LIM-SP-333-CS SA333G6 M-246A-194 LIM-SP- 182-SS316 SA I 82F3 16 M-246A-232 LIM-SP-181-CS SA181Gr2 M-246A-194 LIM-SP- 105-CS SA 105Gr2 M-246A- 194 LIM-3-STUD-CS SA540 B-24CL2 M-246A-218 LIM- 1.00-P SA516-Gr70 M-246A-277 LIM-F- I 18-CS SA516-Gr70 M-246A-211 LIM-F-,812-CS SA5l6-Gr70 M-246A-277 LIM-RHR-HT-EX-IR SA105-CL2 ISI-2E-205 LIM-28-SS-O'LAY SA312Gr304 FSC-265-14 LIM-22-SS-O'IAY SA3 I Gr304 FSC-265-14

.1 lion Science A Technology 2-48 LJiM02. GO3 Revision 0 IS? Program Plan Limerick Generating Station Units I A 2, Third Interval TABLE 2.4-9 LGS UNIT 2 ASME SECTION XI UT CALIBRATION BLOCKS LI M-20-SS-O'LAY SA3 1 2Gr304 FSC-265-14 RPV STD. I A SA533 M-246B- 184 RPV STD. 2 SA533 M-246B-39 RPV STD. 3 SA533 M-246B-127 RPV STD, 4 SA533 M-246B-128 RPV FLANGE SEAL LIM-2 SA533 M-246B- 188 MAIN STEAM ZONE 3 A285 M-246B-188 RECIRC OUT ZONE 3 A285 M-246B- 188 FEEDWATER ZONE 3 A285 M-246B-. 88 PART I THRU 2i SA508 M-246B-2 S/S NO. 4 SA508 M.246B-157 RPV CLOSURE STUD SA540 M-246B- 115 NUT NO. B61 SA540 M-246B137 LIM-U2-N1-NOZ SA508 M-246B-206 LIM-U2-NI-SE SA 182 M-246B-207 LIM-U2-N8-SE SAJ82 M-246B-208 BF-9-CB-I SA508 M-246B-163 BF-9-CB-2 SA508 M-246B-164 A4lion Science A Technology 2-49 LiM62O2(;3 Rev'ision 0

ISI Program Plan Limerick Generating Station Units I & 2, Third Interval 2.5 Technical Approach and Positions When the requirements of ASME Section X1 are not easily interpreted, LGS has reviewed general licensing/regulatory requirements and industry practice to determine a practical method of implementing the Code requirements.

The technical approach and position documents contained in this section have been provided to clarify LGS's implementation of ASME Section X1 requirements.

An index which summarizes each technical approach and position is included in Table 2.5-1.A/ion Science & Technology 2-50 LIMO2.G03 Revision 0 IS] Program Plan Limerick Generating Station Units I & 2, Third Interval TABLE 2.5-1 TECHNICAL APPROACH AND POSITIONS INDEX/SUMMARIES Position Revision Status' (Program)

Description Number Date 2 0 (SPT) System Leakage Testing of Non-Isolable 02/01/07 Buried Components.

0 (SPT) Valve Seats as Pressurization I3T-02 Active Bonres 02/01/07 Boundaries.

13T-03 0Active (CISI) Accessibility for Containment 02/01/07 Examinations.

0 (lSI) Position On Visual Examination 13T-04 Active Anomalies and Required Additional 02/01/07 Examinations.

0 (ISI) Position on Preservice ISI Baseline 13T-05 Active Examination Coverage Limitations Less Than 02/01/07 90%.0 (ISI) Position on ASME Section XI, 13T-06 Active Subsection IWF Successive Exams and 02/01/07 Additional Examinations.

0 (SPT) Position on Performing ASME Section 13T-07 Active XI Pressure Testing of the Reactor Coolant 02/'01/07 Pressure Boundary.13T-08 0Active (1SI) Position on Snubber Operability and LCO 02/01/07 Log.Note 1: Technical Approach and Position Status Options: Active -Current IS1 Program technical approach and position is being utilized at LGS; Deleted -Technical approach and position is no longer being utilized at LGS.Note 2: The revision listed is the latest revision of the subject technical approach and position.

The date noted in the second column is the date of the IS1 Program Plan revision when the technical approach and position was incorporated into the document.Alion Science A Technology 2-51 1 1M02. G03 Revision 0 ISI Program Plan Limerick Generating Station Units)I & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-01 Revision 0 COMPONENT IDENTIFICATION:

Code Class: 2 and 3

Reference:

IWA-5244(b)(2)

Examination Category:

C-H, D-B Item Number: C7.10, D2.10

Description:

System Leakage Testing of Non-Isolable Buried Components Component Number: Non-isolable Buried Pressure Retaining Components CODE REQUIREMENT:

IWA-5244(b)(2) requires non-isolable buried components be tested to confirm that flow during operation 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, LGS has established the following 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 adequate flow through the lines.For lines in which the open end is accessible to visual examination while the system is in operation, visual evidence of flow discharging the line is considered as reasonable proof of adequate flow through the open ended line.For open ended portions of systems where the process fluid is pneumatic, evidence of gaseous discharge shall be considered reasonable proof of adequate flow through the open ended line. Such test may include passing smoke through the line, hanging balloons or streamers, using a remotely operated blimp, using thermography to detect hot air, etc.This acceptance criteria will be utilized in order to meet the requirements of IWA-5244(b)(2).

LGS's position is that proof of adequate flow is all that is required for testing these open ended lines and that no further visual examination is necessary.

This is consistent with the requirements for buried piping, which is not subject to visual examination.

A.lion Science & Technologyp 2-52 L13102. G03 Revision 0 IS1 Progrant Plan Limerick Generating Station Units I & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-02 Revision 0 COMPONENT IDENTIFICATION:

Code Class:

Reference:

Examination Category: Item Number:

Description:

Component Number: CODE REOUIREMENT:

1, 2, and 3 IWA-5221 IWA-5222 B-P, C-H, D-B B15.10, C7.10, D2.10 Valve Seats as Pressurization Boundaries All Pressure Testing Boundary Valves IWA-5221 requires the pressurization boundary for system leakage testing extend to those pressure retaining components under operating pressures during normal system service.POSITION: LGS's position is that the pressurization boundary extends up to the valve seat of the valve utilized for isolation.

For example, in order to pressure test the Class I components, the valve that provides the Class break would be utilized as the isolation point. In this case the true pressurization boundary, 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 the other side of the valve seat is ISI Class 1, 2, or 3.In order to simplify examination of classed components, LGS will perform a VT-2 visual examination of the entire boundary valve body and bonnet (during pressurization up to the valve seat)..4lion Science & Technology 2-53 L03102. G03 Revision 0 ISI Program Plan Limerick Generating Station Units 1 & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-03 Revision 0 COMPONENT IDENTIFICATION:

Code Class: MC

Reference:

, Table IWE-2500-1 Examination Category:

E-A Item Number: E1.I1,EI.12,EI.20

==

Description:==

Accessibility for Containment Examinations Components Number: Various CODE REQUIREMENT:

Table IWE-2500-1, Examination Category E-A, Note 1, requires examination of all accessible interior and exterior surfaces of Class MC components, parts, appurtenances, and metallic shell and penetration liners of Class CC components., Interpretation XI- 1-98-71 was published in Volume 46 of the ASME Section Xl Interpretations.

This interpretation confirmed that it was the intent of Table IWE-2 500-1. Category-E-A, Accessible Surface Areas, that surface areas could be considered inaccessible if visual access by line of sight with adequate lighting from permanent vantage points is obstructed by permanent plant structures, equipment, or components, provided these surface areas do not require examination in accordance with the inspection plan for IWE- 1240 (i.e., Surface Areas Requiring Augmented Examination).

This interpretation was incorporated into the 2000 Addenda of the 1998 Edition of sub-paragraphs IWE-1231(b), IWE-1232(c), IWE-2310(a), and IWE-2330(b) under Code Action BC-99-489 and proijdes the needed clarification to define accessible surface areas.It should be noted that this definition of accessible surfaces cannot be applied to containment surface areas subject to augmented examination in accordance with IW E- 1240 and examined to the requirements of Table IWE-2500-1, Examination Category E-C.POSITION: LGS's position on accessibility for containment examinations is that surface areas are considered inaccessible if visual access by line of sight with adequate lighting from pemfanent vantage points is obstructed by permanent plant structures, equipment, or components, provided these surface areas do not require augmented examination.

Alion Science A 2-54 L1MO2.G03 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third interval TECHNICAL APPROACH AND POSITION NUMBER 13T-04 Revision 0 COMPONENT IDENTIFICATION:

Code Class: 1, 2, and 3

Reference:

IWA-2213 Examination Category:

F-A Item Number: F1. 10, F1.20, F1.30, F1.40

Description:

Position On Visual Examination Anomalies and Required Additional Examinations Component Number: Class 1, 2 and 3 Piping Supports CODE REOUIREMENT:

IWA-22 13 states that VT-3 examinations are conducted to determine the general mechanical and structural condition of components and their supports by verifying parameters as clearances, settings, and physical displacements; and to detect discontinuities and imperfections, such as loss of integrity at bolted or welded connections, loose or missing parts, debris, corrosion, wear, or erosion and conditions that could affect operability or functional adequacy.POSITION: In accordance with ASME Section X1, IWA-2213, VT-3 visual examinations are conducted to determine the general mechanical and structural condition of components and their supports by verifying parameters such as clearances, settings, and physical displacements; and to detect discontinuities and imperfections, such as loss of integrity at bolted or welded connections, loose or missing parts, debris, corrosion, wear, or erosion. VT-3 includes examinations for conditions that could affect operability or functional adequacy of snubbers and constant load and spring type supports.

Integral to these examinations is the determination of the integrity of the component to perform its intended function.As such, anomalies identified during performance of the visual examinations that do not negate the integrity of the component to perform its intended function do not require conducting additional or successive examinations (such as those required by paragraphs IWF-2430 or IWF-2420(b), respectively), even if the station chooses to perform corrective measures for the purpose of restoring the component to its original design condition.

One example of this would be a locking nut found to be loose on a sway strut connection with the adjacent main nut found secure. In this example, because the main nut was found to be secure. the sway strut remained capable of performing its intended function, even though corrective measures to tighten the locking nut areperformed:

This position is consistent with ASME Section XI Interpretation Xl- I 30R.Additionally, anomalies identified during performance of the visual examinations that can be clearly determined to not be service-induced failures do not require conducting additional or Alion Science & Technology 2-55 L A14,1Z G03 Revision 0 ISI Program Plan Limnerick Generating Station Units I & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-04 Revision 0 successive examinations (such as those required by paragraphs IWF-2430 or IWF-2420(b), respectively), even if corrective measures are required to restore the component in order for it to be able to perform its intended function, again consistent with ASME Section XI Interpretation XI1- 30R.Examples are as follows: A sway strut is found bent as the result of rigging or other physical work activity.

In this example, the condition can be directly attributed to a physical work activity and not as a result of system normal or transient operation (i.e., service-induced) that could have potentially impacted other components on the same piping run.Anomalies are observed that are clearly from workmanship issues and not caused by operating conditions, such as, arc strikes, clearances introduced by original fabrication or improper installation, and bent components caused .by welding and not from overloading.

41lion Science & 7,chtioloi,'y 2-56 LJ1.02.G03 Revision 0 ISi Program Plan Limerick Generating Station Units I & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-05 Revision 0 COMPONENT IDENTIFICATION:

Code Class: 1, 2, and 3

Reference:

IOCFR50.55a(g)(5)(iv)

Examination Category:

N/A Item Number: N/A

Description:

Position on Preservice ISI Baseline Examination Coverage Limitations Less Than 90%Component Number: N/A In accordance with 10CFRS0.55a, "Each operating license for a boiling or pressurized water-cooled nuclear power facility is subject to the conditions in paragraphs (f (Inservice Testing Requirements)(pumps and valves)) and (g (Inservice Inspection Requirements))

of this section...in addition to those specified in section 50.55.Paragraph (g)(5)(iv) states, "Where an examination requirement by the code or addenda is determined to be impractical by the licensee and is not included in the revised Inservice Inspection program as permitted by paragraph (g)(4) of this section, the basis for this determination must be demonstrated to the satisfaction of the Commission not later than 12 months after the expiration of the initial 120-month period of operation from start of facility commercial operation and each subsequent I 20-month period of operation during which the examination is determined to be impractical.

POSITION: The purpose of this position statement is to clarify the action(s) required for Preservice ISI baseline examinations for which examination coverage is limited to less than 90%, as it pertains to Inservice Inspection requirements.

I OCFR50.55a, Codes and Standards, provides the basis for this position statement.

Unless otherwise stated, all paragraph and sub-paragraph reference identifiers in this position statement pertain to I OCFR50.55a.

Following in-depth reviews of applicable Code of Federal Regulations sections and ASME Code documents, as well as discussions with industry peers, it is LGS IS] Program's position that paragraph (g)(5)(iv) is also applicable to Preservice IS] baseline examinations performed following repairs/replacements and/or modifications within a current 120-month period of operation ti.e., inspection interval).

An example would be the performance of a Preservice ISI baseline ultrasonic exam of a piping weld for which less than 90% examination coverage could only be obtained.

In this case, the submittal of a pending relief request would be tracked within the ISI Program for submittal to the Commission to demonstrate the basis for this determination not later than 12 months after the expiration of the 120-month period of operation (inspection interval) in which the limited examination occurred.A4lion Science & Technology 2-5 7 LI3M02.G03 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-06 Revision 0 COMPONENT IDENTIFICATION:

Code Class: 1, 2, and 3

Reference:

IWF-2420 Examination Category:

F-A Item Number: Fl7.10, Fl.20, F1.30, F1.40

Description:

Position on ASME Section XI, Subsection IWF Successive Exams and Additional Examinations CODE REOUIREMENT:

ASME Section XI, IWF-2420, dictates the requirements for Successive Examinations, including the requirements for re-examination of a component support accepted for continued service in accordance with. IWF-3112.2 or JWF-3122.2 (i.e., during the next inspectionperiod).

ASME Section XI, IWF-2430, dictates the Additional Examinations required for component support examinations performed in accordance with Table IWF-2500-1 that reveal flaws or relevant conditions exceeding the acceptance standards of IWF-3400.Table IWF-2500-1 provides the examination requirements and frequency of inspection for Examination Category F-A Supports scheduled for examination during Each Inspection Interval.POSITION: A Successive Examination (re-examination) of a component support which had been accepted for continued service in accordance with 1WF-3112.2 or IWF-3122.2 is performed per the requirements of IWF-2420, Successive Examinations, and is not an examination scheduled per the 10-year Inspection Interval requirements and frequency of inspection in accordance with Table IWF-2500-1.

Therefore, the additional examination requirements of IWF-2430, Additional Examinations, do not apply to a successive examination that reveals flaws or relevant conditions exceeding the acceptance standards of IWF-3400, Rather, IWF-2420 continues to apply for that component (i.e., accepted for continued service in accordance with IWF-3 112.2 or IWF-3122.2 and re-examination during the next inspection period).A4ion Science & Technology' 2-58 J1.1102. G03 Revision 0 ISI Program Plan Limerick Generating Station Units 1 & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-07 Revision 0 COMPONENT IDENTIFICATION:

Code Class: 1

Reference:

Table IWB-2500-1; IWA-4500 Examination Category:

B-P Item Number: B 15.10

Description:

Position on Performing ASME Section XI Pressure Testing of the Reactor Coolant Pressure Boundary BACKGROUND:

A 1996 revision to I OCFR50 Appendix G, "Fracture Toughness Requirements" for the reactor coolant pressure boundary (RCPB), included an explicit prohibition against completing ASME Section XI pressure tests after initiating core criticality (i.e., nuclear heat may not be used to achieve pressurization).

This prohibition was the result of issues involving pressure testing at Plant Hatch, and related backfit appeals by NUBARG in the late 1980's and early 1990's. This issue resurfaced in 1997 when Quad Cities Station performed an ASME Section XI leakage test of the "RPV" after startup from a refueling outage (i.e., the OPS HYDRO was performed using nuclear heat). The USNRC issued Information Notice 98-13 to remind licensees of the prohibition on core criticality prior to the completion of ASME Section XI pressure tests.Although IOCFR50 Appendix G applies to the entire RCPB (i.e., all ASME Class I systems), it is important to note that the specific prohibition applies only to ASME Section XI pressure testing of the 'Reactor Vessel". It is also noted that during the 1996 Rule Making process the ACRS and NEI both took specific exception to the Staff s prohibition.

At issue are the three (3) types of pressure tests that include the RPV in the boundary of the test: 1. ASME Section XI, Table IWB-2500-1, Periodic pressure tests of systems comprising the RCPB following each refueling outage." The ASME Code clearly requires that these pressure tests be performed "prior to plant startup" from each refueling outage.* Core criticality (i.e., nuclear heat) may not be used to achieve pressurization.

2. ASME Section X1; IWA-4540, Repair and Replacement pressure tests of affected RCPB components.

The ASME Code allows the component(s) to be tested "prior to or immediately upon return to service".* Per the ASME Code, either flood-up and pressurization from external sources (non-nuclear heat) or core criticality (nuclear heat) may be used for pressurization.

3. Procedure MA-AA-736-012, non-ASME Code. Post Maintenance Tests (PMT). of the RCPB systems or components.

Alion Science & Tecthnohkgy 2-59 LIM,102. G03 Revision 0 IS! Program Plan Limerick Generating Station Units I & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-07 Revision 0 9 Pressure tests, performed solely to meet MA-AA-716-012 PMT requirements, are not subject to the prohibitions of I OCFR50 Appendix G.o By procedure, either flood-up and pressurization from external sources (non-nuclear heat) or core criticality (nuclear heat) May be used for pressurization.

In all applicable documentation, the USNRC Staff has identified this as a compliance issue.However, the Staffs basis for their position that ASME Section XI pressure testing provides assurance that GDC- 14 requirements to design, fabricate, erect and test the RCPB so as to have an extremely low probability of abnormal leakage, of rapidly propagating failure, and of gross rupture have been met, cannot withstand technical challenge.

Extensive research by the American Society of Mechanical Engineers has shown that ASME Section X1 pressure testing of the RCPB is adequate for determining leak tight integrity but is of little to no value for determining structural integrity.

RCPB structural integrity is best measured by the periodic performance ASME Section XI surface and volumetric nondestructive examinations and best protected by adherence to T.S. operating limits.The Staff's risk determination also cannot withstand technical challenge.

A review of the risks involved in performing ASME Section X1 pressure tests by flood-up and pressurization from external sources (non-nuclear heat) has concluded that this type of testing represents the most significant challenge to plant safety. Although there is no USQ involved with the conduct of the pressure test; the margin to brittle fracture is reduced; the highest operating stresses are imposed;an additional thermal cycle is imposed; fatigue usage is increased; infrequently used/abnormal system alignments are required and; the potential for violations of Plant Technical Specifications is increased.

Based on our analysis we concur with the USNRC Staff that the issue of ASME Section XI pressure testing and core criticality is one of compliance and not an issue involving nuclear safety provided we remain in compliance with the applicable Codes, Standards and Regulations.

Although permitted by the ASME Code, to ensure compliance with I OCFR50 Appendix G, for ASME Section Xl Repair and Replacement pressure tests (Type 2 tests, above) to the RPV shell (pressure retaining membrane excluding bolting), out to and including the safe ends, and interior attachment welds to the RPV shell (pressure retaining membrane only, internal components excluded) shall not use core criticality (nuclear heat) to achieve pressurization.

A review of previous and current pressure testing activities at both PB and LG has determined that LGS, as summarized above, has complied and shall remain in compliance with all requirements related to the issue ASME Section X1 pressure testing and core criticality, including the 1996 revision to I 0CFRS0 Appendix G.Alion Science & Teclhnoiogy' 2-60 LIM02.6"03 Rev'ision 0

ISI Program Plan Limerick Generating Station Units I & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-07 Revision 0 CODE REOUIREMENTS:

ASME Section XI 2001 Edition through the 2003 Addenda requires the following pressure testing of the reactor coolant pressure boundary (RCPB): a) A system leakage test following each refueling outage, prior to plant start-up (Examination Category B-P).* The ASME Code clearly requires these tests to be performed "prior" to plant startup., Flood-up and pressurization from external sources (non-nuclear heat) is required..Core criticality (i.e., nuclear heat) may not be used to achieve pressurization.

Once this test is performed, the Code requirement is satisfied for the entire fuel cycle.b) A pressure test (hydrostatic., leakage, functional, or inservice) following certain ASME Section Xi repairs and replacements (IWA-4540).

Only required when a non exempt (from pressure testing) ASME Section X1 repair or replacement has been performed." Test boundary may be limited to the specific component repaired or replaced.* Code allows the component(s) to be tested "prior to or immediately upon return to service".* Code does not specify the method for achieving pressurization.

Therefore, flood-up or core criticality m be used for pressurization." 1OCFR50, Appendix G applies to the pressure boundary of the RCPB. Therefore, limitations on the Code pressure tests shall apply only to Code repairs and replacements of the RPV shell (out to and including the nozzle safe ends) and interior attachments to the shell. Either flood-up or core criticality may be used for pressurization to conduct testing of Code repairs and replacements of RPV internal components.

Repair or replacement of bolting of the R.CPB is under the jurisdiction of the Code rules, however bolting is exempt from the Code pressure testing requirements.

Therefore, flood-up or core criticality May be used for pressurization to conduct testing of RCPB mechanical connections associated with bolting repair or replacement.

Additionally, Procedure MA-AA-716-012, non-Code, Post Maintenance Tests (PMT) of the RCPB may be needed." Opening./closing of the RCPB at a mechanical connection, without repairing or replacing pressure boundary components.

is not a Code repair or replacement.

Therefore, Code pressure testing does not apply.* Pressure tests performed solely to meet MA-AA-71 6-012 PMT requirements are not subject to the prohibition of I OCFR50, Appendix G.Alion Science & Technologtiy 2-61 L IM102, G03 Revis'ion 0

ISI Program Plan Limerick Generatlng Station Units I & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-07 Revision 0" Either flood-up or core criticality May be used for pressurization to perform PMT pressure tests.* The removal of a fuel bundle from* the RPV during a planned or forced maintenance outage is not a Code repair or replacement, nor is it a refueling outage activity.

Therefore Code repair / replacement and periodic pressure testing is not required.ASME Section XI rules for pressure testing do not contain direction regarding core criticality.

When asked the specific question regarding use of nuclear heat (via the Code Inquiry Process), the Code Committee's official response was that the Code did not address such issues (Ref. 10).USNRC STAFF BASIS: In the USNRC response to the NUBARG appeal (Ref. 5), the USNRC. denied the appeal and provided further clarity as to their intent regarding the prohibition on core criticality.

The basis of the Staff position is as follows: Defense in Depth: Any "testing" of a barrier used for the prevention of accidental release of fission products is inappropriate using nuclear power (i.e., core critical)Examinations:

The quality of examinations conducted.

under the conditions of core criticality are potentially questionable, considering the temperature, radiological, and access conditions.

POSITION: As required by 1 OCFR50, Appendix G, core criticality shall not be initiated before the completion of the following ASME Section XI required pressure tests: 1) Post refueling outage leakage or periodic hydrostatic test (Examination Category B-P), or 2) Pressure tests required by ASME Section XI following repairs or replacements associated with the reactor vessel shell (nozzle safe ends inward).All other pressure tests of the RCPB can be conducted after initiation of core critical.Examples-Replacement of Main Steam Relief Valves following the completion of the Examination Category B-P pressure testing.ASME Section XI repair or replacement of mechanical connections associated with lines connecting to the reactorvessel (e.ga; headvent line).Subsequent non-refueling outage breaches of the RCPB, where no ASME Section XI repair or replacement has been perfonned (e.g.; change-out of leaking fuel element).A4lion Science & Technouloi'v 2-62 LIMO2.GO3 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-07 Revision 0 LGS BASIS: The explicit prohibition of I OCFR50 Appendix G applies to ASME Section XI pressure testing of the reactor vessel. Other ASME Section XI pressure tests required for components outside the reactor vessel (but within the RCPB) are not subject to the prohibition.

Defense in Depth: Examinations:

Operational:

Test Performance:

Following completion of the periodic pressure test required by ASME Section XI, Examination Category B-P or IWA-4540, requiring sub-critical core conditions prior to conducting other pressure tests of the RCPB would result in additional thermal cycling of the reactor vessel.This would represent an unnecessary challenge to the vessel from both a fatigue usage and brittle fracture margin perspective.

Examinations of portions of the RCPB are reasonable to perform successfully, even under core critical conditions, since access and ambient temperatures are not significantly different prior to and following criticality.

Radiation exposure for the smaller scope of examinations performed at low power levels is not a concern.Maintaining applicable Mode conditions (i.e., no core criticality) to conduct all pressure tests of the RCPB can result in unnecessary cycling of the RCPB and unnecessary operation of associated components due to Mode limitations.

This can contribute to degradation of the structural components, which is contradictory to the goal of safe operation.

Verification of leak tight integrity may require the benefit of full thermal expansion, which is not achievable with artificial heating. Installation of alternate heating sources, to achieve full thermal expansion, is not warranted.

The Final Rule's prohibition explicitly applies only to the "reactor vessel", and only during required ASME Section XI pressure testing. The ASME Section XI requirements do not explicitly prohibit core criticality.

Current Code requirements and Interpretations (Ref. 11 throughl 3) for pressure testing imply core critical conditions may be used (i.e., Inservice Pressure Test, by definition, requires system to be operating).

Additionally, the ACRS response to the proposed Final Rule (Ref. 6) included a recommendation to revisit the prohibition, as they felt it could not be justified in terms of risk. Nevertheless, after review of all documents associated with this issue, USNRC Staff challenge for use of nuclear heal to conduct any pressure testing of any portion of the RCPB- cannot be ruled out. Undocumented discussions with the Staff and industry experts indicated some disagreement about the appropriate extent of the subject prohibition.

Alion Science & Technology 2-63 L1MO2.,G03 Revixsio 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-07 Revision 0

REFERENCES:

I. ASME Boiler & Pressure Vessel Code,Section XI, Rules For Inservice Inspection Of Nuclear Power Plant Components; 1980 Edition w/ Addenda through Winter 1981 (PBAPS), 1986 Edition (LGS)1995 Edition w/ 1996 Addendum Code Edition currently proposed for USNRC endorsement per 62FR63892, dated 12/3/97 2. Federal Register, (60FR65456, dated December 19, 1995); Final Rule I OCFR Part 50,"Fracture Toughness Requirements for Light Water Reactor Pressure Vessels" 3. SECY-95-205, Revisions to Regulatory Requirements for Reactor Pressure Vessel Integrity in I OCFR Part 50, dated August 4, 1995.4. USNRC Information Notice 98-13: Post-Refueling Outage Reactor Pressure Vessel Leak Testing Before Core Criticality, dated April 20, 1998.5. USNRC letter: James M. Taylor, USNRC Executive Director for Operations, to Messrs.Reynolds and Stenger of the Nuclear Utility Backfitting and Reform Group (NUBARG), dated February 2, 1990.6. Advisory Committee on Reactor Safeguards (ACRS) letter to J. M. Taylor, "Proposed Final Rule and Regulatory Guide for Fracture Toughness Requirements for Light Water Reactor Pressure Vessels", dated June 16, 1995.7. ASME Section XI Code Case N-515, Class I Mechanical Joint Pressure Tests Section X1, Division 1.8. ASME Section XI Code Case N-508-1, Rotation of Serviced Snubbers and Pressure Relief Valves for the Purpose of Testing Section X1, Division 1.9. Draft Regulatory Guide DG-1050 (Revision 12 to Regulatory Guide 1.147), May 1997.10. ASME Section XI Code Inquiry XI-1-86-53, dated 2/11/97.1 I. ASME Section Xl Code Case N-416-1, Alternative Pressure Test Requirement for Welded Repairs or Installation of Replacement Items by Welding, Class 1, 2 and 3.12 ASME Section XI Code Case N-498-Testing for Class I, 2 and 3 Systems.13. ASME Section XI a. Xl- 1-83-25 b. XI-1-83-37R2

c. XI-1-83-70R

d. XI-1-86-13R

e. X]-1-86-34

f. Xl- 1-89-08 g. Xl-1-89-15

h. Xl-1-89-33

i. XI-1-92-23 j .XI-1-92-30 Code Inquiries:

dated 10/27/83 dated 9/19/89 dated 1/26/90 dated 6/10/91 dated 9/18/86 dated 11,14/88 dated 5/t17/89 dated 2/7,90 dated 31 16/92 dated 5;222/92 1, Alternative Rules for 10-Year System Hydrostatic Use of steam for pressure test Hydro testing repair & replacements Leakage test disassembled components Pressure tests disassembly

/ reassembly Exam Calegory B-P pressurizing medium Pressure test for replacement of bolts Pressure tests Class I components Pressure testing after disassembly Exam Category B-P pressurizing medium]WA-5214 pressure tests Alion Scie'nce & Tet'hriolngy 2-64 2-64 LJM02, G03 Revision 0 IS, Program Plan Limerick Generating Station Units 1& 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-07 Revision 0 k. XI-1-92-65

1. XI-1-95-50 dated 2/7/94 dated 11/12/96 Pressure test, replacement of bolting Required pressure tests 2-65 L 1M02. GO.?Aliun Science & Telhnohztyv

'2-65 Revision 0 eiISI Program Plan Limerick Generathig Station Units I & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-08 Revision 0 COMPONENT IDENTIFICATION:

Code Class: 1,2, and 3

Reference:

IWF-5000 Examination Category:

N/A Item Number: N/A

Description:

Position on Snubber Operability and LCO Log BACKGROUND:

The purpose of this engineering evaluation is to document the process that is currently being used to control the Tech Spec 3/4.7.4, Snubber, Allowed Outage Time and to verify that these additional administrative controls meet the requirements of approved Operations and Maintenance procedures.

The structure of snubber related Work Orders as planned in PIMS does not provide for efficient control of the Tech Spec 3/4.7.4, Snubber, Allowed Outage Time. Accordingly the Snubber LCO Log, a LAN based system similar to a Narrative Log,. has been developed for this purpose.POSITION: Snubber related Work Order Activities should be statused in PIMS in accordance with the Maintenance/Outage Schedule.

The actual equipment (snubber) status shall be documented in the Snubber LCO Log by entries made by the Work Group. The LCO/TS Action and ST/RT Logs in the MCR require only a single entry at the beginning of the Snubber Inspection (outage)and may remain open until the end of the Inspection at which time they may be closed.The start of the Snubber AOT shall be the "Pin Out" time entered in the Snubber LCO Log. The end of the Snubber AOT shall be the "VT-3 SAT" time entered in the Snubber LCO Log. The PMT for all snubbers removed for testing or maintenance work is a VT-3 Visual Examination after reinstallation.

An entry in the Snubber LCO Log documenting the satisfactory completion of the PMT is sufficient to return the snubber to operable status.BASIS: OP-AA-108-105, Unavailable Equipment/Equipment Release Q or Tech Spec snubber activities do not require a clearance.

Levels of administrative control, comparable to a Clearance, are provided by the Work Order Activity Description, LCO/TS Action Log and Snubber LCO Log.U.'na'ailability Review -Unavailability Reviews have been completed for 100% of the snubber population.

Engineering and at least two (2) members of Shift Management performed the review. Unavailability Reviews do not require re-review each outage unless there is a A lion Science & Technolog; 2-66 L131072. G03 Revision 0 IS! Program Plan Limerick Generating Station Units I & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-08 Revision 0 Modification involving the addition/deletion of snubbers or other supports within the Snubber Inspection System (SIDS No.). Details of the review are documented in Work Order Activity Description "Special Clearance Requirements".

Two (2) members of Shift Management, one of whom is the Control Room Supervisor, shall authorize snubber Work Order Activities.

Shift Management authorization of snubber Work Order Activities releases the snubber to the Work Group but shall not be considered as starting the TS 3/4.7.4 Allowed Outage Time (AOT). See LS-AA-105, Operability, below.Shift Management authorization of the first snubber Work Order Activity for the Snubber Inspection shall require an entry to be made in the Regulatory Action (LCOITS Action) Log. See OP-AA- 108-104-1000, Regulatory Action, below.LS-AA-105, Operability Affected SSC's are identified by the Snubber Inspection System (SIDS No.) and Snubber LCO Log No. SSC's required to be operable, remain operable with the snubber removed during the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Allowed Outage Time (AOT) provided by TS 3/4.7.4. See USNRC position, below. The snubber AOT shall start with the "Pin Out" time recorded in the Snubber LCO Log and shall end with the "VT-3 SAT" time also entered in the Snubber LCO Log.USNRC Position on Snubber 72 Hour Action Statement:

If a snubber is removed from its installation for testing, the action requirement for the supported system is not applicable, as long as the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months limit is not exceeded.

The snubber could be removed one at a time and replaced, or all snubbers are removed at the same time, and replaced as a group at the same time. The Tech Spec operability requirements do not require consideration of supported system redundancy or impact until the snubbers are out of service in excess of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . The supported system will have to be declared inoperable if the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months limit is exceeded.If a snubber is found to be inoperable, the action statement requires that an engineering evaluation of the supported system be performed or that the supported system be declared inoperable immediately.

The engineering evaluation is to determine if the supported system was affected by the inoperable snubber. This does not relate to the capacity of the attached system to withstand a seismic event.If the results of the evaluation show, prior to the end of the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , that the supported system was made inoperable by the inoperable snubbers and those snubbers were not restored or replaced, then the supported system Tech Specs should be entered then, and not at the end of the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .Note: when a snubber is removed from service for the purpose of testing, an engineering evaluation is not required.Alion Science & Technologly 2-67 L1M02.G03 Revision 0 ISi Program Plan Limerick Generating.Station Units I & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-08 Revision 0 When a supported system LCO is not met due to a support system LCO not being met, only the support system, and not the supported system LCO actions are required to be entered.OP-AA-108-104-1000, ST/RT Status Log Requires only one entry per ST per Snubber Inspection (OUTAGE).

The entry may remain open for the duration(until

the end) of the Inspection at which time they may be closed.* ST-4-103-000-1(2).

Generic Snubber Visual Inspection

ST-4-103-301-1(2), Snubber Functional Test* ST-i-1 03-300-1 (2), 24 Month Snubber Functional Test Program* ST-1 -103-990-1(2), Snubber Service Life Monitor The Plant Information Monitoring System (PIMS), Regulatory Action (LCO/TS Action) Log and the Snubber LCO Log shall be used to control and document the status of snubber activities on SSC's required to be operable.

The most timely information is provided by the Snubber LCO Log.OP-AA-102-102, Narrative Logs / Scope of Entry The Snubber LCO Log is analogous to Narrative Logs for the CRS, ACRS, the ROs, and the PRO. The Snubber LCO Log is available to be viewed in the MCR by CRS, ACRS, the ROs, and the PRO on the LAN, which is accessible from terminals in the MCR.The Snubber LCO Log includes the following information for each snubber: , Outage number* Snubber number* Work Order No.* Date and time the snubber was removed for testing or maintenance

Calculates and displays the 72 hr AOT* Date and time snubber was replaced* Status of visual/functional examinations, SAT/iJNSAT

The supported system* Other affected systems The Snubber LCO Log is updated by the Work Group (Station Maintenance).

This update will always precede updates in PIMS W/O Completion Remarks (CREM).OP-AA-1,08-104-1000, Regulatory Action Upon authorization of the first TS Work Order for snubber inspections/maintenance, Shift Management shall make an entry in the LCO/TS Action Log. The entry shall direct the reviewer to the Snubber LCO Log for the status of a specific snubber. Only one (1) entry in the LCO/TS Action Log isrequired for all inspections/maintenance to be performed on TS snubbers.

The LCOTS Action Log entry may be closed when the last TS snubber Work Order is in "ACT COMPLETE" status in PIMS at the end of the Refueling Outage.Alion Science & Technltagy L1.1102. G03 Revision 0i I s Program Plan Limerick Generating Station Units I & 2, Third Interval TECHNICAL APPROACH AND POSITION NUMBER 13T-08 Revision 0 MA-AA-716-010, Work Order (W/O) Work Performance Snubber Work Order Activities may be taken to "SCHED" or "INPROG" status in PIMS any time following authorization by Shift Management. "SCHED" or "INPROG" status in PIMS shall not be considered as starting the TS 3/4.7.4 Allowed Outage Time (AOT).The entering, by the Maintenance Work Group, of the snubber "PIN OUT" time in the Snubber LCO Log shall constitute:

The start of the 72 Hour Allowed Outage Time, and* Prior notification to Shift Management of the actual start of work.See LS-AA- 105, Operability, above.MA-AA-716-012, Post Maintenance/Modification Testing (PMT)Snubber Post Maintenance Testing is included in the PIMS Component "C" Type Activity for the removal/maintenance/reinstallation of a particular snubber. Completion of the Post-Installation Verification section of procedures M-200-043, M-200-044 or M-200-045, as applicable to the size and make of the specific snubber shall be considered as completion of the PMT for that snubber.OP-AA-108-106, Equipment Return to Service A member of Shift Management shall authorize the return of equipment or systems back to an Operable status after confirmation of the following information as appropriate:

A snubber is considered returned to service and operable status following the satisfactory completion of the PMT based on the following:

o Proper housekeeping and equipment condition has been verified by the PMT.o Completion of a Work Order search is not required since the PMT is required to be completed satisfactorily and deferral of the VT-3 Visual examination is not permitted.

o The PMT is the final required Surveillance Test for that snubber and its satisfactory completion indicates the snubber is in surveillance.

o Required Independent/Double verifications have been completed as specified by individual procedure.

o The system/equipment has been walked down as appropriate to verify that it can be safely operated to fulfill its design function.o The snubber is considered a support system and does not require other auxiliary and support systems for operability.

No Operating Procedures, including COLs, are required to return equipment'systems to service.No compensatory actions other than completing the snubber work within the snubber 72 Hour AOT are taken or needed to be closed out.,41ion Science & Techinlogy 2-69 LIA.112. G03 Revision 0 IS1 Program Plan Limerick Generating Stalion Units I & 2, Third Interval 3.0 COMPONENT ISI PLAN The LGS Component ISI Plan includes ASME Section XI nonexempt pressure retaining welds, piping structural elements, pressure retaining bolting, attachment welds, pump casings, valve bodies, reactor vessel interior, reactor vessel core support structures, and reactor vessel interior attachments of ISI Class 1, 2, and 3 components that meet the criteria of Subarticle IWA- 1300. These components are identified on the ISI Boundary Drawings listed in Section 2.3, Table 2.3-1. These drawings are identified with a special prefix of "ISI" for the color-coded P&IDs (e.g.; ISI-M-01).

Corporate procedure ER-AA-330-002 "Inservice Inspection of Welds and Components", implements the ASME Section XI welds and components program. This Component ISI Plan also includes component augmented inservice inspection program information specified by documents other than ASME Section XI as referenced in Section 2.2 of this document.See the Augmented Inspection Program for details on these additional requirements and references.

3.1 Nonexempt

ISI Class Components The LGS IS] Class I components subject to examination are those that are not exempted under the criteria of Subarticle IWB-1220 in the 1989 Edition, No Addenda of ASME Section XI (see Section 3.1.2 below). The LGS ISI Class 2 and 3 components identified in ISI Boundary Drawings are those not exempted under the criteria of Subarticles IWC- 1220 and IWD- 1220 in the 2001 Edition through the 2003 Addenda of ASME Section XI. A summary of LGS Units 1, 2, and Common ASME Section XI nonexempt components is included in Section 7.0.3.1.1 Identification of 1SI Class 1, 2, and 3 Nonexempt Components ISI Class 1,'2, and 3 components are identified on the 1S1 Isometric and ISI Component 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. The Class I and 2 Isometric Drawings are identified with a special prefix of "FIG" for Unit 1 and "Xl" for Unit 2 (e.g.; FIG-01-01 or XI-DCA-204-1).

Welded attachments are also identified by controlled LGS support drawings.3.1.2 1 OCFR50.55a(b)(2)(xi) specifies that the 198:9 Edition, No Addenda of ASME Section XI, Subarticle IWB-1220 shall be used in lieu of the 2001 Edition through the 2003 Addenda of ASME Section XI. Subarticle IWB- 1220.11 B- 1 12.O, Co mponents Exempti rim. fom mination (1989 Edition. No SLLA ada) -The following components (or parts of components) are een7ptiedfrom the volumetric and suribce examination requirements of per the Code paragraph referenced:

..:lion Science & Techltdnov 3-I LIA102.G03

......... r Revision 0 151 Program Plan Limerick Generating Station Units I & 2, Third Interval (a) Components that are connected to the Reactor Coolant System and part of the reactor coolant pressure boundary, and that are of such a size and shape so that upon postulated rupture the resultingflow of coolant from the Reactor Coolant System, under normal plant operating conditions, is within the capacity of makeup systems which are operable from on-site emergency power;(Refer to Section 3.3 of this document).(b)(1) piping of Nominal Pipe Size (NPS) I and smaller;(b) (2) components and their connections in piping of NPS I and smaller;(c) reactor vessel head connections and associated piping, NPS 2 and smaller, made inaccessible by control rod drive penetrations.

3.2 Risk-Informed Examination Requirements Piping structural elements that fall under RISI Examination Category R-A are risk ranked as High (1, 2, and 3), Medium (4 and 5), and Low (6 and 7). Per the EPRI Topical Reports TR- 112657, Rev. B-A, TR-1006937, Rev. 0-A, and Code Case N-578- 1, piping structural elements ranked as High or Medium Risk are subject to examination while piping structural elements ranked as Low Risk are not subject to examinations (except for pressure testing).

Thin wall welds that were excluded from. volumetric examination under ASME Section XI rules per Table IWC-2500-1 are included in the element scope that is potentially subject to RISI examination at LGS.Piping structural elements may be excluded from examination (other than pressure testing) under the RISI Program if the only degradation mechanism present for a given location is inspected for under certain other LGS programs such as the Flow Accelerated Corrosion (FAC) or IGSCC Programs.

These piping structural elements will remain part of the FAC or IGSCC Programs, which already perform"for cause" inspections to detect these degradation mechanisms.

Piping structural elements susceptible to FAC or IGSCC along with another degradation mechanism (e.g., thermal fatigue) are retained as part of the R1SI scope and are included in the element selection for the purpose of performing exams to detect the additional degradation mechanism.

The RISI Program element examinations are performed in accordance with Relief Request 13R-02..-lion Science & Technology 3-2 LI,1102.G03 Revision 0 IS] Program Plan Limerick Generating Station Units I & 27; Third Interval 3.3 ISI Class I Piping Size Exemption for Water and Steam The basis for determining the size of ISI Class I water and steam lines exempted from the surface and volumetric examination requirements of ASME Section XI Article IWB-1200 are provided in LGS Calculation No., MISC-41, Rev. 3.The ISI Class I size exemption for water and steam at LGS (refer to IWB-1220)consists of the following systems: Pump 'Maximum Emergency System Flow Rate Fluid Temp. Power RCIC -(Reactor Core Isolation 600 GPM 95° F Yes, Cooling).

UFSAR, Subsection On-site 5.4.6 CRD -(CRD Cooling Water 170 GPM 95" F Yes, Flow). UFSAR, Subsection 4.6.1 On-site LGS has determined through the criteria of Subarticle IWB-1220(a) that Class 1 components which are (1) 1.53" ID and smaller for liquid filled components or (2)2.96" ID and smaller for steam filled components are exempt from the volumetric and surface examinations.

In determining the size of the liquid and steam lines excluded from surface and volumetric examination, liquid lines were defined as those that penetrate the RPV below the normal water level and steam lines as those that penetrate the RPV above the normal water level.Note that RCIC does not perform an ECCS function, therefore, this system meets the ASME Section XI criteria for inclusion as a makeup source under IWB-1220(a).

This same approach applies to the alternative requirements of IWA-4131.1 (a)(2).Alion Science & hluhnolq,,,ýy 3-3 LIIIO?. 603 Revisint, 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval 4.0 SUPPORT ISI PLAN The LGS Support ISI Plan includes the supports of ASME Section XI nonexempt ISI Class 1, 2, and 3 components as described in Section 3.0. Corporate procedure ER-AA-330-003 "Visual Examination of Section XI Component Supports", implements the ASME Section XI Support ISI Plan.4.1 Nonexempt ISI Class Supports The LGS IS] Class 1, 2, and 3 nonexempt supports are those which do not meet the exemption criteria of Subarticle IWF-1230 of ASME Section XI. A summary of LGS Units 1, 2, and Common ASME Section XI nonexempt supports is included in Section 7.0.4.1.1 Identification of I:SI Class 1, 2, and 3 Nonexempt Supports ISI Class 1, 2, and 3 supports are identified on the ISI Isometric and Component Drawings listed in Section 2.4, Table 2.4-1, 2.4-2, 2.4-3, 2.4-4, 2.4-5. and 2.4-6. The Class I and 2 Isometric Drawings are identified with a special prefix of "FIG" for Unit I and "XI" for Unit 2 (e.g.; FIG-01-01 or XI-DCA-204-l).

Supports are also identified by controlled LGS individual support detail drawings.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 Examinations and lnservici' Tests (functional tests) of snubbers to be performed in accordance with the Operation and Maintenance of Nuclear Power Plants (OM), Standard ASME/ANSI OM, Part 4. Relief Request 13R-05, which requests relief from the visual examination and functional testing requirements of Paragraphs IWF-5200(a), IWF-5300(a), IWF-5200(b), and IWF-5300(b).

The purpose of this relief request is to justiA, replacing the visual examination and functional testing requirements of Paragraphs lWF-5200(a) and (b) and IWF-5S00(a) and (b) and the fiequency required by OMa-1988 Addenda to the ASME:ANSI OM-1987 Edition. Part 4, with the requirements of LGS Technical Specifications (TS) snubber program, Section 3/4.7.4. A summary of the LGS Unit 1. 2. and Common TS and non-TS snubbers is included in Section 7.0 under Augmented Components.

Corporate procedure ER-AA-33-0-004

"'Visual Examination of Technical Specification Snubbers-.

implements fhe visual inspection progam for TS and non-TS snubbers.

Corporate procedures ER-AA-330-010

"'Administration of Snubber Functional Testing", ER-AA-330-01 1"'Snubber Service Life Monitoring Program", and station sur'eillance test procedures are used to implement the functional testing. visual-lion Science Technology 4-1 Li.1102.G03 Rehvisin 0 ISI Program Plan Limerick Generating Station Unith I & 2, Third Interval examination, and service life monitoring requirements for TS and non-TS snubbers, as applicable.

The ASME Section XI IS] Program uses Subsection IWF to define support inspection requirements.

The ISI Program maintains the Code classified snubbers in the populations subject to inspection per Subsection IWF.This is done to accommodate scheduling and inspection requirements 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 X1 Paragraphs IWF-5200(c) and IWF-5300(c) require integral and non-integral attachments for snubbers to be examined in accordance with Subsection IWF of ASME Section XI. This results in VT-3 visual examination of the snubber attachment hardware including the bolting, load pins, and their interface to the clamp, also referred to as"pin-out", but does not include the component-to-clamp interface.

The ASME Section XI IS] Program uses Subsection IWF to define the inspection requirements for all IS Class 1, 2, and 3 supports, regardless of type. The ISI Program maintains the ISI classified snubbers in the support populations subject to inspection per Subsection IWF. This is done to facilitate scheduling and inspection requirements of the snubber attachment hardware (e.g., bolting and pins) per IWF-5200(c) and IWF-5300(c).

Per Relief Request 13R-05, the examination of the snubber body and extension, also referred to as "pin-in", will be performed in accordance with the TS snubber program.It should be noted that the examination of snubber welded attachments will be performed in accordance with the ASME Section XI SubsectionsIWC, and IWD welded attachment examination requirements (e.g.;Examination Categories B-K, C-C, and D-A)._4ion Science s Tctl. gy 4-2 LI1 102.G03 Revivion 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval 5.0 SYSTEM PRESSURE TESTING ISI PLAN The LGS System Pressure Testing (SPT) ISI Plan includes all pressure retaining ASME Section XI, ISI Class 1, 2, and 3 components, with the exception of those specifically exempted by Paragraphs IWC-5222(b) and IWD-5240(b).

All RISI piping structural elements, regardless of risk classification, remain subject to pressure testing as part of the current ASME Section XI program.The SPT ISI Plan performs system pressure tests and visual inspections on the 1SI Class 1, 2, and 3 pressure retaining components to verify system and component structural integrity.

This program conducts both Periodic and Interval (10-Year frequency) pressure tests as defined in ASME Section XI Inspection Program B. Corporate procedure.ER-AA-330-001 "Section XI Pressure Testing", as well as several LGS site-specific surveillance test procedures, implement the ASME Section XI System Pressure Testing ISI Plan.5.1 ISI Class Systems All Class I pressure retaining components, typically defined as the reactor coolant pressure boundary, are required to be tested. Those portions of Class 2 and 3 systems that are required to be tested include the pressure retaining boundaries of components required to operate or support the system safety functions.

Class 2 and 3 open ended discharge piping and components are excluded from the examination 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 are shown in color on the ISI Boundary Drawings listed in Section 2.3, Table 2.3-1. These drawings are identified with a special prefix of"IS]" for the color-coded P&IDs (e.g.; ISI-M-01).

5.1.2 Identification

of System Pressure Tests The System Pressure Test Boundary Drawings used to define which systems, or portions of systems, fall under a specific test are identified in attachments to the site-specific surveillance procedures.

5.2 Risk-Informed Examinations of Socket Welds Socket welds selected for examination under ,he RISI Prozram are to be inspected with a VT-2 exam each refueling outage per ASME Code Case N-57-I (see footnote 12 in Table I of the Code Case). To facilitate this, socket welds selected for inspection under the RISI Program shall be pressurized each refueling outage in accordance with Paragraph IWA-5211 (a).t lior Science & Technolovl, 5-I L 13102. G63 Revision 0 ISI Program Plan Limerick Generating Station Units ! & 2, Third Interval 6.0 CONTAINMENT ISI PLAN The LGS CISI Plan includes ASME Section XI ISI Class MC pressure retaining components and their integral attachments, and Class CC components and structures that meet the criteria of Subarticle IWA-1300.

This CISI Plan also includes information related to augmented examination areas, component accessibility, and examination review. The CISI Second Inspection Interval for Subsections IWE and iWL is defined in Relief Request 131R-01.The inspection of containment structures, components, and post-tensioning systems are performed per corporate procedures:

1. ER-AA-330-005, "Visual Examination of Section XI Class CC Concrete Containment Structures" 2. ER-AA-330-007, "Visual Examination of Section XI Class MC Surfaces and Class CC Liners" 6.1 Nonexempt CISI Class Components The LGS CISI Classified MC and CC components identified in the ISI Database are those not exempted under the criteria of Subarticles IWE-1220 and Subarticle IWL- 1220 in the 2001 Edition through the 2003 Addenda of ASME Section XI.A summary of LGS Units I and 2 ASME Section XI nonexempt CISI components is included in Section 7.0.The process for scoping LGS components for inclusion in the CfSI Plan is included in the containment sections of the ISI Classification Basis Document.These sections include a listing and detailed basis for inclusion of containment components.

Components that are classified as Class MC and CC must meet the requirements of ASME Section XI in accordance with I0CFR50.55a(g)(4).

Supports of IWE components are not required to be examined in accordance with I OCFR50.55a(g)(4).

6.1.1 Identification

of IS[ Class MC and CC Nonexempt Components C1SI classified MC and CC components are identified on the CISI Reference Drawings listed in Section 2.4, Table 2.4-7. These drawings are identified with special prefixes of"C-' or "M-" for LGS Unit I and 2 (e.g.; C-0247 or M-0057)...lion Science & Technologyw 6-1 LIM02. G03 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval 6.1.2 Identification of SI Class MC and CC Exempt Components The process for exempting LGS components from the CISI Plan per IWE- 1220 and IWL- 1220 is included in the containment sections of the ISI Classification Basis Document.

These sections include a listing and basis for exempting applicable components.

6.2 Augmented

Examination Areas Metal containment components potentially subject to augmented examination per IWE- 1240 have been evaluated in the containment sections of the ISI Classification Basis Document.

These sections define the areas that are subjected to augmented examination.

Similarly, concrete surfaces may be subject to Detailed.

Visual examination in accordance with IWL-23 10, if declared to be 'Suspect Areas' by the examiner or the Responsible Engineer.No significant conditions were identified in the First CISI Interval and no significant conditions are currently identified in the Second Interval as requiring application of additional augmented examination requirements under IWE- 1240 or IWL-23 10.6.3 Component Accessibility Class MC pressure retaining components subject to examination shall remain accessible for either direct or remote visual examination from at least one side per the requirements of ASME Section Xl, Subarticle IWE- 1230.The accessibility for containment examinations is documented in technical approach and position 13T-04.6.4 Responsible Individual and Engineer ASME Section XI Subsection IWE requires the Responsible Individual to be involved in the development, performance, and review of the CISI examinations.

The Responsible Individual shall meet the requirements of ASME Section XI, Subarticle

]WE-2320.ASME Section XI Subsection IWL requires the Responsible Engineer to be involved in the development, approval, and review of the CIS] examinations.

The Responsible Engineer shall meet the requirements of ASME Section XI, Subarticle lWL-2320.Alion Science & TechnaMho 6-2 LIMO2.G03 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval 7.0 COMPONENT

SUMMARY

TABLES 7.1 Inservice Inspection Summary Tables The following Tables 7.1 -1 and 7. 1-2 provide a summary of the ASME Section X1 pressure retaining components, supports, containment structures, system pressure testing, and augmented program components for the Third ISI Interval and Second CISI Interval at LGS Units 1, 2, and Common.The format of the Inservice Inspection Summary Tables is as depicted below and provides the following information:

Examination Item Number Description Exam Total Number of Relief Notes Category (with (or Risk Requirements Components by Request/Examination Category System TA&P Category Number or Number Description)

A ugmented Number)()(2) (3) (4) (5) (6) (7)(1) Examination Category (with Examination Category Description):

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

Only those Examination Categories applicable to LGS are identified.

Examination Category "R-A" from Code Case N-578-1 is used in lieu of ASME Section Xl Examination Categories B-F, B-J, C-F-I, and C-F-2 to identify Class I and 2 piping structural elements for the RISI Program.Examination Calegory "NA" is used to identify Augmented ISI examinations and other LGS commitments.

(2) Item Number (or Risk Category Number or Aupamented Number): Provides the Item Number as identified in ASME Section XI,.Tables IWB-2500-1, IWC-2500-I, IWD-2500-1, IWE-2500-1, IWF-2500-1, and lWL-2500-l.

Only those item numbers applicable to LGS are identified.

For piping structural elements under the RISI Program, the Risk Category Number (e.g., 1-5) is used in place of the Item Number.Specific abbreviations such as: AUG-0 I, AUG-02. and AUG-05 have been developed to identify Augmented ISI examinations and other LGS commitments.-Ulivii Science &~ Technology' 7-1 LIIO ZG03 Revision 0 IS] Program Plan Limerick Generating Station Units I & 2, Third Interval (3) Item Number (or Risk Category Number or Augmented Number)

Description:

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

For Risk-Informed piping examinations, a statement of the Risk Category is provided.For Augmented inspection commitments, a description of the Augmented requirement is provided.(4) Examination Requirements:

Provides the examination method(s) required by ASME Section XI, Tables IWB-2500-1, IWC-2500-1, IWD-2500-1, IWE-2500-1, IWF-2500-1, and IWL-2500-1.

Provides the examination requirements for piping structural elements under the RISI Program are in accordance with the EPRI Topical Reports TR-] 12657, Rev.B-A, TR-l1006937, Rev. 0-A, and Code Case N-5 78-1.Provides the examination requirements for augmented components from LGS commitments or relief requests.(5)-. Total Number Of Components by System Provides the system designator (abbreviations).

See Section 2.3, Table 2.3-1 for a list of these systems.This column also provides the number of components within a particular system for that Item Number, Augmented Number, or Risk Category Number.Note that the total number of components by system are subject to change after completion of plant modifications, design changes, and ISI system classification updates.(6) Relief Request/ Technical Approach & Position Number Provides a listing of Relief Request/Technical Approach & Position (TA&P)numbers applicable to specific components, the ASME Section XI Item Number, Augmented Number, or Risk Category Number.. Relief requests that generically apply to all components, or an entire class are not listed. If a Relief RequestlTA&P number is identified; see the corresponding relief request in Section 8.0 or the technical approach and position in Section 2.5.41ion Science & fechnohlyg) 7-2 LIMO?. G03 Revision 0 ISI Program Plan Limerick Generating Station Units 1 A 2, Third Interval (7) Notes Provides a listing of program notes applicable to the ASME Section XI Item Number, Augmented Number, or Risk Category Number. If a program note number is identified, see the corresponding program note in Table 7.1-3.-Alion Science & T'chnoklg 7-3 LIM 2.G03 Revision 0 ISI Programn Plan.Limerick Generating Station Units I & 2, Third Interval LGS UNITI 1 & COMMON INSERVICE INSPECTION

SUMMARY

TABLE 7.1-1 iaxmination Category Item Description Exam Total Number of Relief Request/ Notes (with Category Description)

Number Requirements Components by TA&P Number.L__ System _ _ =B-A B I.1 Circumferential Shell Welds (Reactor Vessel) Volumetric RPV: 5 13R-04 Pressure Retaining B I. 12 Longitudinal Shell Welds (Reactor Vessel) Volumetric RPV: 13 13R-04 ........Welds in Reactor Vessel B 1.21 Circumferential Head Welds (Reactor Vessel) .Volumetric RPV: 2 B 1 22 Meridional Head Welds (Reactor Vessel) Volumetric RPV: 13 B 1,30 Shell-to-Flange Weld (Reactor Vessel) Volumetric RPV: I B 1.40 Head-to-Flange Weld (Reactor Vessel) Volumetric

& RPV: 1 Surface B-D B3.90 Nozzle-to-Vessei Welds (Reactor Vessel) Volumetric RPV: 34 Full Penetration Welds of Nozzles in Vessels B3.I 00 Nozzle Inside Radius Section (Reactor Vessel) Volumetric RPV: 34 A lion Science & Teclnoi~n~'

7-4 AlianScience

& Technologw, 7-4 LIMO2.G03 Revision 0 IS! Program Plan Limerick Ge'nerating Station Unitv / & 2, Third Interval LGS UNIT I & COMMON INSERVICE INSPECTION

SUMMARY

TABLE 7.1-1 Examination Category Item Description Exam Total Number of Relief Request/ Notes (with Category Description)

Number Requirements Components by TA&P Number...... __ __ __ __ __ __ __ _ -_System B-G- I .B6,0 Closure Head Nuts (Reactor Vessel) Visual, VT-I RPV: 76 Pressure Retaining B[6.20 Closure Studs, in place (Reactor Vessel) Volumetric RPV: 76 Bolting, Greater Than B6.40 Threads in Flange,(Reactor Vessel) Volumetric RPV: 76 .,_.., 2 in. In Diameter 1B,.50( Closurc Washcrs, Bushings (Reactor Vessel) Visual, VT-I RPV: 76 ........[36,180 Bolts and Studs (Pumps) Volumetric RR: 32[36.190 Flange Surface, when connection disassembled (Pumps) Visual, VT- I RR: 2 136.200 Nuts, Bushings, and Washers (Pumps) Visual, VT-I RR: 32 B-G-2 B7.10 Bolts, Studs, and Nuts (Reactor Vessel) Visual, VT-I RPV: 4 Pressure Retaining B7.50 Bolts, Studs, and Nuts (Piping) Visual, VT-I MS: 18 Bolting, 2 in. and Less RWCU: I In Diameter B[7.70 Bolts, Studs, and Nuts (Valves) Visual, VT-i CS: 4 FW: 4 MS: 22 RHR: 12 RR: 4 1B7"X0 Bolts, Studs, & Nuts in CRD Housing (Reactor Vessel) -Visual, VT-I RPV: 185 11 A lion Sci*~we & Teclrnnlogv LIAIO2. G03 Alion&.ý,-qýe

& 'rechniklogj,....7-5 vLIMo2. G03"""Revision 0

ISI Program Plan Lirnericl Generating Station Units I & 2. Third Interval LGS UNIT 1 & COMMON INSERViCE INSPECTION

SUMMARY

TABLE 7.1-1 Examination Category Item Description Exam Total Number of Relief Request/ Notes (with Category Description)

Number Requirements Components by TA&P Number__,__System

..B-K 11.0.10 Welded Attachments (Pressure Vessels) Surface or RPV: 10 Welded Attachmients fbr Volumetric Vesscls. Piping. Pumps, B310.20 Welded Attachments (Piping) Surface MS: 4 and Valvcs RHR: I RR: 4 B 10.30 Welded Attachments (Pumps) Surface RR: 8 B-L-2 B1 2.20 Pump Casings (Pumps) Visual, VT-3 RR: 2 PumpeCasinos________________________________

________B-M-2 B 12.50 Valve Bodies (Exceeding NPS 4)'(Valves)

Visual, VT-3 CS: 6 Valve Bodies FW: 6 HPCI: 2 MS: 22 RHR: 21 RR: 4 RWCU: 5 Alion S'cience & Technologyr 7-6 LIMO2.G03 Revision 0 ISI Program Plan Limerick Generating Station Units I &, 2, Third tnterval LGS UNIT I & COMMON INSERVICE INSPECTION

SUMMARY

TABLE 7.1-1 I 1- i aioI-I tcaeg;ory Item Description Exam. To'tal Nu'mber of Relief Request/ *Notes (with Category D)escription)

Number Requirements Components by TA&P Number___System o B-N- I B 13. 10 Vessel Interior (Reactor Vessel) Visual, VT-3 RPV: I 13R-03 Interior of Reactor V essel I ... .....,.,...___........

._ ........B-N-2 B13.20 Interior Attachments Within Beltline Region (Reactor Visual, VT-I RPV: 6 13R-03 Vessel)Welded Core Support Structures and Interior B 13,30 Interior Attachments Beyond Beltline Region (Reactor Visual, VT-3 RPV: I I 13R-03 A ttachm ents to V essel) ... ... ._.. .." 1 ... ._....___......__...

.. ..... .....Reactor Vcssefs R 13.40 Core Sup1port Structure (Reactor Vessel) Visual, VT-3 RPV: 842 13R-03 13-0 B 14.10 Welds in CRD Housing (Reactor Vessel) Volumetric or RPV: 80 12 Pressure Rclaining Welds in (10% of Peripheral CR1D Housings)

Surface.Control Rod 1-ot sinus .... ........A4lion SciMei & Technaologj

...7-7 LIMO2.G03 Revision 0

.IN Programl.

p/an Limerick Generatin~g Station Units I & 2, Third Interval LGS UNIT 1 & COMMON INSERViCE INSPECTION

SUMMARY

TABLE 7.1-1 Examination Category Item Description Exam Total Number of Relief Request/ Notes (with Category Description)

Number Requirements Components by TA&P Number__-_.........

Sy stem B-P B 15.10 System Leakage Test (IWB-5220)

Visual, VT-2 CS 13R-08 All Pressure FW !3T-02 Retaining Components HPCI 13T-07 MS RCIC RHR RPV RPV-APP RR RWCU SLC Alian Sciece.t'&

Teclhnology 7-8 LI.M02.G03 Revision 0 ISi Program Plan imnerick Generating Station Units I A 2, Third Interval LGS UNIT I & COMMON INSERVICE INSPECTION

SUMMARY

TABLE 7.1-1 Exalmiuation Category Item Description Exam Total Number of Relief Request/ Notes (with Category Description)

Number Requirements Components by TA&P Number System Pr... ure i ..C-A C1.10 Shell Circumferential Welds (Pressure Vessels) Volumetric RHR: 6 13R-06 Pressure Retaining Welds iP1ressure Vessels C1.20 Head Circumferential Welds (Pressure Vessels) Volumetric Ri-IR: 2 C-3. (.2.21 Nozzle-to-Shell (Nozzle to Head or Nozzle to Nozzle) Volumetric

& RHR: 4 Pressure Rctaining Welds Without Reinforcing Plate, Greater Than 1/2" Surface Nozzle Welds in Vessels Nominal Thickness (Pressure Vessels)C2.22 Nozzle Inside Radius Section Without Reinforcing Plate, Volumetric RHR: 4 Greater Than 1/2" Nominal Thickness (Pressure Vessels)C-C C3.10 Welded Attachments (Pressure Vessels) Surface RHR: 16 Welded Attachments C3.20 Welded Attachments (Piping) Surface CRD: 6 f!,tr Vessels, Piping, CS: 17 Pumps, and Valve HPCI: 18 MS: 6 RCIC: 9 RHR: 72.....__ ., __ C3.30 Welded Attachnments (Pumps) Surface RClC: 4 C-C C6.10 Pump Casing Welds (Pumps) Surface CS: 28 1.3R-07 Pressure Retaining Welds in RCIC: 2 Punmps fand Valves R.HR: 28 Alien .Seci"vce

& Technsology~~

.7-9 LIMO2.G03 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval LGS UNIT 1 & COMMON INSERVICE INSPECTION

SUMMARY

TABLE 7.1-1 p p p Examination Category (with Category Description)

Description Exam Requirements Total Number of Components by System Relief Request/TA&P Number Notes I t C-Il All Pressure Retaining Components System Leakage Test (IWC-5220)

Visual, VT-2 CAC CRD CS DWCW FW HPCI INST LRW MS PASS PCIG RADMON RADW RCIC RECW RHR RWCU SDV SLC 13R-1 I 13R- 12 13T-O1 13T-02 i = I AiIon Science & TechiptyloLg' 7-10 LIMO2.G03 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval LGS UNIT I & COMMON INSERVICE INSPECTION

SUMMARY

TABLE 7.1-1 Fxamination Calego ry Item Description Exam Total Number of Relief Request/ Notes (with Category Description)

Number Requirements Components by TA&P Number............

....______________

Svstem D-A D13,20 Welded Attachments (Piping) Visual, VT- I ESW: 75 + 2 Welded Attachments 1"or MS: 47 Vessels. Piping, Pumps, RHRSW: 35 and Valves D-B D2.10 System Leakage Test (IWD-5221)

Visual, VT-2 CSCW 13R-09 All Prssure. DIESEL 13R-10 Retaining Components ESW 13T-01 FPC 13T-02 FPCC FP-DEMN LRW MS PCIG R14R RHRSW RPV RWCU Aljour Sciecte & Technology

_ZII LIMO2.G03 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval l.,XS UNIT i & COMMON INSERViCE INSPECTION

SUMMARY

TABLE 7.1-1 Examination Category Item Description Exam Total Number of Relief Request/ Notes (Will Category Description)

Number Requirements Components TA&P Number E-A. E1. I Containment Vessel Pressure Retaining Boundary -General Visual 9 13R-O1 7 Containment Surfaces Accessible Surface Areas 13T-03 EI.I I Containment Vessel Pressure Retaining Boundary -Visual, VT-3 14 13R-01 7 Bolted Connections, Surfaces 13T-03 EI.12 Containment Vessel Pressure Retaining Boundary -Visual, VT-3 2 13R-01 8 Wetted Surfaces of Submerged Areas ...._13T-03 El .20 Containment Vessel Pressure Retaining Boundary -Visual, VT-3 0 13R-01 8 BWR Vent System 13T-03 Accessible Surface Areas E-C F-4.1 I Containment Surface Areas -Visible Surfaces Visual, VT-1 0 13R-01 9 Containment Surfaces Requiring E4.12 Containment Surface Areas -Surface Area Grid Volumetric 0 13 R-0 1 10 Augmented Examination Grid Line Intersections and Minimum (Thickness)

Wall Thickness Locations A lion Science & Technology 7-12 LJA.f02. G03 Alion SVcience & Technology, LIMO2. G03 Revision 0-------------

-

ISI Program Plan Limerick Generating Station U/nils 1 -& 2, Third Interval LGS UNIT 1 & COMMON INSERVICE INSPECTION

SUMMARY

TABLE 7.1-1 Examination Category Item Description Exam Total Number of Relief Request/ Notes (with Category Description)

Number Requirements Components by TA&P Number Systemn F-A Fl.10( Class I Piping Supports Visual, VT-3 CS: 14 13R-05 I Supports FW: 36 13T-04 HPCI: 10 13T-06 MS: 31 RCIC: 15 RHR: 84 RR; 54 RWCU: 80 SLC: 40 F 1.20 Class 2 Piping Supports Visual, VT-3 CRD: 35 13R-05 1 CS: 108 13T-04 FW: 3 13T-06 HPCI: 95 MS: 78 RCIC: 69 RIR: 393 F1.30 Class 3 Piping Supports Visual, VT-3 ESW: 386 + 13R-05 I MS: 185 13T-04 2 RHRSW: 438 13T-06 F 1.40 Supports Other Than Piping Supports Visual, VT-3 CS: 4 B3R-05 (Class 1, 2, and 3) F/PCI: I 13T-04 RCIC: 4 13T-06'RHR: 20 RPV: 9 RR: 20 Alient Scienvce & Tecnlg...... 7-13-. LIMO2.G03 Revision 0 ISI Progrant Plan Limterick Generating Station Units I & 2, Third Interval LGS UNIT I & COMMON INSERVICE INSPECTION

SUMMARY

TABLE 7.1-1.Examination Category Item Description Exam Total Number of Relief Request/ Notes (wilh Categor. , I)escription)

.Numbe.r Requirements Components TA&P Number L-A i.. I.11 Concretc Surfaces -All Accessible Surface Areas General Visual 3 13R-01 L .Concrelc 1- 1. 12 Concrete Surfaces -Suspect Areas Detailed Visual 0 13R-01 Alion Science & Techno~ogyw 7-14 LIM02.GO3 Revision 0 IS! Program Plan Limerick Generating Station Units I & 2, Third Interval LGS UNIT i & COMMON INSERVICE INSPECTION

SUMMARY

TABLE 7.1-1 Examination Category Risk Description Exam Total Number of Relief Request/ Notes (with Category Description)

Category Requirements Components by TA&P Number Number ..............

System R-A I Risk Category I Elements See Notes FW: 72 13R-02 3 Risk-Informed Piping 4 Examinations 5 6 2 Risk Category 2 Elements See Notes CS: 14 .3R-02 3 RHR: 63 4 RR: 12 5 RWCU: 2 6 SLC: 4 3 Risk Category 3 Elements See Notes FW: 17 13R-02 3 1tPCI: 27 4 RCIC: 28 5 6 4 Risk Category 4 Elements See Notes CS: 20 I3R-02 3 HPCI: 40 4 MS: 237 5 RCIC: 25 6 RHR: 126 RPV-APP: 38 RR: 95 RWCU: 94 SLC: 6 5 Risk Category 5 Elements See Notes FW: 7 13R-02 3 HPCI: 4 4 RCIC: 9 5 RHR: 44 6 A lion .Science & TechnlogyL' 7-15 LIM02.G03 Revision 0 Ist Program Plan Limecrick Generating Station Un &,v I & 2. Third Interval LGS UNIT I & COMMON INSERVICE INSPECTION

SUMMARY

TABLE 7.1-1 Examination Category Aug Descriptio..

Exam Total Number of Relief Request/ Notes (with Category Description)

Number .. .._. Requirements Components TA&P Number NA AUG-01 ilntergranular Stress Corrosion Cracking (1GSCC) in BWR Volumetric Category C: 23 4 Augmented Austenitic Stainless Steel Piping Components and Category D: 1 Componcnts BWRVIP-75 "Vessel, and Internals Project Technical Basis Category E: I for Revisions to Generic Iectter 88-01 Inspection Schedules" AUG-02 BWROG. BWR Feedwater Nozzle and Control Rod Drive Volumetric FW: 12 Return Line Nozzle Cracking Components RPV: 18 AUG-05 USNRC Mechanical Engineering Branch (MEB) Technical Volumetric or NA 6 Position MEB 3-1, NLJREG-000, No Break Boundaries Surface AUG-07 SIL No. 455, Recommendation for Additional ISI of Alloy Volumetric CS: 2 182 Nozzle Weldmcnts. (Note: This augmented inspection RR: 4 program is in conjunction with the AUG-01 program.)

RPV-APP: 3 RR: 12 AUG-09 Examination of the RPV Closure Head Lifting Lugs Surface RPV: 4 AUG-10 UFSAR Table 3.2-I, Non-Q Reactor Pressure Vessel Volumetric or RPV: 17 Internal Components Visual, VT-3 AUG-13 Technical Specification 3/4.7.4, Snubber Examination and Visual, VT-3 AUX STM: I 13R-05 I Testing Program C & RWS: 5 CAC: 26 CE-HVAC: 1 CONDSTE: 5 CS: 61 EDG: 8 ESW:16 FPC: I FPCC: 27 FP-DEMN: 3 FW: 26 HPCI: 51 LRW: 6 MS: 147 PCIG: 2 RCIC: 37 Alion Science & Technologv 7-16 LIM02. G03 Revision 0 IS! Programt Plan Limerick Generating Station Units I & 2, Third Interval LGS UNIT 1 & COMMON INSERVICE INSPECTION

SUMMARY

TABLE 7.1-1 Examination Category Aug Description Exam Total Number of Relief Request/ Notes (with Catego!r Description)

Number _ Requirements Components TA&P Number NA AUG-13 Technieal Specification 3/4.7A4, Snubber Examination and Functional Tests RECW: 12 13R-05 I Augmented Testing Program & Visual, VT-3 R.HR: 358 Components RHRSW: 25 (Continued)

RPV-APP: 24 RR: 123 RWCU: 116 SLC: 6 SW: 13 AUG-14 Balance of Plant Snubber Examination Program Visual, VT-3 AIR: 6 13R-05 I AUX STM: I CAC: 1 DW-CW. I ESW: 10 FPCC: 6 FW: I HEATING: 3 HPCI: 3 LRW: I MS: 97 PCIG: 5 PCLT: 2 RCIC: 2 RECW: 10 RWCU: 22 SW: 21 AUG-19 Weld Centerline Marking NA NA AUG-22 USNRC IEB Nos, 95-02 and 96-03, RHR and CS Suction Visual, VT-3 CS: 5 Strainers RHR: 9 AUG-30 BWRVIP-05, BWR Reactor Pressure Vessel Shell Welds Volumetric RPV: 18'I/on ci~~ce& ecluiologt'

._7-17 LIMOZ GO3 Revision 0 15.1 Program, Plan Limerick Generating Station Units I & 2, Third Interval LGS UNIT 2 INSERVICE INSPECTION

SUMMARY

TABLE 7-1-2 P".'11minalionn Categorv Item Description Exam Total Number of Relief Request/ Notes (with Category Description)

Number Requirements Components by TA&P Number System B-A 131.11 Circumferential Shell Welds (Reactor.

Vessel) Volumetric RpV: 5 13R-04 ____Pressure Retaining 131.12 Longitudinal Shell Welds (Reactor Vessel) Volumetric RPV: 13 13 R-04 Welds in Reactor Vessel B 1.21 Circumferential Head Welds (Reactor Vessel) Volumetric RPV: 2 , B1.22 Meridional Head Welds (Reactor Vessel) Volumetric RPV: 14 B1.30 Shell-to-Flange Weld (Reactor:

Vessel) Volumetric RPV: 1 ' '131.40 Head-to.Flange Weld (Reactor Vessel) Volumetric

& RPV: I Surface B-D B3.90 Nozzle-to-Vessel Welds (Reactor Vessel) Volumetric RPV: 34 Futl Penetration Welds of Nozzles in Vessels 83.100 Nozzle Inside Radius Section (Reactor Vessel) Volumetric RPV: 34 ,'jlion Science & Teclh,,ohn,'v 7-18 LIMO2.G03 Revision 0 ISI Program Plan Linterick Generating Salion Units I & 2, Third Interval LGS UNIT 2 INSERVICE INSPECTION

SUMMARY

TABLE 7-1-2 Examination Category Item Description Exam Total Number of Relief Request/ Notes (with Category Description)

Number Requirements Components by TA&P Number System B-G-lI 6.. 10 Closure I-lead Nuts (Reactor Vessel) Visual, VT-I RPV: 76 Pressure Retaining 1B6.20 Closure Studs, in place (Reactor Vessel) Volumetric RPV: 76 ..............

Bolting. Grcater Than 1.6.40 Threads in Flange (Reactor Vessel) Volumetric RPV: 76 2 in. in Diameter 136.50 Closure Washers, Bushings (Reactor Vessel) Visual, VT-I RPV: 76 136.180 Bolts & Studs (Pumps) Volumetric RR: 32 B16.190 Flange Surface. when connection disassembled (Pumps) Visual, VT-I RR:"2 .............. , .....136.200 Nuts. Bushings.

and Washers (Pumps) Visual, VT- I RR: 32 -B-6-2 137.10 Bolts, Studs, and Nuts (Reactor Vessel) visual, VT-1 RPV: 3 Pressure Retaining RPV-APP: 1 Bolting. 2 in. and Less B7.50 Bolts, Studs, and Nuts (Piping) Visual, VT-I HPCI: I In Diameter MS: 17 RWCU: 2 1B7.70 Bolts, Studs, and Nuts (Valves) Visual, VT-I CS: 4 FW: 4 MS: 22 RHR: 12 RR: 4 B7.80 Bolts, Studs, & Nuts in CR)I Housing (Reactor Vessel) Visual, VT-I RPV: 185 11 Alto,, Seitit#e & Tecluiologt,y

.--,:7-19.LIMO2.G03 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third lntenval LGS UNIT 2 INSERVICE INSPECTION

SUMMARY

TABLE 7-1-2 IExamination Category .Item Description Exam Total Number of Relief Request/ Notes (with Category Description)

Number Requirements Components by TA&P Number xSystem B-K B1"0.10 Welded Attachments (Pressure Vessels) Surface or RPV: 10 Welded Attachmrents for Volumetric Vessels. Piping. Pumps. 1310.20 Welded Attachments(Piping)

Surface MS: 16 and Valves RHR: 4 RR: 16 110.30 Weled A16acim3ens (Pumps) Surface RR: 8..B--2 B112.20 Pump Casings (Pumps) Visual, VT-3 RR: 2... Casings ...... .B-M-2 B12.50 Valve Bodies, (Exceeding NPS 4) (Valves) Visual., VT-3 CS: 6 Valve Bodies FW: 6 HPCI: 2 MS: 22 RHR: 21 RR: 4 RWCU: 5 A lion S~ie,,ce & lechnology 7-20 Alion Science & 7echnology 7-20 LIM02.GO3 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval LGS UNIT 2 INSERVICE INSPECTION

SUMMARY

TABLE 7-1-2 Examination Category Item Description Exam Total Number of Relief Requestl Notes (with Category Description)

Number Requirements Components by TA&P Number System 11-N- Vessel Interior (Reactor Vessel) Visual, VT-3 RPV: I 13R-03 h ~l e s -o f ' R cac it or V e s s e l V: B-N-2 B 13.20 Interior Attachments Within Beltline Region (Reactor Visual, VT-i RPV: 6 13R-03 Vessel)Welded Core Support Structures and Interior B 13.30 Interior Attachments Beyond Beltlinie Region (Reactor Visual, VT-3 RPV: I1 13R-03 Attachments to Vessel)Reactor Vessels 813.40 Core Support Structure (Reactor Vessel) Visual, VT-3 RPV: 838 13R-03 B-0 B 14.10 Welds in CRD Housing (Reactor Vessel) Volumetric or RPV: 80 12 Prcssure Retaining Welds in (10% of Peripheral CRD Housings)

Surface Control Rod H-outisings A lion Sc,,qce & iechnoiqgv

.... 7-21I LIMO2.G03 Revision 0 IS! Program Plan Limerick Generating Station Units I & 2, Third lnterval LGS UNIT 2 INSERVICE INSPECTION

SUMMARY

TABLE 7-1-2 Examinatiorn Category Item Description Exam Total Number of Relief Request/ Notes (with Category Description)

Number Requirements Components by TA&P Number System B-1'. B315.10 System Leakage Test (IWB-5220)

Visual, VT-2 CS 13 R-08 All Pressure FW 13T-02 Retaining Components HPCI 13T-07 MS RCIC RHR RPV RPV-APP RR RWCU SLC llliontiji.SInce

& Teclsnalogv 7-22 LIMO2.G03 Revision 0 IS] Program Plan Limerick Generting Station Un its I & 2, Third Interval LCS UNIT 2 INSERVICE INSPECTION

SUMMARY

TABLE 7--2 Examination Category Item Description Exam Total Number of Relief Request/ Notes (with Category Description)

Number Requirements Components by TA&P Number_ _ _ _ _ _ _ _ _ _System _C-A Ci.10 Shell Circumferential Welds (Pressure Vessels) Volumetric RHR: 6 [3R-06 Pressure Retaining Welds I in [Iressurc Vessels C 1.20 1lead Circumircrntial Welds (Pressure Vessels) Volumetric RI-IR: 2 C-13 C2.21 Nozzle-to-Shell (Nozzle to Head or Nozzle to Nozzle) Volumetric

& RIHR: 4 Pressure RetaininL Nozzle Welds Without Reinforcing Plate. Greater Than 112" Surface Nominal Thickness (Pressure Vessels)Wclds in Vessels C2.2'2 Nozzle Inside Radius Section Without Reinforcing Plate., Volumetric RHR: 4 Greater Than 1/2" Nominal Thickness (Pressure Vessels) _C-C C3.10 Welded Attachments (Pressure Vessels) Surface RHR: 16 Welded Attachments C3.20 Welded Attachments (Piping) Surface CRD: 28 f0r Vessels, Piping, CS: 45 Pumps, and Valves HPCI: 71 MS: 41 RCIC: 63 RHR: 209 C3.30 Welded Attachmcnts (Pu.mps) Surface RCIC: 4 C-. C6. 10 Pump Casing Welds (Pumps) Surface CS: 36 13R-07 Pressure Retaining Welds RCIC: 2 In Pumps and Valves RHR: 44 A lion Science & Tccl;,iologj' 7-23 Alion ý5cicnce & Technologj?

J-23 LIM02. GO3 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval LGS UNIT 2 INSERVICE INSPECTION

SUMMARY

TABLE 7-1-2 Examination Category Item Description Exam Total Number of Relief Request/ Notes (with Category Description)

Number Requirements Components by TA&P Number___________________________.....____System

-, C-H C7.10 System Leakage Test (iWC-5220)

Visual, VT-2 CAC 13R-1 I All Pressure CONDSTE 13R-12 R claining Components CRD 13T-01 CS 13T-02 DWCW FW HPCI INST MS PASS PCIG RADMON RADW RCIC RECW RHR RWCU SDV SLC Alim, Sciciace & Techniology-7-24 LIMO2.GO0 Revision 0 IS) Program Plan Limerick Generating Station Units I & 2, Third Interval LGS UNIT 2 INSERVICE INSPECTION

SUMMARY

TABLE 7-1-2 FExamination Category Item Description Exam Total Number of Relief Request/ Notes (with Category Description)

Number Requirements Components by TA&P Number 1D-A D i.20 Welded Attachments (Piping) Visual, VT- I ESW: 88 Welded Attachments for Vcssels MS: 175 Piping, Pumps and Valves ... .. .... .........__..RHRSW

9 1* -B D2.10 System Leakage Test (IWD-5221)

Visual, VT-2 CAC 13R-09 All Pressure CONDSTE 13R-10 Retaining Components DIESEL 13T-01 ESW 13T-02 FPC FPCC LRW MS PCIG RCIC RHRSW RPV RWCU A lon cj~gc &Techrnology

-_7.25 LIM#2.G#03 Revision 0 187 Program Plan Limerick Generating Stalion Units I & 2, Third Interval LGS UNIT 2 INSERVICE INSPECTION

SUMMARY

TABLE 7-1-2 Ex:amination Category f Item Description Exam Total Number of Relief Request/ Notes (with Cafelrg'rv Description)

Number Requirements CoMnents TA&P Number E-A F1..11 Containment Vessel Pressure Retaining Boundary -General Visual 9 13R-01 7 Containment Suirfaces Accessible Surface Areas 13T-03 E.I I Containment Vessel Pressure Retaining Boundary -Visual, VT-3 14 13R-01 7 Accessible Surface Areas Including Bolted Connections 13T-03 El, I 12 Containment Vessl Pressure Retaining Boundary -Visual, VT-3 2 13R-01 8 Wetted Surfaces of Submerged Areas 13T-03.El .20 Containment Vessel Pressure Retaining Boundary -Visual, VT-3 0 13R-01 8 BWR Vent System 13T-03 Accessible Surface Areas E-C E4.11 Containment Surface Areas -Visible Surfaces Visual, VT-i -0 13R-01 9 Containment Surfaces Requiring E4.12 Containment Surface Areas -Surface Area Grid Volumetric 0 13R-01 10 Augmentcd Examination Grid Line Intersections and Minimum (Thickness)

Wall Thickness locations..Ill,, Science & Technldogy

" 7-26 LIMO2.G03 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Interval LGS UNIT 2 INSERVICE INSPECTION

SUMMARY

TABLE 7-1-2 Examination Category Item Description Exam Total Number of Relief Requestl Notes (with Category Description)

Number Requirements Components by TA&P Number-.... System F-A FI.10 Class I Piping Supports Visual, VT-3 CS: 14 13R-05 Supports FW: 36 13T-04 HPCI: 10 13T-06 MS: 31 RCIC: 15 RHR: 64 RR: 34 RWCU: 63 SBLCC: 40 F1.20 Class 2 Piping Supports Visual, VT-3 CRD: 31 13R-05 CS: 108 13T-04 FW: 3 13T-06 HPCI: 88 MS: 82 RCIC: 80 RHR: 379 Fl1.30 Class 3 Piping Supports Visual, VT-3 ESW: 116 13R-05 I MS: 187 13T-04 RHRSW: 50 13T-06 Fl .40 Supports Other Than Piping Supports Visual, VT-3 CS: 4 13R-05 (Class I, 2, and 3) HPCI: 7 13T-04 RCIC: 4 13T-06 RHR: 52 RPV: 9 RR: 18 Alion Science & lechimpiogr

.... -27 LIMO2.G03 Revision 0 ISI Program Plan Limerick Generating Station Units I & 2, Third Infen'aI LGS UNIT 2 INSERVICE INSPECTION

SUMMARY

TABLE 7-1-2 Examination Category I teln Description Exam Total Number of Relief Request/ Notes with ategoa Deseriefioný Number Requirements Comeonents TA&P Number L-A 1-1.11 Concrete Surfaces-All Accessible Surface Areas General Visual 3 13 R-0 I Concrete I., I ý 12 Concrete Surfaces -Susgect Areas Deta 1.1led Visual 13 R-0 I Alion Science & Technology 7-28 LIMO2. G03 Revision 0 15I Program Plan Limerick Generating Station Units I & 2, Third Interval LGS UNIT 2 INSERVICE INSPECTION

SUMMARY

TABLE 7-1-2 Examnination Category Risk Description Exam Total Number of Relief Request/ Notes (-with Category Description)

Category Requirements Components by TA&P Number Number SIystem =R-A I Risk Category I Elements See Notes FW: 67 13R-02 3 Risk- Piping 4 Examinations 5 6 2 Risk Category 2 Elements See Notes CS: 17 13R-02 3 R.HR: 59 4 RR: 9 5 RWCU: 2 6 SLC: 4 3 Risk Category 3 Elements See Notes FW: 19 13R-02 3 HPCI: 28 4 RCIC: 26 5 4 Risk Category 4 Elements See Notes CS: 19 13R-02 3 HPCI: 40 4 MS: 235 5 RCIC: 30 6 RHR: 123 RPV-APP: 41 RR: 97 RWCU: 15 SLC: 5 5 Risk Category 5 Elements See Notes FW: 5 13R-02 3 HPCI: 5 4 RCIC: 9 5 RHR: 49 6 Alion Science & Technologv 7.-29 LIM02. GO3 Revision 0 ISI Program Plan.Limerick Generating Station Units I & 2, Third Interval LGS UNIT 2 INSERViCE INSPECTION

SUMMARY

TABLE 7-1-2....E inaion Category Aug Description Exam Total Number of Relief Requestf Notes (with Category Description)

Number Requirements Components TA&P Number NA AUG-0 I Intergranular Stress Corrosion CrackingI (IGSCC) in BWR Volumetric Category B: 18 4 Augmented Austenitic Stainless Steel Piping Components and Component BWRVIP-75 "Vessel and Internals Project Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules" _AUG-02 BWROG, BWR Feedwater Nozzle and Control Rod Drive Volumetric FW: 12 Return Line Nozzle Cracking Components

_ _ __RPV: 18 AUG-05 USNRC Mechanical Engineering Branch (MEB) Technical Volumetric or NA 6 Position MEB 3-I, NUREG-0800, No Break Boundaries Surface AUG-07 SIt. No. 455, Recommendation for Additional IS] of Alloy Volumetric CS: 2 182 Nozzle Weldments. (Note: This augmented inspection RR: 4 program is in conliunction with the AUG-01 program.)

RPV-APP: 3 RR: 12 AUG-09 Examination of the RPV Closure Head Lifting Lugs Surface RPV: 4 AUG-10 .JFSAR Table 3.2-1, Non-Q Reactor Pressure Vessel Volumetric or RPV: 17 Internal Components Visual, VT-3 AUG-13 Technical Specification 3/4.7.4, Snubber Examination and Functional Tests AUX STM: 3 13R-05 Tresting Program & Visual, VT-3 C & RWS: 3 CAC: 13 CONDSTE: 5.CS: 28 EDG: 4 ESW: 3 FPC: 27 FPCC: 2 FW: 21 HPCI: 30 LRW: I MS: 166 RCIC: 28 RHIR: 157 RHRSW: 15 RPV-APP: 29 Alion Science& 7echnhlogk 7-30 LIMO2.G03 Revision 0 RIS Program Plan Limerick (;cneraling Station Ujnit, 5 & 2, Third Interval LGS UNIT 2 INSERVICE INSPECTION

SUMMARY

TABLE 7-1-2 Exa'mination Category Aug Description Exam Total Number of Relief Request/ Notes (with Cafegory Description)

Number Requirements Components TA&P Number NA AIJG- 13 Technical Specification 3/4.7.4, Snubber Examination and Visual, VT-3 RR: 70 13R-05 I Augmented Testing Program RWCU: 46 Cornponents SW: 5 (Continued)

AUG-14 Balance of Plant Snubber Examination Program Visual, VT-3 ETS: 13 O3R-05 EXTRSTM: 8 FAS: 8 FCD: 7 FDV: 6 MOS: 8 MS: 18 RETS: I I AUG-19 Weld Centerline Marking NA NA AUG-22 USNRC I EB Nos. 95-02 and 96-03, RHR and CS Suction Visual., VT-3 CS: 5 Strainers

-,,,RKHR:

9 AUG-3{0 BWRVIP-05, BWR Reactor Pressure Vessel Shell Welds Volumetric RPV: 1.8 Alion Science & Technology

.... 7-31... LIM2. G03 Revision 0

/S) I , 1Ugrar PI(In I,imeri' (; Gccrtnermg Sotaion I Inhir I & 2, Third hIterv.al INSPECTION

SUMMARY

TABLE PROGRAM NOTES TABLE 7.1-3 N ____e # Note Summary k Il Snubhhr visual examinations and functional testing are performed in accordance with Relief Request 13R-05 and the LGS TS snubber program. The nmbher of I.iS I mit I, 2. and Common supports identified, include snubbers for the visual examination and functional testing of the snubber per Relief Rcquies 13R--05. and include the intcgral and nonintegral attachments per Paragraphs IWF-5200(c), IWF-5300(c), and IWF-2500(a).

Fora detailed discussion of the snubher program, see ýcclion 4.2.2 lihe Unit I 1population contis inchodc those e omponents that arc common to both units (typically designated as "Common" or "Unit 0"). These Common......cnt.. arc rsf:rcnccd in Tablc 7. 1-1I following a "-_symbol to designate the Common Unit 0.3 FIo the Third InspCclion Interval I ,(S's Class I and 2 piping inspection program will be governed by risk-informed regulations.

The RISI Program methodology is dscrihecd i the [PR I Topical Reporils TR- I 12657, Rev. B-A, TR-1006937.

Rev. 0-A, and Code Case N-578-1. The RISI Program scope has been implemented as aIn alternative In the 2001I -dition through the 2003 Addenda of the ASME Section XI examination program for Class I B-F and B-A welds and Class 2 C-F-I and U-F-2 welds in accordance with I0( CFR50.S5a(aX3)(i).

4 Pir the HPRI Topical Reports TR- 112657, Rev. B-A, TR-1006937, Rev. O-A, and Code Case N-578-1, welds within the plant that are assigned to IGSCC C s B through G will continue to mcet exisling IGSCC schedules, while tGSCC Category A welds have been subsumed into the RISI Program.5 Vx ,imnination requirements within the RISI Program are determined by the various degradation mechanisms present at each individual piping structural element. See_. ToI_._picil 12657, Rev. R-A, TR-1006937, Rev. O-A, and Code Case N-578-I for specific exam method requirements.

6 Flor th Third Inspection Interval.

the RISI program scope has been expanded to include welds in the BER piping, also referred to as the HELB region, which inchdcs ,¢sverat non-clas.

welds that fall within the BER augmented inspection program. All BER augmented welds have been evaluated under the RISI icthmclohwy and have been integrated into the RISI Program under the I OCRSO.59 change process. Additional guidance for adaptation ofthe RISI evalation prtcc.Ne to BI.R piping is givcn in F[PRI TR-1006937 Rev. O-A. Thus. these welds have been categorized and selected for examination in accordance With the [.PRI ro0ical Report TR- 112657, Rev. B-A. TR-1006937, Rev, 0-A. and Code Case N-578-1 in lieu of the original commitment to NI jRlG 0(90( in I WFSAR Section 3,6.7 connections examined per Item E-. I.11require a VT-3 exam once per interval and each time the connection is disassembled during a scheduled El .II exam. Additionally.

a V'r- I exam shall be performed if degradation or flaws are identified during the VT-3 exam. These modifications are required by 1..... IOCt(55a(b)(2)(ix)(()

andi IOCFR50.55a(h)(2)(ix)(H).

9 Items 1,.)2 and F.1.20 require VT-3 visual examination in lieu of General Visual examination, as modified by IOCFR50.55a(b)(2)(ix)(G).

... Ite. .[e4_.1ruirs VT-i visual examination in lieu of Detailed Visual examination, as modified by I OCFR50.55a(b)(2)(ix)(G).

MIt The ultrasonic examination acceptance standard specified in [WE-3511.3 for Class MC pressure-retaining components must also be applied to metallic liners of( lass (C( pressure-retaining components.

as modified by 10CFR50.55a(b)(2)(ix)(l).

..........

..-elr-I0 R5.5 )(2)(xxil(t.

Tahle IWB-2500-1 aranmination requirements, the provisions of Table IWB-2500-1, Examination Category B-G-2, Item 17.8t.ý that are In the l9)5 Edition are applicable only to reused bolting when using the 1997 Addenda through the latest edition and addenda incorporated byl recre. in Iarj.ýraj~h

2) tljis ion 12 1 ..aminatI.ion Category i ning Welds In Control Rod Housings), Item Number B 14. 10 (Welds i n CRD Housing) -the scope of examination isllor pressure retaining welds in 10% o' the peripheral CR1D Housings, These80 components represent the two welds (lower and upper housing welds) on each of the 40 peripheral CRD Housings to be examined during the interval (10% of 80). Note that welds in the peripheral CRD Housings are exempted from examinhation per IWB-1220(a).

See Calculation I.,M-0546, CRD Housiný Weld Exclusion Evaluation for calculation/justification for more details./Ilion Science & Techiohigy 7-32 LIM02.G03 Revision 0

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