ML20095G079

Addendum 1 to Rev 2 to ISI Program Second Ten Yr Interval Units 2 & 3 for Peach Bottom Atomic Power Station

ML20095G079
Person / Time
Site:	Peach Bottom
Issue date:	09/22/1995
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
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ML20095G078	List: ML20095G075 ML20095G079
References
PROC-950922, NUDOCS 9512200010
Download: ML20095G079 (193)

Text

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1 INSERVICE INSPECTION PROGRAM SECOND TEN YEAR INTERVAL

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UNITS 2 & 3' FOR PEACH BOTTOM ATOMIC POWER STATION Prepared by The NED Technical Services Branch eA 9/22/95 Addendum 1 to g h fA [

2 12/29/94 Complete rev. rec rhz kah mjb Incorporates for ECR 94-10073, vmn ECR 94-10237, i ECR 94-11412, ECR 94-10790, ECR 94-07476, NCR 94-00374,

& Addendum 1.

8/30/94 Addendum 1 to nas rh: vmn wtb {

Rev. 1 1 3/14/94 ISSUED FOR USE nas rec vmn mjb O R A A A A A R E P P P P P I V P P P P P .

G I R R R R R {

I E O O O O O N W V V V V V A E A A A A A T R L L L L L 0

R REV NO. DATE REASON FOR LEAD NON-LEAD ISSUE PBAPS UNITS 2 & 3 NO. M-733 ISI PROGRAM A AT PEACH BOTTOM ATOMIC REV NO. 2 Addendum 1 y POWER STATION PECO ENERGY ' Pase 1 of 51 9512200010 951215 PDR ADOCK 05000277 Q PDR ,

Specification M 733, Rev.2 Addendum 1

PBAPS 2 & 3 ISI Program Page 1-il of 51 Summary of Addendum 1 to Revision 2 The primary purpose of this addendum is to update the Augmented inspection Programs applicable to Reactor Pressure Vessel Intemals to reflect the latest VIP based planning. In addition, other changes were incorporated as a function of the transition of programmatic responsibility from Nuclear Engineering to the Station.

The following documents contributed to this revision:

A0915259 A0931782 A0916146 A0947305 Specific changes within this revision include:

j 1. Updated Table 2.51, to reflect latest Code Case revisions and status.

2. Updated Section 8.3.4 to reflect approval for use of Code Case N-498-1.

3. Updated Appendix A Table of Contents to reflect relief request activity since the last revision of this docurnent.

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4. Addition of Relief Request RR 14, Rev. 4.

5. Updated Appendix B Table of Contents to include Comrnitment Tracking Annotation and updated Aug-10 Program title.

. 6. Revised references for AUG-03 Inspection Program.

7. Updated AUG-09 Inspection Program to reflect latest VIP based planning.

8. Expanded AUG 10 inspection Program to include recommendations of GE SIL 588.

9. Expanded Attachment 2 to include the following PECO Energy approved Position papers:

PSC-95-001 Components added to Program PSP-95-004 Weld Reference Marking System

10. Updated the following ISI Program and Augmented ISI Program Tables:

RPV Tables to include 100% shell weld selections per 10CFR50 on Unit 2. l Various System Tables to reflect component reselections for 3R10.

AUG-09 Inspection Program Tables for the RPV Shroud. I AUG 10 Inspection Program Tables to include SIL 588 recommendations.

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Specification M 733 Rev. 2 ,

Addendum 1 PBAPS 2 & 3 ISI Program Page 1-lii of 51 CONTENT OF ADDENDUM 1 TO REVISION 2 Specification Text:

Specification Cover Sheet.

Summary and Content of Addendum 1 to Revision 2 (2 pages).

Page 18 of 51. Table 2.5-1.

Pages 43 & 44 of 51, Section 8.3.4, Class 3 hydrostatic testing.

Appendix A Table of Contents Page 2 of 2 (1 page).

, Relief Request RR 14, Rev. 4, (4 pages).

Appendix B Table of Contents, (1 page).

Appendix B-3, Page 1 of 3 (1 page).

Appendix B 9 (3 pages).

Appendix B 10 (2 pages).

Attachment 2 Table of Contents (1 page).

Attachment 2-4 (3 pages).

Attachment 2 7 (2 pages).

Tables:

Reactor Pressure Vessel ISI Tables, Unit 2 and Common (21 pages).

Augmented Inspection Program 9 Tables, Unit 2 and Common (3 pages).

Augmented inspection Program 10 Tables, Unit 2 and common (2 pages).

Core Spray System ISI Tables, Unit 3, Drawing: DCN-14-MI-303 4-B (6 pages).

Recire. System ISI Tables, Unit 3, Drawing: RCS-02 MI-301 1-A (4 pages).

Recire. System ISI Tables, Unit 3, Drawing: RCS-02-MI 301 1 B (4 pages).

Reactor Drain ISI Tables, Unit 3, Drawing: DDN-04-MI 301 1 (2 pages).

RHR System ISI Tables, Unit 3, Drawing: DCA 10-MI-303-9-B (2 pages).

RHR System ISI Tables, Unit 3, Drawing: DCA 10-MI-3M-13 (2 pages).

Augmented inspection Program 9 Tables, Unit 3 (3 pages).

Augmented inspection Program 10 Tables, Unit 3 (2 paipo;

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l Specification I M-733, Rev. 2 'i PBAPS 2 & 3 l

ISI Program Page 2 of 51 3

TABLE OF CONTENTS 4

1.0 . Introduction i

{ 1.1 Reference Documents i

! 1.2 Definitions

1.3 Abbreviations 1.4 Codes and Standards

2.0 Regulatory Requirements j 2.1 Classification of Components

. 2.2 ASME Section XI l 2.3 Exemptions

2.4 Augmented Requirements i 2.5 Additional Bases j 2.6 ASME Section XI Drawings 1 2.7 System identification 3.0 inservice Inspection Program i

l 3.1 Responsibility I

. 3.2 Records 1

i. 3.3 Methods of Examination 3.4 Repair and Replacement 3.5 Examinations - General 3.6 Relief Requests l 3.7 Evaluation of Examination Results 4.0 Reactor Pressure Vessel (RPV) Examinations  !

4.1 Pressure-Retalning Welds in RPV (Category B A)

4.2 Full Penetration Welds of Nozzles in the RPV Inspection Program B (Category B D)

, 4.3 Partial Penetration Wolds in the RPV (Category B-E) 4.4 Dissimilar Metal Welds (Category B-F) 4.5 Pressure-Retalning Bolting greater than 2' diameter (Category B G 1) 4.6 Pressure-Retaining Bolting less than or equal to 2* diameter (Category B-G 2) 4.7 Integrally Welded Attachments to vessels (Category B-H) 4.8 Pressure-Retaining Welds in piping (Category B-J) ,

t 4.9 RPV Interior Shell and Core Support Structure (Category B-N 1 and B-N-2) i j 4.10 Control Rod Drive Pressure-Retaining Welds (Category B-0)

{ 4.11 Pressure Testing (Category B-P) i

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Specification' M 733, Rev. 2 l PBAPS 2 & 3 )

ISI Program {

Page 3 of 51 5.0 Class 1 Welds, Botting, and Component Examinations (Excluding the RPV) 5.1 Dissimilar Metal Welds (Category B-F) 5.2 Pressure-Retaining Botting greater than 2' diameter (Category B-G 1) 5.3 Pressure-Retaining Bolting less than or equal to 2' diameter (Category B G 2) 5.4 Pressure-Retaining Welds in piping (Category B-J) l 5.5 Integral Attachments (Category B-K 1) 5.6 Pressure-Retaining Welds in pump casings (Category B-L-1) 5.7 Intemal Pressure-Retaining surfaces of pump casings (Category B-L-2) 5.8 Pressure-Retalning Welds in valve bodies (Category B-M-1)

5.9 Intemal Pressure Retaining surfaces of valve bodies (Category B-M-2) 5.10 Pressure Testing (Category B-P) 6.0 Class 2 Welds, Bolting, and Component Examinations

. 6.1 Pressure-Retaining Walds in Class 2 pressure vessels (Category C-A) 6.2 Pressure-Retaining Nozzle Welds in vessels (Category C-B) 6.3 Integral Attachments to vessels, piping and pumps (Category C-C) 6.4 Pressure-Retalning Bolting greater than 2* diameter (Category C D) 6.5 Class 2 Pressure-Retaining Pipe Welds (Category C-F) 6.6 Pressure-Retaining Welds in pumps and valves (Category C-G) 6.7 Pressure Testing (Category C-H)

< 7.0 Class 3 Component Examinations

7.1 Class 3 Integral Attachments (Categories D A, D-B, and D-C) 8.0 Pressure Testing 4

8.1 Class 1 Pressure Test Program 8.2 Class 2 Pressure Test Program 8.3 Class 3 Pressure Test Program t

9.0 Class 1,2, and 3 Component Supports (Excluding Snubber Assemblies) 9.1 General 9.2 Exemptions 9.3 Examination Requirements 1

9.4 Selection Basis

! 9.5 Examination Implementation 10.0 ISI Program Table /Fleids Description

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Specification M 733 Rev. 2 PBAPS 2 & 3 ISI Program Page 4 of 51 ADoendices Appendix A Relief Requests Appendix B Augmented Requirements Appendix C List of ASME Section XI ISI Boundary Drawings List of ASME Section XI ISI isometric and Component Drawings List of ASME Section XI ISI Calibration Block Drawings 4

' Attachments Attachment 1 ASME Section XI Boundaries of Applicability, Basis Document Attachment 2 ASME Section XI ISI Program Position Papers i Ia!2lpa

!Si Program and Augmented Inspection Tables, PBAPS Unit 2 and Common ISI Program and Augmented inspection Tables, PBAPS Unit 3 l

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ISI Program 3

Page 5 of 51 1

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1.0 INTRODUCTION

This document contains the Inservice inspection (ISI) Program for the second 10-year interval of the Peach Bottom Atomic Power Station Units 2 & 3 (PBAPS 2 & 3), as required by Title 10, Code of Federal Regulations, Part 50 (10CFR50), Article 55a, " Codes and Standards." It details the technical basis of the program and provides an overall description of the actrvities planned to fulfill the ISI requirements fo pressure-retaining cornponents and their supports, as defined in the 4 American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code,Section XI,

" Rules for Inservice Inspection of Nuclear Power Plant Components." This Program identifies the 3

Class 1,2, and 3 components (e.g. piping, pumps, valves, vessels) and their supports, subject to a

the exarmnation and test requirements of Subsections lWB, IWC, LWD and IWF of ASME Section XI. It also identifies and details the programs established to satisfy augmented l

requirements imposed at PBAPS 2 or 3, during the second inspection interval.

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The second interval for PBAPS 2 begms on September 19,1986, and ends on November 4,1997.

4 The second interval for PBAPS 3 begins on December 23,1985, and ends on August 14,1997.

! The above dates represent adjustments to the PBAPS 2 & 3 second interval due to refueling outage alignment and extended plant shutdown as detailed in Reference 1.1.2.

1 The ISI Program consists of two parts; the Program text with appendices, and a tables section.

i The text defines the basis of the ISI Program. It lists and explains the specific boundary, exemption, sample size, and component selection criteria utilized for Class 1,2 and 3 components j i

• and their supports. The Appendices contain: Relief Requests. programs established to satisfy l augmented requirements, copies of important reference documents needed to explain program detalis, and listings of the ASME Section XI Drawings including: ISI Boundary drawings, ISI j

isometric drawings, component drawings, and calbration block drawings. The tables portion includes the ISI Program Tables. The ISI Program Tables contain an itemized listing of all

l nonexempt components within the Class 1,2 and 3 ASME boundaries depicted on the ASME l

Section XI Boundary Drawings, along with examination requirements which apply.  :

1.1 REFERENCE DOCUMENTS

1.1.1 Safety Evaluation Report for second 10-year interval ISI Program issued via an April 8,1986, letter j from Dr. Muller (NRC) to E. G. Bauer, Jr. (PECo).

I 1.1.1e Safety Evaluation report for Updated second 10-year interval ISI Program issued via a December j 23,1992 letter from C. L. Miller (NRC) to G.J. Beck (PECo).

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1.1.2 Revised PBAPS interval dates as documented in a August 17,1988, letter from J.W. Gallagher p

i (PECo) to W. T. Russel (NRC), and February 25,1991 letter from G.J. Beck (PECo) to NRC.

1 1.1.3 Generic Letter 88-01, NRC position on IGSCC in BWR Austenitic Stainless Steel Piping, dated January 25,1988; including Supplement 1, February 4,1992 (T02791).

l 1.1.4 CM 1, PBAPS 2 & 3 response to NRC Generic Letter 88-01 dated August 2,1988, March 31,1989, l June 4,1990, and August 17,1992 (T02791).

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4 Spec #ication l M 733, Rev. 2 1

PBAPS 2 & 3 ISI Program Page 6 of 51 i

1.1.5 NUREG-0313, revision 2 - Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping, January,1988.

1.1.8 NUREG-0619, BWR Feedwater Nonle and Control Rod Drive Retum Line Nonle Cracidng

] (November 1980) with Generic Letter 81-11 (February 20,1981).

j 1.1.7 CM 2, PBAPS 2 & 3 Implementation Program for NUREG 0619, PECo letter of January 21,1981,.

{~ J. W. GaNagher to Darrell G. Eisenhut (NRC) (T03155). I 1 1.1.8 PBAPS 2 & 3 Implementation Report for NUREG-0619, PECo lettar of September 29,1983, J. W.

I GaNagher to Darrell G. Eisenhut (NRC).

1.1.9 IE Bulletin No. 8013, Cracking in Core Spray Spargers, dated May 12,1980.

1.1,10 CM 3, PBAPS 2 & 3 Response to IE Bulletin No. 8013, PECo letter of June 13,1980, S. L. DaRroff j to Boyce H. Grier (NRC) (T03414).

5 1.1.11 General Electric Company SIL No. 289, Core Spray Visual Inspection Revision 0, dated February  ;

) 1979 and including Revision 1, Supplement 1, dated February 23,1989.  !

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1.1.12 NUREG/CR-3052, Closeout of IE Bulletin 80 07: BWR Jet Pump Assembly Failure, l November,1984.

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) 1,1,13 IE Bulletin No. 80-07, BWR Jet Pump Assembly Failure, dated April 4,1980, and including  ;

i Supplement No.1 dated May 13,1980. '

l 1.1.14 General Electric Company, SIL No. 330, Jet Pump Beam Cracks, June 9,1980. l 1 l 1.1.15 PBAPS Unit 2 Response to IE Bulletin No. 80-07, PECo letter of May 2,1980, S. L Daltroff to i Boyce W. Grier (NRC).

1.1.16 PBAPS Unit 3 Response to IE Bulletin No. 80-07, PECo letter of May 7,1980, S. L. Daltroff to l Boyce W. Grier (NRC).

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{ 1.1.17 A-C-80 PECO Energy Corporate ASME Section XI Administrative Procedure. l

, i 1.1.18 PBAPS 2 & 3 Updated Final Safety Analysis Report.  !

l 1.1.19 PBAPS 2 & 3 Technical Specifications.

1.1.20 NED Specification number M-710, PBAPS 2 & 3 Pump and Valve Inservice Testing Program,  :

Second Ten Year Interval.

1.1.21 Evaluation of ISI Examinations at PBAPS 2 & 3, PECo letter of February 19,1980 E. G. Bauer, Jr.

i to T. A. Ippolito (NRC).

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Page 7 of 51 1.1.22 Safety Evaluation for PBAPS 2 & 3 First Interval ISI Program Relief Request, NRC letter of May 2, 1983, J. F. Stotz to E. G. Bauer, Jr.

1.1.23 NED Specification M 679, General Requirements for the ASME Section XI Repair and Replacement Program.

1.1.24 Regulatory Guide 1.147, inservice Inspection Code Case AcceptatHlity, ASME Secten XI, Division 1, Revision 11, October 1994. l 1.1.25 General Electric Company, SIL No. 409, incore Dry Tube Cracks, July 31,1986.

1.1.26 General Electric Company, Sll No. 474, Steam Dryer Drain Channel Cracking, October 26,1988.

1.1.27 Updated PBAPS 2 & 3 Second interval ISI Program initial submittal and subsequent updates; PECo to NRC letters dated 11/15/90,3/1942, and 4/16/92.

1.1.28 General Electric Company, SIL No. 462, Shroud Support Access Hole Cracks, December 19,1990.

1.1.29 PECO Energy calculation ME-34, Class 1 exemption sizes.

1.1.30 General Electric Company, SIL No. 551, Jet Pump Riser Brace Cracking,2/26/93.

1.1.31 General Electric Company, SIL No. 554, Top Guide Cracking,4/6/93.

1.1.32 Stone & Webster calculation PM-945, CRD Housing Weld Exclusion Evaluation.

1.1.33 Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors, i 1.1.34 PECO Energy response to Generic Letter 94-03, dated August 24,1994.

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' 1.1.35 C84 4, PBAPS Unit 2 response to Generic Letter 94-03, dated September 9,1994 (T03415).

i i 1.2 DEFINITIONS 1.2.1 ASME Section XI Drawings - Include Piping and instrument Diagrams (PalD's), isometrics, and j component drawings which delineate the specific boundaries, areas, or items requiring NDE, test,

or repair and replacement per ASME Section XI; and augmented NDE or tests.

1.2.2 Augmented Requirements - Those NDE or tests required by documents other than ASME

! Section XI, such as: Regulatory Guides, NUREG's, NRC Generic Letters. I. E. Bulletins / Notices,

FSAR, Technical Specifications, manufacturer's recommendations, etc.

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, 1.2.3 Authorized Nuclear inservice inapoctor (ANil)- A person employed and qualified by an 1

' Authorized Inspection Agency to verify that NDE, tests, and repairs and replacements (excluding welding and brazing) are performed in accordance with the rules of ASME Section XI.

i Specification M 733, Rev. 2 j PBAPS 2 & 3 ISI Program Page 8 of 51 1.2.4 Calibration Block Drawings The drawings which detail the specific configuration of individual

standards used for calibrating ultrasonic test equipment.

i j' 1.2.5 Code - ASME Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components,"

edition and addenda applicable to the individual PECo nuclear plant programs.

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} 1.2.6 Component - An item in a nuclear power plant such as a vessel, pump, valve, etc. Component

may also be used to refer to systems or portions of systems such as welds, botting, and supports.

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i 1.2.7 Form NIS 1, Owners' Data Report for Inservice inspections An ASME form used to document the results of inservice inspection examinations on Class 1 and 2 components. It is to be used as i the certification page for submittal of the ISI Summary Report.

) 1.2.8 Deleted.

l 1.2.9 inservice inspection (ISI) - Those Nondestructive Examinations (NDE) including visual examinations performed on certain Class 1,2, and 3 (or equivalent) components and their supports

! throughout the operating life of the nuclear plant, as required by ASME Section XI, subsections

! IWA, IWB, IWC, LWD, and IWF; and as applicable, lWE.

1110 Inservice inspection Summary Report - The report that is prepared at the completion of each i

refueling outage as specified in ASME Section XI. In the case of PSI, it is submitted per FSAR requirements prior to commercial operation.

f j 1111 inservice Testing (IST) - Those tests conducted on certain pumps and valves to verify their

! operational readiness and/or integrity throughout the operating life of the nuclear plant, as required {

! by ASME Section XI, subsections IWP and IWV. l 1112 inspection interval - As defined by regulations, a ten year time interval, during which the ISl/IST/R&R program is applicable using a specific Edition and Addenda of ASME Section XI. The

first ten year inspection interval commences on the date of commercial operation with the i

' successive intervals beginning on the date the previous interval ends. An inspection interval length may be increased or decreased up to one year, to correspond with plant outages. Additionally, the j interval may be extended for a period equivalent to an outage, which extends continuously for six months or more.

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, 1113 Inspection Period A time frame approximately equivalent to one third of an interval. It is used for i apportioning the implementation of ISI Program NDE during the interval.

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i 1114 ISI Program Document The site / unit specific document (including applicable drawings) which i

addresses the overall ISI requirements during a ten year interval. The complete ISI Program is

, made up of 4 sub-programs as follows:

Wolds, Bolting, and Component Subprogram

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Component Supports and Snubbers Subprogram l

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Reactor Pressure Vessel (RPV) Subprogram i

Pressure Test Subprogram i

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l Specification M 733, Rev. 2 l

PBAPS 2 & 3 l ISI Program l Page 9 of 51 )

l 1.2.15 ISI Tables The unit specific listing of the total population of items such as welds, bolting, components, RPV intemals, supports, snubbers, and portions of systems which are subject to examination, pressure test, and Repair and Replacement during the ten year interval (i.e. all ,

nonexempt components). These listings are included within the ISI Program Document (s), and, as l a minimum, identify items selected for examination along with examination frequency requirements l and other mandatory requirements, if special consideration is appticable. These tables provide the primary basis for development of the ISI implementing Plan.

1.2.16 ISI implementing Plan - The listing of nonexempt components identified in the ISI Tables, with the information necessary for implementation of examinations. Such information shall include:

components selected for examination; scheduling information; applicable NDE methods, procedures, and calibration blocks; etc.

1.2.17 ISI Outage Plan - A listing of those components identified in the ISI implementing Plan which are required to be examined during a particular outage.

1.2.18 Instrument Root Valve - The first valve, in an instrument line, off of the main process line.

" 1.2.19 Nominal Operating Pressure - For Class 1 systems, the range of pressures which may normally be expected when the system is known to be operating at 100% reactor power.

1.2.20 Nondestructive Examination (NDE) Any of several physical, optical, chemical, electrical, or electromagnetic tests used primarily to examine items for surface or intemal defects without destroying the items or impairing their function. Also known as Nondestructive Testing (NDT) and

includes visual, surface, and volumetric methods.

1.2.21 PECO Energy Corporate ASME Section XI Administrative Procedure - The document which defines and controls the all-encompassing effort of Preservice inspection, inservice inspection, Preservice Testing, inservice Testing, Repair and Replacement, and Augmented requirements at PECo's nuclear plants. This procedure, endorsed by the Nuclear Group Senior Management, will apply to all organizations involved with this endeavor.

1.2.22 Position Statement - An ISI/IST/R&R Program record which documents the details of positions i

taken by PECO Energy with respect to generalized Code requirements. These records amplify the

Code requirement and provide consistent guidance for the implementation of the requirement.

4 1.2.23 Preservice inspection (PSI) Those Nondestructive Examinations (NDE) including visual examinations performed on certain ASME Class 1,2, and 3 (or equivalent) components and their supports once, prior to initla! plant operations as part of the Preservice inspection Program, or following a component repair, replacement, or modification. The results of these examinations provide a baseline for comparison to subsequent ISI examinations.

1.2.24 Pressure Test Subprogram - A portion of the overall ISI Program which identifies the components and portions of piping in ASME Class 1,2 and 3 (or equivalent) systems, which are subject to various pressure tests during the ten year interval. These tests include the hydrostatic, pneumatic, leakage, functional, or Inservice types.

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j. PBAPS 2 & 3 ISI Program Page 10 of 51 ~

s l 1.2.25 Reactor Pressure Vessel (RPV) Subprogram - A portion of the ISI Program which identifies the Intemal attachments, surfaces, welds, and components within the reactor pressure vessel boundary,

! including the safe-ends, which require NDE during the ten year interval.

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j 1.2.26 Regulatory Authority The United States Nuclear Regulatory Commission, empowered to issue j and enforce federal regulations influencing design, construction, and operation of nuclear power

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j 1.2.27 Rollef Request - A written request submitted to the regulatory authority which identifies specific j cst,pcE,sats which cannot be examined or tested in accordance with ASME Section XI or j augmented requirements it includes the reason these requirements cannot be met and technical j justification for performing an attemative to the requirements.

) 1.2.28 Snubber - A dynamic restraint device utilized in certain component supports. Can be either hydraulic or mechanical.

1 i 1.2.29 Snubber Assembly The functional unit of a snubber type component support, including: the j snubber body, extension piece or end bracket, and the load pins along with their retainers.

t l 1.2.30 Source Document Any document containing requirements to which PECO Energy is committed or which apply to PECO Energy by virtue of law, such as federal, state, and local laws and j regulations.

2 1.2.31 Structural Discontinuity Weide Include circumferential welds joints at pipe to vessel nozzle, pipe i

to valve body, pipe to pump casing, pipe to fittings and pipe to pipe of different schedule wall thickne6s.

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) 1.2.32 Terminal End Weld - Circumferential welds at the extremities of pipe runs that connect to 4

structures or components or circumferentleJ welds in piping within 3 pipe diameters of the centerline j of rigid pipe anchors.

! 1.2.33 Wolds, Bolting, and Component Subprogram - A portion of the ISI Program which identifies the non-exempt welds, bolting, and components on ASME Class 1,2, and 3 (cr equivaient) systems j

which are subject (se! acted and non selected) to NDE during the ten year interval.

I 1.3 ABBREVIATIONS

, 1.3.1 ALARA - As Low As Reasonably Achievable 4

l 1.3.2 ANS American National Standard a

, 1.3.3 ANSI American National Standard Institute 1.3.4 ASME - American Society of Mechanical Engineers j 1.3.5 ASNT American Society for Nondestructive Testing

Specifk.ation M 733, Rev. 2 PBAPS 2 & 3 ISI Program Page 11 of 51 1.3.6 AUG. - Augmented 1.3.7 BWR - Boiling Water Reactor 1.3.8 DISG - Examine one of a group when disassembled 1.3.9 DISS - Examine when disassembled 1.3.10 EOl End of interval 1.3.11 10 - Interval distribution 1.3.12 IGSCC - Intergranular Stress Corrosion Cracking 1.3.13 ISI Inservice inspection

'1.3.14 ISO Isometric 1.3.15 IST - Inservice testing 1.3.16 MT Magnetic particle testing 1.3.17 NDE Nondestructive examination 1.3.18 NPS Nominal pipe size 1.3.19 NRC United States Nuclear Regulatory Commission 1.3.20 PBAPS - Peach Bottom Atomic Power Station 1.3.21 PECo - PECO Energy 1.3.22 P&lD - Piping and instrument diagram 1.3.23 PT - Penetrant examination 1.3.24 RO Refueling outage l i

1.3.25 RPV - Reactor pressure vee,sel 1.3.26 R&R - Repair and replacement l

1.3.27 RR XX - Relief request 1.3.28 RT Radiographic examination I

Specification M-733 Rev. C PBAPS 2 & 3 ISI Program - 1 Page 12 of 51

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1.3.29 SIL Service information letter  !

1.3.30 UT Ultrasonic examination l 1.3.31 VT - Visual examination i

1.3.32 1P,2P,3P - First period, second period, third period '

1.3.33 74S75 - 1974 Edition thru and including the Summer 1975 Addenda 1.3.34 80W81 - 1980 Edition thru and including the Winter 1981 Addenda 1.3.35 88A87 1986 Edition thru and including 1987 Addenda 1.4 CODES AND STANDARDS 1.4.1 Title 10, Code of Federal Regulations, Part 50 (10CFR50), Article 55a, ' Codes and Standards."

1.4.2 American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code,Section XI, Division 1: " Rules for Inservice Inspection of Nuclear Power Plant Components; 1980 Edition, Winter 1981 Addenda."

1.4.3 Regulatory Guide 1.26 R/3 Quality Group Classifications and Standards for Water, Steam, and Radioactive Waste Containing Components of Nuclear Power Plants.

1.4.4 SNT-TC 1 A,1980 Edition, Recommended Practice for Personnel Qualification in Non-destructive Testing.

1.4.5 ANSI N45.2.6,1976, Qualification of Inspection, Examination, and Testing Personnel for Nuclear Power Plants.

1.4.8 Regulatory Guide 1.58 R/1 Qualification of Nuclear Power Plant inspection Examination and Testing Personnel (endorses ANSI N45.2.6,1978).

1.4.7 Regulatory Guide 1.65 R/0 Materials and Inspection for Reactor Vessel Closure Studs.

1.4.8 Regulatory Guide 1.147, latest revision, inservice Inspection Code Case Acceptability, ASME i Section XI, Division 1.

l 1.4.9 Regulatory Guide 1.150 R/1 - Altemate Method Ultrasonic Testing of Reactor Vessel Welds During i Preservice and Inservice Examination.

1.4.10 Deleted.

1.4.11 Deleted.

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Page 13 of 51 2.0 REGULATORY REQUIREMENTS 2.1 CLASSIFICATION OF COMPONENTS in accordance with 10CFR50.55a (g)(1), an ASME classification has been assigned to plant components and systems for the purpose of applying the appropriate rules of ASME Section XI for Inservice inspection. Classification has been applied in accordance with 10CFR50.2(v) for Class 1 systems and Regulatory Guide 1.26 Revision 3 for Class 2 and 3 systems. System safety functions are consistent with the 1988 revision of the PBAPS UFSAR.

For instruments connected to Class 1 piping, the boundary extends to the excess flow check valve.

For instruments connected to Classes 2 and 3 piping (except main steam), the boundary extends to the Instrument root valve. Branch connections (including instruments lines) on Class 2 main steam piping, outside containment, which are less than 21/2' NPS were not classified, since these lines are not required to be seismically designed per Regulatory Guide 1.29.

i it most be noted that the classification of components as equivalent to ASME Classes 1,2, or 3 Implies equivalency for purposes of inservice inspection only and does not imply that the components were designed in accordance with ASME requirements. Since most of the basic plant design was accomplished prior to December 1969, codes and standards applicable at that time were used as set forth in the PBAPS UFSAR.

See Attachment 1 for the complete basis of component classifications.

1 2.2 ASME SECTION XI In accordance with 10CFR50.55a(g)(4), this program is in compliance, where possible, with the applicable requirements of the 1980 Edition of Section XI with Addenda through Winter 1981 (80W81). Although the basic plant design, accomplished prior to December 1960, is not totally consistent with the examination requirements of later codes, every attempt has been made to obtain maximum compliance. For instances where 100% compliance is not feasible, attemative examinations and tests have been proposed which will satisfy the intent of the Code. This program identifies the areas for which compliance cannot be achieved, with proposed attemative methods of assurance of system Integrity.

An exception to the use of the 80W81 code is found in the area of Class 1 & 2 pipe welds as discussed in the following sections:

2.2.1 ASME Code Class 1 Pipe Welds 10CFR50.55a(b)(2)(li) allows for the optional use of the 1974 Edition with Addenda through Summer 1975 (74S75) of Section XI for determining the extent of examination for Class 1 pressure-retalning pipe welds if the plant's construction permit was docketed prior to July 1,1978.

"...the extent of examination for Code Class 1 pipe welds may be determined from the requirements of Table IWB-2500 and IWB 2600 Category B-J of Section XI of the ASME Code in the 1974 Edition and Addenda through the Summer 1975...'

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Specification' l i

M 733, Rev. 2 PBAPS 2 & 3 p ISI Program i

Page 14 of 51 Table IWB-2600 from the 74S75 Section XI, which specifies the type of NDE to be applied to the I

welds on various size piping, is not used in this ISI Program. For this program, the type of NDE i applied is determined from the 80W81 of Section XI. This position utilizes the later code directions

and represents a more practical approach for determining examination method and associated 4

acceptance criteria.

I To summarize the approach taken for Class 1 pipe welds:

i Exemotions The 80W81 Edition of Section XI was used to determine exemptions (See Section 2.3.1) i Sample Slae i

• The 74S75 Edition of Section XI is used for determining the percentage of nonexempt .

] . welds which are subject to examination.

I weld selection l

• The welds selected represent areas expected to experience higher stresses, as determined by guidance provided in the 80W81 Code. (See Section 3.5.1)

!- Examination Method

' The 80W81 Section XI is used for determining the type of NDE applied to these welds.

[ 2.2.2 ASME Code Class 2 Ploe Wolds 10CFR50.55a(b)(2)(iv)(A) requires the use of the 74S75 Edition of Section XI for determining the extent of examination of Class 2 pipe welds in the Residual Heat Removal, Emergency Core Cooling Systems and Contsjnment Heat Removal Systems.

$ "...the extent of examination for these systems shall be determined by the requirements of

, Paragraph IWC-1220, Table IWC 2520, Category C-F and C-G, and Paragraph IWC-2411 in the

} 1974 Edition and Addenda through the Summer 1975 Addenda."

10CFR50.55a(b)(2)(iv)(B) allows the optional use of the 74S75 Edition of Section XI for determining l the extent of examination for Class 2 pressure retaining pipe welds, for the remaining Class 2 l 4

systems, if the plant's construction permit was docketed prior to July 1,1978, as is the case at PBAPS 2 & 3.

l "...the extent of examination for Code Class 2 pipe welds may be determined by the requirements l l of paragraph IWC 1220, Table IWC-2520, Category C-F and C G and paragraph IWC 2411 in the ,

j 1974 Edition and Addenda through Summer 1975 Addenda of Section XI of the ASME Code..." 1 PBAPS 2&3 has incorporated the above for all Class 2 piping welds as summarized below:

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Specification 1 M 733, Rev. 2 l PBAPS 2 & 3  !

ISI Program Page 15 of 51 Exemptions The 74S75 Edition of Section XI was used to determine exemptions, as required by 10CFR50.55a, (See Section 2.3.2).

Sample Size j

The 74S75 Edition of Section XI was used to determine the percentage of nonexempt welds which are subject to examination.

Weld Selection Weld selections were distributed among all applicable systems based on geometric configuration, (i.e. pipe to elbow, pipe to tee, etc.) to develop a representative sample of structural discontinuity welds. Selections also included terminal ends. (See Section 3.5.1)

Examination Method The 80W81 Edition of Section XI was used for determining the type of NDE applied to these welds.

2.2.3 Non-applicability of Subsection lWE Subsection IWE (Class MC Components) of ASME Section XI has not been endorsed for use by the NRC and is therefore not addressed in this Program. Testing, as required by the Code of Federal Regulations, Appendix J, is being performed at PBAPS 2&3 to verify the integrity of the containment.

2.2.4 Subsections lWP and IWV Subsection IWP (Pump Testing) and Subsection iWV (Valve Testing) are not addressed in this program document. For information regarding these topics, see Reference 1.1.20.

2.3 EXEMPTIONS ASME Section XI rules allow certain components or portions of components (and their supports),

which are classified as ASME Class 1,2, or 3 (or equivalent), to be exempt from the surface and volumetric examination requirements of the Code. The specific Code exemptions which have been applied to the PBAPS 2 & 3 ISI Program are detailed below, it should be noted that these exemptions do not apply to the pressure testing requirements of the Code, and the accompanying VT 2 Examination.

Specification M 733, Rev. 2 i

PBAPS 2 & 3 ISI Program Page 16 of 51 l

1 l 2.3.1 Class 1 Exemotions Discussion: The Class 1 exemptions used in this ISI Program are taken directly from the 80W81

Section XI, Sub article IWB 1220.

, Exemptions used:

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. 1. Components that are connected to the reactor coolant system and part of the reactor l

coolant pressure boundary and that are of such a size and shape so that upon postulated  ;

j rupture the resulting flow of coolant from the reactor coolant system under normal plant operating conditions is within the capacity of make up systems which are operable from

on site emergency power.

For PBAPS 2 & 3, this exemption is applicable to 3' nominal pipe size (NPS) or less for lines containing steam and 1.5" NPS or less for lines containing water (see reference 1.1.29).

, 2. Piping of 1" (NPS) and smaller along with components and their connections in piping of 1' NPS and smaller.

3. Reactor vessel head connections and associated piping,2-inch NPS and smaller, made

', inaccessible by control rod drive penetratioris.

4 2.3.2 Class 2 Exemptions Discussion: The Class 2 exemptions are taken from 74S75 Section XI, subarticle IWC 1220, and from one relief request, as presented in the following:

i l Exemptions used:

1. Components in systems where both the design pressure and temperature are equal to or

less than 275 psig or 200*F respectively.

2. Components in systems or portions of systems, other than emergency core cooling systems, which do not function during normal reactor operation.

4 3. Component connections, piping, and associated valves, and vessels (and their supports)

that are 4' NPS and smaller.

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4. Piping and other components of any size beyond the last shut off valve in open ended portions of systems that do not contain water during normal plant operating conditions.

Note: This exemption is not identified in the 74S75 edition of Section XI; however, it is j

allowed by the 1986 Edition which has been approved for use by i

' 10CFR50,55a(b)(2). Justification for use of this exemption is provided in Relief Request RR 11.

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i' Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Page 17 of 51 2.3.3 Class 3 Exemptione Discussion: The Class 3 exemptions are taken from the 80W81 Section XI, subarticle IWD-1220, i

as presented in the following.

Exemptions used

) 1. Integral attachments of supports and restraints to comp 0rsts that are 4' NPS and smaller

within the oystem boundaries of Examination Categories D-A, D-8, and D-C of

{ Table IWD 25001 shall be exempt from the visual examination VT 3, . . . . . . .

a i Note: Included in this exemption are non-pipe components for which neither the l cumulative inlet nor cumulative outiet area exceeds the area of a 4' l.D. pipe.

2. Integral attachments of supports and restraints to ccmperats exceeding 4' NPS may be exempted from the visual examination VT 3 of Table IWD 25001, provided-

a. The components are located in systems (or portions of systems) whose function is j

not required in support of reactor residual heat removal, containment heat removal, j and emergency core cooling; and

b. The components operate at a pressure of 275 psig or less or at a temperature of 200*F or less.

2.4 AUGMENTED REQUIREMENTS a

For purposes of this ISI Program, augmented examinations are those scheduled examinations i

which are not required by ASME Section XI. These augmented requirements are typically pursuant l

to NRC Generic Letters, NRC Regulatory Guides, or NSSS supplier recommendations (SIL's), etc.

. The PBAPS 2 & 3 augmented examination programs are explained and their examination

' requirements tabulated in Appendix B. It should be noted that some components are subject to both ISI and augmented requirements. In these instances, the component's ISI requirements are identified in the ISI Program Tables, and a reference to applicable augmented requirements is also

provided. The actual augmented examination requirements are then found in the referenced augmented program which is contained in Appendix B.

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! 2.5 ADDITIONAL BASES i

in addition to published Code rules, ASME Section XI Code Cases and Interpretations may be used in formulating the bases of the ISI program. Table 2.5-1 lists the Code Cases and interpretations which have been used to establish the bases of this PBAPS 2 & 3 ISI Program.

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Specification M 733, Rev. 2 Addendum 1 PBAPS 2 & 3 iSI Program

Page 18 of 51

. TABLE 2.51

. CODE CASES AND INTERPRETATIONS APPLICABLE TO THE ISI PROGRAM Approved by Code Case USNRC Reg.

Number Title Guide 1.147 N-343 AMemative Scope of Examination of Yes (Rev. 9)

Attachment Weids for Examination l Categories B-H, B K 1 and C-C N 356 Certification Period for NDE Level ill Yes Personnel N-389 ARemative Rules for Repairs, Replacements, Yes or Modifications N-406 ANemate Rules for Replacement Yes (Rev. 8) l 4

N 416 AMernate Rules for Hydrostatic Te of Yes Repair or Replacement of Class 2 P N 4161 Allemate Rules for Hydrostatic Testing of No 2

Repair or Replacemert of Class 1,2, & 3 Piping.

N-419 Extent of VT-1 Examinations, Category B-G 1 Yes of Table IWB-2500-1

N-426 Extent of VT.1 Examinations, Category B-G-2 Yes Table IWB-2500-1 N 427 Code Cases on inspection Plans Yes N-435-1 ANemative Examination Requirements for Yes Vessels with Wall Thickness 2 in. or less N-448 Qualifications of VT 2 and VT-3 Visual Exam- Yes ination Personnel N 449 Qualification of VT 4 Visual Examination Per- Yes 1 i sonnel l l

1 N-460 Altemative Examination Coverage for Yes

Class 1 and Class 2 Weids N-461 Altemate Rules for Piping Calibration Yes d

Block Thickness N-479 Boiling Water Reactor (BWR) Main Steam Yes (Rev. 9) I j Hydrostatic Test i N-498 Altemative Rules for 10 Year Hydrostatic Yes Pressure Testing for Class 1 and 2 Systems N 4981 Altemative P.ules for 10 - Year Hydrostatic No

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Pressure Testing for Class 1,2, & 3 Systems.

. NOTES: (1l Code Cases approved by Reg. Guide 1.147 are available for use, j- (2, Refer to Relief Request RR-14 for Code Cases not yet approved.

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISl Program Page 19 of 51 2.6 ASME SECTION XI DRAWINGS The ASME Section XI Drawings define and detail the extent of systems and/or components subject to the rules of ASME Section XI, additionally, they depict parts and equipment used to implement

] the required examination programs.

i 2.6.1 A8ME 8ection XI ISI Bounderv Drawines These ASME Section XI ISI Boundary Drawings are Piping and instrumentation Diagrams (P&lD's) that have been color coded to define the extent of the ASME classification boundaries and the j portions therein which are exempt from the surface and volumetric examination requirements of Section XI. In addition, the boundary drawings indicate portions of systems which are outside the

ASME boundaries but subject to the PBAPS 2 & 3 ASME Section XI Repair and Replacement Program.

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i j 2.6.2 ASME Section XI 184 loometric Drawines The ASME Section XI ISI isometric Drawings are specifically prepared isometric type drawings which are derived from design isometric drawings. They depict the ASME classified systems, and i identify the components (welds, bolts, supports, etc.), subject to examination, within these systems.

j They also depict components which are subject to augmented examination requirements and ASME j Section XI rules for repair and replacement only.

2.6.3 ASME Section XI ISI Component Drawines The ASME Section XI ISI Component Drawings are specifically prepared detailed drawings of components, which identify specific areas of these components _which are subject to examination in j accordance with Section XI rules.

l 2.6.4 ASME Section XI ISI Calibration Block Drawines i The ASME Section XI ISI Calibration Block Drawings are design /as-built drawings of the standards

which are used for calibration of the ultrasonic examination equipment prior to the performance of

the code required examinations.

2.6.5 Component Succort Deslan Drawines j The Component Support Design Drawings, while not uniquely an ISI drawing, are an important 1

informational source and are referenced in the ISI Tables. These design drawings detail the  ;

3 component support and generally contain a bill of materials which identifies the scope of items '

j subject to the visual examination requirement of the code.

An index of all ASME Section XI ISl Drawings (excluding component support drawings) is contained in Appendix C.

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Specificat3n M-733, Rev. 2 {

1 PBAPS 2 & 3 ISI Program Page 20 of 51 3

l 2.7 SYSTEM IDENTIFICATION l

The following is a list of systems which are included in this ISI Program. The associated Engineering / Design system identification number and Station System number are also included, Engineering /

, Design System Station System Number System Number 01 Main Steam 01 02 Reactor Recirculation 02 l 03 Control Rod Hydraulic 03 i 04 Nuclear Boiler Vessel Instrumentation and Reactor Drain 04

, 06 Feedwater 06 10 Residual Heat Removal (RHR) 10 11 Standby Liquid Control 11 12 Reactor Water Cleanup 12

13 Reactor Core Isolation Cooling (RCIC) 13 14 Core Spray 14 19 Fuel Pool Cooling and Cleanmp 19 23 High Pressure Coolant injection (HPCl) 23 i 32 High Pressure Service Water 32

. 33 Emergency Service Water 33 g 48 Emergency Cooling Water 48 7

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Specification M 733, Rev. 2 i PBAPS 2 & 3 ISI Program Pa0e 21 of 51 4

A i 3.0 INSERVICE INSPECTION PROGRAM 3.1 RESPONSIBit.lTY i

As owner of PBAPS 2 & 3, PECO Energy bears the overall responsibility for the performance of ISI.

The required nondestructive examinations may be performed by PECO Energy or a qualified examination a0ency. The results and evaluation of the examinations, performed by NDE vendors, will be reported to PECO Energy, who shall retain responsibility for final evaluation and disposition of aN NDE.

! 3.2 RECORDS Records and documentation of all information and inspection results, which provide the basis for evaluation and which facilitate comparison with results from previous and subsequent inspections, a

will be maintained and avaliable for the active life of the plant in accordance with Section XI,

, IWA-6000.

l 3.3 METHODS OF EXAMINATION 1

Nondestructive examination methods to be used for the ISI Program include: visual, surface, and  :

volumetric. Personnel performing nondestructive examinations will be qualified with a written procedure prepared in accordance with ASME Section XI Article IWA-2300 and the following l documents as applicable for the techniques and methods used:

b (1) The American Society for Nondestructive Testing (ASNT), Recommended Practice j No. SNT-TC 1 A, June 1980 Edition.

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(2) American National Standard (ANS), ANSI /ASME N45.2.6,1978 Edition as modified by Regulatory Guide 1.58, Rev.1.

l 3.3.1 Visual Examination Visual examinations (VT) will be performed in accordance with IWA 2210 which defines four types

of VT examinations. These types of VT examinations are summarized as follows

) (1) VT-1 examinations shall be conducted to determine the condition of the part, component, or

surface examined The examination shall determine conditions such as cracks, wear, l

corrosion, erosion, or physical damage on the surfaces of the part or components. This 4

type of examination may be performed by direct or remote methods as defined in

, IWA 2211.

(2) VT-2 examinations shall be conducted to detect leakage (or abnormal leakage) from

pressure retalning components during system pressure or functional tests, i a$ - (3) VT-3 examinations shall be conducted to determine General mechanical and structural j conditions of mmponents and their supports, such as the presence of loose parts, debris, .

1 or abnormal corrosion products, wear, erosion, corrosion, and the loss of integrity at bolted l or welded connections.

(4) VT 4 examinations shall be conducted to determine conditions related to operability of i

components or devices, such as mechanical and hydraulic snubbers, component supports, pumps, valves, and spring loaded and constant weight hangers.

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Specification M-733, Rev. 2 PBAPS 2 & 3 ISI Program Page 22 of 51 3.3.2 Surface Examination

. A surface examination will be performed in accordance with ASME Section XI, IWA 2220 to detect the presence of surface cracks or discontinuities. It may be conducted by either magnetic particle (MT) or liquid penetrant (PT) techniques where the surface conditions, material, and accessibility permit such an examination.

3.3.3 Volumetric Examination A volumetric examination will be performed in accordance with ASME Section XI, IWA 2230 to detect the presence of discontinuities throughout the volume of material. Two such volumetric techniques are radiographic (RT) and ultrasonic (UT) examination. The UT methods are used for the planned examinations in this program, however RT may be used as applicable.

3.4 REPAIR AND REPLACEMENT Repairs, replacements, and modifications of ASME Class 1,2,3 components and additional components depicted on the ASME Section XI ISI Boundary Drawings will be performed in accordance with the PECO Energy Repair and Replacement Program, contained in Specification M679 (see ref.1.1.23).

3.5 EXAMINATIONS - GENERAL The bulk of the ISI Program is the planned periodic examinations of specific components as required by Section XI. This section describes the Code requirements which have been used as criteria for determining which Class 1,2 and 3 components require examination during the second 10 year inspection interval. It describes the philosophy utilized for selection and implementation of component examinations along with the basis used for performing the evaluation of examination resuRs. Sections 4.0 through 9.0 provide a summary of the specific areas or groups of examinations (i.e. Code examination category and item number) planned for: the Reactor Pressure Vessel, Class 1 and 2 welds, bolting and components. Class 3 components, pressure testing, and the component supports and snubbers. Therefore, these sections describe how PECO Energy plans to implement the requirements of subsection lWB, IWC, LWD, and IWF of the Code, for PBAPS 2&3.

3.5.1 Selection Basis Class 1 piping welds (Category B F and B J), which were examined during the first inspection Interval, were reviewed to confirm that their population yleided, in general, a representative sample of Class 1 welds, including: dissimilar metal, structural discontinuity, and terminal end butt welds, l along with their Intersecting longitudinal welds. This approach, similar to the guidelines provided in the 80W81 Code Edition, was utilized in light of the fact that the 74S75 Code Edition does not  !

provide guidance for the selection of specific types of welds for examination. Where previously examined welds did not fulfill the above criteria, a different weld was selected from the remaining nonexempt population.

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i Specification I M-733, Rev. 2 i

PBAPS 2 & 3

ISI Program Page 23 of 51 -

e a

i Cass 2 piping welds, (Category C F and C-G) were selected for examination, using the guidance a

provided in the 74S75 Edition of the Code. A 25% sample of Class 2 piping welds, selected from all geometric configurations throughout the Class 2 systems, was developed using the multiple N nponent concept. (See Section 6.5). This criteria yielded a reprea itative population of s.tuctural discontinuities in both main and branch piping. A sample s . '.stminal end welds was also included in the overall examination population. Longitudinal welds intersecting any of the selected circumferential welds, were also included in the sample.

1 Additionally, if system modifications resulted in an increase to the component population, a l sampling criteria, as described above, with considerations to ALARA and access was used to select f the required additional ccwvcaent examinations.

3.5.1.1 Multicomponent Concept For Class 1,2, and 3 multiple components of similar design, function, and service,Section XI allows for the examinations to be performed on only one of the ceT+0nents or divided among the components such that the total number of examinations performed is equivalent to the number that would be performed it ort / one of the ccirpcnent. was required to be completely examined. This l;

multi-component concept is used in this ISI Program and is indicated in the applicable examination categories listed in Sections 4.0 through 9.0 of this document. Those items qualifying as multiple ccEpc6ents are identitled in the ISI Program tables by listing the specific muni-component group in j the notes column of the table.

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! 3.5.2 implementation 1

} In accordance with Section XI, Article IWA 2400, all portions of the ISI Program conform to Inspection Program B of IWA 2420. Program B defines the inspection interval duration as ten years. However, the durations of the second inspection intervals for PBAPS 2 & 3 have been modified, as discussed in Section 1.0 Accordingly, the second Inspection intervals for PBAPS 2 & .'

3 end on November 4,1997 and August 14,1997 respectively. All Code required examinations i

identified in this ISI Program must be completed by these dates, unless the intervals are extended i due to lengthy outages experienced at both plants. This extension is allowable, in accordance with IWA-2400(C). '

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' inspection Program B of the Code further divides the inspection intervalinto three periods. The normal duration of these periods are: First Period - 3 years; Second Period 4 years; Third Period - 3 years. As allowed by lWB 2412(b), these durations may be decreased or extended by one year, to enable an examination to coincide with a plant outage, provided the not  ;

i increase or decrease over the 10 year interval does not exceed one year. Because of the '

l adjustment of the length of the second interval, the inspection periods for PBAPS 2 & 3 will be

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1 adjusted accordingly, i

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Specification

, M 733, Rev. 2 PBAPS 2 & 3 >

1 ISI Program 4

Page 24 of 51 In addition to completing all Code required examinations by the end of the interval,Section XI i requires several categories of examinations to be completed progressively during the interval, in

accordance with the following table

TABLE 3.51 DISTRIBUTION OF EXAMINATIONS DURING THE INTERVAL Pirigg Examination Comoletion 1st 16% minimum and not to exceed 34% of the total examinations.

2nd 50% minimum and not to exceed 67% of the tota' examinations. This includes the examinations performed during the 1st Period.

3rd 100% of all required examinations (total for all three periods).

Applicable examinations within this program will be implemented in accordance with the above table. This implementation concept is referred to as INTERVAL DISTRIBUTION (ID). It can be applied to some individual examinations as well as to categories of examinations. (i.e. examination of a portion of a weld length each period).

The remainder of the ISI examinations will be implemented as required by the Code. These Code '

j requirements vary, and may include the following:

Examinations which can only be conducted during a refueling outage. These examinations will be noted as RO in the ISI Tables. ,

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• Examinations which must be conducted during a specific period. These examinations will l be noted as 1P,2P or 3P, as appropriate, in the ISI Tables.

1 Examinations which may be conducted anytime during the interval, including deferral until the end of the interval. These examinations will be noted as EOl for "End of Interval

• in the ISI Tables.

• Examinations which must take place when an item is disassembled. These examinations 4

will be noted as DISS in the ISI Tables. For items within a multi-component group, where only one of the multiple components must be examined at time of disassemoly, the examination will be noted as DISG in the ISI Table.

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Page 25 of 51 3.6 RELIEF REQUESTS in cases where the Section XI requirements have been determined to be impractical or impossible to comply with, Relief Requests have been prepared in accordance with 10CFR50.55a(g)(5)(lii).

Although most of the second 10-year interval Relief Requests were previously issued for the first 10-year interval ISI program, some new requests for relief have been added.

All requests for relief from the inspection requirements of Subsections lWB, IWC, IWD or IWF of Section XI will include the following as a minimum:

1. A unique alpha-numeric identifier for the Relief Request.

The identifiers for Class 1,2, and 3 Relief Requests will take the following format:

RR XX Where:

RR = Relief Request XX = Sequentially assigned two-digit number

2. Identification of the component (s) for which relief from Section XI requirements is requested. This shallinclude a brief description of the component's function. l

3. The ASME Code Class, Examination Category, and item Number.

4. The specific ASME Code examination requirement (s) from which relief is requested.

5. Information which justifies the request for relief.

i 6. When applicable, a description of the attemate examination or test which will be pp.brmed in lieu of the ASME Code requirements.

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7. The schedule for implementation of the altemate examination or test.

The IWB, IWC, IWD and IWF relief requests can be found in Appendix A.

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Specification j M 733, Rev. 2

PBAPS 2 & 3 ISI Program j Page 26 of 51

! 3.7 EVALUATION OF EXAMINATION RESULTS i Applicable ISI examination results will be evaluated in accordance with Section XI, Subsection lWA 3000, if criteria is not specified in Section XI, the evaluation will utilize the criteria of the original Construction Code as allowed by Paragraph IWA 3100(b). While original

construction at PBAPS 2&3 was performed in accordance with ANSI B31.1,1967 Edition for piping,

, and ASME Section ill,1965 Editinn with Winter 1965 addenda for the RPV, the construction Code ,

] referenced for use in evaluation is interpreted at Peach Bottom to mean the 1968 Edition of ASME l l Section Ill. This approach will maintain the necessary consistency between the baseline  !

examinations and future ISI examinations to meet the intent of ASME Section XI. Acceptance of i this interpretation was requested from the NRC by reference 1.1.21. Approval of this request was

{ granted by the NRC Ir. reference 1.1.22. The NRC evaluation concluded that it would be j impractical to discard the present data bank in favor of establishing a new evaluation criteria, especially where it is based on earlier Section 111 Code requirements.

If future modifications take place, the constructx>n Code referenced will be the Code applicable to j the construction of that component, as well as the evaluation of examination results.

I 4.0 REACTOR PRESSURE VESSEL (RPV) EXAMINATIONS Code Examination Categories and/or item Numbers which apply exclusively to pressurized water j reactor (PWR) plants are specifically excluded from this document.

j 4.1 PRESSURE-RETAINING WELDS IN RPV (CATEGORY B-A) 5 Items 81.10. B1.11. 81.12 - Shell Welds (Section XI requirements) i Scope of Examination 100% of one beltline region longitudinal and one beltline region i

circumferential shell weld (does not include the shell to flange weld which is item B1.30).

Examination Schedule End of Interval (EOl)

} Discussion Through a change to 10CFR50, the NRC has imposed an augmented examination i program for the reactor pressure vessel shell welds. The program requires examination of each of j the shell welds (longitudinal and circumferential) by the end of the second inspection interval. Due to plant design, access to these welds is impractical from outside of the vessel, therefore, the

, examinations are planned to be performed from the inside of the vessel. Examination of 100% of 1

the length of these welds may not be achievable. Examination limitations will be identified in Relief Request RR-01, and submitted to the NRC for approval.

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t Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Page 27 of 51 Items B1.20. B1.21. B1.22 - Bottom Head Wolds Scope of Examination - 100% of accessible length of one circumferential and one meridional head weld.

Examination Schedule - End of Interval (EOI)

Discussinn - Meridional and circumferential seam welds in the bottom head will be considered individually for physical accessibility and radiation levels.

Items B1.20. B1.21. 81.22 - Too Hood Wolds Scope of Examination - 100% of the accessible length of one circumferential and one meridional head weld.

Examination Schedule - Interval Distribution (ID)

Discussion - The welds on the closure head are accessible for volumetric examination when the head is removed for refueling.

Item B1.30 - Shell to Flance Weld Scope of Examination - 100% of the shell to flange weld.

< Examination Schedule -

1. Interval Distribution (ID) or

2. First Period (1P) and Third Period (3P)

a. First Period Minimum 50% of the total weld length,

b. Third Period Remainder of weld length not performed in first period, so that 100%

i of weld length has been examined.

Discussion This weld will be examined ultrasonically from the seal surface using straight beam 4

examination tschniques as an altemative examination technique as provided by IWA-2240.

Examination from the shell side of the weld will be performed during the third period.

4 item B1.40 - Head to Flance Wold Scope of Examination - 100% of head to flange weld.

Examination Schedule - Interval Distribution (ID)

Discussion This weld is available for UT and MT Examination when the head is removed for refueling.

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Page 28 of 51 item B1.50. B1.51 - Repair Wolds Scope of Examination One weld repair area.

Examination Schedule End of interval (EOl)

Discussion For material (base metal) weld repairs in the beltline region, where the repair depth exceeds ten percent nominal of the vessel wall, one (1) repair weld area will be examined once per inspection interval. If the location of the weld repair is not accurately known, then the individual shell plate, forging, or shell course containing the repair shall be included.

4.2 FULL PENETRATION WELDS OF NOZZLES IN THE RPV - INSPECTION PROGRAM B (CATEGORY B-D)

Note: Inspection Program A is not applicable to the PBAPS 2 & 3 ISI Program, item B3.90 and B3.100 - Reactor Vessel Full Penetration Nonle Welds Scope of Examination - 100% of all nozzle to vessel welds and nozzle inside radius sections.

Examination Schedule (a) ist Period (1P) - At least 25% but not more than 50% of the nozzles.

(b) 2nd Period (2P) See 3rd Period (c) 3rd Period (3P) The remainder of nozzles examination must be completed by the end of the 3rd Period.

Note: Exam schedule for the above is indicated in the ISI Program Table as IP,3P.

Discussion - These RPV nozzle welds are accessible for UT examination from the outside surface of the RPV when the surrounding sections of the sacrificial shield and insulation are removed.

However, due to component configuration (nozzle forging design), a complete Code examination is not practical. See Relief Request No. RR 13.

4.3 PARTIAL PENETRATION WELDS IN THE RPV (CATEGORY B E) ltems B4.11. 54.12. B4.13 - Partial Penetration Welds Scope of Examination - Visually examine 25% of all nozzles within each of the following categories:

Item B4.11 - Vessel Nozzles item B4.12 - Control Rod Drive Nozzles item B4.13 - Instrumentation Nozzles Examination Schedule Interval Distribution (ID)

Discussion - A VT-2 examinat!on will be conducted for evidence of leakage of partial penetration welds in the RPV in accordance with IWA 5240. The examinations will be performed when the RPV la pressurized prior to operation.

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i Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program i Page 29 of 51 4

1 4.4 DISSIMILAR METAL WELDS (CATEGORY B-F) j ltem B5.10. B5.20 - Reactor Vessel Dissimilar Metal Butt Wolds Scope of Examination - 100% of all nonle to safe-end butt welds that meet the dissimilar metal requirements.

Examination Schedule

1. Interval Distribution (ID) or

2. Perform at the same time as the adjacent nonle to vessel welds, Category B-D, (see Paragraph 4.2).

Discussion - There is a dissimilar metal weld between the carbon steel nonle forgings and the piping system on some of the RPV nonles. Access to these dissimilar metal welds will be provided for in the same manner as for the nonle-to-vessel primary welds (Category B-D).

item 85.30 - Reactor Vessel Dissimilar Metal Socket Wolds Not applicable to PBAPS 2 & 3. There are no Reactor Vessel nonle-to-safe end dissimilar metal j socket welds.

, 4.5 PRESSURE-RETAINING BOLTING GREATER THAN 2" DIAMETER (CATEGORY B-O-1)

Item 86.10. B6.20. B6.30. 86.40 and B6.50 - Reactor Vessel Boltina Scope of Examination - All closure head nuts (B6.10), studs (B6.20, B6.30), threads in flange holes (B6.40), closure washers, and bushings (B6.50). Bushings and threads in flange holes only require examination in the event the connection is disassembled.

Examination Schedule Each of the following

1. End of Interval (EOl) - Closure head nuts and washers. Closure head studs shall be examined when removed. I

2. Disassembly (DISS) - Threads in flange hdes and bushings only.

Discussion - The closure head nuts, when removed, will be volumetrically examined as an .

' altemative to a surface examination in accordance with IWA 2240. Closure head studs which are not removed will be subject to a volumetric examination in place. Not all of the closure studs are scheduled to be removed during any one refueling. However, during the course of the Interval, all l studs which are removed will be subjected to both volumetric and surface examination.

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Page 30 of 51 4.6 PRESSURE RETAINING BOLTING LESS THAN OR EQUAL TO 2" DIAMETER (CATEGORY B G-2)

Item 87.10 - Reactor Vessel Boltina Not applicable to PBAPS 2 & 3. There is no Reactor Vessel pressure retaining bolting less than or equal to 2' in diameter.

Item B7.70 - Bolts. Studs. and Nuta Scope of examination All bolts, studs, and nuts in certain selected Class 1 valves. That is, for valve bolting, studs, and nuts, examina*Jons are limited to the valves selected under Category B-M-2 (i.e., one valve under a group of val':es which are greater than 4 inch and of the same size, constructional design, and manufacturing method, and that perform similar system functions).

Examination Schedule Interval Distribution (10).

Item B7.80 - CRD Housine Boltina Scope of Examination - All bolts, studs, and nuts on CRD housings.

Examination Schedule - Only examined when disassembled (DISS).

4.7 INTEGRALLY WELDED ATTACHMENTS TO VESSELS (Category B H)

PBAPS 2 & 3 has adopted Code Case N-343 which limits examinations of this category to integrally welded attachments that meet the following corditions:

J, a) the attachment is on the outside surface of the pressure retaining components b) the attachment provides component support as defined in NF 1110 l c) the attachment base material design thickness is 5/8 in, or greater and d) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the component.

Weld buildup on nozzles that is in compression under normal conditions and provides only component support is excluded from examination.

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l Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program l Page 31 of 51  ;

item B8.10 -Intecrolly Welded Attachments to Reactor Vessel I

Scope of Examination 100% of the RPV support skirt weld, and stabilizer bracket attachment welds, i

I Exarnination tichedule - Interval Distribution (ID)

Discussion Category B-H requires a volumetric or surface examination method be utilized, as applicable. Volumetric examination of the PBAPS RPV integral attachment weld configurations is not practical; therefore, surface examination shall be performed on the RPV support skirt and stabilizer bracket attachment welds.

4.8 PRESSURE RETAINING WELDS IN PlPING (CATEGORY B-J) ltems B9.11. 89.21. and 89.40 - Circumferential/ Socket Wolds Scope of Examinations 25% of all nonexempt circumferential butt welds and socket welds per the 74S75 Edition of Section XI.

Examination Schedule Interval Distribution (ID)

Discussion - Piping welds in this Category included with the reactor pressure vessel examinations are those welds outboard of the vessel nozzles which are gt associated with another system within the ISI boundaries (e.g. head vent line, instrumentation lines, , . .)

4.9 RPV INTERIOR SHELL AND CORE SUPPORT STRUCTURE (CATEGORY B-N-1 and B-N-2)

Item B13.10. B13.20. B13.21. and B13.22 Scope of Examination - All accessible surfaces of the vessel shell interior surfaces and critical intemal components (B13.10), vessel interior attachment welds (B13.20, B13.21) and core support structure surfaces (B13.22).

Examination Schedule Each of the following:

1. Refueling Outages (RO) All surfaces of the vessel shell interior and intemal components (B1310) made accessible by removal of components during a refueling outage shall be examined during the 1st refueling outage and every other refueling outage thereafter (approximately once per period).

2. End of interval (EOl) Applicable to interior attachment welds (B13.20, B13.21) and the Core Support Structure (B13.22) only.

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Page 32 of 51 4.10 CONTROL ROD DRIVE PRESSURE RETAINING WELDS (CATEGORY B-0) ltem B14.10 Reactor Vessel CRD Housino Welds Scope of Examination - Pressure-retaining welds in 10% of the peripheral CRD Housings Examination Schedule - End of Interval (EOI)

See Reference 1.1.3a for calculation /]ustification.

4.11 PRESSURE TESTING (CATEGORY B-P)

ITEM B15.10. B15.11 Reactor Vessel Pressure Retainino Boundarv

See Section 8.1 5.0 CLASS 1 WELDS. BOLTING. AND COMPONENT EXAMINATIONS (EXCLUDING THE RPV) i This section applies to Class 1 welds, botting, and component examinations other than the RPV.

Examinations applicable to the RPV are discussed in Section 4.0. Code examination categories and/or item numbers which apply exclusively to pressurized water reactor (PWR) plants are specifically excluded from this document.

5.1 DISSIMILAR METAL WELDS (CATEGORY B-F)

Item 85.150 - Dissimilar Metal Socket Welds Not applicable to PBAPS 2 & 3. There are no Class 1 dissimilar metal socket welds in the system

, design.

Item B5.130 and 85.140 - Pipino Dissimilar Welds Scope of Examination All dissimilar metal nonexempt pipe welds.

4 Examination Schedule Interval Distribution (ID)

Discussion - This category applies to dissimilar metal welds in piping systems. This includes combinations of carbon or low alloy steels to high alloy steels, carbon or low alloy steels to high nickel alloys, and high alloy steels to high nickel alloys.

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Page 33 of 51 5.2 PRESSURE RETAINING BOLTING GREATER THAN 2" DIAMETER (CATEGORY B-G-1) ltems B6.150 throuah B6.170 and B6.210 throuah B.230 Boltina in Pipina and Valves Not applicable PBAPS 2 & 3. There is no Class 1 bolting greater than 2* diameter for piping or valves utilized in the system design.

Item B6.180, B6.190. and B6.200 - Boltina in Pumps Scope of Examination All studs, bolts, nuts, bushings, and washers. Should the flanged connection be disassembled, the bushings and threads in flange stud holes and 1* a?~.,ar surface of the flange surrounding stud or bolt shall be examined.

The examination of bolting may be limited to the pump selected for examination under B-L 2 as allowed by Code Case N 419. Category B-L 2 permits the application of the multi-component concept for pumps.

Examination Schedule

1. Disassembly (DISG) - Bushings and threads in flange stud holes and flange surfaces only, and

2. End of Interval (EOI) - Bolts, studs, nuts, and washers.

Discussion The Reactor Recirculation Pumps are the only Class 1 pumps. Examinations of bolts, studs, nuts and washers will be performed on only one recirculation pump on each unit.

Examination of bushings and threads in flange stud holes and flange surfaces will be performed whenever a pump is disassembled.

5.3 PRESSURE RETAINING BOLTING LESS THAN OR EQUAL TO 2" DIAMETER (CATEGORY B-G-2) item B7.60 - Boltina in Pumos Not applicable to PBAPS 2 & 3. There are no Class 1 Pumps which contain bolting 2* diameter or less.

Item B7.50 and B7.70 - Boltina in Pipina and Valves Scope of examination - All bolts, studs, and nuts. For vatves, Code Case N-426 allows the bolting examinations to be limited to valves selected for examination under B-M-2. Category B-M-2 permits the application of the multi-component concept for vatves. For piping, the bolting requiring examination is bolting in piping required to be examined under B J.

Examination Schedule

1. Interval Distribution (ID) Piping

2. Disassembly (DISG) Valves Discussion - Valves which do not have pressure retaining bolting are listed in Category B-M-2 section of the ISI Program table with a note indicating no pressure retalning bolting.

Specification M-733, Rev. 2 PBAPS 2 & 3 m ISI Program Page 34 of 51 5.4 PRES 8URE RETAINING WELDS IN PIPING (CATEGORY 8-J) ltems 89.10 through 89.40 Scope of Examinations - 25% of all nonexempt circumferential and branch connection pipe welds per the 74S75 Edition of Secten XI (Reference Section 2.2.1). All longitudinal pipe welds Intersecting any of the selected circumferential welds shall also be examined for a length of at least one pipe diameter, but not more than 12 inches.

Examination Schedule Interval Distribution (10)

Discussion - Welds selected for examination represent areas expected to experience higher stresses. If system modifications result in an increase to the weld population, a representative sampling criteria, with considerations to ALARA, access, geometry, stress levels, etc., will be used to select the required additional welds.

5.5 INTEGRAL ATTACHMENTS (CATEGORY B-K-1)

PBAPS 2 & 3 has adopted Code Case N-343 which limits examinations of this category to integrally welded attachments that meet the following conditions:

a) the attachment is on the outside surface of the pressure retaining components b) the attachment provides component support as defined in NF 1110 l

c) the attachment base material design thickness is 5/8 in. or greater and d) the attachtnent weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the component.

A surface examination is planned for integral attachments in this category. However, a volumetric examination may be used if the integral attachment has a full penetration weld to an appurtenance of the component, as allowed by ASME Section XI, Figure IWB 250014.

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item B10.30 - Intearel Attachments to Valves Not applicable to PBAPS 2&3. There are no integral attachments to Class 1 valves in the plant

design.

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1 Specification

, M 733, Rev. 2  ;

PBAPS 2 & 3 ISI Program Page 35 of 51 ltem B10.10 and 810.20 - Intearal Attachments to Pipina and Pumps Scope of Examination The examinations include only the welded attachments to piping required to be examined under Examination Category B-J and the welded attachments to pumps associated with this piping. The multi-component concept is not applicable to this examination category. This 1

is interpreted to mean 100% of all Class 1 Integrally welded attachments with a base material design thickness of 5/8' or greater.

Examination Schedule Interval Distribution (10)

Discussion Integral attachments to piping include not only attachments associated with component supports, but also attachments associated with piping at containment penetrations. The Class 1 nonexempt piping containment penetrations at PBAPS 2 & 3 are of a forged design as shown in Section XI, Figure IWB 2500-14. The surface exams required by B K 1 need only be performed on welds that are within a region that is 't' inches from the pressure retaining component, where 't* is the wall thickness of the pressure-retalning component (the piping in this case). At PBAPS 2 & 3, none of the Class 1 nonexempt piping containment penetrations have welds that are within this region.

Containment penetrations N 7A-D,9A & 8,11,12,13A & B,14,16A & B, & 17 are the expansion bellows type in which the process pipe passes inside a guard pipe. Spacer lugs are welded to the outside of the process pipe and to the inside of the guard pipe. These lugs do not provide component support as defined in ASME Section ill NF 1110 and are therefore not subject to examination.

2 5.6 PRESSURE RETAINING WELDS IN PUMP CASINGS (CATEGORY B L-1) l ltem 812.10 - Pumo Casino Welds 1

There are no pressure-retaining welds in pump casings that fall under Category B-L-1. There are window welds in the recirculation pump casing, but they are not a weld joint as defined in Figure IWB 250016, but rather a core closure weld in a casting Per IWA 2500, these welds are not required to be examined under Category B-L-1.

5.7 INTERNAL PRESSURE-RETAINING SURFACES OF PUMP CASINGS (CATEGORY B-L-2) d item B12.20 Pumo Casinos Scope of Examination Multi-component concept is applicable; le., only the interior surface of one recirculation pump requires examination.

Examination Schedule DISG Discussion - The only pumps in this category subject to examination are those in the Reactor Recirculation System. VT 3 examinations will be scheduled and performed when the pumps are disassembled for maintenance purposes per Relief Request RR-02.

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f Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Page 36 of 51 5.8

] PRESSURE-RETAINING WELDS IN VALVE BODIES fCATEGORY B-M 1)

!, ltem B12.30 and B12.40 Valve Body Welds Not applicable to PBAPS 2 & 3. There are no valve body welds.

5.9 INTERNAL PRESSURE RETAINING SURFACES OF VALVE BODIES (CATEGORY B-M-2) i ltem B12.50 - Valve Body 4

Scope of Examination Multi-component concept is applicable; however, it is supplemented by the requirement that examinations are limited to one valve within a group of valves that are of the same functional design (globe, gate, check), manufacturing method, and that perform similar functions

within the syetem.

< Examination Schedule DISG i Discussion - The examination of the intemal surfaces of the valve bodies will be performed when the valves are disassembled for maintenance purposes per Relief Request RR-03.

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) 5.10 PRESSURE TESTING (CATEGORY B-P) 1 Items 815.50 throuah B15.71 i

See Section 8.1

6.0 CLASS 2 WELDS BOLTING. AND COMPONENT EXAMINATIONS 3

6.1 PRESSURE RETAINING WELDS IN CLASS 2 PRESSURE VESSELS (CATEGORY C-A)

Item C1.20 and C1.30 - Need Circumferential and Tubbeet to Shell Wolds s

1 Not applicable to PBAPS 2 & 3. There are no welds of this type utilized at PBAPS.

Item C1.10 - Shell Circumferential Welds Scope of Examination Examination of 100% of the weld length of shell circumferential welds at a gross structural discontinuity, such as a shell to flange weld. Multi-component concept is applicable, in that the requirements may be limitml to one vessel or distributed among vessels of

! similar size, design, and service. The only Class 2 vessels that are in scope for this examination

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category are the RHR Heat Exchangers. These Heat Exchangers qualify for the multi-component approach.

Examination Schedule - Interval Distribution (10) j Discussion The shell circumferential welds on the selected RHR Heat Exchanger will be examined to the extent possible as described in Relief Request RR-08. There is a circumferential weld located approximately at the center of each RHR Heat Exchanger, however this weld is not a structural discontinuity.

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I Specification M-733 Rev. 2 PBAPS 2 & 3 ISI Program Page 37 of 51 8.2 PRESSURE-RETAINING NOZZLE WELDS IN VESSELS (CATEGORY C-8) home C2.10 throuah C2.22 - Nosalee Not applicable to PBAPS 2 & 3. Plant design does not utilize noules within these categories.

home C2,31 and C2.32 - Nozzles Scope of Examination All nozzles integrally welded or cast to vessels which are connected to piping examined under Examination Category C F. Examinations shall include nozzle to shell, reinforcing plate to nozzle, and reinforcing plate to vessel weids, The multi-component concept is applicable.

Dimenanlan - The nozzle to shell wolds are inaccessible for examination from inside the vessel, therefore, the tell tale hole in the reinforcing plate shall be examined for leakage during the system pressure test VT 2 examination.

Examination Schedule - Interval Distribution (10) 8.3 INTEGRAL ATTACHMENTS TO VESSELS, PIPING AND PUMPS (CATEGORY C-C) ltem C3.40 - Valves Not applicable to PBAPS 2 & 3. There are no integral attachments to Class 2 valves.

PBAPS has adopted code case N 343 which limits the examinations of this category to integrally welded attachments that meet the following requirements:

(a) the attachment is on the outside surface of the pressure retaining component; (b) the attachment provides component support as defined in NF-1110;

(c) the attachment base material design thickness is 3/4 in, or greater; and (d) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the component. '

Items C3.10. C3.20 and C3.30 Pr====e V^= Mis. Ploina, and Pumne

! Scope of Examination 100% of allIntegral attachments to vessels, piping and pumps. The j multi-component concept may be applied to vessels.

S Examination Schedule Interval Distribution (10) 4 8.4 i- PRESSURE RETAINING BOLTING GREATER THAN 2" DIAMETER (CATEGORY C D)

\ This category is not applicable to PBAPS 2 & 3. Plant design does not utilize pressure retaining bolting greater than 2 inches in diameter.

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1 Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program l Page 38 of 51 6.5 CLASS 2 PRESSURE RETAINING PtPE WELDS (CATEGORY C-F)

FTEMS C5.10 throuch C5.32 - Ploe Wolds I The extent of piping welds to be examined will be determined by the 74S75 Edition of Section XI (Reference Section 2.2.1). The 74S75 Edition has two categories for pipe welds, C-F l and C.G, however PBAPS has elected to categorize all Class 2 piping welds Category C-F. This is a more conservative approach since Category C-F requires a larger percentage of welds to be examined than Category C-G. The weld selection basis is provided in Section 3.5.1. The parts examined and the examination method is determined by the 80W81 Edition of Section XI.

Scope of Examination Nonexempt pipe welds include all circumferential pipe welds and branch connection welds (>4' NPS) located on nonexempt piping. For piping systems or portions of systems, that consist of a single train; 25% of the nonexempt pipe welds shall be examined. All longitudinal pipe welds intersecting any of the selected circumferential welds shall also be examined for a length of at least 2.5T.

i.e. Total welds = 100 x 25% = 25 welds examined.

For piping systems or portions of systems that consists of more than one train (multi train); 25% of the total number of nonexempt welds in all the trains divided by the number of trains, shall be examined.

i.e. Train A welds = 50 Train B welds = 54, Total A & B = 104 + 2 = 52 x 25% = 13 welds examined Examination Schedule - Interval Distribution (10)

In addition, all longitudinal pipe weids intersecting a selected circumferential pipe weld shall also be examined.

Discussion - If system modifications result in an increase in the weld population, a representative sampling criteria with considerations to ALARA access, geometry, etc. will be used to select the required additional welds.

6.6 PRESSURE RETAINING WELDS IN PUMPS AND VALVES (CATEGORY C G)

This category is not applicable to PBAPS 2 & 3. There are no pressure retaining welds in the Class 2 pumps or valves.

6.7 PRESSURE TESTING (CATEGORY C-H)

See Section 8.2 7.0 CLASS 3 COMPONENT EXAMINATIONS Pressure testing for Categories D A, D-B, and D-C is discussed in Section 8.3.

_ _ - _ - - _ _ _- . - - - - . - - - - . -- - - - - - .~ . . - . . - - _ - . .

Specification M 733, Rev. 2 PBAPS 2 & 3 l ISI Program a

Page 39 of 51

7.1 CLASS 3 INTEGRAL ATTACHMENTS (CATEGORIES D A, D 8, AND D C)

The selection basis for this Examination Category is addressed in Section 9.0 Component j Supports, Paragraph 9.3.3, since the examination scope consists of integral attachments i l corresponding to component supports that are selected to be examined under IWF of Section XI, i

per Note 3 of Tables IWD-25001 Examination Category D-A, D-B, and D-C.

j 8.0 PRESSURE TESTING j All pressure retaining components within the ASME Classification boundaries are subject to periodic pressure testing in accordance with Section XI, IWA-5000 and Code Case N498. In addition, j certain repairs, replacement, and modifications of ASME classified and associated components are

subject to pressure testing prior to resumption of service.

1 j 8.1 CLASS 1 PRESSURE TEST PROGRAM 8.1.1 Pressure Test Reauirements (Table IWB ?M1 CNrv B-P) l items B15.20 throuch 815.41 t

Not applicable to PBAPS 2 & 3. Items B15.20 through B15.31 pertain to a PWR.

! PBAPS 2 & 3 does not utilize Class 1 Heat Exchangers applicable to items B15.40 and B15.41.

4 items B15.10. B15.11. B15.50. B15.51. B15.60. B15.61. B15.70. and 815.71 i

j Scope of Examination - All extemal portions of piping. pumps, valves, and the reactor vessel 4

(including nozzles and safe ends) should be examined concurrent with a leakage test and/or hydrostatic test.

It should be noted that there are no exemptions applicable to the pressure test requirements of this l examination category. However, attemative test methods are allowed as described in Section XI, Article IWB-5000.

Examination Schedule

1. Refueling Outages (RO) - Examination concurrent with a leakage test.

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2. End of Interval (EOl) - Examination concurrent with a hydrostatic test.

8.1.2 System Leekane Test Class 1 components will be subjected to a system leakage test of IWB-5221 prior to startup, following each reac1or refueling outage at a test pressure not less than system nominal operating pressure (Reference Para.1.2.19) associated with 100 percent rated reactor power at the Reactor Vessel Top Head Flange. The tests scheduled to be performed during the second 10-year interval l are shown in Table 8.1 1.

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i Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Page 40 of 51 8,1.3 System Hydrostatic Test Class 1 components will be subjected to a system hydrostatic test or altemative test at or near the end of the inspection Interval. In accordance with Code Case N 498, the system is pressurized to nominal operating pressure for at least four (4) hours for insulated systems and ten (10) minutes for noninsulated systems. The nominal operating pressure shall be maintained during the performance of the VT 2 visual examination at the corresponding test temperature derived from the plant technical specifications. The tests scheduled to be performed during the second 10-year interval are shown in Table 8.1 1.

Certain portions of Class 1 systems, by virtue of plant design, cannot adequately be hydrostatically tested with the balance of the Class 1 boundary. The Code requirements, however, may be satisfied by inclusion of these portions of piping into the Class 2 test boundary and testing at a higher (Class 2) test pressure.

TABLE 8.11 CLASS 1 SYSTEM PRESSURE TESTS System System Leakage Test System Hydrostatic Test Main Steam See Footnote (1) See Code Case N-498 or RR-04 Main Recirculation See Footnote (1) See Code Case N 498 or RR-04 Feedwater See Footnote (1) See Code Case N 498 or RR-04 Residual Heat See Footnote (1) See Code Case N-498 or RR-04 Removal Reactor Water See Footnote (1) See Code Case N-498 or RR-04

Cleanup 4

Reactor Core See Footnote (1) See Code Case N-498 or RR-04 Isolation Cooling Core Spray See Footnote (1) See Code Case N-498 or RR-04 High Pressure See Footnote (1) See Code Case N-498 or RR-04 Injection Coolant Standby Liquid See Footnote (1) See Code Case N-498 or RR-04 Control Control Rod Drive See Footnote (1) See Code Case N-498 or RR 04 Hydraulb System (2)

(1) Nominal Operating Pressure associated with 100% rated reactor power is defined as the range of pressure between 980 psig and 1035 psig.

(2) For purposes of this inservice inspection program, this system has been upgraded to Class 1, consistent with what was accomplished in the first ISI interval.

i Specification l

M 733, Rev. 2 i

PBAPS 2 & 3

' ISI Program Page 410151 8.2 CLASS 2 PRESSURE TEST PROGRAM 8.2.1 Pressure Test Reauirements (Table IWC-25001 Cate v C-H) ltems C7.10. C7.20. C7.30. C7.40. C7.50. C7.80. C7.70. and C7.80 Scope of Examination - All extemal portions of pressure vessels, piping, pumps, and valves shall be examined concurrent with both inservice or functional tests and the hydrostatic test.

Examination Schedule 1, 1st Period (1P) 100% examination of the systems concurrent with an inservice or functional test.

2. 2nd Period (2P) - 100% examination of the systems concurrent with an inservice, functional, or hydrostatic test.

3. 3rd Period (3P) - 100% examination of the systems concurrent with an inservice, functional, or hydrostatic test required at or near the end of the inspection interval.

Note: An Inservice or functional test is required each period. However, this requirement is waived in the period that the hydrostatic test is performed. A hydrostatic test must be performed at least once during the ten-year interval, either in the 2nd or 3rd period. ,

8.2.2 System inservice or Functional Test )

Class 2 components will be subjected to the system inservice or functional test requirements of IWC 5200. The tests scheduled to be performed during the second 10-year interval are shown in Table 8 9.1.  !

For those Class 2 systems which normally operate, an inservice test shall be performed while at normal operating pressure. For those Class 2 systems which do not normally operate, a functional test shall be performed at the pressure associated with the quarterly surveillance test. In all cases, only the boundary under pressure shall be VT 2 examined. 1 I

8.2.3 System Hydrostatic Test )

l Class 2 components will be subject to the system hydrostatic test requirements of IWC-5222 or attemate tests per Code Case N-498. The tests scheduled to be performed during the second 10-year interval are shown in Table 8.21 In accordance with IWC-5222 (c), open-ended portions of nonclosed systems extending to the first shutoff valve are exempted from the test requirements of IWC-5000. Examples of this exemption include suction lines from the torus, test lines, and minimum flow recirculation lines which discharge to the torus, containment spray lines, torus spray lines and turbine exhaust lines to the torus. For these lines, demonstration of an open flow path will be performed in lieu of pressure testing in accordance with IWC-5222 (d) l

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Specification M 733. Rev. 2 PBAPS 2 & 3 ISI Frogram Page 42 of 51 TABLE 8.21 CLASS 2 SYSTEM PRESSURE TESTS System inservice or System Hydrostatic Test (2)

System Functional Test Core Spray Cooling See Footnote (1) See Footnote (2)

High Pressure Coolant See Footnote (1) See Footnote (2)

Injection Reactor Core Isolation See Footnote (1) See Footnote (2)

Cooling Standby Liquid Control See Footnote (1) See Footnote (2)

Residual Heat Removal See Footnote (1) See Footnote (3)

CRD Scram Discharge See Footnote (1) See Footnote (2)

Volume Piping Main Steam See Footnote (1) See Footnote (2)

.Ngigs (1) System inservice or functional tests will be performed in accordance with paragraph 8.2.2, with examination per IWA-5000.

(2) System hydrostatic tests requirements will be satisfied using Code Case N-498 during the second 1

or third inspection periods. The boundary subject to test pressurization shall extend to all Class 2 components required to operate or support the safety system function up to and including the first normally closed valve.

(3) VT 2 examine weep holes in reinforcing plates on selected RHR Heat Exchanger nozzles per IWC-25001, Category C 8, item C2.32.

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, 8.3 CLASS 3 PRESSURE TEST PROGRAM

' 8.3.1 Pressure Test Reauirements (Table IWD 2aan-1: C#eeerles D A. D 8 and D-C) l Category D-A is not applicable to PBAPS 2 & 3 since there are no Class 3 systems in support of the reactor shutdown function.

4 l-items D1.10. 2.10 and 3.10 I

t Scope of Examination All extemal portions of pressure vessels, piping, pumps, and valves shall be examined concurrent with both inservice or functional tests and the hydrostatic test.

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Specification M 733, Rev. 2 Addendum 1 P8APS 2 & 3 ISI Program Page 43 of 51 Time Frame

1. 1st Period (1P) 100% examination of the systems concurrent with an inservice or functional test.

2. 2nd Period (2P) 100% examination of the systems concurrent with an Inservice, functional, or hydrostatic test.

3. 3rd Period (3P) 100% examination of the systems concurrent with an inservice, functional, or hydrostatic test required at or near the end of the inspectioi: Interval.

Note: An Inservice or functional test is required each period. However, this requirement is waived in the period that the hydrostatic test is performed. A hydrostatic test must be performed at least once during the ten year interval, either in the 2nd or 3rd period.

8.3.2 System inservice or Functional Test Class 3 components will be subjected to the system inservice or functional test requirements specified in IWD-5200. The tests scheduled to be performed during the second 10-year interval is shown in Table 8.31.

For those Class 3 systems which normally operate, an Inservice test shall be performed while at normal operating pressure. For those Class 3 systems which do not normally operate, a functional test shall be performed at the pressure associated with the quarterfy surveillance test. In all cases, only the boundary under pressure shall be VT 2 examined.

8.3.4 System Hydrostatic Test Class 3 components will be subject to a system hydrostatic test per IWD-5200 or altemate tests per Code Case N-4981. Code testing will be conducted in accordance with IWD-5223. Buried components will be tested and examined in accordance with IWA-5244. The systems subject to testing and the tests scheduled to be performed during the second 10-year interval are shown in Table 8.31.

Specificatin M 733, Rev. 2 Addendum 1 PBAPS 2 & 3 ISI Program Page 44 of 51 TABLE 8.31 CLASS 3 SYSTEM PRESSURE TESTS System inservice or System Hydrostatic System Functional Test (1) Test Emergency Service Water Normal Operating 110% Normal Operating Pressure Pressuremm, or Code Case 4081 High Pressure Service Normal Operating 110% Normal Operating Water Pressure PressureAA, or Code Case N 4981 Emergency Cooling Water Normal Operating 110% Normal Operating Pressure Pressure **, or Code Case N-4981 Fuel Pool Coolltsg Normal Operating Per IWD-5223(c)&(d)

System Pressure Main Steam Relief Valve Not Required See Relief Request Discharge Piping RR 17 Notes:

4 (1) System inservice or functional test will be performed in periods in which the hydrostatic test is not performed. See Section 8.3.2.

(2) See Relief Request RR 09.

(3) IWD-5223(c), (d), and (e) are applied to portions of these systems.

9.0 CLASS 1,2 AND 3 COMPONENT SUPPORTS EXCLUDING SNUBBER ASSEMBLIES 9.1 GENERAL The ISI program for component supports has been developed in accordance with the requirements of Subsection IWF of the 1980 Edition of Section XI with Addenda through Winter 1981. Details of the examination program for component supports, excluding snubber assemblies (Reference Para.1.2.29 and Figure 9.1 1), are identified in this section.

All non exempt component supports, within the ASME classification boundaries, are listed in the ISI Program Tables and shown on the ISI isometric Drawings. This includes those non-exempt component supports containing snubbers, since portions of these supports are subject to the examination requirements of the ASME Section XI ISI Program. Requests for relief from Section XI requirements are contained in Appendix A.

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' 1 Specification .

M 733, Rev. 2

PBAPS 2 & 3 ISI Program Page 45 of 51 9.2 EXEAFTIONS The same exemptions applied to Class 1,2, and 3 pressure retaining components, as identified in i

Section 2.3, were applied to component supports.

i

! 9.3 EXAMINATION REQUIRERENTS 9.3.1 Examination Catenorles

{,

l ASME Section XI, Table IWF 25001 identifies three Examination Categories for component

! supports: F A, F B, and F C. Each of these Categories contain identical requirements (ie. parts examined, examination method, frequency, etc.) and similar hem Numbers. Category F-C differs slightly, from the other categories, in that it also addresses spring and snubber type supports.

} Because of these simNarttles, this program groups aI component supports into one category, noted i

as F A, B, C, item No. F0.00, on the ISI Tables. In lieu of categottzstion, this program identifies each appilcable component support by furetional type and identifies the examination method (s) l required for each. i 9.3.2 Examination Methods 1 Component support examination requirements include the VT 3 and VT-4 visual examination i methods. The VT 3 method is applicable to all component supports, while the VT-4 method is only

applicable to spring type supports.

j 9.3.3 Class 3 Intearal Attachmenta i

Applicable Class 3 integral attachments to the pressure boundary require VT-3 examination during ISI. Although the examination of Class 3 integral attachments is actually an IWD requirement, tids section of the ISI Program addresses the examination of integral attachments. Integral attachments

! are normally considered a part of the pressure-retaining component rather than the component i support, but for Class 3 attachments, there are two logical reasons for including them in the IWF i

Section of the ISI Program. The first reason is because the method of examination is the same as

! that for the support (ie. VT 3); secondly, the integral attachments selected for examination are those i associated with the supports selected for examination. This is in accordance with Note 3 of Table i IWD 25001, Examination Category D A, D-B, and D-C in Section XI.

~

3

{ Note 3 states:

l " ....

The integral attachments selected for examination shall correspond to those component i supports selected by IWF 2510(b)."

Therefore, the ISI Program Tables list all integral attachments to non-exempt Class 3 components, while indicating a VT 3 examination requirement for only those associated with component supports

! selected for examination.

3 i

, - . -.i,-,,.v, - - - , . - . - .

Specification M 733, Rev. 2 PBAPS 2 & 3

I ISI Program Page 46 of 51 9.4 SEl.ECTION SASIS r 9.4.1 General Corrponent supports, per IWF 1100, are considered to be "...those metal supports designed to transmit loads from the component and piping to the load carrying building or structure. This shaN j include the attachment portion of intervening element (s) to pressure-retaining components, 4

... Component supports can also be referred to as anything that supports, hangs, restrains, or

} anchors pressure-retaining components such as, piping, valves, pumps, vessels, heat exchangers, j etc.

The ISI Program Tables lists all component supports of Class 1,2, and 3 nonexempt pressure-retaining pipe and components at PBAPS 2 & 3. Those that are required to be examined j during the second 10-year interval include; all supports on single train systems or portions of systems, and all supports on one train of a mukiple-train system or portion of system.

l 9.4.2 heuttiTrain Concent This Program incorporates the mutkorr1ponent concept specified in Section XI, IWF 2510(b). This paragraph states:

"For multiple components within a system of similar design, function and service, the supports of only one of the mutiple components are required to be examined" f

In the above paragraph, ' components' are considered to be either piping, vessels, pumps, etc., as i

defined in IWA 2110(h) of Section XI. This Program refers to a grouping of these Rems as trains, where a mutiple train is more than one component, piping run, etc., of similar design, function, and l service.

, Systems containing multiple trains are identified by an alpha suffix in the drawing number of the j .

ASME Section XI ISI isometric drawing, which depicts that system. All non-exempt supports on a 1

single train require examination during ISI, while the supports of only one train of a mutiple train l system require examination. For multiple trains, the train with the most supports shall be selected.

l if alllines of a multiple train have the same number of supports, the train selection is random.

! 9.4.2.1 Single / Multiple Train Rules

The following rules are used to determine train multiplicity

I -

A multiple train is considered to be two or more runs of piping and associated components

with a similar function and flow path between identical components (vessels, pumps, etc.).

2 Determination of the number of trains in a multi-train piping systems is based on the entire system. If the system has four sections and only two discharges the system would be  !

considered a two train system.

l j Corresponding branch lines off each loop of a mult$le train system are considered part of

! the parent train.

q l -

Corresponding branch lines off each loop of a multhie train system which combine into i

, headers, lesser in number than the number of loops in the main system, are considered j additional trains in that system, from the point where such headers begin.

f 1

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s Specification M 733, Rev. 2 i

PBAPS 2 & 3 ISI Program Page 47 of 51 FIGURE 0.1 1 SEE SECTION 9.0 OF THE ISI PROGRAM 1

SNUBBER ASSEMBLY

= = =  : :  :

""" SEE RELIEF REQUEST 10 AND 4

AUGMENTED PROGRAM S S

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i FIGURE 9.1-1 j

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Page 48 of 51 Example: 4 corresponding branch lines, each extending from a separate loop of a 4 loop system, combining into 2 headers, each supporting 2 of the branch lines, the headers are considered as additional trains in that system.

4 Branch lines off only one loop of a multhis train system are mnsidered as a single train branch.

Where multple lines enter a common header, the header is considered a single train.

, 9.5 EXAMINATION IMPLEMENTATION All component support examinations and Class 3 integral attachment examinations will be performed utlilzing the Interval Distribution (ID) method of implementation.

10.0 ISI PROGRAM TABLES The ISI Program Tables, contained in this document, present an itemized listing of all nonexempt components which are subled to examination, (selected and non-selected) under the rules of ASME Section XI. Further, these tables identify which cornponents have been selected for examination and provide general guidance for the scheduling of the subject examinations.

Additionally, they provide reference to important pieces of infonnation which apply to some of the 4

listed components (i.e. relief requests, augmented requirements, etc.).

The content of the electronic data file which is used to create the ISI Program Tables is maintained by a specific revision control mechanism.

f

~

The ISI Program Tables are presented in two, slightly different formats, as follows: l

l The first format contains the tables for the Reactor Pressure Vessel (RPV) exclusively. These tables are sorted alpha-numerically by Code Category, Code item Number, and Examination Area '

ID Number.

i The second format is used for all remaining ISI Program Tables. These tables are sorted by

, system and (reference) drawing number, whereby all components (i.e., welds, bolting, equipment l and corrponent supports) which are depicted on a specific drawing are grouped and listed for that  !

drawing, within the system.

l Finally, in addition to the ISI Program Tables, Augmented Program Tables are contained in this document. Augmented requirements have been addressed in the augmented ir,5pection programs of Appendix B. These tables provide an alpha numeric listing of components subject to specific augmented programs and provide additional information necessary to define the applicable program.' )

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, l

Specification M 733, Rev. 2 PBAPS 2 & 3

ISI Program Page 49 of 51 10.1 ISI PROGRAM TABLE FIELDS DESCRIPTION The ISI Program Tables for PBAPS 2 & 3 are located in the tables section of this document. A sample table (Figure 10.11) and a brief description of each data field are given below.

J Figure 10.1 1. Sample Table aL".e"n '=*"A'"sb"'"n&d: ?.il:Fa-s,==: m o =: m oma

, CA exAnsuaAnom g AesseAnces les ess netone

• ^

E m E oe E "^ tam""su"" " E saEens a E M E eEn E m on a m rm a m ne nie on on (1) System - The system name " " ' " " " ' " '"*""*'"

(2) Class - The ASME Section XI Code class.

(3) Drawino - ASME Section XI isometric or other drawing on which the component is depicted.

(4) Section XI Exam CAT and item No. - The specific Code Examination Category and applicable item Number assigned to the component. A plus sign (+) next to the Exam.

Cat., Indicates augmented requirements are applicable to this component.

(5) Examination Area Identification Number - The unique Alpha Numeric or descriptive identifier for the component or portion thereof to be examined.

l (6) Examination Area Description Description of the component identified.

I (7) ISI Examination Method Method of NDE that is required to be performed on the component.

l Where: MT = Magnetic Particle Examination PT = Liquid Penetrant Examination UT = Uitrasonic Examination RT* = Radiograph Examination VT 1 = Visual Examination - 1 VT 2 = Visual Examination - 2 VT 3 = Visual Examination - 3 i

4

• Since UT is the preferred method of volumetric examination, it will normally be specified, however, RT may be performed in lieu of UT.

(7a) Drawino Number the identification number of the drawing which depicts the specific exarnination area. NOTE: Applicable only to the RPV ISI Tables.

(8) ISI Selected This column specifies whether or not (Yes or No) the component is selected for ISI examination in the second interval.

4

1 Specification M 733, Rev. 2 4

PBAPS 2 & 3

ISI Program Page 50 of 51

! (9) Schedulina Reauirements - This column will indicate the schedule for the required

examination. This scheduling la explained in detailin Section 3.5.4. The abbreviations

used in the ISI Tables are shown below; f

1P -

Examine during 1st Period 1 2P -

Examine during 2nd Period 3P -

Examine during 3rd Period 4

1 P, 3P - Examine 25% to 50% during the 1st period and the remainder by the end of the third period.

ID -

Interval Distribution EOl - Examine by End of Interval RO -

Examine during the first Refueling Outage and during subsequent refueling outages at approximately 3 year intervals.

! DISS -

Examine when disassembled l DISG -

Examine only one component within a multi component group when and if disassembly is required for maintenance.

2 -

Examine every 2 refueling cycles.

2/9 -

Examine every 2,9 refueling cycles.

4 -

Examine every 4 refueling cycles.

ID -

Interval Distribution.

RO-ALL- Examine during every refueling outage.

RO1 -

Examine during first refueling outage only.

Note -

See ISI Notes Field.

l (10) ISI Relief Reauest - The identification number of any applicable relief requests.

l j

(11) Auomented Proaram This column identifies which Augmented Program (s) apply to that component. All Augmented Programs are detailed in Appendix B. An example of the augmented program designations follows:

i 1= Augmented Inspection Program-1: NRC Generic Letter 88-01 2= Augmented Inspection Program-2 NUREG 0619 3= Augmented inspection Program l.E.Bulletin 80-13 4= Augmented inspection Program 1.E.Bulletin 80-07, NUREG/CR 3052 i Etc.

i (12) ISI Notes Any additional pertinent information is provided in this space. If the component qualifies for the multi-component concept described in Section 3.5.1.1, the specific q multi-group will be specified in this column.

1 (13) Record Status & Date An entry in this column indicates that some information, associated I with the line item record, has been revised, or the line item record has been added or I deleted.

10.2 AUGMENTED PROGRAMS TABLE FIELDS DESCRIPTION The Augmented Program Tables are also contained in the tables section of this document. A generic sample table (Figure 10.21) along with a brief description of each data field are given below.

Note however, that all fields may not apply to all Augmented Program Tables.

L

Specification M 733, Rev. 2 PBAPS 2 & 3

, ISI Program Page 51 of 51 Figure 10.21, Sample Table Augmented Programs y umeenv eemos narrou atomic pones reanos .uwr a a common *=e.

Aue au. AuemeerreDescenam mu m T

"a"s'"a"""

s m aus aus.mx 7sE e nneman uma uma osanusseseemmecs inacno eensnams name wtweD (Arneasy pannuancy aus.nzmores insce 7xE E nam as m m on a m a m ne mi on on Aus usa 0Poef AueuGNTeDPGOeR4mTM8 na ne

(1) AUG XX. Auomented Prooram Title Indicates the number and program title that applies to the listed components (2) Examination Area ID Number - The unique alpha-numeric descriptive identifier for the component, or portion thereof, to be examined.

(3) Class - The ASME Section XI Code Class, as applicable.

(4) System - The system name within which the component is located.

(5) Drawino Reference - The isometric drawing or figure number on which the component is  ;

1 depicted.

]

(6) ISI Selected - This column specifies whether or not (Yes or No) the component is selected for ISI examination in the second inspection interval.

(7) AUG Proorams identifies all augmented prograrns applicable to an individual component.

(8) AUG XX Selected For a given augmented program XX, this column specifies whether or not (Yes or No) the component is selected for augmented examination.

(9) MG XX Exam Method For a given augmented program XX, this column specifies the NDE method and/or test that is required to be performed per the augmented inspection program.

(1,0) IGSCC Cateoorv The IGSCC category designator (A through F) assigned to the component as defined in NRC Generic Letter 88 01.

(11) AUG XX Exam Frecuency For a given augmented program XX, this column specifies the

[ frequency which the examination / testing is required to be performed. 1 (12) AUG XX Notes For a given augmented program XX, any additional pertinent Information is provided in this space.

(13) Record Status & Date An entry in this column indicates that some information, associated with the line item record, has been revised, or the line item record has been added or I deleted.

(14) AUG XX Report: Auomented Prooram Title The applicable augmented program number and title appear at the bottom of each page.

i

l Specification '

M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix A 1 Page 1 of 2 l l

APPENDIX A - TABLE OF CONTENTS RELIEF REQUESTS Relief Examination  !

Reauest No. Cateoorv Description RR 01 BA Pressure Retaining Welds in Reactor Vessel (Relief Request Rescinded by Generic Action of NRC)

RR-02 BL2 Pump Casings RR 03 8-M 2 Valve Bodies RR-04 B.P Pressure Rataining Components RR 05 B-J Pressure Retaining Welds in Piping RR 06 BK1 Integral Attachments for Piping. Pumps and Valves RR 07 (Relief Request Withdrawn)

' RR 06 CA Pressure Retalning Weids in Pressure Vessels RR-09 DB Systems in Support of Emergency Core Cooling, Containment Heat Removal, Atmosphere Cleanup, and Reactor Residual Heat Removal RR 10 FC Component Standard Supports RR 11 ISI Class 2 Piping and Components Beyond the Last Shutoff Valve in Open Ended Portions of Systems RR 12 Relief Request Denied per NRC Safety Evaluation RR 13 BD Class 1 Full Penetration Welds of Nozzles in Vessels (Inspection Program B)

RR 14 ASME Code Case (s) Authorization Request RR 15 CC Integral Attachments for Vessels, Piping, Pumps, and Valves RR 16 CH Pressure Retaining Components in Pressure Vessels, Piping, Pumps and Valven

RR 17 D A, Class 3 Pressure Retaining Components D-B,

}C

Specification M 733, Rev. 2 Addendum 1 PBAPS 2 & 3 ISI Program Appendix A Page 2 of 2 RR 18 B-H integral Attachments for Vessels RR 19 (Withdrawn) ISI Class 3 Pressure Retaining Components in the Emergency Service l l Water System.

j RR 20 (Withdrawn) Hydrostatic Testing following Repair / Replacements.

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Specification l l

M-733. Rev. 2

. PBAPS 2 & 3

., ISI Program Appendix A 1 Page 1 of 1 4

i REUEF REQUEST NO. RR 01 Revision 1 Relief Request Rescinded per NRC Generic Action 4

4 A

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d' Specifceuon M-733, Rev. 2

PBAPS 2 & 3

, ISI Program

Appendix A-2 Page 1 of 1 RELIEF REQUEST NO. RR-02 Revision 0 Approved

NRC SER dated 12/23/92 with comments *

l. 1. IDENTIFICATION OF COMPONENTS Reactor Recirculation Pumps,2AP34 and 2BP34, (Unit #2) and 3AP34 and 3BP34 (Unit

1. 3), Code Examination Category B-L-2, item Number B12.20. These Class 1 pumps

function during normal reactor operation to provide forced recirculation of reactor coolant J

through the reactor core.

il. CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED ASME Section XI 1980 Edition Winter 1981 Addenda Code Category B-L 2 requires a VT-3 visual examination of the intemal surfaces of at least one (1) of the two (2) Reactor Recirculation pump casings during the second inservice inspection interval.

s j Relief is requested from performance of the Code required visual examination of the puty

casing intemal surfaces due to impracticality of Code requirements at PBAPS.

1 lit. BASIS FOR RELIEF In the absence of any other required maintenance on either of the Reactor Recirculation

pumps, the hardships associated with pump disassembly, solely foi the purpose of visual l Inspection of the intemal surfaces, far exceed any safety benefits resulting from such an

! Inspection.

The disassembly of a reactor recirculation pump at PBAPS constitutes a maintenance job of major proportions, consuming an estimated 10,000 plus manhours and a cumulative

, dose of between 100 and 500 man-rem.

I Plant experience with the pump casing material in this application is favorable. The i additional assurance of structural integrity afforded by visual examination is far outweighed j by the cost and potential hazards presented to facilitate the inspection.

4 IV. ALTERNATE PROVISIONS i

' VT-3 visual examinations will be performed on the intemal surfaces of one (1) reactor recirculation pump should the required inspection area of either pump become accessible as a result of disassembly of the pump for other purposes. In addition, periodic ,

performance tests are conducted which monitor pumping capability and provide an '

indication of the condition of pump intemal clearances.  !

l Finally, Code required visual examinations of the pump pressure boundary during system l pressure testing provide added assurance of structuralintegrity. '

Relief was granted provided that if a pump has not been disassembled, that fact is reported by PECO Energy in the ISI Summary Report at the end of the interval.

i L__-__________

I specification

! M-733, Rev. 2

)-

PBAPS 2 & 3 ISI Program

, Appendix A-3 i Page 1 of 1 l

REUEF REQUEST NO. RR-03 Revision 0 Approved: NRC SER dated 12/23/92 with comments *

l. IDENTIFICATION OF COMPONENTS ISI Class 1 valve bodies exceeding four (4) inches cominal pipe size, Code Examination

.! Category B-M-2, item Number B12.50.

j i 11. CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED

ASME Section XI 1980 Edition Winter 1981 Addenda, Code Category B-M 2 requires a

, VT-3 visual examination of the intemal surfaces of one (1) valve within each group of

, valves that are of the same constrt'ctional design, manufacturing method and that perform

] similar functions in the system, once during the second inservice inspection interval.

Relief is requested from performance of the Code required visual examination of the valve l body intomal surfaces due to irnpracticality of Code requirements at PBAPS.

Ill. BASIS FOR RELIEF The requirement to disassemble ISI Class 1 valves solely for the purpose of performing a

, visual examination of the intamal surfaces of the valve body is impractical. The hardships and potential hazards associated with disassembly far outweigh any foreseeable increase in plant safety resulting from the examination, j Many of the subject valves are non-isolatable from the reactor pressure vessel and would require off loading of fuel and draining the reactor pressure vessel prior to disassembly for examination. Personnel exposure to perform disassembly of the valves is also a major consideration.

i' In addition, Industry experience with both cast and forged valve bodies in this application has been favorble.

IV. ALTERNATE PROVISIONS i When a valve within a particular valve grouping is disassembled for routine maintenance, a VT 3 visual examination will be performed of the accessible intamal surfaces of the j valve body to meet the Code requirement for that grouping.

Valves in groupings where no maintenance has been done are still subject to VT 2 visual i examination during routine system pressure tests. These tests provide added assurance

, . of pressure boundary structural integrity.

Relief is granted provided that if a valve has not been disassembled, that fact is reported by PECO Energy in the ISI Summary Report At the end of the interval.

j' 1

Specification

. M 733, Rev. 2

PBAPS 2 & 3 i ISI Program Appendix A 4 Page 1 of 1 j: REUEF REQUEST NO. RR-04 1 Revision 1 l

Approved: NRC SER dated 12/23/92 *

l. IDENTIFICATION OF COMPONENTS

) All ISI Class 1 pressure retaining components, Code examination Category B-P, item Numbers

B15.11, B15.51, B15.81 and B15.71.

11. CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED i ASME Section XI 1980 Edition Winter 1981 Addenda, Code Category B-P requires that a

! system hydrostatic test of the pressure retaining components within the system boundary be l performed once per Inservice inspection interval, in accordance with the applicable system pressure test requirements of IWB-5000.

l Relief is requested from meeting the hydrostatic test pressure as required by Table IWB 5220-1, " Test Pressure", (i.e.,1082 psig at 212'F).

Ill. BASIS FOR RELIEF

PBAPS Plant Technical Specifications require primary containment integrity be maintained

whenever the reactor water temperature is above 212 degrees Fahrenheit and fuel is in the

vessel. Primary containment integrity requires the drywell to be intact and all automatic primary 4 containment isolation valves to be operable or deactivated in the isolated position. However, to facilitate visual inspection of the reactor pressure vessel head flange and head spray nozzle

areas, the drywell head must be removed. Therefore, a complete Code hydrostatic test cannot be performed at reactor water temperatures above 212 degrees Fahrenheit.

Per Table IWB-5220-1, a test temperature of 212 degrees Fahrenheit corresponds to a test

! pressure of 1082 psig. PBAPS would like to conduct the hydrostatic test with all relief valves in

place and perfon.$ the hydrostatic test at a pressure 30 psig below the lowest relief valve setting. (This setta;9 si determined at the time of the hydrostatic test based on the most current l relief valve bench to

t data.) Gagging and/or removal of the four (4) lowest set relief valves is costly in both critical path time and personnel exposure and is impractical for a relatively small increase in pressure to meet Code requirements. (1082 psig vs.1075 11 psig) i IV. ALTERNATE PROVISIONS

. Code Category B P hydrostatic testing will be performed at a test pressure approximately 30

, psig below the lowest verifiable relief valve set point, nominally 1075 i 11 psig (assuming

bench test data of 1105 psig for the lowest relief valve setting), and at the applicable " Safe

! Opemting Region" test temperature determined from the plant Technical Specifications, Figure l 3.8.1.

Not applicable when Code Case N-498 is used.  :

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I-Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program

Appendix A 5 Page 1 of 4 REUEF REQUEST NO. RR-05 f Revision 2 Approved

NRC SER dated 4/8/86 for Rev.1 l

i. 1. IDENTIFICATION OF COMPONENTS 4

ISI Class 1 pressure retaining welds in piping including circumferential and longitudinal welds, branch pipe connection welds and socket welds, Code Examination Category B-J, item Numbers 89.10 through B9.40 inclusive.

- II. CODE REQUIREMENTS FROM WHICH REllEF IS REQUESTED ASME Section XI 1980 Edition Winter 1981 Addenda, Code Category B4 requires a volumetric

, and/or surface examination of essentially 100% of the weld length of all selected circumferential, and longitudinal welds, branch pipe connection welds and socket welds during

, the second inservice inspection interval.

Relief is requested from performance of a complete examination of the Code required i

area / volume of the weld due to limited accessibility as a result of plant design, component configuration and/or metallurgical or environmental restraints.

lli. BASIS FOR RELIEF The affected welds are individually detailed in Table RR-05-1 for PBAPS Unit #2 and in Table l RR 05-2 for PBAPS Unit #3.

The examination coverage indicated is the maximum practical without undue hardship to l

PBAPS. Increased examination coverage is not possible without costly plant j

, redesign / modification and/or excessive personnel exposure. 1

Partial examinations and examination of other similar selected welds in the system provide l l reasonable assurance of weld structural integrity, in addition, the affected welds are subject to

' Code Examination Category B-P requirements and are visually examined during system pressure testing throughout the interval, l

i IV. ALTERNATE PROVISIONS l 4

i For circumferential welds where examination is completely impractica' (examination 0%

l complete), an additional Code Category B-J weld will be selected for examination.

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i

. Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix A-5 Page 2 of 4 RELIEF REQUEST NO. RR-06 REV. 2 (CONTD) 1 TABLE RR-051

, UNIT #2 d

EXAMINATION AREA l.D. SYSTEM / LIMITING EXAMINATION EXAM CAT / ITEM CONFIGURATION CONDITION  % COMPLETE 1-B 7 Main Steam / Access limited due 86 %

B J, B9.11 Tee-Pipe to pipe support volumetric components within

the examination area 1-B 7LD Main Steam / Access limited due 35% each

! B-J, B9.12 Longitudinal to pipe support surface &

Seam Weld components within volumetric 4

the examination area 1 B-8 Main Steam / One-sided 70%

i B-J, B9.11 Pipe-Cap examination due to volumetric material and/or design configuration with physical plant obstructions on remaining side 1 B 8LU Main Steam / Access limited due 0%

B-J, 89.12 Longitudinal to pipe support surface &

Seam Weld components within volumetric the examination area i

1 D-9 Main Steam / Access limited due 50 %

B J, B9.11 Pipe-Elbow to pipe support volumetric components within the examination area i 1 D-9LU Main Steam / Access limited due 0%

B-J B9.12 Longitudinal to pipe support surface &

Seam Weld components within volumetric i the examination area

/

i[ Specification M-733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix A-5 l Page 3 of 4 j RELIEF REQUEST NO. RR-06 REV. 2 (CONTD) 4 l

j TABLE RR-051 (CONTD) d UNIT #2 EXAMINATION

AREA l.D. SYSTEM / LIMITING EXAMINATION EXAM CAT / ITEM CONFIGURATION CONDITION  % COMPLETE

?

i 1-D 12 Main Steam / One-sided 40%

B-J, B9.11 Pipe Valve examination due to volumetric j material and/or

design configuration

, with physical plant obstructions on

remaining side i

1 D-7LD Main steam / Access limited due 45% each l B-J, B9.12 Longitudinal to pipe support surface & l i Seam Weld components within volumetric

the examination area i

i 10-1B 15LU Residual Heat Access limited due 10% each

B4, B9.12 Removal / to pipe support surface & l 4

Longitudinal components within volumetric

- Seam Weld the examination area i

10-IA 15LU Residual Heat Access limited due 20% each

B J, B9.12 Removal / to pipe support surface & l

! Longitudinal components within volumetric )

i Seam Weld the examination area i i

10-0-35LD Residual Heat Access limited due 66% each j B J, B9.12 Removal / to penetration surface &

l Longitudinal volumetric

! Seam Weld J

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Specification M-733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix A 5 Page 4 of 4 RELIEF REQUEST NO RR-06 REV. 2 (CONTD)

TABLE RR-05-2 UNIT #3 EXAMINATION AREA l.D. SYSTEM / LIMITING EXAMINATION j EXAM CAT / ITEM CONFIGURATION CONDITION  % COMPLETE 1 A 7LD Main Steam / Access limited due 50% each B J, B9.12 Longitudinal to pipe support surface &

Seam Weld components within volumetric the examination area 1 B-7 Main Steam / One-sided 85%

B.J, B9.11 Tee-Pipe examination due to volumetric material and/or design configuration with physical plant obstructions on remaining side 4

1 B 7LD Main Steam / Access limited due 25% each B J, B9.12 Longitudinal to pipe support surface &

Seam Weld components within volumetric 1 the examination area a

I Specification i M-733, Rev. 2 PBAPS 2 & 3 i ISI Program

- Appendix A-6 Page 1 of 4

REUEF REQUEST NO. RR-06

Revision 2 Approved

NRC SER dated 4/8/88 with comments *

1. IDENTIFICATION OF COMPONENTS ISI Class 1 integral attachments for piping and pumps, Code Examination Category B-K 1, item Numbers B10.10 and B10.20.

II. ,QQDE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED ASME Section XI 1980 Edition Winter 1981 Addenda, Code Category B-K-1 requires a

, volumetric or surface examination of essentially 100% of the weld length of integrally welded attachments to piping and pumps during the second inservice inspection interval.

Relief is requested from performance of a complete examination of the Code required area / volume of the weld due to limited accessibility resulting from plant design, component configuration, and/or metallurgical or environmental restraints.

Ill. BASIS FOR RELIEF The affected welds are individually detailed in Table RR 06-01 and RR-06-02.

Table RR-06-01 lists those integrally welded attachments where examination is partially / completely obstructed due to plant design, i.e. access for complete examination is obstructed by other essential plant components (whip restraints, containment penetration, other support components such as lugs...). These welds are examined to the maximum extent practical. Increased examination coverage is not possible without costly plant

redesign / modification.

Table RR-06-02 lists those integrally welded attachments (pipe lugs) where complete examination is not practical due to the support pipe clamp. Complete examination is possible only upon removal of the clamp. Reme"al of the clamp involves engineering analysis and l rigging / temporary support of systems important to plant safety, in order to gain a small j percentage of increased examination coverage. Examination of accessible portions of the j attachment weld provide assurance of structural integrity without unnecessary hardship.

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Specification

! M 733, Rev. 2 PBAPS 2 & 3 4

ISI Program

. Appendix A-6 l Page 2 of 4 REUEF REQUEST NO. RR 06 REV 2 (CONTD) i IV. ALTERNATE PROVISIONS No attemate provisions are practical for the components listed in Table RR-06-01.

I For those pipe support lugs listed in Table RR-06-02, examination of the obstructed weld

] locations will be performed should the pipe clamp be removed for maintenance or other 4

reasons.

1 TABLE RR-06 01 i

PBAPS UNITS 2&3 l Examination Cateaorv B-K-1, item No 810.10 i

1 EXAMINATION AREA EXAMINATION SYSTEM IDENTIFICATION UNIT  % COMPLETE' M.S. GA1 (IA) 2 25%

l M.S. GB1 (IA) 2 0%

l M.S. GC1 (IA) 2 0%

l 1

M.S. GD1 (IA) 2 0%

RHR 10DCN-H155(1A) 2 85 %

RHR 10DCN-H156 (IA) 2 80 %

M.S. GA1 (IA) 3 0% l 0

j M.S. GB1 (IA) 3 0%

M.S. GC1 (IA) 3 0%

M.S. GD1 (IA) 3 0%

1

1. Approximate % complete based on Code required examination area.

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Specification l M 733, Rev. 2 l i

PBAPS 2 & 3 ISI Program Appendix A-8 l j

Page 3 of 4 REUEF REQUEST NO. RR-06 REV 2 (CONTD) l TABLE RR-06-02 PBAPS UNITS 2&3 Examination Cateoory B-K 1. Item No 810.10

?

EXAMINATION AREA EXAMINATION SYSTEM IDENTIFICATION UNIT  % COMPLETE' M.S. HA1 (IA) 2 80 %

M.S. HB3 (IA) 2 80 %

M.S. HC3 (IA) 2 80 %

M.S. HD1 (IA) 2 80 %

REClRC H1 A (IA) 2 80 %

, RECIRC HIB (IA) 2 80 %

RECIRC H9A (IA) 2 80 %

RECIRC H98 (IA) 2 80 %

F.W. 8DD-H57 (IA) 2 80 %

F.W. 8DD-H58 (IA) 2 80 %

RWCU 12DCN-H149 (IA) 2 80 %

RWCU 12DCN-H152 (IA) 2 80%

O.S. 14DCN-H73 (IA) 2 80 %

l C.S. 14DCN-H74 (IA) 2 80 %

C.S. 14DCN-H77 (tA) 2 80 %

C.S. 14DCN-H78 (IA) 2 80 %

HPCI 23DBN-H51 (IA) 2 80 %

M.S. HA1 (IA) 3 80 %

j M.S. HB3 (IA) 3 80 %

M.S. HC3 (IA) 3 80 %

M.S. HD1 (IA) 3 80 %

F.W. 8DD-H57 (IA) 3 80 %

F.W. 8DD-H58 (IA) 3 80 %

~

1. Approximate % complete based on Code required examination area.

l Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix A-6 Page 4 of 4 RELIEF REQUEST NO. RR 06 REV 2 (CONTD)

TABLE RR-06-02 (COP (TO)

PBAPS UNITS 2&3 Examination Cateoory B-K-1. Item No B10.10 EXAMINATION AREA EXAMINATION SYSTEM IDENTIFICATION UNIT  % COMPLETE' F.W. 6DDNL-H6 (IA) 3 80 %

F.W. 6DDNL H18 (IA) 3 80%

F.W. 6DDNL-H24 (IA) 3 80%

F.W. 6DONL-H25 (IA) 3 80 %

F.W. 6DDNL-H26 (IA) 3 80%

)

F.W. 6DDNL H27 (IA) 3 80%

F.W. 6DDNL-H28 (IA) 3 80%

F.W. 6DDNL-H44 (IA) 3 80 % l RWCU 12DCN-H152 (IA) 3 60%

RWCU 12DCN-H149 (IA) 3 80 %

C.S. 14DCN H73 (IA) 3 80% l C.S. 14DCN-H74 (IA) 3 80 %

C.S. 14DCN-H77 (IA) 3 80%

C.S. 14DCN-H78 (IA) 3 80 %

HPCI 23DBN H51 (IA) 3 80 % l 1

1. Approximate % complete based on Code required examination area.

Approved Rev.1 provided that examination of the obstructed integral attachment welds is performed when the pipe clamps are removed for maintenance or other reasons.

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i Specification 4

M 733, Rev. 2 PBAPS 2 & 3 l lSi Program Apperxkx A 7 )

3 Page 1 of 1 i REUEF REQUEST NO. RR-07 Revision 1 Withdrawn f

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- - _ _ - - . - - . - - . . . - - -- . . - . -- ~ . . - . . . - -- . . ~ . - - -~

Specification l; M-733 Rev. 2 PBAPS 2 & 3 ISI Program )

Appendix A-8  !

j Page 1 of 1 f RELIEF REQUEST NO. RR 08 l Revision 0 1 Approved: NRC SER dated 12/23/92  :

1. IDENTIFICATION OF COMPONENTS l 181 Class 2, pressure retalning shell circumferential welds in the Residual Heat Removal (RHR) Heat Exchanger, Code Examination Category C-A, item Number C1.10. The RHR Heat Exchangers provide heat removal capacity in support of various operating modes of the RHR system during normal and emergency conditions.

q ll. CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED J

ASME Section XI 1980 Edition Winter 1981 Addenda, Code Category C A requires volumetric examination of essentially 100% of the weld length of shell circumferential j wolds at gross structural discontinuities on one (1) RHR Heat Exchanger or the equivalent of one (1) RHR Heat Exchanger distributed among all heat exchangers. The welds I selected initially for examination shall be reexamined during the second inservice

inspection interval.

1 '

Relief is requested from complete examination of the uppershell to flange circumferential i weld, (10-2HXA 01, Units #2/#3) due to component design configuration.

lli. BASIS FOR RELIEF The subject RHR Heat Exchanger uppershell to flange weld can only be examined from one (1) side of the weld due to component configuration (i.e. the flange), in addition, i access for a one-sided examination is limited due to weld crown configuration. Fifteen (15) percent of the required examination volume is inaccessible for examination due to the i above conditions.

Partial examination of the subject weld coupled with complete examination of the  ;

remaining one (1) required shell weld on the heat exchanger provide adequate '

I assessment of heat exchanger structuralintegrtty. )

Also, all welds including inaccessible weld locations - are subject to VT 2 visual l l examination during routine system pressure tests.

I IV. ALTERNATE PROVISIONS Altemate examination provisions are not practical for this examination. )

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Specification l M 733 Rev. 2 PBAPS 2 & 3 ISI Program Appendix A-9 Page 1 of 2.

REUEF REQUEST NO. RR-00 Revision 0 Approved: NRC SER dated 4/8/88

l. IDENTIFICATION OF COMPONENTS l ISI Class 3 pressure retaining components in the High Pressure Service Water (HPSW)

System, the Emergency Service Water (ESW) System, and the Emergency Cooling l

System, Code Examination Category D-B, item Number D2.10.

1 The HPSW System is designed to provide a reliable supply of cooling water for the Residual Heat Removal System under post-accident conditions, and for shut down cooling.

The ESW System is designed to provide a reliable supply of cooling water to the diesel  :

engine coolers and selected equipment coolers and compartment air coolers during a loss of off-site power.

The Emergency Cooling System is designed to provide an adequate on-site heat sink to be used in conjunction with HPSW to support the RHR System during reactor shutdown, j and with ESW to provide cooling for the reactor building cooling water heat exchangers, stardby diesel generator coolers, and the ECCS pump room coolers. The Emergency Cooling System also provides sufficient water storage to allow operation of the emergency cooling tower until a water supply can be established, ,

t

11. ,QQQg , REQUIREMENTS FROM WHICH RELIEF IS REQUESTED t l ASME Section XI 1980 Edition Winter 1981 Addenda, Code Category D-B requires a 1 system h/drostatic test of all pressure retaining components within the system pressure  !

i retaining txxJndary once during the second inservice inspection interval. LWD 5223(a) of l

the Code requires the system hydrostatic test for the subject systems be performed at a test pressum of at least 1.10 times the system design pressure or the lowest pressure setting among the safety / relief valves within the boundary of the system to be tested.

I

Relief is requested from meeting the test pressure requirements of IWD-5223(a) due to i plant hardship.

l l

lll. BASIS FOR REggF,

' Hydrostatic testing of the subject systems to at least 1.10 times the system design '

pressure is imprac.tical to implement at PBAPS. The required test pressure is beyond the i

capability of the ex.' sting system pumps and, therefore, would require the use of hydrostatic test purr:ps. The only available test connections on these systems are 3/4 and j 1 inch lines which would sharply limit the inflow capability from the hydrostatic test pumps.  ;

Under these conditior,s, successful performance of the test is a function of the degree of leak tightness of large system valves (i.e., 14,16,20, and 24 inch). Valve leak-tightness  !

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix A-9 Page 2 of 2 RELIEF REQUEST NO. RR 69 REV 0 (CONTD) for these systems is not required and considerable manpower would be required to rework / upgrade these valves in preparation for performance of the hydrostatic test.

In addition, testing to 1.10 times the system design pressure would seriously affect plant operations since removal of the ESW or HPSW Systems would result in an interruption of shutdown cooling.

1 IV. ALTERNATE PROVISIONS PBAPS proposes performance of Code required hydrostatic testing of the ESW, HPSW and Emergency Cooling Systems to 1.10 times the system operating pressure. Testing to this pressure can be accomplished utilizing existing plant equipment while still providing assurance of pressure boundary integrity of these systems.

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i

Specification i M-733, Rev. 2 PBAPS 2 & 3 4

ISI Program Appendix A-10

] Page 1 of 1 1 REUEF REQUEST NO. RR-10 l Revision 0 Approved: NRC SER dated 4/8/86

l. IDENTIFICATION OF COMPONENTS

[ ASME Class 1,2, and 3 snubber assemblies, Code Examination Category F-C, item

Number F3.50. This relief request is applicable to the snubber assembly only; that is, the snubber body and attachments out to and including the load pins and their retainers.

11. CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED J

q ASME Section XI,1980 Edition up to and including the Winter 1981 Addenda (80W81),

i Examination Category F-C requires a VT-3NT-4 visual examination of mechanical type snubbers.

In addition, Article IWF 5000 details inservice testing requirements for snubbers less than l 50 Idps. (Requirements for snubbers 50 kips or greater are in the course of preparation.)

i Relief in requested from the examination requirements of Articles lWF-1000, lWF 2000,

!- (exclud.ng IWF-2520), and Table IWF-2500-1 and the inservice testing requirem9nts of Article IWF 5000 due to the redundancy of these examination / test requirements to PBAPS 2 & 3 Technical Specification requirements.

Ill. BASIS FOR REllEF 1

i implementation of both the aformentioned Code requirements and requirements contained in the PBAPS 2 & 3 Technical Specifications results in redundancy and poses an unnecessary hardship, without a compensating increase in plant safety. Both programs j are designed to demonstrate continued operational readiness and structural integrtty by

. visual examination and functkmal testing of snubber assemblies. However, while the test j requirements in the Code are incomplete (depending on the size of the snubber), the program described in Technical Specification 3/4.11.D is comprehensive and meets the l Intent of ASME Section XI examination and testing.

i IV. ALTERNATE PROVISIONS The examination and testing of snubber assemblies shall be performed in accordance with

, Technical Specification 3/4.11.D in lieu of the aforementioned Code examination and i

testing requirements. Following the issuance of a license amendment revising the PBAPS 2 & 3 Technical Specifications to incorporate the examination and testing requirements of Augmented inspection Program-5 in place of the existing Technical i Specification requirements, the examination and testing of snubber assemblies shall be performed in accordance with the revised Technical Specification 3/4.11.D in lieu of the j aforementioned Code requirements. Note that the general requirements of Subsection IWA, such as examination methods, personnel qualifications, etc., still apply. Additionally, all repairs, replacements, records, and reports will be in accordance with ASME Section XI.

L The remainder of the component support, outboard of the snubber assembly shall be examined in accordance with ASME Section XI, Subsection IWF requirements.

1 a

Specification i M-733, Rev. 2 1

PBAPS 2 & 3 i

ISI Program Appendix A 11 Page 1 of 1 i

RELIEF REQUEST NO. RR 11

, Revision 0 l

1 Approved: NRC SER dated 12/23/92 l.

f IDENTIFICATION OF COMPONENTS i

ISI Class 2 piping and components beyond the last shutoff valve in open-ended portions of systems.

ll. CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED

ASME Section XI 1980 Edition Winter 1981 Addenda, Article IWC-1000 does not provide any j exemption for the subject piping and components, and, therefore, requires examination of appropriate pressure retaining components and their integral attachments in accordance with j

Table IWC 25001, during the second inservice inspection interval.

Relief is requested from the Code Examination requirements of Table IWC-25001 for ISI Class

] 2 piping and components beyond the last shutoff valve in open-ended portions of systenis.

l 111. BASIS FOR RELIEF The 1986 Edition of the Code, which has been approved for use, recognizes the impracticality l of examination of the subject piping and components. Per IWC-1221 (f) and IWC-1222 (d),

4

' Piping and other components of any size beyond the last shutoff valve in open ended portions

of systems that do not contain water during normal plant operating conditions

• shall be j exempted from the inservice examination requirements of IWC-2500.

Much of the subject piping is impractical to examine due to limited access as a result of plant design. Also, since this portion of the system does not contain water during normal operating j conditions, the piping is ' pressure retaining' relatively infrequently.

l Exemption of the subject piping and components, consistent with later Editions of the Code, does not preclude all examinations within the Code boundaries. Exempted piping and

{~ components are subject to the requirements of Code Examination Category C-H.

Demonstration of open flow path testing provides assurance of the availability of the piping to

, perform its intended function.

IV. ALTERNATE PROVISIONS ISI Class 2 piping and components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal plant operating conditions shall be exempt from the examination requirements of IWC-2500.

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-. .- .. . - . . . - . . - - _ . . _ - . - - - . . - . . _ _ _ - - - = ~ . . - . . . . . . - - -

Specmcation l M-733, Rev. 2

.!: PBAPS 2 & 3 ISI Program Appendix A 12 i

Page 1 of 1 4-REUEF REQUEST NO. RR-12 j Revision 1

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__ _ _ . _ _ . _ _ . . _ ~ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ - _ _ __

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program

, Appendix A-13 j Page 1 of 7 4

RELIEF REQUEST NO. RR-13

, Revision 1 Approved: NRC SER dated 12/23/92

- 1. IDENTIFICATION OF COMPONENTS q ISI Class 1 full penetration nouie to vessel welds in the reactor pressure vessel, Code Examination Category B D, item Number B3.90.

) ll, CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED l

ASME Section XI 1980 Edition Winter 1981 Addenda, Code Category B D requires volumetric examination of the noule to vessel welds (full penetration) of all nozzles in the reactor pressure vessel during the second inservice inspection interval.

Relief is requested from performance of a complete examination of the Code required volume

)

due to access restrictions as a consequence of plant design and/or component configuration.

l 111. BASIS FOR RELIEF l PBAPS has thirty (30) Code Category B D nozzle to vessel attachment welds on each unit, 3 many of which cannot be completely examined due to vessel nozzle forging configuration. The i barrel type nozzle forging configuration precludes complete ultrasonic examination since scanning of the weld is only practical from one side of the weld. Also, in support of ALARA, many of the nozzle to vessel welds are to be examined utilizing a remote automated nozzle

scanner; thereby, slightly exaggerating the limitations, versus a manual examination, due to

! scanner design. In addition to the nozzle forging configuration, physical plant design restrictions, such as adjacent componerts, further limit the available scan path.

t Tables RR 13-1 (Unit #2) and RR 13-2 (Unit #3) list the nozzle to vessel welds and detail the i extent of examinations completed (for nozzles already examined), or provide the expected i examination coverage (for nozzles not yet examined).

! All examinations are performed to the maximum extent practical. In the case of examinations

! performed utilizing remote automatic equipment, only a very slight increase in examination coverage (- 5%) can be realized with supplemental manual exams; however, this small j increase comes with a significant increase in personnel exposure, and, therefore, manual

examination was not performed.

I

^

Limited volumetric examination coupled with the visual examination requirements of Code Examination Caitgory B-P during system pressure testing provide reasonable assessment of 1

weld structuralintegrity.

. IV. ALTERNATE PROVISIONS No attemate provisions are practical for these examinations.

f s

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d Specification l M 733, Rev. 2 PBAPS 2 & 3 i ISI Program Appendix A 13 l Page 2 of 7 )

REUEF REQUEST NO. RR 13 REY.1 (CONTD) l TABLE RR 131 Effect of Nonle Design Configuration on Component inspectability' Examination Cateoory B-D. Item No B3.90 l

Unit #2 Nonle Identification / Type  % Code  % Inner 1/4T Descriotion Scan' Comolete* Code Comoiete' NIA 45T 17.2 (A)

' 41.5 (A)

Recirculation Outlet 60T 28.3 (A) 66.9 (A)  ;

60P 23.6(A) j 57.2 (A)

N2A 45T 29.1 (A) 51.5 (A)

Recirculation Inlet 60T 37.4 (A) 71.1 (A) 60P 23.0 (A) 43.9 (A)

N2B 45T 28.7 (A) 50.8 (A)

Recirculation inlet 60T 36.9 (A) 70.1 (A) 60P 22.7 (A) 43.2 (A)

, N2C 45T 28.7 (A) 50.8 (A)

Recirculation inlet 60T 36.9 (A) 70.1 (A)

60P 24.0 (A)

45.8 (A)

, N2D 45T 29.5 (A) 52.2 (A)

Recirculation Inlet 60T 37.9 (A) 72.1 (A) 60P 23.4 (A) 44.5 (A)

N2E 45T 32.0 (A) 56.7 (A)

Recirculation inlet 60T 41.1 (A) 78.1 (A) 60P 25.7 (A) 48.9 (A)

N2F 45T 28.2 (A) 50.0 (A)

Recirculation inlet 60T 36.3 (A) 69.0 (A) 60P 22.4 (A) 42.6 (A) ecirculation inlet ^

60 43.2 82[2

, 60P 26.7 (A) 50.8 (A) b

l Specification M-733, Rev. 2 .

PBAPS 2 & 3 l lSI Program i Appendix A 13  !

Page 3 of 7 l l

REUEF REQUEST NO. RR-13 REV.1 (CONTD) i 1

, TABLE RR-13-1 (CONTD.)

UnN#2 Nonle identification / Type  % Code  % Inner 1/4T Dascriotion Scan

• Comolete' Code Conolete'

N3A 45T 9.6 (A) 33.4 (A)

Main Steam 60T 23.7 (A) 66.9 (A)

. 60P 11.3 (A) 40.1 (A)

N3D 45T 8.9 (A) 31.2 (A)

Main Steam 60T 22.2 (A) 62.5 (A) 60P 10.4 (A) 36.7 (A) I N4 45T 28.8 (M)* 66.5 (M)*

Feedwater 60T 45.5 (M)' 100.0 (M)* <

l (Typ. of 6 noules) 60P 27.0 (M)* 62.6 (M)'

l 1

NSA 45T 23.6 (A) 46.7 (A)

Core Spray 60T 34.2 (A) 65.1 (A) 60P 19.7 (A) 39.4 (A)

NSB 45T 23.6 (A) 46.7 (A) ,

Core Spray 60T 34.2 (A) 65.1 (A)  ;

60P 19.7 (A) 39.4 (A) l N8A 45T 92.4 (M) 100.0 (M)

Jet Pump 60T 93.0 (M) 100.0 (M) ,

instrumentation 45P 80.1 (M) 83.7 (M) 1 60P 80.1 (M) 83.7 (M) )

N9 45T 31.1 (M)' 71.6 (M)' l Control Rod Drive 60T 46.6 (M)* 100.0 (M)*

Nonle 45P 17.4 (M)5 37.3 (M)*

(Typ. of 1 nonle) 60P 27.5 (M)' 62.5 (M)*

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. . . ______________________I

. Specification M-733, Rev. 2

PBAPS 2 & 3 ISI Program

, Appendix A-13

, Page 4 of 7 REUEF REQUEST NO. RR-13 REV.1 (CONTD) i Footnotes:

1) Component inspectability based on actual examination results or evaluation of nozzle design l configuration for each given type / size nozzle.

2) Unless indicated, a 45 degree parallel scan is not practical due to weld configuration.

3)  % Code complete is that percent of the ASME Code required examination volume which can

! effectively be examined using automated (A) or manual (M) ultrasonic examination techniques.

4)  % Inner 1/4T Code complete is that percent of the critical inner 1/4T wall volume which can effectively be examined using automated (A) or manual (M) ultrasonic examination techniques.

}

5) N4 Foodwater and N9 Control Rod Drive nozzle % complete is optimum based on estimated accessible Code volume utilizing manual ultrasonic techniques; actual automated ultrasonic examination data, (not available at this time) is expected to yleid slightly reduced coverage to due equipment limitations.

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i Specification M 733, Rev. 2 PBAPS 2 & S 181 Program Appendix A-13

~ Page 5 of 7 s

REUEF REQUEST NO. RR 13 REV.1 (CONTD) l TABLE RR 13-2 Effect of Nozzle Design Configuration on Component inspectability'

Examinatbn Cateoory B-D. Item No. B3,jo, Unit #3 i

a Nozzle identification / Type  % Code  % Inner 1/4T Description jggn" Complete

• Code Complete' j.

^ NIA 45T 6.2 (A) . 27.0 (A)

Recirculation Outlet 60T 18.9 (A) 63.5 (A) 60P 12.4 (A) 47.6 (A)

N2A 45T 16.1 (A) 40.4 (A)

, Recirculation Inlet 60T 30.5 (A) 70.2 (A) 60P 13.9 (A) 34.3 (A)

N2B 45T 14.9 (A) 37.4 (A) l Recirculation inlet 60T 28.3 (A) 65.1 (A)

, 60P 12.8 (A) 31.8 (A)

N2C 45T 17.1 (A) 42.8 (A)

Recirculation inlet BOT 32.3 (A) 74.3 (A) 60P 14.7 (A) 36.4 (A) i N2D 45T 16.4 (A) 41.0 (A)

Recirculation inlet 00T 31.0 (A) 71.2 (A) j 60P 13.9 (A) 34.3 (A)

N2E 45T 16.6 (A) 41.6 (A) 1 Recirculation inlet 60T 31.4 (A) 72.3 (A)

, 60P 14.3 (A) 35.4 (A)

N2F 45T 16.1 (A) 40.4 (A)

Recirculation Inlet 60T 31.4 (A) 72.3 (A) 60P 14.3 (A) 35.4 (A) 4 N2H 45T 16.8 (A) 42.2 (A)

Recirculation inlet 60T 31.9 (A) 73.3 (A) 60P 14.3 (A) 35.4 (A) 4

Specification M-733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix A 13 Page 6 of 7 RELIEF REQUEST NO. RR-13 REV.1 (CONTD)

TABLE RR 13-2 (CONTD.)

Unit #3 Nonle Identification / Type  % Code  % Inner 1/4T Description Scan' Comolete' Code Comolete' N3A 45T 9.8 (A) 38.1 (A)

Main Steam 60T 24.3 (A) 76.4 (A) 60P 11.4 (A) 45.0 (A)

N3D 45T 9.4 (A) 36.6(A)

Main Steam 60T 23.4 (A) 73.4 (A) 60P 11.0 (A) 43.4 (A)

N4 45T 24.6(M)* 63.3 (M)'

Feedwater 60T 41.7 (M)' 99.1 (M)*

(Typ. of 6 nonles) 60P 23.0 (M)* 59.2 (M)8 NSA 45T 19.9 (A) 44.0 (A)

Core Spray 60T 31.3 (A) 65.4 (A) 60P 15.1 (A) 35.6 (A)

, NSB 45T 20.2 (A) 44.7 (A)

Core Spray 60T 31.8 (A) 66.4 (A) 60P 15.3 (A) 36.2 (A)

N8A 45T 91.8 (M) 100.0 (M)

Jet Pump 60T 92.5 (M) 100.0 (M)

Instrumentatk.7 45P 77.3 (M) 80.7 (M) 60P 77.3 (M) 80.7 (M)

N9 45T 29.0 (M)' 70.6 (M)*

Control Rod Drive 60T 45.0 (M)' 100.0 (M)'

Nonle 45P 14.9 (M)' 34.8 (M)*

(Typ. of 1 nonle) 60P 25.4 (M)' 61.0 (M)'

Specification M 733, Rev. 2

' PBAPS 2 & 3 ISI Program Appendix A 13 Page 7 of 7 REUEF REQUEST NO. RR-13 REV.1 (CONTD)

Footnotes:

1) Component inspectability based on actual examination results or evaluation of nozzle design configuration for each given type / size nozzle.

2) Unless indicated, a 45 degree parallel scan is not practical due to weld configuration.

3)  % Code complete is that percent of the ASME Code required examination volume which can effectively be examined using automated (A) or manual (M) ultrasonic examination techniques.

i

4)  % Inner 1/4T Code complete is that percent of the crtecal inner 1/4T wall volume which can effectively be examined using automated (A) or manuat -(M) ultrasonic examination techniques.

5) N4 Feedwater and N9 Control Rod Drive nozzle % complete is optimum based on estimated 1

accessible Code volume utilizing manual ultrasonic techniques; actual automated ultrasonic axamination data, (not available at this time) is expected to yield slightly reduced coverage to due equipment limitations.

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4

Specification j M 733, Rev. 2 l Addendum 1 PBARS 2 & 3 ISI Program

Appendix A 14 i Page 1 of 4 RELIEF REQUEST NO. RR 14 Revision 4

] Approved: NRC SER dated 8/24/95

1. SCOPE

! This relief request has been developed to request approvalfor the use of specific ASME 1' Section XI Code Cases in this ISI Program. These Code Cases have not yet been specifically l endorsed for use by the NRC, in Regulatory Guide 1.147 (reference 1.1.24).

I 11. DISCUSSION

! Code Cases are periodically published by the ASME for the purpose of either clarifying the l Intent of Code requirements or for providing requirements for circumstances which are not currently covered by existing Code, but need to be addressed in a timely manner. Use of these 1 non-mandatory Code Cases for Inservice inspection is subject to NRC acceptance of the Code

Case (s). Regulatory Guide 1.147 lists those Code Cases that have been reviewed by the NRC and are generally acceptable for implementation in an ISI Program. Other Code Cases may be used provided specific authorization is secured pursuant to 10CFRSO.55a.

! The purpose of this relief request is to request authorization for the adoption of specific Code i Case (s) for implementation in the PBAPS, Units 2 and 3 Second Interval ISI Program.

i 111. CODE CASEfS) REQUIRING AUTHORIZATION 1 The Code Case (s) requiring specific authorization for use in the PBAPS, Units 2 and 3

! ISI Program are identified on the attached Table (s).

IV. ALTERNATE PROVISIONS j The altemative provisions of the Code Case (s) identified in Section 111 above, shall be implemented in the PBAPS, Units 2 and 3 ISI Program for the second inservice inspection interval. Any deviations from these requirements are identified in the referenced Tables. These Tables address the specific application of the associated Code Case in the ISI Program.

)

V. BASIS FOR REllEF The Code Case (s) referenced in Section 111 above, represent technically acceptable altemative ,

requirements to the ASME Section XI Code requirements. The fact that the Code Case (s) has  :

not been endorsed in the Regulatory Guide in no way detracts from their technical adequacy, since the major reason for their omission is the timing of their publication with respect to the i

most recent revision of the Regulatory Guide. That is, the subject Code Case (s) is relatively recent and it is expected that it will be accepted in a subsequent revision of the Regulatory Guide. Adoption of the Code Case (s) provides an acceptable level of quality and safety and does not compromise the adequacy of the PBAPS, Units 2 and 3 ISI Program in meeting the intent of ASME Section XI.

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Specification M 733, Rev. 2 .

Addendum 1 PBAPS 2 & 3 ISI Program Appendix A 14 l Page 2 of 4 i RELIEF REQUEST NO, RR-14 REV 4 (CONTD)

Table RR-141 CODE CASE N-4981

1. IDENTIFICATION OF COMPONENTS PBAPS, Units 2 and 3 Class 1,2, and 3 systems.

11. CODE REQUIREMENTS FROM WHICH REllEF IS REQUESTED The 10-Year System Hydrostatic Pressure Testing requirements for Class 1,2, and 3 systems, as identified in Section XI, Division 1, Table IWS-25001, Category B-P, Table IWC 2500-1 Category C-H, and Table IWD-2500-1, Categories D A, D-B, and D C respectively; as contained in the 1980 Edition of ASME Section XI, including addenda through the Winter 1981 Addendum.

111. BASIS FOR REllEF - Code Case N 498-1:

The burden imposed by the higher test pressures associated with the current 19 year hydrostatic test requirement, is not commensurate with the increase in safety banefit.

Hydrostatic pressure tests are performed at elevated pressures which require special maintenance activities for isolation of components to be tested, such as: temporary gagging or l removal of relief valves installed to prevent overpressurization, leaktight repair of valving which does not nrstmally serve a pressure isolation function, and installation of portable hydrostatic pressure pumps. The higher pressures imposed on the pressure boundary components during hydrostatic testing do not challenge the structural integrity of the material, and produce only a slight enhancement in leak detection capability. The additional leakage, above that which occurs during a system pressure test at nominal operating pressure, is inconsequential in determining pressure boundary integrity. Therefore, the additional burden, and in some instances additional radiological dose to personnel associated with these maintenance activities, i

can be avoided.The experience gained by the performance of these tests indicates that the l goal of the test (i.e. to discover pressure boundary leakage or evidence of structural distress) l Will still be achieved at lower test pressures.

Adoption of this Code Case will allow substitution of a system pressure test, conducted at nominal operating pressure, for the ten year hydrostatic test, currently required for Class 1,2, and 3 systems.

IV. ALTERNATE PROVISIONS As an altemative to the hydrostatic testing requirements, a system pressure test, at nominal operating pressure, may be conducted at or near the end of the interval. The boundary, subject to test pressurization during this system pressure test, will extend to all Class 1, 2, :md 3 components as identified on the ASME Section XI Boundary P & ID's.

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! Specification M 733, Rev. 2

Addendum 1

PBAPS 2 & 3 i' ISI Program l Appendix A 14 Page 3 of 4 i

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RELIEF REQUEST NO. RR 14 REV 4 (CONTD)

Tatne RR-14 2 CODE CASE N 4161 l

l. IDENTIFICATION OF COMPONENTS PBAPS, Units 2 and 3 Class 1,2, and 3 systems.

II. CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED ASME Section XI,1980 Edition, Winter 1981 Addenda, Article IWA-4000 and IWA-5000

- hydrostatic pressure test requirements.

Ill. BASIS FOR RELIEF - Code Case N-4161:

The above Articles require that hydrostatic pressure testing be performed after welded repair or

installation of replacement items by welding on ASME Class 1,2 and 3 pressure boundary j components.

l The burden imposed by the process of hydrostatic testing is not commensurate with the increased level of safety achieved. Hydrostatic pressure tests are performed at elevated i pressures which require special maintenance activities for isolation of components to be tested, such as: temporary gagging or removal of relief vanes installed to prevent overpressurization, l leaktight repair of valving which does not normally serve a pressure isolation function, and

, installation of portable hydrostatic pressure pumps. The higher pressures imposed on the pressure boundary components during hydrostatic testing do not challenge the structural integrity of the material, and produce only a slight enhancement in leak detection capability.

The additional leakage, above that which occurs during a system pressure test at nominal operating pressure, is inconsequential in determining pressure boundary integrity. Therefore, the additione.' burden, and in some instances additional radiological dose to personnel

associated with these maintenance activities, can be avoided.

I Adoption of this Code Case will allow substitut' ion of a system leakage test, conducted at nominal operating pressure, for the post repair / replacement hydrostatic test, currently required for Class 1,2. dnd 3 systems.

1 1- IV. ALTERNATE PROV!Sjlif, 1 The requirements of Code Case 4161 will be implemented as altemate provisions to the ASME Section XI Code,1980 Edition with Addenda through Winter 1981, for Class 1,2 and 3 j pressure boundary component welded repairs and installation welds for replacement items.

j 4

__________a______._________________________________-______._________--a,--

.~ _ - -. .. - -_

Specnication M 733, Rev. 2 )

Addendum 1  !

PBAPS 2 & 3 ISI Program Appendix A 14 i Page 4 of 4 i RELIEF REQUEST NO. RR 14 REV 4 (CONTD)

Table RR-14 2 CODE CASE N-4161 IV. ALTERNATE PROVISIONS (Contd)

In addition, Nondestructive Examination (NDE) of Class 1,2, and 3 repair or replacement butt welds shall be performed in accordance with the UFSAR license commitments, whict will equal or exceed the NDE methods and acceptance criteria of the applicable Subsection of the 1992 Edition of ASME Section Ill. In the absence of volumetric examination requirements, a surface examination of the root pass of the butt weld shall be performed.

Surface examination of Class 1,2, and 3 repair or replacement socket welds shall be performed on the final pass of the socket weld.

The above provisions provide an equivalent level of safety to that associated with hydrostatic testing, and are consistent with ALARA good practice.

Use of this Code Case shall be documented on the applicable Code Form, and included in the ISI Summary Report.

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Specification M 733 Rev. 2 PBAPS 2 & 3 ISI Program Appendix A 15 Page 1 of 2 REUEF REQUEST NO. RR-15 Revision 1 Approved: NRC SER dated 12/23/92

1. IDENTIFICATION OF COMPONENTS ISI Class 2 integral attachments for vessels, piping, pumps and valves, Code Examination Category C C, item numbers C3.10 through 3.40.

i

11. CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED ASME Section XI 1980 Edition Winter 1981 Addenda, Cod 3 Category C-C, requires a surface examination of essentially 100% of the required area of each welded attachment selected for examination during the second inservice inspection interval.

Relief is requested from performance of a complete examination of the Code required area due to limited accessibility resulting from plant design, component configuration, and/or environmental restraints.

Ill. BASIS FOR RELIEF The affected Unit #2/ Unit #3 integral attachment welds are individually detailed in table RR 1S-01.

Examination of these welds are to the maximum extent pratical. increased examination coverage is not possible without costly plant redesign / modification.

e IV. ALTERNATE PROVISIONS No attemate provisions are pratical for the components listed in Table RR 15-01.

1 2

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix A-15 Page 2 of 2 RELIEF REQUEST NO. RR-15 REV 1 (CONTD)

TABLE RR-15-01 UNIT #2/#3 EXAMINATION AREA EXAMINATION LIMITING IDENTIFICATION UNIT  % COMPLETE' CONDITION PUMP-B lWS 2 50 % Complete exam is not '

(RHR PUMP LUGS) practical due to support design;

access restrictions exist on all of four (4) pumps.

PUMP A lWS 3 50 % Complete exam is not (RHR PUMP LUGS) practical due to support design; access restrictions exist on all of four (4) pumps.

10GB H50(IA) 2 88 % Pipe Component lateference.

PUMP A-lWS 2 48% Complete exam is not practical due to support design; access restrictions exist on all of four (4) pumps.

PUMP-C-lWS 2 44 % Complete exam is not practical due to support design; access restrictions exist on all of four (4) pumps.

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u specification l M 733, Rev. 2 j PBAPS 2 & 3 ISl Program Appendix A 16 Page 1 of 2

! REUEF REQUEST No. RR 1tl Revision 0 i Approved: NRC SER dated 12/23/92

l. IDENTIFICATION OF COMPONENTS s ISI Class 2 pressure retaining components, Code Examination Category C H, item Numbers C7.10 through C7.80 inclusive.

l The specific Class 2 components affected by this relief request are detailed in

Table RR 16-01.

p 11. CODE REQUIREMENTS FROM WHICH REllEF IS REQUESTED ASME Section XI 1980 Edition Winter 1981 Added, Code Category C-H, requires that all pressure retaining corcyrsesnts within each system boundary be subject to system pressure tests of IWC-5000 under which conditions visual examination VT 2 is performed to detect leakage. These required VT-2 visual examinations are conducted in conjunction with functional tests, inservice tests, hydrostatic tests and/or pneumatic tests, as applicable, at the Code required pressures, temperatures, and holding times.

The required system pressure tests shall be performed during the second inservice inspection interval in accordance with Table IWC-25001.

Relief is requested from system pressure testing of portions of certain Class 2 piping systems and/or components which cannot be accomplished in accordance with the Code due to physical plant and/or operational restrictions.

Ill. BASIS FOR RELIEF l

The affected components (pressure vessels, piping, pumps and valves) requiring relief are detailed in Table RR 16-01. Included in this Table is all pertinent information relative to -

the system pressure test including the basis for relief.

IV. ALTERNATE PROVISIONS Where practical, any attemate provisions proposed in lieu of Code requirements are so noted in Table RR 16-01.

4

i Specification M 733. Rev. 2 PBAPS 2 & 3 ISI Program Appendix A-16 Page 2 of 2 RELIEF REQUEST NO. RR-16 REV 0 (CONTD)

TABLE RR 16 01

1. IDENTIFICATION OF COMPONENTS ABAPS 2 & 3 Class 2 Residual Heat Removal Heat Exchangers, HX 2AE24 2DE24 and 3AE24 3DE24 and associated test boundary piping and valves.

II. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED IWC 5222 System Hydrostatic Test 111. BASIS FOR RELIEF The Code required hydrostatic test pressure for the RHR heat exchangers is 562.5 psig (1.25 x 450 poig). However, plant operating procedures limit operation of the RHR System (shell side) to a pressure less than HPSW (tube side) pressure to preclude possible in-leakage of contaminated water into " clean

• HPSW cooling water. The HPSW pumps are the limiting factor in that, even at dead head conditions, insufficient pressure is available to support Code hydrostatic test pressures. Therefore, relief is required from the <

system hydrostatic test pressure requirements of IWC-5222(a) to allow testing at a I reduced pressure.

IV. ALTERNATE PROVISIONS The RHR heat exchanger and associated test boundary piping and valves will be tested at 1.25 times the normal operating pressure. (Normal operating pressure for this test is RHR pump dischatge pressure 0 11,000 gpm flow, nominally 230 psig i 10.)

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- -. - ,e---------n - -,-n. - . - -. m

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix A 17 Page 1 of 2 REUEF REQUEST NO. RR 17 Revision 0 Approved: NRC SER dated 12/23/92

1. IDENTIFICATION OF COMPONENTS ISI Class 3 pressure retaining components, Code Examination Categories D A, D-B, and D-C, item Numbers D1.10, D2.10, and D3.10, respectively.

The specific Class 3 components affected by this relief request are detailed in Table RR 17-01.

11. CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED ASME Section XI 1980 Edition Winter 1981 Addenda, Code Category D-A, D-B, and D-C require that all pressure retainirq components within each system boundary be subject to system pressure tests of IWD-5000 under which conditions visual examination VT-2 is performed to detect leakage. These required VT-2 visual examinations are conducted in conjunction with functional tests, inservice tests, hydrostatic tests and/or pneumatic tests, as applicable, at the Code required pressures, temperatures, and holding times.

The required system pressure tests shall be performed during the second inservice inspection interval in accordance with Table IWD-2500-1.

Relief is requested from system pressure testing of portions of certain Class 3 piping systems and/or components which cannot be accomplished in accordance with the Code due to physical plant and/or operational restrictions.

Ill. BASIS FOR RELIEF The affected components (pressure vessels, piping, pumps and valves) requiring relief are detailed in Table RR 17 01. Included in this Table is all pertinent information relative to the e

system pressure test including the basis for relief.

IV. ALTERNATE PROVISIONS l- Where practical, any attemate provisions proposed in lieu of Code requirements are so noted in j Table RR-17 01.

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Specif'cation M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix A 17 Page 2 of 2 REUEF REQUEST NO. RR-17 REV 0 (CONTD)

TABLE RR-17 01

1. IDENTIFICATION OF COMPONENTS PBAPS 2 & 3 Class 3 Main Steam relief valve discharge lines.

II. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED IWD-5223, System Hydrostatic Test lll. BASIS FOR RELIEF Hydrostatic testing of the subject piping is impractical at PBAPS 2 & 3. Per IWD-5223(f), a pneumatic test (at a pressure of 90% of the pipe submergence head of water) that demonstrates leakage integrity shall be performed in lieu of the system hydrostatic test. At PBAPS 2 & 3, this requirement translates into a pneumatic test at a test pressure of about 2 pelg.

Currently, no test connections exist to facilitate performance of the pneumatic test; plant modification would be required to add the necessary test connections. The assurance of leakage integrity afforded through performance of a 2 psig pneumatic test is questionable; therefore, performance of the test at PBAPS 2 & 3 represents a hardship with no compensating increase in plant safety.

Relief is requested from meeting the system pressure test requirements of IWD-5223.

IV. ALTERNATE PROVISIONS Instrumentation (acoustic, temperature) on these lines provide indirect information relative to the j integrity of these lines. This instrumentation is routinely monitored when the MSRVs are lifted.

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i Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix A 18 Page 1 of 2 RELIEF REQUEST NO. RR-18

! Revision 0 Approved: NRC letter dated 8/22/94

l. 1QgNTIFICATION OF COMPONENTS i

ISI Class 1 Integrally Welded Attachments to the Reactor Pressure Vessel, Examination Category B-H, item Number B8.10.

The specific Class 1 components affected by this relief request are detailed in Table RR 18-01.

II. CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED ASME Section XI,1980 Edition, through the Winter 1981 Addenda, Code Category B-H;

requires that 100% of the welds connecting all integral attachments to the Reactor Pressure Vessel be examined using the volumetric or surface examination methods. The required examinations shall be performed during the second inservice inspectxm interval in accordance with Table IWB 25001.

Relief is requested from performing a complete (100%) examination of certain Class 1 integrally i welded attachments due to physical plant restrictions.

Ill. BASIS FOR REllEF a

The components requiring relief are detailed in Table RR 18-01. The subject welded  :

attachments are the Eight (8) Reactor Pressure Vessel Stabilizer Bars. Access to perform

, complete examinations of these attachments is physically restricted by the bioshield wall.

Because the top of the shield wall is immediately adjacent to the underside of the stabilizer bar, access for examination of a portion of this region does not exist. Major plant modifications would be required to improve access and incrocse examination coverage. Included in Table l RR 18-01 is the pertinent information relative to the extent of examination which has been, or is  ;

j expected to be completed, along with the basis for the access restrictions.

i IV. ALTERNATE PROVISIONS Each of the Stabilizer Bars will be examined to the maximum extent possible, using the surface

examination method. No attemate provisions are appHcable in this situation.

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix A 18 Page 2 of 2 Relief Request RR 18 (Contd)

Revision 0 TABLE RR-18 01 l UNR 2 Component Limiting Examination Identification Description Condition  % Complete Support 1(IA) Stabilizer Bar Bloshield 76%

0 0 Deg.

Support-2(IA) Stabilizer Bar Bioshield 76 %

0 45 Deg.

Support-3(IA) Stabilizer Bar Bioshield 76%

o 90 Deg.

Support-4(IA) Stabilizer Bar Bioshield 76 %

i 0135 Deg.

Support-5(IA) Stabilizer Bar Bioshield 76 %

0180 Dog.

Support-6(IA) Stabilizer Bar Bioshield 76%

0 225 Deg.

Support 7(IA) Stabilizer Bar Bioshield 76%

O 270 Deg.

Support 8(IA) Stabilizer Bar Bioshield 76%

0 315 Deg.

UNIT 3 Support 1(IA) Stabilizer Bar Bioshield 76%

0 0 Deg.

Support-2(IA) Stabilizer Bar Bioshield 76 %

0 45 Deg.

Support 3(IA) Stabilizer Bar Bioshield 76 %

0 90 Deg.

Support 4(IA) Stabilizer Bar Bioshield 76%

0135 Deg.

Support 5(IA) Stabilizer Bar Bioshield 76%

O 180 Deg.

Support-6(IA) Stabilizer Bar Bioshield 76%

0 225 Deg.

Support 7(IA) Stabilizer Bar Bioshield 76%

0 270 Deg.

Support-8(IA) Stabilizer Bar Bioshield 76%

0 315 Deg.

1 1

l

Specification M 733, Rev. 2 PBAPS 2 & 3

! . ISI Program

( Appendix A 19 l Page 1 of 3 i

RELIEF REQUEST NO. RR 19 f Revision 0 j Submitted to NRC on 6/3/94 j Withdrawn on 12/29/94 l l. IDENTIFICATION OF COMPONENTS i

ISI Class 3 pressure retaining components in the Emergency Service Water (ESW) l System / Emergency Cooling Water (ECW) System.

4 j The ESW System is designed to provide a reliable supply of cooling water to the 1

emergency diesel generator engine coolers and selected equipment coolers and compartment air coolers during a loss of off-site power.

The ECW System is designed to provide an adequate on-site heat sink to be used in i conjunction wth High Pressure Service Water (HPSW) to support the Residual Heat Removal (RHR) System during reador shutdown, and with ESW to provide cooling for the

] reactor building cooling water heat exchangers, emergency diesel generator coolers, and the Emergency Core Cooling System (ECCS) pump room coolers during a loss of the Conowingo Pond or during a design basis flood. The ECW System also provides i sufficient water storage to allow operation of the emergency cooling tower for seven days, j without makeup.

The specific locatbn of the subject components, within the referenced systems, is 1 annotated on the attached schematic diagram of the ECW System. This portion of the l system is a ASME Class 3, moderate energy (i.e. less than 200* F max. operating i

temperature, and less than 275 psig max. operating pressure) cooling water system, and

!- does not normally operate.

i

11. CODE REQUIREMENTS FROM WHICH REllEF IS REQUESTED l ASME Section XI,1980 Edition through and including the Winter 1981 Addenda,

j. Subsections IWA-4000, IWD-4000, IWA 7000, and (WD-7000 provide rules for the repair j and replacement of pressure retaining components within the ASME Class 3 jurisdictional boundaries of the Section XI Code. While there is no prescrbed schedule for

) implementation of Class 3 repairs or replacements, PECO Energy's position is that the a

implied timely implementation of identified ASME Section XI Repairs or Replacements should be 30 calendar days. Acceieiv;y, PECO Energy Company requests one time j

schedular relief from the ir@ lied 30 day implementation schedule in order to develop and i

perform corrective actions, while avoiding a dual unit shutdown.

Ill. BASIS FOR RELIEF As documented in Nonconformance Report (NCR) PB 93-00809, a leaking pinhole indication was discovered in the ESW Booster Pump suction piping during plant operations. The structural integrity of the degraded piping was verified by computation, and therefore the operability of the system was confirmed. The NCR disposition was to

! i perform a non-Intrusive ASME Section XI welded Code repair to correct the situation.  ;

1 I 4

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f i

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- ., , - , . , - - , - - ---- - - .,-,-a m - , - , . - - - , , ,v-~

--w- - - -'

5

, Specification i M 733, Rev. 2

{ PBAPS 2 & 3

ISI Program Appendix A 19 j Page 2 of 3 l'

i Relief Request RR-19 (Cont'd)

] Revision 0

, evaluated and found acceptable, thereby reaffirming the operabilety of the component and system. The effects of the leakage on surrounding components and cooling capabilities of j the system were also evaluated and found to be acceptable. A revision to the original i NCR was then developed. The revised NCR disposition included intrusion into the system to perform both welded repairs, as well as potential replacement of pressure boundary j Components.

1 The above circumstances were communicated to the NRC during a conference call on i April 28,1994. The need for this relief request was discussed during the teleconference. It

, was determined that the relief request was not needed at that time, since a Code repair was planned for the immediate future.

i

Since the degraded component is located in a non-isolable portion of the system, common to both Unit 2 and Unit 3, special isolation techniques are required to implement the

. repairs, otherwise, a dual unit shutdown would be necessary. Repeated attempts to isolate i

the affected portion of the system, using freeze plugs, have been unsuccessful, thereby J delaying implementation of the planned repains beyond the time frame identified in the teleconference. Therefore, this relief request is being submitted.

i Also, because of the isolation problems described above, deferral of a Code acceptable i repair until the next refueling outage, in accordance with the guidance of Generic Letter 90-05, is not applicable; since a one unit refueling outage does not allow this portion of the system to be isolated.

l l While Code acceptable repair and replacement are still under consideration, PECO l' Energy is investigating other options, including an altemative repair.

l

! IV. ALTERNATE PROVISIONS

[ As a result of finding the pinhole leak in the pipe weld, ultrasonic (UT) thickness j measurements were performed at the as found indication as well as other locations around the weld. Subsequently, additional UT thickness measurements were performed to check for wall thinning or corrosion at other locations in this portion of the ESW System.

The results of these additional examinations were then used to reaffirm both structural

} integrity, as well as component / system operability. While the pinhole has stopped leaking,

, it continues to be visually monitored on a weekly basis. Additionally, follow-up NDE will be performed every 90 days to verify the condition of the degradation, until repairs can be

. perfonned. Expansion of the existing examination locations for raw water piping, l developed in accordance with Generic Letter 8913, will be assessed.

PECO Energy will keep the NRC Staff informed as to progress of Code repairs or any attemative repair techniques being considered for implementation. Verbal notification of which option will be pursued is expected on or before July 15,1994, it is intended that this relief will apply until either a Code acceptable repair is implemented, or until an attemative repair plan is autmtted to, and approved by the NRC.

4 l

. - , . , - * , -_-.,_ -.-m-- , ---- .-- ,--- ---- _ - + - - -

l

) Specification i M 733, Rev. 2

PBAPS 2 & 3 lSl Program l Appendix A 19 Page 3 of 3 i

i

Rollef Request RR 19 Rev. 0 (Cont'd)

! Figure RR 19.1 l,

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1

Specification M 733, Rev.2 Addendum 1 1

PBAPS 2 & 3 ISI Program 1

Appendix B Page 1 of 1 APPENDIX "B" TABLE OF CONTENTS

, AUGMENTED PROGRAMS AUGMENTED APPENDIX PROGRAM DESCRIPTION

, B1 - AUG 1 C41 NRC Generic Letter 88-01, Intergranular Stress Corrosion Cracidng l B-2 AUG 2 CE2 NUREG-0619, BWR Feedwater Nozzle and Control 4

Rod Drive Retum Line Nozzle Cracidng l 1

.B 3 AUG-3 C43 IE Bulletin No. 80-13, Cracking in Core Spray Spargers l B-4 AUG-4 NUREG/CR 3052. Closeout of IE Bulletin 80-07: BWR Jet Pur@ Assembly Failure

B-5 AUG-5 Snubber Examination and Test Program (Technical Specification Snubbers)

B-6 AUG-6 SIL No. 409, Incore Dry Tube Cracks

. B7 AUG 7 SIL No. 474, Steam Dryer Drain Channel Cracking B8 AUG-8 SIL No. 462, Shroud Support Access Hole Cover j Cracks l B-9 AUG-9 CM4 Generic Letter 94-03, Examination of RPV Core Shroud l l

Welds l B 10 AUG 10 SIL No. 554 & 588, Top Guide and Core Plate Cracking l 4

i 4

1

Specification ;

M 733, Rev. 2 l PBAPS 2 & 3 ISI Program Appendix B 1 Page 1 of 7 AUGMENTED INSPECTION PROGRAM 1: NRC Generic Letter 88-01, Intergranular Stress Conosion Cracking GENERAL This augmented program (AUG 1) defines the activitlea conducted during inservice inspection at PBAPS 2 and 3, pursuant to the examination requiremonts of NRC Generic Letter 88-01. This program addresses only those requirements dealing with periodic examination. Specific PECO Energy commitments concerning all of the aspects of NRC Generic Letter 88-01 are contained in the PECO Energy response to the letter, reference 1.1.4.

NRC Generic Letter 88-01 requires that an augmented inspection program be developed and implemented for certain au:teninc stainless steel piping webs and reactor vessel attachments. The technical bases for the NRC staff positions, put forth in the Generic Letter, are detailed in Reference 1.1.5. The apphcable requirements of the Generic Letter are summarized below.

DESCRIPTION OF NRC GENERIC LETTER 8801 CRITERIA USED TO DETERMINE THE EXTENT OF PEACH BOTTOM COMPONENTS WITHIN AUG-1 PROGRAM SCOPE NRC Generic Letter 88-01 r.pplies to piping system portions tha? meet the following criteria:

• austenitic stainless steel, a four inches or larger in nominal diameter, and

• contain reactor coolant at a temperature above 200'F, during power operation.

The following piping systems have portions which meet these criteria and are therefore within the scope of NRC Generic Letter 88-01:

• Reactor Recirculation System

• Residual Heat Removal System

. Core Spray System

• Reactor Water Clean-up System

• Reactor Pressure Vessel System The NRC Generic Letter also applies to reactor vessel attachments and appurtenances such as jet pump instrumentation penetration assemblies, and head spray and vent components.

The following Reactor Vessel attachments and appurtenances have portions which are within the scope of NRC Generic Letter 88-01:

• Reactor Vessel Stainless Steel Safe Ends >4' NPS.

- . - _ -. - . = - . - - -. - . . - -

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-1 Page 2 of 7 SCOPE OF COMPONENTS WITHIN THIS AUOMENTED PROGRAM Reactor Recirculation System (Loope A & B)

Reference:

PBAPS 2 and Common PalD's M-353, sht.1 and 2 l ASME Section XI isometric Dwgs: RCS-02-MI-201 1 A RCS-02 MI-201 1 B PBAPS 3 PalD's M-353, sht. 3 and 4 ASME Section XI Isometric Dwgs: RCS-02-MI-301-1 A l RCS-02-MI-301 1-B Scope:

28' NPS Reactor Recirculation Pumps A and B suction piping, from the welds joining the RPV N1 nonles to safe ends, through and including the welds to the Recirculation Pumps auction nonie.

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• 28' NPS Reactor Racirculation Pumps A and B discharge piping, from the weld to

the Recirculathn Pumps discharge nonie, through the 22' NPS headers and including the five (5),12' NPS piping segments, from the headers, to the RPV N2 i nonles to safe-end welds.

The weld connecting the 20' NPS RHR piping to the A pump suction, and the welds connecting the 24' NPS RHR piping to the A and B pump discharge.

Residual Heat Removal System

Reference:

PBAPS 2 4 PalD's M-361, sht.1 and 2 l ASME Section XI 4

Isometric Dwgs

DE 10-MI 203-9-A

, DE 10-MI-203-9-B DCN 10-MI-20716 PBAPS 3 i PalD's M 361, sht. 3 and 4 ASME Section XI

$ Isometric Dwgs: DCA 10-Mi-303-9-A DCA 10-MI-303-9-B DCA-10-MI 30613 l

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Specification M 733, Rev. 2 PBAPS 2 & 3 lSI Program

Appendix B 1 Page 3 of 7 Scope:

• 20' NPS RHR supply piping, from the connection at the A loop Reactor Recirculation Pump suction line, up to normally closed inboard containment isolation valve MO 18. (Note: RHR piping beyond valve MO 18 is below 200*F during reactor power operation and is therefore not in scope).

• 24' NPS RHR retum piping, from check valves AO-46A and B, to the Reactor Recirculation Pump A and B discharge piping. (Note: RHR piping beyond valves AO-46A and B is below 200*F during reactor power operation and is therefore not in scope.)

Core Spray System

Reference:

PBAPS 2 and Common P&lD M 362, sht.1 ASME Section XI lsometric Dwgs: DCN-14 MI-203-5-A DCN-14-MI 203-5 B PBAPS 3 PalD M-362, sht. 2 ASME Section XI lsometric Dwgs: DCN 14 Mi-303-4 A OCN 14-MI 303-4 B Scope:

• 12' NPS Core Spray supply piping, from valves 14A and B to the 10' NPS Reactor Vessel N5 nozzle to safe-end welds. (NOTE: The Core Spray piping beyond valves 14A and B is below 200*F during reactor power operation and is therefore

, not in scope).

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B 1 Page 4 of 7 Reactor Water Clean-Up System

Reference:

PBAPS 2 and Common

. PalD M-354, sht.1 ASME Section XI isometric Dwgs: DCA 12 Mi-201 1 DE 12 Mi 202 2 DCA 12-MI 203 3 DE 12 MI-203-4,5,6 PBAPS 3 P&lD M-354, sht. 2 ASME Section XI isometric Dwgs: DCA 12 MI 301 1 DE-12-Mi 302 2 DCA 12 MI-303-3 DE-12 MI-303-4,5,6 Scope:

• RWCU 6' NPS piping, from the connection at the RHR Pump suction piping, thru primary containment penetration N 14, and up to 6' x 3' reducers in the RWCU pump suction header.

RWCU 4' NPS piping, from 4' x 3' reducers in the RWCU pump discharge header, to the tube side inlet of the Regenerative heat exchanger.

RWCU 4' NPS piping from the tube side outlet of the Regenerative heat exchanger, to the tube side inlets of the Non-Regenerative heat exchangers.

RWCU 4' NPS retum piping, from the shell side outlet of the Regenerative heat exchanger, to RWCU check valve 62 Gust prior to retuming to the Feedwater System).

Reactor Pressure Vessel System (Jet Pump Instrumentation)

Reference:

PBAPS 2 and Common PalD M 352, sht.1 ISI Dwgs. ISI RPV-01 PBAPS 3 PalD M-352, sht. 3

] lSI Dwgs. ISI RPV-01

f Specification Mc733 Rev. 2 PBAPS 2 & 3 ISI Program Appendix B 1 Page 5 of 7

! Scope:

• Jet Pump Instrumentation Penetration seal to safe-end welds. These welds are associated with the N8 RPV nonles for Unit 2. The Unit 3 safe-ends and penetration seals are one piece forgings that do not have a safe end to penetration i seal weld.

Reactor Vessel Stainless Steel Sefe Ends The RPV attachments and appurtenances within the scope of this response are limited to stainless steel safe-ends, greater than 4' NPS, attached tp RPV nonles.

Reference:

PBAPS 2 and Common PalD M-351, sht.1 PalD M 352, sht.1 ISI Dwgs. ISI-RPV-05 PBAPS 3 PalD M-351, sht. 3 PalD M-352, sht. 3 ISI Dwgs. ISI-RPV 05 Scope:

4

• The stalniess steel safe-ends attached to RPV nonles N8, and N9.

Note: Safe-end attachment to RPV nonles N1, N2, and N5 are included, and have been previously identified within the scope description of the systems associated with these connections.

EXAMINATION PROGRAM NRC Generic Letter 88-01 requires that each pressure retaining weld, in scope components, be assigned to a category. The available categories are Category A thru Category G. The assignment of these categories is based on the degree to which the weld is susceptable to Intergranular Stress Corrosion Cracking (IGSCC). Category A welds are least susceptable, Category G welds are most

. susceptable. NRC Generic Letter 88-01 and NUREG 0313 Rev. 2 provide details on the determination of IGSCC category. The inspection frequency for each of the scope welds is determined by the IGSCC

, category that is assigned to the weld . This is explained in more detail under the section of this augmented program document entitled INSPECTION SCHEDULES.

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__ - - ...- - . - - - - . - - -. - . - .- . - . . ~ . . . _ - - - - - - .

r

! Specification

, Mo733, Rev. 2 I 1

PBAPS 2 & 3 i ISI Program Appendix B 1

!l Page 6 of 7 i

i l Inspection Methods and Personnel PECO Energy is committed to complying with the NRC Staff positions on inspection methods and j personnel as delineated in NRC Generic Letter 88 01. The inspection method to be performed is an j ultrasonic (UT) type volumetric exam. For UT inspectable ASME Class 1 and 2 weids, the IGSCC i inspections will generally be performed in accordance with the requirements contained in the applicable i edit 6on and addenda of ASME Section XI for the ASME class of the weldment. For UT inspectable

[ ASME Class 3 and non class welds, the requirements in Section XI for Class 2 welds will apply.

Details of the volumetric examination method may be upgraded as practical to ensure that the examinations will be effective. The personnel performing the IGSCC volumetric inspections will be j qualified for such inspections by a formal program approved by the NRC.

Inapection Schedules 4

i The inspection frequencies in this augmented program conform to the NRC staff positions provided in j Generic Letter 88-01. The frequency of inspection depends on the IGSCC category that the weld is

)

assigned to. The inspection frequencies are as follows:

! IGSCC CGlocorv Insoection Extent and Schedule i A 25% overy 10 years (at least 12% in 6 years) i 8 50% overy 10 years (at least 25% in 6 years) i C All within next 2 refueling cycles and then all every 10 years (at least j 50% in 6 years) i

D All every 2 refueling cycles  !

j E 50% next refueling outage, then all

every 2 refueling cycles F All every refueling outage  ;

1 G All next refueling outage i j '

RWCU 10% sample per outage

, outside f containment

! The IGSCC category assigned depends on such factors as whether stress improvement is performed, whether cracks are known to exist in the weld, whether the weld la reinforced by overlay, corrosion resistant cladding has been approved, what the base and weld material are, and whether the weld has i been UT inspected utilizing the inspection methods and personnel indicated in the Generic Letter.

t Since some of these factors can change, the IGSCC category assigned to a particular weld is also l subject to change.

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-1 Page 7 of 7 Weld Selection Where the augmented program required examination of a sample of applicable welds, the size and content of the sample was determined from the total population of circumferential butt welds subject to the program requirements.

The selection of welds for examination under this augmented program has been coordinated with the

, selection of welds for examination under the ISI Program, (i.e. If a weld requiring augmented examination is selected for ISI Exam, it was also selected for augmented examination). The examination requirements of both the ISI Program and the Augmented Program are therefore satisfied simultaneously, to the extent that those requirements overlap (i.e., a single volumetric examination performed to satisfy all angmented requirements, and the voumetric examination requirements of the ISI Program). This selection philosophy has been reviewed and deemed to yield a representative sample of the welds requiring the augmented examinations.

4 Augmented Program Tables (AUG-1) for PBAPS 2 & 3 list, by system, the total population of welds

subject to examination under this augmented program. Specifically, these tables identify the weld by identification number, the AGME Section XI drawing depicting the weld, the IGSCC Examination Category assigned to the weld, the inspection method planned for the weld (if selected), if the weld has d

been selected for the ISI examination, and finally an indiction of whether the weld is selected for augmented examination. Notes may also be provided as necessary.

Sample Expansion if one or more Category A, B, C, or D welds are found to be cracked, or if additional cracks or significant crack growth is discovered in a Category E weld during the interval, a sample expansion plan will be invoked. The cample expansion plan utilized will be as put forth in the Staff Position on Sample Expansion of NRC Generic Letter 88-01, including Supplement 1.

NRC Notification If any flaws are identified which do not meet the acceptance criteria for continued operation (referenced below under flaw evaluation), the NRC will be duly notified of the disposition of the affected flaws. NRC approval of the disposition for each flaw exceeding the criteria will be obtained before operation is resumed. All communication with the NRC will comply with the requirements of the PECO Energy i Corporate ISI/IST Administrative Manual, l

Flaw Evaluation l Flaws exceeding the acceptance criteria of IWB-3500 of ASME Section XI will be evaluated, then either repaired, replaced, or deemed acceptable for continued operation. Repairs or replacements will be documented in the Owners Report for Repairs and Replacements as required by ASME Section XI.

Evaluations of flaws for continued operation will be performed in accordance with the criteria in IWB-3600 of ASME Section XI. For aspects of flaw evaluation which are not contained in IWB-3600, the requirements in NUREG-0313 Revision 2 will be used in conjunction with IWB-3600. l The above referenced criteria for acceptance and evaluation are found in the 1986 Edition of ASME Section XI.

t

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t Specification i

M 733, Rev. 2

PBAPS 2 & 3

ISI Program Appendix B 2 Page 1 of 8 1

1

! AUGMENTED INSPECTION PROGRAM - 2: NUREG-0619, BWR Feedwater Nonle and Control Rod Drive Retum Une Nonle Cracking

1. RQQEE

! This augmented inspection program (AUG 2) defines the mandatory inspection requirements of 4

NRC NUREG 0619 applicable to the PBAPS Units 2 & 3 Feedwater nonles/spargers.

! Inspections manaelated with the Control Rod Drive Retum Uno (CRDRL) nonle (N9)/ piping system are not required at PBAPS 2 & 3. The CRDRL nonles (one per unit) have been cut and capped and the CRDRL eliminated. Augmented examinations per NUREG-0619 are not applicable.

Inspection requirements, as detailed in this document, are exclusive of those ASME Section XI inservice inspection requirements for the Feedwater nonles/spargers and the CRDRL nonle; however, where possible, individual examinations performed may be used to satisfy both j requirements (See ISI Program Tables for common components).

1

11. REFERENCES i

$ A. NUREG-0619, BWR Feedwater Nonle and Control Rod Drive Retum Une Nonle

Cracking (November 1980) w;th Generic '.atter 81 11 (February 20,1981).

B. PECo letter of January 21, W1 A W. Gallagher to Darrell G. Eisenhut (NRC).

C. PECo letter of September 29,1983, J. W. Gallagher to Darrell G. Eisenhut (NRC).

lil. GENERAL i

in order to facilitate early detection of the initiation of feedwater nonle thermal fatigue cracking j and thereby limit crack growth within the bounds of approved repair methods, NUREG-0619

' requires the implementation of a plant specific inspection program in accordance with

Section 4.3 of the NUREG.

i The PBAPS 2 & 3 reactor pressure vessels have six (6) feedwater nonles, in accordance with General Electric Company recommendations intended to minimize the probability of thermal fatigue crack initiation and growth, the PBAPS 2 & 3 feedwater nonles have undergone j modifications to remove the nonle cladding and replace the original feedwater spargers with j improved design ' triple sleeve spargers' on all noules. These modifications were

' accomplished in Spring 1980 for Unit #2 and Spring 1981 for Unit #3. The routine inspection program required by Table 2 of the NUREG for the PBAPS 2 & 3 specific nonle configuration is detailed in Table B 21 and Section IV of this document.

IV. FEEDWATER NOZZLE INSPECTION PROGRAM The PBAPS 2 & 3 inspection program requirements, based on the ' triple-sleeve spargers with

two piston-ring seals, clad removed

• configuration is lilustrated below:

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B 2 Page 2 of 8 ROUTINE INSPECTION INTERVALS Inspection Intervais* Refueling Cycles (or Startuo/ Shutdown Cycles)

Visual Inspection Routine E of Soaroer PT PBAPS 2 & 3 2 4 9 (or 135)

The inspection interval began Spring 1980 and Spring 1981 for Unit 2 and Unit 3 respectively.

Ultrasonic (UT) examinations shall be performed on all feedwater nozzle to safe end welds, nozzle bores and inside biend radii once eve y two (2) refueling cycles. These examinations shall be performed to the extent shown in Figure B 21 utilizing ultrasonic (UT) examination techniques designed to optimize detection of small thermal fatigue cracks given the specific feedwater nozzle forging configuration.

Visual examination of the feedwater spargers shall be performed once every four (4) refueling cycles This examination shall include the entire sparger with special attention given to the junction point of the sparger arms and the flow nozzles (Figure B-2 2).

Routine dye-penetrant (PT) examinations shall be performed the lesser of once every nine (9) refueling cycles or upon achieving 135 startup/ shutdown cycles.' A complete routine PT consists of PT examination of accessible portions of the nozzle bore and inner radius of all feedwater nozzles (sparger intact).

' A startup/ shutdown cycle is defined as a reactor thermal power increase from nominally zero, and subsequent retum to zero, which produces both pressure and temperature changes and involves the flow of any amount of cold feedwater through the feedwater nozzles, including scrams to low-pressure hot standby and conventional startup/ shutdowns.

i f'

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Specification M-733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-2 Page 3 of 8 l .

'In light of the difficulties associated with routine PT examinations radiological environment, access provisions PECO Energy is continuing to monitor advances in ultrasonic examination

, techniques which may facilitate elimination of the requirement for PT examination completely.

V. INSPECTION RESULTS If upon completion of the required ultrasonic examinations, Indications are discovered, the indications shall be dispositioned as follows:

A. Ultrasonic indications in the nonle to safe end weld shall be evaluated per ASME Section XI, 1

B. Recordable ultrasonic indications, in any nonie, interpreted to be cracked shall i necessitate a follow up penetrant examination (PT) of the entire affected nonle (sparger j removed) and the accessible portions of the remaining nonles, C. Confirmation of cracking by penetrant examination (PT) shall require removal of all remaining feedwater spargers and subsequent complete PT of all noules, and D. A!! nonle cracks shall be repaired using approved repair plans.

, Visual examination test results shall be evaluated in accordance with ASME Section XI.

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Cracking discovered during routine penetrant examinations shall be dispositioned as follows:

A. The sparger(s) of the affe%c nonle(s), and all remaining spargers shall be removed, and

the entire nonle bore ud inner radius of all nonies penetrant (PT) examined, and B. All nonle cracks shall be repaired using approved repair plans.

. VI. REPORTS / RECORDS '

i Within six (6) months of completing an outage during which an inspection (UT, PT or VT) was I performed in accordance with NUREG-0619, a detailed report discussing the inspection shall be submitted to the Regional Director, inspection and Enforcement with copies to the Director, inspection and Enforcement, and the Director, Nuclear Reactor Regulation. The report shall include the following information:

A. Number of startup/ shutdown cycles since the previous inspection and the total number of cycles, B. Summary of methods used and results of previous inspections, including maximum crack depth and previous number of cracks detected / repaired.

C. Description of system / operational changes that should be considered in predicting future crack initiation and growth, and 1

I D. A detailed discussion of inspection results. l l

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-2 Page 4 of 8 All records associated with the subject inspections shall be nulntained in accordance with ASME Section XI and plant procedures.

NOTE: Inspections, as required by this augmented program, are typically performed during a normal refueling outage in which routine ASME Section XI inservice inspections (ISI) are also performed. ASME Section XI requires that a summary report be filed, within 90 days of completion of the inservice inspection, with jurisdictional enforcement and regulatory authorities. Due to the similar nature of these activities, reports as required by this augmented program may be submitted in conjunction with the ISI summary report provided the reporting requirements of this augmented program are met.

4 E

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l Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B 2 Page 5 of 8 TABt.E B 21 AUGMENTED EXAMINATION PROGRAM 2 Inspection Interval (No. of Exam Area Figure NDE Refueling Identification Number Number Method hien) Notes N4A Noz to Safe End Wold B21 UT 2 N4A Noz Bore B-2 1 UT 2 B21 PT 9 (or 135 Startup/ Shutdowns)

N4A Noz Inner Radius B21 UT 2 B21 PT 9 (or 135 Startup/ Shutdowns)

N4A Sparger B-2-2 VT 4 N48 Noz to Safe End Weld B21 UT 2 N48 Noz Bore B21 UT 2 B21 PT 9 (or 135 Startup/ Shutdowns)

N4B Noz inner Radius B-2 1 UT 2 B-2 1 PT 9 (or 135 Startup/ Shutdowns)

N48 Sparger B22 VT 4 N4C Noz to Safe End Weld B21 UT 2 N40 Noz Bore B21 UT 2 B21 PT 9 (or 135 Startup/ Shutdowns)

N4C Noz Inner Radius B21 UT 2 B21 PT 9 (or 135 Startup/ Shutdowns)

N40 Sparger B22 VT 4 1 1

N4D Noz to Safe End Weld B21 UT 2

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B 2 Page 6 of 8 TABLE B 21 AUGMENTED EXAMINATION PROGRAM 2 inspection interval (No. of Exam Area Figure NDE Refueling Identification Number Number Method Cycles) Notes N40 Noz Bore B-2 1 UT 2 B21 PT 9 (or 135 Startup/ Shutdowns)

N4D Noz Inner Radius B21 UT 2 B-2 1 PT 9 (or 135 Startup/ Shutdowns)

N4D Sparger B22 V7 4 N4E Noz to Safe End Weld B21 UT 2 N4E Noz Bore B-2 1 UT 2 B21 PT 9 (or 135 Startup/ Shutdowns)

N4E Noz inner Radius B21 UT 2 B21 PT 9 (or 135 Startup/ Shutdowns)

N4E Sparger B22 VT 4 N4F Noz to Safe End Weld B21 UT 2 N4F Noz Bore B21 UT 2 B21 PT 9 (or 135 Startup/ Shutdowns)

, N4F Noz Inner Radius B21 UT 2 B-2 1 PT 9 (or 135 I Startup/ Shutdowns)

N4F Sparger B22 VT 4

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-2 Page 7 of 8 Figure B-2-1 Feedwater Nozzle Extent of Examination l

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i Specification l M 733, Rev. 2 PBAPS 2 & 3 ISI Program

Appendix B-2

, Page 8 of 8 4

Figure B-2-2 l

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Specification l M 733, Rev. 2 Addendum 1 PBAPS 2 & 3

ISI Program 4

Appendix B-3

Page 1 of 3 i

AUGMENTED INSPECTION PROGRAM - 3: IE Bulletin No. 80-13, Cracking in Core Spray Spargers j l. }&QPg a

j This augmented inspection program (AUG-3) defines the mandatory inspecik,n requirerr ents of i NRC IE Bulletin 80-13 applicable to the PBAPS 2 & 3 Core Spray Sparger and Core Spray supply header piping.

Inspection requirements, as detailed in this document, are exclusive of those ASME Section XI i inservice inspection requirements for the Core Spray spargers/ supply header piping; however, I' where possible, individual examinations performed may be used to satisfy both requirements.

1 (See ISI Program Tables for common components).

11. REFERENCES l

! A. IE Bulletin No. 80-13, Cracidng in Core Spray Spargers, dated May 12,1980.

i l B. PECo letter of June 13,1980, S. L. Daltroff to Boyce H. Grier (NRC).

1 j C. General Electric Company SIL No. 289, Core Spray Visual Inspection Revision 0, dated February 1979 and including Revision 1, Supplement 1, Rev.1 dated March 15,1989.

j

D. PECO Energy NCR PB 9340754, Core Spray Pipe in RPV with 3 inch Linear Indication, dated 10/25/93.

j 111. GENERAL

< Instances of intergranular stress corrosion cracking (IGSCC) in Core Spray spargers have been reported in IE Bulletin 80-13. The key contributors to IGSCC are plant specific, however;

stresses in the stainless steel spargers from cold work and sensitization during fabrication and l Installation, coupled with service in the BWR environment, are all considered prime factors.

! In addition to the sparger piping, other welds on the "T-box"(Just inside of the RPV nozzle in the Core Spray header (supply piping) have been identified as susceptible to cracking (Reference C).

Failure of either of these critical RPV intemal cornponents could result in poor cooling distribution and/or reduced flow to the core during activation of the Core Spray system. For this reason, IE Bulletin 8013 mandates routine inspections of the subject components as detailed in i Table B-31 and Section IV of this document.

IV. CORE SPRAY SPARGER/ PIPING INSPECTION PROGRAM 1

i Visual examination of the PBAPS 2 & 3 Core Spray spargers and supply header piping shall be 4

performed at each refueling outage. The inspection area shall include:

A. All spargers and piping within the shroud, l

I l

L Specification l

M 733, Rev. 2 PBAPS 2 & 3 f ISI Program

Appendix B-3 Page 2 of 3

Failure of either of these critical RPV intomal components could result in poor cooling distribution and/or reduced flow to the core during activation of the Core Spray system. For this reason, lE Bulletin 80-13 mandates routine inspections of the subject ceirvonents as detailed in Table B41 and Section IV of this document.

IV. CORE SPRAY SPARGER/ PIPING INSPECTION PROGRAM Visual examination of the PBAPS 2 & 3 Core Spray spargers and supply header piping shall be performed at each refueling outage. The inspection area shall include:

A. All spargers and piping within the shroud, B. All supply header piping from the RPV inlet nozzle to the RPV shroud, and C. The "T-box' front cover plate welds.

' Due to RPV conditions during a normal refueling outage, the required visual examinations are performed utilizing a remote underwater TV camera. Adequate resolution to satisfy the IE Bulletin shall be demonstrated by insitu viewing of 0.001 in. (1 mil) diameter fine wires.

V. INSPECTION RESULTS All relevant conditions identified during the required examinations of this augmented program shall be recorded , characterized, and evaluated as to type of defect, location and extent.

Supplementary examinations, where practical, may be performed to aid in evaluation of the

. Indications.

All cracks shall be reported to the Director - NRC Region I within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of identification.

VI. REPORTS / RECORDS In the event of identified cracks, an evaluation report shall be submitted to NRC NRR for review and approval prior to retum to operation.

A detailed report of the results of the examinations and corrective actions taken (if any) shall be submitted to the Director - NRC Region I (Copy to NRC Office of I & E, Washington D.C.).

All records associated with the subject examinations shall be maintained in accordance with ASME Section XI and plant procedures.

NOTE: Inspections, as required by this augmented program, are typically performed during a normal refueling outage in which routine ASME Section XI inservice inspections (ISI) are also performed. ASME Section XI requires that a summary report be filed, within 90 days of cciTp;etion of the inservice inspection, with jurisdictional enforcement and regulatory authorities. Due to the similar nature of these activities, reports as required by this augmented program may be submitted in conjunction with the ISI summary report provided the notification requirements of this augmented program are met (e.g. l new or additional cracks found). '

l

Specification M 733 Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-3 Page 3 of 3 TABLE B-31 AUGMENTED EXAMINATION PROGRAM 3 Exam Area NDE Examination Identification Number Method Frecuency Notes

'A' CS Sparger VT* Every Refueling CS Piping within the Outage shroud

'B' CS Sparger VT* Every Refueling CS Pipiry within the Outage shroud

'C' CS Sparger VT* Every Refueling CS Piping within the Outage shroud

'D' CS Spayr VT* Every Refueling CS Piping within the Outage shroud

'A&C' CS Supply VT* E<ery Refueling From NSB nozzle to Header Piping ' Outage shroud entrance

'B&D' CS Supply Vi* Every Refueling From NSA nozzle to Hander Piping Outage shroud entrance  !

'T-box' froni cover VT* Every Refueling plate welds Outage Visual examination with dernonstrated resolution to detect in situ 0.001 diameter fine wires.

I

Specification

M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-4 Page 1 of 3 AUGMENTED INSPECTION PROGRAM - 4: NUREG/CR-3052, Closeout of IE Bulletin 80-07: BWR Jet Pump Assembly Failure

1. SCOPE This augmented inspection program (AUG 4) defines the recommended inspection requirements of NRC NUREG/CR-3052 applicable to the PBAPS 2 & 3 Jet pump hold-down beam assemblies.

11. REFERENCES A. NUREG/CR 3052, Closeout of IE Bulletin 80-07: BWR Jet Pump Assembly Failure, November,1984.

B. IE Bulletin No. PO47, BWR Jet Pump Assembly Failure, dated April 4,1980, and including Supplement No.1 dated May 13,1980.

C. General Electric %mpany, SIL No. 330, Jet Pump Beam Cracks, June 9,1980.

D. PECo letter of Mt4y 2,1980, S. L. Daltroff to Boyce W. Grier (NRC).

E. PECo letter of May 7,1980, S. L Daltroff to Boyce W. Grier (NRC).

Ill. GENERAL The occurrence of BWR Jet pump hold-down beam cracking and/or failures at several domestic BWRs resulted in the issuance of NRC IE Bulletin 80-07, which mandated both visual and ultrasonic inspection of the jet pump hold-down beam astemblies at operating BWRs, including l PBAPS 2 & 3. Intergranular stress corrosion cracking (IGECC) has been identified as the failure mechanism of the beams.

There are twenty (20) Jet pump hold-down beams per unit at PBAPS. As a required action of IEB 80-07, all of the " original BWR/4' hold-down beams installed on PBAPS 2 & 3 were subsequently visually and ultrasonically inspected for evidence of lack of integrity of the hold-down beams due to IGSCC. Ultrasonic examinations on PBAPS #3 revealed one (1) beam with confirmed cracking; inspections on PBAPS #2 determined all beams intact.

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Sp.c m u M-733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-4 Page 2 of 3 General Electric Company's preferred resolution to the problem was the design and manufacture of an improved Jet pump hold-down beam with a new heat treatment. This irnproved beam coupled with installation at a reduced preload is expected to have a significantly increased service life, in 1984 (Unit #2) and 1988 (Unit #3), all original hold-down beams at PBAPS 2 & 3 were replaced with the ' improved BWR/4 beam design with improved heat treatment

• and 25 kips (vs. 30) preload.

IV. INSPECTION PROGRAM installation of new BWR/4 beams with the new heat treatment and reduced preload on PBAPS 2 & 3 satisfies the requirements of IEB 80-07. As such, the bulletin may be considered closed and there are no further requirements for nondestructive examination of the beams. However, per NUREG/CR-3052, due to lack of plant experience with the new design beam, it is recommended that ultrasonic examination of all jet pump hold-down beams be performed once every ten (10) years. Note: Ten (10) years means ten (10) years of service above 200* F, and not ten (10) calendar years.

INSPECTION FREQUENCY PBAPS #2 UT once every 10 years JET PUMP HOLD DOWN BEAMS following installation of JP #1 THROUGH JP #10 the new beam.'

(20 TOTAL)

PBAPS #3 UT once every 10 years JET PUMP HOLD-DOWN BEAMS following installation of JP #1 THROUGH JP #10 the new beam 88 (20 TOTAL)

! 1) The PBAPS #2 new beams were installed August of 1984.

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2) The PBAPS #3 new beams were installed August of 1988. l

3) Beam #6 on PBAPS #3 was installed in Spring,1981, to replace the original beam with

confirmed IGSCC.

Ultrasonic examinations shall be performed with technique intended for the detection of IGSCC in the given configuration.

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1 Specification M 733, Rev. 2 PBAPS 2 & 3

ISI Program Appendix B-4 i

Page 3 of 3 V. INSPECTION RESULTS Ultrasonic indications identified during the required examinations of this augmented program j shall be recorded, characterized, and evaluated as to type of defect, location and extent.

Per General Electric Company recommendations, beams having crack indications should be considered for replacement.

VI. RECORDS / REPORTS All records / reports shall be in accordance with ASME Section XI and plant procedures.

4 NOTE: Inspections, as required by this augmented program, are typically performed during a normal refueling outage in which routine ASME Section XI inservice inspections (ISI) are also performed. ASME Section XI requires that a summary report be filed, within 90 days of completion of the inservice inspection, with jurisdictional enforcement and

regulatory authorities. Due to the similar nature of these activities, reports as required by this augmented program may be submitted in conjunction with the ISI summary report.

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! l Specification l M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-5

Page 1 of 28 i

AUGMENTED INSPECTION PROGRAM 5: Snubber Examination and Test Program (Technical Specification Snubbers)

NOTE: This Augmented Program is planned for implementation after adoption of Improved

. Technical Specifications.

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1. SCOPE 1

This augmented inspection program (AUG-5) defines the mandatory examination and testing I requirements for snubbers. This program has been prepared as a complete replacement for l j the Surveillance Requirements of PBAPS 2 & 3 Technical Specification 3/4.11.D.

All snubbers installed on the reactor coolant system and all other safety related systems are  ;

subject to the requirements of this augmented inspection program. Snubbers installed on

{ nonsafety related systems are also within the scope of this program and may be excluded only

{ if their failure or failure of the system on which they are installed would have no adverse effect j on any safety related system. 1 1

Examination and testing requirements of this augmented inspection program apply to the

, snubber assembly which includes the snubber body and attachments out to and including the load pins and their retainers (Figure B-5-1). Snubber support components beyond this defined space are outside of the scope of this augmented inspection program.

A complete listing of all snubbers within the scope of this augmented inspection program is l provided in the Augmented Program (AUG-5) Tables, j 11. REFERENCES A. ANSl/ASME Operations and Maintenance Standard OM-1987 with OMc-1990 Addenda, Part 4 (including additional industry / committee studies).

B. PBAPS 2 & 3 Technical Specification 3/4.11.0 Snubbers

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i Specification ,

M-733, Rev. 2 PBAPS 2 & 3 ISI Program -

Appendix B-5 Page 2 of 28 i' 111. DEFINITIONS A. Activation - the parameter that verifies restraining action.

J j B. _ Appication Induced Failure - failures resulting from environmental conditions or application of the snubber for which it has not been designed or qualified.

i C. Breakaway Force - the minimum applied force required to initiate extension or retraction of the snubber.

D. Defined Test Plan Group a population of snubbers having similar design or application '

characteristics selected for testing in accordance with the 10 percent or 37 testing

. sample plan.

4 E. Design or Manufacturing Failure - failures resulting from a potential defect in manufacturing or design that give cause to suspect other similar snubbers. This includes 4

failures of any snubber (s) that fails to withstand the environment or application for which it was designed.

F. Drag Force - the force required to maintain the snubber movement at a constant velocity J

prior to activation.

G. _ Equipment Dynamic Restraint (Snubber) - a device wtDh provides restraint to a i ccmf,onent or system during a sudden application of forces but allows essentially free motion during thermal movement.

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l H. Examination Group - a composition of snuuoers which have been selected to be

, examined.

F

l. Examination the performance of visual observations for impaired functional ability due i to physical damage, leakage, corrosion or degradation from environmental or operating i conditions.

j J. Failure Mode Group - a composition of snubbers whose failure and potential for the j same failure is similar.

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. Specification l M 733, Rev. 2 i

PBAPS 2 & 3 ISI Program Appendix B-5 Page 3 of 28 K. Inaccessible Snubbers - those snubbers that are in a high radiation area or other i conditions that would render it irrge.:,tical for the snubbers to be examined under normal

plant operating conditions without exposing plant personnel to undue hazards.

L leolated Failure - the nature of the failure does not lend other snubbers to be suspect.

For example, failures resulting from damage during installation or shutdown (i.e., dropping equipment or tools on the snubber, missing pins, etc.).

4 M. Maintenance - replacement of parts, adjustments, and similar actions which do not

change the design of the snubber, taken to prevent deficiencies in the function of a l

snubber.

4 i N. Maintenance, Repair, installation Induced Failures failures which result from damage during maintenance, repair, or installation activities, the nature of which lends other snubbers to be suspect.

O. Mechanical Snubbers - devices in which load is transmitted entirely through mechanical cOmpOir66ts.

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P. Modification - alteration in the design of a snubber to improve its suitability for a given 1

environment or application

, Q. Normal Operating Conditions - operating conditions during reactor startup, operating at power, hot standby, reactor cooldown to cold shutdown.

R. Operability Testing measurement of parameters that verify snubber operability.

S. Operating Temperature - the temperature of the environment surrounding a snubber at its installed plant location during the phase of plant operation for which the snubber is required.

l T. Qualitative Testing - that testing performed to establish the functioning of a parameter without determining the specific measure of the parameter, similar to go/no-go gaurjing.

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-5 Page 4 of 28

U. Quantitative Testing that testing performed to establish the specific measure or the limit of the functioning of a parameter, such as that required to establish that a parameter is

] functioning within a specified range.

V. Release Rate - the rate of the axial snubber movement under a specified load after

, activation of the snubber took place.

W. Repair - replacement of parts and sinnlar actions which do not change the design of the snubber, taken to correct deficiencies in the function of a snubber.

X. Replacement Snubber - any snubber other than the snubber immediately previously installed at the location.

Y. Swing Clearance - the movement envelope within which the snubber must operate without restriction, from the cold installed position to the hot operating position.

j Z. Test Temperature - the temperature of the environment surrounding the snubber at the j time of the test.

AA. Unacceptable Snubbers - those snubbers which do not meet examination or testing requirements.

1 AB. Unexplained Failure - failures that cannot be categorized as design or manufacturing, i maintenance, repair, installation, application induced, or isolated. This includes all j failures for which the cause of the failure cannot be determined.

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Specification t

M-733, Rev. 2 PBAPS 2 & 3 ISI Riogram t

Appendix B 5 Page 5 of 28 i

) Figure B 51 3 Snubber Scope of 1l Examination /Testina 4

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1 SNUBBER ASSEMBLY (PIN to PIN)

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Specification M 733, Rev. 2 PBAPS 2 & 3

ISI Program Appendix B-5 Page 6 of 28

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IV. GENERAL SNUBBER EXAMINATION AND TESTING REGUIREMENTS J

Snubbers are installed on safety and nonsafety related systems at PBAPS 2 & 3 to ensure the continued structural integrity of the reactor coolant system and other safety related systems following a seismic or other event initiating dynamic loads. As such, assurance of the ability of j these snubbers to perform as designed through examination and testing is imperative.

l Requirements for examination and testing of snubbers are addressed by regulatory and industry groups in plant Technical Specifications, ASME Section XI, ANSI, OM-1987 with OMc-i 1990 Addenda and INPO good practices. This augmented program, prepared by PECO Energy, is intended to provide a comprehensive program which demonstrates the operability of applicable PBAPS 2 & 3 snubbers and effectively addresses both regulatory and industry 4

concems regarding snubber examination and testing.

This augmented program constitutes the ' Surveillance Requirements'section of plant Technical Specification 3/4.11.D. Requirements of Technical Specification 3/4.11.D, other than surveillance requirements, still apply.

A. Responsibility l PECO Energy, as owner of PBAPS 2 & 3, is responsible for the preparation and

implementation of this program including

a) Implementation of the requirements of this program in accordance with site administrative procedures and the Quality Assurance Program.

b) Qualification of personnel performing the examinations and tests.

c) Preparation of all necessary written procedures for complying with the j requirements of this program.

d) Collection and retention of all design and operating information necessary for the performance of the examination and testing program. This information shall be available for use during implementation of the program.

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Specification M-733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-5 Page 7 of 28

8. Procedures Examinations, tests, and maintenance or repair activities shall be performed in accordance with written procedures.

C. Examination and Test Results The results of all examination and testing shall be documented and shall. include as a minimum:

a) Manufacturer's model number, serial number, type, unique location identification and/or PECO Energy identification of the snubber, as applicable, b) Pertinent examination and test data.

c) Identification and disposition of nonconformances.

d) Information to identify the test / examination performed, procedure used, and date.

e) Test equipment used.

f) Acceptability of test / examination results.

g) Identification of examination and test personnel.

D. Personnel Qualifications Test Personnel who are required to witness, perform, and/or evaluate the snubber testing shall be qualified in accordance with site administrative procedures. Examination personnel performing and evaluating visual examinations shall be qualified for VT-3 and VT 4 visual examination in accordance with ASME Section XI 1980 Edition, up to and including the Winter 1981 Addenda (1980W81), or PECO Energy approved equivalent.

E. Instrumentation and Test Equipment

! Instrumentation and test equipment used to verify snubber performance shall have the range and accuracy necessary to demonstrate conformance to specific examination or test requirements.

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Specification M 733 Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-5 i Page 8 of 28 All instruments and test equipment used in performing the examination and testing program shall be calibrated and controlled in accordance with site administrative i procedures.

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F. Snubber Maintenance or Repair i

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Snubbers within the scope of this program shall not be subjected to maintenance or

' repair prior to examination and/or testing specifically for the purpose of meeting the  ;

examination and/or testing requirements. The preventative or corrective actions required I

by the PBAPS Quality Assurance Program shall supercede this requirement. i J

G.' Post Maintenance Examination and Testing Maintenance activities which can alter the snubber's intended function shall be evaluated 1 by considering the effects of the maintenares on the snubber's ability to meet the  !

examination and testing acceptance criteria. Snubbers which undergo maintenance j  !

' activities which could alter the snubber's ability to perform its intended function shall be l examined and tested in accordance with the applicable requirements of Section V of this i

appendix. The requirements selected shall ensure that the function (s) which may have

" l been affected are verified by the examination or tests to be acceptable.

i The site administrative procedures goveming maintenance activities shall address these requirements.

, H. Snubber Repair, Replacement, or Modification All snubbers within the scope of this program shall be repaired, replaced or modified in

( accordance with ASME Section XI and site administrative procedures.

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Specification l M-733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-5 Page 9 of 28 1

Repair activities which can alter the snubbers intended function shall be evaluated by considering the effects of the repair on the snubbers ability to meet the examination and testing acceptance criteria. Snubbers which undergo repair activities which could alter i

the snubbers ability to perform its intended function shall be examined and tested in accordance with the applicable requirements of Section V of this appendix.

i Replacement or modified snubbers shall be visually examined in accordance with the requirements of Section V of this appendix.

Visual examinations or operability testing, as may be required above, shall be addressed

. In site administrative procedures goveming ASME Section XI repair / replacement activities.

i 1. Deletion of Unacceptable Snubbers When unacceptable snubbers are deleted (based on analysis of the affected piping system), the deleted snubber (s) shali, nevertheless, be considered in its respective i failure mode group; and the effect of the corrective action taken, for the balance of the i failure mode group, shall apply. For example, for the purposes of the applicable

! corrective action, the deletion of the snubber may be considered the same as l replacement with a snubber qualified for the application.

J. Transient Dynamic Event If a transient dynamic event occurs which may affect operability, the affected system (s) and associated snubbers shall be reviewed and any appropriate corrective action taken.

Any corrective actions taken are independent of the examination and testing

, requirements of this program.

f K. Supported Component (s)/ System Evaluation An engineering evaluation shall be performed of component (s) and/or system (s) on which an unacceptable snubber is installed for possible damage to the supported system l and/or component.

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Specif'cation M 733 Rev. 2 PBAPS 2 & 3 ISI Program Appendix B 5 l Page 10 of 28

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l V. SNUBBER EXAMINATION AND TESTING PROGRAM Each snubber within the scope of this augmented program shall be demonstrated operable by l performance of the program requirements as detailed in this Section.

l Certain snubbers may be waived in part or totally from the requirements of this program (on a case-by-case basis), provided technical justification for the deviation be filed with regulatory authorities prior to implementation of the deviation.

A. Visual Examination Visual examination for operational readiness is required for snubbers with the frequency of reexamination being determined by the number of unacceptable snubbers within a group and the corrective action taken.

Visual examination shall be performed to identify physical damage, leakage, corrosion, or degradation from environmental exposure or operating conditions. Extemal features which may indicate operability of the snubber shall be examined. An examination checklist shall be prepared for this purpose.

The initial visual examinations performed in accordance with this augmented program shall be implemented during the first refueling outage following regulatory acceptance of this program.

1) Examination Documentation The following documentation is necessary to support implementation and verification of the visual examinations:

a) Examination procedures and checklists verifying examination and as-found conditions.

i b) Examination records.

c) Thermal movement inspection records.

d) Records of nonconformance and corrective actions that are required.

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Specification

M-733, Rev. 2 l PBAPS 2 & 3

, ISI Program Appendix B-5 Page 11 of 28

2) Snubber Categorization Snubbers may be categorized and grouped as accessible and inaccessible; these groups may be considered separately for the purpose of visual examination.

4 Determination of accessble/ inaccessible snubber groups and plans for separate

! or joint application of program requirements by group shall be made and documented prior to initiating examinations for a given examination interval. Once determined, groups shall be used throughout the examination interval and shall 4

not be changed.

3) Examination Sample Size

, The initial and all subsequent visual examinations shall include all (100%) of the i snubbers of all groups as may have been established in 2) above.

2 3 4) Examination Frequency The initial inservice examination of all snubbers shall be started not less than two months after attaining 5% reactor power operation and shall be completed i within 12 calendar months after attaining 5% reactor power operation.

Subsequent examination intervals shall be as follows:

1 (a) The second inservice examination shall be conducted at the first refueling outage. No schedule change in accordance with Table B-5-1 is required.

(b) The third inservice examination shall be conducted at the second refueling outage.

(c) Subsequent examination intervals shall be in accordance with Table B-5-1.

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Specification

, M 733 Rev. 2 PBAPS 2 & 3 ISI Program Appendix B 5 Page 12 of 28

5) Outage-Based Visual Examinations Table B-51, Outage-Based Visual Examination Table, provides the permissible number of inoperable snubbers allowed, for various snubber populations or groups, to continue wRh the normal examination frequency schedule. In addition, Table B 51 details all corrective actions to be taken and provides examination frequency adjustments to be made, based on the number of unacceptable snubbers found during the visual examination.

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1 Specification M 733, Rev. 2 PBAPS 2 & 3 i

ISI Program Appendix B 5 l Page 13 of 28 i

TABLE B 51 REFUELING OUTAGE BASED VISUAL EXAMINATION TABLE 4

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1 NUMBER OF UNACCEPTABLE SNUBBERS a

Populaties Coluna A Columa B Celuna C

erOreup For Estended laterval Mazimum forSame as Previous ForlatervalBeduction by 113 (Neto 11 (Notes 2 and 3) laterval(Notes 2 and 4) INeces 2,6,6) 1 0 0 1 80 0 0 2 l 100 0 1 4 l 180 0 3 8

200 2 5 13 300 5 12 25 1

400 8 18 34 j 500 12 24 48

' 780 20 40 78 1000 29 64 109 1500 44 91 173 1

l NOTE 1: lassepelaties between pr9 elation er group sises and the aanber of unacceptable snubbers is permissible. Use the nest lower integer found lier the perusasible ammber of-- . Mle anubbers.

i N 0 rt 2: The basic interval shall be the normal Asel eyele up to 24 =aaeha The esamination laterval asey be as great as twice the fueleyene teste aler as small as 14 etthe Amt cycle (astes 5(b)and 4). The ===i=== tprevices interval)value ,

l used to determaine the most e=e-i=% interval shall be one normal fuel cycle. The essauastles intervals may I very by 226 pervent to esencide with the actual cunge.

i NOTE 3: if the -har of unaseeptable snobbers is equal te er less than the value la colusan A, them the aest essai astion '

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I lotorval assy be leeressed to twice the past osamination isterval i.e., the nest osaa seeerding to the former l

interval miay be skipped. When the Isreser interval is the renneling cycle, the saubbers maey be esamined saly every other reAnoling eyele laterval se leeg as the resulta of the visual ==,=ination smeet the requireanents of coluna A.

l The amebbers that are inmallad at Isostices where the anubbers were - - , _ile at the previous esamination j shall be esamined during the skipped renaeling outage.

i NOTE 4: If the messber of unaeceptable snubbers eseeeds the vales la solusan A, but is equal to er less than the aanber la i

solumna B, them the nest visual osaannatise shall be seedineted at the same interval as the 8-dately preceding laterval. When the fermer intervalis the renaeling cycle the nest interval le the current refueling cycle.

NOTE 4: If the member of unneceptable anubbers enesode the number in soluaan B but is equal

• er less than the value la  !

j soleman C, then see of the Isliewlag shall apply:

) I (a) A review and evaluation tojustify emotinued use of the snobbers shall be H.L. . i 'line previces esamination laterval may then be used. Whom the fermer interval is the refueling cycle the mest interval is the current j refuelingeyele.OR 1

(b) The most **a-lattlee laterval M be diecreened by one. third of the previous e=aminaties interval er,la j

asserdamee with the im--; ' ' between estusmas B and C, la p , - %e to the esact namnber of unacceptable

amebbers.

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! NOIT 4: If the assaber of -- - _ _ ; Mle anubbers eseeeds the value in colonna C, then the corrective actions and just:8 cations 4

etNees 5e shall be , f -- - f and the ==i-ties intervalshall be decreased to eme. third of the previous laterval i

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Specification  !

M-733 Rev. 2 PBAPS 2 & 3 ISI Program Appendix B 5 Page 14 of 28 i

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6) Visual Examination Acceptance Criteria Visual examinations shall verify conformance of the snubber installation to the following requirements:

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i a) Must Restrain Movement.

I Snubbers shall be installed such that when activated, piping / component

movement is restrained. Visual observation of loose fasteners, corroded or j

deformed members, or detection of disconnected components or other conditions that might interfere with the proper restraint of movement l requires evaluation. Snubbers which are determined to be incapable of

restraining movement shall be considered unacceptable, b) Must Permit Thermal Movement.

1 Snubbers shall be installed in such condition that thermal movement of the  !

piping / component is not restricted to the extent that unacceptable overstressing could develop. Observed binding, misalignment, and/or '

deformation may be indicative of such a situation, and shall be evaluated.

l Snubber installations determined to excessively restrict piping / component i thermal movatwit shall be considered unacceptable, l c) Design Specific Observations.

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Snubbers shall be free of defects that may be generic to particular designs, as may be detected by visual examination Visual examination anomalies which indicate potential impaired operability of the snubber (s) may be

!' resolved by operability testing in accordance with the Section V, Paragraph A.7 of this appendix.

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I Specification j M 733, Rev. 2 1 PBAPS 2 & 3 l lSI Program i Appendix B-5 l Page 15 of 28 l l

7) Operability Test Evaluation l Any snubber (s) found to be unacceptable as a result of visual examination may be  !

operability tested in accordance with the requirements of Section V, Paragraph B.

of this appendix. Results may be used to evaluate the snubber as acceptable,  !

provided that testing can show the unacceptable condition did not affect operability.

B. Operability Testing Operability testing for operational readiness is required to be performed on representative samples of snubbers, based on the sampling plans provided herein. The number of snubbers to be tested is determined by the sampling plan chosen and the corrective actions prescribed by that sampling plan. Additional samples taken, based on the number of unacceptable snubbers found, is also determined by the specific sampling plan chosen.

Testing, as required by this augmented program, shall be implemented during the first refueling outage following regulatory acceptance of this program.  !

1) Testing Documentation The following documentation is necessary to support implementation and verification of operability testing:

a) Operability testing procedures.

b) Previous test records.

l c) Nonconformance results, evaluations, and corrective actions.

d) Defined test plan grouping.

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Specification M 733, Rev. 2 J

PBAPS 2 & 3 ISI Program Appendix B-5 Page 16 of 28

2) Operability Testing Requirements The following general requirements apply to all operability testing performed:

a) Operability testing loads Snubbers shall be tested at a load sufficient to verify the operating parameters specified in Section V, Paragraph B.5, of this appendix.

Testing at less than rated load must be correlated to operability parameters at rated load.

b) Test correction factors Differences may exist between the installed operating conditions and the conditions under which a snubber is tested. In such cases, correction factors shall be established and test results shall be correlated to operating conditions as appropriate.

c) Test-as found.

Operability testing should be performed on snubbers in their 'as-found*

condition, to the fullest extent practical, for all snubber parameters to be tested.

d) Test restrictions.

Testing methods utilized shall not alter the condition of the snubber such 4

, that the test results no longer represent snubber parameters prior to testing.

e) In situ testing.

Where desirable, in situ operability testing (i.e., testing with the snubber installed in its permanent location) may be utilized provided test methods and equipment have been approved by PECO Energy.

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d Specification M 733, Rev. 2 PBAPS 2 & 3 i ISI Program Appendix B-5 l Page 17 of 28 f) Bench testing.

Operability testing may be performed by removal of the snubber and bench

, testing, provided test methods and equipment have been approved by PECO Energy. Following reinstallation of the snubber, a visual examination in accordance with the applicable requirements of Section V, Paragraph A of this appendix, shall be performed.

g) Subcomponent testing.

Where snubber physical size, test equipment limitations, or snubber inaccessibility prevent the use of either in situ testing or bench testing, the snubber subcomponents shall be tested and reassembled in accordance with PECO Energy approved procedures.

I h) Correlation of indirect measurements.

l Testing methods may be used which measure parameters indirectly or parameters other than those specified, if those results can be correlated to the specified parameters, through established methods.

i) Parallel and multiple installations.

The snubbers of parallel and/or multiple installations shall be identified and counted individually.

j) Fractional sample sizes All fractional sample sizes shall be rounded up to the next integer.

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-5 Page 18 of 28

3) Qualitative Testing.

Qualitative testing may be used in lieu of quantitative measurements in meeting the operability test acceptance criteria of this document, following review and approval of this method, by regulatory authorities. Sufficient data, based upon service history or life cycle testing, shall be obtained to demonstrate the ability of the parameter in question to be within specification over the life of the snubber (e.g. demonstration that activation takes place without measurement of the activation level). A test report shall be prepared for each snubber exempted from quantitative operability testing requirements. The test report shall verify the parameter was within specifications to allow exemption of the snubber from quantitative testing of the parameter.

4) Operability Testing Acceptance Criteria Operability testing shall vertfy conformance to the following requirements:

a) The force that will Initiate motion (breakaway force), the force that will maintain low velocity (drag force), or both, as required by the test procedure, are within specified limits, both in tension and in compression.

b) Activation is within the specified range of time, velocity, or acceleration in both tension and compression.

c) Release rate, where applicable, is within the specified range in tension and compression. For units specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be demonstrated, i

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B 5 Page 19 of 28

5) Operability Testing Failure Evaluation Snubbers that do not meet the operability testing acceptance criteria for quantitative testing or qualitative testing shall be evaluated to determine the cause of failure, using test failure mode groups, a) Test failure mode groups

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Unacceptable snubber (s) shall be categorized into test failure mode group (s). Test failure mode group (s) shall include all unacceptable snubbers that have a given failure mode, and all other snubbers subject to the same failure mode. The following failure modes shall be used:

1) Design, manufacturing

2) Application induced.

3) Maintenance, repair, installation.

4) Isolated.

5) Unexplained.

b) Test failure mode group boundaries Once a test failure rnode group has been established, any snubber (s) in that test failure mode group will not be part of the defined test plan groups from which the snubber (s) originated except as noted in (c) below. The new test failure mode group will remain as defined until corrective action has been completed.

Note that for the 37 testing sample plan, established failure mode groups once separated from the defined test plan group (s), are referred to as

' independent" test failure mode groups.

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-S Page 20 of 28 c) Snubbers in more than one test failure mode group in the event that a snubber (s) becomes included in more than one test failure mode group, it shall be counted in each failure mode group in which it is unacceptable and shall be subject to the corrective action of each test failure mode group.

d) Additional failure mode group review Once the operability test requirements are satisfied for a given defined test plan group, then any additional failure mode group review or testing shall

not require any subsequent testing on the defined test plan group.

6) Defined Test Plan Groups.

Defined test plan groups shall be determined prior to initiating testing. These groups shall encompass all snubbers and shall be based on similarities of design y

or application. That is, snubbers may be grouped by size, type, design, application, or other means as determined by engineering evaluation.

7) Operability Testing Interval Testing in accordance with the selected sampling plan shall be performed each refueling outage for each defined test plan group.

8) Operability Testing Sampling Plan Selection.

Testing shall be conducted for each defined test plan group using one of the i

following sampling plans:

a) 10 percent testing sample plan b) 37 testing sample plan i

i

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-5 Page 21 of 28 I

The plan to be used for each defined testing plan group of snubbers shall be selected before testing begins for the test interval. Once selected, the plan shall be used throughout the test interval for that defined test plan group and any failure mode group that is determined from the original defined test plan group.

9) Operability Testing Corrective Action and Continued Testing Snubbers that do not meet the operability testing acceptance criteria for quantitative testing or qualitative testing shall be subject to corrective action (s),

with its indicated impact on continued testing. Selection of the corrective action shall be govemed by the sampling plan which is used. Any maintenance, repairs, replacements or modifications shall meet the requirements of this program.

10) The 10 Percent Testing Sample Plan When the 10 percent testing sample plan is chosen for a defined test group, the following criteria shall apply:

a) initial test sample lot size and composition for a test interval.

For the first sample lot tested, a representative / random sample of 10 percent of the snubbers in the defined test plan group shall be selected.

As far as practical, the sample selected shallinclude the various designs, configurations, operating environments, range of sizes, capacity of

. snubbers, etc. The first sample lots tested shall be a composite based on the ratio of each particular category to the total number of snubbers in the i

defined test plan group. Sample lot selection from the representative categories of snubbers shall be random.

i a

4

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-5 Page 22 of 28 b) Additional test (s) lot size in the same test interval.

Nr atry snubber (s) determined to be unacceptable as a result of testing, an additional sample of at least 1/2 the size of the initial sample lot shall be tested until the total number tested is equal to the initial sample size multiplied by the factor,1 + C/2, where C is the total number of snubbers found to be unacceptable; or all snubbers in the failure mode group have been tested. (The testing of additional samples by this criteria is also required for snubbers determined to be unacceptable in any additional test lot.)

c) Additional test lots composition in the sans test interval.

As far as is practical, the additional samples shall include:

(1) Snubbers of the same manufacturer's design.

(2) Snubbers immediately adjacent to those found unacceptable.

(3) Snubbers from the same piping system.

(4) Snubbers from other piping systems that have similar operating conditions such as tempera'ure, humidity, vibration, and radiation.

(5) Snubbers which are previout Y untested, d) Subsequent test interval population st'ection.

I For subsequent refueling outages, each representative sample shall be selected in accordance with a), b), and c) above, from the total population of the defined test plan group, i

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Specific 3 ion M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-5 Page 23 of 28 4

a) Sample plan corrective action.

The 10 percent earnple plan corrective actions are dependent upon the assigned failure mode group as follows:

Design, manufacturing, maintenance, repair, installation and application

Induced test failure modes

1) All snubbers in a test failure mode group shall be replaced or i modified in accordance with Section IV, Paragraph H of this -

document, and categorized as acceptable.

OR 1

2) The unacceptable snubbers in the test failure mode group shall be replaced, or repaired to the original qualified condition. The number

, of unacceptable snubbers shall determine the additional test lots of Section V, Paragraph B.10.b.

OR

3) The unacceptable snubbers in an acolication induced test failure ,

! mode oroup shall be replaced or repaired to an acceptable condition. l All snubbers in this group shall be categorized as acceptable provided the environment or applications are compatible wf h the design parameters. .

, , Isolated test failure mode I s

The unacceptable snubbers in this test failure mode group shall be replaced or repaired in accordance with Section IV, Paragraph H of this appendix and l

, categorized as acceptable. I

l Unexplained test failure modo l

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- . = . =. __ - .. .-- .-- -- ._ ...- - . . - - . - - . . . .

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program i Appendix B 5 Page 24 of 28 i

The unacceptable snubbers in this test failure modo group shall be replaced or repaired in accordance with Section IV, Paragraph H of this appendix. The 1 number of unacceptable snubber (s) shall determine the additional testing lots in accordance with Section V, Paragraph B.10.B.

A i

13) The 37 Testing Sample Plan When the 37 testing sample plan is chosen for a defined test group, the following criteria shall apply:

a) Initial sample size and cciTpcolilen.

1 i The initial sample shall consist of 37 anubbers selected randomly for each defined test group which utilizes the 37 testing sample plan.

b) Additional defined test plan group testing 1

For any snubber (s) determined to be unacceptable as a result of testing, l additional samples shall be selected such that the following test plan equation is satisfied (Figure B-5 2):

N 2 36.49 + 18.18 C where

, N = Total number of snubbers tested which were selected from the defined test pian group and C = Total number of unacceptable snubbers found in the defined test plan group (excluding those in independent test failure mode groups) plus one

} for each independent test failure mode group.

E.

j Additional samples shall be selected in a random manner from the remaining population of the defined test plan group. Snubbers in test

! failure mode groups shall be separated and should not be included in the additional sample (s).

]

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l Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-5 Page 25 of 28 I

l c) Independent failure mode group testing l 1

Once a test failure mode group has been established, it shall be separated for continued testing apart from the defined test plan group. It is then identified as an independent test failure mode group.

For an independent test failure mode group, the number of unacceptable snubbers which define the test failure mode group shall determine the additional testing in the test failure mode group in accordance with the following equation (Figure B-5-2):

N h 36.49 + 18.18 C where N = Initial defined test plan lot of 37 tested plus all those selected and tested from the independent test failure nyde group.

and C = Total number of unacceptable snubbers in the independent test failure mode group, in addition, the following criteria shall apply to additional testing in an independent test failure mode group:

1) Snubbers are selected in a random manner from the independent test failure mode group.

2) Any additional unacceptable snubbers found in the independent test failure mode group shall be counted for continued tesung only for that independent test failure mode group.

3) Testing completion is in accordance with the above equation in c) above.

h 1

-- =. . . . ..- . _ -._ . - -- .- - - _. . . - - - . . .

l O 3

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-5 2

Page 26 of 28

d) The 37 testing sample plan corrective action

! The following corrective action shall apply:

1) All unacceptable snubbers in the defined test plan group shall be

' replaced or repaired in accordance with Section IV, Paragraph H of this appendix to the original qualified condition. These unacceptable

, snubbers shall remain categorized as unacceptable for the purpose

of additional testing per the 37 testing sample plan,Section V.B.13.b 4

of this appendix.

l

' 2) The unacceptable snubber (s) in a test failure mode group shall be replaced or repaired in accordance with Section IV, Paragraph H of i ,

this appendix to the original qualified condition. These unacceptable

i snubbers shall be used in determining the requirements for

additional testing per the 37 testing sample plan,Section V.B.13.c of this appendix.

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Nb FIGURE B-5-2 THE 37 TESTING SAMPLE PLAN ~

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TESTING -

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REGION -

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Cs - -

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N = 36.49 + 18.18C 2 -

ACCEPT LINE 3- M

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/ REGION 0 - / , ,

u,ah.

0 10 20 30 40 50 60 70 80 90 100 ~110 12 0 13 0 3bhEf$

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Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-5 Page 28 of 28 VI. SERVICE LIFE MONITORING 1

The service life of all snubbers shall be monitored to ensure that the service life is not exceeded between augmented examination / testing intervals.

The maximum expected service life for various seals, springs, and other critical parts shall be extended of shortened based on monitored test results and failure history. Critical parts shall j be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be operable. Replacements shall meet the requirements of Section IV, Paragraph H of this appendix.

I Vll. REPORTS / RECORDS 1

All reports / records associated with the examinations / testing of this augmented program shall be

, prepared / maintained in accordance with ASME Section XI and site administrative procedures.

Records of service life monitoring shall be maintained in accordance with PBAPS Technical Specification record retention requirements.

Summary reports detailing the results of examinations / testing as required by this augmented j examination program shall be included h the ISI Summary Report.

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Specification M-733, Rev. 2

! PBAPS 2 & 3

, ISI Program Appendix B4 Page 1 of 2 4

AUGMENTED INSPECTION PROGRAM 6: SIL No. 400, incore Dry Tube Cracks 1

l L SCOPE This augmented inspection program (AUG 6) defines the specific examination requirements of General Electric Company (GE) Nuclear Services Information Letter (SIL) No. 409, as applicable to PBAPS 2 & 3. This SIL provides information/ recommendations relative to cracks found in BWR Intermediate Range Monitor (IRM) and Source Range Monitor (SRM) instrumentation dry tubes.

Examination requirements, as detailed in this document, are exclusive of any ASME Section XI

] Inservice Inspection requirements for the identified components within the scope of this document.

j ll REFERENCE

. A. GE SIL No. 409, incore Dry Tube Cracks, Revision 1 Category 2, July 31,1986.

[ B. MEMO R. W. Gropp to File, dated 12/6/88; NRC Bulletin No. 88-09, " Thimble Tube Thinning in Westinghouse Reactors.'

4

111. GENERAL Examinations of IRM/SRM dry tubes at several BWRs have resulted in cracking and/or crack

Indications observed in a number of IRM/SRM instrumentation dry tubes. All of the observed

' cracks are within the top two (2) feet of the dry tube assembly, primarily in the perforated tube adjacent to either the well between the tube and the guide plug or the weld between the tube

, and the primary pressure boundary.

The cracking is considered to be caused by a combination of crevice corrosion cracking and inadiation assisted stress corrosion cracking (IASCC), while crack initiation time is strongly dependent on BWR water chemistry (i.e. water conductivity).

The PBAPS 2 & 3 IRM/SRM instrumentation dry tubes are the original BWR/2-6 design and as 4

such are susceptible to the cracidng described. Crack initiation time and growth rate for the i PBAPS 2 & 3 configuration is dependant on time in use, water quality, and loading variations l (e.g., flow induced vibration, bumping during fuel movements).

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Specification i M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix B-6 Page 2 of 2 IV. EXAMINATION PROGRAM There are four (4) SRM and eight (8) lRM dry tube assemblies in each PBAPS 2 & 3 reactor pressure vessel. Visual examination (VT 1) of the top two (2) feet of these dry tubes is recommended in accordance with Table B-61.

V. EXAMINATION RESULTS Visual examination results shall be documented /dispositioned in accordance with ASME Section XI.

VI. REPORTS / RECORDS All reports / records associated with the examinations of this augmented program shall be l prepared / maintained in accordance with ASME Section XI and plant procedures.

TABLE B 6-1 INCORE DRY TUBE RECOMMENDED INSPECTION PROGRAM i i

Water Conductivity Meets EPRI Does Not Meet Guidelines' EPRI Guidelines' 1 PBAPS 2 & 3 4/2'# 2/1**

SRM/lRM Dry Tubes j 1. EPRI water conductivity guidelines appear in EPRI NP 358g SR LD for the cumulative service

of dry tubes.

4

2. X/Y Visual examination should be performed during the 'Xth' refueling outage after dry tube Installation. Subsequent visual examinations should be performed when accessible.

)

3. The SAM /lRM dry tubes are located between the Top Guide and Core Plate and are not accessible during a normal refueling outage. Removal of an adjacent fuel cell is required to provide access for remote visual examination.

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Specification I M 733, Rev. 2 PBAPS 2 & 3 lSi Program l

i Appendix B 7 Page 1 of 1 l

j AUGMENTED INSPECTION PROGRAM - 7: SIL No. 474 Steam Dryer Drain Channel Cracking i

1. SCOPE l This augmented inspechon program (AUG 7) defines the specdic examination recommendations of General Electric Company (GE) Nuclear Services Information Letter (SIL) l 3

No. 474, as applicable to PBAPS 2 & 3. This SIL reports the occurrence of cracking in the drain channel to steam dryer skirt attachment welds and the related GE examination j recommendations.

ll. REFERENCES A. GE SIL No. 474, Steam Dryer Drain Channel Cracking, October 26,1988.

4 i 111. GENERAL The PBAPS 2 & 3 steam dryers are not safety related components; their function is to improve

the quality of the steam before it leaves the reactor vessel. The steam dryer drain channels i

channel water runoff from the dryer back into the reactor pressure vessel. Cracking has been i discovered at several BWR/4, 5 and 6 plants in the drain channel to dryer skirt attachment

, welds, both the horizontal and vertical welds. GE analysis indicates that crack initiation was

. due to high cycle fatigue.

The subject cracking is not a safety concem; however, if extreme cracking would occur, steam

, quality would become severfy degraded and could potentially damage balance of plant l components. Failed drain channels could result in loose parts and potentially damage RPV i

' infomal components. As such, augmented examination is recommended to ensure steam dryer reliability.

t I IV. EXAMINATION REQUIREMENTS Visual (VT 1) examination of the PBAPS 2 & 3 steam dryer drain channel attachment welds is recommended every refueling outage.

V. EXAMINATION RESULTS 4

Examination results generated from this augmented inspection program shall be recorded and evaluated in accordance with applicable plant procedures, i

Any cracking detected shall be evaluated for repair to preclude any further crack growth.

VI. REPORTS / RECORDS i

. All reports / records anmelated with the examinations of this augrnented program shall be prepared / maintained in accordance with ASME Section XI and plant procedures.

i

Specification M 733, Rev. 2 PBAPS 2 & 3

) ISI Program Appendix B-8 i

Page 1 of 2 4

AUGMENTED INSPECTION PROGRAM 8: SIL No. 462 Shroud Support Access Hole Cover Cracks I. SCOPE 1

i This augmented inspection program (AUG 8) defines the specific examination

recommendations of General Electric Company (GE) Nuclear Services Information Letter

(SIL) No. 462, as applicable to PBAPS 2, and 3. This SIL addresses the intergranular stress corrosion cracking (IGSCC) of the shroud support access hole covers and the GE j- recommended actions regarding susceptibility / routine examination, j 11. REFERENCES l

, A. GE SIL No. 462, Shroud Support Access hole Cover Cracks, Supplement 3.

l

! III. GENERAL

! There are two (2) access holes in the shroud support plate which are utilized for access to the lower plenum during construction and are subsequently closed by welded access hole 1

covers. As reported in SIL No. 462, cracking in the access hole cover plate attachment weld has been detected in a BWR/4 The cracking occurred in the heat affected zone of the creviced alloy 600 access hole cover plate and is attributed to crevice accelerated i

IGSCC.

While the PBAPS 3 access hole covers were cut out and replaced with bolted in covers, j PBAPS 2 retains the original, welded design, access hole covers. The modification of the i Unit 3 covers was the result of circumferential cracking which was discovered in the heat i affected zone of the weld.The UT examination that detected the circumferential cracking was not sensitive for detection of radial cracking which has also been found in these wolds. Because the tooling to ultrasonically examine these areas for the purpose of detecting radial cracking has not been developed, an attemative method of examination l will be used to detect such cracking. Therefore augmented examinations are

! recommended for both PBAPS units, i

IV. EXAMINATION REQUIREMENTS PBAPS 2 configuration-Beginning with the ninth refueling outage (2ROg), a visual VT-1 examination will be performed on each of the two covers. This examination will concentrate on the weld which attaches the cover to the shroud support. The examination will be conducted to detect

either circumferential or radial cracking around these welds. These VT 1 examinations will be repeated every other refueling outage until UT tooling is available to be used to examine for radial cracking.

Beginning with the tenth refueling outage (2RO10), a UT examination will be conducted on the weld which attaches each of the access hole covers to the shroud support. This UT j examination will be conducted to detect circumferential cracking in the welds. When

appropriate tooling is available, this UT examination can be expanded to detect radial cracking as well as the circumferential cracking, i

l

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1 Specification M 733, Rev. 2  :

PBAPS 2 & 3 ISI Program Appendix B-8 Page 2 of 2

! PBAPS 3 configuration-j Since the Unit 3 covers have been replaced with bolted designs, UT examination of the welds is impractical without removing the bolted cover. Additionally, UT examination is not as imperative since the modified design yields reduced residual stresses in this area. Since i radial cracking could still be concem, a visual ( VT 1) examination will be performed during q

the ninth refueling outage (3RO9), to extent practical. This examination will be conducted around the perimeter of the bolted hatch cover, with close scrutiny in the areas where the shroud support is welded to the shroud cylinder and the vessel wall. This examination may be repeated every other refueling, as determined by the station.

2 Note that both access hole covers have been included for routme visual (VT-3) examination in accordance with the ISI program for Code Examination Category B N 1.

This AUG-8 program involves additional requirements to those of the ISI Program.

If cracking is detected visually, a remote UT examination for defect characterization and sizing will be performed.

In summary, an Ultrasonic Examination (UT) of the Unit 2 access hole covers will be

! performed every other outage beginning with the tenth refueling outage (2R10). Visual VT-1 examinations will be performed every other outage, beginning with the ninth refueling outage (2RO9). This will result in Inspections each outage by altemating techniques (i.e.

visual (VT) and ultrasonic (UT)). A visual VT 1 examination will be conducted on the Unit 3 access hole covers during the ninth refueling outage (3RO9).

1 Review of plant water chemistry and/or the Incidence of IGSCC in other RPV intemal I components may necessitate a revised frequency of this examination.

V. EXAMINATION RESULTS l

Examination results generated from this augmented inspection program shall be recorded i and evaluated in accordance with applicable plant procedures.

4 j VI. REPORTS / RECORDS

] All reports / records associated with the examinations of this augmented program shall be j prepared / maintained in accordance with ASME Section XI and plant procedures.  ;

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6 Specification M-733, Rev. 2 Addendum 1 PBAPS 2 & 3 4

ISI Program Appendix B 9 Page 1 of 3 AUGMENTED INSPECTION PROGRAM - 9: Examination of the Reactor Pressure Vessel Core Shroud Welds

1. SCOPE This augmented inspection program (AUG-9) defines the examinations applicable to PBAPS 2

& 3 Core Shroud. This program is based on the Boiling Water Reactor and Vessel intemals Project (BWR VIP) recommendations contained in the "BWR Core Shroud Inspection and Flaw Evaluation Guidelines". This BWR VIP document addresses the occurrence of cracking in the Roactor Pressure Vessel core support shroud welds, and recommends actions for detection and evaluation of such cracking.

Examination requirements, as detalled in this document, are exclusive of those ASME Section XI inservice inspection requirements for the subject areas.

11. REFERENCES A. NRC Information Notice 93 79, Core Shroud Cracking at Beltline Region Welds in Boiling Water Reactors.

B. NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors, dated 7/25/94.

C. BWR VIP Guidelines - BWR Core Shroud Inspection and Flaw Evaluation Guidelines, (G E Nuclear Energy Document, GE-NE-523113-0894, Rev.1, Dated April 21,1995).

D. BWR VIP Core Shroud NDE Uncertainty & Procedure Standard, dated November 21, 1994.

E. Evaluation and Screening Criteria for the Peach Bottom Unit-3 Shroud Indications, GENE 523141 1093. Rev.1, dated 12/03/93.

F. Evaluation and Screening Criteria for the Peach Bottom Unit 2 Shroud, GENE 523-176-1293, dated 12/13/93.

G. NCR PB-93-00743, Rev.1, Unit 3 core shroud indications,3R09.

H. NCR PB 94-00374, Rev. O, Unit 2 core shroud indications,2R10.

J. Screening Criteria and Flaw Evaluation Methodology for the Peach Bottom Unit 3 Shroud, GENE-523 A076-0895, dated August 1995.

til. GENERAL Due to the frequency of occurrence, and the unpredictability of expecting cracking location, the NRC lssued Generic Letter 94-03 (Reference B). Through this GL, the NRC is seeking expanded shroud weld examinations. The extent of examinations and the scheduling of initial examinations is dependant on the susceptbility of a plant's shroud welds. The factors contributing to susceptibility are identified in Reference C, along with recommendations for extent of examinations. This document was developed under the direction of the Boiling Water Reactor Vessel and Intemals Project. Together, these two basis documents form the source of

. _ . _ _ _ . _ _ . . . _ _ _ . _ _ _ _ _ _ ~ . . . __ _ _ _ _ _ . _ _ _ . _ _ ._. _ .

Specification M 733, Rev. 2 Addendum 1 PBAPS 2 & 3 ISI Program

Appendix B 9 Page 2 of 3 i

i this Augmented inspection Program, and have superseded the recommendations of GE Service

Information Letter No. 572.

The PBAPS 2 & 3 Core Shroud assemblies were fabricated by the Rotterdam Drydock Co.

LTD., Rotterdam, Holland. Figure 9.1 illustrates the general configuration of the shroud, as well as weld locations within the shroud assembly. Because of the materials of fabrication, and the j extent and nature of hot operating service these shrouds have experienced, the susceptibility to

shroud weld cracking is fairfy high. Accordingly, recommendations for comprehensive

examination of all horizontal shroud welds are applicable.

l Shroud weld examinations may be conducted using Enhanced visual examination techniques or

Ultrasonic testing (UT) techniques. Additional examination techniques are currently being

] pursued. Currently, UT is the preferred technique.

, IV. EXAMINATION PROGRAM For plants with high carbon Type 304 stainless steel shrouds with six (6) years or more of power operation and low early life water quality, the VIP recommends examination of the accessible areas of the Heat Affected Zone of all horizontal seam welds. (The PBAPS 2 & 3

! shrouds are fabricated from high carbon content plate and low carbon content forged rings, see Figure 9.1). Reexamination schedules are dependent on the extent of initial examinations completed per weld, as well as the results of these examinations.

l

. PBAPS Unit 3 performed initial Shroud examinations during Refueling Outage (3R09) in 10/93.

The examinations utilized the Enhanced VT 1 technique, and included the entire ID length of the H 3 and H-4 welds; along with portions of welds H 1, H 2 H-3, H 5, H 6, and H 7 from the 4 OD. These examinations resulted in indications observed adjacent to the H3 and H4 welds.

Accciai,5y, Shroud examinations will again be performed at the next refueling outage of PBAPS 3 (3R10), utilizing similar techniques as performed during the refueling outage 2R10, as

described below. Results of 3R10 shroud examinations will be evaluated utilizing Reference J.

! l j PBAPS Unit 2 performed initial Shroud examinations during Refueling Outage (2R10) in 10/94.

These examinations utilized the UT examination technique, and included comprehensive (i.e. all j accessible length) examinations of welds H 2, H-3, H-4, and H 5. Welds H-1, H-6, and H 7 received UT examination of portions of the weld length due to access limitations. These examinations identified some Indications at a number of the shroud welds. These indications were evaluated and disposition per Reference F. Reexamination of welds H 1 H-6, and H-7, which had limited initial examinations, will be conducted during the next refueling outage. The l

remaining shroud welds will be reexamined at the second refueling outage following initial examinations,

[

j- V. EXAMINATION RESULTS 4

All as found indications shall be evaluated in accordance with Reference C and ASME l Section XI. 8 4

i' All indications detected using the enhanced VT 1 technique shall be considered through-wall indications for initial evaluation purposes.

VI. REPORTS / RECORDS Reporting and record-keeping shall be in conjunction with the ASME Section XI Program requirements.

i 1

Specification M 733 Rev. 2 Addendum 1 PBAPS 2 & 3 ISI Program Appendh B 9 Page 3 of 3 REACTOR PRESSURE VESSEL - SHROUO PEACH BOTTOM ATOMIC POWER STATION UNIT 2 & 3 pDRrdR/ SEPARATOR SUPPCRT RING WELD NO. 1-_

W ITEM 7 A182-F 304 0.035 % C gg Vi v2 ITEM 5 A240 TP. ?,04 0.062 %j C (MAX)

H2% ,gTOP GUIDE SUPPORT RING, kw w ITEM 6 A182-F 304 0.028 % C (UNIT 2) i l 0.030 % C (UNIT 3 ITEM 4 A240 TP.304 0.060 % C (MAX)

V3 V4 H4 V5 V6 ITEM 14 A240 TP.304 0.060 % C (MAX)

H5 gCORE PLATE SUPPORT RING F#fA ITEM 13 A182-F 304 0.030 % C (UNI" 2) 0.035 % C (UNIT 3)

ITEM 12 A240 TP.304 0.059 % C (MAX)

H7 V7 V8

/rSHROUD (ALLOYSUPPORT600) CYLINDER 9  :

'1- REF. DWG. M-1-B-26 I

Figure 9.1 _

l 1

Specification M 733, Rev. 2 Addendum 1 PBAPS 2 & 3 l ISI Program Appendix B 10 Page 1 of 2 AUGMENTED INSPECTION PROGRAM - 10: SIL No. 554, Top Guide Cracking SIL No. 588, Rev.1, Top Guide and Core Plate Cracking

1. SCOPE This augmented inspection program (AUG 10) defines the specific examination recommendations of General Electric Company (GE) Nuclear Services information Letters (SILs) No. 554 and 588, Rev.1, as applicable to PBAPS 2 & 3. These SILs address Top Guide and Core Plate cracking and the GE recommended actions regarding susceptibility / routine examination.

II. REFERENCES A. GE Sll No. 554, Top Guide Cracking, April 6,1993.

B. GE RICSIL No. 059, Top Guide Crack Indications, May 31,1991.

C. GE SIL No. 588, Rev.1, Top Guide and Core Plate Cracking, May, 18,1995.

l Ill. GENERAL Cracking has been identified in the Top Guide beams of a GE BWR/2 reactor. As a result, General Electric Co. Issued both RICSIL No. 059 and Sll No. 554. These Information Letters recommend examination 2 of the Top Guide " egg crate" beams, if the fluence level at the Top Guide is above 1x10 ' neutrons per square centimeter, invessel Visual Inspections (lWI) are recommended for grid k> cations which are accessible due to fuel and blade guide removal.

Cracking has also been identified in the Top Guide and Core Plate rim welds in a non GE BWR, located outside the United States. As a result, GE issued Sll 588 on February 17,1995, and later revised this SIL on May 18,1995. This SIL recommends visual examinations of a l sample of the Top Guide and Core Plate hold down devices, during one of the next two  !

refueling outages, for plants without Top Guide and Core Plate wedges. Since the PBAPS, Unit l

2 & 3 core stmetures do,no,t incorporate wedges at the Top Guide or Core Plate, the l recommended examinations are applicable. I IV. EXAMINATION PROGRAM SIL 554 recommended Visual examinations have been performed at PBAPS 2 & 3, starting with the PBAPS 3 Ninth Refueling Outage (3R09) and PBAPS 2 Tenth Refueling Outage (2R10).

Visual examiriations should be performed on a sampling of grid locations where fuel and blade guides have been removed. The video camera should be positioned below the beams and aimed up toward the bottom of the beams, if crack!ng is detected visually, an increased sampling of examinations should be performed.

l l

Specification .

M 733, Rev. 2 Addendum 1 PBAPS 2 & 3 l ISI Program Appendix B 10 Page 2 of 2 SIL 588 recommended Visual examinations will be implemented beginning with the PBAPS, i

Unit 3 Tenth Refueling Outage (3R10), and the PBAPS, Unit 2 Eleventh Refueling Outage (2R11). These examinations will include Visual (VT 3) examinations of the Top Guide

" Aligners', and a sample of the Core Plate " Hold Down Bolt". locking devices.-The extent of the i examinations of the Top Guide Aligners will be sufficient to assure integrity of the devices to

transfer loads from the Top Guide to the Shroud. The extent of examination of the Core Plate hold down bolts will include verification that the bolt locking devices are in place.

PBAPS, Unit 2 & 3 has four (4) aligners which engage the Top Guide to the top guide support ring of the shroud, and 34 Core Plate Hold Down Bolts. These components are tabulated on the Augmented Inspection Program 10 Tables, (AUG-10 Tables). All four Top Guide Aligners j will be examined within the next two refueling outages. Examinations beyond the next two refueling outages will include one (1) aligner examination every other refueling outage.

Examinations of the Core Plate Hold Down Bolt Retainers will be performed on a sample basis.

, The examinations will be performed on a sample of the fuel cell locations where fuel and blade guides have been removed. The examinations will be scheduled each refueling outage.

, V. EXAMINATION RESULTS i Examination results generated from this augmented inspection program shall be recorded and

evaluated in accordance with applicable plant procedures.

VI. REPORTS / RECORDS i

• All reports / records associated with the examinations of this augmented program shall be

prepared and maintained in accordance with ASME Section XI and plant procedures.

]

i 1

1 4

4 4

1 4

l 1

l

Specification M 733 Rev. 2 PBAPS 2 & 3 ISI Program Appendix C Page 1 of 14 APPENDIX C TABLE OF CONTENTS REFERENCE DRAWINGS List of ASME Section X1 Boundary Drawings List of ASME Section XI isometric and Component Drawings PBAPS Unit 2 & Common l

List of ASME Section XI isometric and Component Drawings PBAPS Unit 3 List of ASME Section XI ISI Calibration Block Drawings l

1 l

l l

Specification l M 733, Rev. 2 PBAPS 2 & 3

ISI Program

! Appendix C j Page 2 of 14 i

A8ME Section XI 181 Boundary Drawinge Drawina Number (Sheet (s)) E!g, a 181 303 (1,3) Main Steam, Bypass & Crosseround a 181-304 (1,2) Turbine & Extraction Steam l 181 306 (1,2,3,4) Feedwater & Feed Pumps (Sheet 1,3 Augmented only) 181 309 (1,2) Condensate Storage (Augmented only) 1S1 315 (1,2,3,4,5) Emergency Service Water and High Pressure Service Water 181-330 (1) Emergency Cooling System j 181 331 (1,3) Off-Gas Recombiner System 1S1 351 (1,2,3,4) Nuclear Boiler i ISl 352 (1,2,3,4) Nuclear Boiler Vessel Instrumentation

, 181 353 (1,2,3,4) Reactor Recirculation Pump System

, ISI 354 (1,2) Reactor Water Clean Up System 181 356 (1,2) CRD Hydraulic System Part A 181 357 (1,2) CRD Hydraulic System - Part B i ISI 358 (1,2) Standby Liquid Control System ISl 359 (1,2) Fleactor Core Isolation Cooling System i 1S1360 (1,2) RCIC Pump Turbine Details 181 361 (1,2,3,4) Residual Heat Removal System ISI 362 (1,2) Core Spray Cooling System 1S1 363 (1,2) Fuel Pool Cooling and Cleanup System ISI 365 (1,2) High Pressure Coolant injection System i

ISI 366 (1,4) HPCI Pump Turbine Details ISI-367 (1,2) Containment Atmospheric Control System

ISl 372 (1,2) Containment Atmosphere Dilution System i

}

i i

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1 l

Specification M 733. Rev. 2 PBAPS 2 & 3 ISI Program Appendix C Page 3 of 14 ASME Section XI loometric & Component Drawings PBAPS Unit 2 & Common System loometric Drawino Comoonent Drawino Core Spray DCN 14 MI 203-5-A DCN 14 MI 203-5-B GB 14-MI 202 2 A GB 14-Mi 202 2 8 GB 14 MI 202 2-C GB 14 MI 202 2 D GB 14 MI 203 3 A GB 14 MI 203 3-8 GB 14-MI 203-4 A GB 14 MI 203-4 B HB 14 MI 2011 A HB 14 MI 201 1 B HB-14 MI 2011 C HB 14-MI 201 1 D HC 27 MI 201 1 (AUG. R&R)

Emergency Cooling Water GB 48-Mi-0012 (Unit 2,3 and Common) GB-48 MI-0013 HB 48 MI-001 1 HB 48 MI 0013 HB 48-MI-0014 HB-48-MI-001 5 Emergency Service Water HB 33-Mi 201 1 HB 33-MI 2012 HB 33-MI 2013 HB 33 MI 2014 HB 33-MI 2015 HB 33 MI 2016 HB-33-MI 2017 HB 33 MI 2018 HB 33 MI 2019 HB 33-MI 201 10 HB 33 MI-201 12 HBC-33-MI 201 13 HBC 33-MI 201 14 HBC-33-MI 201 15 l

I

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix C Page 4 of 14 ASME Section XI loometric & Component Drawings PBAPS Unit 2 & Common System Isometric Drawina Comoonent Drawina ESW (Cont) HBC 33 MI-201 16 HBC 33-MI 201 17 HBC-33-MI 201 18 HBC-33-MI 201 19 HBC-33 MI 20120 HBC-33-MI 20121 HBC-33-MI-20122 HBC-33-MI-20123 HBC 33-MI 20124 HBC-33-Mi-20125 HBC-33-MI 20126 HBC 33-MI 20127 HBC-33 MI 20128 HBC-33-MI-20129 HBC-33-Ml 20130 HBC-33-MI 20131 HBC-33 MI 20132 Feedwater DDN 06-MI 2012 A DDN-06-MI 2012 8 DD-06-MI 201 1 (AUG. R&R)

High Pressure Coolant DBN 23-Mi 203-6 injection DBN 23 MI 203 7 DON 23-MI 202 2 DDN-23-MI 202 3 DON 23-MI 202 4 DDN-23-MI 202 5 HB 23 MI 2011 (CL 2 & AUG. R&R)

HB 23-MI 204-8

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix C Page 5 of 14 ASME Section XI loometric & Component Drawings PBAPS Unit 2 & Common System Isometric Drawino Component Drawino High Pressure Service GB-32 MI 201 1 Water GB 32 MI 2012 GB-32 Mi-2013 GB 32-MI-2014 A GB-32 MI-201-4 B GB 32-MI-2015-A GB-32 MI-2015-B GB-32 Mi-202-6 A GB-32-MI 202-6-B GB-32-MI 202 7 Main Recirculation RCS-02 MI 201 1 A ISI 2-02-1 RCS-02-MI-201 1 B 1S1202-2 Main Steam DBN-01 MI 201-1 A DBN-01 Mi 20118 DBN-01 MI 201 1-C DBN 01 MI-2011 D DB-01 MI-2012-A DB 01 MI-2012 B DB-01 MI-2012-C DB-01 MI 2012-D DB-01 MI-2213 DB-01 MI 2214 (AUG, R&R)

DB-01 MI-222-5 A DB 01 MI 222 5-B Main Steam GG-01 MI-271 A

, Relief Valve GG-01 Mi 271 B GG-01 Mi 271-C GG 01 MI-271 D GG 01 MI 271 E GG-01 MI 271 F  !

GG-01 MI 271 G GG-01 MI-271 H l GG-01 MI-271 J GG-01 MI 271 K GG 01 MI 271 L

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix C Page 6 of 14 ASME Section XI isometric & Component Drawings l PBAPS Unit 2 & Common  !

Syste_m isometric Drawina Comoonent Drawina Reactor Core Isolation Cooling DDN 13 Mi 201 1 Reactor Drain DCN-04 Ml-2012 DDN-04 MI 201 1 Reactor Pressure Vessel RCS-02-MI-201 1 A ISI 2-RV-01 RCS-02-Mi 201-1 B ISI-203-RV 02 ISI 203-RV-03

, ISI-203-RV-04 ISI-2 RV-05 ISI 203-RV-06 ISI 203 RV-07 ISl-203-RV-08 ISI-203-RV-09 ISl 203-RV 10 ISI-203-RV 11 ISl 203 RV 12 ISI-203-RV-13 ISI-203-RV 14 ISI 203-RV 15 ISI-203-RV 16 ISI-203-RV 17

, ISI 203-RV 18 ISI-203-RV 19 l lSI 203 RV 20 ISI-203 RV 21 ISl-203 RV 22 ISI 203 RV 23 ISI 203-RV 24 Reactor Water Clean-up DCA 12 MI 201 1 DCA 12 MI-203-3 (Class 1 and AUG. R&R)

DE 12-MI 202 2 DE 12-MI-203 4 (AUG.1)

DE 12 MI-203-5 (AUG.1)

DE 12-MI-203-6 (AUG.1)

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix C Page 7 of 14 ASME Section XI leometric & Component Drawings PBAPS Unit 2 & Common System Isometric Drawino Comoonent Drawina Residual Heat Removal DCN-10-MI 20615 ISI-210 l DCN 10-MI 20716 ISl-2-10-2 DDN 10-MI-203-8-A l DDN.10-MI 203-8-B DE-10-MI 203-9-A

{

l l DE 10-Mi 203-9-B GB 10-Mi 202-3-A GB-10-MI-202-3-B GB 10-MI 202-3-C GB-10 MI 202 3-D j l GB-10-MI-202-4 A l' l GB-10-Mi 202-4-B GB-10-MI-202-4-C GB 10-MI-202-4 D l GB-10-MI-203-5-B GB 10-MI-203-6-8 GB 10-MI-203 7 A GB 10-Ml 203-7-B GB 10-MI-20410-A l GB-10-MI 20410-8 GB 10-Ml 20411 A

( GB-10-Mi-20411 B GB 10-MI-20512 A GB-10-MI 205-13-A GB-10 MI-205-13-B GB 10-MI 206-14 HB-10-MI-2011 A HB 10-MI-201 1-B HB 10-MI 201 1 C HB 10 MI-201 1 D HB 10-MI 2012-A HB 10-MI-2012-C HB 10-MI-2012-D HB 10 MI-20717 l

Scram Discharge Volume CS-03-MI 2011 A CS-03-MI 201 1 B CS-03-MI-201 2-A

_ _ - . - . -- .- - - . __ = .- -. ..

Specification M-733, Rev. 2 1

PBAPS 2 & 3 ISI Program Appendix C d Page 8 of 14 ASME Section XI loometric & Component Drawings P8APS Unit 3 System Isometric Drawina Component r]mdn2 i

Core Spray DCN 14-MI-303-4 A DCN 14-Ml-303 4-B GB 14 MI-302-2 A GB-14-Mi 302-2 8 GB-14-MI-302 2 0 GB-14-MI-302 2 D GB 14-Ml-303 3-A GB 14-MI 303-3-B HB 14-Ml-301 1 A HB-14-MI-301 1 B HB-14-MI-301-1 C HB 14-MI-301 1-D HCR 27 MI-301 1

(AUG. R&R)

HCR-27 MI-3012 (AUG. R&R)

Emergency Cooling Water See Unit 2 and Common l

Emergency Service Water HB 33-MI 301-1 4

HB-33-MI-301 2 i

HB-33-Mi-301 3 HB-33-MI-301-4 HB-33-MI-301-5 HB-33-MI 3016 j HB 33-MI 3017

HBC-33-MI 301-8 HBC-33-MI 3019 HBC-33-MI 301 10 HBC-33-MI 301 11 HBC-33-MI-301 12 HBC-33-Mi-301 13 HBC-33-MI-301 14 HBC-33-MI-301 15 HBC 33-MI 30218

^ HBC-33-Mi 30217 HBC 33-MI-30218 HBC-33-MI-30219 j

i

Specification M 733, Rev. 2 PBAPS 2 & 3

ISI Program Appendix C Page g of 14 ASME Section XI isometric & Component Drawings P8APS Unit 3 SYelem Isometric Drawina Comoonent Drawina

~

ESW (Cont) HBC-33 MI 302 20 HBC 33-MI 302-21 HBC-33-MI 302 22 HBC-33-MI 302-23 HBC 33-Mi 302 24

Feedwater DDN 06-MI 3012 A DDN-06-Mi-301 2-8 DD-06-MI 301 1 1

(AUG. R&R)

High Pressure Coolant DBN-23-Ml 303-5 injection DON-23 MI-303-6 DBN-23-MI 303-7 DON-23-MI 302 2 DDN-23 MI 302-3 DDN-23-MI 302 4 HB-23 MI 301 1

+

(CL 2 & AUG. R&R)

HB 23-MI-304-8 High Pressure Service GB 32 MI 3011 j Water GB 32-MI 3012 GB 32-MI 3013 GB-32 Mi 301-4 GB-32 MI 3015 A GB-32-MI 301 5-B GB 32 MI 3016 A 4

GB-32-MI 3016-B GB 32-MI 302 7 A GB 32 Mi-302-7 B GB-32 MI-302-8 Main Recirculation RCS-02 MI 3011 A ISI 3-021 RCS-02 MI 3011 B 1S1-3-02-2

Specification i M 733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix C Page 10 of 14 ASME Section XIloometric & Component Drawinge PBAPS Unit 3 System Isometric Drawino Component Drawino Main Steam DBN 01 MI 3011 A DBN 01 MI 301 1 B DBN-01 Mi 301 1 C DBN-01 MI 3011 D DB-01 MI 3012 A

DB-01 MI 3012-8 DB 01 MI-3012 C DB-01 MI 3012 D i

DB-01 Ml-3213 DB-01 MI 3214 (AUG. R&R)

DB-01 Mi 322 5 A DB-01 MI 322 5-B Main Steam GG-01 MI 371 A Relief Valve GG-01 Mi 371 B GG 01 MI-371 C GG-01 MI-371 D GG-01 MI 371 E 4 GG-01 MI 371 F GG-01 MI 371-G GG 01 Ml 371 H GG 01 MI 371 J

GG-01 MI 371 K GG-01 MI 371 L Reactor Core isolation DDN 13 MI 3011 Cooling 4 Reactor Drain DCN 04 MI 3012 DDN 04 MI 3011 i

I

Specification M-733, Rev. 2

. PBAPS 2 & 3 j ISI Program Appendix C Page 11 of 14 ASME Section XI isometric & Component Drewings PBAPS Unit 3 Syggrn isometric Drawino Component Drawina Reactor Pressure Vessel RCS-02-MI-301-1-A ISI-3-RV-01 1- RCS-02-MI-301-1 B ISI-203-RV ; ISI-203-RV-03

ISI-203-RV-04 ISI-3-RV 05 j ISI-203-RV-06 1

ISI 203 RV 07 ISI-203-RV 08 ISl-203-RV-09 ISI 203-RV 10 ISI 203-RV 11

ISI 203-RV-12 i ISI-203-RV-13 4

ISI-203-RV-14 ISI-203-RV-15

ISI-203-RV 16 i ISI-203-RV-17 l lSI 203-RV 18 i ISI 203-RV-19 ISI-203-RV-20 ISI-203-RV-21 ISI-203 RV-22 l ISI-203-RV-23

ISl-203-RV-24 1

ISI 3 RV 50 (later)

ISI-3-RV 51 (later) i; ISI-3-RV-52 (later) j Reactor Water Clean-up DCA 12 MI-301 1 4 DCA-12-MI-303 3 (Class 1 and AUG. R&R)

! DE 12-MI-302-2 DE-12-MI 303-4 (AUG.1)

DE 12-MI-303-5 (AUG.1)

DE-12-MI-303 6 (AUG.1)

I.

a 4

1

Specification M-733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix C Page 12 of 14

, ASME Section XI isometric & Component Drawinja PBAPS Unit 3 EXgt.g.n. l Isometric Drawina Component Drawina Residual Heat Removal DCA 10-Mi-303-9-A ISI-310-1 1 DCA-10-Mi-303-9-B 1S1-3-10-2 DCA 10-MI-30613 i DDN 10-MI 303-8 A DDN 10-MI 303-8-B GB 10-MI 302-3-A GB 10-MI-302 3-B 2

GB-10-MI-302 3 0

, GB-10-MI-302 3-D

, GB 10-MI 302-4-A 4 GB-10-MI-302-4-B GB 10-MI 302 4 C GB 10-Mi 302-4 D GB 10-Mi-303-5-A G310-MI-303-5-B GB 10-MI 303-6-A GB-10-Mi 303-7-A GB 10-MI-303 7 B GB-10-Mi-304-10-A GB-10-Mi-304-10-B l

GB-10-MI-304-11-A j GB 10-MI-304-11-B GB 10-MI 305-12 A GB 10 MI-305-12-B HB-10-Mi 301 1 A i HB-10-MI 301 1-B HB 10-MI-301 1-C  !

! HB 10-MI-301 1 D HB 10-MI-3012 A HB-10-MI-3012-C

! HB 10-MI-3012 D HB-10-MI 30614 Scram Discharge Volume CS-03-MI-301-1 A CS 03-MI 301 1-B l

I l

1 l

1 l

L Specitication

M 733, Rev. 2

[ PBAPS 2 & 3 i ISI Program i

Appendix C Page 13 of 14 l

ASME Section XI ISI Calibration Block Drawings 4

Drawino Number ,T,,Lig i CBD-1 ASME Section XI UT Calbration Block for Peach Bottom APS Units No. 2 & 3

. CBD-1 A ASME Section XI UT Calbration Block for 26" Main Steam

! CBD-2A ASME Section XI UT Calbration Blod for 24" Pipe CBD-3 ASME Section XI UT Calbration Block for 12" Feedwater Riser

. CBD-4 ASME Section XI UT Calbration Block for 6" Head Spray

)- CBD-5A ASME Section XI UT Calbration Block for 6" Reactor Water Cleanup CBD-6A ASME Section XI UT Calbration Block for 6" Main Steam Safety and Relief CBD 7A ASME Section XI UT Calibration Block for 10" High Pressure Coolant injection j CBD4 ASME Section XI UT Calbration Block for 14" High Pressure Coolant Injection i 'CBD-8A ASME Section XI UT Calibretion Block for 14" High Pressure Coolant injection

- CBD-9A ASME Section XI UT Calbration Block for 28" Main Recire. Suction & Discharge CBD-10 ASME Section XI UT Calibration Block for 4" RWCU Main Recirculation Bypass, CRD CBD-10A ASME Section XI UT Calibration Block for 4" RWCU Main Recirculation Bypass, CRD

! CBD-12 ASME Section XI UT Calibration Block for 12" Core Spray CBD-13A ASME Section XI UT Calbration Block for 20" Feedwater (block not used) l CBD-130 ASME Section XI UT Calbration Block for 20" Feedwater l

CBD-14A ASME Section XI UT Calibration Block for 22" Main Recirculation Manifold

CBD-15 ASME Section XI UT Calibration Blod for 14" Feedwater Riser 4 CBD 16A ASME Section XI UT Calibration Block for 12" Feedwater Riser

! CBD-17 ASME Section XI UT Calbration Block for 4.5 Pipe CBD-18A ASME Section XI UT Calibration Block for 12" Main Recire. Nozzle-To-Safe End CBD-19A ASME Section XI UT Calibration Blod for 12" Main Rec:rc. Safe End-to-Nozzle

CBD 20A ASME Section XI UT Calbration Block for 3P 1 1/2" Flat Pipe i

CBD-21 ASME Section XI UT Calibration Block for 5.125 CRD Safe End CBD-22 ASME Section XI UT Calibration Block for RPV Nut 4

CBD-24 ASME Section XI UT Calbration Block for Closure Head Thickness CBD-25 ASME Section XI UT Calibraiton Blod for 6* Pipe i CBD-26 ASME Section XI UT Calibration Block for 12" Pipe CBD-27 ASME Section XI UT Calibration Block for 4" Pipe

] CBD-28 ASME Section XI UT Calibration Block for 26" Pipe CBD-29 ASME Section XI UT Calibration Block for 20" Phe CBD-30 ASME Section XI UT Calibration Block for 24" Pipe i CBD-31 ASME Section XI UT Calbration Block for 24" Pipe j CBD-32 ASME Section XI UT Calbration Block for 24" Pipe

CBD-33A ASME Section XI UT Calbration Block for 20" Phe

CBD-34 ASME Section XI UT Calibration Block for 10" Pipe

CBD-35 ASME Section XI UT Calbration Block for 6" SS Pipe

, CBD-36 ASME Section XI UT Calibration Block for 12" Phe CBD-38 ASME Section XI UT Calibration Block for OD inner Radius j CBD-39 ASME Section XI UT Calibration Block for Clad Vessel i

Specification l M-733, Rev. 2 PBAPS 2 & 3 ISI Program Appendix C l Page 14 of 14 ASME Section XI ISI Calibration Block Drawings Drawino Number B!f.

i

, CBD-41 ASME Section XI UT Calibration Block for Nozzle Cap 1 CBD-42 ASME Section XI UT Calibration Bbck for Pump Stud -

CBD-43 ASME Section XI UT Calibration Block for Stabilizer Bracket l ' CBD-44 ASME Section XI UT Calkation Block for Pump Nut CBD-45 ASME Section XI UT Calibration Block for Nut  ;

l CBD-46 ASME Section XI UT Calibration Block for Stud CBD-47 ASME Section XI UT Calibration Block for PRV Closure Head CBD-48 ASME Section XI UT Calibration Block for RPV Stud l CBD-49 ASME Section XI UT Calibration Block for 10" Pipe

. CBD-50 ASME Section XI UT Calbration Block for 6" SS Pipe CBD 51 ASME Section XI UT Calibration Block for 6" CS Pipe 3 CBD-52 ASME Section Xi UT Calibration Block for 20" SS Pipe

CBD 53 ASME Section XI UT Calibration Block for 20" CS Pipe

, CBD-54 ASME Section XI UT Calibration Block for 24" SS Pipe CBD-55 ASME Section XI UT Calibration Block for 24" CS Pipe CBD-56 ASME Section XI UT Calibration Block for 12" SCH 100 Pipe CBD-57 ASME Section XI UT Calibration Block for 22" Pipe CBD-58 ASME Section XI UT Calibration Block for 28" Pipe CBD-59 ASME Section XI UT Calibration Block for 28" Pipe CBD-60 ASME Section XI UT Calibration Block for 30" Pipe CBD-61 ASME Section XI UT Calibration Block for 24" SCH 120 CS Pipe CBD-62 ASME Section XI UT Calibration Block for 3/4" CS Plate CBD 62A WE Section XI UT Calibration Block for SS 12" Clad Overlay (02-19-60)

CBD-64 ASME Section XI UT Calkation Block for Jet Pump Seal CBD-65 ASME Section XI UT Calkation Block for 20" Pipe l CBD-65A ASME Section XI UT Calbation Block for 4" Pipe l CBD-66 ASME Section XI UT Calibration Block for 4" RWCU Pipe

! CBD-67 ASME Section XI UT Calibration Bicek for Clad Core Spray (3-453, i

CBD-67A ASME Section XI UT Calibration Block for Core Spray Nozzle to Safe End i

CBD-68 ASME Section XI UT Calibration Block for Vessel (12-CS-5)

CBD 69 ASME Section XI UT Calibration Block for SS 22" Overlay (f 8 46) (Block not used) 1 CBD-70 ASME Section XI UT Calibration Block for SS 20" Overlay (C CBD 71 3-46) (Block not used)

ASME Section XI UT Calibration Block for Jet Pump Oveday js-08-47) 4 r

e f

4

SpecNication M 733, Rev. 2 PBAPS 2 & 3 ISI Program Attachment 1 Page 1 of 18  ;

1

1.0 INTRODUCTION

This document provideo background information and engineering justNication for the revised second 10 year interval inservice inspection (IGI) ASME Section XI ISI Boundary Drawings for PECO Energy's Peach Bottom Atomic Power Stations Unit 2 and 3 (PBAPS 2 & 3). This information may be used as a basis for the classification of systems added or changed by l modNications. In addition, it establishes a clear reference point when accessing subsequent changes in Regulatory and Code requirements and their effect on the ISI Program boundaries and exemptions.

The basis for the ISI classifications (Class 1,2, and 3) are Regulatory Guide 1.26, 10CFR50.55a, and 10CFR50.2(v). Included within this document are discussions on each ISI classification including specWic system boundaries, PECO Energy position in regard to these boundaries and exemptions applied to the specific systems. In addition, systems important to safety, which are not addressed in Regulatory Guide 1.26 are discussed.

i ASME Section XI Inservice Testing (IST) of pumps and valves is specifically excluded from the i scope of this document. In addition, the exemptions stated are for NDE only and are not applicable to system pressure testing requirements.

2. Cl. ASS 1 (QUALITY GROUP A)

{

l 2.1 Boundary Definition i

i Class 1 generally includes piping and components that are part of the reactor coolant pressure

boundary defined in 10CFR50.2(v). The extent that systems which are part of or connected to the reactor coolant pressure boundary, are classified Class 1 equivalent for inservice inspection is provided in 10CFR50.55a(e). For PBAPS, the following describes the Class 1 system 4 l boundaries

!

! a. The Reactor Coolant System including Feedwater and Main Steam piping up to and I

including the outermost containment isolation valve (CIV).

! b. Piping and components connected to the Reactor Coolant System up to and including i any of the following: l

{ The outermost CIV, for systems penetrating the primary containment.

f .

The second of two normally closed valves for systems tht.t do not penetrate the primary containment. If either or both of these valves are capable of automatic

closure, they may be normally open.

The excess flow check valve for instrument lines penetrating the primary

containment.

j. .

The reactor coolant system safety and relief valves.

Specific PBAPS 2 & 3 systems boundaries and exemptions are provided in Table 2.1-1.

1 e

i

TABLE 2.1-1 CLASS 1 BOUNDARIES AND EXEMPTIONS System # Drawino(s) System Name Boundary Exemotes 1 M-351 ' Main Steam From the reactor up to and Branch connections 53*NPS.

including the outboard civ.

,. 2 M-353 Reactor Recirculation Entire system. Branch connections 51.5"

/ NPS.

4 M-353, 354 Reactor Drain From the reactor vessel to Drain piping $2" made the connection with the inaccessible by CRDs.

RWCU inlet header.

4' M-351 Reactor Vents From the Reactor Vessel to Entire system since all pipmg the second normally closed is 53' NPS.

isolation valve on each of the two flow paths.

. . 4 M-351, 352, 353 Nuclear Boiler Vessel From the reactor vessel to Entire system since all piping Instrumentation the excess flow check valves. is $1.5" NPS.

5 M-351 Feedwater From and including the Branch connections 51.5" outboard CIV's to the reactor NPS.

vessel.

Eaf n 1%$

(n - y R n 'Il R 3.3[$$ n

l .

i l

TABLE 2.1-1 CLASS 1 BOUNDARIES AND EXEMPTIONS j System # Drawina(s) System Name Boundary Exemptions 10 M-361 Residual Heat Removal 1. From and including the low Branch conneetion 51.5* NPS.

pressure injection outboard CIV to the reactor vessel

2. Shutdown cooling suction from the Reactor Recirculation System conncetion up to and including the outboard CIV.

3. Shutdown cooling retum from the Reactor Recirculation System

/ conneetion up to and including the outboard CIV.

~

11 M-351 Standby Liquid Control From and including the Entire Class 1 portion, since outboard containment check all piping is $1.5* NPS.

valve to the reactor.

t' 5$f" ~1 mO pm,a>8-m 33

=-_-__ _ _-- -_- - _ - - - - - - - - _ - _ - - _ _ - _ - ----_-_----___ _ _ _ _ _ _ _ _ .

TABLE 2.1-1 CLASS 1 BOUNDARIES AND EXEMPTIONS System # Drawino(s) System Name Boundary Exemptions i 12 M-354 Reactor Water Cleanup RWCU inlet line from the Branch connections s1.5" (RWCU) reactor up to and including NPS.

the outboard CIV. RWCU retum line from and including the outboard CIV to the feedwater header.

13 M-359 Reactor Core isolation RCIC turbine steam supply RCIC turbine steam supply is Cooling (RCIC) from the Main Steam header all exempt since the piping is up to and including the 53' NPS. Discharge header +

outboard ClV. RCIC pump branch connections 51.5" i descharge header from and NPS.

including the outboard CIV to the Feedwater connection.

14 M-362 Cor's Spray Core spray discharge piping Branch conneetion s1.5*. NPS.

from and including the outboard CIV to the reactor. >

'15

.. l' -$]&

Af Qe N3 E g l m2 p. $ 5' l

l u 'w "

TABLE 2.1-1 CLASS 1 BOUNDARIES AND EXEMPTIONS System # Drawinois) System Name Boundary Exemotions 23 M-366 High Pressure Coolant HPCI turbine steam supply Steam supply piping branch Injection (HPCI) from the Main S*eam header connections 53' NPS. HPCI up to and inclucing outboard pump discharge header CIV. HPCI pump discharge branch connectons 51.5*

header from and including the NPS.

outboard CIV to the Feedwater header inlet l

l l

r' m

Oe 3 3p 33 m$

- w 8 y

d 98k a- u,o l

B

Spec #ication M 733, Rev.2 PBAPS 2 & 3 l lSI Program  ;

) Attachment 1 j Page 6 of 18 t

{ 3.0 CLASS 2 (QUAL.lTY GROUP B) 3.1 Boundary Definition b

Class 2 boundaries for PBAPS 2 & 3 were determined in accordance with C.1 of Regulatory Guide 1.26, Rev. 3. Regulatory Guide 1.26 specNies that the boundaries for Class 2 systems

! loclude the portions of the system required to accomplish the specific safety function and connected piping up to and including the first valve (including safety or relief valve) that is either 4

normally closed or capable of automatic closure when the safety function is required. PBAPS 2

& 3 has taken the following positions with regard to these boundaries:

1

a. For instrument lines connected to Class 2 piping or components the boundary shall be

, at the instrument root valve.

b. Valves that are normally open and are equipped with remote manual actuators are 4

considered an accef4(ieAe boundary valve.

j c. Main steam piping branch connections 52.5" NPS are not classified.

General Design Criterion 2 of Appendix A to 10CFR Part 50 requires that nuclear power plant structures, systems, and mmponents important to safety, to be designed to withstand the j effects of earthquakes without loss of capability to perform their safej runction. Regulatory Guide 1.29 classifies these systems as Seismic Category l. Because systems and components classified in either Quality Group B or C by Regulatory Guide 1.26 are important to safety, they i

must also be Seismic Category 1. However, Regulatory Guide 1.29 specifically excludes Main Steam piping downstream of the outboard CIV that is s2.5" NPS from Seismic I categorization.

Consequently, since this piping is not Seismic I, it should not be Quality Group B or C.

Therefore, PBAPS 2 & 3 Main Steam piping downstream of the outboard CIV that is s2.5" NPS

.' is not classed for Seismic I purposes.

l 3.2 PBAPS 2 & 3 Class 2 Systems Regulatory Guide 1.26 requires that systems or portions of systems that perform the following safety functions shall be Class 2:

1

a. Emergency Core Cooling l

b. Post Accident Contalament Removal

, c. Post Accident Fission Product Removal

d. Reactor Shutdown i e. Residual Heat Removal

)

l i

5_______________.__

i Specification M-733, Rev.2 PBAPS 2 & 3 ISI Program Attachment 1 Page 7 of 18 in addition, Main Steam piping downstream of the outboard CIV and up to but not including the turbine stop and bypass valves shall be Class 2.

Specific Class 2 PBAPS 2 & 3 systems and their safety function are provided in Table 3.2-1.

3 Boundaries and exemptions for these systems are provided in Table 3.2-2.

l TABLE 3.21 l CLASS 2 SYSTEMS i

SYSTEM FUNCTION l

i Main Steam (MS) Specifically identified in R.G.1.26 Control Rod Drive Hydraulic (CRD) Reactor Shutdown

. Containment Atmosphere Post Accident Fission 1

Control (CAC) Product Removal Residual Heat Removal (RHR) Emergency Core Cooling, Post Accident Containment Heat 3

Removal Residual Heat Removal Standby Liquid Control (SLC) Reactor Shutdown j Reactor Core isolation Cooling (RCIC) Residual Heat Removal Core Spray (CS) Emergency Core Cooling i

High Pressure Coolant injection (HPCI) Emergency Core Cooling Containment Atmosphere Dilution (CAD) Connected to containment and Torus Spray piping i

i u

. . . - ~. .. . - - -- -

t TABLE 3.2-2 CLASS 2 BOUNDARIES AND EXEMPTIONS System Drawina(s) System Name Boundary Exemptions 1 M-304, 303, 351 Main Steam From outboard CIV up to AH piping and but not including the components <4" NPS.

turbine stop and bypass valves. Branch connections s2.5" NPS are unclassed.

3 M-356, 357 Control Rod Drive Scran supply and All piping and Hydraulic exhaust headers cric,4,nents <4* NPS. ,

including the scram discharge volume. The scran discharge volume vent and drain piping to the first isolation valves.

This classification is consistent with the GE classification that has i

been accepted by the '

NRC in NUREG-0803.

9 M-367 Containment From penetrations N All piping and Atmosphere Control .,

and N-219 to the c6iipOncrats operate at g h '__ E N },

Standby Gas Treatment less than 200 F and 275  %

8 =

System connection. PSIG, therefore, are exempt.

g$ h Ink m

em a j p. $ 5-abs

_ _ _ - - _ _._ . . _ _ ._ . - . . . . _~ --- .m.-- ~ . . _ . - . _ . _ . . - - - _ . . _ _ _ _ . _. . . _ .

l TABLE 3.2-2 CLASS 2 BOUNDARIES AND EXEMPTIONS System Drawino(s) System Name Boundary Exemotions 10 M-361 Residual Heat Removal Entire system with the 1. Piping and exception of the portion components beyond the which is Class 1. last shut off valve that do not contain water dunng normal operation.

2. Piping and components <4* NPS.

11 M-358 Standby Liquid Control The entire system, All pW and excludog the test tank components since NPS and associated piping, is <4".

up to the outboard containment check valve.

.. IM'48E 4D rf) - -

o to 33

2. . PI6 oo- s

,e

. - . . . . - .. ~ . _. - .. . . - . - . . -. .- - - - .

TABLE 3.2-2 CLASS 2 BOUNDARIES AND EXEMPTIONS System Drawino(s) System Name Boundary Exemptions 13 M-359, 360 Reactor Core Isolation 1. Steam supply line This system is not an Cooling from the outboard emergency core coohng containment isolation system and it does not valve up to but not operate during normal including the turbine reactor operation, throttle valve. therefore, all piping and

2. Turbine exhaust components are piping from the turbine to exempt.

the suppression pool including associated drains up to but including the barometric condensate.

3. Water piping from suppression pool through the pump to the outboard containment isolation on the the discharge header including minimum flow @g@@FM piping and lube oil cooler piping.

S gaK,jurn4 - 5 5 g ro 3 E EA 3 9e I 6 g- ca io "

. . _ . ._ _ _ _ _ _ _ _ _ ._. . _ _. _.... _ . . . , ,___ .. _ . _ _ _ . . . m . . _

TABLE 3.2-2 CLASS 2 BOUNDARIES AND EXEMPTIONS 14 M-362 Core Spray Entire system with the 1. Piping and exception of the portion ccirvonerds beyond the which is Class 1. last shut offvalve that do not contain water during normal operation.

2. Piping and ccirpOnents 54' NPS.

i

. I

~

it!!if

p! i l aa n !' s-l g un

1_________________________ _ _ - _ - _ _ _ _ _ _ _ _ - - - ------- - -

TABLE 3.2-2 i

• CLASS 2 BOUNDARIES AND EXEMPTIONS l

System Drawina(s) System Name Boundary Exemptions .;

23 M-365,366 High Pressure Coolant 1. Steam supply line 1. Piping and Injection from the outboard components beyond the containment isolation last shut off valve that valve up to but not do not contain water including the turbine during normal throttle valve. operations.

2. Turbine exhaust 2. Piping and piping from the turbine to components 54' NPS.

the suppression pool including associated

, drains up to but not including the barometric condenser.

3. Water piping from the suppression pool through the pump to the outboard containment isolation on the discharge header including minimum flow piping and lube oil cooler E$

1 nim. i 44 E R $%h.

p. f g 5'

g- ca io .'

1 TABLE 3.2-2 ,

CLASS 2 BOUNDARIES AND EXEMPTIONS System Drawinofs) System Name Boundary Exemptions 52 M-372 Containment i

From the ccscsuen with All piping and Atmosphere Dilution the RHR containment components operate at spray header up to and less than 200 F and 275 includmg the first PSIG, therefore, are isolation valve. exempt.

i

, 2 E 3 FP

! * - 1 o>2ft 89 =.

al u

aa n x ,t -

- .3" u io 1

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Attachment 1

, Page 14 of 18 4.0 CLASS 3 (Quality Group C) 4.1 Boundary Definition Class 3 boundaries for PBAPS 2 & 3 were determined in accordance with C.2 of Regulatory Guide 1.26, Rev. 3. Regulatory Guide 1.26 specifies that the boundaries for Class 3 systems include the portions of the system required to accomplish the specific safety function and connected piping up to and including the first valve (including safety or relief valve) that is either normally closed or capable of automatic closure when the safety function is required. PBAPS 2

& 3 has taken the following positions with regard to these boundaries:

a. For instrument lines connected to Class 3 piping or components the boundary shall be at the instrument root valve.

b. Valves that are normally open and are equipped with remote manual actuators are considered an acceptable boundary valve.

4.2 PBAPS 2 & 3 Class 3 Systems i

Regulatory Guide 1.26 requires that systems or portions of systems that perform the following safety functions shall be Class 3. The following are the safety functions applicable to PBAPS 2 i & 3.

a. Cooling water systems that are designed foe:

1. Emergency Core Cooling

2. Post Accident Containment Heat Rernoval

3. Post Accident Containment Atmosphere Cleanup

4. Primary and Secondary Residual Heat Removal from Reactor and Spent Fuel Storage Pools.

b. Cooling and seal water systems for diesels and control room.

c. Systems or portions of systems with a safety function that are connected to the reactor coolant pressure boundary and are capable of being isolated from the boundary during .

all modes of reactor operation by two valves, each of which is either normally closed or I

. capable of automatic closure. Since 10CFR50.2(v) considers the primary relief valve as an adequate reactor coolant boundary, the relief valve discharge lines are Class 3.

Specific PBAPS 2 & 3 systems and their safety functions are provided in Table 4.21.

Boundaries and exemptions for these systems are provided in Table 4.2-2.

l l

1 l

l

d TABLE 4.2-1 CLASS 3 SYSTEMS System Function Main Steam (MS) Connected to reactor coolant pressure boundary. Functions to direct Main

. Steam relief vahm discharge to suppression pool Fuel Pool Coohng and The Reair6d Heat Removal System provides primary cooEng via RHRHX and Cloenup (FPC) secondary (make-up for water Isot during pool boil oN) safety related fanirtd

- heat removal for rancent and spent fuel pools, however, portons of the FPC

piping are m=y to connect the RHR system to the prd_  !

' % Pressure Service Provides cooling water for ECCS and Post Accariant Containment Heat removal.

Water (HPSW) i i Emergency Service Water Provides cooling for Emergency Desel Generators and ECCS room coolers.

l (ESW) l Emergency Cooling Water Pmvides haelay to ESW. t (ECW) 1 l

I 1 g y I HE E u sl. .

g- PI{

ca '.

_ . . . . . - . - . ~ - . . _ . . - . . - - ---. . - . . - - . - - - - . . . - - . . . . . . . . - . . . _ . - - . . ~ . . - . . .

TABLE 4.2-2 CLASS 3 BOUNDARIES AND EXEMPTIONS System DrawinWs) System Name Boundary Exemptons -

1 2 ,

19 M-363 Fuel Pool Coohng and Portions of the system All piping and '

Cleanup necessary to provute the components operate at RHR system with a less than 200 F and 275 suction and discharge to PSIG, therefore, are the spent fuel and '

exempt.

refueling pools.

32 M-315,330 High Pressure Service Entire System. 1. Piping and Water components s4* NPS. ,

i 33 M-315, 330 Emergency Service Entire System. 1. Piping and i Water components 54 NPS.

2. Piping and components beyond the test shut off valve on retum lines to pond are i subject to less than 200 l F and 275 PSIG and are no longer in support of ECCS, therefore, are ,

exempt.

48 M-315 Emergency Coolmg Entre System. Piping and components Water i s4"NPS.  ;

a nA t 9= $ "6 i g" u', i i 4

1 Specification M 733 Rev. 2 PBAPS 2 & 3 ISI Program

, Attachment 1 Page 17 of 18 5.0 Systems Not Address in Reg. Guide 1.26 Section D of Reg. Guide 1.26 mentions systems not covered by the guide that should be tested to quality standards commensurate with the safety function performed. PBAPS 2 & 3 has evaluated these and other systems not covered by Reg. Guide 1.26 and has determined that

the surveillance testing presently being performed satisfies this requirement. Table 5.01 contains a listing of the systems evaluated and a brief discussion on how they are tested.

i 5

j 1

e i

1 1

i 1

1

_ . -._ _ _ . . _ . . . . _ _ _ _ _ _ _ . _ - . __ _ _ _ _ _ . _ _ _ _ . _ _-. _. . ___ .- .m .

TABl.E 5.0-1 '

, System Dimen=ainn Non-safety systems that penetrated This piping is not addressed in Reg. Guide 1.26, and due to the vinta2e of PBAPS the primary containment.

2 & 3, these lines were not constructed as Class 2 lines. These systems were evaluated and it was determined that if they were designated Class 2 for ISI purposes, they would all be exempt, and, therefore, only pressure testing would be required. Because the only safety function of these lines is to maintain containment integrity, it was determined that the Appendix J, Type A & C testing would ensure the capahmey of this pipeg to perform its safety function. Therfore, j this piping is not cla*=mf for ISI.

instrument Nitrogen Provides makeup rutrogen to /DS accumulators. Integrity of the system is constantly monitored by flow indscation per UFSAR 7.3A.7.15.  ;

Diesel Startmg Air and Fuel Oil Starting Air is necessary for diesel starting and the Fuel Oil Transfer System is Transfer naca==ary for long term operation of the diesels. The diesels are tested exterdc;.'; by Tech. Specs. In parbcular, Tech. Spec. 4.9.A.1 ansures the integrity i of these systems.

MSIV Accumulators The accumulators are installed to assist in the closum of the MSIV. There is a controversy as to whether or not the accumulators are needed in order for the MSIV to stroke in the required time. If it is determined that the acnunulators are .i needed, then an inservice test to stroke the MSIV will be performed with the make up to the accumulators isolated,thus, the inservice test wlE verify the integrity of the accumulator. If it is determined that the accumulators are not needed, then the accumulator has no safety function. In either case, the acnnnulators are not classed for ISI purposes.

I' R E m' F R=>

8b!y e.

g- a 5 s.M s er wa=

_ _ _ _ _ - . _ _ _ - - . . _ - - - - - - _ _ _ - - _ - - - -- - - - - - - - - - - - - ~ - - - - - - - - - - - - -

1 Specification M-733, Rev. 2 l PBAPS 2 & 3 ISI Program Attachment 2 Page 1 of 1 TABLE OF CONTENTS Attachment Number Position Paper Number Subiect 1 21 PSC-92-003 Insulation removal for component support examination 2-2 PSC-92-004 Additional examinations of component supports

. . . - .. . - - - - - - ~ . - -

i l

Specification l M-733, Rev. 2 l PBAPS 2 & 3 ISI Program Attachment 2-1 l Page 1 of 2 ASME SECTION 3 ISI PROGRAM Position Paper No. PSC-92-003 Supersedes Position Statement IPS # 87 002

Subject:

This ISI program position provides guidance for the implementation of specific component support examination requirements of the ASME Section XI Code.

Reference:

This position is for use in conjunction with the 1980 Edition of ASME Section XI, through the 1986 Edition.

Applicability: This position applies to all component supports which are within the jurisdiction of the '

Section XI Code. It pertains to nonintegrally attached supports which have bolted or other mechanical connections buried beneath the component insulation.

Discussion: ASME Section XI (subparagraph IWF 1300(e)) allows the component support visual examination boundary to extend from the surface of the component insulation, provided the nonintegrally attached support either carries the weight of the component or serves as a structural restraint in compression. This rule assumes that loss of integrity of the bolting or other mechanical connection buried beneath the insulation, and not accessible for visual examination, will become obvious on the extemal surface of the insulation. Therefore, the

subject component support must be canying the weight of the component at all times.

Position: If a component support required to be examined, is a nonintegrally attached support, and contains a mechanical connection which is buried beneath the component insulation, the insulation need not be removed provided the support carries the weight of the component (either in tension or compression), or acts as a restraint in compression during normal

plant operations (per design calculations). Snubbers do not qualify for this position, since they do not carry the weight of the component.

1 i

if the bolted or other mechanical connection of a nonintegrally attached support is able to be examined without removing the insulation, then this position does not apply, since the insulation does not need to be removed.

Examples: Component supports which qualify for use of this position paper.

-spring hangers i

rod hangers l

-spring supports '

-vertically oriented struts (above or below component)

-frame supports or restraints (containing bolted or other mechanical connections) which bear the weight of the component l

-restraints acting in compression during normal operations, 1

l Component supports which do not qualify for use of this position paper.

i snubbers horizontal struts (not acting in compression)

{

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Attachment 21 Page 2 of 2 Summary: 1. Component supports must carry the weight of the component (in tension or compression) or act as a restraint in compression during normal operations to qualify for this position paper.

2. Snubbers do not qualify for this position paper.

3. If the mechanical connection is not buried within the component insulation, then the insulation need not be removed.

Reference:

1. ASME Section XI interpretation No. IN92-010, dated March 10,1992.

2. ASME Section XI Interpretation No. IN92-006B, dated March 10,1992.

3. ASME Section XI Position Statement IPS# 87-002, dated November 28,1988.

l i

l l

1 l

I l

l l I

l

- . - - .. . - . ... . . - . -. .~ .-. - . . . -

i Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program i Attachment 2 2

, Page 1 of 2 t

ASME SECTION XI

ISI PROGRAM l Position Paper No. PSC-92-004 Supersedes Position Statement IPS # 91001 q

Subject:

This ISI program position provides guidance for the implementation of specific component j support examination requirements of the ASME Section XI Code.

Reference:

This position may be used in conjunction with the 1980 Edition of ASME Section XI, through the 1986 Edition. It may also be used in conjunction with the Limerick (LGS) 1 &

2 component supports examination program conducted in accordance with LGS Relief Request RR-09.

4 l Applicability: This position may be applied to all component supports which are within the jurisdiction of l the station ISI or attemate ISI Program (LGS) for component supports examination. It shall l .nqt be applicable to the examination and testing programs for snubbers, which are j conducted in accordance with the plant Technical Specifications.

, Discussion: - ASME Section XI, subparagraph IWF-2430(a) requires additional examinations of component supports, if the results of regularly scheduled ISI examinations of component I

supports require corrective measures in accordance with the provisions of IWF 3000.

Paragraph IWF-3122 provides four methods for acceptance of the results of examinations

;

IWF-3122.1 Acceptance by Examination; IWF-3122.2 Acceptance by Repair, lWF 3122.3 .

Acceptance by Replacement; and IWF 3122.4 Acceptance by Evaluation or Test. l Component support examination results which do not satisfy first-line screening or acceptance criteria, do not automatically require repair or replacement as described in ,

, subparagraphs IWF 3122.2 and IWF-3122.3 respectively. Generally, such unacceptable  !

component supports may be found acceptable for continued / intended service via l j evaluation or test, as described in subparagraph IWF 3122.4. This acceptance by l evaluation or test is not considered a corrective measure. I i

l Occasionally, component support examination results found acceptable by evaluation or i

test may still require some minor rework of the support, often to avoid making unnecessary i

changes to the applicable design documents. Such rework, after the support has been i determined to be acceptable for continued / intended service, is also not considered a corrective measure.

. Position: Component supports found acceptable for continued / intended service' by evaluation or test l

(even though examination results deviate from screening / acceptance criteria), are not considered supports requiring corrective measures as referenced in lWF 2430a.

Accordingly, additional examinations need not be performed. Additionally, minor rework of

a component support after it's acceptance for continued service by evaluation or test, is l also not considered a corrective measure, and does not require additional examinations '

to be performed.

2

Specification M 733, Rev. 2 PBAPS 2 & 3 ISI Program Attachment 2 2 Page 2 of 2 Component supports found unacceptable for continued / Intended service after evaluation or test _dq require additional examinations to be performed. Likewise, component supports requiring automatic rework, repair, or replacement as a result of examination results, will also require additional examinations to be performed.

1. For the purpose of this position paper, ' continued / intended service' is defined as a condition within the design basis of the component, and the condition will not compromise the long term use of the component.

Examples: A variable spring hanger has an as-found spring load setting which deviates from the design drawing specified setting by more than the tolerance allowed in the examination procedure. After evaluation, the as-found load setting is determined to be acceptable for intended and continued service, however the design drawing setting would then have to be revised. In lieu of revising the design drawings, the variable spring hanger is field adjusted (reworked) to the design load setting. This situation would aqt require additional examinations to be performed.

Examination of a variable spring hanger reveals that the spring can load scale (provided for measuring load setting) is missing. Subsequent evaluation of linear measurements recorded, Indicate that the as-found spring position represents an acceptable load setting, and the support is acceptable for its intended service. Minor rework is conducted however, 4

to attach a new load scale to the spring can. Additional examinations of IWF 2430a are no_1 required in this situation.

Examination of a rigid sway strut reveals a completely cracked weld between the strut body and the extension tube. Evaluation (if conducted) reveal that the support would not fulfill its intended function in a tension mode. Repair of the support is required. Additional examinations are, required in this situation.

Summary: 1. Component supports with unacceptable examination results which are found to be acceptable for continued / Intended service by evaluation or test, do not require the examination of additional supports.

2. Minor rework performed on component supports found acceptable for continued / Intended service need not be considered corrective measures. Addi+Jonal examinations do not need to be performed.

Reference:

1. ASME Section XI interpretation No. XI 188 30 dated April 30,1986.

2. ASME Section XI Position Statement IPS# 91001, dated December 30,1991.