ML20076F988

Rev 0 to Second 10-Yr Interval ISI Plan for Callaway Nuclear Power Plant

ML20076F988
Person / Time
Site:	Callaway
Issue date:	10/12/1994
From:	Kulat S, Mccraken S, Potter H UNION ELECTRIC CO.
To:
Shared Package
ML20076F985	List: ML20076F984 ML20076F988
References
PROC-941012, NUDOCS 9410180375
Download: ML20076F988 (66)

Text

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SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PLAN !

FOR THE  !

CALLAWAY NUCLEAR POWER PLANT 1

i UNION ELECTRIC COMPANY 1

I bb $00br5 ??bObjaz, PDR

REVISION 0 October 12,1994 i SECOND INTERVAL INSERVICE INSPECTION PLAN CALLAWAY NUCLEAR PLANT Prepared by h lY0 S. L. McCracken S. D, Kulat VECTRA ISI Engineer ISI Engineer ANIER w Supervisor Review V rr a te lvk. ( r H. JYotter D. S. Hollabaugh H S B. I. & I. Co. Supervising Engineer.

Performance /IS!

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TABLE OF CONTENTS SECTION DESCRIPTION PAGE Revision Summary Sheet iv 1.0 Introduction and Plan Description 1-1 1.1 Oveniew 1-1 1.2 Basis ofInservice Inspection Plan 1-1 1.3 System Classification 1-2 1.4 Augmented Inservice Inspection Requirements 1-3 2.0 Inservice Inspection Program Drawings 2-1 2.1 Drawing Nomenclature 2-1 2.2 Inservice Inspection Boundary Drawings 2-3 2.3 Piping Isometrics 2-7 2.4 Equipment Detail Drawings 2-11 2.5 Component / Equipment Support Drawings 2-12 3.0 Inservice Inspection Summary Tables 3-1 3.1 ASME Section XI Insenice Inspections 3-1 3.2 Augmented Insenice Inspections 3-13 4.0 Alternative Requirements to ASME Section XI,1989 4-1 Edition 4.1 Adoption of Code Cases 4-1 4.2 Use of Subsequent Editions of ASME Section XI 42 4.3 Inservice inspection Relief Request Index 4-3 i 4.4 Inservice Inspection Relief Requests 4.4-1 5.0 NRC Correspondence 5-1 I

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REVISION SUMM ARY SITEET SECTION EFFECTIVE PAGE(S) REVISION DATE 1.0 1-1 0 10/12/94 1.1 1-1 0 10/12/94 1.2 1-1 to 1-2 0 10/12/94 1.3 1-2 to 1-3 0 10/12/94 1.4 1-3 0 10/12/94 2.0 2-1 0 10/12/94 2.1 2-1 to 2-3 0 10/12/94 2.2 2-3 to 2-6 0 10/12/94 2.3 2-7 to 2-10 0 10/12/94 2.4 2-11 0 10/12/94 2.5 2-12 0 10/12/94 3.0 3-1 0 10/12/94 3.1 3-1 to 3-12 0 10/12/94 3.2 3-13 to 3-14 0 10/12/94 4.0 4-1 0 10/12/94 4.1 4-1 to 4-2 0 10/12/94 4.2 4-2 0 10/12/94 4.3 4-3 to 4-4 0 10/12/94 44 Reference Section 4 3 for Revision Status of Relief Requests 5.0 5-1 0 10/12/94 iv

Callaway Plant 2nd Interval Inservice Inspection Plan SECTION

1.0 INTRODUCTION

AND PLAN DESCRIPTION  :

-1.1 Overview 1.1.1 This Insersice Inspection Plan outlines the requirements for the inspection of Class 1,2, and 3 pressure retaining components and their supports at the Callaway

• Nuclear Power Plant.

1.1.2 This Inservice Inspection Plan will be effective from August 1,1995, through and i including December 18,2004, which represents the second ten-year interval for the  :

Callaway Nuclear Power Plant.

1.1.3 The key features of this Plan are the Introduction and Plan Description, Relief Requests, and Summary Tables. The details of theinservice Inspection Program 1 are addressed in other documents that are available at the Callaway Plant. These -  ;

documents include, but are not limited to, inservice inspection boundary drawings,  ;

piping isometric drawings, equipment detail drawings, a component database ,

listing of each weld, valve, suppon, etc., and documents supporting  ;

implementation of the Inservice Inspection Program. -

1.2 Basis ofInservice Inspection Plan  ;

1.2.1 ' This Inservice Inspection Plan was developed in accordance with the requirements delineated in the December 31,1992, issue of 10 CFR 50.55a and the 1989 }

Edition of the American Society ofMechanical Engineers (ASME) Boiler and l Pressure Vessel Code,Section XI, Subsections IWA, IWB, IWC, IWD, and IWF, for Inspection Program B. Accordingly, this Inservice Inspection Plan provides the details necessary for performing the inservice inspection of the Callaway Class 1,2, and 3 pressure rctaining components and supports.

1.2.2 The following ASME Section XI,1989 Edition Subsections, Anicles, or Paragraphs are not included or addressed in this Inservice Inspection Plan >

1 1.2.2.1 The containment liner and concrete inspection and testing requirements of Subsections IWE and IWL are not included in this Inservice Inspection I Plan. The rules ofIWE and IWL are currently not required by 10 CFR '

50.55a.

l.2.2.2 The pump and valve testing requirements of Subsections IWP and IWV  ;

are not included in this Inservice Inspection Plan. The rules ofIWP and  !

IWV are addressed in a separate submittal to the NRC staff.

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Callaway Plant 2nd Interval Inservice Inspection Plan 1.2.2.3 The snubber inservice inspection requirements of Paragraphs IWF.

5200(a), IWF-5200(b), IWF-5300(a), and IWF-5300(b) are not addressed in this Inservice Inspection Plan. The extent, frequency, and acceptance standards for snubber assembly testing and inspection will be in accordance with Callaway Technical Specification 3/4.7.8.

1.2.2.4 The steam generator tubing examination requirements of Table IWB-2500-1, Examination Category B-Q and the acceptance standards of Paragraph IWB-3521.1 are not addressed in this Inservice Inspection Plan. The extent, frequency, and acceptance standards for steam generator tubing inspection and testing will be in accordance with Callaway Technical Specification 3/4.4.5.

1.2.3 Alternative requirements to ASME Section XI,1989 Edition, are set forth in Section 4.0 of this Inservice Inspection Plan. Alternative requirements are in accordance with 10 CFR 50.55a and ASME Section XI. ,

1.2.4 With the exception of examinations that may be deferred until the end of the inspection interval as specified in Table IWB-2500-1, inservice inspections shall be performed in accordance with Inspection Program B as outlined in IWA-2432, IWB-2412, IWC-2412 and IWD-2412 of ASME Section XI. The inspection schedule for the second interval is divided into three periods such that approximately one third of the inspections will be completed every period.

Successive inspections shall be in accordance with IWB-2420, IWC-2420, and Code Case N-491 -2420. Deviations to inspection schedules may occur provided compliance with Code requirements is maintained.

1.2.5 The commercial operating license date for the Callaway Nuclear Power Plant was December 19,1984. As allowed by ASME Section XI, Paragraph IWA-2430, the first inspection inte val was extended from December 18,1994 to July 31,1995.

1.2.6 The construction code for all ASME components is ASME Section Ill. The principal edition used for construction of the plant was the 1974 Edition thru Summer 1975 Addenda.

i 1.3 System Classification 1.3 1 The quality group classification system for radioactive water / steam-containing components important to the safety of water-cooled nuclear power plants is established by NRC Regulatory Guide 1.26, Revision 3, in conjunction with 10 CFR 50.55a. Regulatory Guide 1.26," Quality Group Classification and Standards", defines the Quality Group Classification System consisting of four Quality Groups, A through D. The definition of Quality Group A is provided by 10 CFR 50.2 under " Reactor Coulant Pressure Boundary" The definitions of ,

l Groups B, C, and D are provided by Regulatory Guide 1.26.

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Callaway Plant 2nd Interval inservice Inspection Plan ;

1.3.2 Components subject to insenice inspection are shown on the Inservice Inspection  :

Boundary Drawings listed in Section 2.2 of this Insenrice Inspection Plan.

Pursuant to 10 CFR 50.55a, the inservice inspection requirements of AShfE ,

Section XI have been assigned to these components within the constraints of existing plant design.

1.4 Auemented Inservice Inspection Requirements Augmented inservice inspection requirements are those examinations that are specified by documents other than the ash 1E Section XI Code. The additional examinations required by the following documents have been added to the Callaway Inservice Inspection Program:

1.4.1 U.S. Nuclear Regulatory Commission Standard Review Plan (SRP), Section 3.6.1, Rev.1," Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment"(NUREG-0800). Several piping systems require augmented inspections for protection against postulated piping failures as outlined in SRP Section 3.6.1. Piping systems subject to the augmented inspection criteria of SRP Section 3.6.1 are shown on the Inservice Inspection Boundary Drawings listed in Table 2.2 of this Inservice Inspection Plan. In addition, detailed high energy pipe break isometric drawings of applicable systems are provided in Section 3.6.1 of the Callaway Plant FSAR. A summary of the number of welds subject to the augmented inspection criteria of SRP Section 3.6.1, is provided in Table 3.2 of this Inservice Inspection Plan.

1.4.2 U.S. Nuclear Regulatory Commission Standard Review Plan, Section 6.6, Rev. I,

" Inservice Inspection of Class 2 & 3 Components"(NUREG-0800).

1.4.3 U.S. Nuclear Itegulatory Commission Regulatory Guide i 14, Rev.1," Reactor Coolant Pump Flywheel Integrity" 1.4.4 U.S. Nuclear Regulatory Commission Regulatory Guide 1.65, Rev. O, "hiaterials and Inspections for Reactor Vessel Closure Studs" 1.4.5 U.S. Nuclear Regulatory Commission Regulatory Guide 1.137, Rev O " Fuel-Oil Systems for Standby Diesel Generators" 1.4.6 U.S Nuclear Regulatory Commission Regulatory Guide 1.150, Rev.1," Ultrasonic )

Testing of Reactor Vessel Welds During Presenice and Inservice Examinations",

Regulatory Position C.8 (Alternative hfethod).

1.4.7 Code of Federal Regulations, Part 10,50.55a(g)(6)(ii)( A), December 31,1992,

" Augmented Examination of Reactor Vessel" i

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Callaway Plant 2nd Interval Inservi:e Inspection Plan i

SECTION 2.0 INSERVICE INSPECTION PROGRAM DRAWINGS ,

This section provides a listing of the various drawings applicable to the Callaway Inservice Inspection Program. ,

2.1 Drawing Nomenclature 2.1.1 System Designators Table 2.1 below lists the two letter System Designator used for each piping system subject to inservice inspection at the Callaway Plant.

TABLE 2.1. f SYSTEM DESIGNATORS I t

System Designator System 1 AB Main Steam  :

AE Main Feedwater AL Auxiliary Feedwater BB Reactor Coolant System including. i Reactor Pressure Vessel Pressurizer  !'

Steam Generators BG Chemical and Volume Control  !

BL Reactor Make-up Water BM Steam Generator Blowdown BN Borated Refueling Water Storage '

EC Fuel Pool Cooling and Cleanup  !

EF Essential Service Water EG Component Cooling Water ,

EJ Residual Heat Removal EM High Pressure Coolant Injection EN Containment Spray EP Accumulator Safety Injection FC Auxiliary Feedwater Pump Turbine ,

GF Miscellaneous Building HVAC GG Fuel Building  !

GK Control Building HVAC l GL Auxiliary Building HVAC i GN Containment Cooling GP Containment Integrated Leak Rate Test 2-1 .

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1 Callaway Plant 2nd Interval -

Inservice Inspection Plan System Designator System ~

GS Containment Hydrogen Control GT Containment Purge HVAC HB Liquid Radwaste HD Decontamination JE Emergency Fuel Oil KA Compressed Air E KB- Breathing Air KC Fire Protection KJ Standby Diesel Generator LF Auxiliary Building Equipment  :

SJ Nuclear Sampling [

2.1.2 Piping Classifications 2.1.2.1 Piping classifications are designated by a three-letter code Listed below l' are the appropriate letter designations for piping subject to inservice inspection. The first letter indicates the Standard Rating Class; the i second letter the type of material, and the third letter the Code or ,

standard to which the piping is designed. j 2.1.2.2 First Letter - Primary Rating Class l A - Specific pressure & specific temperature B - Class 2500 C - Class 1500 D - Class 900 i E - Class 600 F - Class 400 G - Class 300 7 l

H - Class 150 Second Letter - Material ,

B - Carbon Steel C - Austenitic Stainless Steel L - Carbon Steel-impact tested F

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i Callaway Plant 2nd interval inservice Inspection Plan Third Letter - Anolicable Codes A - ASME B & PV Code, Section Ill, Class 1 B - ASME B & PV Code,Section III, Class 2 C - ASM3 B & PV Code,Section III, Class 3 D - Power Piping Code, ANSI B31.1 2.1.3 Line Identification Numbers The line numbers identified on the drawings listed herein provide useful information about the piping. The lines are identified using the following '

convention:

t AB - 107 - EBB - 6" System Designator Pipe Size Sequence Number Pipe Classification Each line, a portion ofline, is assigned a system desigt .ar, line sequence '.

number, pipe classification, and pipe size. The system designator and line sequence number can be cross referenced to Bechtel Specification MS-2 to determine the line description, design temperature and pressure, and service or ,

normal operating temperature and pressure. The pipe classification can be cross referenced to Bechtel Specification MS-1 to determine the pipe schedule and material specification. >

2.2 Inservice Inspection Boundary Drawines Table 2.2 provides a listing of the Inservice Inspection Boundary Drawings applicable to the second interval at the Callaway Plant. These drawings are Callaway Plant Piping &

Instrumentation Drawings that are color coded to identify the Quality Group A, B, and C ,

piping and components subject to inservice inspection. The color code also identifies Non-Exempt, Exempt, and Augmented boundaries. Listed below is a brief description of each type boundary depicted on the boundary drawings.

2.2.1 Non-Exempt Bogndaries The non-exempt boundaries identify piping and components subject to the ,

nondestructive examination, visual examination, and pressure test requirements of .

ASA1E Section XI, Subsections IWB, IWC, or IWD. Non-Exempt Quality Group A, B, and C boundaries are color coded red, blue, and green respectively 2-3

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2.2.2 Exemot Boundarie_s The exempt boundaries identify piping and components that are subject only to the 'I pressure test requirements of ASME Section XI, Articles IWB-5000, IWC-5000, and IWD-5000. As permitted by ASME Section XI, Paragraphs IWB-1220, IWC- ,

1220, IWD-1220, and Code Case N-491, the piping, components, and suppons within the exempt boundaries do not require nondestructive (i.e., volumetric or  :

surface) examination or visual (i.e., VT-1 or VT-3) examination. Exempt Quality l Group A, B, and C boundaries are color coded orange, light blue, and light green i respectively. 1 2.2.3 Augmented Boundaries The boundaries for the high energy lines that require augmented examination in  !

accordance with NRC Standard Review Plan, Section 3.6.1 are identified by l dashed colored lines on the applicable boundary drawings. In addition, the Diesel l Generator Fuel Oil piping that requires augmented pressure testing in accordance  !

with NRC Regulatory Guide 1.137 is identified on the applicable boundary [

drawings. .i TABLE 2.2 INSERVICE INSPECTION BOUNDARY DRAWINGS  ;

Drawing Number System '[

ISI-M-22AB01(Q) Main Steam  !

ISI-M-22AB02(Q) Main Steam ,

ISI-M-22AE02(Q) Main Feedwater =!

ISI-M-22AL01(Q) Auxiliary Feedwater -l ISI-M-22BB01(Q) Reactor Coolant '

ISI-M-22BB02(Q) Reactor Coolant {

ISI-M-22BB03(Q) Reactor Coolant l ISI-M-22BB04(Q) Reactor Coolant ISI-M-22BG01(Q) Chemical and Volume Control i ISI-M-22BG02(Q) Chemical and Volume Control }

ISI-M-22BG03(Q) Chemical and Volume Control ISI-M-22BG04(Q) Chemical and Volume Control l ISI-M-22BG05(Q) Chemical and Volume Control i ISI-M-22BL01(Q) Reactor Make-up Water >

ISI-M-22BM01(Q) Steam Generator Blowdown ISI-M-22BN01(Q) Borated Refueling Water Storage  !

ISI-M-22EC01(Q) Fuel Pool Cooling and Clean-up ISI-M-22ECO2(Q) Fuel Pool Cooling and Clean-up j ISI-M-2UEF01(Q) Essential Service Water ISI-M-22EF01(Q) Essential Service Water 1 2-4 j r

mer Callaway Plant 2nd Interval Inservice Inspection Plan TABLE 2.2 INSERVICE INSPECTION BOUNDARY DRAWINGS (cont.)

Drawing Number System ISI-M-22EF02(Q) Essential Service Water

, ISI-M-22EG01(Q) Component Cooling Water ISI-M-22EG02(Q) Component Cooling Water ,

ISI-M-22EG03(Q) Component Cooling Water ISI-M-22EJ01(Q) Residual Heat Removal ISI-M-22EM01(Q) High Pressure Coolant Injection ISI-M-22EM02(Q) High Pressure Coolant Injection ISI-M-22EN01(Q) Containment Spray ISI-M-22EP01(Q) Accumulator Safety Injection ,

ISI-M-22FC02(Q) Auxiliary Feedwater Pump Turbine ISI-M-22GF01(Q) Miscellaneous Building HVAC ISI-M-22GG02(Q) Fuel Building HVAC ISI-M-22GK01(Q) Control Building HVAC i ISI-M-22GK03(Q) Control Building HVAC ISI-M-22GL01(Q) Auxiliary Building HVAC ISI-M-22GLO2(Q) Auxiliary Building HVAC ISI-M-22GLO3(Q) Auxiliary Building HVAC ISI-M-22GN01(Q) Containment Cooling ISI-M-22GP01(Q) Containment Integrated Leak Rate Test ,

ISI-M-22GS01(Q) Containment Hydrogen Control l ISI-M-22GT01(Q) Containment Purge HVAC j ISI-M-22HB01(Q) Liquid Radwaste ' I ISI-M-22HD01(Q) Decontamination ISI-M-22JE01(Q) Emergency Fuel Oil ISI-M-22KA01(Q) Compressed Air i ISI-M-22KA02(Q) Compressed Air (Service Air) _

_ISI-M-22KA05(Q) Compressed Air ISI-M-22KB01(Q) Breathing Air ISI-M-22KC02(Q) Fire Protection  !

ISI-M-22KJ01(Q) Standby Diesel Generator "A" Cooling Water ISI-M-22KJ02(Q) Standby Diesel Generator "A" Intake Exhaust, Fuel Oil and Starting Air ISI-M-22KJ03(Q) Standby Diesel Generator "A" Lube Oil ISI-M-22KJ04(Q) Standby Diesel Generator "B" Cooling Water ISI-M-22KJ05(Q) Standby Diesel Generator "B" Intake Exhaust, Fuel Oil and Starting Air ISI-M-22KJ06(Q) Standby Diesel Generator "B" Lube Oil 1

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Inservice Inspection Plan - i TABLE 2.2 INSERVICE INSPECTION BOUNDARY DRAWINGS (cont.)

Drawing Number System ISI-M-22LF03(Q) Auxiliary Building Floor and Equipment Drain ISI-M-22LF09(Q) Reactor Bldg. & Hot Machine Shop Floor and' Equipment Drain ISI-M-22SJ01(Q) Nuclear Sampling ISI-M-22SJ04(Q) Nuclear Sampling we T

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1 Callaway Plant 2nd Interval Inservice Inspection Plan 2,3 Pinine Isometric Drawines Table 2.3 provides a listing of the Piping Isometric Drawings for systems subject to inservice inspection. These drawings identify pipe welds, flange and valve bolted connections, pump and valve internal surfaces, integral attachments, and pipe supports that are within the non-exempt piping boundaries. 'In addition, system identification, location, room numbers, pipe classification, pipe size, and configuration are identified.

Piping and components that are exempt from nondestructive and visual examination in j accordance with ASME Section XI, Paragraphs IWB-1220, IWC-1220, and IWD-1220 are not normally depicted on these drawings. If exempt piping or components are shown,  !

it is for information only.

J TABLE 2.3 l PIPING ISOMETRIC DRAWINGS ,

Drawing Number Title REFERENCE DRAWINGS ISI-Ref., Sht.1 Inservice Inspection Drawing Cross Reference ISI-Ref., Sht. 2 Inservice Inspection Drawing Nomenclature ISI-Ref., Sht. 3 Inservice Inspection Drawing Symbols MAIN STEAM AB-01-01, Sht. I Loop 1 AB-02-01, Sht.1 Loop 2 l AB-03-01. Sht.1 Loop 3 )

AB-04-01, Sht. I Loop 4 i MAIN FEEDWATER l AE-01-04. Sht.1 Loop 1 l AE-02-04. Sht. I Loop 2 l AE-03-05, Sht.1 - Loop 3 _ j AE-04-05, Sht.1 Loop 4 l AUXILIARY FEEDWATER l AL-01-02. Sht.1 Motor Driven Auxiliary Feedwater Pump "A" Discharge Piping AL-02-03. Sht. I Motor Driven Auxiliary Feedwater Pump "B" Discharge Piping AL-03-04, Sht.1 Turbine Driven Auxiliarv Feedwater Pump Discharge Piping  !

REACTOR COOLANT BB-00-01, Sht.1 Primary Loop-General Layout BB-01-01. Sht. I Loop 1 B B-01-02. Sht.1 Pressurizer Relief Header BB-01-04. Sht. I Pressurizer Spray Line BB-01-04, Sht. 2 Pressurizer Spray Line BB-01-08. Sht. I Pump "A" Seal Water injection Line BB-02-01. Sht. I Loop 2 BB-02-02. Sht.1 Pressurizer Safety Valve Lines BB-02-11. Sht.1 Pump "B" Seal Water Injection Line BB-03-01. Sht.1 Loop 3 BB-03-09, Sht. I Pump "C" Seal Water injection Line 2-7 i

Callaway Plant 2nd Interval insen' ice inspection Plan TABLE 2.3 PIPING ISOMETRIC DRAWINGS (cont.)

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Drawing Number Title l REACTOR COOLANT (cont.) _ l BB-04-01, Sht. I Loop 4 l BB-04-07, Sht.1 Pump "D Seal Water injection Lino BB-05-01, Sht.1 Pressurizer Surge Line BB-06-01, Sht. I Loop Drain to Reactor Coolant Drain Tank CHEMICAL AND VOLUME CONTROL BO-01-01, Sht. I Normal Charging Line Containment Penetration BG-01-21, Sht. I Normal & Alternate Charging Lines BG-02-22, Sht.1 Letdown Line BG-02-22, Sht. 2 Letdown Line Containment Penetration BG-03-23, Sht.1 Excess Letdown Line _

BG-04-09, Sht. I RCP Seal Water injection Containment Penetratica BG-05-24, Sht.1 Auxiliary Spray Line BG-06-02. Sht.1 CCP Suction BG-06-02. Sht. 2 CCP Discharge (HPSI Discharge)

BG-06-10 Sht.1 CCP Discharge to Seal Water Injection Filters STEAM GENERATOR BLOWDOWN BM-01-01, Sht. I Loops "A" & "D" BM-01-02, Sht. I Loops "B" & "C" ESSENTIAL SERVICE WATER EF-01-01. Sht. I "A" Train Supply EF-01-01, Sht. 2 "A" Train Supply EF-01-02. Sht. I "A" Train Supply EF-01-02, Sht. 2 "A" Train Supply EF-01-03. Sht. I "A" Train Return EF-01-03. Sht. 2 "A" Train Return EF-01-07. Sht. I 'A" Train Return ,

EF-01-08. Sht. I "A" Train Supply l

EF-01-11. Sht. I "A" and "B" Train Return EF-02-01, Sht. I "B" Train Supply i EF-02-01. Sht. 2 "B" Train Supply EF-02-01. Sht. 3 "B" Train Return i EF-02-04 Sht. I "B" Train Supply EF-02-05. Sht. I "B" Train Return EF-02-05. Sht. 2 "B" Train Return EF-02-06. Sht. I "B" Train Supply EF-02-08. Sht. I "B" Train Supply EF-02-08. Sht. 2 "B" Train Return COMPONENT COOLING WATER EG-01-01. Sht. I "A" Train CCW licat Exchanger EG-01-02. Sht. I "A" Train Supply EG-01-02. Sht. 2 " A" Train Return EG-02-03. Sht. I "B" Train CCW Heat Exchanger __

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TABLE 2.3 PIPING ISOMETRIC DRAWINGS (cont.)

Drawing Number Title 3 COMPONENT COOLING WATER (Cont.)  !'

EG-02-03 Sht. 2 "B" Train EG-02-05, Sht. I "B" Train Retum  ;

EG-02-05, Sht. 2 "B" Train Supply

• EG-03-06, Sht.1 Common Header EG-03-07, Sht.1 Common Header ,

EG-04-01, Sht.1 RHR Heat Exchanger Supply i EG-04-01, Sht. 2 RHR Heat Exchanger Return i EG-05-06, Sht. I Letdown Heat Exchanger Supply EG-05-06, Sht. 2 Letdown Heat Exchanger Retum EG-06-09, Sbt.1 RCP "B" & "C" Supply  !

EG-06-09, Sht_ 2 RCP Return RESIDUAL HEAT REMOVAL EJ-01-01, Sht. I "A" Train RHR Pump Suction i EJ-01-01, Sht. 2 "A" Train RHR Pump Discharge EJ-01-01, Sht. 3 "A" Train RHR Pump Discharge EJ-01-01, Sht. 4 "A" Train Pump Discharge to Safety injection l EJ-01-01, Sht. 5 Return to Refueling Water Storage Tank l' EJ-01-04, Sht. I "A" Train RHR Pump Suction EJ-02-02, Sht. I "B" Train RHR Pump Suction l EJ-02-02, Sht. 2 "B" Train RHR Pump Discharge j EJ-02-02, Sht. 3 "B" Train RHR Pump Discharge EJ-02-02, Sht. 4 "B" Train RHR Pump Discharge to Safety Injection ,

EJ-02-02, Sht. 5 "B" Train RHR Pump Discharge to Safety Injection .

EJ-02-04, Sht. I "B" Train RHR Pump Suction l EJ-02-04, Sht. 2 "B" Train RHR Discharge to Accumulator Injection l EJ-02-04, Sht. 3 "B" Train RHR Pump Discharge to Safety Injection Loops 2 & 3  ;

HIGH PRESSURE COOLANT INJECTION l EM-01-01. Sht.1 Safety injection Pump "A" Suction -l; EM-02-01, Sht. 2 Safety injection Pump "B" Suction EM-03-05, Sht.1 Safety Injection Pumps to RHR EM-04-03, Sht.1 Safety injection Pumps to RCS - i EM-05-01. Sht.1 Safety Injection Pump Suction Cross Tie -i EM-05-01, Sht. 2 Safety injection Pump Suction Cross Tie to CVCS EM-0. 02 Sht. I HPSI Discharge to RCS

- EM-06-02, Sht. 2 HPSI Discharge to RCS EM-06-03, Sht.1 HPSI Discharge to RCS CONTAINMENT SPRAY EN-01-01, Sht. I "A" Train Pump Suction EN-01-01, Sht. 2 "A" Train Pump Discharge EN-02-02, Sht. I "B" Train Pump Suction EN-02-02, Sht. 2 "B" Train Pump Discharge 2-9

t Callaway Plant 2nd Interval Inservice Inspection Plan TABLE 2.3 ,

PIPING ISOMETRIC DRAWINGS (cont.) .

Drawinz Number Title l ACCUMULATOR SAFETY INJECTION EP-01-01, Sht.1 Loop 1  ;

EP-02-02, Sht.1 Loop 2 EP-03-02, Sht.1 Loop 3 .

EP-04-01, Sht. I Loop 4 AUXILIARY TURBINE FC-01-01, Sht.1 Aux. Feedwater Pump Turbine Steam Supply Piping CONTAINMENT COOLING GN-01-01, Sht. I "A" Train Supply i GN-01-01, Sht. 2 "A" Train Return GN-01-01, Sht. 3 "A" Train Cooler "A" Supply and Return Headers l GN-01-01, Sht. 4 "A" Train Coolci "C" Supply and Return Headers GN-01-02, Sht. I "A" Train Supply .;

GN-01-03, Sht. I "A" Train Return  !

GN-02-02, Sht. I "B" Train Supply  ;

GN-02-02 Sht. 2 "B" Train Return ,

GN-02-02, Sht. 3 "B" Train Cooler "B" Supply and Return Headers GN-02-02, Sht. 4 "B" Train Cooler "D" Supply and Retum Headers I GN-02-04, Sht. I "B" Train Supply l GN-02-05. Sht. I "B" Train Retum i STANDBY DIESEL GENERATOR  ;

KJ-01-01, Sht.1 Diesel Generator "A" Cooling Water Piping i KJ-02-04, Sht. I Diesel Generator "B" Cooling Water Piping -l

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i Callaway Plant 2nd interval Inservice Inspection Plan  :

2.4 . Eauipment Detail Drawinns ,

Table 2.4 provides a listing of Equipment Detail Drawings for equipment welds or  ;

components subject to inservice inspection. These drawings display unique  !

identification numbers for equipment welds, integral attachments, or. bolted  !

connections that require examination. In addition, weld joint detads, component  !

configuration details, weld locations, etc., are depicted.

?

TABLE 2.4 .

EQUIPMENT DETAIL DRAWINGS  ;

Drawing Number Title  ;

ISI-EBB 01 A. Sht.1 Steam Generator "A" EBB 01 A ISI Equipment Welds ISI-EBB 01 A. Sht. 2 Steam Generator "A" EBB 01 A ISI Equipment Welds i ISI-EBB 01B Sht. I Steam Generator "B" EBB 01B ISI Equipment Welds I ISI-EBB 01B, Sht. 2 Steam Generator "B" EBB 01 B ISI Equipment Welds . j ISI EBB 0lC. Sht. I Steam Generator "C" EBB 01C ISI Equipment Welds ISI-EBB 01C. Sht. 2 Steam Generator "C" EBB 01C ISI Equipment Welds  ;

ISI-EBB 01D. Sht. I Steam Generator "D" EBB 01D ISI Equipment Welds ISI-EB B01 D. Sht. 2 Steam Generator "D" EBB 01D ISI Equipment Welds' j r

ISI-EEJ01 A. Sht.1 RHR Heat Exchanger "A" EEJ01 A ISI Equipment Welds .

ISI-EEJ01B. Sht. I RHR Heat Exchanger "B" EEJ01B ISI Equipment Welds ISI-RBB01. Sht.1 Reactor Vessel RBB01 ISI Equipment Welds  !

ISI-RBB01. Sht. 2 Reactor Vessel RBB01 ISI Equipment Welds l ISI-RBB01. Sht. 3 Reactor Vessel RBB01 ISI Equipment Welds l ISI-RBB01. Sht. 4 Reactor Vessel RBB01 ISI Equipment Welds ISI-TBB03. Sht.1 Pressurizer Vessel TBB03 ISI Equipment Welds j Pressurizer Vessel TBB03 ISI Equipment Welds  ;

ISI-TBB03. Sht. 2 ISI-TBB03. Sht. 3 Pressurizer Vessel TBB03 ISI Equipment Welds ISI-PUMPS. Sht. I Miscellaneous Pumps ISI Equipment Welds l

l 1

i

[

i 2 - 11 L i

Callaway Plant 2nd Interval Insersice Inspection Plan 2.5 Component /Eauipment Sunnort Drawings Table 2.5 provides a listing of the Component / Equipment Support Drawings for component or equipment supports subject to inservice inspection. These drawings display the configuration of the supports and provide a unique location number for each support assembly that requires visual examination.

TABLE 2.5 COMPONENT / EQUIPMENT SUPPORT DRAWINGS Drawing Number Component Description OP-1459F01 Reactor Vessel (RBB01) Supports OP-1459F02 Steam Generator "A", "B", "C" & "D" (E8801 A, B, C & D)

OP-1459F04 Suppons OP-1459F08 OP-1459F09 OP-1459F07 Reactor Coolant Pump "A", "B", "C", & "D"(PBB01 A, B, C & D)

Supports OP-1459F10 Pressurizer (TBB03) Supports 5736 RHR Heat Exchanger "A" & "B" (EEJ01 A & B) Supports C-2S 1904 RHR Pump "A" & "B"(PEJ01 A & B) Supports C-2S1908 C-2S 1904 Containment Spray Pump "A" & "B"(PEN 01 A & B) Supports M-721-040 Centrifugal Charging Pump "A" & "B"(PBG05 A & B) Supports OP-300-J49728 Safety Injection Pump "A" & "B"(PEM01 A & B) Supports OP-D-75-569 Chemical & Volume Control Letdown Heat Exchanger (EBG01)

Supports M-072-0001 Component Cooling Water Heat Exchanger "A" & "B"(EEGO1 A &

B) Supports M-082-012-10 Component Cooling Water Pump "A", "B", "C", & "D" (PEG 01 A, B. C & D) Supports M-089-U0012 Essential Service Water Pumr 'A" & "B"(PEF 01 A & B) Supoorts M-154-U0018 Essential Senice Water Self Cleaning Strainer "A" & "B"(FEF02A

& B) Suppons M-07-00001 -08 Fuel Pool Cooling Heat Exchanger "A" & "B"(EEC01 A & B)

Supports B-49HMTA86X 16 Motor Driven Auxilian Feed Water Pump "A" & "B"(PALOI A &

B) Supports M-021-005 Turbine Driven Auxiliary Feed Water Pump (PALO2) Supports 11908662 Diesel Generator Jacket Water Heat Exchanger "A" & "B" (EKJ04 A & B) Supports M-018-00091 Diesel Generator Intercooler Heat Exchanger "A" & "B" (EKJ03 A

& B) Supports M-018-00724 Diesel Generator Lube Oil Heat Exchanger "A" & "B"(EKJ06A &

B) Supports  !

l 2 - 12

N >

f Callaway Plant 2nd Interval  ;

Inservice Inspection Plan SECTION 3.0  ;

INSERVICE INSPECTION

SUMMARY

TABIIS 1

This section provides a summary listing of all items subject to insetvice inspection. Section 3.1 addresses the inservice inspections required by ASME Section XI while Section 3.2 covers augmented inspections. ,

3.1 ASME Section XI Inservice inspections The ASME Section XI Inservice Inspection Summary Table 3,1 provides the following information; ,

3.1.1 Examination Category f This column lists the examination category as identified in ASME Section XI,'

Tables IWB-2500-1, IWC-2500-1, IWD-2500-1, and Code Case N-491 -2500-1.- -

Only those examination categories applicable to the Callaway Plant are identified.

3.1.2 Item Number and Description of Components Examined ,

These columns list the item number and description as defined in ASME Section XI, Tables IWB-25a0-1, IWC-2500-1, IWD-2500-1, and Code Case N-491 -2500-1. Only those item numbers applicable to the Callaway Plant are identified.

3.1.3 Number of Components This column lists the population of components potentially subject to examination. l The number of components actually examined during the inspection interval will be  !

based upon the Code requirements for the subject item number (e.g.,25% of ' i Examination Category B-J, item Number B9.11 components will be examined i during the inspection interval).

l 3.1.4 Examination Method The column lists the examination method ls) requited by'ASME Section XI, Tables ,

IWB-2500-1. IWC-2500-1, IWD-2500-1, end Code Case N-491 -2500-1, l I

3.1.5 Relief Request Number  :

i This column provides a listing of applicable relief requests. If a relief request ,

number is identified, see the corresponding relief request in Section 4 4.  :

3-1

Callaway Plant 2;;d Interval inservice Inspection Plan TABLE 3.1 ASME SECTION XI INSERVICE INSPECTION

SUMMARY

TABLE Relief Examination item Description of Components Examined Number of - Examination Request Category Number Components Method Number B-A B l .1 i Circumferential Shell Welds 2 Volumetric

Pressure Bl.12 Longitudinal Shell Welds 9 Volumetric Retaining B 1.21 Circumferential Ilead Welds 3 Volumetric Welds in Bl.22 Meridional IIcad Welds 8 Vo!umetric Reactor Bl.30 Shell-to-Flange Weld 1 Volumetric Vessel B 1.40 Ilead-to-Flange Weld 1 Volumetric &

Surface B-B B2.11 Pressurizer Circumferential Shell-to-llead Welds 2 Volumetric Pressure B2.12 Pressurizer Longitudinal Shell-to-IIead Welds 2 Volumetric Retaining B2.40 Steam Generator Tube Sheet-to-IIcad Weld 4 Volumetric Welds in Vessels Other Than Reactor Vessels B-D B3.90 Reactor Vessel Nozzle-to-Vessel Welds 8 Volumetric ISI-05 Full B3.100 Reactor Vessel Nozzle inside Radius Section 8 Volumetric ISI-05 Penetration B3.110 Pressurizer Nozzle-to-Vessel Welds 6 Volumetric Welds of B3.120 Pressurizer Nozzle Inside Radius Section 6 Volumetric-Nozzles in B3.140 Steam Generator (Primary Side) Inside Radius Section 8 Volumetric Vessels 3-2

Czilaway Plant 2nd Interval Inservice Inspection Plan .

TABLE 3.1 ASME SECTION XI INSERVICE INSPECTION

SUMMARY

TABLE (cont.)

Relief Examination item Description of Components Examined Number of Examination Request Category Number Components Method Number B-E B411 P rtial Penetration Vessel Nozzle Welds i Visual, VT-2 Pressure Retaining B4.12 Partial Penetration Control Rod Drive Nozzle Welds 78 Visual, VT-2 Partial Penetration B4.13 Partial Penetration Instrumentation Nozzle Welds 58 Visual, VT-2 Welds in Vessels B4.20 Partial Penetration Pressurizer lleater Penetration 78 Visual, VT-2 Welds B-F B5.10 Reactor Vessel Dissimilar Metal Nozzle-to-Safe End 8 Volumetric & - 1S1-05 Pressure Butt Welds NPS 4 or Larger Surface Retaining  ;

Dissimilar B5.40 Pressurizer Dissimilar Metal Nozzle-to-Safe End Butt 6 Volumatric &

Metal Welds Welds NPS 4 or Larger Surface B-G-1 B6. l e- Reactor Vessel Closure Head Nuts 54 Visual, VT-1 Pressure B6.20 Reactor Vessel Closure Studs,in Place 54 Volumetric Retaining B6.30 Reactor Vessel Closure Studs, when Removed 54 Volumetric &

Bolting Greater Surface Than 2 in. in B6.40 Threads in Reactor Vessel Flange 54 Volumetric Diameter B6.50 Reactor Vessel Closure Washers,-Bushings 54 Visual, VT-1 B6.180 Bolts & Studs in Pumps 4 Volumetric B6.190 Flange Surface, When Connection Disassembled, in 4 Visual, VT-1 Pumps -

B6.200 Nuts, Bushings, & Washers in Pumps 4 Visual, VT-1 3 -_-_ _ ___- _ - __-- . . . . - . . _ . . . . . . - . .- . . - . . - - - - . _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _

.1 Callaway Plant 2nd Interval Inservice inspection Plan TABLE 3.1 ASME SECTION XI INSERVICE INSPECTION

SUMMARY

TABLE (cont.)

Relief Examination item Description of Components Examined Number of Examination Request Category Number Components Method Number B-G-2 B7.20 Bolts. Studs, & Nuts in the Pressurizer i Visual, VT-1 -

Pressure B7.30 Bolts, Studs, & Nuts in Steam Generators 8 Visual, VT-1 Retaining B7.50 Bolts, Studs, & Nuts in Piping 11 Visual, VT-1 Bolting, 2 in. B7.70 Bolts, Studs, & Nuts in Valves 25 Visual, VT-1 +

& Less in Diameter B-J B9.11 Circumferential Welds in Piping 315 Volumetric &

Pressure NPS 4 or Larger Surface Retaining B9.12 Longitudinal Welds in Piping N/A Volumetric & ISI-04 Welds in NPS 4 or Larger Surface  ;

Piping B9.21 Circumferential Welds in Piping 309 Surface Less than NPS 4 B9.31 Branch Pipe Connection Welds 13 Volumetric &

NPS 4 or Larger Surface B9.32 Branch Pipe Connection Welds 37 Surface Less than NPS 4 B9.40 Socket Welds iI Surface i B-K' B 10.10' Integrally Welded Attachments to Vessels 5 Surface 1S1-06 Integral Attachments l for Class i Vessels, Piping, Pumps

& Valves l 3-4

,, ,,r..~..- - . - - . < .,. .-..n... -. , e-,,.. , -- - , < . w -r. , . - - - - . . -

Callaway Plant 2nd Interval Inservice Inspection Plan TABLE 3.1 ASME SECTION XI INSERVICE INSPECTION

SUMMARY

TABLE (cont.)  :

Relief Examination item Description of Components Examined Number of Examination Request Category Number Components Method Number B-L-2 B 12.20 Pump Casings 4 Visual, VT-3 i Pump Casings B-M-2 B 12.50 Valve Bodies, Exceeding NPS 4 25 Visual, VT-3 ,

4 Valve Bodies B-N-1 B1310 Vessel Interior i Visual, VT-3 Interior of Reactor Vessel B-N-2 B 13.60 Interior Attachments beyond Beltline Region in 6 Visual, VT-3 Integrally Reactor Vessel Welded Core Support Structures &

Interior Attachments to Reactor Vessels B-N-3 B 13.70 Core Support Structure in Reactor Vessel i Visual, VT-3 Removable Core Support Structures ,

3-5

_ ._ __ _ -_ _ ._ __ . . _ . .. _ _~ . _ _ , . - - - - . . ._.

Callaway Plant 2nd Interval .

Inservice Inspection Plan TABLE 3.1 ASME SECTION XI INSERVICE INSPECTION

SUMMARY

TABLE (cont.)

- Relief Examination - Item Description of Components Examined Number of Examination Request Categorv ~ Number Components Method Number B-O B14.10 Welds in CRD llousing 32 Volumetric or Pressure Surface Retaining Welds in Control Rod llousings B-P B 15.10 RPV - System Leakage Test i Visual, VT-2 ISI-07 AllPressure B 15.11 RPV - System liydrostatic Test i Visual, VT-2 ISI-07 Retaining B15.20 Pressurizer - System Leakane Test i Visual, VT-2 ISI-07 Components B 15.21 Pressurizer - System liydrostatic Test i Visual, VT-2 ISI-07 (Class 1) B 15.30 Steam Generator - System Leakage Test 4 Visual, VT-2 ISI-07 B 15.31 Steam Generator - System flydrostatic Test 4 Visual, VT-2 ISI-07 B 15.50 Piping - System Leakage Test See Note 6 Visual, VT-2 1S1-07 B 15.51 Piping - System flydrostatic Test See Note 6 Visual, VT-2 ISI-07 B 15.60 Pumps - System Leakage Test 4 Visual, VT-2 ISI-07 B 15.61 Pumps - System flydrostatic Test 4 Visual, VT-2 ISI-07 B 15.70 Valves - System Leakage Test See Note 6 Visual, VT-2 1S1-07 B 15.71 Valves - System Ilydrostatic Test See Note 6 Visual, VT-2 ISI-07 2

B-Q B 16.20 Steam Generator Tubing in U-Tube Design 4 Volumetric Steam Generator Tubing 3-6

Callaway Plant 2nd Interval Inservice Inspection Plan TABLE 3.1 ASME SECTION XI INSERVICE INSPECTION

SUMMARY

TABLE (cont.)

l Relief Examination item Description of Components Examined Number of. Examination Request Category Number Components Method Number C-A Cl .10 Shell Circumferential Welds 16 Volumetric Pressure C120 llead Circumferential Welds 4 Volumetric Retaining C130 Tubesheet-to-Shell Welds 4 Volumetric Welds in Pressure Vessels C-B C2 21 Nozzle-to-Shell (or liead) Weld without Reinforcing 8 Volumetric &

Pressure Plate in Vessels > 1/2" Nominal Thickness Surface Retaining C2.22 Nozzle Inside Radius Secticn 8 Volumetric Nozzle Welds C2.33 Nozzle-to-Shell (or llead) Welds when Inside of 4 Visual, VT-2 in Vessels Vessel is inaccessible, for Vessels > l/2" Nominal Thickness with Reinforcing Plates C-C'~ C3 10' Integrally Welded Attachments to Pressure Vessels 2 Surface ISI-06 Integral C3.20' Integrally Welded Attachments to Piping 107 Surface ISI-06 Attachments C3.30' Integrally Welded Attachments to Pumps 20 Sudete ISI-06 for Class 2 Vessels, Piping, Pumps and Valves -

3-7

Callaway Plant 2nd Interval Inservice Inspection Plan TABLE 3.1 ASME SECTION XI INSERVICE INSPECTION

SUMMARY

TABLE (cont.)

Relief Examination item Description of Components Examined Number of Examination Requests Cate; tory Number Components Method . Number C-D C4.40 Bolts and Studs in Valves 4 Volumetric Pressure Retaining

• Bolting Greater Than 2 in. in Diameter C-F-1 C5. I 1 Circumferential Welds in Austenitic Stainless Steel or 717 Volumetric &

Pressure Iligh Alloy Piping 2 3/8" Nominal Wall Thickness for Surface Retaining Piping > NPS 4 Welds in C5.12 Longitudinal Welds in Austenitic Stainless Steel or N/A Volumetric & ISI-04 Austenitic Ifigh Allow Piping 2 3/8" Nominal Wall Thickness for Surface Stainless Steel Piping > NPS 4 orliigh Alloy C5.21 Circumferential Welds in Austenitic Stainless Steel or 177 Volumetric &

Piping liigh Alloy Piping 21/5" in. Nominal Wall Thickness Surface for Piping 2 NPS 2 and 5 NPS 4 C5 30 Socket Welds 20 Surface C54i Circumferential Welds in Pipe Branch Connections of 14 Surface Branch Piping 2 NPS 2 1 3-8 i

L__--____.._-____-____-_______-_ _ _ _ . - . _ _ _ _ _ _ . . _- . . . _ . _ . _. - -_. ___ - __________ - _ ___- --___-

Callaway Plant 2nd Interval Inservice Inspection Plan TABLE 3.1 ASME SECTION XI INSERVICE INSPECTION

SUMMARY

TABLE (cont.)

Relief Examination Item Description of Components Examined Number of Examination Request Category Number Components Method Number C-F-2 C5.51 Circumferential Welds in Carbon or Low Alloy Steel 303 Volumetric &

Pressure Piping 2 3/8" Nominal Wall Thickness for Piping Surface Retaining > NPS 4 Welds in C5 52 Longitudinal Welds in Carbon or Low Alloy Steel N/A Volumetric & ISI-04 Carbon or Low Piping 2 3/8" Nominal Wall Thickness for Piping Surface Alloy Steel > NPS 4 Piping C5.81 Circumferential Welds in Carbon or Low Alloy Steel 2 Surface Pipe Branch Connections of Branch Piping > NPS 2 C-G C6.10 Pump Casing Welds 10 Surface Pressure Retaining Welds in Pumps and Valves C-II C7.10 Pressure Vessels - System Pressure Test See Note 6 Visual, VT-2 ISI-07 All Pressure C7.20 Pressure Vessels - System 11ydrostatic Test' See Note 6 Visual, VT-2 ISI-07 Retaining C7.30 Piping - System Pressure Test See Note 6 Visual, VT-2 ' ISI-07, 09 Components C7.40 Piping - System Ilydrostatic Test' See Note 6 Visual, VT-2 ISI-07, 09 (Class 2) C7.50 Pumps - System Pressure Test See Note 6 Visual, VT-2 ISI-07 C7.60 Pumps - System f lydrostatic Test' See Note 6 Visual, VT-2 ISI-07 C7.70 Valves - System Pressure Test See Note 6 Visual, VT-2 ISI-07 C7.80 Valves - System Ilydrostatic Test' See Note 6 Visual, VT-2 ISI-07 l

l l 3-9 L__________._-________________________ _ . . _ _ _ . _ . .

Callaway Plant 2nd Interval Inservice Inspection Plan TABLE 3.1 ASME SECTION XI INSERVICE INSPECTION

SUMMARY

TABLE (cont.)

Relief Examination item Description of Components Examined Number of Examination Request Category Number Components Method Number D-A' Dl.10' Integrally Welded Attachments to Pressure Vessels 42 Visual, VT-1 ISI-06 integral DI.20' Integrally Welded Attachments to Piping 165 Visual, VT-1 ISI-06 Attachments D I .30' Integrally Welded Attachments to Putnps 4 Visual, VT-1 ISI-06 for Class 3 Vessels, Piping, Pumps

& Valves D-A Dl.10 Class 3 Pressure Retaining Components Systems in Support of - System Pressure Test See Note 6 Visual, VT-2 Reactor Shutdown - System Ilydrostatic Test See Note 6 Visual, VT-2 Function DB D2.10 Class 3 Pressure Retaining Components Systems in Support of - System Pressure Test See Note 6 Visual, VT-2 Emergency Ccie Cooling. - System Ilydrostatic Test See Note 6 Visual, VT-2 Containment Ileat Removal, Atmosphere Cleanup, and Reactor Residual lleat Removal 3 - 10

___- _ . _ ____-__ - -____-_ _ - __ _ .- ~ . . - .

i Callaway Plant 2nd Interval Inservice Inspection Plan TABLE 3.1 ASME SECTION XI INSERVICE INSPECTION

SUMMARY

TABLE (cont.)

l Relief Examination item Description of Components Examined Number of Examination Request Category - Number Components Method Number D-C D3.10 Class 3 Pressure Retaining Components Systems in Support of - System Pressure Test See Note 6 Visual, VT-2 Residual lieat Removal from - System Ilydrostatic Test See Note 6 Visual, VT-2 ,

Spent Fuel lorage Pool F-A id F l .10' Class 1 Piping Supports 297 Visual, VT-3 Suppons F l .20' Class 2 Piping Supports 367 Visual, VT-3 F130' Class 3 Piping Supports 657 Visual, VT 3 FI40' Supports Other Than Piping Supports 160 Visual, VT-3 ISI-03 (Class 1,2, and 3) 3 - 11

Callaway Plant 2nd Interval Inservice Inspection Plan Notes:

1. Reference Callaway Relief Request ISI-06 for a description of the Examination Categories and Item Numbers used for the insenice inspection ofintegrally welded attachments.

2. The extent, frequency and acceptance standards for the examination of Steam Generator tubing will be in accordance with Callaway Technical Specification 3/4.4.5.

3. Reference Code Case N-491 for a description of the Examination Category and item Numbers used for the inservice inspection of supports.

4. Snubber assemblies will be tested and inspected in accordance with Callaway Technical Specification 3/4.7.8. Integral and non-integral attachments for snubbers, including lugs, bolting, pins, and clamps, shall be examined in accordance with the requirements of Code Case N-491.

5. The system hydrostatic pressure test will be performed to the alternate mies for 10-year hydrostatic pressure testing delineated in Code Case N-498.

6. Pressure retaining components (e.g., pressure vessels, pumps, valves, piping, etc.) that are subject to a system pressure or hydrostatic test are identified on Inservice inspection Boundary Drawings.

Peference Section 2.2 of this Plan for details pertaining to these drawings.

l l

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'3 - 12

Callaway Plant 2nd Interval inservice Inspection Plan 3.2 Auemented inservice inspections The Augmented Inservice Inspection Summary Table 3.2 provides the following information:

3.2.1 Implementing Document This column lists the basis document for the augmented insenice examination.

3.2.2 Description of Components Examined This column provides a description of the components subject to augmented inservice inspection.

3.2.3 Number of Components This column lists the population of components potentially subject to augmented examination. The number of components actually examined during the inspection interval will be in accordance with the requirements of the implementing document.

3.2.4 Examination Method This column lists the examination method required by the implementing document.

3.2.5 Relief Request Number This column provides a listing of applicable relief requests. If a relief request number is identified, see the corresponding relief request in Section 4.4.

3-13

Callaway Plant 2nd Interval Inservice Inspection Plan TABLE 3.2 AUGM ENTED INSERVICE INSPECTION

SUMMARY

TABLE implementing Description of Components Examined Number of Examination ~ Relief Document Components Method Request Number NRC Standard Circumferential, Longitudinal and Branch 376 Volumetric Review Plan Welds in Piping 2" NPS and Greater Sections 3.6.1 and 6.6 Circumferential Welds in Piping i 1/2" 16 Surface 1S1-02 NPS Socket Welds in Piping i 1/2" NPS and 105 Surface Greater Regulatory RCP Flywheelin Areas ofliigher Stress 4 Volumetric Guide 1.14 Concentration at the Bore and Keyway ,

RCP Fivwheel at Exposed Surfaces 4 ' Surface RCP Flywheel Entire Volume 4 Volumetric Regulatory Reactor Vessel Closure Studs, 54 Surface Guide 1.65 When Removed Regulatory Fuel System for Standby Diesel 2 Visua!, VT-2 Guide 1.137 Generators Regulatory Reactor Vessel Welds 32 Volumetric .

Guide 1.150 3-14

_ _ _ - - - _ = _ _ _ _ _ _ . -- - . . - - - - . - . . . . - .-- . . . - . - . .- - - - . . . , - . - . - . . - -

Callaway Plant 2nd Interval Inservice inspection Plan SECTION 4.0 ALTERNATIVE REOUIREMENTS TO ASME SECTION XI,1989 EDITION This section lists the alternative requirements to ASME Section XI,1989 Edition, being adopted for the Second Interval Inservice Inspection Program at the Callaway Plant. The alternative requirements presented are in accordance with ASME Section XI and 10 CFR 50.55a, as applicable.

4.1 Adoption of Code Cases This Section addresses the adoption of Code Cases during the Second Inservice Inspection Interval at the Callaway Plant. Code Cases adopted for Inservice Inspection use during the Second Interval will be listed in Table 4.1 of this Inservice inspection Plan. Code Cases for Repair / Replacement activities are not addressed in this Inservice Inspection Plan. In all cases, the use and adoption of Code Cases will be in accordance with ASME Section XI, IWA-2440 and 10 CFR 50.55a. The methodology for adopting Code Cases is divided into the four categories clarified below.

4.1.1 Adoption of Code Cases Listed for Generic Use in Regulatory Guide 1.147 Code Cases that are listed for generic use in Regulatory Guide 1.147, Revision 10, and later, will be adopted for use during the Second Inservice Inspection Interval by listing them in Table 4.1 of this Inservice Inspection Plan. All conditions or limitations delineated in Regulatory Guide 1.147 for a particular Code Case will apply.

4.1.2 Adoption of Code Cases Nc. Listed for Generic Use in Regulatory Guide 1.147 Adoption of Code Cases that have been approved by the Board of Nuclear Codes and Standards, but that have not been listed for generic use in Regulatory Guide 1.147, may be submitted in the foim of a Relief Request in accordance with 10 CFR 50.55a(a)(3). Alternatively, Code Cases may be adopted for use by special permission from the NRC as specified in Callaway FSAR, Appendix 3 A.

4.1.3 Adoption of Code Cases Listed for Generic Use in Regulatory Guide 1 147 But Subsequently Annulled by ASME Section XI Under cenain circumstances, it may be necessary to adopt a Code Case that has been listed for generic use in Regulatory Guide 1.147, but subsequently annulled by ASME Section XI. Therefore, Union Electric Company endorses all revisions of Regulatory Guide 1.147 from Revision 10 up to and including the most recent revision. Endorsement of these revisions of Regulatory Guide 1.147 does not commit the Callaway Plant to all Code Cases listed therein, but rather allows for selection of a previously accepted Code Case The purpose of this endorsemen: is to identify all Code Cases that could potentially be incorporated into the Inservice Inspection Plan in accordance with IWA-2441 4-1

l t

Callaway Plant 2nd Interval Inservice Inspection Plan - ,

.4.1.4 Adoption of Code Cases Issued Subsequent to Filing this Insenice Inspection Plan Code Cases issued by ASME Section XI subsequent to filing this inservice '  ;

Inspection Plan will be proposed for use in amendments to this Plan in accordance j with ASME Section XI, IWA-2441(d).  !

i 5

Y TABLE 4.1 LIST OF ADOPTED CODE CASES ,

CODE REG. GUIDE CASE TITLE 1.t47 DATE NO. REVISION ADOPTED ..

N-460 Alternative Examination Coverage for 10 8/1/95 t Class I and Class 2 Welds N-461 Alternative Rules for Piping Calibration 10' 8/1/95 j Block Thickness i N-489 Alternative Rules for Level III NDE 10 8/1/95 i Qualification Examinations N-491 Alternative Rules for Examination of Class 10 8/1/95 .

1,2,3 and MC Component Supports of j Light Water Cooled Power Plants  !

N-498 Alternative Rules for 10-Year Hydrostatic 10 8/1/95  !

g Pressure Testing of Class 1 and 2 Systems .

t 4.2 Use of Subsequent Editions of ASME Section XI l In accordance with 10 CFR 50.55a(g)(3)(v), components (including supports) may meet ,

the requirements set forth in subsequent editions of Codes and Addenda, or ponions j thereof, which are incorporated by reference in .0 CFR 50.55a(b), subject to the- l limitations and modifications listed therein. This Section of the Insersice Inspection Plan  !

provides for alternative requirements from approved subsequent Code editions that may [

be adopted during the Second Insenice Inspection Interval. This Inservice Inspection Plan will be amended for adoption of subsequent Code niles-4-2 i

e 4 -

Callaway Plant 2nd Interval  !

Inservice Inspection Plan i

4.3 Inservice Inspection Relief Reauest Index  !

t This section provides a summary listing and revision status of all Relief Requests related to inservice inspections at the Callaway Plant. i i

TABLE 4.3 INSERVICE INSPECTION RELIEF REQUEST INDEX Relief 1 Request Page Rev. Date Topic i ISI-01 4.4-2 0 10/12/94 Exemption from Appendix VII 1 Ultrasonic Examination Personnel Qualification Requirements I

ISI-02 4.4-4 0 10/12/94 Exemption of Circumferential Welds in 1 1/2" NPS Piping from Volumetric ,

Examination Requirements of NRC Standard Review Plan, Section 3.6.1 ISI-03 4.4-6 0 10/12/94 Limited Examination of Reactor Vessel Suppons ,

ISI-04 4.4-9 0 10/12/94 Alternate Examination Requirements for  ?

Longitudinal Welds in Class 1 and 2  ; '

Piping ISI-05 4.4-10 0 10/12/94 Alternate Rules for Deferral of Inspections on Nozzle-to-Vessel Welds, Inside Radius Sections and Nozzle-to-Safe End Welds af the Reactor Vessel i ISI-06 4.4-15 0 10/12/94 Alternate Rules for the Sciection and -

Examination of Class 1,2 and 3  !

Integrally Welded Attachments ISI-07 4.4-21 0 10/12/94 Alternate Rules for Insulation Removal During IWB-5000 and IWC-5000 Pressure Tests at Bolted Connections in Systems Borated for the Purpose of -

Controlling Reactivity i

i 4-3 f

1 I

Callaway Plant 2nd Interval Inservice Inspection Plan TABLE 4.3 -

INSERVICE INSPECTION

- RELIEF REQUEST INDEX (cont.)  ;

Relief Request Page Rev. Date Topic ISI-08 4.4-24 0 10/12/94 Alternate Rulec for Corrective Measures  :

if Leakage Occurs at a Bolted Connection  ;

ISI-09 4.4-26 0 10/12/94 Alternate Provisions for Pressure Testing ,

Code Class 2 Piping and Valves at  :

Containment Penetrations Where the Balance of the System is Outside the Scope of Section XI e

s

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r l

i I

1 4

4-4 y - - -

e , - . - , . ,

Callaway Plant 2nd Interval Inservice Inspection Plan 4.4 Inservice Inspection Relief Reauests 4.4.1 This section contains Relief Requests written in accordance with 10 CFR 50.55a(g)(5) when specific ASME Section XI requirements for inservice inspection are considered impractical. The enclosed Relief Requests are subject to change throughout the inspection interval. If examination requirements are determined to be impractical during the course of the interval, additional or modified relief requests shall be submitted in accordance with 10 CFR 50.55a(g)(5).

4.4.2 Exceptions to Code required examinations may also be authorized by NRR, as allowed by 10 CFR 50.55a (a)(3), provided that design, fabrication, installation, testing and inspection performed in compliance with Codes and Section XI requirements would result in hardship without a compensating increase in the level of quality and safety, or provided that the proposed alternative examination will assure an acceptable level of quality and safety. Specific exceptions may also be documented in the form of Relief Requests and included in this Section, as applicable.

4.4.3 Relief Requests for incomplete examinations shall be submitted in accordance with 10 CFR 50.55a(g)(5)(iv) throughout the interval as limitations are identified. Due to ongoing changes in nondestructive examination procedures, techniques and requirements, the Union Electr;c Company censiders that submitting Relief Requests for incomplete examinations when they are evaluated will provide a more accurate representation of the limitations.

4.4-1

l l

Callaway Plant 2nd Interval Inservice Inspection Plan RELIEF REOUEST NUMBER: ISI-01 (Page 1 of 2)

I COMPONENT IDENTIFICATION l

)

Code Classes: I and 2

References:

IWA-2311(b) and Appendix VII l, Examination Categories: B-A, B-B, B-D, B-F, B-G-1, B-J, C-A, C-B, C-D, C-F-1, C-F-2 Item Numbers: Bl .11, Bl.12, B l.21, B l.22, Bl.30, B l .40, B2.11, B2.12, B2.40, B3.90, B3.100, B3.110, B3.120, B3.140, B5.10, B5.40, B5.70,  !

I B6.20, B6.30, B6.40, B6.180, B9.11, B9.12, B9.3 !

Cl.10, C1.20, Cl.30, C2.21, C2.22, C4.40, C5.11, C5.12, C5.21, C5.51, C5.52

Description:

Exemption from Appendix VII Ultrasonic Examination Personnel Qualification Requirements Component Numbers: All Class 1 and 2 components requiring ultrasonic examination CODE REOUIREMENT {

Paragraph IWA-2311(b) specifies that the training, qualification, and certification of ultrasonic examination personnel shall also comply with the requirements of Appendix VII.

Appendix VII provides requirements for the employer's written practice, qualification of ultrasonic l examiners, qualification records, and the minimum content ofinitial training courses for the ultrasonic  ;

examination method in addition to those required in SNT-TC-1 A. f BASIS FOR RELIEF ,

I Union Electric requests relief from implementation of Appendix VII until the performance i demonstration requirements of Appendix VIII are fully implemented. Implementation of Appendix -  !

VII prior to full implementation of Appendix Vill is considered impractical and without a compensating increase in quality and safety. t i

Appendix VII was first introduced in the 1988 Addenda to Section XI. This Appendix represents a t dramatic change from previous Code editions and current industry practices in the requirements for qualification of ultrasonic examination personnel. New training programs must be developed and ,

taught by trained instmetors, employer's written practices must l'e completely rewritten, examination question banks must be developed, flaw specimens containing actual or simulated flaws must be l acquired, and performance demonstrations (practical examinations) must be completed.  ;

I 4.42 -,

Callaway Plant 2nd Interval Inservice Inspection Plan RELIEF REOUEST NUMBER: ISI.01 ~

(Page 2 of 2)

Implementation of Appendix VII will require a substantialindustry effort. Although work is progressing towards compliance with Appendix VII, full implementation has not yet been achieved. q Since Appendix VII provides for use of specimens prepared for ultrasonic performance demonstrations per Appendix VIII, many NDE vendors are developing these two programs concurrently in order to avoid duplicated effort. Though currently not required, the nuclear industry anticipates that the' Appendix VIII performance demonstration requirements will be mandated by a )

backfit ruling in the Federal Register. In anticipation of this ruling, the Performance Demonstration Initiative (PDI) Committee is currently leading an industry wide effort to implement Appendix Vill.

The tentative completion dates for pipe weld performance demonstrations and reactor vessel ]

i performance demonstrations are January of 1996, and January of 1997, respectively, The Union Electric Company intends to fully implement Appendix VII when the performance '

demonstrations of Appendix VIII are mandated by a backfit mling in the Federal Register.

PROPOSED ALTERNATE PROVISIONS The Callaway Plant shall utilize ultrasonic examination personnel qualified in accordance with the requirements oflWA-2300, except for IWA-2311(b). The additional Appendix VII training, qualification, and certification requirements referenced in IWA-2311(b) shall be fully implemented when the performance demonstrations of Appendix VIII are mandated by a ruling in the Federal Register.

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i Callaway Plant 2nd' Interval Inservice Inspection Plan RELIEF REOUEST NUMBER: ISI 02 (Page 1 of 2)

COMPONENT IDENTIFICATION Code' Class: 2

References:

NRC Standard Review Plan, Section 3.6.1 (NUREG-0800)

Examination Category: N/A

• Item Number: N/A

Description:

Exemption of Circumferential Welds in l_1/2" NPS Piping from the Volumetric Examination Requirements ofNRC Standard Review Plan, Section 3.6.1 Component Numbers: RCP "A" Seal Water Injection Line Welds 2-BG-09-FW387 2" x 1 1/2" Reducer to 1 1/2" Pipe .

2-BG-09-FW386 . I 1/2" Pipe to Valve 2-BG-09-FW3 85 1 1/2" Pipe to Valve 2-BG-09-FW384 2" x 1 1/2" Reducer to 1 1/2" Pipe RCP "B" Seal Water Injection Line Welds 2-BG-09-FW432 2" x 1 1/2" Reducer to 1 1/2" Pipe 2-BG-09-FW431 1 1/2" Pipe to Valve 2-BG-09-FW430 1 1/2" Pipe to Valve 2-BG-09-FW429 2" x 1 1/2" Reducer to 1 1/2" Pipe RCP "C" Seal Water Injection Line Welds 2-BG-09-FW417 2" x 1 1/2" Reducer to 1 1/2" Pipe 2-BG-09-FW416 1 1/2" Pipe to Valve 2-BG-09-FW415 1 1/2" Pipe to Valve 2-BG-09-FW414 2" x i 1/2" Reducer to 1 1/2" Pipe RCP "D" Seal Water injection Line Welds 2-BG-09-FW402 2" x 1 1/2" Reducer to 1 1/2" Pipe '

2-BG-09-FW401 1 1/2" Pipe to Valve 2-BG-09-FW400 1 1/2" Pipe to Valve 2-BG-09-FW399 2" x 1 1/2" Reducer to 1 1/2" Pipe AUGMENTED REOUIREMENT i Standard Review Plan, Section 3.6 I requires that circumferential welds in piping exceeding 1"  !

NPS be subject to volumetric examination.

4.4-4

Callaway Plant 2nd Interval Inservice Inspection Plan RELIEF REOUEST NUMBER: ISI-02 (Page 1 of 2)

BASIS FOR RELIEF The sixteen welds listed above are all within portions of the Reactor Coolant Pump Seal Water Injection Lines which are schedule 160,1 1/2" NPS. A combination of the small pipe diameter and pipe thickness cause the volumetric examinations to yield meaningless results.

PROPOSED ALTERNATE EXAMINATIONS As an alternative to the requirements of NRC Standard Review Plan, Section 3.6.1, liquid penetrant examinations shall be performed on all sixteen of the ~ subject welds. In. addition, a visual VT-2 examination shall be performed on these welds as specified in ASME Section XI.

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4 4.4-5 l

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Callaway Plant 2nd Intervai .

Inservice inspection Plan  !

RELIEF REOUEST NUMBER: ISI-03 {

(Page1of3) l t

i COMPONENT IDENTIFICATION t

Code Class: I  ;

References:

Code Case N-491, Table -2500-1 Examination Category: F-A  ;

Item Number: F1.40 I

Description:

Limited Examination of Reactor Vessel Supports Component Numbers: 2-RBB01-01,2-RBB01-02,2-RBB01-03, and 2-RBB01-04 CODE REOUIREMENT  !

ASME Section XI, Code Case N-491. Table -2500-1 requires that 100% of Class I supports,  ;

other than piping, be subject to a visual VT-3 examination once every inspection interval.

BASIS FOR RELIEF  !

The Callaway Reactor Vesselis supported by two cold leg nozzles and two hot leg nozzles. I There is a support assembly at each of these nozzles that consists of a nozzle weld build up, shoe  :

plate, air cooled box, and steel support structure embedded in the primary shield wall. Figure ISI- l 03 depicts these support assemblies. As shown in the figure, only the nozzle weld build up and  !

shoe plate are completely accessible for a visual VT-3 examination. The majority of the air cooled box and the entire steel support structure are located beneath a steel walk plate and only +

the top of the air cooled box is directly accessible. An additional 20 to 30 percent of the air  :

cooled box and a very small percentage of the steel support structure would be made accessible if i the steel walk plate and insulation were removed. l t

The Reactor Vessel supports are located in a confined space below the refueling pool permanent seal ring. The area can only be accessed through four seal ring hatches. In addition to difDcult access, the radiation in the area is between 1.5 to 2.0 man-rem per hour. It is estimated that the j removal and re-installation of the walk plate and insulation in this confined space, ecmbined with ,

the visual VT-3 examination, would result in an exposure of approximately 36 man-rem.

Removal of the walk plate and insulation under these conditions to increase the examination of the air cooled box by approximately 20 to 30 percent and a very small percentage of the steel support structure is considered impractical without a commensurate increase in quality or safety. Based on this, reliefis requested from the visual VT-3 examination of the air cooled box and steel support stmeture that is obstructed by the walk plate and insulation. l 1

4.4-6  ;

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x. .  ;

Callaway Plant 2nd Interval 3 Inservice Inspection Plan -!

RELIEF REOUEST . ' UMBER: ISI-03 l

- (Page 2 of 3)  !

PROPOSED ALTERNATE EXAMINATION .f A limited visual VT-3 examination, with the walk plate and insulation installed, shall be performed' i on the_ accessible NF portions of the Reactor Vessel support assemblies'to satisfy the requirements i

, . of Code Case N-491, Table -2500-1, Item No. Fl.40. If conditions are discovered during this .

limited VT-3 examination that do not meet the acceptance standards of N-491, -3400, the walk i plate or insulation will, if necessary, be removed to meet the evaluation requirements of N-491, -3112.2 or -3112.3. ,

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j Callaway Plant 2nd interval ;

Inservice inspection Plan RELIEF REOUEST NUM BER: ISI-04 (Page1of2)

COMPONENT IDENTIFICATION Code Classes: I and 2

References:

Table IWB-2500-1, Table IWC-2500-1 Examination Categories: B-J, C-F-1, C-F-2 Item Numbers: B9.12, B9.22, C5.12, C5.22, C5.42, C5.52, C5.62, and C5.82

==

Description:==

Alternate Examination Requirements for Longitudinal Welds in Class '. and 2 Piping Component Numbers: All Class 1 and 2 Longitudinal Piping Welds Subject to Surface or Valumetric Examination CODE REOUIREM ENTS Gass 1 Piping:

Table IWB-2500-1 requires the performance of surface and volumetric examinations on Item No.

B9.12 longitudinal welds, and a surface examination on Item No. B9.22 longitudinal welds. The examination includes at least a pipe diameter length, but not more than 12 in., of each longitudinal weld intersecting the circumferential welds required to be examined by Examination Categories B-F and B-J.

Class 2 Pioing:

Table IWC-2500-1 requires the performance of surface and volumetric examination on Item Nos.

C5.12, C5.22, C5.52 and C5.62, and a surface examination on Item Nos. C5.42 and C5.82. The examination includes a length of 2.5t at the intersecting circumferential welds required to be examined by Examination Categories C-F-1 and C-F-2.

HASIS FOR RELIEF Based on the reasons stated below, the performance of surface and volumetric examination on longitudinal piping welds has a negligible compensating efTect on the quality or safety of Class I and 2 piping. In addition, there is little, if any, technical benefit associated with the performance of these examinations, but they result in a substantial man-rem exposure and cost.

1) Throughout the nuclear industry, there has been no evidence of rejectable service induced flaws being attributed to longitudinal piping welds

2) During the first inservice inspection interval at the Callaway Plant, no inservice flaws have been detected in longitudinal piping welds 4.4-9

Callaway Plant 2nd Interval Inservice Inspection Plan RELIEF REOUEST NUMBER: ISI-04 (Fege 2 of 2)

3) There are distinct differences between the processes used in the manufacturing of longitudinal and circumferential welds which enhance the integrity oflongi:udinal welds.

First, longitudinal welds are typically manufactured under controlled shop conditions whereas circumferential welds are produced in the field under less ideal conditions.

Secondly, longitudinal welds usually undergo heat treatment in the shop which improves their material properties and relieves the residual stresses created by welding. Finally, shop manufacturing inspections can be performed under more favorable conditions which further increase the confidence level of the longitudinal weld quality.

4) During field installation of piping, the ends of the longitudinal welds may be affected during welding of the intersecting circumferential field welds. This small area falls within the circumferential weld inspection boundaries. Therefore, the ends of the longitudinal welds will still be subject to examination.

5) Fiom an industry-wide standpoint, there has been no evidence oflongitudinal weld defects compromising safety at nuclear generating facilities.

6) No significant loading conditions or known material degradation mechanisms have become evident to date which specifically relate to longitudinal seam welds in nuclear plant piping.

7) There is a significant accumulation of man-rem exposure and cost associated with the inspection of Class I and 2 longitudinal piping welds.

8) The alternative examinations proposed below provide an acceptable level of quality and safety without causing undue hardship or difficulties.

PROPOSED ALTERNATE EXAMINATION Surface and volumetric examinations shall be performed, as applicable, on the length of the longitudinal weld that is normally examined during inspectica for the intersecting circumferential weld (s). The volumetric examination at the ir,tersection of circumferential and longitudinal welds will include both transverse and parallel scans within the Ir.ngth of the longitudinal weld that falls ,

within the circumferential weld examination boundary. l l

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4.4-10 l

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l Callaway Plant 2nd Interval  ;

' Inservice Inspection Plan i RELIEF REOUEST NUMBER: ISI-05 (Page1of4)

COMPONENT IDENTIFICATION- ,

i Code Class:- 1

References:

IWB-2500, Table IWB-2500-1 -l Examination Categories: B-D,- B-F l Item Numbers: B3.90, B3.100, B5.10

Description:

Alternate Rules for the Deferral of Inspections on Nozzle-to-Vessel Welds, Inside Radius Sections and Nozzle-to-Safe End  !

Welds of the Reactor Vessel l Component Numbers:- Nozzle-to-Vessel Welds (Item No. B3.90) .!

2-RV-105-121-A  ;

2-RV-105-121-B  !

2-RV-105-121-C t 2-RV-105-121-D  !

2-RV-107-121-A ,

2-RV-107-121-B 2-RV-107-121-C .

2-RV-107- 121-D Inner Radius Sections (Item No. B3.100) 2-RV-105-121-A-IR l 2-RV-105-121-B-IR  !

2-RV- 105- 121 -C-IR l 2-RV-105-121-D-IR  !

2-RV-107-121-A-IR 2-RV-107-121-B-IR ,

2-RV-107-121-C-IR l 2-RV-107-121-D-IR Nozzle-to-Safe End Welds (Item No. B5.10) 2-RV-301 - 121- A ,

2-RV-301-121-B ,

2-RV-30 l- 121-C 2-RV-301-121-D 2-RV-302-121-A  !

2-RV-302- 121-B l 2-RV-302- 121-C 2-RV-302-121 -D i

i 4.4-11

e i Callaway Plant 2nd Interval Inservice Inspection Plan  !

RELIEF REOUEST NUMBER: ISI 05 (Page 2 of 4) -

CODE REOUIREMENT r ASME Section XI,1989 Edition, Table IWB-2500-1, Examination Category B-D requires '

volumetric examination of reactor vessel nozzle-to-vessel welds and their inside radius sections once each ten-year inspection interval. Note (2) of Examination Category B-D states that at least i 25 percent, but not more than 50 percent (credited), of the reactor vessel nozzles shall be examined by the end of the first inspection period, and the remainder by the end of the inspection  ;

interval. [

Table IWB-2500-1, Examination Category B-F, Note (1) states that the reactor vessel nozzle-to- l safe end weld examinations may be performed coincident with the vessel nozzle examinations ,

required by Examination Category B-D.

BASIS FOR REl,IEF j Reliefis requested to defer 100 percent of the reactor vessel nozzle-to-vessel weld examinations, the nozzle inside radius section examinations, and the nozzle-to-safe end weld examinations to the end of Callaway's second ten-year inspection interval.

Union Electric believes that performing 25 percent to 50 percent of the reactor vessel nozzle  ;

examinations in the first period of the second inspection interval is impractical for the following reasons:

i

1) The vendor cost alone (not including site training, plant support, or potential critical path time) to perform these examinations with automated tooling in the first inspection period is currently estimated at $250,000. The cost to perform these ame examinations at the end of the second inspection interval concurrent with the reactor vessel ten year examination is i estimated at only $25,000. The major expense associated with the first inspection period examinations is the added equipment and personnel mobi',ization costs and equipment assembly and disassembly costs. ,

2) Approximately three to four man-rem exposure is currently expended for automated ,

equipment assembly and disassembly in the reactor cavity area. In addition to exposure, there  !

are approximately two to three cubic feet of solid radwaste generated during performance of automated examinations in the reactor vessel. Under current Code rules, this personnel exposure and radwaste generation would be incurred twice; once for the nozzle first inspection period examinations and again for the reactor vessel examinations at the end of the inspection interval. Performing the nozzle examinations concurrent with the reactor vessel ten-year examinations will save approximately three to four man-rem exposure and two to three cubic feet of solid radwaste.

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4.4-12

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Callaway Plant 2nd Interval  !

Inservice Inspection Plan a

RELIEF REOUEST NUMBER: ISI-05 (Page 3 of 4) l l

For reasons listed below, Union Electric believes that deferral of 100 percent of the reactor vessel nozzle examinations to the end of the second inspection interval will provide an acceptable level 4 of safety and quality.

1) All four of Callaway's Reactor Vessel hot leg nozzle-to-vessel welds, hot leg nozzle inside radius sections, and hot leg nozzle-to-safe end welds were examined in 1987 during the first period of the first ten-year inspection interval. No indications or relevant conditions were discovered that required successive inspections in accordance with Paragraph IWB-2420(b).

Funhermore, no insenice repairs or replacements by welding have ever been performed on any of the nozzle-to-vessel welds, nozzle inside radius sections, or nozzle-to-safe end welds at Callaway.

2) From an industry perspective, there are two reasons why deferral of Callaway's nozzle examinations to the end of the second inspection interval will not decrease the level of quality and safety. First, PWR reactor vessels similar to Callaway's have been operating for over 20 years with no recorded inservice induced flaws or potential degradation mechanisms. Since each PWR reactor vessel in operation is representative of the operating conditions throughout the industry, continued inspection of these vessels ensures that any potential degradation mechanism will be detected. Second, given the present large population of PWR reactor vessels in operation, the examination of nozzles within the industry during any ten-year interval is evenly distributed. This distribution is essentially equivalent, regardless of whether or not a percentage of the nozzle examinations are performed in the first inspection period or performed concurrent with the reactor vessel ten-year examinations at the end of the inspection inten'al.

3) The pressurizer and primary steam generator nozzle-to-vessel welds, inside radius sections, and nozzle-to-safe end welds are similar in configuration, material properties, weld process parameters, and operate in the same reactor coolant system environment as the reactor vessel nozzles. Due to this similarity, distribution of the pressurizer and steam generator nozzle examinations in accordance with Examination Category B-D and Examination Category B-F will further substantiate the integrity of the reactor vessel nozzles until they are examined at or near the end of the second insenice inspection intenal.

4) Performing all the automated reactor vessel examinations during a single refueling outage improves consistency of the examinations by utilizing the same equipment, personnel, and procedures Moreover, this improves the reliability and reproducibility of the examinations i

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. Callaway Plant 2nd Interval -

Inservice Inspection Plan RELIEF REOUEST NUMBER: ISI-05 (Page 4 of 4) ,

-i PROPOSED ALTERNATE EXAMINATION -  !

Union Electric shall complete the required nozzle-to-vessel weld examinations, the nozzle inside '

radius section examinations, and the nozzle-to-safe end weld examinations concurrent with the ,

reactor vessel ten-year examinations at or near the end of the second ten-year inservice inspection interval. In addition, the reactor vessel hot leg nozzle inside surfaces, including the inside radius sections and nozzle-to-safe end weld areas, that are made accessible with the upper internals '!

removed and lower internals (core barrel) installed, shall be visually VT-3 examined once each ,

inspection period of the second ten-year inservice inspection interval. ,

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4.4-14

, . - . . .. - . = . . - - . ._ ~__ . -. .

% i Callaway Plant 2nd Interval- l Inservice Inspection Plan RELIEF REOUEST NUMBER: ISI-06 (Page l'of 6)

COMPONENT IDENTIFICATION Code Classes: 1,2 and 3 ._ l

References:

Table IWB-2500-1, Table IWC-2500-1, Table IWD-2500-1 i Examination Categories: B-H, B-K-1, C-C, D-A, D-B, D-C ,

Item Numbers: B8.10, B8.20, B8.30, B8.40, B 10.10, B 10.20, B 10.30, C3.10, C3.20, C3.30, C3.40, DI.20, DI.30, Dl,40, DI.50, DI .60, D2.20, f D2.30, D2.40, D2.50, D2.60 l

Description:

Alternate Rules for the Selection and Examination of Class 1,2 and 3 Integrally Welded Attachments Component Numbers: All Class 1,2 and 3 Integral Attachments Subject tu Inservice

• Inspection ,

CODE REOUIREMENTS i

i Class 1 Attachments:

Table IWB-2500-1, Examination Categories B-H and B-K-1 require the performance of surface t or volumetric examinations, as applicable, on integral attachments with a design thickness of 5/8" or greater. j Class 2 Attachments:  ;

Table IWC-2500-1, Examination Category C-C requires the performance of a surface l examination on integral attachments with a design thickness of 3/4" or greater.

i Class 3 Attachments Table WD-2500-1, Examination Categories D-A, D-B and D-C require the performance of a - i visual VT-3 inspection on integral attachments.

For complete details on ASME Section XI Code examination requirements, see Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1. ,

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1 4.4-15 1

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Callaway Plant 2nd Interval Inservice Inspection Plan RELIEF REOUEST NUMBER: ISI-06 '

(Page 2 of 6)

BASIS FOR RELIEF Reliefis being requested to allow the use of r.lternate requirements for the examination of Class 1,

. 2 and 3 integral attachments. The basis for this request is as follows:

1) During the first inservice inspection interval at the Callaway Plant, no inservice flaws were detected in integrally welded attachments which would affect safety or compromise the integrity of the plant.

2) Within the nuclear industry, failures in integral attachments have been very rare and have not affected plant safety. When failures or inservice defects are found in integral attachm: nts, they are usually associated with a support which has been damaged during operation.

Therefore, flawed or broken integral attachments are typically detected during the investigation of damaged supports rather than during Code scheduled inservice inspections.

One purpose of the alternative examination proposed below is to focus the inspection of integral attachments on those instances where the associated supports show signs of damage. This will increase the likelihood oflocating damaged integral attachments.

3) There is a significant amount of man-rem exposure and cost associated with the scheduled inspection of Class 1,2, and 3 integral attachments.

4) Unlike ASME Section XI, the alternate examinations proposed below do not impose a minimum thickness requirement for the inspection of an integral attachment. Therefore, a greater population ofintegral attachments will be available for inspection because inspections will not be limited to thick attachments This provision improves the quality and safety level established by these examinations.

5) The alternate examinations proposed below provide an acceptable level of quality and safety without causing undue hardship or difficulties.

PROPOSED ALTERNATE EXAMINATION The following rules will be used to select and examine integrally welded attachments'.

1) This Relief Request is limited to Examination Categories B-H, B-K-1, C-C, D-A, D-B and D-C.

2) Class 1,2 and 3 component supports shall be selected for examination in accordance with Code Case N-491.

3) Except for the selection of component supports for examination, all references to Section XI within this Relief Request are from the 1989 Edition.

. 4.4-16

i Callaway Plant 2nd Interval l Inservice Inspection Plan  !

RELIEF REOliEST NUMBER: ISI 06 (Page 3 of 6) J l

Scope These requirements apply to examination and sample selection of Class 1,2, and 3 integrally welded attachments of vessels, piping, pumps, and valves listed in Table 2500-1 as follows:

a) Table 2500-1, Examination Category B-K shall be used for Class I integrally welded attachments in Examination Categories B-H and B-K-1 ofIWB.

b) Table 2500-1, Examination Category C-C shall be used for Class 2 integrally welded attachments in Examination Category C-C ofIWC.

c) Table 2500-1, Examination Category D-A shall be used for Class 3 integrally welded attachments in Examination Categories D-A, D-B, and D-C ofIWD.

Exemotion Criteria a) The exemption criteria provided in IWB-1220, IWC-1220, and IWD-1220 may be applied to Class 1,2, and 3 components respectively, with integrally welded attachments, required to be examined in accordance with Table 2500-1.

b) Class 1,2, and 3 integrally welded attachment examinations performed as a result of component support deformation cannot be credited under the requirements ofIWB-241I or IWB-2412, IWC-2411 or IWC-2412, and IWD-2411 or IWD-2412, respectively.

Inspection Schedde Class 1,2, or 3 integrally welded attachments selected for examination by sample selection criteria in accordance with Table 2500-1, Examination Categories B-K, C-C and D-A, shall meet the requirements ofIWB-2411 or IWB-2412, IWC-2411 or IWC-2412, or IWD-241 I or IWD-2412, respectively.

Additional and Successive Examinations a) Class 1,2, and 3 additional and successive examination requirements ofIWB-2430 and IWB-2420 for Class 1, IWC-2430 and IWC-2420 fbr Class 2 and 3 as applicable, shall be applied to integrally welded attachments whose examinations reveal flaws or relevant conditions that exceed the acceptance standards ofIWB-3000 IWC-3000, and IWD-3000, respectively.

When integrally welded attachments are examined as a result ofidentified component support deformation and the results of these examinations exceed the applicable acceptance standards listed above, additional or successive examinations shall be performed when determined necessary based on an evaluation.

4.4-17

Callaway Plant 2nd Interval  !

insetvice inspection Plan RELIEF REQUEST NUM HER: ISI-06 (Page 4 of 6)

TABLE 2500-1 EXAMINATION CATEGORIES EXAMIN ATION CATEGORV H-K, INTEGRAL ATTACIIMENTS FOR CLASS 1 VESSELS, PIPING. PUMPS, AND VALVES ,

Item No. . Parts Esamined' Esamination Examination Acceptance Extent of Examination *# Frequency of Examination' Requirements / Fig. No. Method Standard B 10.10 Pressure Vessels IWB-2500-13. -14. and - Surface' IWB-3516 100% of required areas of Each identified occurrence and ,

Integrally Weided 15 each welded attachment each inspection interval

• Attachments B 10.20 Piping IWB-2500-13. -14, and - Surface IWB-3516 100% of required areas of Each identified occurrence and Integrally Welded 15 each welded attachment each inspection interval' Attachments Blo.30 Pumps IWB-2500-13. -14, and - Surface IWB-3516 100% of required areas of Each identified occurrence and integrally Wclded 15 cach welded attachment each inspection interval' Attachments

. B10.40 Valses 1WB-2500-13. -14. and - Surface IWB-3516 100% of required areas of Each identified occurrence and Integrally Wclded 15 each welded attachment each inspection intenal' Attachments NOTES:

(1) Examination i- limited to those integrally welded attachments that meet the following conditions:

(a) tly .achment is on the outside surface of the pressure retaining component; (b) tb attachment provides component support as defined in NF-1110. and (c) the attachment wcldjoins the attachment cither directly to the surface of the component or to an integrally cast or forged attachment to the component.

g(2) The extent of the examination includes essentially 100% of the length of the attachment we'd at cach attachment subject to examination.

r (3) Selected samples of integrally wclded attachments shall be examined each inspection interval.

(4) In the case of multipic vessels of similar design. function and senice, only one integrally welded attachment of only one of the multiple sessels shall be selected for examination (5) For piping. pumps. and salves. a sample of 10% of the wcided attachments associated with the component supports selected for examination under Code Case N-491 shall be c.xammed.

(6) Examination is required whenever component support member defonnation (e g.. broken. bent, or pulled out parts) is identified during operation, refueling.

maintenance. cxamination. insenice mspection. or testing.

(7) For the configuration show n in Fig. IWB-2500-14, a volumetric examination of volume A-B-C-D from side (B-C) of the circumferential welds may be performed in heu l of the surface examination of surfaces A-D and B-C.

4.4-18

Callaway Plant 2nd Interval Inservice Inspection Plan -

RELIEF REOUEST NUMBER: 1S1-06 (Page 5 of 6) _

TABLE 2500-1 (cont'd)

EXAMINATION CATEGORIES EXAMINATION CATEGORY C-C, INTEGRAL ATTACHMENTS FOR CLASS 2 VESSELS, PIPING, PUMPS, AND VALVES Item No. Parts Examined' Examination Examination Acceptance Extent of Examination *# Frequency of Examination

• Requirements / Fig. No. Method Standard C3.10 Pressure Vessels IWC-2500-5 Surface IWB-3512 100% of required areas of Each identified occurrence and Integrally Wclded each welded attachment each inspection intervall Attachments C3.20 Piping IWC-2500-5 Surface IWB-3512 100% of required areas of Each identified occurrence and Integrally Weided each welded attachment each inspection interval' Attachments C3.30 Pumps IWC-2500-5 Surface IWB-3512 100% of required areas of Each identified occurrence and Integrally Welded each welded attachment each inspection intenal' Attachments C3.40 Vahes IWC-2500-5 Surface IWB-3512 100% of required areas of Each identified occurrence and .

5 Integrally Weided each welded attachment cach inspection interval l Attachments NOTES:

(1) Examination is limited to those integrally ucided attachments that meet the following conditions:

(a) the attachment is on the outside surface of the pressure retaining component; y (b) the attachment provides component support as defined in NF-1I10. and (c) the attachment wcld joins the attachment cither directly to the surface of the component or to an integrally cast or forged attachment to the component.

(2) The extent of the examination includes essentially 100% of the length of the attachrnent wcld at each attachment subject to examination.

(3) Selected samples ofintegrally welded attachments shall be examined cach inspection interval.

(4) In the case of multiple vessels of similar design. function and settice, only one integrally wclded attachment of only one of the multiple vessels shall be selected for examination.

(5) For piping. pumps. and valves. a sampic of 10% of the welded attachments associated with the component supports selected for examination under Code Case N-491 shall be examined.

(6) Examinanon is required w hencter component support member deformation (e.g.. broken, bent. or pulled out parts) is identified during operation. refueling.

l mamtenance. examination. inservice inspection. or testing.

4.4-19

Y Callaway Plant 2nd Interval Inservice Inspection Plan -

RELIEF REOUEST NUMBER: ISI-06 (Page 6 of 6)

TABLE 2500-1 (cont'd)

EXAMINATION CATEGORIES EXAMIN ATION CATEGORY D.A. INTEGRAL ATTACilMENTS FOR CLASS 3 VESSELS. PIPING, PUMPS, AND VALVES Item No. Parts Examined' Examination Examination Acceptance Extent of Examination * Frequency of Examination-

Requirements / Fig. No. Method Standard D1.10 Pressure Vessels IWD-2500-1 Visual VT-1 IWD-3000 100% of required areas of - Each identified occurrence and integrally Wclded each welded attachment each inspection interval Attachments D1.20 Piping IWD-2500-1 Visual, VT-1 IWD-3000 100% of required areas of Each identified occurrence and Integrally Wclded each welded attachment each inspection interval Attachments DI.30 Pumps IWD-2500-1 Visual. VT-1 IWD-3000 100% of required areas of Each identified occurrence and Integrally Welded each wclded attachment each inspection interval Attachments D 1.40 Vahes IWD-2500-1 Visual. VT-1 IWD-3000 100% of required areas of Each identified occurrence and integrally Welded each welded attachment each inspection interval Attachments NOTES:

(1) Examination is limited to those integrally welded attachments that meet the following conditions:

(a) the attachment is on the outside surface of the pressure retaining component; (b) the attachment provides component support as defined in NF-1110; and (c) the attachment wcld joins the attachment cither directly to the surface of the component or to an integrally cast or forged attachmcnt to the component.

(2) The extent of the examination includes essentially 100% of the length of the attachment wcld at each attachment subject to examination.

(3) Selected samples ofintegrally wclded attachments shall be examined each inspection interval. All integrally welc'ed attachments selected for examination shall be subject to corrosion. such as the integrally welded attachments of the Senice Water or Emergency Service Water systems. In the case of multiple vessels of similar design, function and sen-ice, the integrally welded attachments of only one of the multiple vesscIs shall be selected fcr examination. For integrally welded attachments of piping. pumps. and valves. a 10% sampic shall be selected for examination. This percentage sample shall be proportional to the total number of nonexempt integrally welded attachments connected to the piping. pumps, and valves, located within cach system subject to these examinations.

(4) Examination is required whencter component support member deformation (e.g , broken, bent, or pulled out parts) is identified during operation, refueling, maintenance. examination. inservice inspection. or testing 4.4-20

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, , , . . . . . . .-.+x naa. ,. ,n ---x - -- = - . . ~ . .1 . -a.-

i

'i Callaway Plant 2nd Interval ,

inservice inspection Plan l RELIEF REOUEST NUMBER: ISI-07  ;

(Page1of3) i t

COMPONENT IDENTIFICATION l Code Classes: I and 2  ;

References:

IWA-5242(a) l Examination Categories: B-P and C-H l' Item Numbers: All Item Numbers Listed Under Examination Categories B-P and C-H

Description:

Alternate Rules for Insulation Removal During IWB-5000 l and IWC-5000 Pressure Tests at Bolted Connections in  !

Systems Borated for the Purpose of Controlling Reactivity [

Component Numbers: Bolted Connections in Systems Borated for the Purpose of j Controlling Reactivity l CODE REOUIREMENT I i

ASME Section XI,1989 Edition,- Paragraph IWA-5242(a) states,"For systems borated for the purpose -  !

of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for visual {

examination VT-2." i BASIS FOR RELIEF ,

Reliefis requested from the requirement to remove insulation for visual VT-2 examination of bolted  !

connections during a system pressure test on systems borated for the purpose of controlling reactivity. l Union Electric believes that removal ofinsulation at bolted connections in borated systems solely for a ,

visual VT-2 examination is impractical for the reasons listed below: i i

1) Code Class 1 and 2 systems borated for the purpose of controlling reactivity are extensive and large  ;

systems covering many areas and elevations. Scaffolding will be required to access many of the bolted connections. In addition, many of the bolted connections are located in diflicult to access areas and in medium to high radiation areas. Insulation removal combined with scafTolding requirements will increase the financial cost, personnel exposure, and generation of radwaste associated with i performance of visual VT-2 examinations.

I

2) The visual VT-2 examination of Class 1 systems, primarily the Reactor Coolant System (RCS) piping and components, is performed between plant mode 3 and 2 ascending. As required by IWB-5221, the  !

RCS is at a normal operating pressure of 2235 psig. Between modes 3 and 2 ascending, the ,

temperature is approximately 557 0F, Performance of a visual VT-2 examination, installation of ,

insulation, and disassembly of scafTolding at bolted connections under these operating conditions is a personnel safety hazard. The visual VT-2 examination is a critical path activity and normally has a j duration of six to eight hours. Since the majority of Class I piping is inside the containment building bio-shield wall, insulation installation and disassembly of scafTolding will add to the outage duration.  !

Critical path cost is currently estimated at $207,000 per day.

4.4-21 ,

i 1

Callaway Plant 2nd Interval l Inservice Inspection Plan i

RELIEF REOUEST NUMBER: 151-07 j (Page2of3)

Union Electric believes that the established Callaway programs described below in addition to the l alternative examination proposed below, provide an acceptable level of safety and quality for j

. bolted connections in systems borated for the purpose of controlhng reactmty.

1) In response to NRC Generic Letter 88-05, Union Electric has established a program for- l Engineering to inspect all boric acid leaks discovered in the containment building and to . l evaluate the impact of those leaks on carbon steel or low alloy steel components. All evidence ,

ofleaks, including boric acid crystals or residue, is inspected and evaluated regardless of j whether the leak was discovered at power or during an outage. Issues such as the following l are considered in the inspection and evaluation: 1) evidence of corrosion or metal degradation, j

2) effect the leak may have on the pressure boundary,3) possibility of boric acid traveling  ;

along the inside ofinsulation on piping, and 4) possibility of dripping or spraying on other . ,

components. Based on this evaluation, Engineering initiates appropriate corrective actions to ,

prevent reoccurrence of the leak and to repair, if necessary, any degraded materials or components. ,

2) In addition to the nondestructive examinations required by ASME Section XI, Union Electric i has committed to the bolting examination requirements of NRC Bulletin 82-02. In accordance' [

with this Bulletin, at least two nondestructive examination techniques (e.g., ultrasonic, liquid i penetrant, magnetic particle, or visual VT-1) are performed on bolted connections of the following components: Steam Generator primary manways, Pressurizer primary manway,  !

Pressurizer safety valves, and a total of 22 Reactor Coolant System isolation valves that are {

greater than 6" NPS. As a minimum, two nondestructive examination techniques are used whenever the bolted connection of one of the subject components is disassembled for maintenance or other inspection. These additional examinations ensure that degradation i mechanisms such as Stress Corrosion Cracking or corrosion do not go undetected in bolted  ;

connections critical to reactor safety. .!

3) The only carbon steel components at the Callawa s P ant that are in systems borated for the  :

purpose of controlling reactivity are clad with staimess steel. Specifically, these clad l components are the Reactor Vessel, Steam Generators (primary side), and Pres:urizer. All  ;

other piping and components in borated systems that are within inservice inspection boundaries are fabricated of stainless steel. There is substantial information, such as EPRI .

NP-5679, attesting to the resistance of stainless steels to boric acid corrosion. To ensure that j degradation mechanisms in stainless steels are mitigated, Union Electric maintains a program i at the Callaway Plant that controls materials (insulation, thread lubricant, boron, etc.) that may i come in contact with safety related components, including bolting This program ensures that  !

impurities are not present in concentrations that would promote development of Stress Corrosion Cracking in stainless steel bolted connections. j

)

4.4 22

- Callaway Plant 2nd Interval inservice Inspection Plan RELIEF REOUEST NUMBER: ISI-07 (Page 3 0f 3)

PROPOSED ALTERNATE EXAMINATION Bolted connections in systems borated for the purpose of controlling reactivity shall receive a -

visual VT-2 examination during the system pressure tests ofIWB-5000 and IWC-5000 with the insulation installed. If evidence ofleakage is detected, either by discovery of active leakage or evidence of boric acid crystals, the insulation shall be removed and the bolted connection shall be -

re-examined and, if necessary evaluated in accordance with the corrective measures of Subarticle IWA-5250.

Ifinsulation is removed for planned maintenance, repair, or other inspection at a bolted connection in a system borated for the purpose of controlling reactivity, a _ visual VT-2 examination shall be performed on the bolted connection prior to disassembly and, if evidc..ce of leakage is discovered, evaluated in accordance with the corrective measures of Subarticle IWA-5250.

4.4-23

i Callaway Plant 2nd Interval  ;

Inservice Inspection Plan  :

REL1EF REOUEST NUMBER: ISI-08 (Page 1 of 2) ,

COMPONENT IDENTIFICATION ,

Code Classes: 1,2, and 3

Reference:

IWA-5250(a)(2)

Examination Category: N/A '

Item Number: N/A

Description:

Alternate Rules for Corrective Measures if Leakage Occurs at a Bolted Connection Component Numbers: Class 1,2, and 3 Pressure-Retaining Bolted Connections CODE REOUIREMENT .

ASME Section XI,1989 Edition, Subparagraph IWA-5250(a)(2) states, "ifleakage occurs at a bolted connection, the bolting shall be removed, VT-3 visually examined for corrosion, and evaluated in accordance with IWA-3100."

BASIS FOR RELIEF A leaking environment at a bolted connection may be a significant variable in the degradation mechanism of bolted connections. However, leakage is not the only variable, and in some cases i may not be the degradation mechanism. Other variables to be considered are: bolting materials, leaking medium, duration of the leak, and orientation of the leak (not all the bolts may be wetted).

These variables are important to consider before disassembling a bolted connection for a visual VT-3 examination. Removal of bolting at a mechanical connection may not be the most prudent decision and may cause undue hardship without a compensating increase in the level of quality or safety. Union Electric proposes an alternative to the requirements ofIWA-5250(a)(2) that will provide an equivalent level of quality and safety at Class 1,2, and 3 bolted connections.

PROPOSED ALTERNATE EXAMINATION Leakage discovered at a bolted connection by visual VT-2 examination during systeni pressure test will be evaluated to determine the susceptibility of the bolting to corrosion and potential future failure. The evaluation will, as a minimum, consider the following variables: I

1) Location ofleakage

2) History ofleakage

3) Bolted connection materials

4) Visual evidence of corrosion with the connection assembled

5) Corrosiveness of the process fluid .

6) History and studies of similar bolted material in a similar environment .l

7) Other components in the vicinity that may be degraded due to the leakage I

4.4-24 l i

l

_ - I

Callaway Plant 2nd Interval

-Inservice Inspection Plan RELIEF REOUEST NUMBER: ISI-08 (Page 2 of 2)

When evaluation of the variables above indicates the need for further evaluation, the bolt closest to the source ofleakage will be removed, receive a visual VT-3 examination, and be evaluated in accordance with IWA-3100(a). If the leakage was identified with the bolted connection in service and evaluation supports continued service, this VT-3 examination may be deferred to the next outage of sufficient duration. When the removed bolt has evidence of rejectable degradation, all remaining bolts shall be removed and subsequently receive a visual VT-3 examination and evaluated in accordance with IWA-3100(a).

4.4-25

i f

~!

Callaway Plant 2nd Interval. j Inservice Inspection Plan l RELIEF REOUEST NUMBER: ISI-09 l (Page1of3)

COMPONENT IDENTIFICATION .l

. Code Class: 2  !

Reference:

Table IWC-2500-1 Examination Category: C-H Item Numbers: C7.30, C7.40, C7.70, and C7.80 l

Description:

Alternate Provisions for Pressure Testing Code Class 2 Piping and. f Valves at Containment Penetrations Where the Balance of the l System is Outside the Scope of Section XI.

Component Numbers: Line Number Penetration Description

{

BB-103-HCB-1" P-62 Pressurizer relief tank gas line  ;

BL-028-HCB-3" P-25 Reactor water storage tank to f RCP standpipes BM-053-HBB-3" P-78 Steam Generator drain EC-067-HCB-6" P-53 Fuel pool cooling return j EC-072-HCB-6" P-54 Refueling pool to fuel pool  !

cooling pump suction [

EC-081-HCB-3" P-55 Refueling pool to fuel pool l skimmer pump i EM-071-BCB-3/4" P-92 SIS pump test line return to  ;

Reactor water storage tank i GP-003-HBB-1" P-51 ILRT test connection lines  !

GP-005-HBB-1" P-51 ILRT test connection lines. f GS-025-HBB-6" P-65 Hydrogen purge subsystem to - l ESF filters GT-007-HBB-36" V-160 Containment shutdown purge GT-004-IIBB-36" V-161 Containment shutdown purge l GT-029-HBB-18" V-161 Containment shutdown purge GT-034-HBB-18" V-160 Containment shutdown purge i GT-033-HBB-18" V-160 Containment shutdown purge GT-030-HBB-18" V-161 Containment shutdown purge i HB-015-HCB-3" P-26 From reactor coolant drain tank heat exchanger HB-025-HBB-3/4" P-44 Reactor coolant drain tank to waste gas compressor HD-015-HBB-2" P-43 Auxiliary steam for reactor vessel head decontamination 4.4-26

Callaway Plant 2nd Interval Inservice Inspection Plan RELIEF REOUEST NUN 1BER: 1S1-09 (Page 2 of 3)

Component Numbers (Cont.): Line Number Penetration Description KA-244-HCB-1 1/2" P-30 Compressed air KA-259-HCB-1 1/2" P-30 Compressed air

'KA-051 -HB B-5" P-63 Service air KA-261-HBB-1" P-63 Reactor building service air KA-732-HBB-1" N/A Personnel hatch penetration test lines K A-733-HBB-1" N/A Personnel hatch penetration test lines KB-001-HCB-2" P-98 Breathing air KC-560-HBB-4" P-67 Fire protection LF-842-HCB-6" P-32 Containment building floor drain header SJ-002-BCB-1" P-69 Nuclear sampling from pressurizer vapor space SJ-003-ECB-1" P-95 Nuclear sampling from accumulator tanks SJ-001-BCB-1" P-93 Loop i hot leg liquid sample to PASS SJ-029-BCB-1" P-93 Loop I hot leg liquid sample to PASS SJ-021-BCB-1" P-64 Loop 3 hot leg & pressurizer liquid sample to PASS SJ-024-BCB-1" P-57 PASS to reactor coolant drain tank SJ-025 -BCB- 1 " P-58 PASS to reactor coolant drain tank CODE REOUIREN1ENT ASME Section XI, Table IWC-2500-1, Examination Category C H, requires the performance of a visual VT-2 examination during a system pressure test on Code Class 2 pressure retaining components. Note 7 of this table states,"The pressure boundary includes only those portions of the system required to operate or support the safety system function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required." l l

l 4.4-27 i

! l u -

j Callaway Plant 2nd Interval Inservice Inspection Plan j r

RELIEF REOUEST NUMBER: ISI-09 l (Page 3 of 3)

BASIS FOR RELIEF l 5

Union Electric Company requests relief from the requirement to perform a pressure test in  !

accordance with ASME Section XI, Table IWC-2500-1, Examination Category C-H on the Code l Class 2 lines listed above. Based on the discussion below, these pressure tests are considered l

redundant and without a compensating increase in the level of quality or safety. ,

The lines listed above are portions of non-safety related piping systems that penetrate the primary  :

reactor containment. At each containment penetration, the process pipe is classified Code Class 2 and provided with isolation valves that are either locked shut during normal operation, capable of I automatic closure, or capable of remote closure to suppon the containment safety function. The  :

piping and valves are considered pan of the primary reactor containment and upgraded to Code  !

Class 2 at the penetration only to support the primary reactor containment safety function.  !

Except for this, the lines listed above provide no safety function. I The primary reactor containment integrity, including all containment penetrations, is periodically verified by performing leakage tests in accordance with a 10 CFR 50, Appendix J. Each of the Code Class 2 lines listed above and their associated isolation valves are tested during an Appendix J, Type A, B or C leakage test at a pressure not less than 48.1 psig. The Type A leakage test is performed three times in a ten year interval and the Type B and C leakage tests are performed at 3 intervals not greater than 24 months. Performance of these Appendix J leak tests will verify the integrity of the subject Code Class 2 lines at each respective penetration. The performance of j ASME Section XI, Examination Category C-H pressure tests on these same lines will provide  ;

little, if any, additional verification of primary reactor containment integrity. Based on this, the performance of Examination Category C-H pressure tests on these lines is considered by Umon j Electric to be unnecessary and provides a negligible increase in the level of quality or safety.

i PROPOSED ALTERNATE PROVISIONS I r

Union Electric shall perform 10 CFR 50, Appendix J leakage tests on the primary reactor containment penetration lines listed above, and on their associated valves, in accordance with Callaway Technical Specification 3/4.6. j t

i i

4.4-28 i

Callaway Plant 2nd Interval Inservice Inspection Plan SECTION 5.0 NRC CORRESPONDENCE This Section contains all NRC correspondence related to the Second Interval Inservice Inspection Plan at the Callaway Plant. The purpose of this Section is to incorporate NRC correspondence directly into the Inspection Plan so that related requests for information, submittals, decisions and approvals are permanently documented.

s 5-1