ML20214A066

PGE-1049, Trojan Nuclear Plant Inservice Insp Program for First 10-Yr Interval 860520-960519

ML20214A066
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	11/14/1986
From:	PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20214A039	List: ML20214A038 ML20214A066
References
PGE-1049, TAC-63974, NUDOCS 8611190186
Download: ML20214A066 (109)

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I PGE-1049 f

l TROJAN NUCLEAR PLANT INSERVICE INSPECTION PROGRAM FOR THE SECOND 10-YEAR INTERVAL I

May 20, 1986 through May 19, 1996 1

Portland General Electric Company 121 SW Salmon Street j

Portland OR 97204 4

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l PGE-1049 INSERVICE INSPECTION PROGRAM CONTENTS Section Title Page l

Table of Contents 1-11 l

List of Tables..

iii

1.0 INTRODUCTION

1 2.0 ADMINISTRATIVE CONTROLS 6

2.1 SYSTEM BOUNDARIES 7

2.2 EKAMINATION PROGRAM 10 3.0 CLASS 1 COMPONENTS.

11 3.1 CLASS 1 SYSTEM BOUNDARIES 13 3.1.1 Piping Pressure Boundary...

13 3.2 CLASS 1 EXEMPT COMPONENTS 17 19 3.3 CLASS 1 RELIEF REQUESTS 3.3.1 Seal Monitoring Test Penetration.

19 3.3.2 Nozzle Inner Radius on Steam Generators 20 22 3.3.3 Reactor Coolant Pump.

4.0 CLASS 2 COMPONENTS.

24 4.1 CLASS 2 SYSTEM BOUNDARIES 26 4.2 CLASS 2 EXEMPT COMPONENTS 30 4.2.1 Category C-F and C-G Components 30 34 4.2.2 Class 2 Components..

(Except Category C-F and C-C)._

PGE-1049 INSERVICE INSPECTION PROGRAM CONTENTS Section Title Page 4.3 CLASS 2 RELIEF REQUESTS 36 4.3.1 Class 2 Hydrostatic Test.

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4.3.2 RHR Heat Exchanger Nozzle-to-Vessel Weld...

41 4.3.3 Reactor Coolant Filter.

43 4.3.4 Seal Water Heat Exchanger 44 4.3.5 Seal Water Return Filter.

45 4.3.6 Regenerative Heat Exchanger 46 5.0 CLASS 3 COMPONENTS.

48 5.1 CLASS 3 SYSTEM BOUNDARIES 49 5.2 CLASS 3 EXEMPT COMPONENTS 50 5.3 CLASS 3 RELIEF REQUESTS 52 5.3.1 Inaccessible Components 52 6.0 COMPONENT SUPPORTS.

55 6.1 EXEMPT COMPONENT SUPPORTS 56 6.2 RELIEF REQUESTS 58 l -

PGE-1049 INSERVICE INSPECTION PROGRAM TABLES Number Title Page 1

Inservice Inspection Program Class 1 Components.

59 2

Inservice Inspection Program Class 2 Components.

73 3

Inservice Inspection Program Class 3 Components.

98 4

Inservice Inspection Program Class 1 Supports.

101 5

Inservice Inspection Program Class 2 Supports.

102 6

Inservice Inspection Program Class 3 Supports.

103 Notes for Tables 1 through 6 104

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PGE-1049

1.0 INTRODUCTION

This summary submittal describes the Trojan Nuclear Plant's Second 10-Year Inservice Inspection Program.

The Inspection Program, which consists of ASKE Class 1, 2, and 3 sys-tems, components, and supports, is being developed by giving due con-sideration to the following documents:

• 10 CFR 50.55(a)

• Section XI of the ASME Code

• Section V of the ASME Code

• USNRC Regulatory Guides Regulatory Guide 1.147 l

Regulatory Guide 1.26 Regulatory Guide 1.14 Regulatory Guide 1.150 Regulatory Guide 1.83

• Trojan Nuclear Plant - FSAR

• Trojan Nuclear Plant - First 10-Year Inspection Plan

• Trojan Nuclear Plant - PSI Inspection Plan The First 10-Year Inspection Plan was written and implemented in accordance with the 1974 Edition through Summer 1975 Addenda of Section II of the ASKE B & PV Code.

l The Preservice Inspection was conducted in accordance with the 1971 Edition through Winter 1972 Addenda of Section II of the ASME B &

PV Code.

i Title 10. Chapter 1, Code of Federal Regulations (CFR) Energy, Part 50, Section 50.55a(g) sets forth the requirements for inservice J

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PGE-1049 inspection (ISI) of nuclear power plant components. The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components", is referenced by 10 CFR 50.55a(g) as the standard to be used for inservice inspection of nuclear class components and their supports.

The Trojan Nuclear Plant Construction Permit was issued on February 8, 1971. Class 1, 2, and 3 components and their supports for Trojan were committed to design and provision for access to enable the performance of inservice examination. The First 10-Year Interval Inservice Inspection Program for Trojan began on the date of commercial opera-tion, May 20, 1976, and extended through May 19, 1986.

This program outlines the ISI requirement for the Second 10-Year Interval which started May 20, 1986 and runs through May 19, 1996.

This interval will be divided into three periods of three years', four years', and three years' duration for the first, second, and third periods, respectively. The Class 1, 2, and 3 components and their supports will meet the standards in the 1983 Edition and Addenda through the Summer of 1983 of ASME Section XI.

Systems and components at Trojan are classified by quality group according to Amendment 3 (July 1985) of the Updated Final Safety Analysis Report (FSAR). The following relation between Trojan quality groups and ASME Section XI, Code Classes, has been adopted for the purpose of defining inservice inspection requirements for the Trojan Nuclear Plant:

Trojan Quality Group ASME Section XI Code Class 1

1 2

2 3a 3

3b 3

Aa Non-Class Ab Non-Class.

PGE-1049 1

The boundaries which define the applicable examination requirements for a given system or component are discussed in Section 3.1 for Class 1 systems, Section 4.1 for Class 2 systems, and Section 5.1 for Class 3 systems.

In certain cases, strict compliance with ASME Section II has been determined to be impractical for Trojan.

It is stated in 10 CFR 50.55a(g)(iii) that:

"If the licensee has determined that conformance with certain code requirements is impractical for his facility, the licensee shall notify the Commission and submit information tc support his determinations."

Relief from the examination requirements of ASME Section XI standards for Class 1, 2, and 3 components at Trojan are discussed in Sections 3.3, 4.3, and 5.3, respectively. Relief from the examination requirements is requested based upon the justification and alternate examination method provided.

The ISI program has been developed from an engineering review of the systems, components, and supports at Trojan. A provision in 10 CFR 50.55a(s) allows for taking exception to examination of compo-nents in the event that unforeseen difficulties are encountered. When an examination is determined to be impractical during the process of performing inspections or tests, the exception will be identified in the ISI outage summary, and relief will be requested by revision to the ISI program.

The following is a list of items to be examined in the program that are in addition to Code requirements or performed under the Technical Specifications. _ _ _ _.. _ _ _

PGE-1049 (1) The reactor coolant pump motor flywheels are to be examined in accordance with the requirements of NRC Regulatory Guide 1.14.

Flywheels will be ultrasonically examined in place, utilizing the access provided by the gauge holes through the flywheels. Surface examinations will not be performed as accessible surfaces of the flywheels are painted.

(2) Inservice inspection will be conducted to the extent prac-tical on each of the Class 2 main steam welds located between the Containment penetration and the second main steam isolation valve.

(3) Steam generator tubes are to be examined by eddy current in accordance with the requirements of Technical Specifica-tion 4.4.5, per Section II, Subarticle IWB-2413.

(4) System leakage and hydrostatic pressure tests are scheduled and controlled under specific Plant procedures. Reports of test results will be included in each ISI summary report.

(5) Performance testing of safety-related pumps and valves is scheduled and controlled under PGE-1048, " Inservice Testing Program for Pumps and Valves".

Repairs, modifications, replacements, and alterations to pressure-i retaining components will be made in accordance with ASME Section XI, Subsections IWA-4000 and IWA-7000, as applicable.

ASME Section XI, Subsection IWE, requirements fcr the examination.

inservice inspection, repair and replacement of Class MC pressure-l retaining components and their integral attachments, and steel por-tions of Class CC pressure-retaining components not backed up by 4

PGE-1049 i

concrete, and their integral attachments will be considered separately per the Federal Register, Volume 48, Number 26, dated Monday, February 7, 1983.

This ISI Program is subject to change. Changes will be effected via relief requests or document revisions. The Trojan ISI Program will be 4

updated every 10 years or more frequently to reflect optional owner i

upgrades or regulatory comitments.

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PGE-1049 2.0 ADMINISTRATIVE CONTROLS The inservice inspection (ISI) 0F ASME Section II, Class 1, 2, and 3 components and their supports, is required by the Trojan Nuclear Plant Technical Specifications, Appendix A to Facility Operation License (FOL) NPF-1.

It has been acknowledged by the Nuclear Regulatory Commission (NRC) that variances or exceptions to examination requirements will be iden-tified during implementation of the ISI Program. The Nuclear Plant Engineering Department (NPED) is assigned the responsibility for iden-tifying and reporting these exceptions to the Plant Staff and to the Nuclear Safety & Regulation Department (NSRD) for subsequent reporting to the NRC.

Implementation of the program described in this report will be accom-plished in accordance with PGE-8010 " Nuclear Quality Assurance Pro-gram".

Compliance with the provisions of the examination and testing requirements of ASME Section II shall be assured by an inspector as required by Paragraph IWA-2120.

All items to be examined during a given period are to be scheduled for completion by the end of the applicable period. A summary ISI report for class 1, 2, and 3 components and their supports shall be filed within 90 days after completion of the ISI, with the enforcement and regulatory authority having jurisdiction at the Plant. The summary l

ISI report will be prepared by NPED.

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PGE-1049 f

2.1 SYSTEM BOUNDARIES Classification of systems for the Trojan Nuclear Plant is outlined in Section 3.2.2, Amendment 3, July 1985 of the Updated Final Safety Analysis Report (FSAR). To provide a general view of how this classi-fication system has been applied to Trojan, color-coded figures for the systems can be found in the Updated FSAR, indicating classes as represented by the applicable codes and standards.

In these figures, red indicates those components built to the standards and codes of Class 1, orange indicates those components built to the standards and codes of Class 2. green indicates those components built to the stan-dards and codes of Class 3, and black indicates those components that are Non-Class. Occasionally some components have been built to a higher classification than required because of convenience or eco-nomics of fatrication or construction.

The systems listed below encompass those Class 1, 2, and 3 systems which have been included in this ISI Program:

Updated FSAR System Flaure No.

P&ID No.

Reactor Coolant System 5.1-1 M-201 Reactor Coolant System 5.1-la M-201 Residual Heat Removal System 5.4-7 M-205 Safety Injection System 6.3-1 M-206 Containment Spray System 6.5-1 M-207 Spent Fuel Pool Cooling 9.1-4 M-227 Demineralizer System Service Water System 9.2-1 M-218 Component Cooling Water System 9.2-4 M-215 Makeup Water Treatment System 9.2-8 M-228 1,,

PGE-1049 Updated FSAR System Flaure No.

P&ID No.

Instrument and Service Air System 9.3-1 M-223 Process Sampling System 9.3-2 M-231, Sht. 1 9.3-4 M-231, Sht. 3 Chemical and Volume Control System 9.3-14 M-202 9.3-15 M-203 9.3-16 M-204 Chilled Water System 9.4-2 M-248 Diesel Fuel Oil System 9.5-3 M-226 Main Steam System 10.2-3 M-208 Circulating Water and Turbine 10.4-1 M-216 Building Cooling Water System Condensate and Feedwater System 10.4-2 M-213, Sht. 1 10.4-2a M-213, Sht. 2 Auxiliary Steam System 10.4-3 M-214 Steam Cenerator Blowdown System 10.4-8 M-348 Clean Radioactive Waste Treatment 11.2-9 M-220 System Dirty Radioactive Waste Treatment 11.2-14 M-221 System Radioactive Gaseous Waste System 11.3-4 M-222 In addition, the portions of Non-Code Class Systems that have been upgraded and are part of the containment isolation boundaries are included in the ISI Program. These specific portions of Non-Code Class Systems will be examined according to the requirement of ASME Section II, Subsection IWC. '

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PGE-1049 The systems listed below encompass those Non-Code Class Systems which are included in the ISI Program:

Updated FSAR System Figure No.

P&ID No.

Hydrogen Vent System 6.2-50 M-243 Containment Purge System 6.2-50 M-243 Spent Fuel Pool Cooling and 9.1-4 M-227 Domineralizer System

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2.2 EXAMINATIOW PROCRAM Inservice inspection of Class 1, 2, add 3 compot uts and their sup-ports is required to meet the standards in the 1983 Edition of ASME Section II and Addenda through Sumet 1983 with the exception of

' categories B-J. C-F, and C-G, which will meet the selection criteria

. identified in the 1974 Edition and Addenda through Sumer 1975. The

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wamination of these cor.iponents and their supports has been scheduled asoutlinediniWk-240J. The Edition a.id Addenda of ASME Section II used in defining ISI requirements is moolfied at 10-year intervals by the requirettents of 10 CFR 50.55a(s), and successive programs will be updated to later editions and addenda in effect 12 months prior to s

3-commencement nf the succersiva. interval.

Class 1 components h' ave been schedulad for exan.Instlen in accordance with the inspection program outlined in' Paragraphs IWB-2412 (Inspec-tion Prograd B). IWL-2420, and IWB-2430. l'abli 1 pt esents the sumary of these examinations for the Second 10-Year Interval.

a C1sss2componentshavebeenscheduiedferemNinationinaccordance with the inspection program outlined in Paragt:aph IWC-2412 (Inspection Program B), IWC-2420, nyif 1W0-2430. Table 2 presents the sumary of thage examinations for the Second 10-Year Interval.

Class 3 components have been scheduled for, examination in accordance with the inspection program outlined in IWu-2400. Table 3 presents the sumary of thou examinetpons for the Second 10-Year Interval.

Class i 2, and 3 pmponentI typort.s basi been scheduled for exanina-tion in accordance with the inspection program outlined in IWF-2400.

Tables 4, 5, and 6 presenk the nunebry of these examinations for the Second 10-Year Interval.

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PGE-1049 3.0 CLASS 1 COMPONENTS Class 1 components, with the exception of Category B-J components, 5

have been scheduled in accordance with the regular inspection program outlined in ASME Section II, Paragraphs IWB-2412. IWB-2420, and IWB-2430. Because the application for a construction permit for the Trojan Nuclear Plant was "... docketed prior to July 1, 1978, the extent of examination for Code Class 1 pipe welds may be determined by the requirements of Table IWB-2500 and IWB-2600 Category B-J of i

Section XI, of the ASME Code in the 1974 Edition and addenda through the Summer 1975 Addenda.

.", per 10 CFR 55a(b)(ii). With the j

exception of items covered under Category B-J, the extent of examina-tion for all Class 1 components was determined by the requirements of Table IWB-2500 of the 1983 Edition and addenda through the Summer 1983 Addenda. Table 1 lists and quantifies these requirements. Acceptance standards for flaw indications, repair procedures, system pressure tests, and replacements are defined in Paragraphs IWB-3000, IWB-4000, IWB-5000, and IWB-7000, respectively.

Section 3.2 is a listing of those components which have been exempted from examination under the provisions of ASME Section II and other laws regulating operation of a nuclear power generating plant.

Title 10, Chapter 1, Code of Federal Regulations Energy, Part 50, Section 50.55a(g)(iii) states that ".

. If the licensee has deter-mined that conformance with certain code requirements is impractical for his facility, the licensee shall notify the Commission and submit information to support his determination." Section 3.3 provides iden-tification of components and information for support of the conclu-sions that examination is impractical.

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i PGE-1049 The class 1 components requiring examination at the Trojan Nuclear Plant are:

(1) Reactor pressure vessel.

(2) Pressurizer.

(3) Steam generators.

(4) Piping pressure boundary.

(5) Reactor coolant pumps.

(6) Valve pressure boundary.

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PGE-1049 3.1 CLASS 1 SYSTEM BOUNDARIES The systems listed below include those Class 1 systems which have been included in this ISI Program:

Updated FSAR System Figure No.

P&ID No.

Reactor Coolant System 5.1-1 M-201 Reactor Coolant System 5.1-la M-201 Residual Heat Removal 5.4-7 M-205 System Safety Injection System 6.3-1 M-206 Chemical and Volume control 9.3-14 M-202 System 9.3-15 M-203 3.1. '1 Piping Pressure Boundary Portions of the piping systems in the Reactor Coolant System (RCS),

Chemical and Volume Control System (CVCS), Residual Heat Removal Sys-tem (RHR), and Safety Injection System (SIS) are Class 1.

Those por-tions of each system which are Class 1 are color-coded red in the

~.4 dated FSAR drawings.

Class 1 piping pressure boundaries which require examination in addi-tion to the four main reactor coolant loops under Category B-J are:

Loop 1 (1) Hot-leg high-head injection 6-and 2-in. lines to Check Valve 8905B.

(2) RCS 2-in. hot-leg and cold-leg resistance temperature detector (RTD) manifold lines and 3-in. return line.

PGE-1049 (3) CVCS 3-in normal charging line to Check Valve 8378B.

(4) Waste Disposal System 2-in, reactor coolant drain line to Valve 8058A.

(5) SIS 10-in. accumulator discharge line to Valve 8808A, RHR System 6-in. low-head injection line to Check Valve 8818A.

(6) SIS 1-1/2-in. boron injection line to Valve 8818A.

Loop 2 (1) Hot-les high-head injection 8, 6, and 2-in. lines to Check Valve 8905A and 8-in. RHR System return to Check Valve 8736A.

(2) RCS 2-in. hot-leg and cold-leg RID manifold lines and 3-in.

return line.

(3) RCS 14-in, surge line to pressurizer.

(4) RCS 6-in lines to Pressurizer Safety Valves 8010A, B, and C.

(5) RCS 3-and 6-in. lines to Pressurizer Safety Valves PCV-455A and PCV-456.

(6) RCS 4-in. spray line to pressurizer.

(7) Waste Disposal System 2-in. reactor coolant drain line to Valve 8058B. _ -_-__

PGE-1049 (8) SIS 10-in, accumulator discharge line to Valve 8808B, RHR System 6-in. low-head injection line to Check Valve 8818B, and 2-in. cold-les high-head injection to Check Valve 8814B.

(9) SIS 1-1/2-in boron injection line to Valve 8810B.

Loop 3 (1) Hot-leg high-head injection 6-and 2-in. lines to Check Valve 8905D.

(2) RCS 2-in. hot-leg and cold-leg RTD manifold lines and 3-!

return line.

(3) CVCS 3-in. letdown line to Valve LCV-459 and RCS 2-in.,

drain line to Valve 8058C.

(4) SIS 1-1/2-in. boron injection line to Valve 8810C.

(5) RCS 4-in. spray line.

Loop 4 (1) RHR 14-in. takeoff to Valve 8701, high-head injection 8,

6, and 2-in. lines to Check Valve 8905C, and 8-in. RHR System return to Check Valve 8736B.

(2) RCS 2-in. hot-leg and cold-leg RTD manifold lines and 3-in.

return line.

(3) Waste Disposal System 2-in, reactor coolant drain line to Valve 8058D.

(4) CVCS 3-in. alternate charging line to Check Valve 8379B..

PGE-1049 (5) SIS 10-in, accumulator discharge line to Valve 8808D, RHR System 6-in. cold-les low-head injection line to Check Valve 8818D, and 2-in, cold-leg high-head injection line to Check Valve 8819D.

(6) SIS 1-1/2-in boron injection line to Valve 8810D.

Safety Injection System Boron injection 1-1/2-in, lines from Valves 8810A, B, C, and D to Check Valve 8815.

Chemical and Volume Control System RCS 2-and 1-1/2-in. seal injection water lines to Check Valves 8350A, B, C, and D.

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PGE-1049 3.2 CLASS 1 EXEMPT COMPONENTS The following Class 1 components or parts of components for Trojan are exempted from volumetric and surface examination by Paragraph IWB-1220 according to the following criteria:

(a) Components that are connected to the reactor coolant system and part of the reactor coolant pressure boundary and that are of such a size and shape so that upon postulated rupture the resulting flow of coolant from the reactor coolant sys-tem under normal plant operating conditions is within the capacity of makeup systems which are operable from on-site emergency power; (b)

(1) Piping of 1 in. nominal pipe size and smaller, except for steam generator tubing; (2) Components and their connections in piping of 1 in.

nominal pipe size and smaller; (c) Reactor vessel head connection and associated piping, 2 in.

nominal pipe size and smaller, made inaccessible by control rod drive penetrations.

Class 1 piping and components which are exempt from examination by IWB-1220 are:

(1) RCS temperature element lines to TE-413A, 413B, 423A, 423B, 433A, 433B, 443A, and 443B.

(2) RCS 1-in. hot-leg RTD takeoff lines. -.

PGE-1049 (3) RCS RTD loop temperature element lines to TE-410A, 410B, 411A, 411B, 420A, 420B, 421A, 421B, 430A, 430B, 431A, 431B, 440A, 440B, 441A, and 441B.

(4) CVCS 1-in. excess letdown line to Valve 8153.

(5) Reactor vessel head 1-in. vent line to blind flange.

(6) Reactor vessel lower head in-core instrumentation conduits.

(7) Reactor vessel flange seal leakoff 1-in. lines to 1 x 3/4-in. reducer.

(8) RCP 3/4-in. seal bypass lines to Flow Orifices FO-1957,

-1958, -1959, and -1960.

(9) RCP 3/4-in. labyrinth seal lines to Pressure Trans-ducers PDT-146, 147, 148, AND 149.

(10) RCS RTD loop flow orifice connections to FE-417. -427,

-437, and -447 and FO-1915. -1917

-1919, and -1934.

(11) RCP seal leakage drain lines.

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PGE-1049 3.3 CLASS 1 RELIEF REQUESTS 3.3.1 Seal Monitoring Test Penetration 3.3.1.1 Code Requirement The area surrounding each penetration shall be examined for evidence of leakage during the pressure test.

3.3.1.2 Code Deviation Request Request relief from the visual examination of inner and outer seal monitoring tube penetrations (Table IWB-2500-1, Category B-E, Item B4.13).

3.3.1.3

Reason for Request

The reactor vessel, T-201, is a Class 1 component which is a part of the pressure-retaining boundary for the RCS.

The closure head is sealed to the vessel by two 0-ring seals. The vessel flange has two penetrations for closure head seal leakage monitoring. The inner monitoring tube detects leakage across the outer 0-ring seal. Each of these tubes is connected by a partial penetration weld on the vessel flange gasket seal surface, which is weld overlaid with 5/32-in.-thick stainless steel.

These welds are outside the pressure boundary for normal operation and will only be pressurized if the closure seals leak. The monitoring tubes are 1-in. nominal pipe size.

Table IWB-2500-1, Category B-E, Item B4.13 (Instrumentation Nozzles) requires visual examination of these welds during hydrostatic test-ing. Paragraph IWB-1220 exempts these components based on the size of l

PGE-1049 the tubing, but imposes a requirement for visual examination during hydrostatic pressure testing.

Volumetric (ultrasonic), surface, or visual examination of the welds cannot be performed due to the geometric configuration and inaccessi-bility. Hydrostatic pressure testing of the welds is not feasible due to their location outside of the pressure-retaining 0-ring seals on the vessel flange. These welds will only be pressurized in the event of the loss of integrity of the seals. Failure of both the 0-ring seals and the tube welds is considered unlikely.

Loss of coolant due to complete severance of a monitoring tube can be made up by normal charging methods.

3.3.1.4 Alternative Examination The welds will not be examined.

3.3.2 Nozzle Inner Radius on Steam Generators 3.3.2.1 Code Requirement Volumetric examination of 100 percent of the nozzle inner radius dur-ing each inspection interval (Table IWB-2500-1, Category B-D, Item B3.140).

3.3.2.2 Code Deviation Request Perform a visual examination of nozzle inner radius in lieu of volu-metric examination. - -_

PGE-1049 3.3.2.3

Reason for Request

There are four steam generators of the vertical shell and U-tube evaporator type at the Trojan Nuclear Plant. The portions of each steam generator which contain reactor coolant pressure are Class 1, and the portions which contain the steam generating system are Class 2.

The Class 1 portion of each steam generator consists of the hemis-pherical bottom head with inlet and outlet nozzles, a vertical parti-tion plate for dividing the inlet and outlet chambers, a tube plate, and inverted U-tubes.

Manways are provided in the bottom hemispher-ical head for eccess to both sides of the partitioned head.

The bottom head is cast with the nozzles as an integral part; there-fore, there are no nozzle-to-head welds. The reactor coolant inlet and outlet nozzles are tapered with an inner radius section.

The general radiation in the area is 15-30 rads per hour, gamma plus beta. The outer surface of the bottom head is in the as-cast condi-tion, which precludes performing an ultrasonic examination of the inner radius. The inner surface of the bottom head is clad, which precludes performing a surface examination of the inner radius.

3.3.2.4 Alternative Examination The nozzle inner radius will be visually examined from the manway opening using manual or remote techniques each time a steam generator ISI tube examination is performed. - -

PGE-1049 3.3.3 Reactor Coolant Pump 3.3.3.1 Code Requirement Table IWB-2500-1, Categories B-L-1 and B-L-2, Items B12.10 and B12.20, requires pump casing welds and pump casings to be examined on at least one pump by the end of the inspection interval.

3.3.3.2 Code Deviation Request Request relief from perforning the volumetric examination of the pump casing weld (Item B12.10) and the visual examination of the internal pressure boundary surfaces in the pump casing (Item B12.20).

3.3.3.3

Reason for Request

The code requirement to disassemble an RCP strictly for visual and volumetric examination has a very small potential for the identifi-cation of service-induced flaws.

This fact is demonstrated when reviewing the results from a number of pump casings examined in the industry at this time. No potentially degrading flaws or indications have been found during these examinations. The inappropriate balance of possible flaw detection and enormous impact on expenditures of Plant manpower does not justify a pump disassembly solely for exami-nation purposes. Also, when reviewing the substantial expenditures of man-rem (potentially on the order of 150-200) and the small potential for finding flaws, justification for these inspections is not warran-ted and is very undesirable due to ALARA concerns. The design and construction of the pump casings greatly reduce any potential for failure in the areas which require inspection by the code; also, the pumps are continually monitored for vibration, bearing temperature, seal flow, and seal flow temperatures. The RCS is also monitored con-tinuously for identified and unidentified leakage, which is computed on a three-day basis by site personnel and is visually inspected prior to startup after refueling. - - -

PGE-1049 3.3.3.4 Alternative Examination As an alternative, the examinations will be performed when pump disas-sembly is required for maintenance purposes. However, a surface exam-ination of the pump casing weld OD shall be performed as a supplement at the end of the inspection interval.

Delay of the required examina-tions will not affect Plant operation.. - -.

PGE-1049 4.0 CLASS 2 COMPONENTS Class 2 components, with thw exception of Categories C-F and C-G com-ponents, have been scheduled in accordance with the regular inspection program outlined in ASME Section II, 1983 Edition, Summer 83 Addenda, Paragraphs IWC-2412 IWC-2420, IWC-2430, AND IWC-2500. Because the application for a construction permit for the T,rojan Nuclear Plant was

. docketed prior to July 1, 1978, the extent of examination for Code Class 2 pipe welds may be determined by the requirements of Paragraph IWC-1220. Table IWC-2520, Category C-F and C-G and Paragraph IWC-2411 in the 197% Edition and Addenda through the Summer 1975 Addenda of Section II of the ASMF Code.

." per 10 CFR 50.55a(b)(iv)(B). The actual welds selected for the Second 10-Year Interval include 100 percent of the welds done during the first 10 years, plus additional welds evaluated as necessary to meet the requirements of IWC-2430. Table 2 lists and quantifies these requirements. Acceptance standards for flaw indications, repair pro-cedures, system pressure tests, and replacements are defined in IWC-3000(*), IWC-4000, IWC-5000, and IWC-7000, respectively. Table 2 lists and quantifies these requirements.

Section 4.1 identifies those system components requiring examination at the Trojan Nuclear Plant. Section 4.2 is a listing of those com-ponents which have been exempted from examination under the provisions of ASME Section XI and other laws regulating operation of a nuclear power generating plant.

• This article is in the course of preparation; the rules of IWB-3000 may be used, l )

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PGE-1049 Title 10, Chapter 1, Code of Federal Regulation - Energy, Part 50, Section 50.55a(g)(iii) states that ".

. If the licensee has deter-mined that conformance with certain code requirements is impractical for his facility, the licensee shall notify the Conunission and submit information to support his determinations." Section 4.3 provides identification of components and information for support of the con-clusions that examination is impractical.

l l.

PGE-1049 4.1 CLASS 2 SYSTEM BOUNDARIES The systems listed below encompass those Class 2 systems which have been addressed in this ISI program:

Updated FSAR System Figure No.

P&ID No.

Reactor Coolant System 5.1-1 M-201 Reactor Coolant System 5.1-la M-201 Residual Heat Removal System 5.4-7 M-205 Safety Injection System 6.3-1 M-206 Containment Spray System 6.5-1 M-207 Spent Fuel Pool Cooling 9.1-4 M-227 and Demineralizer System Component Cooling Water System 9.2-4 M-215 Makeup Water Treatment System 9.2-8 M-228 Instrument and Service Air 9.3-1 M-223 System Process Sampling System 9.3-2 M-231, Sht.1 Chemical and Volume Control 9.3-14 M-202 System 9.3-15 M-203 Chilled Water System 9.4-2 M-248 Main Steam System 10.2-3 M-208 Condensate and Feedwater 10.4-2a M-213, System Sht.2 Steam Generator Blowdown 10.4-8 M-348 System Clean Radioactive Waste 11.2-9 M-220 Treatment System Dirty Radioactive Waste 11.2-14 M-221 Treatment System Radioactive Gaseous Waste 11.3-4 M-222 System -_- -. -.. - - -.-

PGE-1049 Class 2 piping pressure boundaries which require examination under Category C-F are:

(1) 14-in. takeoff line from Valve MO-8701 to Valves MO-8700A and B, and 14-in. supply line from the Refueling Water Storage Tank (RWST) to Valve MO-8812.

(2) Train A:

14-in. suction line from Valve 8700A to Pump P-202A, and recirculation sump 14-in, suction line to Valve 8811A.

(3) Train A:

8-in. discharge line from Pump P-202A to Heat Exchanger E-212A inlet, and 8-in. heat exchanger bypass line to Valve 8726A.

(4) Train A:

8-in. discharge line from Heat Exchanger E-212A outlet to Valve 8716A, 8-and 6-in. low-head injection to Loops 1 and 2 cold legs up to Valves 8818A and B, and 8-in. line to charging pump suction to Valve 8804A.

(5) Train B:

14-in. suction line from Valve 8700B to Pump P-202B, and recirculation sump 14-in suction line to Valve 8811B.

(6) Train B: 8-in discharge line from Pump P-202B to Heat Exchanger E-2128 inlet, and 8-in. heat exchanger bypass line to Valve 8726B.

(7) Train B:

8-in. discharge line from Heat Exchanger E-212B outlet to Valve 8716B, 8-and 6-in. low-head injection to Loops 3 and 4 cold legs up to Valves 8818C and D, 8-in.

line to safety injection pump suction to Valve 8804B, and 8-in. discharge to the Spent Fuel Pool Cooling System (SFPCS) to Valve SF-051..-.

PGE-1049 l

(8) Heat Exchanger 8-in, bypass lines from Valves 8726A and B to Valve HCV-618.

(9) RHR 12-and 8-in, return lines from Valves 8716A and B to check Valves 8736A and B, 8-in. bypass line to Valve HCV-618, and 8-in. discharge to RWST to Valve 8735.

(10) Accumulator lines to Accumulator Tanks T-205A, B, C, and D.

Class 2 piping pressure boundaries which require examination under Category C-G are:

Hain Steam (1) Loop 1:

28-and 32-in. lines from steam generator to non-return check valve, 28-in. safety valve header manifold, 8-and 6-in relief lines to Valve CV-2210, and 6-in. con-densate drain line to 6-x 1-in. reducer.

(2) Loop 2:

28-and 32-in. lines from steam generator to non-return check valve, 28-in. safety valve header manifold, 8-and 6-in. relief lines to Valve CV-2230, and 6-in. con-densate drain line to 6-x 1-in. reducer.

(3) Loop 3:

28-and 32-in. lines from steam generator to non-return check valve, 28-in, safety valve header manifold, 8-and 6-in. relief lines to Valve CV-2250, and 6-in. con-densate drain line to 6-x 1-in. reducer.

(4) Loop 4:

28-and 32-in. lines from steam generator to non-return check valve, 28-in. safety valve header manifold, 8-and 6-in, relief lines to Valve CV-2270, and 6-in. con-densate drain line to 6-x 1-in. reducer.

PGE-1049 Main Feedwater (1) Loop 1:

16-and 14-in, lines from steam generator to check valve.

(2) Loop 2:

16-and 14-in. lines from steam generator to check valve.

(3) Loop 3:

16-and 14-in. lines from steam generator to check valve.

(4) Loop 4:

16-and 14-in lines from steam generator to check valve.

Component Cooling Water (1) CCW 14-in. return line at Penetration P-74 from first weld inside Containment to Valve MO-3346.

(2) CCW 14-in. return line at Penetration P-76 from first weld inside Containment to Valve MO-3290.

(3) CCW 14-in. return line at Penetration P-43 from first weld inside Containment to Valve MO-3292.

(4) CCW '14-in, return line at Penetration P-42 from first weld inside containment to Valve MO-3291.

PGE-1049 4.2 CLASS 2 EXEMPT COMPONENTS 4.2.1 Category C-F and C-G Components Class 2 Category C-F and C-G components for Trojan are exempted from volumetric and surface examinations by Paragraph IWA-1220 1974 Edi-tion, Summer 1975 Addenda according to the following criteria:

(1) Components in systems where both the design pressure and temperature are equal to or less than 275 psig and 200*F, respectively.

(2) Components in systems or portions of systems, other than emergency core cooling systems, which do not function dur-ing normal reactor operation.

(3) Component connections, piping, and associated valves and vessels (and their supports) that are 4-in. nominal pipe size and smaller.

Class 2 components and supports exempted under these guidelines will be visually examined during system hydrostatic pressure tests. The hydrostatic pressure tests will be scheduled to meet the requirements of Paragraph IWC-2412 and to coincide with hydrostatic testing required for system modifications and repairs.

Based on an assumed 40-year plant life, Class 2 components to be examined have been selected in accordance with the provisions for multiple loop systems in Paragraph IWC-2411. _ - _ _

PGE-1049 Class 2 systems (piping and components) which are exempt frma examina-tion by IWC-1220 are:

(1) Reactor Coolant System: All piping identified as Class 2 on P&ID M-201 (Updated FSAR Figures 5.1-1 and 5.1-la) is equal to or less than 4-in. nominal pipe size and is exempted by IWC-1220(d).

(2) Residual Heat Removal System:

Piping not included in Section 4.1 but identified as Class 2 on P&ID M-205 (Updated FSAR Figure 5.4-7) is all less than 4-in. nominal diameter and is exempted by IWC-1220(d).

(3) Safety Injection System (a) The suction piping to the SIS pumps from the RWST has a design temperature of 200'F and a design pressure of 240 psig and is exempted by IWC-1220(a).

(b) The suction piping to the SIS pumps from Valve 8804B in the RHR System has a design temperature of 200*F and a design pressure of 240 psig and is exempted by IWC-1220(a).

(c) All other piping identified as Class 2 on P&ID M-206 (updated FSAR Figure 6.3-1) is equal to or less than l

4-in. nominal diameter and is exempted by IWC-1220(d).

(4) Containment Spray System: The CSS does not perform an l

emergency core cooling function and is not utilized during normal Plant operation; all piping identified as Class 2 on P&ID M-207 (Updated FSAR Figure 6.5-1) is exempted by IWC-1220(b).

l -. - _ _, - -

PGE-1049 (5) Spent Fuel Pool Cooling System: All piping identified as Class 2 on P&ID M-227 (Updated FSAR Figure 9.1-4) is not utilized during normal Plant operation and is exewpted by IWC-1220(b).

(6) Makeup Water Treatment System: Demineralized water supply piping, associated with Penetration P-58, identified as Class 2 on P&ID M-228 (Updated FSAR Figure 9.2-8), is less than 4-in. nominal diameter and is exempted by IWC-1220(d).

(7) Instrument and Service Air System:

Instrument and service air piping, associated with Penetrations P-21 and P-22 and identified as Class 2 on P&ID M-223 (Updated FSAR Figure 9.3-1), is less than 4-in. nominal diameter and is exempted by IWC-1220(d).

(8) Process Sampling System: All piping identified as Class 2 on P&ID M-231 (Updated FSAR Figure 9.3-2) is less than 4-in.

nominal diameter and is exempted by IWC-1220(d).

(9) Piping identified as Class 2 on P&ID M-231 (Updated FSAR Figure 9.3-2) associated with Containment Penetration P-14-1 is less than 4-in. nominal diameter and is exempted by IWC-1220(d).

(10) Chemical and Volume Control System: All piping identified as Class 2 on P&ID M-202 (Updated FSAR Figure 9.3-14),

except as included in Section 4.1, is equal to or less than 4-in. nominal diameter and is exempted by IWC-1220(d).

(11) Chemical and Volume Control System: All piping identified as Class 2 on P&ID M-203 (Updated FSAR Figure 9.3-15) is equal to or less than 4-in. nominal diameter and is exempted by IWC-1220(d). k

PGE-1049 (12) Chilled Water System: Piping associated with Penetra-tions P-57-1 and P-57-2 and identified as Class 2 on P&ID M-248 (Updated FSAR Figure 9.4-2) is equal to or less than 4-in, nominal diameter and is exempted by IWC-1220(d).

(13) Main Steam System: Piping not included in Section 4.1 but identified as Class 2 on P&ID M-208 (Updated FSAR Figure 10.2-3) is all less than 4-in. nominal diameter and is exempted by IWC-1220(d).

(14) Condensate and Feedwater System: Piping not included in Section 4.1, but identified as Class 2 on P&ID M-213, Sheet 2 (Updated FSAR Figure 10.4-2a), is all less than 4-in. nominal diameter and is exempted by IWC-1220(d).

(15) Steam generator blowdown: All piping identified as Class 2 on P&ID M-348 (Updated FSAR Figure 10.4-8) is less than 4-in. nominal diameter and is exempted by IWC-1220(d).

(16) Radwaste piping associated with Penetrations P-17 and P-5-1 and identified as Class 2 on P&ID M-220 (Updated l

FSAR Figure 11.2-9) is less than 4-in. nominal diameter and is exempted by IWC-1220(d).

(17) Containment sump discharge piping at Penetration P-13, identified as Class 2 on P&ID M-221 (Updated FSAR Figure 11.2-14), is less than 4-in. nominal diameter and is exempted by IWC-1220(d).

(18) Pressurizer relief tank and reactor coolant drain tank vent piping at Penetration P-54, identified as Class 2 on P&ID M-222 (Updated FSAR Figure 11.3-4), is less than 4-in. nominal diameter and is exempted by IWC-1220(d). _.. -

PGE-1049 (19) Chemical and Volume Control System: Charging pump suction from 8-x 4-in. reducer in outlet line from Volume Control Tank T-213 to inlets of Pumps P-205A and B and the suction from RHR System to Valve 8804A has a design pressure of 220 psig and a design temperature of 200*F and is exempted by IWC-1220(a).

4.2.2 Class 2 Components (Except Category C-F and C-G)

Class 2 components (except Category C-F and C-G which are covered in Subpargraph 4.2.1) are exempted from volumetric and surface examina-tion by Paragraph IWC-1220 1983 Edition, Summer 1983 Addenda, accord-ing to the following criteria:

(1) Components of systems or portions of systems that during normal Plant operating conditions are not required to operate or perform a system function but remain flooded under static conditions at a pressure of at least 80 per-cent of the pressure that the component or system will be subjected to when required to operate.

(2) Components of systems or portions of systems, other than Residual Heat Removal Systems and Emergency Core Cooling Systems, that are not required to operate above a pressure of 275 psig or above a temperature of 200*F.

(3) Component connections (including nozzles in vessels and pumps), piping and associated valves, and vessels and their attachments that are 4-in. nominal pipe size and smaller...

PGE-1049 Class 2 components which are exempt from examination by IWC-1220 are:

(1) The four Safety Injection System Accumulators (T-205A, B, C, and D) on P&ID M-206 and the eight Main Steam System Accumulators (T-166A, B C, and D and T-157A, B, C, and D) on P&ID M-208 are exempted by IWC-1220(a).

(2) The Boron Injection Tank (T-207) P&ID M-206 FSAR Updated Drawing 6.3-1 is exempted by IWC-1220(a).

Piping support members and piping support components that are encased in concrete shall be exempted from the examination requirements of IWC-2500 per Paragraph IWC-1230. This is the fuel transfer canal on P&ID M-227.

PGE-1049 4.3 RELIEF REQUESTS Under the provisions of 10 CFR 50.55a(g) for taking exception to examination and test requirements which are determined to be impracti-cal, relief is taken from specific ASME Section II (1974 Edition and Addenda through the Summer of 1975) examination requirements.

The general format for relief requests used addresses specific items listed in Appendix B to "NRC Staff Guidance for Complying with Certain Provisions of 10 CFR 50.55a(g), " Inservice Inspection Requirements".

4.3.1 Class 2 Hydrostatic Tests 4.3.1.1 Code Requirement The system hydrostatic test pressure shall be at least 1.10 times the system pressure P,y for systems with design temperature of 200*F or less, and at least 1.25 times the system pressure P,y for systems with design temperature above 200*f.

The system pressure P,y shall be the lowest pressure setting among the number of safety or relief valves provided for overpressure protection within the boundary of the system to be tested. For systems (or portions of systems) not pro-vided with safety or relief valves, the system design pressure Pd shall be substituted for P,y.

4.3.1.2 Code Deviation Request Request relief from the hydrostatic testing requirements of Class 2 piping that cannot be isolated from Class 1 piping.

1 -_ __. _ _ _

PGE-1049 4.3.1.3

Reason for Request

The following lines are Class 1 penetrations into a Class 1 pressure boundary without an isolation valve or other means for isolating the Class 2 system from the Class 1 system for hydrostatic testing. The transition between classes is made by a 3/8-in. diameter orifice con-nection. This hole size restricts flow such that loss of coolant due to severance of one of these lines can be made up by normal charging methods.

(1) Reactor Coolant System (a) Reactor coolant loop flow meter elbow taps for flow transmitters FT-414, -415

-416, -424

-425, -426,

-434, -435, -436, -444, -445, and -446.

(b) Reactor coolant loop resistance temperature detector (RTD) system vent and drain lines (3/4-in.

RC-250lR-17).

(c) RTD system return instrument lines for Flow Indicator Switches FIS-417, -427, -437, and -447.

(d) Reactor coolant loop sampling lines from Loop 1 to manually operated Globe Valve 8056 and from Loop 3 to manually operated Globe Valve 8077 (3/4-in.

RC-250lR-30).

(e) Reactor vessel inner and outer seal monitoring tube piping to manually operated Globe Valves 8069A and 8069B (3/4-in. RC-250lR-15).

(f) Pressurizer spray control valve bypass lines (3/4-in.

RC-250lR-4). -

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(g) Pressurizer inetrument lines for Level Transmitters LT-459, -460, -461, and -462 and Pressure Transmit-ters PT-455, -456, -457, -458, -467A, and 1467B.

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(h) Pressurizer steam sampling I ne from the pressurizer power-operated relief valve piping to manually oper-sted Globe Valves 80f3 and 8094 (3/4-in. RC-2501R-29).

gy (i) Pressurizer liquid campling line froi the pressurizer to manually operated Globe Valve, 8080 (3/4-in.

'- RC-2501R-29).

c (j) Phessurigersafetyvalvesealwaterdrainlinesto manuab.y operated Globe Valve 8093 (3/4-in.

RCi2501R-12).

L (2) Chemical and Volume Control System.

(a) Reactor coolant pump (RCP) seal bypass lines from i

Flow Orifices FO-1957, -1958, -1959, and -1960 to air-operated Globe Valve CV-8142 (3/4-in.

CS-2501$28). -

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's (b) RCP seal.leakof(311nas from the RCP to air-operated s 't Globe Valves CV-814iA, CV-8141B, CV-8141C, and s

[J CV-t,141D (2-ine es!?501R.28).

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(c) RCP seal injection and seal bypass vent and drain

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lines from the Class 1 piping'to manually operated Globe Valveg 8363A, 8363B, 8363C, 8363D, 836AA, 8364B, 8364C, and 8364D..

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PGE-1049 (3) Residual Heat Removal System RHR instrument sensing lines for Pressure Transmit-ters PT-403 and -405.

(4) Safety Injection System (a) Accumulator discharge test line connections (3/4-in.

SI-2501R-22) from the class 1 piping to air-operated Globe Valves CV-8877A, CV-8879A CV-8877B, CV-8879B, CV-8877C, CV-8879C, CV-8877D, and CV-8879D.

(b) Boron Injection Tank T-207 discharge to the RCS cold-less test line connections (1-in. SI-2501R-23 and 3/4-in. SI-250lR-1) from the Class 1 piping to air-operated Globe Valve CV-8882.

(c) SIS Pumps P-203A and P-203B discharr,e'to the RCS loops hot-legs test line connection (3/4-in.

SI-2501R-22) from Class 1 piping to air-operated Globe Valves CV-8889A, CV-8889B, CV-8889C, and CV-8889D.

The components within each line are exempt from volumetric examination under the provisions of IWC-1220(d).

The lines are required to be visually examined during hydrostatic pressure testing by IWC-2500.

Pressurizing the lines to the hydrostatic test pressure required by IWC-5000 would require pressurizing the Class 1 system to a pressure in excess of that required by IWB-5000. Pressurizing the RCS is undesirable because of the limitations on the hydrostatic test pres-sure and the number of hydrostatic test cycles incorporated into the design of the system components (most notably the reactor vessel and fuel assemblies).

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PGE-1049 Class 2 piping systems which are connected to a Class 1 boundary by a check valve oriented for flow into the Class 1 system.

(1) Chemical and Volume Control System (a) Normal chatging line and bypass line (3-in.

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CS-250lR-5 and 3/4-in. CS-250lR-4) from air-operated Globe Valve CV-8146 and manually operated Globe Valve CV-8393 to Check Valve 8378B.

(b) Alternate charging line (3-in. CS-250lR-6) from air-operated Globe Valve CV-8147 to Check Valve 8579B.

(c) RCP seal injection lines (2-in. CS-250lR-28) from manually operated Globe Valves 8352A, 8352B, 8352C, and 8352D to Check Valves 8350A, 8350B, 8350C, and 8350D.

(2)

Residua.'. Heat Removal System (a) RHR return to the RCS cold legs (0-in. SI-250lR-31) from~ motor-operated Gate Valve MO-8809A to Check Valves 8818A and 8818B, and from motor-cperated Gate

, Valve MO-8809B to Check Valves 8818C and 8818D.

l (b) RHR discharge header to RCS Loops 2 and 4 (3/4-in.

I and 19-in. RH-250lR-19) from motor-operated Globe Valve MO-8703 and manually operated Globe Valve CV-8825 to Check Valves 8736A and 8736B.

PGE-1049 Pipelines listed under (1)(a) and(1)(b) are Class 2 piping pressure boundaries Which are part of the letdown return to the RCS and are normally pressurized to RCS pressure. Pipelines listed under (1)(c) are Class 2 piping pressure boundaries on the discharge of the charg-ing pumps and are normally pressurized to RCS operation pressure.

Pipelines listed under (2)(a) and (2)(b) are Class 2 to Class 1 boun-dary change through a check valve.

The pipelines are required to be visually examined during hydrostatic test by Table IWC-2500-1.

Pressurizing the lines to the hydrostatic test pressure required by IWC-5000 would require pressurizing the RCS in excess of that required by IWB-5000 due to the flow direction of the check valve from the Class 2 system to the Class 1 system.

Pres-surizing the RCS is undesirable because of the limitations on the hydrostatic test pressure and the number of hydrostatic test cycles incorporated into the design of the system components (most notably the reactor vessel and fuel assemblies).

4.3.1.4 Alternative Examination Visual examination for evidence of leakage will be conducted on the identified portions of these systems at hydrostatic test pressures in accordance with the requirements of IWB-5222 for the adjoining class 1 systems. Hydrostatic pressure tests will be performed at or near the end of each 10-year inspection interval in accordance with Paragraph IVB-5210.

4.3.2 RHR Heat Exchanger Nozzle-to-Vessel Weld 4.3.2.1 Code Requirement A volumetric and surface examination shall cover 100 percent of the nozzle-to-vessel attachment weld. - - - -

PGE-1049 4.3.2.2 Code Deviation Request Request relief from the volumetric examination of RHR heat exchanger nozzle-to-vessel welds.

4.3.2.3

Reason for Request

The RHR heat exchangers E-212A and E-212B, are of a tube and shell type with the tube side as Class 2.

The RHR system transfers heat from the RCS to the CCWS to reduce and maintain the temperature of the reactor coolant to cold shutdown temperature.

The nozzle-to-vessel welds on the tube side of the heat exchangers are listed in Table IWC-2500-1 Category C-B, Item C2.20 (nozzle-to-vessel welds), with a requirement for volumetric and surface examination.

Table IWC-2500-1, Category C-B (pressure-retaining nozzle welds in vessels), Item No. C2.20, requires examination of 100 percent of the nozzle-to-vessel attachment.

Access for the ultrasonic examination of each RHR heat exchanger nozzle-to-vessel weld is locally restricted by the adjacent vessel supports and tube sheet flange, and examination cannot be performed on 100 percent of the weld. Access for ultrasonic examination is esti-mated at 75 percent of the total weld.

4.3.2.4 Alternative Examination The subject welds will receive a volumetric examination on the acces-sible portions and a 100 percent surface examination as required by Section XI (IWC-2500-1).. -. -- -

PCE-1049 4.3.3 Reactor Coolant Filter 4.3.3.1 Code Requirement The volumetric examinations shall cover 100 percent of each circumfer-ential weld.

4.3.3.2 Code Deviation Request Request relief from the volumetric examination of the reactor coolant filter.

4.3.3.3

Reason for Request

The reactor coolant filter is identified in the Updated FSAR as F-204.

The reactor coolant filter is part of the pressure-retaining Class 2 boundary between the demineralizers and the volume control tank.

Table IWA-2500-1 Category C-A, Item C1.10 (circumferential butt welds), requires 100 percent volumetric examination of the vessel welds.

The thickness (0.165 to 0.185 in.) of the material used to construct this thin-walled pressure vessel is such that the combined " dead zone" and "near-field" effect of the ultrasonic transducer would render ultrasonic examination meaningless.

1 4.3.3.4 Alternative Examination Volumetric examination of these welds will not be performed. Surface and visual examinations of welds on these vessels shall be performed as an alternative method at the frequency and extent required in Table IWC-2500-1 for volumetric examinations. _ _ _.- _--

PCE-1049 4.3.4 Seal Water Heat Exchanger 4.3.4.1 Code Requirement The volumetric examinations shall cover 100 percent of each circumfer-ential weld.

4.3.4.2 Code Deviation Request Request relief from the volumetric examination of the seal water heat exchanger.

4.3.4.3

Reason for Request

The seal water heat exchanger is identified in the Updated FSAR as E-203.

The seal water heater exchanger is part of the pressure-retaining Class 2 boundary between the RCPs and the charging pump suction.

Table IWC-2500-1, Category C-A, Item C1.10 (circumferential butt welds), requires 100 percent volumetric examination of the vessel welds.

The thickness (0.165 to 0.185 in.) of the material used to construct this thin-walled pressure vessel is such that the combined " dead zone" and "near field" effect of the ultrasonic transducer would render ultrasonic examination meaningless.

I 4.3.4.4 Alternative Examination Volumetric examination of these welds will not be performed. Surface and visual examinations of welds on these vessels shall be performed as an alternative method at the frequency and extent required in Table IWC-2500-1 for volumetric examinations.. - - _ _ _ _ _ _.

PGE-1049 4.3.5 Seal Water Return Filter l

4.3.5.1 Code Requirement The volumetric examinations shall cover 100 percent of each circumfer-ential weld.

4.3.5.2 code Deviation Request-Request relief from the volumetric examination of the seal water return filter.

4.2.5.3

Reason for Request

l The seal water return filter is identified in the Updated FSAR as F-209.

The seal water return filter is part of the pressure-retaining Class 2 boundary between the RCPs and the charging pump suction.

Table IWC-2500-1, Category C-A, Item C1.10 (circumferential butt welds), requires 100 percent volumetric examination of the vessel welds.

The thickness (0.165 to 0.185 in.) of the material used to construct this thin-walled pressure vessel is such that the combined " dead zone" and "near-field" effect of the ultrasonic transducer would render ultrasonic examination meaningless.

4.3.5.4 Alternative Examination Volumetric examination of these welds will not be performed.

Surface and visual examinations of welds on these vessels shall be performed as an alternative method at the frequency and extent required in Table IWC-2500-1 for volumetric examinations. -

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

PGE-1049 4.3.6 Reaenerative Heat Exchanaer 4.3.6.1 Code Requirement The volumetric examinations shall cover 100 percent of each circumfer-ential weld.

4.3.6.2 Code Deviation Request Request relief from the volumetric examination of circumferential welds in the regenerative heat exchanger.

4.3.6.3

Reason for Request

The regenerative heat exchanger (RHX) is identified in the Updated FSAR as E-206.

The RHX is pressure-retaining boundary in the CVCS.

It is used for heat transfer to reduce reactor coolant temperature prior to purification and to preheat the reactor coolant prior to its return to the reactor coolant loops. Table IWC-2500-1, Item C1.10 (circumferential butt welds), requires 100 percent volumetric examina-tion of the circumferential welds.

Exception to full volumetric examination of the welds on the RHX is taken, as only a straight-beam scan can be performed.

The RHI is a cast component; therefore, the calibration block for this component is also cast to the same specification and of the same material as the RHX.

During ISI for refueling core outage (I-II) per-formed from March 17, 1978 through May 24, 1978, it was reported that the calibration block caused metallurgical noise signals that preven-ted angle beam calibration. The limited volumetric examination (straight beam only) was therefore supplemented by the addition of a surface examination.

PGE-1049 4.3.6.4 Alternative Examination The welds in the cast RHI shall be ultrasonically examined by the straight-beam method and supplemented by surface examination. The examination frequency shall be as required by Table IWB-2500-1 volu-metric examination of this component. -

PGE-1049 5.0 CLASS 3 COMPONENTS Class 3 components have been scheduled fcr examination in accordance with the regular inspection program outlined in ASME Section XI, Para-graph IWD-2400. Table 3 lists and quantifies these requirements.

Acceptance standtrds for flaw indications, repair procedures, system pressure tests, and replacements are defined in IWD-3000(*), IWD-4000, IWD-5000, and IWD-7000, respectively.

Section 5.1 identifies those components requiring examination at the Trojan Nuclear Plant. These are found in Table 3.

Section 5.2 is a listing of those components which have been exempted from examination under the provisions of ASME Section II and other laws regulating operation of a nuclear power generating plant.

Title 10 Chapter 1 Code of Federal Regulation Energy, Part 50, Section 50.55a(g)(iii) states that ".

If the licensee has deter-mined that conformance with certain code requirements is impractical for his facility, the licensee shall notify the Commission and submit information to support his determinations." Section 5.3 provided identification of components and information for support of the con-clusions that examination is impractical.

• Article being prepared. The rules of IWB-3000 may be used.

-4R-

PGE-1049 5.1 CI. ASS 3 SYSTEM BOUNDARIES The systems listed below encompass those Class 3 systems which have been addressed in this ISI program:

Updated FSAR System Figure No.

P&ID No.

Reactor Coolant System 5.1-1 M-201 Reactor Coolant System 5.1-la M-201 Residual Heat Removal System 5.4-7 M-205 Safety Injection System 6.3-1 M-206 Containment Spray System 6.5-1 M-207 Spent Fuel Pool Cooling 9.1-4 M-227 and Demineralizer System Service Water System 9.2-1 M-218 Component Cooling Water System 9.2-4 M-215 Process Sampling System 9.3-2 M-231, Sht. 1 9.3-4 M-231, Sht. 3 Chemical and Volume Control 9.3-14 M-202 System 9.3-15 M-203 9.3-16 M-204 Diesel Fuel Oil System 9.5-3 M-226 Main Steam System 10.2-3 M-208 Circulating Water and Turbine 10.4-1 M-216 Building Cooling Water System Condensate and Feedwater 10.4-2 M-213, System Sht. 1 10.4-2a M-213, Sht. 2 Auxiliary Steam System 10.4-3 M-214 Dirty Radioactive Waste 11.2-14 M-221 Treatment System Radioactive Gaseous Waste 11.3-4 M-222 System ___ _. -

PGE-1049 5.2 CLASS 3 EXEMPT COMPONENTS Per IWD-1220, items exempt from examination:

Integral attachments of supports and restraints to components that are 4-in nominal pipe size and smaller within the system boundaries of Examination Categories D-A, D-B, and D-C of Table IWD-2500-1 shall be exempt from the visual examination VT-3, except for Auxiliary Feedwater Systems.

Integral attachments of supports and restraints to components exceeding 4-in. nominal pipe size may be exempted from the visual examination VT-3 of Table IWD-2500-1 provided:

(a) The components are located in systems (or portions of systems) whose function is not required in support of reactor residual heat removal, containment heat remo-val, and emergency core cooling; and (b) The components operate at a pressure of 275 psig or less and at a temperature of 200*F or less...

PGE-1049 Class 3 systems (piping and components) which are exempt from examination by IWD-1220 are:

Updated FSAR System Figure No.

P&ID No.

Process Sampling System 9.3-2 M-231, Sht. 1 M-231, Sht. 3 Chemical and Volume control 9.3-14 M-202 System 9.3-15 M-203 9.3-16 M-204 Diesel Fuel Oil System 9.5-3 M-226 Main Steam System 10.2-3 M-208 Circulating Water and 10.4-1 M-216 Turbine Auxiliary Steam System 10.4-3 M-214 Dirty Radioactive Waste 11.2-14 M-221 Treatment System Radioactive Gaseous Waste 11.3-4 M-222 System

PGE-1049 5.3 CLASS 3 RELIEF REQUESTS Under the provisions of 10 CFR 50.55a(s) for taking exception to examination and test requirements which are determined to be impract-ical, relief is taken from specific ASME Section XI (1974 Edition and Addenda through the Summer of 1975) examination requirements.

The general format for relief requests addresses specific items listed in Appendix B to "KRC Staff Guidance for Complying with Certain Pro-visions of 10 CFR 50.55a(s) ' Inservice Inspection Requirements'".

5.3.1 Inaccessible Components 5.3.1.1 Code Requirements Table IWD-2500-1 requires VT-2 examination of 100 percent of the sys-tems in support of Reactor Shutdown Function (Category D-A); Emergency Core Cooling, Containment Heat Removal, Atmosphere Cleanup, and Reactor Residual Heat Removal (Category D-B); and Residual Heat Remo-val From Spent Fuel Storage Pool (Category D-C).

5.3.1.2 Code Deviation Request Request relief from the visual examination of:

(1) Diesel oil storage tanks (T-119A and B), diesel oil transfer pumps (P-144A and B), and portions of the associated piping as shown in Isometrics HBD-72-1, HBD-72-2, HBD-72-3, HBD-72-4, HBD-72-50, and HBD-72-51.

52-r

-.--.-------._----y

---...-,,y.

y.---.

y 5y

PGE-1049 (2) Service water pumps (P-108A, B, and C) and portions of the associated piping as shown in Isometrics HBD-52-3, HBD-52-5, HFD-1-1 HFD-1-2, HFD-1-3, HFD-1-4, HFD-2-2, NFD-2-3, HFD-3-2, HFD-3-3, HFD-4-1, KFD-4-2, HFD-4-3, HFD-4-10, NFD-4-50 HFD-5-1, HFD-5-2, HFD-5-3, HFD-5-10, HFD-5-50, HFD-6-1, HFD-7-2, MFD-7-3, and HFD-8-1.

(3) Containment spray pump suction line from the refueling water storage tank (RWST) (T-206) as shown in Isometric SI-151R-10-1.

5.3.1.3

Reason for Request

(1) The diesel oil storage tanks (T-119A and B) and portions of the associated piping are either buried underground or in con-crete. The diesel oil transfer pumps (P-144A and B) are sub-merged in the diesel oil storage tanks (T-119A and B).

These areas cannot be seen by the examiner while the system is in operation or undergoing system testing.

(2) The service water pumps (P-108A, B, and C) and portions of the associated piping are buried underground, buried in concrete, or submerged in water. The piping from the discharge of the service water pumps (P-108A, B, and C), as shown in Isometric HFD-1-4, is submerged in water at the intake struc-ture. This area cannot be seen by the examiner while the sys-tem is in operation or undergoing system testing.

(3) The Containment spray pumps (P-204A and B) suction line from the refueling water storage tank (RWST) (T-206), as shown in Isometric SI-151R-10-1, is buried underground. This area can-not be seen by the examiner while the system is operating or undergoing system testing..

=. _ - _.

~

PCE-1049 i

5.3.1.4 Alternative Examination (1) The examination to locate evidence of leakage in diesel fuel oil components will be performed by verifying that the flow l

of diesel fuel oil during operations is not impaired. Veri-l fying that the flow of diesel fuel oil is not impaired is performed on a monthly basis during plant tests of the diesel fuel oil system.

l 1

(2) The examination to locate evidence of leakage in the Service Water System is performed by verifying that the flow of j

service water during operation is not impaired. Verifying that the flow of service water is not impaired is performed on a monthly basis during plant tests of the Service Water System.

(3) The examination to locate evidence of leakage in the Con-tainment spray pumps suction line is performed by verifying that flow from the RWST during operation is not impaired.

Verifying that the flow of water is not impaired is per-1 formed on a monthly basis during plant tests of the Contain-ment Spray System.

i i

f i

i i

i 4

PGE-1049 6.0 COMPONENT SUPPORTS Class 1, 2, and 3 component supports have been scheduled for exami-nation in accordance with the regular inspection program outlined in ASME Section II, Paragraph IWF-1200. Acceptance standards for exami-nation evaluations, repair procedures, inservice test requirements, and replacements are defined in Paragraphs IWF-3000, IWF-4000, IWF-5000, and IWF-7000, respectively. Tables 4, 5, and 6 list and quantify these requirements for components not exempted by Paragraph IWF-1230.

Section 6.1 is a listing of those components which have been exemptid from examination under the provisions of ASME Section II and other laws regulating operation of a nuclear power generation plant.

t J - - _ _ _ _ _ _,

PCE-1049 6.1 EXEMPT COMPONENT SUPPORTS Selected Class 1, 2, and 3 component supports are exempted from exam-ination according to the following criteria (*):

Class 1 Supports on piping and related components NPS 1 inch and smaller.

. Supports on NPS 2 inches and smaller reactor vessel head piping made inaccessible by control rod drive penetrations.

Class 2

. Supports for piping and components NPS 4 inches and smaller except for supports in the High Pressure Safety Injection System.

. Supports for piping and components of any size that operate at a pressure equal to or less than 275 psig and at a temperature equal to or greater than 200*F in systems other than RHR, ECC, and CHR.

. Supports for the safety injection tank and associated systems.

. Supports of piping and other components of any size beyond the last shutoff valve in open-ended portions of systems.,

PGE-1049 Class 3

. Supports for components NPS 4 inches and smaller, except for the Auxiliary Feedwater System.

i

. Supports for Auxiliary Feedwater System NPS 1 inch and smaller.

. Supports for piping and components exceeding NPS 4 inches where:

a.

The components and piping are located in systems whose function is not required to support reactor residual heat removal, containment heat removal, and emergency core

cooling, b.

The components and piping operate at a pressure of 275 psig

r less and a temperature of 200*F or less.

• ASME Section II, 1983 Edition, Summer 83 Addenda:

IWF-1230

" Supports Exempt From Examination and Test" is in the course of preparation. i

PGE-1049 6.2 IWF RELIEF REQUESTS No relief reques*s at this time.

c AW/rp 3991C PEE-1049 Page 59 TABLE 1 INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Reactor Vessel (T-201)

Extent of Exmination Exa.

Method of Itan No.

Cat.

rw t Identification Exmination 1st Period 2nd Period 3rd Period Rem rks 81.10 B-A Shell Welds 81.11 8-A Circtsuferential Voltanetric 1 Beltline Region Weld 21.12 B-A Longitudinal Volumetric 1 Beltline Region Weld 81.20 B-A Head Welds 81.21 IWL Circunderential Voltanetric Accessible length of I weld 81.22 B-A Meridional Voltanetric Accessible length of I weld 81.30 B-A Shell-to-Flange Weld Voltanetric 501 of I weld Renaining weld 81.40 B-A Head-to-Flange Weld Voltanetric SOE of I weld Remaining weld and surface 81.50 B-A Repair Welds 81.51 B-A Beltline Region N/A See Note 1

PGE-1049 Page 60 TABLE 1 I

INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Reactor vessel (T-201)

Extent of Ex mination Eman.

Method of Iten It).

Cat.

rr=panent Identification Exmination 15t Period 2nd Perlod 3rd Period Renerks B3.90 B-D Nozzle-to-Wessel Welds (8)

Voltanetric 1005 of 2 nozzles 1001 of 2 nozzles 100% of 4 nozzles B3.100 B-D Nozzle Inside Radius Section (8)

Voltanetric 100E of 2 nozzles 1001 of 2 nozzles 1001 of 4 nozzles B4.10 B-E Partial Penetration Welds 84.11 8-E Vessel Nozzles (1)

Visual, VT-2 one 84.12 B-E Control Rod Drive Nozzles (78)

Visual, VT-2 20 B4.13 B-E Instrumentation Nozzles (58)

Visual, VT-2 15 See Relief Request 3.3.1 I

i B5.10 B-F Maninal Pipe Size > 4 in. (8)

Voltanetric 2 welds 2 welds 4 welds Nozzle-to-Safe End Butt Welds and Surface 85.20 B-F Naminal Pipe Size < 4 in.

N/A See Note 2 l

Nozzle-to-Safe End Butt Welds 85.30 B-F Nozzle-to-Safe End Socket Welds N/A See Note 3 i

86.10 B-G-1 Closure Head Nuts (54)

Surface 18 nuts 18 nuts 18 nuts 96.20 B-G-1 Closure Studs, in place (54)

Volisnetric 18 studs 18 studs 10 studs B6.30 B-G-1 Closure Studs, when renoved (54)

Surface and 18 studs 18 studs 18 studs Volisertric

PGE-1049 Page 61 TABLE 1 INSERVIE INSPECTION PROGRAM CLASS 1 COMPONENTS Reacter vessel (T-201)

Extent of Ex mination Exm.

Method of Itsen No.

Cat.

r=panent Identification Em mination 1st Period 2nd Period 3rd Period Reserks 86.40 8-G-1 Threads in Flange (54)

Volumetric 18 stud holes 18 stud holes 18 stud holes 86.50 8-G-1 Closure Washers, Bushings (54)

Visual, VT-1 18 washers 18 washers 18 washers 87.10 8-G-2 Bolts, Studs, and Nuts (54)

N/A See Note 4 87.80 8-G-2 CRD Housings Visual, VT-1 6 bolts 6 bolts 6 bolts Bolts, Studs, and Nuts (18) j leen Dissembled 4

88.10 8-H Integrally Welded Attactunents N/A Sce Note 5 813.10 8-N-1 Wessel Interior Visual, VT-3 100E of accessible 1005 of accessible 1001 of accessible areas areas areas i

i 813.50 8-N-2 Interior Attactunents Within Visual, VT-1 100E of accessible Beltline Region welds j

813.60 8-N-2 Interior Attactunents Beyond Visual, VT-?

1001 of accessible Beltline Region welds 813.70 8-N-3 Core S w t Structure Visual, VT-3 1001 of accessible surfaces l

i

PEE-1049 Page 62 TABLE 1 INSERVICE INSPECTION PROGIMI CLASS 1 00MOENTS Reactor vessel (T-201)

Extent of Ex mination Exa.

Method of Itan No.

Cat.

W t Identification Ex mination 1st Period 2nd Period 3rd Period Remarks 814.10 B-O Welds in DID Housing (78)

Voltanetric 3 peripheral (29 Peripheral) or Surface housings 815.10 B-P Pressure Retaining Boundary Visual, VT-2 Each refueling Each refueling Each refueling outage outage outage 815.11 8-P Pressure Retaining Boundary Visual, VT-2 One test l

PGE-1049 Pa p 63 TAetE I INSERVIE INSPECTION PROGRAM CLASS 1 COMPONENTS Pressurizer (T-202)

Extent of Exmination Exasm.

Method of Iteen No.

Cat.

Ctzgonent Identification Exasnination 1st Period 2nd Period 3rd Period Remarks 82.10 8-8 Shell-to-Head Welds 82.11 8-8 Circtsaferential (2)

Voltanetric 1005 of I weld 1005 of I weld B2.12 8-8 Longitudinal (2)

Voltanetric 1 ft of I weld I ft of I weld B2.20 B-8 Head Welds 82.21 8-8 Circtsaferential N/A See Note 6 82.22 8-8 Meridional N/A See Note 7 B3.110 8-D mzzle-to-Vessel Welds (6)

Voltanetric 1001 of 2 welde 1001 of 2 welds 1005 of 2 welds B3.120 B-D Nozzle Inside Radius Section Volumetric 1001 of 2 nozzles 100% of 2 nozzles 1005 of 2 nozzles 84.20 8-E Heater Penetration Welds (78)

Visual, VT-2 All welds 85.40 B-F Naninal Pipe Size > 4 in. (6)

Volumetric 1005 of 2 welds 100% of 2 welds 1001 of 2 welds Nozzle-to-Safe End Butt Welds and surface 85.50 8-F Naninal Pipe Size < 4 in.

N/A See Note 2 Nozzle-to-Safe End Butt Welds 85.60 B-F Nozzle-to-Safe End Socket Welds N/A See Note 3

=

PGI-1049 Page 64 TABLE 2 INSERVI & INSPECTION PROGRAM CLASS 2 (XIMPONENTS Pressurizer (T-202)

Extent of Exmination Exm.

Method of Iten163.

Cat.

rw t Identification Exmination 1st Period 2nd Period 3rd Period Renerks 86.60 B-G-1 Bolts and Studs N/A See Note 8 86.70 B-G-1 Flange Surface, when N/A See Note 8 connection disassest>1ed 86.80 B-G-1 Nuts, Bushings, and Washers N/A See Note B B7.20 B-G-2 Bolts, Studs, and Nuts (16)

Visual, VT-1 5 bolts 5 bolts 6 bolts B8.20 B-H Integrally Welded Attachments Volumetric 100% of weld Support Skirt or surface, as applicable B15.20 B-P Pressure Retaining Boundary Visual, VT-2 Each refueling Each refueling Each refueling outage outage outage B15.21 B-P Pressure Retaining Boundary Visual, VT-2 One test I

l PGE-1049 Pa y 65 TABLE 1 INSERVICE INSPECTION PROGRAM CLASS 1 @ MPONENTS SQem Generators (E-201A, E-201B, E-201C, and E-201D)

Extent of Exmination Exam.

Method of Iten No.

Cat.

Camponent Identification Examination 1st Period 2nd Period 3rd Period Remarks B2.30 B-B Head Welds B2.31 B-B Circtsaferential N/A See Note 6 82.32 B-B Meridional N/A See Note 7 B2.40 B-B Tubesheet-to-Head Weld Volumetric 1 Weld B3.130 B-D Nozzle-to-Vessel Weld N/A See Note 9 B3.140 B-D Nozzle Inside Radius Section Voltanetric 1001 each SG See Relief Request 3.3.2 85.70 B-F Nominal Pipe Size > 4 in. (8)

Voltsnetric 3 welds 3 welds 2 welds Nozzle-to-Safe End Butt Welds and Surface 85.00 B-F Nominal Pipe Size < 4 in.

j Nozzle-to-Safe End Butt Welds N/A See Note 2 85.90 B-F Nozzle-to-Safe End Socket Welds N/A See Note 3 86.90 B-G-1 Bolts and Studs N/A See Note 8 i

i

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i PGE-1049 1

Page $

, {'

-3 TABLE 1

/

' ' ls ',

1 INSUWi2 INSPECTIO4 PYIOr##

4, CLAS51 b3ffFENTS

' s "x

,} s 1

x 5 team Gererators (E-201A, E-2018. E-201C, and E-201D)

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Eater.t of Ezmination a~ ')

Exam.

Mettext of 1

Iteen No.

Cat.

,_Ctsgurient Identification

'_Lumination 1st Period 2nd Pericd.

7tti Period '

~

Runerks

'/

\\

See Note 8

- 96.171 B-G-1 Flange Surface, When N/A

' ~

Connection Disassembled s

4

,~

1

/.

B6.110 A-G-1 Ets, Bushings, and Washers N/A,

~

I

' 'de Note 8

-N i

s 48 bolts

, ; /.ohlt 32 bcits 87.33 M-2 Bolts, Studs, and Nuts (128)

Visual, VT-1 '

l:

88.30 B-H Integrally Welded Attictaments N/A Sea Note 5 '

815.30 B-P Prtssure Retaining Boundary Visual, VT-2 Each rs'aeling,

Each refuelire, Each nfueling

"' e r. age 1 cutage outage

-a 815.31 8-P Pressure Retaining Boundary Visual, VT-2 One test, i

816.20 B-Q 5 team Generator Tubing in Volumetric tPer Tech. SM G 4.4.5 C4 Tube Design e.,

.?

J g

m h

k o

f

PGE-1049 Page 67 TABLE 1 INSERVICE INSPECTION PROGRAM CLASS 1 (DNPONENTS Heat Exchangers Extent of Examination Exm.

Method of It m No.

Cat.

Congonent Identification Examination 1st Period 2nd Period 3rd Period Remarks B2.50 B-B Head Welds B2.51 B-B Circumferential N/A See Note 10 B2.52 B-B Meridional N/A See Note 10 B2.60 B-B Tubesheet-to-Head Welds N/A See Note 10 B2.70 B-B Longitudinal Welds N/A See Note 10 82.00 B-B Tubesheet-to-Shell Welds N/A See Note 10 B3.150 B-D Nozzle-to-Vessel Welds N/A See Note 10 83.160 B-D Nozzle Inside Radius Section N/A See Note 10 85.100 B-F Nominal Pipe Size > 4 in.

N/A See Note 10 Nozzle-to-Safe End Butt Welds B5.110 B-F Nominal Pipe Size < 4 in.

N/A See Note 10 Nozzle-to-Safe End Butt Welds n

PE-1049 -

Page 68 TABLE 1 INSERVICE INSPECTION PROGRAM CLAS5 1 (X)MPONENTS Heat Exchangers Extent of Exmination Item No.

Cat.

Component Identification

_Ex mination 1st Period 2nd Period 3rd Period Remarks B5.120 B-F Nozzle-to-Safe End Socket Welds N/A

~

See Wote 10' B6.120 B-G-1 Bolts and Studs N/A See Note 10 B6.130 B-G-1 Flange Surface, When N/A See Note 10 Connection Disassenbled B6.140 B-G-1 Nuts, Bushings, and Washers N/A See Note 10 B7.40 B-G-2 Bolts, Studs, and Nuts N/A See Note 10 88.40 B-H Integrally Welded Attachments N/A See Note 10 B15.40 B-P Pressure Retaining Boundary N/A See Note 10 B15.41 B-P Pressure Retaining Boundary N/A See Note 10

PGE-1049 Page 69 TABLE 1 INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Piping Extent of Examination Exam.

MPthod of Iteun No.

Cat.

Camponent Identification Exmination 1st Period 2nd Period 3rd Period Remarks B5.130 B-F Ntzninal Pipe Size 14 in.

N/A See Note 11 Dissimilar Metal Butt Welds 85.140 B-F Nominal Pipe Size < 4 in.

N/A See Note 11 Dissimilar Metal Butt Welds 85.150 B-F Dissimilar Metal Socket Welds N/A See Note 12 B6.150 B-G-1 Bolts and Studs N/A See Note 8 B6.160 B-G-1 Flange Surface, when connection N/A See Note 8 disassenbled B6.170 B-G-1 Nuts, Bushings, and Washers N/A See Note 8 B7.50 B-G-2 Bolts, Studs, and Nuts (148)

Visual, VT-1 52 bolts 48 bolts 48 bolts 89.10 B-J Nominal Pipe Size 1 4 in.

B9.11 B-J Circumferential Welds (456)

Surface and 38 welds 38 welds 38 welds voltanetric B9.12 B-J Longitudinal Welds N/A See Note 13

PK-1049 Page 70 TABLE 1 INSERVICE INSPECTION PROGRAN CLASS 1 COMPONENTS Piping Extent of Examination Exam.

Nethod of Iten No.

Cat.

Caponent Identification Examination ist Period 2nd Period 3rd Period Renerks 89.20 B-J Nominal Pipe Size < 4 in.

89.21 B-J Circumferential Welds (202)

Surface 17 welds 17 welds 17 welds 89.22 B-J Longitudinal Welds N/A See Note 13 B9.30 B-J Branch Pipe Connection Welds 89.31 B-J Nominal Pipe Size > 4 in. (11)

Surface and I weld I weld I weld voltanetric 89.32 B-J Nominal Pipe Size < 4 in. (23)

Surface 2 welds 2 welds 2 welds 89.40 B-J Socket Welds (509)

Surface 43 welds 43 welds 42 welds B10.10 B-K-1 Integrally Welded Attachments Volumetric 6 welded 7 welded 7 welded (20) or surface, attactunents attactunents attachments as applicable B15.50 B-P Pressure Retaining Boundary Visual, VT-2 Each refueling Each refueling Each refueling outage outage outage B15.51 8-P Pressure Retaining Boundary visual, VT-2 One test

PGE-1049 Page 71 TABLE I INSERVICE INSPECTION PROGRAM CLASS 1 QMPONENTS Punps (P-201A, P-201B, P-201C, and P-201D)

Extent of Exmination Exam.

Method of Iten No.

Cat.

Component Identification Examination 1st Period 2nd Period 3rd Period Renarks 86.100 B-G-1 Bolts and Studs (24 each punp)

Volumetric 24 bolts 24 bolts 48 bolts 86.190 B-G-1 Flange Surface, When Connection Visual, VT-1 1 pump 1 punp 2 pups Disassenbled B6.200 B-G-1 Nuts, Bushings, and Washers Visual, VT-1 24 bolts 24 bolts 48 bolts (24 each pop)

B7.60 B-G-2 Bolts, Studs, and Nuts Visual, VT-1 12 bolts 12 bolts 24 bolts (12 each pump) 810.20 B-K-1 Integrally Welded Attachments N/A See mote 5 B12.10 B-L-1 Punp Casing Welds Volumetric 1 weld See Relief Request 3.3.3 (1 each pa p)

B12.20 B-t-2 Pep Casing Visual, VT-3 1 casing See Relief Request 3.3.3 B15.60 B-P Pressure Retaining Boundary Visual, VT-2 Each refueling Each refueling Each refueling outage outage outage B15.61 B-P Pressure Retaining Boundary Visual, VT-2 One test

PGE-1049 Page 72 TABLE _1 INSERVICE INSPECTION PROGRAM CLASS 1 @MPONENTS Valves Extent of Exmination Exam.

Method of

-3 tem No.

Cat.

Cannonent Identification Examination 1st Period 2nd Period 3rd Period Renarks 86.210 B-G-1 Bolts and Studs N/A See Note 8 B6.220 B-G-1 Flange Surface, When Connection N/A See Note 8 Disassenbled B6.230 B-G-1 Nuts, Bushings, and Washers N/A See Note 8 B7.70 B-G-2 Bolts, Studs and Nuts (%4)

Visual, VT-1 106 bolts 168 bolts 210 bolts B10.30 B-K-1 Integrally Welded Attachments N/A See Note 5 B12.30 B-M-1 Valves, Nominal Pipe Size < 4 i N/A See Note 14 Valve Body Welds B12.40 B-M-1 Valves, Naminal Pipe Size > 4 i N/A See Note 14 Valve Body Welds B12.50 B-M-2 Valve Body, Exceeding 4 in. (27)

Visual, VT-3 6 valves Nominal Pipe Size B15.70 B-P Pressure Retaining Boundary Visual, VT-2 Each refueling Each refueling Each refueling outage outage outage B15.71 B-P Pressure Retaining Boundary Visual, VT-2 One test l

PGE-1049 Page 73 TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 (XMPONENTS Stem Generators (E-201A, E-2018. E-201C, and E-2010)

Extent of Examination Exam.

Method of Iten No.

Cat.

Camponent Identification Examination 1st Period 2nd Period 3rd Period Remarks l

C1.10 C-A Shell Circtsaferential Welds Volumetric 1 weld I weld I weld Cl.20 C-A Head Circtsnferential Welds Voltsnetric 1 weld C1.30 C-A Tubesheet-to-Shell Weld Volumetric 1 weld C2.10 C-8 Nozzles in vessels $ 1/2 in.

Nominal Thickness C2.11 C-B Nozzle-to-Shell (or Head) Weld N/A See Note 15 C2.20 C-8 Nozzles Without Reinforcing Plate in Vessels > 1/2 in.

Nominal Thickness C2.21 C-B Nozzle-to-Shell (or Head) Weld Surface and I weld I weld volumetric C2.22 C-B Nozzle Inside Radius Section Voltanetric 1 weld I weld

PGE-1049 Page 74 TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 (DMPONENTS Stem Generators (E-201A, E-201B, E-201C, and E-201D)

Extent of Examination Exam.

Method of Item No.

Cat.

Camonent Identification Examination 1st Period 2nd Period 3rd Period Remarks C2.30 C-8 Nozzles With Reinforcing Plate in vessels > 1/2 in. Nominal Thickness C2.31 C-B Reinforcing Plate Welds to N/A See Note 16 Nozzle and Vessel C2.32 C-8 NO221e-to-Shell (or Head) Welds N/A See Note 16 When Inside of Vessel Is Accessible C?.33 C-8 Nozzle-to-Shell (or Head)

N/A See Note 16 When Inside of Vessel Is Inaccessible C3.10 C-C Integrally Welded Attachments N/A See Note 5 C4.10 C-D Bolts and Studs N/A See Note 8 C7.10 C-H Pressure Retaining Conponents Visual, VT-2 One test One test One test C7.20 C-H Pressure Retaining Conponents Visual, VT-2 One test

PGE-1049 Page 75 TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 CONPONENTS Excess Letdown Heat Exchanger (E-208)

Extent of Exmination Exam.

Method of Iten No.

Cat.

Component Identification Exmination 1st Period 2nd Period 3rd Period Renerks C1.10 C-A Shell Circumferential Welds N/A See Note 17 C1.20 C-A Head Circtseferential Welds Volumetric 1 weld C1.30 C-A Tubesheet-to-Shell Weld N/A See Note 18 C2.10 C-8 Nozzles in Vessels $ 1/2 in.

Nominal Thickness C2.ll C-8 Nozzle-to-Shell (or Head) Weld N/A See Note 15 C2.20 C-8 Nozzles Without Reinforcing Plate in Vessel > 1/2 in.

Nominal Thickness C2.21 C-8 Nozzle-to-Shell (or Head) Weld N/A See Note 19 C2.22 C-8 Nozzle Inside Radius Section N/A See Note 19

PGE-1049 Page 76 TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS Excess Letdown Heat Exchanger (E-208)

Extent of Exmination Exam.

Method of It m No.

Cat.

Component Identification Examination 1st Period 2nd Period 3rd Period Remarks C2.30 C-8 Nozzles With Reinforcing Plate in Vessels > l/2 in. Nominal Thickness C2.31 C-8 Reinforcing Plate Welds to N/A See Note 16 Nozzle and Vessel C2.32 C-B Nozzle-to-Shell (or Head) Welds N/A See Note 16 When Inside of Vessel Is Accessible C2.33 C-B Nozzle-to-Shell (or Head)

N/A See Note 16 When Inside of Vessel Is Inaccessible C3.10 C-C Integrally Welded Attachments N/A See Note 5 C4.10 C-D Bolts and Studs N/A See Note 8 C7.10 C-H Pressure Retaining Conponents Visual, VT-2 One test One test One test C7.20 C-H Pressure Retaining Conponents Visual, VT-2 One test

PE-1049 Page 77 TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS Residual Heat Exchangers (E-212A and E-2128)

Extent of Examination Exam.

Method of Iten No.

Cat.

Cog onent Identification Examination 1st Period 2nd Period 3rd Period Remarks i

C1.10 C-A Shell Circumferential Welds Volumetric 1 weld C1.20 C-A Head Ciretaferential Welds Volumetric 1 weld C1.30 C-A Tubesheet-to-Shell Weld N/A See Note 18 C2.10 C-8 Nozzles in Vessels $ 1/2 in.

Nominal Thickness C2.ll C-B Nozzle-to-Shell (or Head) Weld N/A See Note 15 C2.20 C-B Nozzles Without Reinforcing Plate in Vessels > 1/2 in.

Nominal Thickness C2.21 C-B Nozzle-to-Shell (or Head) Weld Surface and 2 welds See Relief Request 4.3.2 voltmetric C2.22 C-B Nozzle Inside Radius Section N/A See Note 20 1

PGE-1049 Page 78 TABLE 2 INSERVIE INSPECTION PROGRAM CLASS 2 COMPONENTS Residual Heat Exchangers (E-212A and E-2128)

Extent of Examination Exam.

Method of Iten No.

Cat.

Congonent Identification Examination 1st Period 2nd Period 3rd Period Renarks C2.30 C-B Nozzles With Reinforcing Plate in Vessels > l/2 in. Nominal Thickness C2.31 C-8 Reinforcing Plate Welds to N/A See Note 16 Nozzle and Vessel C2.32 C-B Nozzle-to-Shell (or Head) Welds N/A See Note 16 When Inside of Vessel Is Accessible C2.33 C-B Nozzle-to-Shell (or Head)

N/A See Note 16 When Inside of Vessel Is Inaccessible C3.10 C-C Integrally Welded Attachments Surface 100% of 2 support attacionents C4.10 C-D Bolts and Studs N/A See Note 8 l

C7.10 C-H Pressure Retaining Conponents Visual, VT-2 One test One test One test C7.20 C-H Pressure Retaining Caponents Visual, Vt-2 One test

PGE-1049 Page 79 TABLE 2 INSERVICE INSPECTION PROGRAN CLASS 2 COMPONENTS Seal Water Heat Exchanger (E-203)

Extent of Examination Exam.

Method of Item No.

Cat.

Camonent Identification Examination 1st Period 2nd Period 3rd Period Remarks C1.10 C-A Shell Circumferential Welds Volumetric 1 weld See Relief Request 4.3.4 C1.20 C-A Head Circtmferential Welds Volumetric 1 weld See Relief Request 4.3.4 C1.30 C-A Tubesheet-to-Shell Weld N/A See Note 18 C2.10 C-8 Nozzles in Vessels < 1/2 in.

Nominal Thickness C2.ll C-B Nozzle-to-Shell (or Head) Weld N/A See Note 15 C2.20 C-B Nozzles Without Reinforcing Plate in Vessels > 1/2 in.

Nominal Thickness C2.21 C-B Nozzle-to-Shell (or Head) Weld N/A

- See Note 19 C2.22 C-8 Nozzle Inside Radius Section N/A See Note 19 i

l 4

PGE-1049 Page 80 TABLE 2 INSERVI INSPECTION PROGRAF.

CLASS 2 COMPONENTS Seal Water Heat Exchanger (E-203)

Extent of Examination Exam.

Method of Item No.

Cat.

Component Identification Examination 1st Period 2nd Period 3rd Period Remarks C2.30 C-B Nozzles With Reinforcing Plate in Vessels > 1/2 in. Nominal Thickness C2.31 C-B Reinforcing Plate Welds to N/A See Note 16 Nozzle and Vessel C2.32 C-B Nozzle-to Shell (or Head) Welds N/A See Note 16 W en Inside of vessel Is Accessible C2.33 C-B Nozzle-to-Shell (or Head)

N/A See Note 16 When Inside of Vessel Is Inaccessible C3.10 C-C Integrally Welded Attachments N/A See Note 5 C4.10 C-D Bolts and Studs N/A See Note 8 C7.10 C-H Pressure Retaining Conponents Visual, VT-2 One test One test One test C7.20 C-H Pressure Retaining Conponents Visual, VT-2 One test

PGE-1049 Page 81 TABLE 2 INSERVI& INSPECTION PROGRAM CLASS 2 COMPONENTS Letdown Heat Exchanger (E-207)

Extent of Ex mination Exm.

Method of Item No.

Cat.

Camonent Identification Examination 1st Period 2nd Period 3rd Period Renarks 1

C1.10 C-A Shell Circumferential Welds Voltsnetric 1 weld C1.20 C-A Head Circtsnferential Welds Volumetric 1 weld C1.30 C-A Tubesheet-to-Shell Weld N/A See Note 18 C2.10 C-B Nozzles in Vessels < 1/2 in.

Nominal Thickness C2.ll C-8 Nor21e-to-Shell (or Head) Weld N/A See Note 15 C2.20 C-8 Nozzles Without Reinforcing Plate in Vessels > 1/2 in.

Nominal Thickness C2.21 C-B NOZ21e-to-Shell (or Head) Weld N/A See Note 19 C2.22 C-B Nozzle Inside Radius Section N/A See Note 19 s

i

PGE-1049 Page 82 TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS Letdown Heat Exchanger (E-207)

Extent of Examination Exam.

Method of Item No.

Cat.

Coeonent Identification Examination 1st Period 2nd Period 3rd Period Remarks C2.30 C-B Nozzles With Reinforcing Plate in vessels > l/2 in. Nominal Thickness C2.31 C-B Reinforcing Plate Welds to N/A See Note 16 Nozzle and Vessel C2.32 C-B Nozzle-to-Shell (or Head) Welds N/A See Note 16 When Inside of Vessel Is Accessible C2.33 C-8 Nozzle-to-Shell (or Head)

N/A See Note 16 When Inside of Vessel Is Inaccessible C3.10 C-C Integrally Welded Attachments N/A See Note 5 C4.10 C-D Bolts and Studs N/A See Note 8 C7.10 C-H Pressure Retaining Conponents Visual, VT-2 One test One test One test C7.20 C-H Pressure Retaining Components Visual, VT-2 One test

PGE-1049 Page 83 TABLE 2 INSERVICE INSPECTION PROGRAM class 2 COMPONENTS Regenerative Heat Exchanger (E-206)

Extent of Examination Exam.

Method of Iten No.

Cat.

Component Identification Examination ist Period 2nd Period 3rd Period Renarks C1.10 C-A Shell Circumferential Welds N/A See Note 6 C1.20 C-A Head Circumferential Welds Volunetric 2 welds See Relief Request 4.3.6 C1.30 C-A Tubesheet-to-Shell Weld Volumetric 2 welds See Relief Request 4.3.6 C2.10 C-B Nozzles in Vessels $ 1/2 in.

Nominal Thickness C2.ll C-8 Nozzle-to-Shell (or Head) Weld N/A See Note 15 C2.20 C-8 Nozzles Without Reinforcing Plate in Vessels > 1/2 in.

Nominal Thickness C2.21 C-8 Nozzle-to-Shell (or Head) Weld Surface and 4 welds volunetric C2.22 C-8 Nozzle Inside Radius Section Volumetric 4 nozzles d

1 k

PGE-1049 Page 84 TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 (XMPONENTS l

Regenerative Heat Exchanger (E-206) i Extent of Examination Exam.

Nethod of Its No.

Cat.

Cog onent Identification Examination 1st Period 2nd Period 3rd Period Remarks C2.30 C-B Nozzles With Reinforcing Plate in Vessels > 1/2 in. Nominal Thickness C2.31 C-8 Reinforcing Plate Welds to N/A See Note 16 Nozzle and Vessel C2.32 C-B Nozzle-to-Shell (or Head) Welds N/A See Note 16 When Inside of vessel Is Accessible C2.33 C-B Nozzle-to-Shell (or Head)

N/A See Note 16 m en Inside of vessel Is Inaccessible l

C3.10 C-C Integrally Welded Attachments N/A See Note 5 C4.10 C-D Bolts and Studs N/A

$ee Note 8 C7.10 C-H Pressure Retaining Conponents Visual, VT-2 One test One test One test C7.20 C-H Pressure Retaining Conponents Visual, VT-2 One test

l PGE-1049 Page 85 TABLE 2 INSERVICE INSPECTION PROGRAN CLASS 2 COMPONENTS Voline Control Tank (T-213)

Extent of Examination Exam.

Nethod of Item No.

Cat.

Congonent Identification Examination 1st Period 2nd Period 3rd Period Remarks C1.10 C-A Shell Circtmferential Welds N/A See Note 6 C1.20 C-A Head Circumferential Welds Voltmetric 2 welds C1.30 C-A Tubesheet-to-Shell Weld N/A See Note 18 C2.10 C-8 Nozzles in Vessels < 1/2 in.

Nominal Thickness C2.11 C-8 Nozzle-to-Shell (or Head) Weld N/A See Note 15 C2.20 C-8 Nozzles Without Reinforcing Plate in Vessels > 1/2 in.

Naninal Thickness C2.21 C-8 Nozzle-to-Shell (or Head) Weld N/A See Note 19 C2.22 C-B Nozzle Inside Radius Section N/A See Note 19 l

l i

l 1

PGE-1049 Page 86 TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 CDPFONENTS Voltme Control Tank (T-213)

Extent of Examination Exam.

Method of Iten No.

Cat.

Consonent Identification Examination ist Period 2nd Period 3rd Period Remarks C2.30 C-8 Nozzles With Reinforcing Plate in vessels > 1/2 in. Nominal Thickness C2.31 C-B Reinforcing Plate Welds to N/A See Note 16 Nozzle and Vessel C2.32 C-B Nozzle-to-Shell (or Head) Welds N/A See Note 16 When Inside of Vessel Is Accessible C2.33 C-B Nozzle-to-Shell (or Head)

N/A See Note 16 when Inside of Vessel Is Inaccessible C3.10 C-C Integrally Welded Attachments Surface 100% of all support attactments C4.10 C-D Bolts and Studs Volumetric N/A See Note 8 C7.10 C-H Pressure Retaining Conponents Visual, VT-2 One test One test One test C7.20 C-H Pressure Retaining Conponents Visual, VT-2 One Test

PGE-1049 Page 87 TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 (X)MPONENTS a lsation Dampener (X-218)

Charging tire u

Extent of Examination Exam.

Method of Itan No.

Cat.

Camponent Identification Examination 1st Period 2nd Period 3rd Period Remarks C1.10 C-A Shell Circunferential Welds N/A See Note 6 C1.20 C-A Head Circumferential Welds Volumetric 1 weld C1.30 C-A Tubesheet-to-Shell Weld N/A See Note 18 C2.10 C-B Nozzles in Vessels < 1/2 in.

Naninal Thickness C2.ll C-B Nozzle-to-Shell (or Head) Weld N/A See Note 15 C2.20 C-8 Nozzles Without Reinforcing Plate in Vessels > 1/2 in.

Nominal Thickness C2.21 C-B Nozzle-to-Shell (or Head) Weld N/A See Note 19 C2.22 C-8 Nozzle Inside Radius Section N/A See Note 19

PGE-1049 Page 8B TABLE 2 INSERVICE INSPECTION PROGRAN CLASS 2 COMPONENTS a

Charging Line Pulsation Danpener (X-218)

Extent of Examination Exam.

Nethod of Itan No.

Cat.

Component Identification Examination 1st Period 2nd Period 3rd Period Renarks C2.30 C-B Nozzles With Reinforcing Plate in Vessels > 1/2 in. Nominal Thickness C2.31 C-B Reinforcing Plate Welds to N/A See Note 16 Nozzle and Vessel C2.32 C-8 Nozzle-to-Shell (or Head) Weld N/A See Note 16 When Inside of Vessel Is Accessible C2.33 C-B Nozzle-to-Shell (or Head)

N/A See Note 16 When Inside of Vessel Is Inaccessible C3.10 C-C Integrally Welded Attachments Surface 100% of I support attachment C4.10 C-D Bolts and Studs N/A See Note 8 C7.10 C-H Pressure Retaining Conponents Visual, VT-2 One test One test One test C7.20 C-H Pressure Retaining Copponents Visual, VT-2 One test

PGE-1049 Page 89 TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS Reactor Coolant Filter (F-204)

Extent of Examination Exam.

Method of I

Itsn No.

Cat.

Component Identification Examination 1st Period 2nd Period 3rd Period Remarks C1.10 C-A Shell Circunferential Welds Volumetric 1 weld See Relief Request 4.3.3 C1.20 C-A Head Circunferential Welds Volunetric 1 weld See Relief Request 4.3.3 Cl.30 C-A Tubesheet-to-Shell Weld N/A See Note 18 C2.10 C-8 Nozzles in Vessels < 1/2 in.

Nominal Thickness _

C2.ll C-B Nozzle-to-Shell (or Head) Weld N/A See Note 15 C2.20 C-8 Nozzles Without Reinforcing Plate in Vessels > 1/2 in.

Nominal Thickness C2.21 C-8 Nozzle-to-Shell (or Head) Weld N/A See Note 19 C2.22 C-B Nozzle Inside Radius Section N/A See Note 19

PGE-1049 Page 90 TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 (XWONENTS Reactor Coolant Filter (F-204)

Extent of Examination Exam.

Method of Item No.

Cat.

Crmponent Identification Examination ist Period 2nd Period 3rd Period Renarks C2.30 C-8 Nozzles With Reinforcing Plate in vessels > 1/2 in. Naninal Thickness C2.31 C-B Reinforcing Plate Welds to N/A See Note 16 Nozzle and Vessel C2.32 C-8 Nozzle-to-Shell (or Head) Welds N/A See Note 16 When Inside of vessel Is Accessible C2.33 C-8 Nozzle-to-Shell (or Head)

N/A See Note 16 When Inside of Vessel Is Inaccessible C3.10 C-C Integrally Welded Attachments Surface 100% of all support attachments C4.10 C-D Bolts and Studs N/A See Note 8 C7.10 C-H Pressure Retaining Conponents Visual, VT-2 One test One test One test C7.20 C-H Pressure Retaining Conponents Visual, VT-2 One test

PGE-1049 Page 91 TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS Seal Water Return Filter (F-209)

Extent of Exmination Exm.

Method of Ita No.

Cat.

Co monent Identification Exmination 1st Period 2nd Period 3rd Period Renarks C1.10 C-A Shell Circunferential Welds Volumetric 1 weld See Relief Request 4.3.5 C1.20 C-A Head Circunferential Welds Volumetric 1 weld See Relief Request 4.3.5 Cl.30 C-A Tubesheet-to-Shell Weld N/A See Note 18 C2.10 C-B Nozzles in Vessels < 1/2 in.

Naninal Thickness C2.11 C-8 Nozzle-to-Shell (or Head) Weld N/A See Note 15 C2.20 C-8 Nozzles Without Reinforcing Plate in Vessels > 1/2 in.

Naninal Thickness C2.21 C-8 Nozzle-to-Shell (or Head) Weld N/A See Note 19 C2.22 C-8 Nozzle Inside Radius Section N/A

'See Note 19

PGE-1049 Page 92 TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS Seal Water Return Filter (F-209)

Extent of Examination Exam.

Method of Item No.

Cat.

Canoonent Identification Examination 1st Period 2nd Period 3rd Period Renarks C2.30 C-8 Nozzles With Reinforcing Plate in vessels > l/2 in. Nominal Thickness C2.31 C-B Reinforcing Plate Welds to N/A See Note 16 Nozzle and Vessel C2.32 C-B Nozzle-to-Shell (or Head) Welds N/A See Note 16 Wwm Inside of Vessel Is Accessible C2.33 C-8 Nozzle-to-Shell (or Head)

N/A See Note 16 When Inside of Vessel Is Inaccessible C3.10 C-C Integrally Welded Attachments Surface 100% of all support attachments C4.10 C-D Bolts and Studs N/A See Note 8 C7.10 C-H Pressure Retaining Conponents Visual, VT-2 One test One test One test C7.20 C-H Pressure Retaining Components Visual, VT-2 One test

PGE-1049 Page 93 TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS Piping Extent of Examination Exam.

Method of Iten No.

Cat.

Caponent Identification Examination 1st Period 2nd Period 3rd Period Renarks C3.20 C-C Integrally Welded Attachnents (33) Surface 100% of 11 support 100% of 11 support 100% of 11 support attachments attactwnents attachments C4.20 C-D Bolts and Studs N/A See Note 8 C5.10 C-F Piping Welds < 1/2 in. Nominal Wall Thickness C5.11 C-F Circumferential Weld (436)

Surface 21 welds 34 welds 29 welds C5.12 C-F Longitudinal Weld (30)

Surface 4 welds 4 welds 4 welds C5.20 C-F Piping Welds > 1/2 in. Nominal Wall Thickness C5.21 C-F Circumferential Weld (313)

Surface and 24 welds 27 welds 25 welds volumetric C5.22 C-F Longitudinal Weld (4)

Surface and I weld volumetric

a p.

PK-1049 Page 94 l

. TABLE 2

/

.r*

INSERVI& INSPECTION PROGRAM CLASS 2 COMPONENTS y,

s Piping f

s s

Extent of Examination "ethod of Exam.

n Itan No.

Cat.

reccr.ent Identification Eueibtion

' lst Period jpd Period 3rd Period Renerks t

5 C5.30 C-F Pipe Branch Conrections > 4 in.

Nominal Branch Pipe Size l

C5.31 C-F.

CircuPfematial Weld

'N/A 5se Note 21 C5.32 C-F Longitudioal L'eid N/A See Note 71 $

C7.30 C-H Pressere Retaining Conponents Visual, VT-2 One test' Cne test' One test E

C7.40 C.-H Pressure Retaining Components.

Visual, VT-2 One test See fielief Regt=st 4.3.1 5

i s

I I

I

_/

t

[

'O.

f

PGE-1049 Page 95 TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 (X)MPONENTS Residual Heat Removal Ptsps (P-202A and P-2028)

Extent of Exmination Exam.

Method of Item No.

Cat.

Cogonent Identification Exmination 1st Period 2nd Period 3rd Period Renerks C3.30 C-C Integrally Wided Attactunents N/A See Note 5 C4.30 C-D Bolts and as #.

N/A See Note 8 C6.10 C-G Ptmp Can ; ',*1d5 N/A See Note 22 C7.50 C-H Pressure Retaining Components Visual, VT-2 One test One test One test C7.60 C-H Pressure Retaining Copponents Visual, VT-2 One test I

i

~

V J

e 4

-k

PGE-1049

~

Page %

TABLE 2 INSERVICE INSPECTION PROGRAM CLASS 2 (X)MPONENTS Centrifugal Charging Ptaps (P-205A and P-27A)

Extent of Exmination Exm.

Method of Item No.

Cat.

Com onent Identification Exmination 1st Period 2nd Period 3rd Period Remarks C3.30 C-C Integrally Welded Attachments Surface 100% of 4 support attactunents C4.30 C-D Bolts and Studs N/A See Note 8 C6.10 C-G Ptap Casing Welds N/A See Note 22 C7.50 C-H Pressure Retaining Components Visual, VT-2 One test One test one test C7.60 C-H Pressure Retaining Conponents Visual, VT-2 One test l

l

PEE.1049 Page 91 TABLE y INSERVIM INSPECTION PROGRAM CLASS 2 00FFONENTS Valves Extent of Examination Exam.

Method of Item No.

Cat.

Caponent Identification Examination 1st Period 2nd Period 3rd Period Renarks C3.40 C-C Integrally Welded Attachments N/A See Note 5 C4.40 C-0 Bolts and Studs N/A See Note 8 C6.20 C-G Valve Body Welds N/A See Note 14 C7.70 C-H Pressure Retaining Caponents Visual, VT-2 One test One test One test C7.00 C-H Pressure Retaining Conponents Visual, VT-2 One test

PGE-1049 Page g8 TABLE 3 INSERVICE INSPECTION PROGRAM CLASS 3 CDMPONENTS Systems in Support of Reactor Shutdown function Extent of Exmination Exam.

Method of Itm No.

_ Cat.

Caponent Identification Examination ist Period 2nd Period 3rd Period Remarks DI.10 D-A All Pressure Retaining Conponents Visual, VT-2 Syst e Inservice Systm Inservice Systm Hydrostatic See Relief Request 5.3.1 Within the System Boundary Test Test Test DI.20 D-A Integral Attachment, Conponent Visual, VT-3 2 Supports 2 Supports 2 Supports Supports and Restraints AFW (6)

DI.30 D-A Integral Attactment, Mechanical N/A See Note 23 and Hydraulic Snubbers 01.40 D-A Integral Attactnent Visual, VT-3 1 Support Spring Type supports AFW (1)

DI.50 D-A Integral Attachment N/A See Note 24 Constant Load Type Supports DI.60 D-A Integral Attachment N/A See Note 25 Shock Absorbers

l l

PGE-1049 Page 99 TABLE 3 i

INSERVIE INSPECTION PROCRAM i

CLASS 3 COMPONENTS t

t Systes in Support of Emergency Core Cooling, Containment Heat Renoval, Atmosphere Cleanup, and Reactor Residual Heat Removal Extent of Examination l

Exam.

Method of It a No.

Cat.

Ctmoonent Identification Examination 1st Period 2nd Period 3rd Period Renarks D2.10 D-B All Pressure Retaining Components Visual, VT-2 Systen Functional System Functional System Hydro-See Relief Request 5.3.1 Within the Systen Boundary Test Test static Test D2.20 D-8 Integral Attactonents, Copponents Visual, VT-3 1

Supports and Restraints CCW5 (191) 60 attactunents 61 attachments 60 attactunents SIS (9) 3 attactonents 3 attachments 3 attactuments D2.30 D-8 Integral Attachments, Mechanical Visual,VT-3 and Hydraulic Snubbers C.W5 (5) 2 attachments 2 attachments I attachment D2.40 D-B Integral Attachments Visual, VT-3 Spring Type Supports CCWS (21) 7 attachments 7 attachments 7 attacionents SIS (3)

I attachment I attachnent I attachment D2.50 D-B Integral Attachment N/A See Note 24 Constant Load Type Supports D2.60 D-B Integral Attachment N/A See Note 25 Shock Absorbers

PGE-1049 Page 100 TABLE 3 INSERVICE INSPECTION PROGRAM CLASS 3 COMPONENi5 Systems in Support of Residual Heat Removal frun Spent Fuel Storage Pool Extent of Examination Exam.

Method of Item No.

Cat.

Congonent Identification Examination 1st Period 2nd Period 3rd Period Resnarks D3.10 D-C All Pressure Retaining Copponents Visual, VT-2 System Inservice System Inservice System Hydrostatic See Relief Request 5.3.1 Within the System Boundary Test Test Test D3.20 D-C Integral Attactonent, Component Visual, VT-3 Supports, and Restraints SFPCS (1)

I attachment D3.30 D-C Integral Attachments, Nechanical N/A See Note 23 and Hydraulic Snubbers D3.40 D-C Integral Attachment N/A See Note 26 Spring Type Supports D3.50 D-C Integral Attactanent N/A See Note 24 Constant Load Type Supports D3.60 D-C Integral Attachment N/A See Note 25 Shock Absorbers

PGE-1049 Page 101 TABLE 4 INSERVICE INSPECTION PROGRAM CLASS 1 SUPPORTS

~

Extent of Examination Exam.

Method of Itesa No.

Cat.

Component Identification Examination 1st Period 2nd Period 3rd Period Remarks Fl.10 F-A Plate and Shell Type Supports (24) Visual, VT-3 2

2 2

through F1.40 F2.10 F-8 Linear Type Supports (70)

Visual, VT-3 6

6 6

through F2.40 F3.10 F-C Component Standard Supports Visual, VT-3 25 25 25 tbrough (293)

Visual, VT-4 F3.50 1

PGE-1049 Page 102 TABLE 5 INSERVICE INSPECTION PROGRAM CLASS 1 SUPPORTS Extent of Exmination Exm.

Method of It m No.

Cat.

Component Identification Ex mination 1st Period 2nd Period 3rd Period Remarks i

F1.10 F-A Plate and Shell Type Supports (12) visual, VT-3 1

1 1

through F1.40 F2.10 F-8 Linear Type Supports (30)

Visual, VT-3 3

3 3

through F2.40 F3.10 F-C Camponent Standard Supports (195)

Visual, VT-3 16 16 16 through Visual, VT-4 F3.50 i

i i

PGE-1049 Page 103 TABtE 6 INSERVICE INSPECTION PROGRAM CLASS 1 SUPPORTS Extent of Examination Exam.

Method of Itan No.

Cat.

Camonent Identification Examination 1st Period 2nd Period 3rd Period Reserks F1.10 F-A Plate and Shell Type Supports (8)

Visual, VT-3 2

1 1

through F1.40 F3.10 F-8 Linear Type Support Structure (85) Visual, VT-3 7

8 7

thrxxsgh F2.40 F3.10 F-C Component Standard Supports (526)

Visual, VT-3 44 44 44 through Visual, VT-4 F3.50 AWrc 3909C

PGE-1049 NOTES FOR TABLES 1 THROUGH 6 1.

There are no weld repair areas in the Beltline Region.

2.

There are no nozzle-to-safe end butt welds < 4-in. NPS.

3.

There are no nozzle-to-safe end socket welds.

4.

There are no bolts or studs 1 2-in.

5.

There are no integrally welded attachments.

6.

There are no circumferential welds in the head (shell).

7.

There are no meridional welds in the head.

8.

There are no bolts or studs > 2-in.

9.

There are no nozzle-to-vessel welds.

10.

There are no Class 1 heat exchangers other than steam generators.

11.

There are no dissimilar metal butt welds.

12.

There are no dissimilar metal socket welds.

13.

There are no longitudinal pipe welds.

14.

There are no valve body welds.

15.

There are no nozzle-to-shell (head) welds in vessels i 1/2-in.

nominal thickness.

16.

There are no nozzles with reinforcing plates in vessel > 1/2-in.

nominal thickness.

17.

There are no shell circumferential welds.

18.

There are no tubesheet-to-shell welds.

19.

There are no nozzles without reinforcing plate vessels > 1/2-in.

nominal thickness.

20.

There are no nozzle inside radius sections.

21.

There are no pipe branch connections > 4-in. NPS.

22.

There are no pump casing welds.

- 104 -

PGE-1049 Notes for Tables 1 Through 6 Page 2 23.

There are no integral attachments for mechanical and hydraulic snubbers.

24.

There are no integral attachments for constant load type supports.

25.

There are no integral attachments for shock absorbers.

26.

There are no integral attachments for spring type supports.

1 A0W/mr 4327C 1

3

- 105 -

-.