ML20128D676

Co ISI Program for Third ISI Interval 921228-021228

ML20128D676
Person / Time
Site:	Maine Yankee
Issue date:	01/28/1993
From:	Maine Yankee
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ML20128D650	List: ML20128D646 ML20128D676
References
PROC-930128, NUDOCS 9302100200
Download: ML20128D676 (722)

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I nV Maine Yankee = Atomic Power Company-Inservice Inspection Program-

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For The Ibini Inservice Inspection Interval I From: December 28.1992 to December 28. 2002 -)

Date Program Issued: 01/28/93 Prepared Ily:

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Ylant ISI Coordinator -

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lf/A YNSD /SI Coordina' tor bYd' dr  ?

ng Section Head Performance Encia Wh!$D PED Manager

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M:ine Yankee Atomic Pewt Compny

.nird Intervalist Program M Inservice Inspection Program - Table of Contents l'4C 1.0 1NTRODUCTION 11 1.1 Ilackground 12 1.2 - Reference Documents 12 1.2.1 Regulatory Documents 12 1.22 Codes and Standards 13 1.23 Maine Yankee Documents 1-4 2.0 GENERAL REQUIREMENTS 2-1 2.1 Responsibilities 21 2.1.1 Owner 2-1 2.1.2 Authorized Inspection Agencies -21 2.13- Authorized Nuclear Inservice Inspectors 2-1 2.1.4 NDE Services Providers ;2-1 21 p) y 2.2 2.2.1 Scope Classification of Systems, Portions of Systems, and/or Components 21 2-3 2.2.2 Program Exclusions 23 Examination Requirements 2-3 23.1 Examination Methods 23 23.2 Qualification of Nondestructive Examination Personnel 2-4 233 Examination Coverage .2-5 23.4 Examination Evaluations- 25 2.4 Examination Equipment and Test Procedures - 7 2.5 Records and Reports 2-7

.2 5.1 ISI Records 27 2.5.2 ISI Summary Report 27 3.0 EXEMPTIOSi a ND POSITION STATEMENTS 3-1 3.1~ Code-Allowed Exemptions 31 3.1.1 Class 1 Exemptions 31 3.1.2 Class 2 Exemptions . 31 3.13 Class 3 Exemptions - 3-2' 3.1.4 Class 1,2, and 3 Support Exemptions 32 i2O

.L/ . 3.2 Maine Yankee Position Statements 3-3 i

Maine Yankee Atomic Power Company Third Interval 1st Program 9: P2Lt 41 4.0 RELIEF REQUESTS 5.0 INSERVICE INSPECTION SUBPROGRAMS 51 5.1 General 5-1 5.1.1 Multiple-Component Concept 5-1 5.1.2 Selection Optimization 51 5.13 Relief Requests 52 5.1.4 Selection Basis 52 5.1.5 Definitions 52 _

5.1.6 ISI Program Tables 52 5.2 Class 1 (IWil) Welds / Components Subprogram 5-3 5.2.1 Examination Category B-A 5-3 5.2.2 Examination Category B-B 5-4 5.23 Examination Category B-D 5-5 5.2.4 Examination Category B-E 5-6 5.2.5 Examination Category B-F 5-7 5.2.6 Examination Category B-G-1 5-7 5.2.7 Examination Category B-G-2 5-8 5.2.8 Examination Category B-H 5-9 9 5.2.9 5.2.10 Examination Category B-J Examination Category B K-1 59 5-11 5 11 5.2.11 Examination Category B L 1 1.2.12 Examination Category B-L-2 5-11 5.2.13 Examination Category B-M.1 5-12 5.2.14 Examination Category B M-2 5-12 --

5.2.15 Examination Category B-N-1 5-13 -

5.2.16 Examination Category B-N-2 5 13 5.2.17 Examination Category B-N-3 5-14 5.2.18 Examination Category B-O 5-14 5.2.19 Examination Category B-P 5-15 5.2.20 Examination Category B-Q 5 15 53 Class 2 (IWC) Welds / Components Subprogram 5-15 53.1 Examination Category C-A 5 15 -

53.2 Examination Category C-B 5-15 533 Examination Category C-C 5-16 53.4 Examination Category C-F-1 5-17 53.5 Examination Category C-F-2 5 20 53.6 Examination Category C-O 5 22 5.4 Class 3 (IWD) Welds / Components Subprogram 5-23 5.4.1 Examination Categories D-A, D-B, and D-C 5-23 O

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Maine Yankee Atomk Power Company

'Ihird Interval ISI Program l'ait 5.5 Class 1,2, and 3 Supports Subprogram 5 24 5.5.1 Piping Supports 5 24 5.5.2 Nonpiping Supports 5 25 5.53 Category F A Item Summary 5-25 5.5.4 Piping Support Sumraary By Class, System, & Support Type 5 26 5.6 System Pressure Testing Subprogram 5-27 5.6.1 General 5 27 5.6.2 Class 1 System Pressure Testing 5 28 5.63 Class 2 System Pressure Testing 5 29 5.6.4 Class 3 System Pressure Testing 5-30 5.6.5 Pressure Test Drawings 5 31 6.0 REPAIR AND REPLACEh1ENT PROGilAh! 61 APPENDICES

• Appendix A - Multiple-Component Group Listing O

• Appendix B Relief Ilequests

• Appendix C Guidelines for Program hialntenance and Implementation

• Appendix D - Listing of Applicable FAI Series Dewings (P&lD's)

• Appendix E - Zone, ISI Drawing, and Line/ Equip Number Cross lleference

• Appendix F - ISI Drawings (Piping Isometries and Co uponent Identification Drawings)

• Appendix G - ISI Program Tables O

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Mainc Yankee Atornic Power Ccmpany .

• third Interval ISI P..ogram t

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1.0 INTRODUCTION

i nis document containt, the Insenice Inspection (ISI) Program for the third inspection s interval of the Maine Yankee Atomic Power Plant, as required by Title 10, Ccde bf Federal Regulations, Part 50 (10CFR50), Section 50.55a, Codes and Standards. This Program has been updated to incorporate channes necessitated by modifications, repairs,-

and/or replacements to systems, components, and/or. welds through the second interval.

As allowed by 10CFR50.55a(g)(4), this updated ISI Program is in compliance, to the extent practical, with the governing ASME Code rules (reference paragraph 1.2.2.1)1 It' details the technical basis of the Program and provides an overall description of the activities planned to fulfill the ISI requirements ' - uclear power plant components and their supports, as defined in the American Soci ' ar Mechanical Engineers (ASME),

Boiler and Pressure Vessel Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components." This Program identifies the Class 1,2, and 3 components (e.g., piping, pumps, valves, vessels) and their supports, subject to the examination and test requirements of Subsections IWB, IWC, IWD, and IWF of ASME Section XI (also referred to as the " Code"). It also identifies and details programs established tJ satisfy 1 augmented inspections imposed at or desired by Maine Yankee.

The start of the third inspection intenal at Maine Yankee, and thus the effective date for this updated ISI Program, is December 28, 1992. Maine Yankee may begin in'plementation of this ISI Program upon internal approval, as outlined in Appendix C.

He anticipated completion of the third h,terval will be ten years from this date on

, December 28,2002.

In accordance with 10CFR50.55a, the applicable Code governing the third interval ISI Program at Maine Yankee is the 1986 Edition of Section XI of the ASME Boiler and -

Pressure Vessel Code. Any further references made to the Code (ASME Section XI)

,- within this ISI Program Document imply the 1986 Edition, unless specifically stated othenvise. Plant Technical Specifications in conjunction with ASME Section XI provide-the inspection requirements for steam generator tubing. In addition, ASME Code Cases (identified in paragraph 1.2.2.7) have been utilized in accordance with Regulatory Guide 1.147 or a Relief Request to provide alternatives to ASME Section XI Code requirements.

l Maine Yankee is also committed to comply with additional and/or supplemental inspection requirements imposed by regulatory authorities or internal recommendations.

These commitments include augmented inspections of Main Steam piping in the MSVH (Superpipe) High-Energy Line . Break (HELB) piping, and Feedwater nozzle weld

-inspections. These inspection requirements are tracked in the ISI database and are considered part of the overallISI Program. Maine Yankee reserves the right to alter augmented inspection ~s that are based on internal recommendations without approval from the NRC. -

l This updated ISI Program consists of the Program text, followed by Appendices. The text defines the ISI Program, explaining the specific boundaries, exemption criteria, sample sizes, and component selection criteria utilized for Class 1,2, and 3 nonexempt components and their supports. This Program is to be controlled in accordance with the =

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Mxine Yankee Atomic Power Company .

Dird IntervJ- ISI hogram

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() ' guidelines contained in Appendix C. The Appendices include in this Program a.e as follows:

• Appendix A - Multiple-Component Group Listing appendix B Relief Requests Appendix C - Guidelines for Program Maintenance and Implementation Appendix D - Listing of Applicable FM Series Drawings (P&lD's)

Appendix E - Zone, ISI Drawing, and Line/ Equip Number Cross Reference Appendix F - ISI Drawings (Piping Isometries and Component Identification Drawings)

• Appendix G ISI Program Tables ,

1.1 BACKGROUND

The Maine Yankee Atomic Power Plant is a Combustion Engineering 900 megawatt, 3-loop, pressurized water reactor (PWR) plant. Maine Yankee was built to the -

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ANSI B31.1 Construction Code, and the assignment of safety classifications is in accordance with ANSI Standard N18.2 (reference paragraph 2.2.1 for discussion of safety classifications).

Maine Yankee began commercial operation in December 1972. The first ISI Program-was developed in 1975 for Class I components, then revised in 1979 to include Class 2 and 3 components. A summary of Maine Yankee's ten year inservice inspection intervals and applicable Code Editions utilized is as follows:

1st Interval December 28,1972 to December 28,1982 - ASME XI 1974/S75 2nd Interval- December 28,1982 to December 28,1992 - ASME XI 1980/W80 3rd Interval December 28,1992 to December 28,2002 - ASME XI 1986 1.2 REFERENCE DOCUMENTS 1.2.1 Reculatory Documents 1.2.1.1' Title 10, Code of Federal Regulations, Part 50.55a, Codes and Standards 1.2.1.2 Federal Register, Thursday, August 6,1992, Page 34666, Nuclear Regulatory Commission adoption of new' mandatory augmented requirements for RPV shell examinations.

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Third Interval ist Prograre -

1.2.1.3 USNRC Regulatory Guides:

• Reg Guide 1.58 Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel-

• Reg Guide 1.65 Materials and Inspections for Reactor Vessel Closure Studs -

• Reg Guide 1.83 Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes

• Reg Guide 1.147 Inservice Inspection Code Case Applicability ASME Section XI Division 1

• Reg Guide 1.150 Ultrasonic Examination of Reactor Vessel Welds During Preservice and Inservice Examinations 1.2.1.4 NUREG-0800, LWR Edition - Standard Review Plan - High Energy Line Breaks 1.2.2 Codes and Standards 1.2.2.1 ASME Boiler & Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components,1986 Edition 1.2.2.2 ASME Boiler & Pressure Vessel Code,Section V, Nondestructive Examination, 1986 Edition 4

1.2.2.3 ASME Boiler & Pressure Vesm! Code,Section XI Interpretations, (Through Volume

'f 3 30) 'l 1.2.2.4 ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition, Nonmandatory Appendix F, Preparation of Inspection Plans 1.2.2.S ANSI Standard N18.2, Nuclear Safety Criteria for the Design of Stationary )'

Pressurized Water Reactor Plants i

1.2.2.6 ASNT Recommended Practice No. SNT-TC-1 A,1980 Edition 1.2.2.7 ASME Boiler & Pressure Vessel Code,Section XI Code Cases: ,

The below referenced Code Cases are intended to be utilized for the third interval ISI Program as applicable. Some of the Code Cases however, will not necessarily.

be adopted until a situation arises that would justify their use. _ Code Cases which have been specifically adopted within this program are indicated by reference to the  ;

section or paragraph of the Program in which they are utilized. '

ASME Section XI Code Cases Code Case Number Title Remarb

\/ N4011 Eddy Current Examiration N416 Alternative Rules for Ilydrostatic Testing of Repair or Replacement of Gss 2 Piping i

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Maine Yankee Atomic Power Company I Third Interval ISI Program ASME Section XI Code Cases Code Case Number Title Remarks N435-1 Alternativc baminanon Requircrents for Vesscis With Walt Dickness 2 in or txss N-437 Use of Digital Readout and Digital Measurement Equipment Devices for Performing Pressure Tests N445 Use of Later Editions of SNT-TC 1A for Quahficatic t See paragraph 2.3.2 of Nondestructive unmiaation Personnel N446 Recertification of Visual Examination Personnel See paragraph 2.3.2 N448 Quahfication of Vf-2 and VT 3 Visual bamination See paragraph 2.3.2 Personnel N457 Oualification Specimen Notch location for Ultramnic Examination of Bolts and Studs N450 Alternatrve Examination Coverage for Class 1 ai.d 2 See paragraph 2.3.3 Weld:

N461 Alternatwe Rules for Piping Cahbration Block nickness N491 Ahernative Rules for Examination of Class 1,2, and 3 See Section 53 Component Supports N-496 lichcal Coil nreaded Inserts N495 Alternatwe Rules for 10-Year flydrostatie l'ressure See Section 5 6 Testing for Class 1 and 2 Systems 1.23 Maine Yankee Documents _

1.23.1 ISI Program - Second Interval 1.23.2 Operational Quality Assurance Program 1.2.33 Final Safety Analysis Report (FSAR) 1.23.4 Technical Specifications 1.23.5 Letter to MYAPCo from USAEC dated 11/29/73 - Main Steam Headers in MSVH Tech Spec change No. 5 (Superpipe) 1.23.6 MYTTS 01-62-06, Cyclic Volumetric Examination of Feedwater Line to Steam Generator Nozzle Welds 1.2.3.7 OAS-1-29-17 -ISI Testing of Potential High Energy Line Break 1-4

I Milne Yankee Atomic Power Cornpa:y - l Wird I:terval ISI Progr:m ~

l 1.2.3.8 Engineering implementing Procedures:

e' 3.17.6 Inservice Inspection l

• 3.17.6.2 - Steam Generator Tube Eddy Current Testing

• 3.17.6.3 Reactor Coolant System Leak Test

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• 3.17.6.4 - Surveillance Inspection of Shock Suppressors

• 3.17.6.8 Visual Examination of the Reactor Vessel and Closure Head Internals a 17-25 Hydro Testing i

• 17-26 CleaninFfor NDE

• 17 27 NDE of Safety Class Components

• 17 205 ISI History

• 0-08-1 Material Identification and Control

• 0 @ -1 Control of Special Processes *

• 0@-2 Documentation of Welding and Associated Equipment

• 0-16-3 Work order Processing Procedure

• 5 216-5 Rework Identification and Corrective Action Program

• 17-21-2 Engineering Design Change Request

• 17-23 ! Design Change Installation Instructions

• 17-226 Technical Evaluations

• YAEC Guidelines Book II

• YAEC Guidelines Book Ill O

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1 Maine Yankee Atomic Power Company Third Interval ISI Progr:m 2.0 GEbTRAL REOUIREMENTS 2.1 RESPONSillILITIES 2.1.1 OnncI The Owner shall bear the overall responsibility for the performance ofISI activities, The responsibility of the Owner is to meet all requirements where relief is not requested, as

• delineated in AShiE Section XI, Plant Technical Specifications, and other NRC .

Commitments. The Owner's respon>ibilities are outlined in ASME Section XI, Subarticle IWA 1400.

2.1.2 Authorized InspectLon Agencies The Authorized Inspection Agency, including its staff of Authorized Nuclear Inservice Inspectors, shall meet the requirements of ANSI /ASME N626, 2.1.3 Authortred Nuclear Inservice Inspectors (ANID The . responsibilities of the ANIl are delineated in ASME Section XI, Subsubarticle IWA.2110, 2.1.4 NDE Services Providers The responsibilities of the examination agencies who provide NDE services are delineated in the YAEC procedure YA-ISI 2 and the applicable purchasing specifications for NDE services.

2.2 SCOPE I

2.2.1 .ClassLfication of Systems. Portions of Systems. and/or Componenlg Safety Class 1,2, and 3 components and their supports, unless otherwise exempt, are subject to the rules and requirements of ASME Section XI Components that are part of system boundaries which are exempt from examination by ASME Section XI shall be visually inspected during system pressure tests.

ASME Safety Classifications correspond with the NRC group classifications as follows:~

NRC Quality Group Flow Diagram and ASME Classification ' Class g

L A 1

[( B 2 C 3 D 0 i

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Mame Yantse Atomk Power Company Third Interni ISI Program i

The original assignment of Safety Classifications at the time of plant construction was done to ANSI Standard NI8.2, The classifications and system boundaries assigned by the plant constructor appear on the plant flow diagrams (FM series drawingr),

The following table lists those portions of systems which may be applied to subparagraph IWA 1320(d) of the 1986 Edition of ASME Section XI which states: "The portion of piping that penetrates a containment vessel, which is required by Section III to be constructed to Class I or 2 rules for piping and which may differ from the classification of the balance of the piping system, need not affect the overall system classification that determines the applicable rules of this division." Accordingly, where the components beyond the containment penetration area are classified as nonnuclear Class, the Class 2 piping will be considered exempt from the requirements of Section XI and tested in -

accordance with 10CFR50, Appendix J requirements, Class 2 Portions of Systems at Containment Penetrutions Whose Classineation Diliers From tiie Overall System Classincation Line/Com ponent Rercrmee Penetration Druning Numt.ers Clan function Cl1M 4, 5, 6 l'M-22A 74 A, 74 D, 74C 2 NNS GN-2, GN-3 13129A 44 2 NNS CARDoX 111 2'>C L1-A 2 NNS D RL-38 FM 30A 39 2 NNS PW-18 1%I-30A 37 2 NNS Sll-10 1432A 68 2 NNS V RL-7, 37, 39 1%f.31A 24 2 NNS VL-22 13133n 42 2 NNS DRL-82, DRL-84 1%33n 92 2 NNS PCC 169,170,156,190, 237, 2R 167, 131 MC 3,4,5,6,86.89, 2 NNS 187, ISS, 157, 158, 159, 146, 156, 154, RI A, 81 n 24 L 147,148,191, 200, 201, 202. 242, 243, 244, 245, 261, 262, 2612t4, 372, 265, 251, 152, 25 1 254, 255, 275, 276, 277, 278, 279, 258, 259, 260, 256, 157, 371, 250, 273, 271, 272, 246, 370, 270, 266, and 274 RWIA TM40A 79 2 NNS ACC-25. ASC-35 1 4 81D 43 2 NNS 1-1/T lA l'M 81F 49 2 NNS 1/r IA 131-81G 49 2 NNS LM-1 LM-2, LM-3.11,1-4 l'M 96D 63A, 6311, 61 A, 61B 2 NNS 2-2

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Maine Yonkee Atomic Power Company TNrd Inte.tval ISI Progrem ~

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; l k/ ' 2.2.2 Procram Exclusions l l

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• Specifically excluded from the scope of this ISI Program are the inservice testing j requirements of ASME Section XI, Subsections IWP and IWV (Pump and Valve Testing), and IWF 5000 (Inservice Testing of Snubbers), These requirements are contained in Maine Yankee's IST Program.

• See Section 3.0 of this ISI Program for exemptions.

2.3 EXAMINATION REQUIREMENTS 23.1 Examination Methods Nondestructive examination methods to be used for this ISI Program include visual, surface, and valumetric methods.

2.3.1.1 Visual Examination Visual examinations (VT) will be performed in accordance with IWA-2210, which defines three types of VT examinations, summarized as foHows:

• VT 1 examinations shall be conducted to determine the condition of the part, -

O component, or surface examined. The examination shall determine conditions such' as cracks, wear, corrosion, erosion, or physical damage on the surfaces of the parts or components, This type of examination may be performed by direct or_ remote visual methods, as defined in IWA 2211.

• VT-2 examinations shall be conducted to locate _ evidence of leakage from pressure-retaining components or abnormal leakage from components,- with or without leakage collection systems, as required during the conduct of system _ pressure or -

tu,vtional testing. This examination shall be conducted in accordance with IWA-ci240.

• VT-3 examinations shall be conducted to determine the general mechanical and structural condition of components and their supports, such as the verification of-clearances, settings, physical displacements, loose or missing parts, debris, corrosion, wear, erosion, or the loss of integrity at bolted or welded connections. He VT-3 examination shall include examinations for conditions that could affect operability or functional adequacy of snubbers and constant load and sprinj;-type supports. For component supports and component interiors, the examinations may be performed remotely, with or without optical aidsi to verify _ the structural integrity _ of the component.

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l(~f 23;1.2' 9 Surface Examination

- A surface examination 'will be performed in accordance _with 1WA 2220 to detect the presence of surface discontinuities. Surface examinations may be conducted by either 7

magnetic particle (MT; reference Article 7 of ASME Section V) or a liquid penetrant (LP or PT; reference Article 6 of ASME Section V) method, depending on surface conditions, material, and accessibility.

23.13 Volumetric Examination A volumetric examination will be performed in accordance with IWA 2230 to detect the presence of discontinuities throughout the required volume of the material. Two acceptable volumetric methods are radiographic (RT) and ultrasonic (UT) examinations.

The UT method is primarily used for the planned examinations in this program; however, RT may be used, as applicable, on certain components.

23.1.4 Alternative Examination Methods In accordance with IWA-2240, " Alternative examination methods, a. combination of-methods, or newly developed techniques may be substituted for the methods specified...,

provided the Inspector is satisfied that the results are' demonstrated to be equivalent or -

superior to those of the specified method."

O 23.2 Oualif1 cation of Nondestructive Examination Personnel Personnel performing NDE and visual examinations of Safety Class 1, 2, and 3 components, and the equipment and materials used for these examinations, shall be .

qualified in accordance with the provisions of ASME Section XI and- approved procedures. Procedures used to qualify personnel to perform nondestructive 4 examinations shall be prepared in accordance_ with IWA 2300 and - the following documents, as applicable,-for the techniques and methods used:

• The American Society for Noridestructive Testing (ASNT) Recommended Practice -

SNT TC-1 A,1980 Edition.

Note 1: In accordance with Code Case N 445, the: 1984 Edition of SNT TC 1A;may be utilized in lieu of the 1930 Edition referenced '

in ASME Section XI,1986 Edition, r

Note 2: In accordance with IWA-2300(a), certification of personnel qualified .

with a procedure prepared in accordance with the 1975 Edition ofi SNT-TC-1A will remain valid until recertification is required.

• ASME Code Case N-446, which allows standardization of recertifications consistent '

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with those of NDE Certifications (i.e., Level I and II visual examination personnel o may be recertified every 3 years by examination only, and Level III- visual examinatior. personnel may be recertified by examination every 5 years). -

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• ASME Code Case N-448, which allows personnel performing VT 2- and VT 3 examinations to be qualified in accordance with IWA-2300(a) and (b) in lieu of IWA 2300(c), and that all other provisions of IbA 2300 shall be met. Basically, this allows use of SNT TC-1A for the basis of qualifications for methods not specifically addrewed in SNT-TC-1A.

233 Euminaljon Coverart Examination coverage for components within the scope of the ISI Program shall be in accordance with Code examination requirements / figures.

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'Ihe alternative rules of Code Case N-460 for examination coverage of Class 1 and 2 welds may be utilized when the required volume or area cannot be examined due to interference of another component or part geometry. The overall reduction in examination coverage, however, must be less than 10%.

23.4 Eumination Evaluations and Accenlants Evaluation of volumetric and surface examinations conducted on Class 1 or 2 components during inservice inspections or preservice inspections shall be performed by comparing the examination results with:

• the recorded results of preservice examinations and prior inservice examinations (if applicable); and a the applicable Code acceptance standards (Paragraph 23.4.1).

Evaluation of visual examinations conducted on Class 1,2, or 3 components during inservice inspections or preservice inspections shall be performed by comparing the examination results with:

• the applicable Code acceptance standards (Paragraph 23.4.1).

Flaws detected on Class 1, 2, or 3 components during inservice examinations or preservice examinations shall be characterized in accordance with IWA 3300 of the Code.

Verified flaws of preservice examinations, or changes to known flaws from prior examinations (identified during inservice inspections), shall be recorded in accordance with IWA 1400(h) and IWA-6220 of the Code and, additionally, IWA-2200(b) of the Code for Class 1 components.

Class 1,2, and 3 components whose examinations reveal flaw indications which exceed the specified acceptance standards shall be unacceptable for continued service until corrected or accepted in accordance with the Code. Class 1, 2, and 3 component supports whose examinations exhibit unacceptable conditions shall be unacceptable for continued service until corrected or accepted in accordance with Code Case N 491, it 2-5

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Mainc Yankes Atomic Power Companyi Third Intervel ist Program .]

is Maine Yankee's position that components in which analytical evaluations are being ;

performed to determine flaw acceptance may be considered acceptable 'or service during this evaluation process.

Class 1,2, and 3 components evaluated as acceptable for continued service by analytical y

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evaluation shall be subject to successive inspections in accordance with paragraph 2.3.4.2. j Class 1,2, and 3 component supports subjected to corrective measures shall be subject ~l to successive inspections in accordance with paragraph 23.4.2.  ;

I 23.4.1 Acceptance Standards The acceptance standards for Class 1,2, and 3 components shall be in accordance with the reference found in the applicable Category and item Number of Tables IWB 25001, IWC 25001, and IWD-25001. Table IWD 25001 references IWD 3000, which is in the course of preparation; however, the rules ofIWB 3000 may be applied. For component supports, acceptance standards shall be in accordance with Code Case N 491, . ,

, Subarticle 3400.

If acceptance standards are not specified in Section XI, the evaluation will utilize the applicable standards of the original Construction Code for evaluation of flaws, as allowed by IWA 3100(b).

23.4.2 Successive Inspections O' To the extent practical, the sequence e component examinations established during previous inspection intervals shall be repeated during successive inspection intervals.

In the case where flaw indications in Class 1 and'2 components are evaluated as -

acceptable for continued service based on analytical evaluatic,n, the area containing the flaw shall be subject to successive examinations in accordance with IWB-2420(b) and (c) or IWC-2420(b) and (c) of the Code, as applicable. There are no requirements for.

successive examinations for Class 3 components in the 1986 Code.

Class 1, 2, and 3 component supports whose examinations result in ' unacceptable conditions requiring corrective measures shal.1 be subject to successive examinations in accordance with Code Case N 491.

Following completion of the required successive examination (s), the examination:

schedules for components containing flaw indications which have remained unchanged,.

and/or component supports requiring no further correction, may revert back to the' original examination schedule.

~ 23.43 Additional Examinations Class 1 and 2 component examinations (excluding VT-2. visual examinations), performed . <

in accordance with the routine examination requirements of the Code that reveal-indicatiens which exceed the prescribed acceptance standards (paragraph 23.4.1), shall-L O be extended to include additional examinations. These additional examinations shall be 2-6 b

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Third Intem!151 Pmgr:m y y in accordance with IWB-2430 and IWC 2430, respectively. The 1986 Code does not - >

require additional examinations for Class 3 component examinations.

Class 1,2, and 3 component support examinations requirmg corrective measures shall - = - - -

be extended to include additional examinations in accordance with Code Case N-491.  ;

2.3.4.4 Supplemental Examinations Volumetric or surface examinations that detect flaws that require evaluation may be supplemented by other examination methods and techniques (IWA 2240) to determine -

the character of the flaw (i.e., size, shape, and orientation).

Visual examinations that reveal relevant conditions may be supplemented by surface or

• volumetric examinations to determine the extent of the unacceptable conditions and the need for corrective measures, repairs, analytical evaluation, or replacement.

Note: Supplemental examinations are not the same as the al rnate examination methods previously discussed in paragraph 2.3.1.4.

2.4 EXAMINATION AND TEST EQUIPMENT PROCEDURES All examination techniques and NDE procedures shall be in compliance with the 1986-Edition of ASME Section ~XI. Approved procedures shall be provided by either the

examination agencies, Yankee Atomic Electric Company, or by Maine Yankee.

2.5 RECORDS AND REPORTS 2.5.1 IST Records Records and documentation of all information and inspection results, which provide the basis for evaluation and which facilitate compariso'n with results from previous and .

subsequent inspections, will be maintcined and available for the active life of the plant - -

in accordance with ASME Section XI, IW.* 6000.

- 2.5.2 - ISI Summary Report Inservice Inspection Summary Reports for Class 1 and 2 pressure-retaining components and their supports will be prepared at the completion of a r- :ng . outage in which -

4. inspections were conducted. All examinations and tests conducted since the preced.ing summary report shall be included.

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The summary report will be prepared in accordance with ]WA-6220. These requirements . <

are as follows:

1. Numbers assigned to the components Ly the State,-Municipality, or Province,

2. National Board Numbers assigned to the components by the rtanufacturer, j

3. Name of the components and descriptions, including size, capacity, . material, _

l location, and drawings to aid identification.-

4. Name and address of manufacturers. ,

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5. Manufacturer's component identification numbers.

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6. Date of completion of the examination, test, replacement, or repair.

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7. Name of Inspector who witnessed or otherwise verified the examinations, tests, -- t replacements, or repairs, and the Inspector's employer and business address, when required.

8. Abstract of examinations, tests, replacements, or repairs performed; conditions recorded; and corrective measures recommended or taken.

9. Signature of Inspector, when required.

10. Owner's Report fo'r Inservice Inspections, Form NIS 1, and Owner's Report for Repairs or Replacements, Form NIS.2, as shown in Appendix II of the Code. -

Plans, schedules, records, and summary reports shall have a cover sheet providing the

~

following information:

l-

, 1. Date of' document completion I

2. Name and address of Owner.

L 3, Name and address of generating plant.

I 4. - Name or number designation of the unit, l-5,- Commercial operating date for the unit.-

"~he subject Inservice Inspection Summary Report will be filed with enforcement and regulatory authorities within 90 days of completion of the inspections conducted during the refueling outage.

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l Maine Yentee Atc.nle Pcmer Company =

nird Interval 151 Program 2.5.2.1 Form NIS 1 This form is required to be completed and submitted with the ISI Summary Report as a record of the components inspected. Refer to Mandatory Appendix II of the Code for a sample of this form.

2.5.2.2 Form NIS.2 This form is required to be completed and submitted with the ISI Summary Report as a record of the components which have been repaired or replaced. Refer to Mandatory Appendix 11 of the Code for a sample of this form.

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Maine Wnice Atomic Power Com;eny

' third Interval ISI Program 3.0 MEMPTIONS ANJ) POSITION STATEh1M))i 3.1 CODE ALLOWED EXEMPTIONS ASME Section XI rules allow certain components or portions of components (and component supports), which are classified as ASME Class 1,2, or 3, to be exempt from examination requirements (except VT 2) of the Code. The specific Code exemptions which are specified in the 1986 Code Edition and which have been applied to the Maine Yankee ISI Program are detailed in the follov,ing:

Note: Some positions have been taken by Maine Yankee regarding component exemptions, and are detailed in Paragraph 3.2.

3.1.1 Class 1 ComponenLLetetions:

• Piping of 1" NPS and smaller (except for steam generator tubing), along with components and their connections in piping 1" NPS and smaller.

• Reactor vessel head connections and associated piping,2" NPS and smaller, made inaccessible by control rod drive penetrations.

3.1.2 fJut.2._Cenps.nznj.Etejnplimtn Components Within Residual lleat Removal (RilR), Emergency Core Cooling (ECC),

and Containment Heat Removal (CIIR) Systems (or Portions of Systems)

• Vessels, piping, pumps, valves, and other components 4" NPS and smaller in all systems except the High-Pressure Safety injection System.

• Vessels, piping, pumps, valves, and other components 1 1/2" NPS and smaller in the -

High-Pressure Safety Injection System.

• Component connections 4" NPS and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other components of any size in all systems except the fligh Pressure Safety injection System.

• Component connections 1 1/2" NPS and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other components of any size in the High-Pressure Safety injection System.

• Vessels, piping, pumps, valves, other components, and component connections of any size in the statically pressurized, passive portion of the Safety Injection System.

• Piping and other components of any size beyond the last shutoff valve in open-ended portions of systems that do not contain water during normal plant operating ,

conditions.

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Mainc Yannes Atomic Power Company .

nird Interval ISI Program Components Within Systems (or Portions of Systems) Other Than RHR, ECC, and CllR

• Vessels, piping, pumps, valves, ana other components 4" NPS and smaller.

Component connections 4" NPS and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other components of any size.

• Vessels, piping, pumps, valves, other components, and component connections of any size in systems or portions of systems that operate (when the system function is required) at a pressure equal to or less than 275 psig and at a temperature equal to or less than 200*F.

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

Concrete Encased Components Piping support members and piping support components that are encased in concrete shall be exempted from the examination requirements of IWC-2500.

3,1.3 Class 3 Compramt Ennelinas Integral attachments of supports and restraints to components that are NPS 4 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 the Auxiliary Feedwater System. _

Integral attachments of supports and restraints to components that exceed NPS 4 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 removal, 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.

3.1.4 Class 1. 2. anU_ Support Eumptions The exemption criteria for component supports is in accordance with paragraph -1230 of Code Case N-491, which states that " Component supports exempt from the examination requirements of -2000 are those connected to components and items exempted from examination under IWB 1220, IWC-1220, and IWD-1220. In addition, portions of supports that are inaccessible by being encased in concrete, buried 3-2

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Maine Yankee Atomic Power Company -

Third interval ISI Progrrm yJ underground,-or encapsulated by guard pipe are also exempt from the examination

( -

requirements of Article -2000 "

3.2 MAINE YANKEE POSITION STATEMENTS Because certain ASME Section XI Code rules can be subject to interpretation, Maine -

Yankee has developed the following " Position Statements" to clarify Maine Yankee's intended application of the Code rules.

• In addition to the Class 3 exemptions listed in 3.1.3 above, integral attachments of supports and restraints to components that are 1" NPS and smaller for the Auxiliary l Fecdwater System, within the system boundaries of Examination Categories D-A, 1 D B, and D-C of Table IWD-2500-1, shall be exempt from the visual examination, VT-3. This position is based on the minimum size exemption given for Class 1 l

piping and components.

In addition to the Class 2 and Class 3 exemptions listed in 3.1.2 and 3.1.3 above, nonpiping component size exemptions shall be based on the following: Nonpiping components having a cumulative inlet and a cumulative outlet nominal cross-sectional area, neither of which exceeds the nominal cross-sectional area of the applicable-exemption size, shall be exempted from the surface, volumetric, and visual VT-1 and -

A VT-3 examination requirements of IWC-2500 and IWD-2500. The applicable V exemption size shall be 4" NPS for all systems except the Class 2 High-Pressure Safety injection System, which shall be 1-1/2" NPS and, except for the Class 3 Auxiliary Feedwater System, which shall be 1" NPS.

t This position is based on Maine Yankee's interpretation of the clarification made by footnote 1 of IWC-1220 and IWD-1220 in the 1989 Addenda to ASME Section XI.

For the purpose of applying this criteria, it is assumed that the intention of the Code is not to eccumulate the cross-r.:ctional areas of piping from different fluid systems entering a given component (e.g., heat exchanger shell and tube sides).

Storage tanks which are vented to atmosphere, and their associated piping to the first isolation valve,-shall be considered nonpressure-retaining components and are therefore not subject to examination requirements (except VT-2).

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L!

. Maine Yankee Atomic Power Company i j Third Intervsl ist Program 4.0 RELIEF REOUESTS

'In cases where ASME Section XI requirements have been determined to be impractical I to comply with,' Relief Requests have been prepared in ~ accordance with 10CCR50.55a(g)(5)(iii). Relief Requests may also be generated to-allow for use of=

alternative requirements from later unapproved Code Editions / Addenda or unapproved Code Cases.

t All requests for relief from the inspection requirements of ASME Section XI and/or any  ;

alternative inspection requirements utilized in this ISI Program willinclude the following, as applicable:

1. A unique alphanumeric identifier for the Relief Request.

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

3. The ASMC Code Class, Examination Category, and Item Number.

4. The specific inspection requirement (s) from which relief is requested. .

5. Information which justifies the request for relief,

6. When applicabie, a description of the alternate examination or test which will be performed in lieu of the Code requirements (or other inspection requirements, as applicable).

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

Below is a summary listing of the Relief Requests submitted for the third intervalISI

, Program. All Relief Requests are contained in Appendix B.

Relief Request Summary Relief Requeu Code Number Class Categoryntem Subject 1 1 SP. IM 40 & Cast stainless steel componentsi

!!i 130 2 1 41,.1 & 41,-2 Pump casing welds and internal

' n11.10 & 1112.20 surface esaminations.

3 1- RJ, B9.11 Cast stainless steel components.

4L '1'

. SM.2,1112.50 Valve internal surface examinations.

5 1 S F,10,130 Cast stainless steel comronents.

6 3 D-A.n.C Pressure testing of buried piping ,

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

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Maine Yenkee Atomic Pontt Company - _

Third Interval ISI Pro; ram '-

az' :Y .

' Reller Rtquest Sunnmary Relief Request ~ Code .

Number Class Category /liem Subject..

7 1;u,3 P-A Use of Code Case N-491.'

8 1,2,3 IkP, C II, l'rcssure testing . Insulation -

D-A.II,C removal at bolted connections. -

9 1,2,3 1UP, C.II, Preuure testing . Removal of.

D-A,II,C botting when icakage ha4 occurred. )

30 1 lkj Tabic IW11-?300-1 stress / usage selection requ*rements.

11 1 . ILM4,i4140 Valve body wclds l

I d

i

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Maine Yankee Atomic Power Company Dird Interval !$1 Program .

V 5,0 liSSERVICE INSPECTION SU11 PROGRAMS 5.1 GENERAL q The Code provides rules and requirements for the inservice inspection of Class 1,2, and 3 components and their supports. Included in these Code requirements are rules for the selection of specific components for examination. The following subprograms address these Code rules, as they apply to Maine Yankee, and provides the specific selection criteria or basis applied to each Code Category and/or item.

In accordance with the 1986 Edition of Section XI, Article IWA 2400, all portions of the ISI Program conform to Inspection Program B; therefore, the requirements within each -

subprogram are specific to Inspection Program B of the Code.  !

t Information presented in this section is organized by Code Class and Examination Category (as found in Table IWX 25001 of the Code); Class 1,2, and 3 ccmponent supports are discussed separately. The subprograms are discussed as follows:

5.2 Class 1 (lWB) Welds / Components Subprogram 5.3 Class 2 (IWC) Welds / Components Subprogram 5.4 Class 3 (IWD) Welds / Components Subprogram +

5.5 Class 1,2, and 3 Supports Subprogram

• 5.6 Class 1,2, and 3 System Pressure Testing Subprogram 5.1.1 Multiple Component Concep1 s The multiple component concept is used frequently in the selection of annpining-components in a variety of Code Exaiaination Categories. Basically, for a group oflike components (i.e., multiple nonpiping components, such as valves, pumps, heat exchangers, etc.) typically, equipment of similar design and performing a similar function the Code may require examination of only one component from the group of these multiple-components. Where the multiple component concept is applied for selections in this -

document, it is so noted under the appropriate Code Examination Category / Item. Refer to Appendix A for multiple-component group listing.

5.1.2 . Selection Optimization Where possible, selections should be made to optimize examination performance and still meet Code requirements; however, other variables (such as selection of previously.

examined compunents) may' take precedence over optimization. Some examples of-selection optimization are:

'

• Selection of components which may have augmented examination requirements

- which duplicate the Code examination methods required for that same component.-

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l M:lae Yankie Atomic Power Company Third Interval tsi Program I

7 V + Selection of components having more desirable plant locations, or several components in close proximity to each other, to minimize scaffolding, insulation removal, AIARA, and other implementation-related requirements.

5.13 E.cutfErautill Relief Requests, referenced within the applicable portion of their associated subprogram, are discussed in Section 4.0, and are contained in Appendix B.

5.1.4 Selection Itnsis The selection basis provided for each Code Category and/or item iepresents the initial ~

component selections for the third inservice inspection interval. However, throughout this interval, changes in plant configuration resulting from plant repairs, replacements, or modifications and changes to the ISI Outage Plan are cause to review these selection bases, to ensure continued conformance to Code requirements. This section is intended to clearly provide the information necessary to support the initir.! ISI component selections for the third interval, and to make easier the evaluation of the effect of plant changes, ISI Program revisions, or other situations which may impact ISI Program commitments.

These selection bases r epresent the minimum number of component selections necessary n to satisfy the Code requirements.

(j 5.1.5 DefinitlDn1

• Structural Discontinuity Welds (SD) - Includes circumferential weld joints at pipe-to-vessel nozzle, pipe-to-valve body, pipe-to-pump casing, or pipe to-fittinc. Fitting-to-fitting connections shall also be considered structural discontinuities for the purposes of this program. Gross structural discontinuity (GSD) welds (reference _

Category C A) are junctions between shells of different thicknesses, cylindrical shell to conical shelljunctions, shell (or head) to-flange welds, and head to-shell welds.

• Terminal End Welds (TE) - The extremities of piping runs that connect to -

structures, components, or pipe anchors, each of which acts as a rigid restraint or provides at least two degrees of restraint to piping thermal expansion. Note: This definition (reference IWA-9000) is interpreted to include circumferential welds in piping within 3 pipe diameters of the centerline of rigid pipe anchors or anchors at the penetration of the primary reactor containment, and branch connection welds (e.g., branch pipe-to-weldolet, or branch pipe-to-safe end) in which the main process pipe is at least 3 times larger than the branch run. Terminal ends to vessels (TEV) are generally considered to be the pipe-to-safe end or pipe-to-nozzle weld of a-vessel.

5.1.6 ISI Procram Tables A Contained in Appendix G are the ISI Program Tables. These tables are a detailed listing C/ of all nonexempt components and their supports which are part of the overall Isl 5-2

Mime Yankee Atomic Power Company Third IntervalIM Propum Program at Maine Yankee. Iriformation pertinent to the ISI Program and subsequent companent selection / scheduling for this intenal are contained within these tables.

5.2 CIASS 1 (IWII) WELDS / COMPONENTS SUllPROGRAM

!.2.1 EXUnination Cattgory B A. Pressure Retninine Welds in RearlDI_Ytut!

5.2.1.1 - Shell Welds, item Numbers 111.11 and 111.12 In accordance with Table IWB 2500-1 and Notes 3 & 4, only one beltline region circumferential weld and one beltline region longitudinal weld are required to be examined this intenal.

The Federal Register (Thursday, August 6, 1992 34666), however, has imposed an augmented requirement which will require 100% of the reactor vessel shell welds to be examined during the first period of the third intenal. Derefore,100% of the reactor pressure vessel shell welds shall be examined during this inspection interval.

5.2.1.2 Ilead Welds, item Numbers H1.21 and 111.22 In accordance with Table IWIb2500-1 and Note 4, the accessible length of one circumferential weld and one meridional weld shall be selected for examination this O interval. The selected welds shall be the same welds selected for examination during the second inten al.

5.2.1.3 Shell-to Flarge and llead-to-Flange Welds, item Numbers B1.30 and 111.40 In accordance wi.h Table IWB 2500-1, eacn weld, subject to the requirements of Code Examination Category B-A, shall be selected for examination this interval.

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4 Mdne Wakes Atomic Power Cornpa:y TMrd Intervalist Program l

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5.2.I A Category Summaryl l'xamination Category ll A Code leeru Total Total to be f bruber la Plant Ysamined Remt ks 131.11 3 3 Reg Guide 1,150; rederol Register 8/6/92 34%6 U1.12 9 9 Reg Guide 1.130; l'edatal l

Register s/6/92 34666 111.21 2 i Reg 0utde t.150 .3 111.2 2 13 1 Reg Guide 1.130 DI.30 1 1 Re: O mde 1.150 DIA0 1 1 Reg Guide 1.130 Totals. 29 16 5.2.2 Ihamination Category 1111. Pressurt Retalning Welds in Veifels Other Than Reactor Ycisch .

5.2.2.1 Pressurlier Shell to IIcad Welds, Item Numbers !!2.11 and 112.12 v .

i In accordance with Table IWB 25001 and Notes 2 & 3, all circumferential shell to head welds and one foot of one longitudinal weld per head (intersecting the circumferential >

weld), subject to the requirements of Code Examination Category B B, shall be selected for examination this inter.al. Longitudinal welds selected for examination during the second interval shall be reselected for examination this intenal, 5.2.2.2 Steam Generator licad Welds, item Numbers B2.31 and 112.32 In accordance with Table IWB 25001 and Notes 1 & 3, one circumferential weld and one meridional weld per head of one of the three steam generators (multiple component ,

concept), subject to the examination requirements of Code Examination Category B B, shall be selected for examination this intenal. For item B2.32, there are 5 bottom head meridionalwelds and 4 extension rinit meridional welds for each steam generator. Table -

IWB 25001 references Figure IWB 2500 20(d), which indicates that one meridional weld from each area (total of 2) shall be selected for examination this inten al. Welds selected for examination during the second interval shall be reselected for examination this .

interval. Refer to Appendix A for multiple component group listing.

5.2.2.3 Steam Generator Tube Sheet to IIerid Welds, item Number B2.40 in accordance with Table IWB 25001 and Notes 1 & 3, one tube sheet to-head weld 6f

~

one of the three steam generators (multiple component = concept), subject to the examination requirements of Code Examination Category B.B,'shall be selected for -

" ~ N cxamination this interval.- The weld selected for examination during the second interval 54 ,

I.

_ , , ._- , , . . - - - . . - - - - e- - _ m-_ _ ---

Mains YorAce Atomic IWtt Cbmpany 1hird Interstl ISI Progtsm shall be reselected for examination this inteival. Refer to Appendix A for multiple-component group listing.

5.2.2.4 IIcal thchangers (Primary Side) . Shell, item Number 112.60 in accordance with Table IWB n001 and Notes 1 & 3, tube sheet to head welds of one heat exchanger among a group of heat exchangers performing a similar function, subject to the examination requirements of Code Examination Category B B, shall be selected for examination. Since the Regenerative lleat Exchanger is the only heat exchanger applicable to this Category /ltem and it has two tube sheet to. head welds, both shall be examined.

5.2.2.5 Category Summary:

t Examination Category 1111 Code linn Total Number of Total to be Number laliant Compment liaminal Rwaarks Grovin  !

112.1 1 2 N/A 2 112.1 2 4 N/A 2 11231 12 1 1 4 welds let steam generator 11232 27 1 2 9 welds per steam generstor .

(5 on llcad. 4 on Iht. IUng) n240 6 1 2 2 welds per sicam generator n2.(4 2 N/A 2 Totals. 53 . 11 ,

5.2.3 E5amlnlill0fLCnirgory ll-D. lisil l'enetratjun Welds of Non]tLbLl'cHels finsncsliga l'regram_l0 In accordance with Table IWB-2500 :, all Class 1. components subject to the _

requirements of Code Examination Category B.D shall bc selected for examination.

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Maine Yankee Atomic Power Company

'lhird Interval ist Program 5.2.3.1 Category Summary:

Examination Category 11.D Code item lotal Total to be

"*I _.,I" E"".I.__..__ b"*l"#

?.' ._ .

!!3 90 6 6 113100 C 6 113.110 6 6 n3120 6 6 U3.130 6 6

!!3.140 6 6 Totals. 36 36 5.2.4 EMtmlnall01LQltrgory it E. Pressur.cd[tinLulng htihhl'tt1CitRLlun_Wtids in Vessch 5.2.4.1 Partial Penetration Welds, item Numbers 114.12 and 114.13 in accordance with Table IWIs 25001,25% of all partial penetration welds in the control rod drive nozzles and vessel instrumentation nozzles shall be selected for examination this interval. Selections should be evenly distributed among the different types of partial-penetration welds by selecting 25% by Code item Number.

5.2.4.2 Pressurizer IIcater Penetration Welds, item Number 114.20 In accordance with Table IW13 25001. all pressurizer heater penetration welds shall be selected for examination.

5.2.4.3 Category Summary:

Examination Category ll-E Code Item Total Total to lie Number in Plant 11am'med ltrmarks 14.12 65 17  ;$% sample, Conduct during sptem hydrostatic test IM 13 42 13 23% sampic; Conduct durmg system bydrostatic test D4.20 120 120 Conduct during sptem hydrostatic test Tot als,.. 2tt 150 56

Maine Yanhos Atomk Po**r(Wpny 1hird interni til hosr:m 5.2.5 thatnhiatl01LCalfguEll:EftfRHitlMDIDIDLDhillnihr_MrlaLWelds

^1 In accordance with Table IWH.2500.I, all Class I components subject to the requirements of Code IIxamination Category B.F shall be selected for examination.

5.2.5.1 Category Summary:

I'xamination Category lll' Code Itna Total 1etaltotie  !

Nwnlar la I'lant Itmamined I1540- 2 2

)

, 113.3 0 4 4 n3.130 17 17 D1140 10 to Totals . 33 33

+

5.2.6 linininallnn_Calfgury ll G 1. IfreMultlMaining.llDllitig._Grtafer Than 2 InchenJn >

lilatacitt 5.2.6.1 Henctor Vessel, item Numbers 116.10 through 116.50 Inclusive In accordance with Table IWB 25001, all Class I components within the subject Code ,

item Numbers shall be selected for examination.  ;

5.2.6.2 Pumps, Item Numbers 116.180 through 116.200 Inclush e -

Selection of the reactor coolant pump bolting shall be in accordance with Table f IWB.25001, Note 3, *For ... pumps, ... examinations are limited to components selected

.for examination under Examination Categories ... D.L 2, ... ." Referring to Examination '

Category B L.2, Pump _ Casings, the multiple component concept applies, and examinations are limited to one of three reactor coolant pumps. Flange surface (Item B6.190) is only required to be examined if the connection is disassembled. Refer to .

Appendix A for multiple-component group listing.

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=. . _-  :..-.. . ..-. . - . - - . - . . . ~,

i Mrine Ytnkte Atomic Pomer CompaIy -

'I%d intem! Isl Prc; rom

/ l

) 5.2.6.3 Category Summaryl Ihamination Category ll G 1 Code lans total Number of 'tutal to be Number la N at Compoecnt 1.tamined Manarkt ,

U "'"I".,,_ j IE10 54 N/A $4 lbg ovide 1,65 t

D6 20/30 81 N/A BI Reg Guide 1 Al 116 40 54 N/A $4 lleg Ovide 1 As IE50 54 N/A 54 Reg Guide 143 116.180 48 1 16 16 per reactor contant pump 14190 3 1 i per reactor rootent pump m' hen connection is damembled 116 200 48 1 16 16 per tractor toolant pump Totals... .M2 . 276 5.2.7 E3amblathtn Category ll G 2. Pre 51RttRtlahlhlgl!ullitig11Mht111 tid.ht$1}ILUJAllttiti 5.2.7.1 Reactor Vessel, item Number 117.10 In accordance with Table IWB 25001, all Examination Category B O 2 bolts, studs, and nuts in the reactor vessel shall be selected for examination.

5.2.7.2 Pressurizer, item Number 117.20 In accordance with Table IWB 25001, all Examination Category B-0 2 bolts, studs, and - ~

nuts in the pressurizer shall be selected for examination.

5.2.7.3 Steam Generntors, item Number 117.30 Selection of Examination Category U-O 2 bolts, studs, and nuts for steam generators is in accordance with Table IWB 25001, Note 2,'For ... heat exchangers, examinations are limited to components selected for examination under Examination Categories ...-D B "

Referring to Exrmination; Category B B, Steam Generators, the multiple component concept applies, and examinations are limited to one of the three steam generators.

Refer to Appendix A for multiple component group listing.

5.2.7.4 Piping, item Number 117.50 In accordance with Table IWB 25001, all Examination Category B-O 2 bolts, studs, and nuts in piping which is subject to the requirements of Code Examination Category DJ shall be selected for examination, 58 ,

--e # - - -- =-.# .m , . _ . - - - --- - ,

t; -

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- A. Mair.e Yankee Atornic Power Company

,, y Bird intc rval !$1 Program r

5.2.7.5 Valves, item Number 117.70 Selection of Examination Category B O 2 belts, studs, and nuts for vahes is in accordance with Table IWB 25001, Note 2, 'For ... valves, examinations 1 re limited to components selected for examination under Examination Categories .. B M 2."

Referring to Examination Category B-M 2, Valve Bodies, the multiple component concept applies, and examinations are limited to one valve in a multiple component group. Refer to Appendix A for multiple. component group listing.

5.2.7.6 Category Summary:

Examination Cates:ory ll G 2 Code lugn Tutal Nuist.cr or 'I otal Io lie Numlier is the Coiuponent liamined Heinarks

" 3" D7.10 32 N/A 32 D7 20 20 N/A 20 11730 120 1 40 40 per steam generator D7.50 $ N/A 5 117.7 0 11 4 4 Valve Groups 3. 4. 9. & 10 Totals. 231 - 101 5.2.8 LuminalltuLCattunILhlldnirgIdA11aduntnts l For Vench in accordance with Table IWB 2500-1, there are no required examinations during the third inspection interval for this Code Category.

5.2.9 liMuninallH!LCaltantLllAhtintitEtllllulHLWghts in Piping In accordance with Table IWB-25001, and Relief Request No.10, the welds selected for examination shall consist of a 25% sample of all Class 1 nonexempt circumferential, branch connection, and socket welds in each system which are subject to the requirements of Examination Category ;-J.

Note: All dissimilar metal piping welds are examined in accordance with Category B F; however, in accordance with note 1(c) of Table IWB 25001 for Category B.J, these dissimilar metal welds are to be included in the total population and sarnple calculation for Category B.J.

The 25% sample calculated for each system shall include:

a all terminal ends connected to vessels (refer to paragraph 5.1.5 for definition of terminal ends);

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Maine Yankee Atomic Powcr Company 1hlid interval ISI Program l

• other welds where high stress levels are expected; e all dissimilar metal welds; and e additional welds so tha' the total number of welds selected for examination within each system equals 25% of the total population for that system. These additional welds selected for examination shall take into consideration previously examined welds, weld size, accessibility, and ALARA.

The selected welds shall then be reselected for examination during subsequent inspection intervals.

~

A portion (one pipe diameter length but not more than 12 inches) of the longitudinal

. velds intersecting any of the selected circumferential welds shall be examined coincident with the circumferential weld.

5.2.9.1 Category Summary:

Ihaminallon Category lbj Code Item Total Numlier la 1%nt Remarks D9.ll 275 2 4' N!'S Cirtumferential O' 119.21 217 < 4' NPS Circumiciential 119.31 7 ;t 4' NPS llranch Ccmnection D9.32 27 < 4* NPS 11 ranch Ccmnection D9.40 319 Socket Welds Totals... &43 5.2.9.2 System Summary:

thamination Category Ibj Splem Sunmiary ,

Total Total Reg'd Niandatory Standatory hiandatory Remaining Sptne ILF BJ Total 25 % Ibj ILJ liigh B l' Reg'd Ibj Name Welds Welds Welds' Samide' TEV Mids Stress Welds Welds Sam ple' Cll 2 192 194 49 0 19 2 28 DR 3 133 136 34 0 9 3 22 1151 0 129 129 33 0 1$ 0 18 RCS 28 391 419 103 18 18 25 41 Totals 33 E45 873 221 15 61 33 109 Nrde it Total welds includes both Category D-l' and ILJ per Note 1(c) of hble IWD.2500-1 for Code Category thj.

5 10

Maine Yankee Atomic Puutt Company 1hird Interval ist Program I

Note 21 Splem $ ample ralculations gesulting in fractional nives are tvunded up to ensure that the minimum required casmination tamples are met Note 31 l'inal remaining ILJ sample is calculated as fonows

((ILP + HJ) ' 2.M) - (ILJ 11N's) - (ILJ liigh Steru)- (ibi') . Remaining Reg'd ILJ Sample 5.2.10 lhamlaallun Category ll K Idntrgral_AtladmttalduLl'litlutd'umndutd Vnh es in accordance with Table IWB 2500-1, there are no required examinations during the third inspection interval for this Code Category.

5.2.11 lhatulunilE0_Catetury ll 1 lditm lil2.w. PowECashte Welfl1 Selection of Class 1 reactor coolant pump caing welds for examination is in accordance with Table IWB 25001, Note 1," Examinations are limittJ to at least one pump in each group of pumps performing similar functions in the system. . . ." The multiple-component concept applies; therefore, examinations are limited to the casing welds of one of the three reactor coolant pumps. Refer to Appendix A for multiple component grouplisting.

5.2.11.1 Category Summary:

1:samination Category 11-1 1 Code hem Total Number er Total to be Numbe r lalhnt Component limuined Remarks G roups H1210 3 1 1 1 wcid per reactor coolant pump.

Ihamine when disassemtiled per Rehef Request L Totals... 3 + 1 5.2.12 lhatninallon Catsgury_II.L-2dttpLIUJ,20, PumECasings Selection of Class 1 reactor coolant pump casings for examination is in accordance with Table IWB-25001, Note 1,' Examinations are limited to at least one pump in each group of pumps performing umilar functions in the system, .. ." The multiple component concept applies, and examinations are limited to one of the three reactor coolant pumps.

Refer to Appendix A for multiple-component group listing.

?

5 11

Maine Yankee Atomic Pontt Company Third Interval 151 Prognm O

V 5.2.12.1 Category Summary:

lhaminution Category 111,2 Code item Total Number of Total to be Number la Plant ' Comgenent Examined Remarks Groirps  !

D12.20 3 1 1 1 per teactor coolant pump.

Ihamine when danssembled per Relief Request L Tota ts... 3 . t  !

5.2 13 Examination Category ll M.I. Iluttilll2.30 nnd Ill2A0. Valve llody Welds Selection of Class 1 valve body welds for examination is in accordance with Table IWB 25001, Note 3, Examinations are limited to at least one valve in each group of.

valves that are of the same size, constructional design, and manufacturing method, and that perform similar functions in the system, ... ." The multiple-component concept applies, and examinations are limited to one valve in each valve group. Refer to Appendix A for multiple component group listing.

5 2.13.1 Category Summary:

Examination Category ll M.1 Code item Total Number of Total to be Number la I%nt Component Enamined Remarks Groups B12.30 2 1 1 Valve Group 5 D12.40 6 2 2 Valve Groups 4 and 10; lixamine per Relicf Request lb Totals._ B . 3 5.2.14 Examination Ca@corv Il M 2. Item 1112.50. Valte llodies Execedine NPS 4

+

Selection of Class 1 valve bodies for examination is in accordance with Table IWB 2500-1, Note 3, " Examinations are limited (o at least one valve in each group of valves that are of the same size, constructional design, and manufacturing method, and that perform similar functions in the system, ... ." The multiple component concept .

applies, and examinations are limited to one valve in each valve group. Refer to Appendix A for multiple-component group listing.

O 5 12

. _ . . m

Maine Yentes Atomic Power Compaxy i uttd interval 151 Pitram ,

,q-.

-Q 5.2.14.1 Category Summary: ,

Etaminallots Category ll.M 2 Code I nm Total Number of Total to be Number la 1%nt Comienent I;tamlued Hanarks Groups D12JO 26 9 1 per group Valve _06oups 1,2,3,4,6,7,8,9,10 Ihamine when disassembled per [

Relief Request L Totals 26 . . I per group 5.2.15 Elaminallin1_ Category 11.N.I. ItenL1U2d(Lininjor or Ikattor.Vesnj in accordance with Table IWD.25001 Note 1, all areas made ticcessible for examinadon by removal of components during normal refueling outages shall be selected for  ;

examination, 5.2.15.1 Category Summary!

Examination Category 11 N.1  ;

O

'Q.

Code liens Number Total la l' tant Total to be' l'.namined itnaarts .;

1113.10 1 1 All accessitste areas; Refer to Procedure 3.1748; thamine once cach inspection perloo. 3 Totats 1- -1 5.2.16 Examina11on - Category H.N.2. Items 1113.50 and 1113.60.1(caIlpr Yessel interior z 611achments (PWI.11 In accordance with Table IWB 25001, all accessible interior attachment welds shall be -

selected for examination, 5 13' W

y y .- , , , , - . ., E . 5

Maine Yankte Atomic Pontr Company

^!brd Inte rval ISI Program 5.2.16.1 Category Summary l'xatnination Category ll N.2 Code Itun Total Total to be Number la11 ant ihamlued Remarks 1113.50 1 1 New Code liem; All accessible utlJa.

Refer to Procedurs 317.68 for component identification and locations.

Dr .50 1 1 New Code litm; All actessible wclds.

fiefer to Procedure 3.17.6 8 for component identification and locations.

Totals... 2 2 5.2.17 Elapilnation Cattgury ll N 3. littp 1113.70. litnmvatile CortSitpport Strutlutti in accordance with Table IWB-25001, all accessible surfaces subject to the requirements of Examination Category B N 3 shall be selected for examination.

5.2.17.1 Category Summary:

I'xamination Category ll N 3 Code litsu Total Total to be Number inliant Esam:uis! Remarks U13 70 1 1 All accessible surfaces.

Totats- 1 1 5.2.18 EAamination_Cattgury 11-0. Item 1114.10. PttnuteRetalningEtlis in Control. Rod lioniings In accordance with Table IWB-2500-1, pressure-retaining welds of 10% of the 28 peripheral control rod drive housings, subject to the requirements of Examination Category B-0, shall be selected for examination, 5.2.18.1 Category Summary:

Examination Category 15 0 Code Itein Total Total to be Number la Plant Examined Ruuarks

[114 10 23 3 10'4 Sampic Totals ... 28 3 5 14

Mame Yatikee Atomic Power Compeny

( 'Ihird Internt ist l'rograrn 5.2.19 homination Caltgery B PJ Pressure Relaittiligfumpantuli See Section 5.6 5.2.20 Jhamipalla!Lfaltg017J1.QJ1tamJ1tutrator Tubing in accordar ce witu Table IWB 25001, Note 1, the extent and frequency requirements for volumetric examination of the steam generator tubing shall be in accordance with Plant Technical Specifications. In conjunction with Plant Technical Specifications, Regulatory Guide 1.83 shall also be utilized.

53 CIASS 2 (IWC) WELDS / COMPONENTS SUllPROGl(AM 53,1 Esamina110nfategary C-A>_P.tnsurnikialnhigMtidi.jn Pressure Vessels Examination of Category C A welds is in accordance with IWC 25001 and Note 4,'In the case of multiple vessels of similar design, size, and service (such as steam generators and heat exchangers), the required examinations may be limited to one vessel or distributed among the vessels." Therefore, the multiple-component concept applies, and examinations are limited to the equivalent of one vessel for each group of vessels. For O ltem C1.10, the welds required to be examined are limited to weld 3 at gross structural discontinuities. The welds selected duiing the second interval shall be reselected for examination this interval. Refer to Appendix A for multiple-compenent group listings.

5.3.1.1 Category Summary:

Exainination Category C A Code Itetu Total Nuniber of Total to be Nurnber ta l%nt Component Examined Reinarks Groups C1.10 9 1 3 3 wclds per steam generator.

C1.20 8 2 3 2 welds per steam generator. ,

I weld per IUIR heat exchg.

C130 5 2 2 1 wsto per steam generator.

I scid per RilR heat exchgt.

a 3.tg 22 -

53.2 E.xamination Catteory C-H, Pressure-Retalnine Nonle Welds in Vessels Examination of Category C-B welds is in accordance with IWC 2500-1 and Note 4. The multiple-component concept applies; therefore, examinations are limited to the O equivalent of one vessel for each group of vesseb. Additionally, examinations are limited 5-15

i Miino Ytnkes Atomi Yower Company 1Nrd tritetval 151 l'rugram h

G.

to those nozzles at terminal ends of nonexempt Category C F piping runs (as described  ;

in IWC 25001, Note 1) which are selected for examination under Examination Category C-F (per Note 2). The welds selected during the second interval shall be .

reselected for examination this interval. Refer to Appendix A for multiple-component group listings. ,

53.2.1 Category Summary:

Examination Category C Il

. Code item Total Nmober or Total to be ,

Number la F* ait Cocose.eut Exambmi Remarks g Groups C2JI 10 2 4 2 welds per steam generator.

2 welds per IUIR heat eachgr.

C2.22 6 1 2 2 insido in&l per steam generator.

Totals... 16 - 6 533 I;mD11millon Category C.C. IntegadA110timtentifor Vessels. Plplag.fumps. and Vah es i

5.3.3.1 Pressure Vessels, Item Number C3,10

=In accordance with IWC 2500 1, Note 2, In case of multiple vessels of similar design and service, the required examinations may be conducted on only one vessel? Therefore, the >

multiple component concept applies. Components selected shall have been selected for examination during the second interval. Refer to Appendix A for multiple component group listing.

5.33.2 Piping, Item Number C3.20 In accordance with IWC 25001, Notes ? and 4, examinations are limited to attachments o' those compor,ents required to be examined under Examination Category C-F, and the components initially elected r, hall be reexamined over the service lifetime of the compenent.

Note: Five of the 22 piping integrally welded attachments are located on piping which is not required to be examined due to its wall thickness.

L 53.33 Pumps, item Number C3.30 :

In accordance with IWC 25001, Notes 3 and 4, examinations are limited to attachments -

~

of those components required to be examined under Examination Category C 0, and the -

components initially selected shall be reexamined over the service lifetime of the-A'g component. Referring to Category C 0, Note 1,' the multiple-component concept applies; therefore, only one pump per group of pumps of similar design, size, function,-

5 16

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

Maine Yankee Atomic Power Company

'!hltd interval Isl Program l

and selvice need be examined during this interval. lle'er to Appendix A for a listing of multiple component groups.

5J.3 A Category Summary:

thatninution Category C C Code Iqna Total Number of lotal to tw Number in Ihnt Cotapouent laam*un.d Itnuarks Groups C310 18 1 6 6 per steam generstcir C320 22 N/A 17 5 attachments are krated ott piping < .375 wall thitLness.

C3.30 5 2 2 1 per LPs! pump i per CS pump Totals.- 43 25

] .

53A faamlnallanlategunf lild'LeuurerIktaining_ mms _it1Attsintilidilainini.SinLuc liiginAllov Pining in accordance with IWC 2500-1, Note 2, "The welds selected for examination shall include 7.5%, but not less than 28 welds, of all austenitic stainless steel or high alloy welds not exempted by IWC 1220. (Some welds not exempted by IWC 1220 (e.g., > NPS 4 piping welds which are < 3/8 nominal wall) are not required to be nondestructively examined per Examination Category C-F 1. 'ihese welds, however, shall be included in the total weld count to which the 7.5% sampling rate is applied.)" Longitudinal weids sha)! be excluded from the total to which the 7.5% sample is applied, since they shall be scheduled for examination in conjunction with the intersecting circumferential weld, if selected.

Note: Any Class 2 dissimilar metalwelds (if any) will be included in Category C-F-1 in accordance with ASME Section XI Code Interpretation XI-1-89-57.

"The examinations shall be distributed as follows:

(a) The examinations shall be distributed among the Class 2 systems prorated, to the degree practicable, on the number of nonexempt austenitic stainless steel or high-alloy welds in each system (i.e., if a system contains 30% of the nonexempt welds, then 30% of the nondestructise examinations required by Examination Category C-F-1 should be performed on that system);

(b) Within a system, the exa~minations shall be distributed among terminal ends (TE's) and structural discontinuities (SD's).. prorated, to the degree practicable, on the number of nonexempt terminal ends and structural discontinuities in that system (in the event that proration calculations indicate essentially zero TE selections, a minimum of one TE selection shall be made.); and 5-17

Maine Yenkee Atomic l'ontt Company l Ditd intervtl 151 l'rgram (c) Within each system, examinations f. hall be distributed between lines sizes prorated to the degree practicable."

Notel Refer to Paragraph 5.1.5 for definitions of terminal ends and structural discontinuities.

5.3.4.1 Category Summary:

Examletation Category C.F.1. Item Summary Code linu lotal Number la Plant Rnuarks N/A 543 Nonesempt piping welds > 4' NPS, and c 3/8 nominal ws,II.

N/A 0 Nonenempt piping welds a 2' NPS, and 5 4' hPS, and 51/5 nominal wall, C5.11 330 > 4' NPS Circumferential C5.21 188 a 2* & 5 4' NPS Circumferential C3.30 48 Socket Welds C5 41 1*: a 2' NPS Dranch Circumferential Total 1120 5.3.4.2 System Summary:

Examination Category C.F 1 System Sample Summary Totals Include Item = N/A Totals Do Not Imlude Item = N/A 7.5 % Systeu Systnu . Systein 10% of SD% of .TE SD System Total Sasuple Total Total Total Total Total Total - Reg'd Reg'd Name Welds' Size' - Welds Other TC+ SD TE+SD Sample' Sample' !

TE's _ __ SD's.-

CII 287 22 IM 4 130 0 30% ' 97.0% 1' 21-CS 327 25 99 5 80 14 5.9% 94.1 % 1 24 IISI 195 15 195 9 183 3- 4.7% 95.3 % 1 14 1.S1 - 40 3 40 0 40 0 0.0% 100.0 % 0 3 R11R -271 21 109 4 99 6 39% 96.1% 1 20 TOTAli. 1120 86 577 22 531 23 . . 4 S2 Note it Spiem weld totals include those welds identified as Category C F.1. Item Number N/A (thin wall piping),in order to producc the calculation of the sampic required within each system, Actual wtid selections shall exclude these welds.

'i Note 2: Overall sptem sample calculations resulting in fractional values are rounded up, thus ensuring that the minimum required -

cramination samples are achieved.

5 18

1 Mains Yankee Atomie Power Company Third Interval 151 Prgr:m

- Note 3 Final 1E and SD sample calculations whic h result la fsactional values are rounded to the centest whtde number, however, la the event that the rr uhant required 1E sample rounds down to tero, the *II required sample will be tour.ded up to one, and the SD required sarr'de wdl be lowesed by one.

5.3.43 Summary by Line Size j l

Category C.F.1 Sunnmary fly Line Sire - 1 l

Wild l'ipe Total Total  !

Sptein Tne Site Welds Siented Cil $D $ 22 $

SD 3 12 2 l

- 4 SD 4 96 16 f 1E 3 3 1 12 4 1 0 (3 - 14 1 0-

. 16 1 0  ;

. IB ' 12 0 i e

SD 14 21 6 t SD 16 30 9 SD 16 29 9 ,

(- *IE 14 3 1- .I

, e 1E 15 2 0- ,;

1851 - 10 3 0-'

SD 2- 4 1 SD 3' 28 2

-SD 4 75 $

SD -6 4 1-SD 8 3 0 '

SD  : 10 69 5-l 1E 4 -6 0

~~

TE 10 3' 1-

~151- - SD - 6- 40 3 1 RilR . 12 3 0 i- t

. . 14 3 0- l SD '12 $1 10 -..

SD 14 40 9-5 10 l-  :

.-. . _ ._t . . - _ _ - - . . . _ -- . _ _ - _ _ _ _ . . _ - . _ . _ _ _ . _ . - - . - . . _ _ - . . - . . ,

Maine Yankee Atomic Poetr Comjcy 1hird laterd ISI Pre nm

-f. P Category C.F 1 Summary fly Une Size Weld 111 e Total Total l Systwo Tnw me mids S A ted SD 16 8 1 1E 12 o 1E 14 1 0 1E 16 2 1 Totals.., . . $n .

5.3.5 Est11111tiluttfaircory C.P.2. Pressure.RWisitigMsitisjnfarbon l or laiw.Allov Steel

• l'.lRitig ,

in accordance with IWC.25001, Note 2, "The welds selected ivr namination shall include 7.5%, but not less than 28 welds, of all carbon and low. alloy steel welds not -

exempted by IWC.1220. (Some welds not exempted by IWC.1220 (e.g.i > NPS 4 piping welds which are < 3/8 nominal wau) are not required to be nondestructively examined per Eumination Categon C.F.2. These welds, however, shall be included la the total. .

weld count to which the 7.5% sampling rate is applied.)" Longitudinal welds shall be -  ;

y excluded from the total to which the 7.5% sample is applied, since th , shall be scheduled for examination in conjunction with the intersecting circumferential weld, if - .-

selected.

"The examinations shall be distributed as follows:

(a) "Ihe examinations shau be distributed among the Class 2 systems prerated, to the degree practicable, on the number of nonexempt carbon and low. alloy steel welds '

in each system (i.e.,if a system contains 30% of the nonexempt welds, then 30% of the nondestructive examinations required by Examination Category CJ 2 should be performed on that system);

(b) Within a system. the examinations shall be distributed among terminal ends (TE's) and structural discontinuities (SD's)... prorated, to the degree practicable, on the number of nonexempt terminal ends and structural discontinuities in that system (In -

the event that proration calculations indicate essentiauy zero _TE selections, a minimum of one TE selection shall be made.); and  ;

(c) Within each system', examinations shall be distributed between lines sizes prorated to the degree practicable."

Note: Refer to Paragraph 5.1.5 for definitions of terminal: ends and structural ,

discontinuities.

O 5 20

=>

M:ine Yankee Atomic Mtr Corrpany

'Ihird Interwl ISI Program

'7 \

\

V /

5.3.5.1 Category Summary:

Examination Category C r 2. llem Surnniary Code Iteau lotal Nuinbt r in Plant Rnuarks

. . _ . ~ _

N/A 0 Nonenempt pipirig welJs > 4' NPS, and

< 3/8 nominal mall.

N/A 0 Noi.entmpt piritig wtIds a 2' NPS.

and n 4' NI'S, and $ 1/3 nominal wall.

C3.31 369 > 4' NPS Circumfertnilal C3 61 0 a 2* A s 4' NPS Circumferential C3.70 0 Sodet Wclds C$,81 33 x 2' NPS Dranch Orcumferential ToteL 4M 5.3.5.2 System Summary:

p V Exarninution Category C.r 2 Sptem Sainple Sutninary Totah include Itau = N/ A Totals Do Not luctude tiemu = N/A 1.5 % S3 stetu S3 stein 53 stria TE% of SD% of TE SD S3 steau Total Sample Total Total Total Total Total Total Req'd Reg'd Natue mids' She' Wi4d4 TE's SD's Other 1E+SD 1E+SD Sasuple' Sample' A1W 146 11 146 3 132 11 2.2% 97.8 % 1 10 IW 116 9 116 7 94 15 6.9% 93 1 % 1 b MS 142 11 142 9 127 6 66% 93.4 % 1 10 TOTAli 4N 31 404 19 333 32 -

• 3 28 Note 11 Sptem weld totals include thme wcids identi6cd as Category C-1;2, liem Number N/A (thin wall piping), in ordet to produce the calculation of the sample required within cach sptem Actual wcld selections shall exclude these welds.

Note 2t Overall system sample calculations resulting in fractional w!ues are rounded vp, thus en6uring that the minimum required examination temples are achieved.

Note 3:  !"inal TU and SD sampic calculations which result in fractionali Tit are rounded to the nearest whole number; however, in the event that the resultant required Til sampic rounds duwn it ero, the lil tcquired samvt will be rounded up to one, and the SD tequired rampts will be lowered by one.

(

,7

.$ )

v 5-21

Maine Yades Atomk Power Comgany 1hird Intem! ISI Pavgram 53.53 Summary by Line Slre e

Category C.I'.2 Summary 113 IJue Sire Mid Pip Total Total Sptete T3 M Sia Wi4ds Seinted s= - -"

AlW . 6 11 0 SD 6 132 10 1 11 6 3 1 IW . 14 15 0 SD 6 3 1 SD 12 10 1 SD 14 I;l 6 1 11 14 4 0 ll!V 14 3 1 MS . 30 6 0 SD 6 $9 4 SD 18 6 1 SD 30 02 5

'll! 6 3 9

• 111 30 3 0 TIN 30 3 1 Totah., . . 404 31 4514 I 53.6 }handnat[nglattgnty C.G. Pressurr.llttalDbg Welds in Pun 1DUUldlahts .

53.6.1 Pumps, item Number C6.10 In accordance with IWC 25001, Note 1 "In case of multiple pumps ... of similar design, size, function, and service in a sy. stem, the examinution of only one pump among each group of nultiple pumps . is required." Therefore, the multiple-component concept applies, and only one pump in each group shall be selected for examination. The pumps selected for examination during th, second interval shall b: reselected this interval.

Refer to Appendix A for multiple-component group listing.

.O I 5 22

Wine hnkte Atomie hmet company 1hird Interval ISI Propam l'

E 53.6.2 Catepry Summary:

?  ; __n_-- '

i:unninnuon eniegmy c c code ti.e 1cial compiment Totalia t.e 2""d*L - 3"!!""' C'""8* ' 2 ""d"'d

___3*

• t _ --

3 c6 w

. l, s 2 2 ire,1.rslrump i ter cs turns Tou a .. 3 -

2

-___m--- -.

G M

5.4 (145S 3 (IWD) Wl:1.DS/COh!PONI:Ni SUllPROGRAh!

5.4J DJinlinal10tLClifmficilhAJhllaitulD4 5.4.1.1 Integral Attachments, items DI,2,3.20 through DI,2,3,60 "The examination requirements for these Code Categories / Item Numbers are identical; therefore, they have been combined for the purposes of this discussion, Integral attachments are listed in T6le IWD 23001 for examination by the type of 5 O support associated with the integral attachment.

utilization of the multiple component concept for integral attachments on nonpiping Note 3 of Table IWD 25001 allows components.

Additionally, the mtegral attachments selected for examination 1, hall correspond to those component supports selected for examination under Code Case N-491 (reference Section 5,5), Therefore, selection of Class 3 integral attachments cor esponds to those component supports selected per Category F A below That is, if a selected Class 3 support has associated integral attachments, then the integral sitachment shall also be selected for examination Refer to Appendix A for multiple.

component group listings.

j I

5 23 F

Maine Yankto Atomic Power Comps:y

'IWd Internt ist Pmge:en l

i V 5.3.6.2 Category Summary: i l

I thamination Category C G 4

Code ltna Total CompuuM Total to ve l Nwater la the Group thamliwd Rnmarks  ;

l C6.10 5 2 2 1 Pet LPSI Pump .

I Per CS rump  !

Totals $ + 2 l i

5.4 CLASS 3 (IWD) WELDS /Coh1PONENTS SUlil'ROGRAh!

5.4.1 lhaminntlunfaltgories D A. D_.IlatnLD:C _

5.4.1.1 Integral Attachments, items D1,2,3.20 through DI 2,3.60 The examination requirements for these Code Categories /ltem Numbers are identicall y therefore, they have been combined for the purposes of this discussion.

Integral attachments are listed in Table IWD 25001 for examination by the type of

(

support associated with the integral attachment.. Note 3 of Table IWD 25001 allows utilization of the multiple component concept for integral attachments on nonpiping _

cornponents. Additionally, the integral attachments selected for examination shall 1 correspond to those component supports selected for examination under Code J Case N 491 (reference Section 5.5). Therefore, selection of Class 3 integral attachments ,

corresponds to those component supports selected per Category F A below. That is, if.

a selected Class 3 support has associated integral attachments, then the integral attachment _ shall also be selected for examination, Refer to Appendh A for multiple. 1 component group listings. >

s u .

5 23 s

- , . , 5 . <m-- - - - - .m,m. ~ - , _ . . , . . . ,.~,,a~,- m. - - - - - - -

i i

Wins Yankee Atornic Pont Compny

'lhltd latend Isl l'rogem 5.4.1.2 Category Summary:

thornintition Categories D A,il,C -

Code tiem Total Number of *1ptal to be Nmnber la liant Component Esasunned Hemarks U 'V"3" ._ __ _.

D2.20 41 4 7 I pct fulR heet exchariger (2)

.]

I per TCC heat encheriger (2)  !

I per scc heat e achanger (2) l 1 per SW purnp (4) 31 on piping D2 40 7 N/A 1 7 on piping D3J0 1 N/A 1 1 on the 1*P hest exchanger Totals. 49 - 9 5.5 CIASS 1,2, and 3 SUPPOltTS SUllPitOGitAM Class 1,2, and 3 piping and nonpiping supports shall be examined in accordance with the requirements of ASME Code Case N 491. Relief Request No. 7 was prepared to allow for the use of the alternative examination requirements of this Code Case. "

In accordance with paragraph 2510 of Code Case N 491: Nor, piping supports to be-examined shall be the supports of those nonpiping components that are required to be .

examined under IWB 2500, IWC-2500, and IWD 2500 by volumetric, surface, or visual-  !

(VT 1 or VT 3) examination methods. Piping supports to be examined shall be the supports of piping not exempted under !WB 1220, IWC-1220, and IWD 1220, This requires that all nonexempt Class 1,2, and 3 piping supports shall be subject to examination, including supports of nonexempt piping not required to be examined in-accordance with IWB. lWC, and IWD (e.g., portions of Class 2 piping lines not required to be examined ur. der Code Categories-C F 1 and C F 2 due to the piping wall ,

thickness).

5.5.1 13pjnglypports. Item Numbers Fl.10. F1.211atd f1.30 t

Per Examination Category F A (Code Case N-491), piping supports shall be selected for examination us follows:

(a) *lhe total number of piping supports required to be selected for examination.is determined by the ASME Section XI classification of the pipe support (i.e., Class 1, '

2, or 3).

• Class 1 (item number Fl.10): 25% of the nonexempt population

.p/

.A Class 2 (Item number Fl.20)

Class 3 (Item number Fl.30) - 10% of the nenexempt population 15% of the nonexempt population 5 24 d ev*r W _-r- p e & er-r's-  %- -?+w rs e W+= - - . - - *e 21'

• Mame Yankee Atomic Power Conipany

'Ihird Internt ist Program (b) All supports shall be assigned a support type, such as: Anchor, Snubber, Rigid, or Spring.

(c) Selecticns shall be distributed among the required number of supports determined in (a) above by system and type, prorated by the number of supports of each type within each system, 5.5.2 &npJping Suppras. Item Number FI A0 For multiple components (e.g. pumps, heat exchangers, etc.) within a system of similar design, function, and service, the multiple. component concept applies, and the supports of only one of the multiple components shall be selected foi examination.

For nonpiping components which are not a part of a multiple. component group, all supports for that component shall be selected for examination.

5.53 Category F.A Ihni Summarli Examination Category F.A . Item Summary Code liern Total Number of Total to lee Number la l'lant Component l'ammlued Resuarks Groups F1.10 229 N/A $8 25% sample (Class i pipe supports)

T1.20 341 N/A $2 15% sampic (Oass 2 pipe supports)

P130 38 N/A 4 10% sample (Oass 3 pipe surgerts)

Pl.40 51 8 20 100% of Cass I,2, A 3 nonpiping ,

supports (utilizing the muhiple.

romponent rule).

9 per steam generator (3) 2 pcr RCP (3)-

1 per CS pump (3) 1 per 1. PSI pump (2)

I per SW pump (4) .

1 per PCC IrrX (2) 1 per SCC 1rrX (2)

I per IUIR IrrX (2) 1 on RPV -

1 on PZR 1 on TP lrrX Totals 659 -

til O

5 25

Mainc YarAce Aiomic rt.ct company 1hird interol IM Pn. gram 5.M DPL811 PPD 11_8H!!1[llDU_I'J ChlWSMlt!&lllbl.811NilNMC

,u . . _ -

%g i l'inini0ation Category liA Pipe Suliliurl Sunninary liy Class, Splem, and Support Type (herau Systan letals Authort Nmbbe rs Rigid' Springs Raq'd Sptuu  %  %  %  % linal' Satund RW' Sys ikq' S>s Req' S3s R eg' S) Reg' Reg'd Cim S 10 Pat hu pl 10 1d kupl ill 1tl Supi 10 10 kupi. lti lti kupl. kmpi

_ _ . _ntno._ _ , _ . -_ _ _ _ , _ ., _ ._ ~ . - . ,

t il 5V 25 % 15 4 6k i 2 14 1 52 MI 13 1 1.7 0 15

{l

' 1 DR 31 U% 8 0 00 0 0 00 0 27 87 1 7 4 12 9 1 8 1 ll$1 72 25 % 18 4 56 1 0 00 0 f3 m) 16 3 42

~

1 16 1 RCS 67 25 % 17 1 1.5 0 13 19 4 3 IV 24 4 5 il 50 7 9 17 Clau 1 Totals 229 - 59 9 . 2 15 4 16 . 41 42 .

11 55 3

2 AlW 43 15 % 7 4 93 1 0 00 0 29 67 4 4 10 23 3 2 7 2 Cil 57 15 % 9 11 19.3 2 0 00 0 40 70 2 6 6 10.5 1 9 2 CS 71 15 % 11 9 12 7 1 0 00 0 35 493 6 27 38 0 4 11 2 IW 5B 15 % 9 a 6.9 1 16 27 6 2 16 27.6 3 22 37.9 3 9 2 1151 31 15 % 5 E 25 R 1 0 00 0 17 54 8 3 6 19 4 1 5 2 131 6 15 % 1 0 00 0 0 00 0 4 66 7 1 2 33 3 0 1 2 M5 30 15 % 5 3 10 0 1 9 Do 2 6 22 0 0 17 40 0 2 5

~

2 ItllR 45 15 % 7 2 44 0 1 2.2 0 20 44 4 4 22 48 9 3 7 Clau 2 Totals 341 .

54 41 7 26 - 4 16 - 27 107 . 16 54 O 3 3

AlW PCC 19 9 10 %

10 %

1 2

3 44 4 15 8 0

0 0

0 00 00 0

0 5

7 12 55 6 63 2 2 1 0 4

00 21.1 0

0 1

2 3 SCC 10 10 % 1 0 00 0 0 00 0 7 7v 0 1 3 30 0 0 1 Cim 3 Totals 3h - 4 7 0 0 - 0 24 4 7 . 0 4

._.s

. -,- =___, m _ __-

m-Gr und l utah 60N .

117 57 . 9 41 N 35 - 72 136 . 27 116 4

- m=r . wn-m . m=r== .

NOTI: 1 Oversti spiem sampic (uilumn 5) talculations whuh rault m fractional ulucs arc rounded up, thus crituring that the mmimum required enamination samples are athnud NOTI: 2 Required sampic calculanons for rath support type are rounJcd to the nearest whole number, which may result in slight differenu:s between the initial meroll required sptem sampic (culumn 5) and the final tverall required spiem sarnple (kst column mhich is the cumulsiwe required san'ple by support typc) Ahhough not readily apparent, this dcnation has been compensated for by adjusting culumn 14, the required ripd support san >ple tiy ( i 1), as nettuary.1his column was chosen for this compenution, since there arc marc of Ibesc supports ovciali Ws:hout this compenssuurt, the final required sampic (IAst column) could equale to Icu than the nunimum icquired umpic merell for the givtn Clau/ item Number.

NOTE 3 Rigittype supports conut of the folloorg Auf Itu.tramt. Resir.nnt, llorvontal Restrami, Vertical Restraint, Lateral Reuramt, Vc rtical/ lateral Itcstramt. llanps. IW llanpr. %pport, and ShJing Support.

O 5 26 s

Mainc Yankee Atomk Poutt Contany Dird inistval 151 h ogram O 5.6 SYSTEh! PRESSUllE TESTING SUllpHOGilAM 5.6.1 Gutmtl System pressure tests shall be conducted in accordance with the rules of IWA 5000,

" System Pressures Tests," to the extent practical. Where such impracticalities exist, relief has been requested aad alternate testing requirements have been proposed. Rellef Requests are discussed in Section 4.0 and are contained in Appendix B. Article IWA 5000 delineates the general pressure test definitions and conditions required for performing a visual examination (VT.2) of components to verify system integrity, Table IWA 52101 references the appropriate Subsection and subattleles for Class 1,2, and 3 components.  !

5.6.1.1 Test Description As stated in paragraph IWA 5211 of the Code, "The pressure retalning components within each system boundary shall be subject to system pressure tests, under which conditions visual examination (VT 2) is performed, in accordance with IWA.5240 to detect leakages. The - quired system pressure tests and examinations, an referenced in Table IWA 5210 4, may te conducted in conjunction with one or more of the following system tests or operations:

(a) A system leakage test conducted following opening and reclosing of a component in O the system after pressurization to nominal operating pressure.

(b) A system functional test conducted to verify operability in systems (or components) not required to operate during normal plani operation while under system operating pressure.

(c) A system inservice test conducted to perform visual exarnination (VT 2) while the system is in service under operating pressure.

(d) A system hydrostatic test conducted during a plant shutdown at a pressure above nominal operating pressure or system pressure for which overpressure protection is -

provided.

(e) A system pneumatic test conducted in-lieu of a hydrostatic pressure test for components within the scope of IWC and IWD."

5.6.1.2 Pressure Retalning Iloited Connections

• For systems borated for. the purposes of controlling reactivity, insulation shall be:

removed from the pressure retaining bolted connections (not comprised of stainless steel '

• bolting and not exempt per paragraph L.6.1.3) for a visual examination (VT.2). Since any leakage will have developed as residue, the system is not required to be pressurized during the VT 2 examination. The examination will, howeveribe scheduled at the same frequency of that system pressure test. This requirement represents an alternative test 5 27

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

Mehe Y:: Lee Atomk Pont Company hird Imsvnt 1st Program l

method ta that proposed by IWA 5242, paragraph (a), and is substantiated by Relief O, Request No. 8.

5.6.1.3 Exemptions Pressure-retaining bolted connections at pressure-seal bonnets, packing bolts, and bolted connections downstream of normally closed vu.t and drain valves. ,

5.6.1.4 Corrtttive Measures Corrective measures shall be in accordance with IWA 5250 and Relief Request No. 9. In l accordance with Relief Request No. 9, corrective measures for leakage at bolted connections l shall consist of the following, in lim of the requirements of IWA 5250(a)(2): l i

(a) Removal of the insulation (b) Plant Engineering Department (PED) evaluation (c) Corrective action per PED evaluation 5.6.2 Class 1 System Pressure Toting in accordance with IWil 5000, the pressure-retaining components shall be tested at tha frequency stated and visually examined by the method specified in Table IWD 2500-1,.

Examination Category 13 P. The system pressure tests and visual examinations shall be O conducted in accordance with IWA 5000, IWB 5000, and Code Case N-498. Reactor coolant -

V shall be used as ths pressurizing mediura.

5.6.2.1 Class 1 System Leakage Test (a) The pressure-retaining boundary during the system leakage test shall correspond to the reactor system coolant boundary, with all valves in the normal position, which is required for normal reactor startup. The VT 2 examination shall, however, extend to and include the second closed valve at the boundary extremity.

(b) The system leakage test will be conducted prior to the plant startup following each reactor refueling outage or following opening and reciosing of a component in the system after pressurization to nominal operating pressure. (Note: The opened component (s) need only be inspected.)

(c) 'Ihe system leakage test shall be conducted at a test pressure not less than the nominal i operating pressure associated with 10% rated power. Pressute and temperature shall be attained at a rate in accordence with the heatup limitations specified for the system in the Plant Technical Specifications and shall be maintained during the performance of the VT 2 examination.

(d) The VT 2 examination may commence upon achieving the test conditions.

O '

5 28

Maine bnkte Atomk hmt Cornpany hd Interval Isl f*rognm 5.6.2.2 Class 1 S3 stem Il3drostatic Test (a) ne pressure retaining boundary during the system hydrostatic test shall friclude all Class 1 components within the system boundary.

(b) The r,ystem hydrostatic test shall be conducted at or near the end of each inspection interval, prior to reactor startup, and at the same pressure and temperature as a system leakage test.

(c) The system hydrostatic test pressure and temperature shall not exceed limiting conditions for hydrostatic test cune, as contained in the Plant Technical Specifications. _

(d) Prior to performing the VT-2 visual examination, the system shall be prnsurized at non Sal operating pressure for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for insulated portions and 10 minutes for noninsulated portions. The system shall be maintained at nominal operating pressure during the performance of the VT 2 visual examination.

5.63 Gaulbhm.frmutt_Inth!g 1'

In accordance with IWC-5000 the pressure tetaining components within each system bounday shall be subjected to the system pressure tests and visually examined by the O method specified in Table IWC 2500-1, Examination Categon C li. The system pressure tests and visual examirations shall be conducted in accordance with IWA 5000, IWC 5000, and Code Case N-498. The contained fluid in the system shall sene as the pressurizing medium except in steam systems, where either water or air may be used.

Where air is used, the test pressuie shall permit the detection and location of through-wallleak. ages in components of the system tested.

5.63.1 Class 2 S3 stem Pressure Test Functional or Inservice (a) The boundary subject to test pressurization during a system inservice test shall extend to those pressure-retaining cornponents under operating pressures during normal system service.

(b) The boundary subject to test pressurization during a system functional test shall include only those pressure retaining components within the system boundary pre:surized under the test mode required during the performance of a periodic system (or component) functional test.

(c) The system shall be examined each inspection period (40 months).

(d) Nominal operating pressure and temperature during the insen' ice or functional test, as applicable, are required for the examination.

(e) For an inservice test, no hold time is required, provided the system has been in 4

operation for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

5 29

Mame Yankte Atomic hmtr Compny 1 bro Interolist Propam (f) For a functional test, a 10 minute hold time is required af ter attaining system operating pressure.

5.63 2 Clast 2 System Ilydrostatic Test (a) 'the boundary subject to pressuri;ation shall ettend to all Class 2 components included in those portions of systems required to operate or support the safety systern function, up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required.

(b) A system pressure test shall be conducted at or near the end of each inspection interval or during the same inspection period of each inspection interval.

(c) Nominal operating pressure as per Code Case N 498 is allowable for the hydrostatic test pressure.

4 (d) Prior to performing the VT 2 mamination, a 10 minute hold time for uninsulated and a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hold time for insulated components is required. *lhe pressure is to be maintained until the VT 2 examination is completed.

5.6.4 Cla5L3_SntritLPnswte Testhu:

In accordance with IWD 5000, the pressure retaining cornponents within the boundary of each system specified in the Examination Categories of Table iWD 25001 (listed below) shall be pressure tested and examined in accordance with Table IWD 25001.

The system hydrostatic test shall be conducted in accordance with IWA 5000, and IWD 5000. The contained fluid in the system shall serve as the pressurizing medium.

Category D A: Systems in support of reactor shutdown function.

Category D-B: Systems in support of emergency core cooling, containment heat removal, atmospheric cleanup, and reactor residual heat removal.

Category D C: Systems in support of residual heat removal from spent fuel storage pool.

5.6.4.1 Class 3 System Pressure Test Functional or Insenice (a) 'Ihe boundary subject to test pressurization during a system inservice test shall extend to those pressure retaining components under operating pressures during norm:l system service.

(b) The boundary subject to test pressurization during a system functional test shall include only those pressure retaining components within the system boundary pressurized under the test mode required during the performance of a periodic system (or component) functional test.

5 30

Z!.,

I M2ine Yankee Atomic Power Compark-Dird Interni 1st Psogram -

7 p' d (c) The system shall be examined each inspection period (40 months).

-(d) Nominal operating pressure of the system operation or functional test, respectively, shall be acceptable for the examination.- ,

(c) For an inservice test, no hald time is required, provided the system has been in '

operation for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(f) For a functional test, a 10-minute hold time is required after attaining system operating pressure.

5.6A.2 Class 3 System Ilydrostatic Test  :

(a) The system boundary extends up to and including the first normally closed valve or. -

valve capable of ntomatic closure, as required, to perform the safety : elated system -

function.

(b) The system hydrostatic test shall be performed at or near the end of each inspection-intelval or during the same inspection period of each inspection interval.-

(c) The system hydrostatic test preaure shall be at least 1.10 times the system's lowest -

act pressure relief valve (or system design pressure for tho.a systems without relief valves) for systems with design temperature of 200*F or less, and at least 1.25 times .

b V the system's lowest set pressure relief valve (or system design pressure for-those systems without relief valves) for systems with design temperature above 200*F.-

(d) Prior to performing the VT 2 examination, a 10 minute hold time for uninsulated and a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hold time.for insulated components is required. The pressure is to be maintained until the VT 2 examination is completed.

5.6.5 Eressure Test Drawings The Class 1,2, and 3 systems, or pot tions thereof, subject to system pressure t'ests are depicted by the Plant "FM" series; drawings (flow diagrams). The following table '~

represents the systems within the scope of the ISI Pressure Test Subprogram:

Systems Within the Scope of the ISI l'ressure Test Subprogram Systein . C1.us 131 Drawing Relief Request

~

Reactor Coolant l 90A 8,9 Chemical & Volume Control t/2/3 91A, 91n, 91C 8.9 I  !!!r Preuurt Safety injection 1/2 91A, 31A 8,9 Primary Sampling - 1/2/3 96A

~

RCP Scal Water 1/2 10ln , 8.9 Main Steam 2 70A 5 31

._L.__._.._:____--_ . :_ _ _

3 Maine Yankee Atomic Power Compny

- Third Interval ISI Program --

I

- /m l 5( l~

^ %/ -

1 1

Systems Within the Scope of the ISI Pressure Test Subprogram-System Class Iht Drawing Relief Request Auxiliary Steam 2/3 72A -

Steam Generator Feedwater 2/3 73A Secondary fligh Pressure Drain 2/3 87A t

Steam Generator Ulowdown 2 87D Residuallleat Removal 2 92A 8,9 Containment Spray 2 92A 8,9 low Pressure Safety injection 2 92A 8,9 Primary Component Cooling '2/3 94A, 94 B, 94C 6 Post Accident Sampling ~!

2/3 960 1

Containment Purge /llydrogen Control 2/3 %C Charging Pump Suction licader Vent - 2 101B Service Water -3 77A:-

Secondary Component Cooling 3- 78A, 78D 6 m Lubricating & Fuel Oil 3 80A Diesel Ocnerator Starting Air 3 88A Gas 3 89A~

Primary Vents & Drains 3 91A,91B,91C, 92A,93A,96A,100 A' Fuel Pool Cooling 3 97A' 8,9 i.

Doron Recovery -3 98A -

Liquid & Solid Waste Disposat 3 99A'-

Waste Gas Disposa! 3- 100A Seal Pot 3 101A L

U 5 32-

l l' Maine Yankee Atomic Power Com;any Third Interval is! Prognm 6.0 REPAIRS AND REPLACEMENTS PROGRAM 6.1 SCOPE This program applies to Safety Class pressure-retaining components and their supports identified by the Inservice inspection Program.

6.2 EXCEPTIONS Exceptions to the scope of this program are identified in IWA-4400 and IWA 7400 of the -

19S6 Edition of ASME Section XI.

o 63 IMPLEMENTATION The following references are utilized in implementing the Repairs / Replacements Program in accordance with the 1986 Edition of ASME Section XI:

Procedure 0 081 Material Identification and Control

• Procedure 0-091 Control of Special Processes

• Procedure 0 09-2 Documentation of Welding and Associated Eqripment

• Procedure 0-16 3 Work Order Processing Procedure Procedure 5-216-5 Rework identification and Corrective Action Program

• Procedure 17-212 Engineering Design Change Request Procedure 17-23-1 Design Change installation Instructions

• Procedure 17 27 NDE of Safety Class Components and Their Supports

• Procedure 17-226 Technical Evaluations O

6-1

r Maine Yen';ei Atomic Power Comy:ny hird interval ISI Program

,rx

- (,) APPENDICES

• Appendix A - Multiple Component Group Listing

• Appendix B Relief Requests

• Appendix C - Guidelines for Program Maintenance and implementation

• Appendix D Listing of Applicable FM Series Drawings (P&ID's)

• Appendix E - Zone, ISI Drawing, and Line/ Equip Number Cross Reference

• Appendix F ISI Drawings (Piping Isometries and Component Identification Drawings)

• Appendix G ISI Subprogram Component Tables b

o

~ Appendix A Meine Yankee Atomic Power Company Multiple-Component Omups Third Intervat ISI Progrtm O

MULTIPLE-COMPONENT GROUPS O

l L

LO

Appenda A Maine Yankee Atomic Power Company Multipic-Component Groups *Ihird Interval 151 Program Multiple-Component Groups Group Component Conigwment Cast:Porged! Cede Number Id(s) Description Size Material Clus , Punction I!X 01 L3A Ileat thchanges N/A ASNtB SA515 2/3 Residual llent thchangers EL3B G R-70 IIX 02 E4A Ilcal Enhanger N/A ASME SA516 3 Primary Component Cooling fleat E4D G R70 Exchangcrs IIX 03 E-5A Ileat E.xchanger N/A ASME SA516 3 Secondary Component Cooling IIcat E-5B GR70 Exchangers PU-01 P-1-1 Pump N/A Cast Stainicss 1 Reactor Coolant Pom3x -

P-1 2 SA351-CIDI P-1-3 PU-02 P 12A I Pump N/A AVIN A182-3M 2 low Pressure Safety injection Pumps P-12B PU-03 P41A Pump N/A ARTM A312 3N 2 Containment Spray Pumps P-61 H P41S PU64 P-29A Pump N/A ASTM D169- 3 Service Water Pumps P 290 A U O Y 614 P 29C P 29D 9 SG-01 L11 D1-2 E-1 3 Steam Generator N/A A533 GR-D CLI 1/2

~

Steam Generaton VI 01 1151-16 Cate Vaht 10' Cast Stainicss 1 S! to RCS Cold legs IIPSI Stop Vahes; IISI-26 ATiht-A351- Pressure Seal Bonnets llSIO6 CP8M VI 02 11S1-17 Check Vahe 14' Casa Stainicss 1 51 to RCS Cold Legs Barrier 'A' Valves ~

1151-27 A351 GR CIMI 11S1-37 VI 03 IISI-61 Check Valve 10" Porged Stamiess 1 Si to RCS Cold I. cgs - Barner 'D' Valves 11S142 SAIS2-03N 1151 4 3 VL-S4 IJ51-12 Check Valve 10' l'orged Stainicss 1 LSI to RCS Cold Legs - Barrier *IP Vahrs LSI 22 AKlM A152-1316 LSI-32 VI-05 PR-S-14 Relief Vahe 2.5"/4* Porged Stainicss  ! Pressuruer Relief Lines PR-S-15 ASlht-A182 P316 VL-06 RC-M 11 MOV-Gate 33 5' Cast Stainless 1 RCS Loop ilot Ieg isolation Vahts RC-M 21 AFI M-A351 RC-M 31 ClM1 VL-07 RC-M 12 MOV. Gate 33.5* Cast Stamiess 1 RCS Loop Cold Leg Isolation Valves RC-M-22 ATPM.A351 RC-M-32 CIMi VIAS RC-M 13 MOV Ang!c 8' Cast Stamiess 1 RCS !. cop Dypass Isolation Valves 9 RC-M-23 RC-M-33 AYTM A351 CIEM

]

A- 1

_ _ _ _ _ _ _ _____ ~

Appenda A Maine Yankee Atomic Power Company Multip!c-Component Groups nird Interval 151 Program Multiple-Coinponent Groups Group Com ponent Compment Casul'orged/ Code Nuraler idis) Description Le Material Clan Function VL-09 IUI-M 1 MOV-Gate 12' Forged Staints.s 1 RilR from loop 2 Ilot leg . Stop Valves Ril M,2 ASTM A1821916 VI-10 SIA-M,ll MOV-Gate 14* .' urged Stainless 1 51 to RCS Cold 14p ha:ation Valves SIA M 21 ASTM-AIB21316 SIA M-31

?~

9.

O O

A-2

O c -

RELIEF REQUESTS O

O

Appendix B

' Maine Y:nkee Atomke Power Company 1 Relief Requests

' third intirval ISI Program -

-t ev n Beller Recuest - 01

-s System: Reactor Coolant Safety Class: 1 Category / Items: B-F, B5.40 and B5.130 i Components: Dissimilar metal welds:

Pay _{un#/Weldf_ Drawint#/ Weld #

MY Isi i Is, SGI MY-Is!-1-21 SSJ MY-Ist 1-1s, sSJ MY-Is!-122, SLD MY-INI 1 16, SGD MY Isl.123, s&n MY-ISI.1 17, SE-n MY lSI-124, SD6 MY-ISI 1 18, SEI MY Ist 124, SSis MY-ISI 1 18, sbJ MY Ist-12s, SSI MY-Is!-1 19, SED MY-Is!-124, SS2 MY ISI-l-20, s&B MY-Is!.127, 561 '

MY-ISI l 21, SS! MY ISI-132, SE2 Requirement:

n 1 e Perform a surface and volumetric examination once each interval-U Relief Request: Relief is requested from full volumetric examination of the above dissimilar metal welds, Basis for Relief: The above dissimilar metal welds join carbon steel piping with CPF8M cast stainless steel safe ends, Ultrasonic examination through the safe end materials does not provide discernible.

information because cast stainless steel is anisotropic, which causes attenuation and -

velocity changes, beam reduction, and scattering of ultrasonic waves. Therefore, thes2-dissimilar metal welds can only be effectively examined from the carbon steel side which would not encompass the full volume of the weld.'

It is also known that standard radiognphy is unable to-detect significant flaws in cast stainless steel.

Maine Yankee believes that attempting to volumetrically examine these dissimilar metal welds through the cast stainless steel material without possibility of discernible results is-neither reasonable or feasible and would increase costs and personnel exposures without-a compensating increase in the level of quality or safety, A' lternate Testing: Perform the required surface examination.

Perform a shear wave ultrasonic examination from the carbon steel side of the weld to

-q examine that side.

O Perform a refracted longitudinal examination from the carbon steel side of the weld to -

examine the dissimilar metal weld area.

B-1) i l

Appendix 0 Maine Yankee Atomic Pontt Company Wiicf Requests Third 1sterval Is! Program

, (7 Relief Reauest - 02

()

System: Reactor Coolant Safety Class: 1 Categories / Items: B-L-1, B-L-2, B12.10, B12.20 (pump casing welds and pump internal surfaces)

Components: Reactor Coolant Pumps P-1-1, P-1-2 and P-13 Requirement: ne examinations performed during each inspection interval shall include 100% of the pressure-retaining welds in at least one pump in a group of pumps performing similar functions in the system. The examinations required are volumetric for the casing welds -

and visual VT 3 for the internal surfaces.

Relief Request: Relief is requested from the volumetric and the visual examination requirements.

Basis for Felief: ne pump casings are made of SA351 CF8M material. This cast stainless steel has a -

large columnar grain structure which prohibits meaningful ultrasonic examination. The pumps and associated piping are in high-radiation areas which could reduce the quality of radiography by' severe fogging. De limited ability to inspect the casing is offset by the inherent fracture toughness of this material and cast stainless steel casings in general, ne service history of these pumps shows no reason to anticipate a service induced weld -

A failure and, of the pumps examined to date, no evidence of failure has been observed.'

Also, in an NRC letter to Maine Yankee dated July 14,1983, it was determined that the volumetric examination requirement was impractical and that a surface examination should '

be done in its place. Also stated in this letter was that the visual examination of the internal surfaces may be performed while the pump is disassembled for maintenance.

Note that the 1989 Code Edition (recently approved for use) now requires that the internal l

surface exams be performed only when the pumps are disassembled for maintenance,-

repair, or volumetric examination.

Alternate Testing: Perform a surface examination in lieu of the volumetric examination, and perform the-visual examination during disassembly of the pump for maintenance.

L l

l l.

l - p b

B-2

Rchef Requests "Ihird Interr_11st Prognm 77 Relief Reauest - 03, Q)

System: Reactor Coolant Safety Class: 1 Category / Item: B-J, B9. I 1 Components: Welds in cast stainless steel piping that were selected per Table IWB-2500-1, Category B-J, Notes 1(a) or 1(b):

Drawine# / Weld!_ DrawinFWeldt MY-Is! 1 17,1.111 MY4st 124,1 MY-Isl-1-17,1.1C MY ls! 1-24,2 MY-Is! 120,12n MY-Ist-124, 3 MY Is! 120,12C MY-ISl-1-24,10 MY-IsI 1-23,1311 MY ls! 123, t3C Requirement: Perform surface and volumetric examinations on selected welds once each interval.

[ Relief Request: . Relief is requested from the volumetric examination.

Basis for Relief: Maine Yankee utilizes CPF8M cast stainless steel materials in its pressurizer surge line, loop bypass lines, and pumps and valves in the RCS loops.

Ultrasonic examination does not provide discernable information because cast stainless steel is anisotropic, which causes attenuation and velocity changes, beam redirection, and scattering of ultrasonic the wave. Therefore these welds cannot be effectively ultrasonic examined.

Through experimentation, it has been shown that standard radiography (x-ray and gamma ray) was unable to detect known flaws in cast stainless steel samples, y Industry experience and studies have shown that due to the fracture toughness properties of this material, a significant defect would lead to a readily detectable leak before fracture.

Maine Yankee believes that attempting to volumetrically examine these welds without posribility of discernible results is neither reasonable or feasible and would increase costs and personnel exposures without a compensating increase in the level of quality or safety.

Alternate Testing: Perform the required surface examination.

u B-3

Relief tequests - Third Interval ist Program I

l

Reller Recuest - 04  ?

System: Various Safety Class: 1 Category / Item: B-M 2, B12.50 Components: Valves exceeding 4" nominal pipe size:

Valves by Groya Valves by Group Valves by Gruya Valves by G11ED lisI-16 IISI41 RC M-11 Ril M-1 1ist-26 11S142 RC-M 21 Ril M 2 InsI N Iisl43 RC-M-31 slA M 11 1Is! 17 LsI-12 RC-M 12 slA M 21 1151-27 LSI 22 RC-M-22 slA,M-31 lisI 37 LSI 32 RC-M 32 RC-M 13 RC-M 23 RC M 33 O Requirement: Visually examine 100% of the internal surfaces of one valve in each group of valves of similar design and function in the system.

Relief Request: Relief is requested from frequency of examination requirements of once per interval.

Basis for Relief: Maine Yankee presently has nine groups of valves in this category. These valves, due to normal plant operatien, have become extremely radioactive. These valves, when assembled, emit from 2 to 6 Rem /hr and when disassembled, emit over 50 Rem /hr.

Disassembly of these valves for the sole purpose of visual examination is impractical and presents a personnel safety hazard.

The service history of these valves shows no reason to anticipate a service induced failure.

Of the valves examined to date, no evidence of failure has been observed.

Note that the 1989 Code Edition (recently approved for use) now requires that the internal -

surface exams be performed only when the valves are disassembled for maintenance, repair, or volumetric examination.

Alternate Testing: Defer the visual examination to a time coincident with the disassembly of the valve for maintenance.

v i

B-4

- Appendix B . Maine Yalkee Atomic Power Compa y

R: lief Requests *Ihlid 1 terval 151 Program

.,g.

, Relief Recuest - 05

)

System: Reactor Coolant Safety Class: -1 Category / Item: B-F, B5.130 Components: Dissimilar metal weld:

Drawing #/ Weld #

MY-ISI-1 28, SE-29 Requirement: Perform a surface and volumetric examination once each interval.

Relief Request: Relief is requested from the volumetric examination.

Basis for Relief: Similar to the dissimilar metal welds of Relief Request No. 2 (RR-2), this weld joins- ,

carbon steel piping to a CPF8M cast stainless steel safe end.

And, for the same reasons as RR-2, this weld cannot be volumetrically examined through h

V the cast stainless steel material, however, unlike RR-2, this weld (SE-29) cannot be ultrasonically examined from the carbon steel side. Due to the geometry of the carbon steel pipe Otting it is not possible to get the ultrasonic wave into the required volume area of the part.

This weld is in a pipe that branches off the bottom of the loop 2 hot leg piping and is not isolable from the reactor vessel, therefore, remains water filled throughout a normal refueling outage. This line would only become drained if the reactor vessel was drained to below the loop nozzles or if a nozzle plug was installed in the loop 2 hot leg nozzle.

Therefore, radiography of this weld during a normal. refueling outage-would not be possible. Maine Yankee believes that reducing the reactor vessel water level or installing a nozzle plug solely for the purpose of a limited volumetric examination of one weld is an undue hardship without a compensating increase in the level of safety or quality; Alternate Testing: Perform the required surface examination.-

Perform radiography to the extent practical (carbon steel side) only if the line is scheduled -

to be drained during a refueling outage.

r \ ,

%/

B-5

Appendix B Mdne Yankee Atomic Power Company i

Relief Requests ' third Interval Is! Program l

g Relief Request .06 b

System: Primary Component Cooling (PCC) and Secondary Component Cooling (SCC)

Class: 3 Categories: D-A, D-B, and D-C Components: Lines: PCC-8. 9,12,15,16,17,514,515; and SCC-8,11,121, and 123 Requirement: IWA-5244(b) - Buried Piping Relief Request: Relief is requested from pressure testing requirernents of Table IWD-2500-1 for the subject lines.

Basis for Relief: The PCC and SCC Systems have both supply and return lines that are routed underground. This piping was not originally designed to facilitate pressure testing, as required by paragraph IWA 5244 of ASME Section XI,1986 Edition.

'Ihe systems are not equipped with valves capable of isolating the underground portions nor instrumentation to measure flow. The accuracy of current " clamp-on" flow measuring instruments is about il% of the reading. The PCC and SCC Systems operate at

. approximately 6000 gpm, which represents i60 gpm error for each end of the system or

.d il20 gpm total for a flow-in versus flow-out test. This inaccuracy would make it impossible to distinguish between real leakage and instrument error.

Maine Yankee monitors the system's surge tank level every four hours to determine system inventory. The tank level is read to the nearest quarter of an inch, which is about i2 gallons. Typically, the level in the tank varies by about a half-inch during a day.

This is due to thermal expansion or contraction and pump seal leakage. A very small leak can be recognized by trending this information and looking for a downward trend. This method has been successful in discovering small packing leaks. A significant leak in the system would be recognized quickly. The tanks are equipped with low-level alarms that sound in the Control Room. The alarms are included in Maine Yankee's preventive maintenance program.

Maine Yankee believes that current system monitoring practices provide a better indication of system integrity, on a continuous basis, than performing a flow test once every three years with potential inaccuracies of il20 gpm.

Alternate Testing: Maine Yankee will continue to monitor the PCC and SCC Systems' inventory for unexplainable changes on a daily basis. This is controlled by Maine Yankee's operation procedures.

b o

1 B4

- Appendu B M:ine Y:nkee Atomic Power Compery:-

lahcf Requests - Third intirval ISI Program TN Relier Recuest - 07 KJ

^

System: Various Class: 1, 2, and 3 Categories: F-A, F-B and F-C Components: Class 1,2, and 3 Component Supports Requirement: . ASME Section XI 1986 Edition, Subsection IWF, requires that component supports selected for examination be the supports of those components that are required to be examined under IWB, IWC, and IWD during the first irepection interval.

Relief Request: Relief is requested from _the requirements of Subsection IWF, except as specifically identified in the alternate rules of ASME Section XI Code Case N-491.

Ilasis for Relief: The Code does not provide specific guidance for component support exemption or selection criteria; therefore, user interpretation of the rulas may not meet the intent of the .

1- Code, in addition, the rules for additional examinations are general and cannot effectively complement the selection basis nor target specific failure modes.

'O

,V-Alternate Testing: The rules provided in ASME Section XI Code Case N 491 (which have been adopted into the 1990 Addenda to ASME Section XI) shall be utilized for the examination requirements of component supports in lieu of Subsection IWF.

l i

. v

B-7

, Appendix B ' ' Maine Yankee Atomic Power Company Relict Requests Third IntervalIsl Prqrem :

.. ,/7 Eclief Recuest - 08 L)

System: Various Class: 1, 2, and 3 Categories: B-P, C-li, D-A, D-D, and D-C Components: Class 1,2, and 3 Pressure-Retaining Components Requirement: ASME Section XI 1986 Edition, Paragraph IWA-5242(a), *For systems borated for the a purpose of controlling reactivity, insulation shall be removed from the pressure-retaining bolted connections for visual examination VT-2."... (Tables IWB 2500-1, IWC-2500-1, or IWD-2500-1 require a VT-2 (IWA-5240) to be performed in conjunction with the specified pressure test )

Relief Request: This Relief Request is intended to authorize attemtives to VT-2 system test conditions for those systems containing boron for the purpose of controlling reactivity.

1. Relief is requested from insulation removal and subsequent direct VT-2 examination for those pressure-retaining connections comprised of stainless steel bolting, r3

[ 2. Relief is requested from performing the direct visual examination of pressure-retaining bolted connections (not mentioned in L1 above) while the system / component is at test pressure.

Basis for Relief: 1. Maine Yankee requires quality standards for materials (insulation, thread lubricant, boron, etc.) that may come in contact with safety class stainless steel components, including bolting, such that impurities _ are not present in concentrations that cause stress corrosion cracking (SCC). SCC would not be detected by the VT-2 examination method anyway. The industry has publishco substantial information, such as EPRI NP-5679, regarding the resistance of stainless steels to boric acid corrosion. Maine Yankee believes that removal of insulation on stainless steel bolting for examination of degradation due to leakage of borated water is an undue hardship and will increase costs and personnel-exposures without a compensating increase in the level of quality or safety.

2. Leakage of borated water will leave an obvious residue of boron. This boron residue is " evidence of leakage" and inconsequential to the system's pressure at the time of the VT-2 examination.

Many of these systems are heat traced to enable the plant to maintain high concentrations of boron solution. Insulation removal would remire disabling the heat tracing which would be detrimental to the contained solution's fluidity and

, system function. The heat trace and associated insulation should be removed

-(o i when the system is not required for operation.

1 i

B-8

Appendix D.- M;ine Yankee Atomic Power Company R: lier Requests *1%d I:lerval ISI Program

[~l Many other systems are inspected at the conclusion of a refueling outage with the

'(/ reactor going critical immediately after inspection. To hold up reactor criticality is considered an undue hardship without a compensating increase in the level of quality or safety. The insulation should be removed and replaced when it would not impact critical path or incur unreasonaYe personnel exposure (ALARA).

Alternate Testing: 1. Evidence of leakage through insulation at pressure-retaining bolted connections comprised of stainless steel bolting will have its insulation removed and the leakage 'and bolting evaluated by the Plant Engineering Department (PED) to determine the appropriate corrective action. 1

2. Insulation will be removed and a direct visual inspection for evidence ofleakage at pressure-retaining bolting (not mentioned in 1 above) will be performed at the required frequency; however, the system / component may or rnay not be at pressure.

B

( 5 e

i

%J B-9

' Appendia B M:ine Yankee Atomk Power Company Rchef Requests Third Intervel l$1 Progrtm Rdiff itequst - 09 O

System: Various Class: 1,2, and 3 -

Categories: H-P, C-Il, D-A, D B, and DD Components: Class 1,2, and 3 Pressure Retalning Components Reqairetrent: ASME Section XI 1986 Edition, Paragraph IWA 5250(a)(2), ...'if leakage occurs at a bolted connection, the bolting shall be removed, VT-3 examined for corrosion, and evaluated in accordance with IWA 3100;"...

Relief Request: This relief request is intended to authorize alternatives to the removal of bolting at pressure-retaining connections when evidence of leakage is located during system pressure testing.

Relief is requested from verbatim compliance of IWA 5250(a)(2) for removal of bolting .

from leaking bolted connections to performing corrective action, as deemed necessary by Plant Engineering Department (PED), as determined by evaluation.

13 asis for Relief: Although a leaking environment may be a significant variable in the degradation of O. bolting, it is not the only variable and, in some cases, has no impact at all. Other variables involved may be the bolting materials, the leaking medium, duration of the leak, and orientation of the leak (not all bolting may be wetted), as well as monitoring of the leak. These items are important to consider before potentially shutting the plant down to remove bolting and perform inspections.

Maine Yankee believes that removal of bolting at leaking bolted connections is not always a prudent decision and may cause an undue hardship without a compensating increase in the level of quality or safety.

Alternate Testing: The Plant Engineering Department will evaluate evidence ofleakage at pressure-retaining bolted connections, considering the applicable variables discussed above, as well as any other impacting considerations, and prescribe the appropriate action. This evaluation methodolo;;y has been proven successful at Maine Yankee through the implementation of the Maine Yankee Doric Acid Corrosion Assessment Program (Reference NRC Generic Letter 88-05).

O 4 B-10

l Rchef Requests TNed Intuvul 151 higt m I

n Relief Rettuest . ID

() System: Various Class: 1 Category: B-J Components: Class 1 piping Welds Requirement: Note 1(b) of Table IWB 2500-1, Category B-J, requires the examination of pipe welds that exceed stress intensities of 2.4 Sm or cumulative usage factor of 0.4 under specl0c seismic and operational loads.

Relief Request: Relief is requested from verbatim compliance of the requirement speelned above to use existing pipe stress calculations and engineering judgment for selection of high stressed welds.

Basis for Relief: As permitted k 10CFR50.55a (b)(2)(ii), Maine Yankee has the option of using the 1974 Edition of Sect.on XI, as addended to Summer 1975 (74/S75), or the 1986 Edition for the extent of examination of Category IFJ pipe welds. The fundamental difference between these two options is that the 74/S75 Code limits the selection to a 25% sample but provides virtually no guidance for selection of welds to be examined; and the 1986 Code, although not being limited to 25% of the weld population, requires an intelligent selection

(] of pipe welds that are more likely to have problems over time, based on stress U considerations.

Maine Yankee agrees with the philosophy of the 1986 Code Edition, however. It unable to comply explicitly with the calculation requirements. Maine Yankee utilized a senior engineer with nea* 10 years of nuclear experience in engineering mechanics (structures, equipment, and L. ~> -

review all readily available pipe stress calculation of Category B-J piping. Typice.: m .nalyses were based on ANSI B31.1 formulas as opposed to ASME Section til formulas. The two Codes used slightly different factors in their formulas.

For the piping that had B31.1 stress analyses available, all welds that were close to 2.4 Sm were selected. (Note: gravity i ading was included, although it is not required.)

Also, highly stressed welds, as judged by the engineer, were selected even though stress levels were well below 2.4 Sm.

Where explicit stress calculations were not readily available, the engineer selected high stress points, based on engineering judgement. This situation is primarily limited to less than six-inch piping.

Maine Yankee believes that this intelligent method of selection is superior to the random selection philosophy of the 74M75 Code and that there is an increase in the level of quality and safety; however, to perform explicit calculations to comply verbatim with the g 1986 Code is an undue hardship without a compensating increase in the level of quality or safety.

j 1

B-11

Appendix B Maine Yankee Atomic Power Company Rehet Requests Dird laterval ISI Prtyram

)~

Alternats Testing: Perforrn Category D-J (note 1(b)) weld selections, based on existing stress analysis and enginecting judgment, O

O B-12

1. Appendia B -- Milne YcnLee Atomic Power Company Relief Requests hird I;terval Isl Program -

14elief Recuest - 11

{

%)

i System: Var ous 8

_1 Class: 1 l

Category / Item: B M 1/B12.40 Components: Stainless Meel valve body welds Inht.lu stA-M. :

SIA-M.21 sIA M.31 Requement: Perform a volumetric examination once each interval.

Relief Request: Relief is requested from the schedule requirement.

Basis for Relies Due to the geometry of the valve body, it is not possible to get the ultrasonic wave into -

the required volume area of the component.

10

(,j

' The valve is not isolable from the reactor vessel, and therefore it remains water filled throughout a normal refueling outage. This line would only become drained if the reactor vessel was drained below the loop nozzles or if a nozzle plug was installed. Therefore, radiography of this weld during normal refueling would not be possible. Maine Yankee believes that reducing the reactor vessel water level or installing a nozzle plug solely for the radiography of these valve welds is an undue hardship without a compensating increase in the level of safety or quality.

Alternate Testing: Perform a surface examination on the OD during the regular schedule, and perform the-required volumetric examination when the loop piping is drained during a scheduled refueling outage.

.,,~

!-- B-13 ,

. - . . . - . - ~ .- .. .~

. _ _ . ,- - , . ~ .

Appendix C . .

Maine Yankee Atomic Power Company Guidelines for Program Maintenance and impi~nentation . - Third Interval ISI Program '

9 b

z GUIDELINESLFOR PROGRAM. MAINTENANCE- -

O IMPLEMENTATION i

O

- Appadir C - M2ine Yadee Atomic Power Company Ouldelines for Program Maintenance and tmpicmentation 'Ihlid Intem! 151 Program -

p ,

i General -

t The Inservice Inspection Program will be revised for each 10 year inspection interval, as -

specified in 10CFR50.55a. The ISI coordinator is responsible for revising the ISI Program and shall have it approved internally prior to the start of a new inspection interval. The

- latest revision of 10CFR50.55a shall be used to determine applicable Code requirements for ~

the revised program. Changes to the ISI Program during the course of an interval shall be .

evaluated by the ISI coordinator to determine their significance an_d, subsequently, the ,

course of action required, as detailed below.-

Document Control

- The plant ISI coordinator is responsible for maintenance and control of the ISI Program anJ - t shall maintain the master copy, a working copy, and two other controlled copies of the ISI Program. Each copy shall _be clearly identified on the cover sheet with " Master C, py,"

" Working Copy," or " Controlled Copy No. _." and shall contain the ISI Coordinator's signature.

The master copy shall be kept in the ISI coordinator's fireproof file unless it is being revised.

The working copy and the other two controlled copies shall be ' retained by the ISI coordinator for his use or distribution at his discretion. ,

After completion of an inspection interval, and after all required' changes have been incorporated into the ISI Program Document, the ISI Program Document shall be transferred to the Technical File Center in accordance with Procedure 017 2.-

Program Revisions / Changes l When changes to the ISI Program may be required, it shall be _ brought to the attention of l~ the ISI coordinator, The ISI coordinator shall determine whether or not a change is necessary and, if so, whether it is a significant or insignificant change, as described below: ,

Significant changes are those which conflict with Code or Technical Specification -

requirements and require NRC approval, as specified by 10CFR50.55a. Relief Requests -

L shall be written for significant changes and are submitted to the NRC for approval, via-the licensing department, within one year of completing the affected inservice inspection.

-*- Insignificant changes are those which do not require NRC approval (e.g., typographical -

errors, changes in selection, or scheduling of components for examination which do not impact Code requirements).

(V}'

o C-1

Appendia C Maine Yankee Atomk Power Company OvWelines for Program Maintenance end Implementation Third Intervat ISI Program -

l

.O. List of Figures:

• Figure C.1 Inservice Inspection Program Change Process

• Figure C.2 Inservice Inspection Program Approval / Cover Sheet

• Figure C,3 Inservice inspection Program Change Log -

• Figure C.4 Insenice inspection Program Change Request -

0 1

O C-2

Appendir C _

Maine Yankee Atomic Power Company .

, e Guidelines for Program Mainten

nce and Implementition . Third Interval ISI Program v' Figure C,1 ISI Program Change Identified ISI Coordinator Evaluates for Significance Significant insignificant

• Wr!!e Rollef Request

• Complete Change Request ,

• Complete Change Request e Log Change Request e Log Change Request

• Place in Front of Wo*Ing Copy

_,O.

• Place in Front of Working Copy I

i Change Request Accepted Change Request Rejected

• Revise Master Program

• Revise CR and Rolssue, or;

• MaA Changes With CR Number

• Mark CR as Rejected

• Revise Master Change Log .

• Place in Front of Working copy

• Place Approved CR in Front of Master e Update Working CR Log

• Revise Other Copies to Reflect Mastor to Reflect Rejection

• Ucensing Submh Relief Roquest to the NRC (Significant Only)

I  ;

Relief Requect Approvod by NRC Roliot Request Rejected by NRC

• Update MastorChange Log and Relief * - Log Rejection in All Copies of Prograrn

- Roque.st to indicate NRC Approval, Cocument .e Void and Dato Working Copy of Reliof and Number, Date, Limitations Change Request -

= ISI Coordinator Shall Initial and Date Notes e Remove Robsf and Change Roquest From AllOther Copies

• Update Other Copios to Reflect Master

• Revise and Reissuo,if Applicable' Q)

C3 '

3 Appendit C Maine Ytnkee Atomic Power Cornpany outoctines for Program Maintenance and Implementttion Third Interval ISI Program p-~

\ )

Figure C.2 Maine Yankee Atomic Power Company inservice Inspection Progrnm-For The Inspection Interval From: to Date Pro , ram Issued:

Prepared Ily:

Plant ISI Coordinator .

fm .

Reviewed and Approved Ily:

l YNSD ISI Coordinator Performance Engineering Section Head PED Manager l

PORC

n. Plant Manager

\_)

C-4

Appendia C Maine Yankee Atomic Ponte Company Oudehnes for Program Maintenance and Implemensation ' third Intenal ISI Program Figure C.3 Maine Yankee Atomic Power Company ISI Program Change Log Change Request Approsal/ Rejection NRC Approval Number Description Date (Doc, Date, Tech File)

-- _g C-5

1

.i. App *ndia C ~ _ _

. Maine Yankee Atomic Power Compny Guidelines for Progrsm bia.ensnee and impicment: tion : '

. Ihird Interval 15I Program -

r\  ;

\s./ Figure C.4 ISI Program Change Request s

ISI Program For The Interval Chanj;e Request Number: Significant: ._ Insignificant: ,_,.

Date:

Description of Change:

Reason for Change:

\,

Add'l Approval For Significant Changes: Approval:

PED Manager Plant ISI Coordinator PORC - YNSD ISI Coordinator .

Plant Manager Performance Engineering Section Head I

d C-6

Appendia D htaine Yantes Atomic l'tstr Comieny Listirig cd Applicable IN Series Dram %p (l' AID's) "Ihlrd Interal 151 l'rogram O

APPLICABLE FM DRAWINGS O

O

Appe:dla D Maine Yankee Atomic hws: Company . t IJsting of Appliceble IN $arica Drswings (Palin)

%ltd intervel151 hogram t

Listing of Applicable l'M Scrits Drawings (l' AID's)

(Nimesempt 11pinl0

!)rawLng No. Title 1%f.70A Mein Steam Splem Piping I N 73A Steam Generator Peedwater Sptem Piping -

IN 78A Scrondary Compom <,4 (hling Sptem hping, f;heet 1 j 1%f 90A Reactor Cmlant $picm Piping i 1%t 91A Chemical & Volume Contsol and liigh Picuure Safety injection Spiem Piping, Sheet 1 ,

-+

IM 9111 Chemical & Voluene Control and liigh Ptn6ure Safety injection Splem Piping, sheet 2 1%ielC Chemical & Yolume Control and liigh heuvre Safety injection Splem Piping. $heet 3 IN 91A Residual liest itemoval. Containment Epray, and low Pressure Safety injection $ptem Piping ,

1%194A Primary Component Cooling Water Syneem Piping. Sheet 1 1 % I 4 811 Primary Component Cooling Water Spiem hpmg. Sheet 2 i

1%f.94C Primsty Ccmponent Cooling Water Splem Piping. Sheet 3 t

D v

9 o o f

t

., p D 1' -

z

-_L -

vv ^

-my p- y , ,v w- ,-g e,,pg, .

-Wy frw' v-,ww- v w g*W-'W v'r+ tw w+ wy ,e m'Wiw '+-W4' *--ww p- r re--,' r' T err'sn

"'hy

• 7v g Y

Appendu U Maine Yankee Atomic Power Company 7ene, Drmns, and IJne/11guip Cams Referente 1hird Inicrval ISI Program O

7 SONE, DRAWING, & LINE NUMBER CROSS-REFERENCE O

O

, Ap;<ndia 13 - .

M:ine Yankee Atomic Power Compny I

' Zone, Drawing. t.nd Une/14uip Crms Itelcrente Third Intervalist ric;cm i l

Zone Drawing, and Une/ Equip Number  :

Cross Reference Zone ISI !)runing 1lue/I'. quip No.

1 M%)St.11 R1 1 MY 15112 R.1 1 MY.lst l.3 R1 ,_

E

'2 MY.lSt.14 R.1 ..

3 MY.lSI 15 Ik11 ,

3 M%ISI 16 611 4 MY.lSt.l.7 lM2 ,

4 MY.lsl.18 612 5 MY.lSI.l.9 1113 '

5- MY ISI 110 IL13 6 M%lSI-1 11  !!.2 6 MY.lsl l.12 I! 2 6 M%ISI 113 IL2 ,

7 M%Isl.1 14 IM7 8 MY-!SI115 31-1/2*RC.1 9 MY.lSt l.16 3L1/2*RC2 10 MWISt.117 - 311/2*RG3 >

\

11 M Y.lSI1 18 311/2*RG7 b 12 MY.lSt.1 19 331/2*ltC-8 13 M%1sl.120 311/2*RC.9 ,

14 MY ISI 121 311/2*RC.12 15 M%151122 - 3L1/2*RC13 16 M%lSt.123 311/2*RC 14

~

, 17 MY 1SI 124 12*RC 6 ~

18 M Y.lSt.1 25 1D*RC-49 18 , M Y Is! 1 25 14*RC48 -

19 MY.lSt.l.26 10*RC 51 :

19 MWist.).26 14*ltC 20 MY ISI 127 10*RC 53 20 M%IS!-127 14*RC 52 -

21 - MY ISI-128 - - 12*RC.29 .

7 22 M%1SI-129 8*RC4 '

23 M%ISI 130 ?8*RC.10 24 MY!St.131 8'RC.15 '

~I MUISI 132 "

g[d 25 26 M%ISI I.33 -

4*RC 19 3*RC-17 SF

Appendia il Maine Yankee Atomic Power Conipany

'he,

, Drawing, and 1.ine/lijurp Cnss itefer;nte "Ihird Interval ISI l'regram Zone, Drawing, and Line/r. quip Nuenber Cron Haftiente 7.oue ISI liraulus lluellNulp No.

27 MY.ls! 134 3'RC.18 28 MY.lst l.35 21/2*RC 26A 28 MY.!SI 135 21/2'l:C 20!!

28 MY lsl.l.35 3*RC-26 29 MY.lSI 1 E 3'ItC 20 29 MY lSI 1.% 3* RC.28 29 MY 15,11.% ThC 22 30 M Y.ISt.l .37 3'h C 5 31 MY lSI 138 3*ItG11 32 MY.lSt.l.39 3*ltC-16 33 MY INI.1-40 21/2'RC46 34 MY.lSt.1-41 2'RC 19 35 MY.lsl.142 2'Itc.%

% MY 131143 10 Sill.22

% MY.lsl.1-43 2'S111 24 37 MY lst 144 1rS11131 37 MY-ISI.141 2'S11144 38 MY ISI 145 17S11142 38 M Y.lSt.145 2* Sill 44 39 MY.lsl 146 4' Sill.20 40 MY.lSt.1-4 7 4* Sill 30 41 MY.lSt.148 4* Sill 41 42 MY lSt.149 2'S111 33 43 MY.lS1150 3'C1146 44 MY.lst 151 3'Cil-61 45 MY lsl.l 52 2 Cll.51 45 MY.lSI-152 21/2*Cll4A 45 MY-lSt.152 21/TCll-51 45 MY-Isl.152 3'C1145 45 MY-ISI l.52 ?Cil 51 46 M Y.lSI.l.53 2"Cll.58 47 MY.lsl.1-$4 2'Cil.126 48 MY.lSI-155 2*Cll.127 49 MY Isl.l.56 2"Cll.12%

50 MY.lSI 157 2'U Ril.1 51 MY ISI 158 2"Dilli 2 152

h

- App: dix !! M:ine Yanho Atomic Pontt CompaIy Zone, Drs*g, and IJne/Ppip Cnas Referente lhtto IntervalISI Pncram O Zone, Drawing, and une/ Equip Numlier Cross Referente 74ae ISI Drawing line/l: gulp No.

32 MY ISI 159 2*l)Ril 3 52 MY ISI 159 2*Didi 4

$3 MY ISI 140 2'Dlui 5

$3 MY ISI 140 2*Didi 6 34 MY-ISI141 2*Dlul4 _

$3 MY ISI 142 2*D1019

$6 Pt1 57 P 12 -

58 P13 39 MY ISI 21 l>1 1 60 MY lSI 2 2 ' Ikt 2 61 MY ISI 2 3 - Ikl 3 63 MY 151-2 5 IL3A 63 MY Isl.2 3 IL3fl 66 MYISI24 10"$11122 66 MY Is! 24 t Sill 22A 67 MYIsi29 10's111-31 67 MY-ISI 19 8'51113t A La MY ISl-210 'lu" Sill-42 f,J MY-ISI-210 8"Stil 42A 69 MY ISt 2 Il ' 1(r$11151 69 MY-ISI 2-11 - 10" Sill 32 70 MY-ISI 212 2* Sill 10 70 MY ISI 2-12 2' Sill 9

~ 70 MY isi 212 3* Sill 26 70 MY ISI 2-12 /S11147 ~

70 MY ISI 212 4* Sill 1 70 MY ISI 212 4' Sill 18 70 MY-ISI 212 4* sill 2 70 MY !SI 212 4 S!!! 3 70 MY ISI 2-12 4" Sill 4 =

70 . MY lSt 212 . 6' Sill 13 70 MY ISI 212 6" Sill 17 71 MY ISI 213 10*Cll 1-71 - MY ISI 213 6*Cil 9 72 MY ISI 2-14 10"Cil 2.

. 72 MY ISI 2-14 6*Cil-12 __

72 MY !SI 2-41 6'CS 4 A 73 MY ISI 215 - 10*Cll4

.R

(

~

74 MY ISI 216 6*Cll 3 -

E3

j Appendia E Maine Yankee Atomk Power Cm;eny hme, Disming, and IJne/I' quip Crte Rc ferente *Ihird Intervalist Program Zone, DrWng, and IJnt/l: quip Number Crou iteference Lee 1S1 Drouing 11w/I' quip No.

75 MY-ISI 217 6*Cil 4 76 MY Isl.218 6*Cil-$

77 MY lst.219 12*101lA 77 MY !Sl-219 14*1011 77 MY lSI.219 16*iu l-3 77 MY IS1219 16*Rit4 77 MY lSI 219 P-12A 77 MY ISI.219 P 12ft 78 MY IS! 2 20 1210120 w 78 MY ISl 2 20 8*ldi 20A 79 MY ISI 2 21 1210100 80 MY 1512 22 10*Illi 27 81 MY ISI 2 23 10*Ril 28 82 MY ISI 2-24 10*Ril 11 R3 MY-Is! 245 10*Rll 12 b4 MY ISI 2 26 10* Ril.13 BS MY lSI 2 27 10*Rll 25 66 MY ISI 2 28 1010126 87 MY 1512 29 6*Ril33 E8 MY ISI-2-30 18 0511 89 MY ISI 2 31 18'CS-12 90 MY ISI 2 32 16*CS-13 91 MY ISI 2 33 16*CS 14 92 M Y ISI.2 M 14*CS.15 V2 MY ISI 2-M 14*CS 16 92 MY ISI 2 M 14*CS 17 93 MY lSI 2 35 10*Cll 21 93 MY ISI 245 10*CS-21 94 MY lSI 2 36 10*CS.22 95 MY !SI 247 10*CS 23 96 MY Isi 248 10* CS.)

97 MY ISI 2-39 10*CS 2 98 MY lSI 240 6*CS 3A 98 MY ISI 2 40 **CS 3 99 MY-IS s1 6*Cs-4A 99 MY lSI-241 8"CS,4 E4

Appendix il Maine Yarkee At(enic Power Com;*ny 2'one, Drawing, and une/Pqvip Crce Reference *!hird Interval ist Program I

~_

Zone, Drawing, and une/l: quip Nurnber Crors Reference

/.cne ISI Drawing IJnell'-guip No.

MLISI 242 6'CS40

_100 102 MY ISI 244 30 SilP 1 102 M%IS! 244 NrsilP4 103 MY ISI 243 30 SilP-2 103 MY Isi 245 30"SilP 5 IN M LIS!246 3rrSilP 3 1D4 M%lsl246 30*SitP 6 105 MLISI 247 6*SDil%I 105 MY ISI 2-47 6*SDilV-2 105 MY ISI 247 6'SDilV 3 10$ MY Ist 2-47 6*SDilV4 106 MY Isl 248 12'%TPD-4 106 MWist248 14 WITD4 107 MY ISI 2-49 12*%T"D B 107 MY ISI 249 14*%TPD-8 108 MY ISI.2 50 12'WITD 10 108 MLIS! 2-50 14 WITD-10 109 MLISI.2 31 6*WAPD 21 110 MWist-2 52 6'WAPD 23 111 MList 2 53 6'WAPD 23 113 MLIS14-1 16" SCC-1 114 MY-lNI-3 2 16' SCC-2 115 MLISI 34 16' SCC-7 116 M %1S144 16* SCC nl 117 M%ISI 15 16* SCC.13 118 MY IS14 6 16'N'C 1 11R M%ISI.16 16 PCL 3 118 MY-ISl 34 16*PCC4 118 MWist 16 20*PCC 5 m

119 MYISl17 20"PCC-8 f 120 M%1SI 18 16"PCC 18 120 MY Isl4 & 16 PCC 19 120 MOISI 18 20*PCC-17 121 M%1SI 19 12'PCC45 121 MLISla-9 12*PCC46 121 MY-Ist 3-9 16 PCC-12 122 MY Isl.3-10 $*PCC 79 123 MLISI 112 B'WCPR 12 124 MW1SI 3-13 S*WCPR 13 E-5

Appendia II Maine Yankee Atomic Pontt Company

/ene Drwing, and une/IMutp Crus heference 'Ihlrd interval ISI Program Zour, Drawing, and 1Jne/ Equip Numtwr Cross iteference 74ne ISI Drawlog the/redp No.

125 MY IS!.314 6*WAl'D 17 I 126 M Y ISl4 15 6*WAPD 19 128 MY !S! 317 1'WAPD-27 130 MY.1512 54 4* Sill 14 130 MY 1SI-2 54 4* Sill.16 131 MY IS! 2 55 4* Sill 20 132 MY.lsi.2 56 3" Sill 25 132 MY-1SI 2 56 4* Sill 29 133 MY-ISI 2 57 4'5111 30 1M MY.lSI 2 58 3 !;111 36 1M MY ISI 2 58 4* Sill-to 135 MY.lSI 2 59 4' Sill-41 IM MY ISI 240 4*Cll 20 137 MY ISI.2 61 4"Cll-21 138 MY-ISI 242 4*Cll 22 139 MY.ls! 243 2*Cll 27 140 MY.ls! 24A 4 C1128 144 MY.!St 245 3*Cll 29 142 MY.lS1246 3'Cil 30 143 MY.lSI-247 4*Cll-33 143 MY lSI 247 4"C1135 144 MY.lst-248 4*Cil.34 144 MY-!SI 248 4"Cll.36 145 MY.ISI 249 2*Cil.234 146 MY-ISl 2 70 6'S11 40 147 MY.!SI-2 71 8'C&l 147 MY-ISt 2.?! B CT.5 147 MY.ls! 2 71 8 Cr4 150  !!-25 151 IL4A 151 12-4 11 152 1. 5A 152 1:.5 11 153 P.29A 153 P 2911 153 P 29C 153 P 29D E.6

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Appendas !! . . . Mtine Ytakes Atomic Pcmtr Company '

- Zone, Drsang, and line/liquip Cross Reference Dird IntervJ ISI Pmgram

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"Ihird Interval 151 Program O

ISI PROGRAM TA'BLES O

O

Appendix 0 Maine Yankee Atomic Power Company ISI Prognm Tables Third late rval 151 Program ISI l'rogratu Tubit s Definlilon IMd IMd Description Resuarks lleader ZONE The tone number auigt.Ld to the component l'icid 1 IIcader ZONE Disc The description of the tone.

Iiclo 2 licader DRAWING The 151 reference drawing anociated with the Facid 3 component (i e. isometric or equipment draming).

llender CIASS The ASME Code etau;fication of the component.

Deld 4 _.

licader SYS11 M The s) stem acronym usigned to the component l'iclJ $

Column 1 LINE SEON 11e sequence number is a unique number nuigned to each component within a ghen tone.

Column 2 l'RO The Prograro identifier for the component record (le.

151, or AUG (Augmented)).

Column 3 COMPONENT ID Identification number auigned to the component Column 4 COMPONENT DESCRil'110N Detcription of the component NDE PROCEDURE NDE Procedure to be utilized for the examination (s) calif 1 RATION BLOCK Cahbration Diocks to be utilized for the examination (s)

Column 5 PIPE SIZE Nominal Piping size for the component if applicable Column 6 LINE/ EQUIP # The hne number or equipment idtntifier suociated I the given compcment Column 7 MULT! GROUP 1he group number assigned for components where the _

multiplc<omponent group concept for selection applies. Refer to Appendtr A and Paragraph 5.1.1 of the ISI Program for further discusion.

Column 8 MT.LD TYPE Weld type such as terminal end or structural discontinuity used for selection and/or proration calculations of Code Category D-J, C.A, and C-F-1/2 Codes utshzed are as follows:

SD Structural Discontinuity GSD Gross Structural Discontinuity TE Terminal End T" . Terminal End to Vessel r to Paragnph 515 of the ISI Prognm for aitions of above codes.

Cohimn 9 CODE CATEO Applicable ASME Code Category.

Column 10 CODE UT.M# Applicable ASME Code Category item Number.

Column 11 RELIEF REOEST Rehef Request number (if any) for the component.

Column 12 NDE M!TlilOD NDE Method applicable for the third interval exammation, taking into consideration alternate methods identified in a Relief Request. if any.

G-i

.t-y Agpadis O Meine Yankee Atomle Tcmer Cbmpany '

Ist Program Tables %lrd IntervalISI Program

( es-ISI l'rograin Tables Def1nllion lidd 11dd thetiptics Remarks Cohamn 13 SEL jndicator thcwleg whether or not the component has been 'seletied* for examination to sottsfy the initialISI or Avgmented Prograrn requirements for the third irderni (i.e. any addillonal exatninations scheduled during the laterval due to flami would not be part of r the initially ' selected' components).

Colume 14 PRD/OTOA Code showing the Period and Outage number in which the component is to be examined during the lotsfval.

De Codes utlhzed are as follomt Illank = not acheduled this intern! r 0/0 . Examine any outage, any period 1/0 . Ihamine 1st period, any outag.o 1/1 - Examine 1st period,1st outage 1/2 . Exaniine 1st period,2nd outage 2/0 + Ihamine 2nd period, any outage 2/1 . Examine 2nd period,1st outage ,

2/2 . Enemine 2nd period,2nd outege 3/D . thamine 3rd period, any outage 3/1 . 11: amine 3rd period,1st outage 3/2

• thaminc 3rd period,2nd outage

. See Remarks for scheduling guidance  ;

Column 15 PJNARFJ Comments pertaining to the given component for the third hierval 151 Program.

U For Code Category Il-J welds, a code is used in the .,

first 4 characters of this field to identify the applicablo noie from Table IWil-25001 regarding selection, as follour 1(a) . Terminal End to Wuct 1(b) . liigh Streu Weld y 1(d) . Additional weld seletied to achiew 25%  !

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INSERVICE INSPECTION PROGRAM TABLES MAINE YANEEE AT0*IC POWER COMPAar ZONE.....: 1 19 YEAR INSERv1CE INST 2 Cit 0M PLAN TNIRD INTERVAL ISI PROGRAM 20mE DESC: REACTOR PRESSURE VESSEL 01/19/73 DRAWING..: PT-ISI-1-1 4 CLASS....: 1 SYSTEM...: RPV N ENT DESCRIPTION PRD/

CE PROCEDURE PIPE MULT, WELD CICE CDCE RELIEF LINE CE METTCD EQ C_T_G8 M "4PKS SEc4 FAG CON ONENT ID CALIS?ATION BLOCK SIZE LINE/EOUTPW CROUP TYPE CATEG ITE=f REcEST

..................... ._........................................_..... .......... R-1

_................. 8-4 B1.12 UT Y t/2 FeCERAL REGISTER REQ'S EKAM OF 120 IS! RPV-VC2 LONG WELD 3 210 DEG.-LOWER SMELL 10C% OF RPV SMELL WELDS.

TB-52 z...

8-A 81.12 UT Y t/2 FEDERAL REGISTER FEU'S EXAM OF 130 151 RPV-VC3 LONG WELD G 330 DEG.-LOWER SHELL R-1 1DC% OF RFV SWELL WELDS.

TB-52

.__ .............___.........................__............................ R1 8-G-1 86.40 UT Y 3/2 340151 LIG(1-27) RPV THREADS IN FLAkGE (1-27)

YA-UT-6 T8-20

.__........................... ................................ ...__..R-1 ................ ......................__.....

8-G-1 66.40 UT Y 3/2 341 151 LIG(28-54) RPV THREADS IN FLANGE (25-54)

YA-UT-6 78-20 ---

R-1 8-E B4.13 VT-2

................... ....Y 3/2*

25% SNtPLE, DURING MfDRO.--

350 ISI INST-1 THRu 45 INSTRUMENTAT10m wozZLES YA-VT-11 N/A R-1 8-N-1 B13.10 VT-3 Y 1/2* EXAMINE 2/2, AND 3/2 ALSO CONCE 360 IS! RPV INTERIOR REACTOR VESSEL INTERIOR PER PEttCD).

YA-VT-11 N/A R-1 5-N-3 813.70 VT-3 Y 3/1 ..... ...

370 ISI RPV CORE SUPT STRU C3RE SUPPORT STRUCTURE YA-VT-11 N/A

.........................__............__........._.................................................__..__....... .......__.... ...... .Y ................-

i R-1 8-P B15.10 8,9 VT-2 1/1* *EACM OUTAGE 300 Ist N/A SYSTEM LEAKAGE TEST YA-VT-11 N/A ..- --- .......

...................................._..............____.......__........._........___.................................._.....................-- Y 3/2 -- -

SYSTEM MYDROSTATIC TEST R-1 B-P B15.11 8,9 VT-2

,390 ISI N/A YA-VT-11 N/A ...._.............. ...........__.....

............__......... ...__....................... ....................__... R-1 s-N-2 s13.50 VT-1 Y 3/1 REFER TO PROC 3.17.6.8

, 400 ISI RPV INT ATTACM - 18 INTERIOR ATTACM IN$tDE BELTLINE N/A R-1 8-N-2 813.60 VT-3 Y 3/1 REFER 70 PROC 3.17.6.8 --

410 ISI RPV INT ATTACM - 08 INTERIOR ATTACM OUTSIDE BELTLINE N/A --- --

APPENDIX G - Page: 2 1 I

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INSERVICE INSPECTION PROGRAM TABLES MAINE YANKEE ATOMIC POWElt CDEPANY 20NE.....: 2 Tn!RD INTERVAL ISI Pt0 GRAM 10 YEAR f 4SERVIE InsPECTicas ptag ZONE DESC: RPV CLOSURE HEAD 01/19/93 DEVIEG..: MY-ISI-1-4 CLASS....: 1 SYSTEM...: RPY CO*PONENT DESL1t!PTION P!PE MULTI WELD CODE CODE RELIEF PC/

LINE NDE P40CEDUEE E L]Nf'EQUIPK CROUP TYPE CATEG JTE"2 REQEST CE "ETHOD E OTG8 *EMAMS SE01 P__R.2 COMMWENT !D CALIBRAYlCN BLOCK }1]_E R-1 9-A B1.40 UT, AND LP Y 1/2* *FRG9 FLANGE FAM 1/2, 00 10 ISI CMF-1 CLOSURE HEAD-TO-FLAEGE REMAINING PotTits 3/1.

YA-UT-22, YA-PE-2 T8-16

.................................................................................................................................................................=

R-1 8-A 81.21 UT

- =--

20 ISI CMC-1 CLOSURE HEAD CIRC. EEAD WELD TA-uT-22 TB-52

............................................._.. ~..............................~

R-1 8-A 81.22 UT 30 151 CHPS-1 MERfDIONAL WELD 3 0 DEG.

YA-UT-22 TB-52 R-1 8-A 81.22 UT 40 ISI CMPS-2 MERIDIONAL WELD a 60 DEC.

TB-52 R-1 8-A 51.22 UT l 50 151 CHPS-3 MERIDIONAL WELD a 120 DEG.

TB-52 R-1 8-A B1.22 UT 60 ISI CHPS-4 MERIDIONAL WELD 2 180 DEG.

78-52 R-1 8-A B1.22 UT 70 ISI CHPS-5 MERIDIONAL WELD a 240 DEG.

18-52 R-1 B-A 61.22 UT E0 151 CHPS-6 MERID10#L WELD G 300 DEG.

18-52 _=

R-1 8E 84.12 YT-2 Y 3/2* 25% SAFPLE, DLRING NTDRO.

90 ISI CRD-1-65 CONTROL RCD CRIVE N0ZZLES YA-VT-11 N/A R-1 5-0 514.10 LP Y 3/2 ERAM!WE TC% PERIPMERAL CFD 91 ISI CRD-1-65 CRD nwSING uELDS NouStuGS YA-PE-2 N/A B-E B4.13 VT-2 Y 3/2* 25% SAMPLE, DURING KYDRO.

100 ISI INST-66 THRd 69 INSTPUMENTATION WCIILES R-1 YA-4-11 N/A R-1 B-G-1 B6.10 MT Y 2/2. ....... .........................

110 ISI CH-N(1-27) RPV NUTS (1-27)

YA-MP-111 N/A -

....e..................................................... .............__.. ................................................ ......... ... ........

111 ISI CH-N(28-54) mPV NUTS (28-54) R-1 s-s-1 86.10 MT Y 2/2 YA-Mp-111 N/A =....................................................... .................- -- ------ -----

....................................................................~_

APPE C!K G - Page: 5

m m b- , b[S -

-- 20NE. . . . . : 2 INSERVICE INSPECTION PROGRAM TABLES MAINE YAntE ATOMIC PWER C:pePANY ZONE DESC: RPV CLOSURE READ 10 YEAR INSERVICE INSPECTICM PLAN THIRD INTERVAL ISI PROGtM4

-DRAWikG..: MY-151-1-4 01/19/93 Ctt.SS.... 1

--SYSTEM...: RPY COMDONENT DESCRIPTION LINE- eE PROCEDURE PIPE MULTI WELD CODE CODE RELIEF PRD/

SEoM PRQ CCF5Y)eiENT 10 CALIBRATION BLOCK SIZE LINE/EQUIPf CPOUP IYPg CATE4 ITEwe REoEST WE METM00 RE* RKS SE_L CTGR 120 ISI CH-S(1-27).. RPV STUDS - RE7CiED (SET 1) R-1 s-G-1 86.30 UT, Am MT Y 1/0

YA-UT-7, YA-MP-111 TB-6

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

121 ist CM-S(28-54) RPV STUDS - REMOVED (SET 2) N-1 8-G-1 B6.30 UT, A m MT Y 2/0 YA-UT-7, YA-MP-111 TB-6

.............................................................. ............... ............................................_ - c............................ .

122 III CH-S(55-81) RPV STUDS - REMOVED (SET 3) a-1 B-G-1 86.30 UT,. A m MT Y 3/0 YA-UT-7, YA-MP-11T TS-6

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

I 140 ISI N-LWC1-27) RPV CLOSURE WASMERS (1-27) R-t 8-G-1 B6.50 VT-1 Y 2/2 4 .. YA-VT-11 4 .-

N/A -

L141 ISI CM-LWC28-54) RPV CLOSURE WASHERS (25-54) R-1 B-G-1 56.50 VT-1 Y 2/2 2 YA-VT-11 N/A 150 151 CH-1EST 1 IRSTRUMENT N0ZZLE BOLTING R-1 8-G-2 87.10 VT-1 Y 3/2 TA-VT-11 N/A t

1 APPENDIK G - Page: 6

, e- sm D Cs C.

, ZONE.....: 3 . INSERVICE IkSPECTIOR PROGRAM TABLES MAINE YANKEE ATOMIC F0WER C[MPANY ZONE DESC: STEAM CENERATOR E-1-1 PRIMARY SIDE 10 YEAR twSERVICE INSPECTION PLAN TNIRD INTERVAL ISI PROCRMt ORAVING..: MY-ISI-1-5 01/05/93 CLASS....: 1 SYSTEr4...: RCS COMPONENT DESCRIPTION LINE NDE PROCEDURE PIPE MULTI WLD CCEE CECE RFtIEF PRD/

SEON M COMDOniENT ID cat!ERATION Rt0CK SITE LINE/ EQUIP 8 GROJP TYPE CATEG ITEwe RECEST NOE mETHC0 S Q QTG3 R[uARK$

10 ISI SG-1-C-1 TUBESMEET-TO-PRIM. EXT. RING E-1-1 SG-01 s-8 82.40 UT YA-UT-22 18-16 20 151 SG-1-M-6 EXT RING MERIDIONAL WELD - 0 DEG E-1-1 SG-01 8-8 82.32 UT TB-16 30 ISI SG-1-M-7 EXT. RING MERIDICNAL WELD - 90 DEG E-1-1 SG-01 8-8 52.32 UT 78-16 40 ISI SG-1 M-S EXT. RING HERIDIONAL UELD - 180 DEG E-1-1 SG-01 B-3 82.32 UT 78-16 50 Ist SG-1-M-9 EXT. RING MERIDIONAL WELD - 27G DEG E-1-1 SG-01 B-8 82.32 UT l 78-16 63 IS! SG-1-C-2 PRIM. ext. RING-TO-rRIMARY HEAD E-1-1 SG-01 8-B 82.31 UT 18-16 520ISISG-1-C-3 PRIMARY HEAD-TO-STAY CASE E-1-1 SG-01 8-s 82.31 UT 18-16 130 ISI SG-1-C-4 TUBESHEET-TO-STAY CTL. EXT. E-1-1 SG-01 8-8 82.40 UT 13-16 140 ISI SG-1-C-5 STAY CTL. EXT.-TO-STAT CYLINDER E-1-1 SG-01 8-8 82.31 UT 18-16 150 ISI SG-1-C-6 STAY CYL.-TO-STAY BASE E-1-1 SG-01 8-8 82.31 UT TB-16 160 ISI SG-1-N-1 INLET N0ZZLE-TO-MEAD E-1-1 8-0 83.130 UT Y 1/1 YA-UT-44 TB-20 170 ISI,SG-1-N-2 OUTLET N0ZZLE-TO-MEAD E-1-1 8-0 83.130 UT Y 1/1 YA-UT-44 T8-20 180 ISI SG-1-N-1-IR INLET N0ZZLE INNER RADIUS E-1-1 8-D 83.140 UT Y 1/1 YA-UT-13 18-20

'l APPENDIX G - Pege: 7

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