Text

Rev 2 to North Anna Unit 1 Inservice Insp Program for Components & Component Supports,Second Insp Interval
	ML20081F346
Person / Time
Site:	North Anna
Issue date:	05/22/1991
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
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ML20081F344	List: ML20081F337; ML20081F346; ML20081F350;
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VIRGINIA POWER

-INSERVICE INSPECTION MANUAL SECTION 7.2, ATTACHMENT 8.1 INSERVICE INSPECTION PROGRAM Section: 7.2 i INTERVAL / PERIOD PLAN Rev. 6 Eff.Date:05/10/91 ;

CHANGE / ISSUE APPROVAL FORM Page: 7 of 7 i STATION: bokTH Anna UNIT NO.: 1 PROGRAM TITLE: Tnsecvue TMSDec I m r3 Moc-e a m '

INTERVAL: 2 PERIOD (S): I 2, A rJ 6 3 i i

Ct%<ENT REVISION: .d__

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DESCRIPTION OF CHANGES:

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DEPARTMENT: Tsriobe naammmmmmmmmmmmmmmmmmmmmmmm'memummmmmmmmmmmmmmmmmmmmmmmmmma a SUPERVISOR - ISI/NDE REVIEWED AND APPROVED: / / N

& DATE: 5 -t () /

SUPERVISOR - ISI/N E AND ENGINEERING PROGRAMS (STATION)

REV.IEWED AND

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APPROVED: o DATE: 5, / /9/'

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STATION NUCLEAR SAFETY AND OPERATING COMMITTEE (SNSOC) t REVIEWED AND J MN APPROVED: DATE:

9.106100010 910531 PDR ADOCK 05000338 Q PDR

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SUMMARY

OF CHANGES NORTH ANNA UNIT 1 O INSERVICE INSPECTION PROGRAM

1) Withdrew relief request NDE-1: NRC_ questioned the percentage volume (3 to 8%) that could be volumetrically examined on the pressurizer surge line nozzle-_to-vessel Wold (9). This relief request will be withdrawn, pending arrival of drawings, which will clarify the difficulty in performing this examination. Upon receipt of this information, a now relief request will be generated.

2) Withdrew relief request NDE-2: NRC questioned the basis (geometry), which precluded the examination (volumetric) of the

-following nozzle inner radii:

a) 10NIR , 11NIR , 12NIR, 13 NIR , 14NIR - Pressurizer nozzles for lines.containing-cafety valves and power operated relief

-valves. The NRC alerted us to other utilities, which performed this examination. We will evaluate these new techniques to determine if they can be successfully applied in our situation.

b) 9NIR (3 total), 10NIR (3 total) - Steam generator mainsteam and feedwater nozzles. Same as "a" above.

O c) 11NIR (3 total), 12NIR (3 total) - Steam generator hot and cold leg nozzles. A new relief request NDE-15 has been generated based upon the need for a specific calibration block to conduct this examination. This ble:k will be supplied with the new steam generators, and upon receipt' examinations will be scheduled.

d)-9NIR - Pressurizer surge line nozzle. A new relief request NDE-16 has been-generated based upon the site Alara dose estimete of 11.2. man-rem.

3) Revised relief request NDE-4 : NRC questioned the extent of inclusion of " terminal ends" in the class 1 pipe weld selection. A telephone conference was held with Mr. G.. Johnson (NRC) on May 2, 1991 and agreement was reached as to the selection of " terminal ends" and other pipe welds. The relief - request was revised accordingly.

4) Withdrew relief request NDE-10: NRC questioned impracticality of performing visual examinations on auxfeedwater supports less than one ' inch nominal pipe size. No examination drawings exist for these components, which is why the original request was submitted.

ISI/NDE will develop the- appropriate drawings for examination inclusion by the second period.

5) Revised relief request SPT-1: NRC requested additional O information on the impracticality of pressurizing the reactor

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coolant pump seals and seal injection line, where it enters the O pump. The relief request was revised accordingly.

6) Revised relief requests SPT-2, SPT-5, and SPT-6: NRC questioned some valve mark numbers. Corrections were made accordingly.

7) Withdrew relief request SPT-10: NRC questioned if rein f request was necessary from exceeding 106% of test pressure on some low pressure systems. Va. Power had assumed that test pressure was required at the highest elevation of the test boundary, and therefore situations would exist where low points might exceed 106%

of test pressure. The NRC position is that you make test pressure as close as possibic at the high point without exceeding the 106%

at the low point. This interpretation of the Code would require no relief request.

8) Minor wording changes were made in the Class 1 and Class 2 piping weld selection description found in the " Program Description". The Class 1 changes conform to the revised relief request NDE-4 previously discussed. The Class 2 changes incorporate the requirement to examine 7.5% of the nonexempt welds in our RHR, CHR, and ECCS (stainless steel) systems. In some instances selection below the thickness requirements of Code Case N-408 will be made to achieve this distribution. This selection critoria was agreed to with Mr. G. Johnson (NRC) during a telephone conference held April 25, 1991. The NRC had previously questioned the ISI Plan distribution in this area.

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VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM FOR THE SECOND INSPECTION INTERVAL VOLUME 1 INSERVICE INSPECTION PROGRAM FOR-COMPONENTS AND COMPONENT SUPPORTS REVISION 2 MAY 1991 INTERVAL 2 DECEMBER 24, 1988 - DECEMBER 24, 1998 l

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VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM SECOND INSPECTION INTERVA d DECEMBER 24, 1988 - DECEMBER 24, 1998 REVISION 1 DISTRIBUTION RECORD DISTRIBUTION DATE DISTRIBUTION DATE NO. ENTERED INITIAL NO. ENTERED INITIAL 1 21 2 22 _

3 23 4 24 5 25 6 26 7 27 __

8 28 9 29 ,

10 30 11 31 12 32 13 33 14 34 15 35 16 36 17 37 18 38 l 19 39 l 20 40 l

! Future distributions to this program plan will be accompanied by two copies of the distribution memo, one of which is to be returned per instructions thereon, and the other one is to be

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filed sequentially behind this'page giving you a record of the contents of each distribution.

l ii N1-000 Rev. 2 1991 l

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O TABLE OF CONTENTS S ECTION - TITLE PAGE i Assignment 11 Dietribution Record 111 Table of Contents iv Abstract 1 Inservice Inspection Program -

General 2 Inservice Inspection Program for Components 3 Inservice Inspection Program for Component Supports 3 lii (V

N1-000 Rev. 2 1991

ABSTRACT VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM SECOND INSPECTION INTERVAL DECEMBER 24, 1988 TO DECEMBER 24,_1998 In accordance with 10 CFR 50.55a dated January 1, 1988, the North Anna Unit 1 (NAPS-1) Inservica Inspection (ISI) Program was updated to meet the requirements of ASME Section XI, 1983 Edition with Addenda through Summer 1983. This updated program is for the NAPS-1 second ten year inspection interval' scheduled to commence December 24,-1988 and be completed Decenber 24, 1998.

-These dates reflect a first interval extension of 201 days 1d ocumented in our letter to the NRC dated 8/25/88,-Serial No.88-486._ In cases where the requirements of-Section XI have been

-determined to be impractical,_ requests for relief have been developed per - 10 CFR 50.55a (g) (5) (iii) .

This program is divided into two volumes. Volume-1 contains the Inservice Inspection: Program, and volume 2, which was previously submitted, contains the Inservice Testing Program. The Inservice Inspection Program does not-include requirements per-Subsection IWE, Requirements For Class MC Components Of Light Water Cooled O Power Plants. Current-Federal Regulations do not require these rules to be' included in ISI programs.

This document provides an overview and-summary of-the NAPS-1 ISI Program for Subsectic.e IWA, IWB, IWC, IWD, and IWF. -The boundaries of the-Iff Program, component classifications, and tne employment of exemptions;in IWB-1220, IWC-1220,_IWD-1220,'and IWF-1230 are shown on the ISI Classification Boundary Drawings (CBDs). listed-on pages-_1-11 to 1-14. The codings, symbols and textiused on-the CBDs are detailed on-31715-CBM-L&S-2, Legends and-Symbols-Drawing.

Section 1 of'this document provides the_ general information and ~

format regarding this program. Section.2 of this document provides_a program implementation overview of the ISI Program for lSI Class 1, 2,_and-3 components. A summary table of_Section XI requirements applicable to. NAPS-1 is provided as well-as relief requests,for components. Section 3 of this document provides a program implementation overview-for-ISI Clb.s 1, - 2 , and 3 c component supports. A summary tableaof Section-XI requirements applicable to NAPS-1 component supports is provided as well as relief. requests.for component supports.

iv N1-000 Rev. 2 1991

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM GENERAL SECOND INSPECTION INTERVAL O

N1-001 1-1 Rev. 2 1991

O SECTION 1 TABLE OF CONTENTS SECTIOli 1%QE 1.0 INSERVICE INSPECTION PROGRAM - GENERAL 1-2 1.1 GENERAL INFORMATION 1-2 1.1.1 Preservico Examinations 1-2 1.1.2 Initial Innervico Inspection Interval 2-2 1.1.3 Second Inservico Inspection Interval 1-2 2.1.4 Inservice Inspection Program 1-2 Doncription 1.2 DRAWING LIST - ISI CLASSIFICATION BOUNDARY 1-11 DRAWINGS A

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l l-vO N1-001 1-2 Rev. 2 1991

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1.0 INSERVICE INSPECTION PROGRAM - GENERAL 1.1 GENERAL INFORMATION North Anna Power Station Unit 1 (NAPS-1) is located on Lake Anna in Louisa County, Virginia. The plant employs a Pressurized Water Reactor (PWR) and associated Nuclear Steam Supply System components provided by Westinghouse Electric Corporation.

1.1.1 Preservice Examinations Preservice examinations at NAPS-1 were performed utilizing the requirements of ASME Section XI, 1974 Edition with Addenda through Summer 1975.

1.1.2 Initial Inservice Inspection Interval NAPS-1 commercial operation commenced on June 6, 1978. Accordingly, the initial ten year inspection interval started on 6/6/78. This interval, however, was extended 201 days to 12/24/88 as documented by letter to the NRC dated 8/25/88, serial no.88-486. Examinations

/ during the first inspection interval were also

(_-)

/ performed per ASME Section XI, 1974 Edition with Addenda through Summer 1975. Certain system pressure testing requirements were completed per

! ASME Section XI, 1977 Edition with Addenda through Summer 1979.

1.1.3 Second Inservice Inspection Interval As mandated by the Code of Federal Regulations, Title 10, Part 50, Section 50.55a (10 CFR ,

50,55a), the NAPS-1 Inservice Inspection (ISI)

Program has been updated to the 1983 Edition through the Summer 1983 Addendum of ASME Section i XI. This is the latest edition and addonda of

( Section XI incorporated into 10 CFR 50.5Sa as of December 24, 1987. The second inservice l

inspection interval is scheduled to commence on December 24, 1988 and be completed on December l

l 24, 1998.

As. allowed by the Code of Federal Regulations Title 10, Part 50, Section 50.55a(g)4(iv), the NAPS-1 Inservice Inspection (ISI) Program shall utilize the 1986 Edition of ASME Section XI for recortification of Level III NDE Personnel as iO required in paragraph IWA-2300a (1) only. (5 year N1-001 1-3 Rev. 2 1991

O 1.1.3 Second Inservice Inspection Interval

' Continued) recertification) 1.1.4 Inservice Inspection Program Description The ISI Program contained herein addresses the inservice inspection and testing of ISI Class 1, 2, and 3 components and the associated component supports. Applicabic requirements in Subsections IWA, IWB, IWC, IWD, IWF and the Mandhtary Appendices of the 1983 Edition of ASME Section XI through the Summer 1983 Addendum have been incorporated into our corporate and site ISI programs and procedures. Any programmatic modifications to these requirements are discussed in this document.

This document is not intended to provide specific information on the implementation of the ISI Program. The intent of this document is to provide specific information on the scope of the NAPS-1 ISI program (i.e., its boundary and f compliance with Section XI) and identify those Section XI requirements which are deemed impractical. Requests for relief for these impractical requirements have been developed per 10 CFR 50. 55a (g) (5) (iii) .

1.1.4.1 Exclusion of Subsection IWE Subsection IWE, Requirements For Class MC Components of Light-Water Cooled Power Plants, is not included in this program per the Final Rules in the Federal Register, Volume 53, page 16053, which specifically excludes the requirements of Subsection IWE from 10 CFR 50.55a.

1.1.4.2 Exclusion of Subsections IWP and IWV Subsections IWP and IWV, Inservice Testing of Pumps and Inservice Testing of Valves in Nuclear Power Plants are not included in this program. The IWP and IWV program was submitted separately.

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l N1-001 1-4 Rev. 2 1991

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\~ 1.1.4.3 Inservice Inspection Plan Thn inservice inspection plan required by IWA-2420, detailing the components and component supports selected for examination during the interval will be provided as a separate document.

1.1.4.4 Inspection Program Employed The ISI Program for North Anna Unit I will utilize the interval format of Inspection Program B, as shown in IWA-2432, 1.1.4.5 Wold Reference System The wold reference system required by IWA-2600 is a recent addition to the rules of ASME Section XI. The implementation plan for this requirement is' detailed in relief requests NDE-13 and NDE-14, shown on pagos 2-69 and 2-70 respectively.

O) s,, 1.1.4.6 Classification of Components A. Classification of Components-Design North Anna Unit 1 was issued construction permit No. CPPR-77 in February 1971. The station design incorporates the codes and standards that were in effect when the equipment was purchased. The codes and standards used for the design, fabrication, erection, and testing of safety related components are commensurate with the importance of the safety functions to be performed.

n N1-001 1-5 Rev. 2 1991

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"# A. Classification of Components-Design (Continued)

The group classifications tabulated in the " Standard Format and Content of Safety Analysis Reports for Nuclear Power Reactors", issued in February 1971, and in Safety Guide No. 26, published in March 1972, incorporated, in most cases, later editions of codes than those in effect when the majority of cafety-related equipment was designed.

Some of the equipment that would fall under a " group" as defined in Safety Guide No. 26 was designed to different codes or different editions of the same code. For example, for different components that would be in the same group, one may be designed to ASME III-1968, one to ASME III-1971, and one to ASME VIII-1968.

Therefore, pressure-containing

(^)N

(_ components of safety-related systems do not necessarily fall under the group classification listed above.

B. Classification of Components-Inservice Inspection The classification of components for Inservice Inspection was performed by employing the guidelines of 10'CFR 50.55a, USNRC Regulatory Guide 1.26 Revision 3, ANSI N18.2-1973, ANSI N18.2a-1975, and NUREG-0800, Standard Review Plan 3.2.2-Revision 1, in conjunction with the System Quality Group Classification Section of the North Anna Power Station UFSAR, Section 3.2.2. Quality Groups A, B, and C, as discussed in Regulatory Guide 1.26 are considered the same as ISI classes 1, 2, and 3 for the purposes of

(" this program.

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N1-001 1-6 Rev. 2 1991

O' B. Classification of Components-Inservice Inspection (Continued)

The ISI Classification of each component included in NAPS-1 program is shown on the ISI Classification Boundary Drawings (CBDs) listed on pages 1-11 to 1-14. The Legends and Symbols ISI Classification Boundary Drawing (11715-OBM-L&S-2) details the line codings and component markings which provide the ISI Classif'ication of all items included within the ISI Program boundaries. In general, the ISI classification of piping is accomplished by 1dne " codings" or symbols shown on 11715-CBM-L&S-2.

ISI Classification of components which graphically cannot be coded, such as pressure vessels, pumps, strainers, and tanks, etc. is shown as text (e.g., ISI Class 1A, 3E,

/~T etc.) either inside the component Is_/ graphics or adjacent to the component mark number.

Classification changes are typically shown at the seat of a valve, with the ISI Class shown on either side of the classification

" break line".

1.1.4.7 Components and Component Supports Exempt from Examination The application of the exemptions allowed per IWB-1220, IWC-1220, IWD-1220, and IWF-1230 is also detailed by the codings and component markings of 11715-CBM-L&S-2 discussed in section 1.1.4.5.2. Because the exemptions of IWF-1230 are "in the course of preparation", a set of exemptions for component supports developed in a proposed code case, WGCS 89-1(b) is being employed. Relief request CS-1 details the reasoning for this program modification.

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N1-001 1-7 Rev. 2 1991

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1.1.4.8 Requests For Relief-Components and Component Supports Where the requirements of ASME_Section XI have been determined to-be imprectical, requests for-relief have been developed in accordance with 10 CFR 50.55a(g) (5) (iii) . The impractical requirements are detailed in three sets of relief requests an NDE series for components and nondestructive.

examination areas, an -SPT- series for -

system pressure testing areas, and'a CS series for component support. areas.

Each relief request is formatted as follows:

I. IDENTIFICATION OF COMPONENTS II. IMPRACTICAL CODE REQUIREMENTS III. BASIS FOR RELIEF ALTERNATIVE EXAMINATION IV.

(OR TESTING)

)

Relief requests which pertain to a specific ASME Section XI Category and Item Number are referenced in the Inservice Inspection Program Summary Tables in Sections 2 and-3 of this document. Relief requests which are-programmaticLin content will~be discussed in the text of. Sections.1, 2, or:3, but-not listed-in the Inservice = ,

Inspection: Program Summary-Tables.

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N1-001 1-8 R6v. 2 1991

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' ASME Section XI Code Cases Incorporated 1.1.4.9 Into Program As allowed by 10 CFR 50.55a(c)(3) and USNRC Regulatory Guide 1.147, Revision 7, the following Code Cases are being incorporated into the NAPS-1 ISI Program:

Case N-401 - Eddy Current Examination,Section XI, Division 1.

Case N-402 - Eddy Current Calibration Standard Material,Section XI, Division 1.

Case N-406 - Alternative Rules for Replacement,Section XI, Division 1.

Case N-408 - Alternative Rules for Examination of Class 2 Fiping Section XI, Divisioni.

Case N-416 - Alternative Rules For Hydrostatic Testing of _

Repair or Replacement of class 2 Piping,Section XI, Division 1.

Case N-426 - Extent of VT-1 Examinations, Category B-G-2 of Table IWB-2500-1, i Section XI, Division 1.

Case N-446 - Recertification of Visual Examination Personnel,Section XI, Division 1.

Case N-457 - Qualification Specimen Notch Location for Ultrasonic Examination of Bolts and StudsSection XI, Division 1.

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N1-001 1-9 Rev. 2 1991

O- 1.1.4.10 Augmented Inservice Inspection Program for ISI Class 1, 2, and 3 Components Augmented Inservice Inspection activities which portain to components within the scope of the ASME Section XI program are summarized in Section 2, Table 2.6. A listing of specific components scheduled to be examined per the augmented pro, ram will be included as part of the Inservice Inspection Plan discussed in Section 1.1.4.3. This plan will be provided as a separate document.

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N1-001 1-10 Rev. 2 1991

1.2 DRAWING LIST NORTH ANNA UNIT 1 SECOND INSPECTION INTERVAL ISI CLASSIFICATION BOUNDARY DRAWINGS t

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N1-001 1-21 Rev. 2 1991

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NORTH ANNA UNIT 1 INTERVAL 2 ISI CLASSIFICATION BOUNDARY DRAWINGS SORTED E SERIES m LEGENDS AND SYMBOLS DRAWING

1. : DRAWING NUMBER SHEET : TITLE

1. 11715-CBM-L&S-2 : 1 OF 1 : LEGEND AND SYMBOLS 11715-CBB SERIES

1. : DRAWING NUMBER : SHEET : TITLE

1. 11715-CBB-006A-2 : 1 OF 3 : AIR COOLING AND PURGING SYSTEM

2. 11715-CBB-0400-2 : 1 OF 3 : AIR CONDITIONING CONDENSER WATER SYSTEM

3. 11715-CBB-102B-2 : 1 OF 1 : INTERIOR FIRE PROTECTION & HOSE RACK SYS 11715-CBM SERIES

1. : DRAWING NUMBER : SHEET : TITLE

1. 11715-CBM-070A-2 : 1 OF 3 : MAIN STEAM SYSTEM

2. 11715-CBM-070A-2 : 3 OF 3 : MAIN STEAM SYSTEM

3. 11715-CBM-070B-2 : 1 OF 3 : MAIN STEAM SYSTEM

4. 11715-CBM-070B-2 : 2 OF 3 : MAIN STEAM SYSTEM

5. 11715-CBM-070B-2 : 3 OF 3 : MAIN STEAM SYSTEM

6. 11715-CBM-072A-2 : 2 OF 3 : AUXILIARY STEAM & AIR REMOVAL SYSTEM

7. 11715-CBM-074A-2 : 1 OF 3 : FEEDWATER SYSTEM x 8. 11715-CBM-074A-2 : 3 OF 3 : FEEDWATER SYSTEM s 9. 11715-CBM-078A-2 : 1 OF 4 : SERVICE WATER SYSTEM 10, 11715-CBM-078A-2 : 3 OF 4 : SERVICE WATER SYSTEM i

11. 11715-CBM-078A-2 : 4 OF 4 : SERVICE WATER SYSTEM *

12. 11715-CBM-078B-2 : 1 OF 4 : SERVICE WATER SYSTEM '

13, 11715-CBM-078B-2 : 2 OF 4 : SERVICE WATER SYSTEM

14. 11715-CBM-078C-2 : 1 OF 2 : SERVICE WATER SYSTEM

15. 11715-CBM-078C-2 : 2 OF 2 : SERVICE WATER SYSTEM i

16. 11715-CBM-078G-2 : 1 OF 2 : SERVICE WATER SYSTEM i

17. 11715-CBM-078G-2 : 2 OF 2 : SERVICE WATER SYSTEM

18. 11715-CBM-078H-2 : 1 OF 1 : SERVICE WATER SYSTEM

19. 11715-CBM-078J-2 : 1 OF 1 : SERVICE WATER SYSTEM

20. 11715-CBM-078K-2 : 1 OF 1 : SERVICE WATER SYSTEM

21. 11715-CBM-079A-2 : 1 OF 3 : COMPONENT COOLING WATER SYSTEM

22. 11715-CBM-079A-2 : 2 OF 3 : COMPONENT COOLING WATER SYSTEM

23. 11715-CBM-079A-2 : 3 OF 3 : COMPONENT COOLING WATER SYSTEM

24. 11715-CBM-079B-2 : 1 OF 5 : COMPONENT COOLING WATER = SYSTEM l

25. 11715-CBM-079B-2-: 2 OF 5 : COMPONENT COOLING WATER SYSTEM

26. 11715-CBM-079B-2 : 3 OF 5 : COMPONENT COOLING WATER SYSTEM l

27. 11715-CBM-079B-2 : 4 OF 5 : COMPONENT COOLING WATER SYSTEM

28. 11715-CBM-079B-2 : 5 OF 5 : COMPONENT COOLING WATER SYSTEM

29. 11715-CBh-079C-2 : 1 OF 5 : COMPONENT COOLING WATER SYSTEM

30. 11715-CBM-079C-2 : 3 OF 5 : COMPONENT COOLING WATER SYSTEM

31. 11715-CBM-079C-2 : 4 OF 5 : COMPONENT COOLING WATER SYSTEM

32. 11715-CBM-079C-2 : 5 OF 5 : COMPONENT COOLING WATER SYSTEM

33. 11715-CBM-079D-2 : 4 OF 5 : COMPONENT COOLING WATER SYSTEM v

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NORTH ANNA UNIT 1~ INTERVAL 2~ ISI CLASSIFICATION BOUNDARY DRAWINGS SORTED BY SERIES-CONTINUED 11715-CBM SERIES

// : DRAWING NUMBER : SHEET : TITLE

34. 11715-CBM-082A-2 : 1 OF 3 : COMPRESSED AIR SYSTEM

35. 11715-CBM-082F-2 : 1 OF 1 : COMPRESSED AIR SYSTEM

36. 11715-CBM-082N-2 : 1 OF 3 : COMPRESSED AIR SYSTEM

37. 11715-CBM-082N-2 : 3 OF 3 : COMPRESSED AIR SYSTEM 38, 11715-CBM-088A-2 : 10F 4 : FUEL PIT CLNG & REFUELING PUR. SYSTEM

39. 11715-CBM-088A-2 : 2 0F 4 : FUEL PIT CLNG & REFUELING PUR. SYSTEM

40. 11715-CBM-088A-2 : 4 0F 4 : FUEL PIT CLNG & REFUELING PUR. SYSTEM

41. 11715-CBM-089B-2 : 3 OF 4 : SAMPLING SYSTEM

42. 11715-CBM-089D-2 1 1 OF 1 : SAMPLING SYSTEM

43. 11715-CBM-090A-2 : 1 OF 2 : VENT & DRAIN SYSTEM

44. 11715-CBM-090C-2 : 1 OF 3 : VENT & DRAIN SYSTEM

45. 11715-CBM-090C-2 : 3 OF 3 : VENT & DRAIN SYSTEM

46. 11715-CBM-091A-2 : 1 OF 4 : CONT QUENCH & RECIR SPRAY SUB SYSTEM

47. 11715-CBM-091A-2 : 2 OF 4 : CONT QUENCH & RECIR SPRAY SUB SYSTEM 48, 11715-CBM-091A-2 : 3 OF 4 i CvNT QUENCH & RECIR SPRAY SUB SYSTEM

49. 11715-CBM-091A-2 : 4 OF 4 : CONT QUENCH & RECIR SPRAY SUB SYSTEM

50. 11715-CBM-091B-2 : 1 OF 1 : CONT QUENCH & RECIR SPRAY SUB SYSTEM

51. 11715-CBM-092A-2 : 1 OF 2 : LEAKAGE MONITOR SYSTEM

52. 11715-CBM-092A-2 : 2 OF 2 : CONTAINMENT VACUUM SYSTEM

53. 11715-CBM-093A-2 : 1 OF 3 : REACTOR COOLANT SYSTEM

54. 11715-CBM-093A-2 : 2 OF 3 : REACTOR COOLANT SYSTEM N 55. 11715-CBM-093A-2 : 3 OF 3 : REACTOR COOLANT SYSTEM s 56. 11715-CBM-093B-2 : 1 OF 3 : REACTOR COOLANT SYSTEM

57. 11715-CBM-093B-2 : 2 OF 3 : REACTOR COOLANT SYSTEM

58. 11715-CBM-094A-2 : i oP 2 : RESIDUAL HEAT REMOVAL SYSTES

59. 11715-CBM-094A-2 : 2 OF 2 : RESIDUAL HEAT REMOVAL SYSTEM

60. 11715-CBM-095A-2 : 1 OF 4 : CHEMICAL AND VOLUME CONTROL SYSTEM

61. 11715-CBM-095A-2 : 2 OF 4 : CHEMICAL AND VOLUME CONTROL SYSTEM

62. 11715-CBM-095A-2 : 3 OF 4 : CHEMICAL AND VOLUME CONTROL SYSTEM

63. 11715-CBM-095A-2 : 4 OF 4 : CHEMICAL AND VOLUME CONTROL SYSTEM l 64. 11715-CBM-095B-2 : 1 OF 2 : CHEMICAL AND VOLUME CONTROL SYSTEM l 65. 11715-CBM-095B-2 : 2 OF 2 : CHEMICAL AND VOLUME CONTROL SYSTEM l

66. 11715-CBM-095C-2 : 1 OF 2 : CHEMICAL AND VOLUME CONTROL SYSTEM

67. 11715-CBM-095C-2 : 2 OF 2 : CHEMICAL AND VOLUME CONTROL SYSTEM

68. 11715-CBM-096A-2 : 1 OF 3 : SAFETY INJECTION SYSTEM 69.-11715-CBM-096A-2 : 2 OF 3 : SAFETY INJECTION SYSTEM

70. 11715-CBM-096A-2 : 3 OF 3 : SAFETY INJECTION SYSTEM

71. 11715-CBM-096B-2 : 1 OF 4 : SAFETY INJECTION SYSTEM'

72. 11715-CBM-096B-2 : 2 OF 4 : SAFETY INJECTION SYSTEM

73. 11715-CBM-096B-2 : 3 OF 4 : SAFETY INJECTION SYSTEM l 74. 11715-CBM-096B-2 : 4 OF 4 : SAFETY INJECTION SYSTEM l 75. 11715-CBM-098A-2 : 2 OF 5 : STEAM GENERATOR BLOWDOWN SYSTEM

76. 11715-CBM-098A-2 : 3 OF 5 : STEAM GENERATOR BLOWDOWN SYSTEM

77. 11715-CBM-098A-2 : 4 OF 5 : STEAM GENERATOR BLOWDOWN SYSTEM f

O) l-13

.. . . . .__>__.___..____.___.__.._.___m..._._._.. . _ . _ . ~ . _ _ _ _ . _ . . _ _ _ _ . _ . . , _ _

NORTH ANNA UNIT 1- INTERVAL 2 ISI CLASSIFICATION BOUNDARY DRAWINGS SORTED BJ SERIES-CONTINUED-

\ 11715-CBM SERIES

1. : DRAWING NUMBER : SHEET : TITLE

78. 11715-CBM-102A-2 : 2 OF 2 : CHEMICAL FEED SYSTEMS

89. 11715-CBM-105B-2 : 1 OF 2 : SECONDARY PLANT GAS SUPPLY SYSTEM

80. 11715-CBM-106A-2 1 1 OF 4 : CONTAINMENT ATMOSPHERE CLEANUP SYSTEM

81. 11715-CBM-106A-2 : 2 OF 4 : CONTAINMENT ATMOSPHERE CLEANUP SYSTEM

82. 11715-CBM-106A-2 : 3.0F 4 : CONTAINMENT ATMOSPHERE CLEANUP SYSTEM

83. 11715-CBM-106A-2 : 4 OF 4 : CONTAINMENT ATMOSPHERE CLEANUP SYSTEM 13075-CBM SERIES

1. : DRAWING NUMBER : SHEET : TITLE

1. 13075-CBM-093C-2 : 1 OF 2 : REACTOR COOLANT SYSTEM

2. 13075-CBM-093C-2 : 2 OF 2 : REACTOP. COOLANT SYSTEM

3. 13075-CBM-102C-2 : 1 OF 1 : CHEMICAI. FEED SYSTEM O

O l-14 l

O VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM FOR COMPONENTS SECOND INSPECTION IliTERVAL 0

N1-002 2-1 Rev. 2 1991

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

O SECTION 2 TABLE OF CONTENTS SECTION PAGE 2.0 INSERVICE IMSPECTION PROGRAM FOR COMPONENTS 2-3 >

2.1 PROGRAM DESCRIPTION . 2-3 2.1.1 Section XI Requirements 2a3 2.1.2 Weld Selection for Class 1 Piping 2-3 2.1.3 Weld Selection for Clacs 2 Piping 2-3 2.2 PROGRAM

SUMMARY

2-4 2.2.1 Inservice Inspection Program Summary Description 7-(

2.3 ISI CLASS 1 COMPONENTS - PROGRAM

SUMMARY

'I ABLE 2-6 2.4 ISI CLASS 2 COMPONENTS - PROGRAM

SUMMARY

TABLE 2-32 2.5 ISI CLASS 3 COMPONENT - PROGRAM

SUMMARY

TABLE 2-43 0'

2.6 AUGMENTED INSPECTION'stEQU7REMENTS ON ISI CLASS 1, OR 3 SYSTFMS - PROGRAM SNMARY TABLE 2, 2-46 2.7 COMPONENT RELIEF REQUESTS 2-48 2.7.1 NDE Series Relief Requests 2-48 2.7.2 SPT Series Relief Requests 2-71 O

N1-002 2-2 Rev. 2 1991

O 2.0 INSERVICE INSPECTION PROGRAM FOR COMPONENTS 2.1 PROGRAit DESCRIPTION 2 . 7. 1 The Inservice Inspection Program for ISI Class 1, 2 and 3 components meets the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1903 Edition through the Summer 1983 Addendum except where these requirements have been determined to be impractical.

Detailed relief requests for these impractical requirements are included in Section 2.7.

Programmatic modifications to Section XI requirements are outlined in Sections 2.1.2 and 2.1.3.

2.3.2 ISI Class 1 piping welds will be selected for exam nation such tha+ 25% of the total number of welds are examined during the interval. The welds selected include all terminal ends and branch connections. In addition, valves which have reactor coolant on one side and a lower pressure system on the opposite side will have the high pressure pipe-to-valve weld included in the interval selection. the remaining balance (q~], of the 25% will be evenly distributed across the ISI Class 1 piping weld population based on line size, line function, and line design to the extent practicable. This criteria will be employed in lieu of Notes 1(b) and 2 of Category-B-J, Table IWB-2500-1. See Relief Request NDE-4 for details.

2.1.3 ISI Class 2 Carbon Steel piping welds will be selected for examination per ASME Section XI, 1974 Edition with Addenda through Summer 1975, IWC-2411 as allowed by 10 CFR

50. 55a (b) (2) (iv) (B) . The Section XI Category (C-F) Item Number, Exam Method, Exam Figure,-and Acceptance Criteria will be per the 1983 Edition' with Summer 1983 Addenda, Table IWC-2500-1 as summarized on page 2-39. ISI Class 2 RHR, CHR, and ECCS (Stainless Steel) welds will be selected for examination such that 7.5% of the total number of nonexempt welds in each system are examined during the interval. In order to achieve this distribution, some welds below the thickness requirement of Code Case N-408 will be selected. Selections within each system will be prorated among terminal ends, structural discontinuities, and line sizes.

-() -

N1-002 2-3 Rev. 2 1991

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

1 J

2.2 PROGRAM

SUMMARY

2.2.1 The Inservice Inspection Program Summary for Components is presented in Sections 2.3, 2.4 and 2.5 in a tabular format. The applicable NAPS-1 components and associated requirements are ,

listed alphabetically according to code Category. Those Categories and Item Numbers listed with "N/A" are for components not found at North Anna Unit I and are included for reference only. The following internation is included in the tables:

A. Code cateaorv - The Snction XI Examination Category as defined in Tables IWB-2500-1, IEC-2500-1 and IWD-2500 1 for Class 1, 2 and 3 components, respectively.

B. Itc1LRpber_- The Section XI Item Number as -

listed in Tables IWD-2500-1, IWC-2500-1 and IWD-2500-1. All .. tom Numbers are listed for each code Categorf with the exception of those associated with Program A of Category B-D.

C. Part Examined - The ASME Section XI description of the area to be examined.

D. Examination Method - Lists the examination method or methods required by the provisions of Section XI. The abbreviations used are as follows:

VOL - Volumetric per IWA-2230 SUR - Surface per IWA-2220 VIS - Visual per IWh-2211, 12 and 13 E. Alternate Examination Method - Lists the examinaticn method that will be performed as an alternative tc the Section XI required examination as stated Ji a relief request.

F. Examination Neauirustnj;1_pI_ Tea.t Recntired

/Fiqure_Nunber - Lists the applicable Section XI figure for determining the volume of the component to be examined.

N1-002 2-4 Rev. 2 1991

O G. Accentance criteria - Lists the applicable portion of Section XI for determinirig the acceptance criteria.

H. Relief Reauest Number - References a specific relief request contained in Section 2.7. Relief requests are presented in two series: an NDE-Series for components and nondestructive examination areas and a SpT-Series for syntem pressure testing areas.

O O

N1-002 2-5 Rev. 2 1991

I, I

f k

i 2.3 ISI Class 1 Components - Program Summary Table 2.3.1 Examination Category B-A, Pressure Retaining Welds in Beactor Vessel [

[

I ALT. EXAM ITEM EXAM. EXAM REQUIRED / ' ACCEPTANCE RELIEF f NO. PARTS TO BE EXAM?NED METIIOD METHOD FIG NO. CRITERIA _FEOUEST Bl.11 Reactor Vessel Circumferential Shel1 VOL IWB-2500-1 IWB-3510 ,

Welds

, Bl.12 Reactor vessel Longitudinal Shell VOL IWB-2500-2 IWB-3510 !

Welds Bl.21 Reactor Vessel Circumferential VOL IWB-2500-3 IWB-3510 I Head Weld i bl.22 Reactor Vessel Meridional Head Seld VOL IWB-2500-3 IWB-3510

. Bl.30 Reactor Vessel Shell-to-Flange VOL IWB-2500-4 IWB-3510 Weld l Bl.40 Reactor Vessel Head-to-Flange Weld VOL & IWB-2500-5 IWB-3510 ;

SUR ,

i Bl.51 Reactor Vessel Beltline Region Repair VOL IWB-2500-1, IWB-3510 l Welds and -2 l

NICLS1 2-6 Fev. 2 1991

)

_ ___m-__- -s - - -

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2.3.2 Examination Category B-3, Pressure Retaining Welds in Vessels Other Than Reactor vessels ALT. EXAM i ITEM EXAM. EXAM REQUIRED / ACCEITAM2 RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD FIG FO. CRITERIA REOt m

, .~

B2.11 Pressurizer Circumferential VOL IWB-2500-1 IWB-351R I

, Shell-to-Head Welds B2.12 Pressurizer Longitudinal VOL IWB-2SOO-2 IWB-3511 Shell-to-Head Welds i B2.21 Pressurizer C1._,taferential Head N/A N/A N/A Welds i

B2.22 Pressurizer Meridonial Head Welds N/A N/A N/A B2.31 Steam Generator Circumferential N/A N/A N/A Head Welds B2.32 Steam Generator Meridonial Head N/A N/A N/A ,

Welds '

B2.40 Steam Generator Tubesheet-to-Head VOL IWB-2500-6 IWB-3511 Weld ~

i NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 1.

i i

! NICLSI 2-7 Rev. 7 1991

i O >

2.3.2 Examination Category B-B, Pressure Retaining Welds in Vessels Other Than Reacter Vessels

] (continued) 4 i

ALT. EXAM

~

ITEM EXAM. EXAM REQUIRED / ACCEPDRCE RELIEF

-l NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA RECa> Lu l B2.51 Heat Exchanger Circumferential N/A N/A N/A Head Welds

) B2.52 Heat Exchanger Meridonial N/A N/A N/A Head Welds B2.60 Heat Exchanger N/A N/A N/A

, Tubesheet-to-Head Welds 82.70 Heat Exchanger longitudinal N/A N/A N/A Welds B2.80 Heat Exchanger N/A N/A N/A

, Tubesheet-to-Shell Welds i

NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included

~

in North Anna Unit 1.

i i

i NICLS1 2-8 Rev. 2 1991

2.3.3 Examination Category B-D, Full Penetration Welds of Nozzles in Vessels Inspection Program B ALT. EXAM ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRIT FJA REOUEST B3.90 Reactor Vessel Nozzle-to-Vessel VOL IWB-2500-7 IWB-3512 Welds B3.100 Reactor Vessel Nozzle Inside VOL IWB-2500-7 IWB-3532 Radius Section B3.110 Pressurizer Nozzle-to-Vessel VOL IWB-2500-7 IWB-3512 NDE-1 Welds B3.120 Pressurizer Nozzle Inside VOL VIS, IWB-2500-7 IWB-3532 NDE-2, Radius Section VT-2 NDE-16 I

, B3.130 Steam Generator Nozzle-to-Vessel N/A N/A N/A Welds B3.140 Steam Generator Nozzle Inside VOL VIS, IWB-2500-7 IWB-3532 NDE-2, Radius Section VT-1 ,

NDE-15 I B3.150 Heat Exchanger Nozzle-to-Vessel N/A N/A N/A Welds B3.160 Heat Exchanger Nozzle Inside N/A N/A N/A Radius Section NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 1.

NICLSI 2-9 Rev. 2 1991

I 2.3.4 Examination Category B-E, Pressure Retaining Partial Penetration Welds In vessels ALT. EXAM ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METTIOD METHOD FIG NO. CFlTERlA RIOUEST B4.11 Partial Penetration Vessel Nozzles VIS, EXTERNAL IWB-3522 VT-2 SURFACE B4.12 Partial Penetration Control Rod VIS, EXTERNAL IWB-3522 !

Drive Nozzles VT-2 SURFACE B4.13 Partial Penetration Instrumentation VIS, EXTERNAL IWB-3522 SPT-11 l Nozzles VT-2 SURFACE B4.20 Pressurizer Heater Penetration VIS, EXTERNAL IWB-35:22 ;

Welds VT-2 SURFACE ;

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1 NICLSI 2-10 Rev. 2 1991 h

4

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\ k 2.3.5 Examination Category B-F, Pressure Retaining Dissimilar Metal Welds A LT. EXAM ITEM EXAM. 'JCAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA Pl.OUEST B5.10 Reactor Vessel Nominal Pipe Size VOL & VOL IWB-2500-8 IWB-3524 24 in. Nozzle-to-Safe SUR End Butt Welds B5.20 Reactor Vessel Nominal Pipe Size N/A N/A N/A

$4 in. Nozzle-to-Safe End Butt Welds B5.30 Reactor Vessel Nozzle-to-Safe N/A N/A N/A End Socket Welds B5.40 Pressurizer Nominal Pipe Size VOL & N/A N/A 24 in. Nozzle-to-Safe SUR End Butt Welds B5.50 Pressurizer Nominal Pipe Size N/A N/A N/A 54 in. Nozzle-to-Safe End Butt Welds B5.60 Pressurizer Nozzle-to-Safe N/A N/A N/A End Socket Welds NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 1.

NICLS1 2-11 Rev. 2 1991 i

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l 2.3.5 Examination Category B-F, Pressure Retaining Dissimilar Metal Welds (continued;( ,

ALT. EXAM ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA FIOUEST B5.70 Steam Generator Nominal Pipe VOL & IWB-2500-9 IWB-3514 Size 2 4 in. Nozzle-to-Safe SUR '

End Butt Welds B5.80 Steam Generator Nominal Pipe N/A N/A N/A Size $ 4 in. Nozzle-to-Safe End Butt Welds I

B5.90 Steam Generator Nozzle-to-Safe N/A N/2 N/A End Socket Welds B5.100 Heat Exchanger Nominal Pipe N/A N/A N/A Size 2 4 in. Nozzle-to-Safe End Butt Welds B5.110 Heat Exchanger Nominal Pipe N/A N/A N/A Size 5 4 in. Nozzle-to-Safe .

End Butt Welds !

l NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included l in North Anna Unit 1. [

i NICLSI 2-12 Rev. 2 1991 i i

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4

. 2.3.5 Examination Category B-F, Pressure Retaining Dissimilar Metal Welds (con.t)

ALT. EXAM ITEM EXAM. EXAM REQUIRED / ACCEPT 7RCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CPlTERIA REQUEST

. I B5.120 Heat Exchanger Nozzle-to-Safe N/A N/A N/A End Socket Welds B5.130 Piping Nominal Pipe Size VOL & IWB-2500-8 IWB-3514

>4 in. Dissimilar Metal SUR ,

Butt Welds !

B5.140 Piping Nominal Pipe Size N/A N/A N/A

<4 in. Dissimilar Metal Butt Welds t

B5.150 Piping Dissimilar Metal N/A N/A N/A Socket Welds NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 1.

i l

NICLSI 2-13 Rev. 2 1991

O O O 2.3.6 Examination Category B-G-1, Pressure Retaining Bolting, Greater Than 2 in. In Diareter ALT. EXAM ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF

NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOUEST i B6.10 Reactor *ressel Closure Head Nuts SUR *

B6.20 Reactor Vessel Closure Studs, VOL IWB-2500-12 IWB-3515 in Place B6.30 Reactor Vessel Closure Studs SUR & IWB-2500-12 IWB-3515 when removed VOL B5.40 Reactor Vessel Threads in Flange VOL IWB-2500-12 IWB-3515 NDE-3 B6.50 Reactor Vessel Closure Washers, VIS, Surfaces Bushings VT-1 B6.60 Pressurizer Bolts and Studs N/A N/A N/A B6.70 Pressurizer Flange Surface, N/A N/A N/A when connection disassembled B6.80 Pressurizer Nuts, Bushings, N/A M/A N/A and Washers B6.90 Steam Generator Bolts and Studs N/A N/A N/A

In course of preparation.

NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 1.

NICLSI 2-14 Rev. 2 1991

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2.3.6 Examination Category B-G-1, Pressure Retaining Bolting, Greater Than 2 in. !

! 'In. Diameter (continued) [

ALT. EXAM ITEM EXAM. EXAM REQUIRED / ACCEPTANCE nELIEF NO. PARTS TO BE EXAMINED METHOD METHOD FIG MO. CRITERIA FEQUEST i

B6.100- Steam Generator Flange. Surface, N/A N/A N/A j i when connection disassembled I

i B6.110 Steam Generator Nuts, Bushings, N/A N/A N/A and Washers i i-1 . B6.120 Heat Exchanger Bolts and Studs N/A N/A N/A i

! B6.130 Heat Exchanger Flange Surface, N/A N/A N/A t

i B6.140 Heat Exchanger Nuts, Bushings, N/A N/A N/A i

1 B6.150 Piping Bolts and Studs N/A N/A N/A ,

[

I B6.160 Piping Flange Surface, N/A N/A N/A !

t- when connection disassembled I

~

B6.170. Piping Nuts, Bushings, and Washers N/A N/A N/A i i

t t

i NOTE:. "N/A" in the EXAM. METHOD column indicates that no applicable components are included j t

in North Anna Unit 1. - .

i NICLSI 2-15 Rev. 2 1991 !

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i 2.3.6 Examination Category B-G-1, Pressure Retaining Bolting, Greater Than 2 in. In Diameter i'

.(continued) 3 l 8 ALT. EXAM !

ITEM EXAM. EXAM NO. REQUIRED / ACCEPTANCE RELIEF ',

1 PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERTA REvU61 f i

[t l B6.180 Pumps Bolts and Studs VOL IWB-2500-12 IWB-3515 !

3 B6.190 Pumps Flange Surface, VIS, Surfaces

4 1

when connection disassembled VT B6.200 Pumps Nuts, Bushings,'and Washers VIS, Surfaces

VT f

] B6.210 Valves Bolts and Studs VOL

}

IWB-2500-12 IWB-3515 B6.220 Valves Flange Surface, VIS, Surfaces

i i

when connection disassembled' VT-1 [

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_ B6.230 Valves Nuts, Bushings, and Washers VIS, Surfaces

i

VT-1 I e

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!

In course of preparation I t I-NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable ccaponents are included t in North Anna Unit I. [

NICLS1 2-16 Rev. 2 1991 j

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I

O O O 2.3.7 Examination Category B-G-2, Pressure Retaining Bolting, 2 in. and Less In Diameter j J

AUT. EXAM ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOUEST B7.10 Reactor Vessel Bolts, Studs and Nuts VIS, Surface

VT-1 B7.20 Pressurizer Bolts, Studs, and Nuts VIS, Surface

VT-1 B7.30 Steam Generator Bolts, Studs, VIS, Surface

and Nuts VT-1 B7.40 Heat Exchanger Bolts, Studs and Nuts N/A N/A N/A B7.50 Piping Bolts, Studs, and Nuts VIS, Surface

VT-1 B7.60 Pumps Bolts, Studs, and Nuts VIS, Surface

VT-1 B7.70 Valves Bolts, Studs, and Nuts VIS, Surface ,

VT-1 -

B7.80 CRD Housings Bolts, Studs and Nuts VIS, Surface

VT-1

In course of preparation.

NOTE: "N/A" in the EXAM. METHOD column indicates that no applicab3e components are included in North Anna Unit 1.

NICLSI 2-17 Rev. 2 1991 i

e

( O O 243.9 Examination Category B-H, Integral Attachments for vessels I

ALT. EXAM ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METI!OD METHOD FIG NO. CPlTERIA REOUEST B8.30 Reactor Vessel Integrally Welded N/A N/A N/A Attachments B8.20 Pressurizer Integrally Wclded VOL OR IWB-2500-13, IWB-3516 Attachments FUR -14, and -15 B8.30 Steam Generator Integrally Welded VOL OR IWB-2500-13, IWB-3516 Attachments SUR -14, and -15 '

B8.40 Heat Exchariger Integrally Welded N/A N/A N/A l Attachments !

i i l

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NOTE: "N/A" in the EXAM. METHOD c lumn indicates that no applicable components are included in North Anna Unit 1.

i 4

4 t

NICLS1 2-18 Rev. 2 1991

O O O 2.3.9 Examination Category B-J, Pressure Retaining Welds in Piping ALT. EXAM ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEP NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CPlTEPlA PiOUE5T ,

B9.11 Nominal Pipe Size > 4 in. VOL & IWB-2500-8 IWB-3514 NDE-4 Circumferential Welds SUR ,

1 B9.12 Nominal Pipe Size > 4 in. VOL & SUR IWB-2500-8 IWB-3514 NDE-4 ;

longitudinal Welds B9.21 Nominal Pipe Size 5 4 in. SUR IWB-2500-8 IWB-3514 NDE-4 Circumferential Welds B9.22 Nominal Pipe Size 5 4 in. SUR IWB-2500-8 IWB-3514 NDE-4 tongitudinal Welds B9.31 Nominal Pipe Size > 4 in. VOL & SUR IWB-2500-9, IWB-3514 NDE-4 Branch Pipe Connection Welds -10, and -11 i

B9.32 Nominal Pipe Size 5 4 in. SUR IWB-2500-9, IWB-3514 NDE-4 Branch Pipe Connection Welds -10, and'-11 B9.40 Socket Welds SUR IWB-25CO-8 IWB-3514 NDE-4 i

i NICL51 2-19 Rev. 2 1991 f

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l j 2.3.10 Examination' Category B-K-1, . Integral Attachments for Piping, Pumps, and Valves i

j. ALT. EXAM- I ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF i-PARTS TO'BE EXAMINED- [

NO. METHOD METHOD FIG NO. CRITERIA REuuz.u !

)

e

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}' B10'.10 Piping Integrally Welded' VOL or IWB-2500-13, IWB-3516 j'

Attachments SU". -14, and -15 ;

6 f B10.20 Pumps Integrally Welded N/A N/A N/A i- Attachments l '

1 l' B10.30 Valves Integrally Welded N/A N/A N/A Attachments f

i, q

0 NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included j in North' Anna Unit 1.

\- i i

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NICIS1- l 2-20 f

Rev. 3 1991 L 1,

4:

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r 2.3.11 Examination Category B-L-1, Pressure Retaining Welds in Pump Casings i

ALT. EXAM l ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEr NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOUEST i

B12.10 Pump Casing Welds VOL SUR IWB-2500-16 IWB-3518 NDE-5 !

I l

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i NICLSI 2-21 Rev. 2 1991

h i.

i 2.3.12 Examination Category B-L-2, Pu:np Casings .

ALT. EXAM

, ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO DE EXAMINED METIIOD METf10D FIG NO. CRITERIA REQUEST i

B12.20 Pump Casing VIS, VIS, Internal

NDE-5 VT-3 VT-1 Surfaces l I

i l

In course of preparation i.

I NICLS1 2-22 Rev. 2 1991 t l

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2.3.13 Examination Category B-M-1, Pressure Retaining Welds la Valve Bodies ALT. EXAM i ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITEFlA PIOUEST B12.30 Valves, Nominal Pipe Size N/A N/A N/A

<4

_ in. Valve Body Welds B12.40 Valves, Nominal Pipe Sl;.e N/A N/A N/A

> 4 in. Valve Body Welds 4

NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 1.

NICIE,1 2-23 Pev. 2 1991

C5 \ %

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I 2.3.14 Examination Category B-M-2, Valve Bodies l

ALT. EXAM i ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF i NO. PARTS TO DE EXAMINED METff0D METHOD FIG NO. CRITEPlA FIG u f B12.50 Valve Body, Exceeding 4 in. VIS, VIS, Internal

NDE-6 Nominal Pipe Size 17-3 5T-3 Surfaces J

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In course of preparation t

i NICIE,1 2-24 Rev. 2 1991 i

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_m _m. _ -__m_ ___ ______ . _ _ _ _ _ _ . _

1 2.3.15 Examination Category B-N-1, Interior of Reactor Vessel ALT. EXAM EXAM. EXAM FEQUIRED/ ACCEPTANCE RELIEF ITEM FIG NO. CRITERIA REOUEST PARTS TO BE EXAMINED METHOD METHOD FO. _

Accessible

Reactor Vessel - VIS, B13.10 areas Vessel Interior VT-3 l

l l

In course of preparation 2-25 Fev. 2 1991 NICLSI

3

%. J i 2.3.16 Examination Category B-N-2, Integrally Welded Core Support Structures and Interior Attachments to Reactor Vessels l ALT. EXAM l ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO DE EXAMINED METHOD METHOD FIG NO. CRITERIA REOtm l

B13.20 BWRs Only N/A N/A N/A 4

B13.30 BWRs Only N/A N/A N/A l B13.50 Reactor vessel Interior Attachments VIS, Accessible

Within Beltline Region VT-1 welds B13.60 Reactor Vessel Interior Attachneents VIS, Accessible

Beyond Beltline Region VT-3 welds 1

l i

In course of preparation

! NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included j in North Anna Unit 2.

i i

NICLS1 2-26 Fev. 2 1991 1

O O O 2.3.17 Examination Category B-N-3, Removable Core Support Structures ;

ALT. EXAM I ITEM IXAM. EXAM REQUIRED / ACCEPTANCE FILIET 3 NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CPlTEPlA PIOUEST 4

B13.40 BWRs Only N/A N/A N/A 1

B13.70 Reactor Vessel Core Support VIS, Accessible

Structure VT-3 Surfaces i i d

(

I

?

In course of preparation l

d l

NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 1. ,

[

NICIIsi 2-27 Rev. 2 1991 j i

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2.3.18 Examination Category B-0, Pressure Retaining Welds in Control Rod Housings ALT. EXArt ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METITOD FIG NO. CRITERIA REQUEST B14.10 Reactor Vessel Welds in CRD Housing VOL or IWB-2500-18 IWB-3523 SUR r

i i

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r NICIE11 2-28 Rev. 2 1991

r.

[h) (Q) (u /)

(J '% /

l 2.3.19 Examination Category B-P, All Pressure Retaining Components ALT. TEST EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF ITEM CRITERIA REOUEST NO. PAPTS TO BE EXAMINED METHOD EEIl199 FIG NO.

Reactor Vessel Pressure Retaining VIS, LEAAGE

SPT-11 B15.10 PER IWB-5221 Bounda ry VT-2 Reactor Vessel Pressure Retaining VIS, HYDROSTATIC

SPT-11 B15.11 Bounda ry VT-2 PER IWB-5222 LEAKAGE

B15.20 Pressurizer Pressure Retaining VIS, Boundary VT-2 PER IWB-5721 HYDROSTATIC

815.21 Pressurizer Pressure Retaining VIS, Boundary VT-2 PER IWB-5222 LEAKAGE

B15.30 Steam Generator Pressure Retaining VIS, Boundary VT-2 PER IWB-5221 HYDROSTATIC

j B15.31 Steam Generator Pressure Retaining VIS, Boundary 'JT-2 PER IWB-5222 l

~

B15.40 Heat Exchanger Pressure Retaining, N/A N/A N/A Boundary B15.41 Heat Exchanger Pressure Retaining N/A N/A N/A Boundary

In Course of Preparation NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 1. Rev. 2 1991 NICLS1 2-29

O O O 2.3.19 Examination Category 0 P, All Pressure Retaining Components (continued)

A LT. TEST ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF

[10. PAPTS TO DE EXAMINED METHOD METHOD FIG NO. CRITEPlA REQUEST B15.50 Piping Pressure Retaining Boundary VIS, LEAKAGE

VT-2 PER IWB-5221 B15.51 Piping Pressure Retaining Boundary VIS, HYDROSTATIC

SPT-1,-2 VT-2 PER IWB-5222 SPT-3,-4 B15.60 Pumps Pressure Retaining Boundary VIS, LEAKAGE

VT-2 PER IWB-5221 B15.61 Pumps Pressure Retaining Boundary VIS, HYDROSTATIC

SPT-1 VT-2 PER IWB-5222 B15.70 Valves Pressure Retaining Boundary VIS, LEAKAGE

VT-2 PER IWB--5221 B15.71 Valves Pressure Retaining Boundary VIS, HYDROSTATIC * **-1,-2 VT-2 PER IWB-5222 Lvr-3,-4

In Course of Preparation NI CLSI 2-30 Rev. 2 1991

l l

l 2.3.20 Examination Category B-Q, Steam Generator Tubing ALT. EXAM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF j ITEM CRITERIA REOUE2I l METHOD METTIOD FIG NO.

NO. PAxis TO DE EXAMINED B16.10 Steam Generator Tubing in Straight N/A N/A N/A Tube Design Steam Generator Tubing in U-Tube VOL Hot Leg IWB-3521 B16.20 and U-Bend Design f30TE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included

~

in North Anna Unit 1 .

2-11 Fev. 2 1991 NICIE,1

s s j \

l 2.4 ISI Claso 2 Componer ts - Prcgram Summary Table 2.4.1 Examination Category C-A, Pressure Retaini',g Welds in Pressure Vessels ALT. 4XAM ITEM ,

EXAM- EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METIICD METiiOD FIG NO. CRITERIA REOUEST C1.10 Pressure Vessel VOL IWC-2500-1 IWC-3000 circumferential Shell Welds C1.20 Pressure Vessel VOL IWC-2500-1 IWC-3000 Circumferential Head Welds ;

C1.30 Pressure Vesuel VOL IWC-2500-2 IWC-3000 Tubesheet-to-Shell Weld NICLS2 2-32 Rev. 2 1991

O O O 2.4.2 Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels A UT. EXAM ITEM EXAM EXAM REQUIRED / ACCEPTANCE RELIEF EO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOUEST C2.11 Pressure Vessel SUR IWC-2500-3 JWC-30bo

< 1/2 in.

Nominal Thickness Nozzle-to-Shell (or Head) Weld C2.21 Pressure Vessel SUR & IWC-2500-A(a) IWO-3000

> 1/2 in. VOL or (b)

Nominal Thic% ness Nozzle-to-Shell (or Head) Weld without Reinforcing Plate ,

C2.22 Pressure Vessel VOL IWC-2500-4(a) TWC-3000

> 1/2 in. Nominal er (b)

Thickness Nozzle Inside '

Radius Section without Reinforcing Plate C2.31 Pressure Vessel SUR IWC-2500-4(c) IWC-3OOO

> 1/2 in.

Nominal Thickness Reinforcing Plate Welds to Nozzle and Vessel NICLS2 2-33 Pev. 2 1991

t. .. _.

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2.4.2 Examination Category C-B, Pressure. Retaining Nozzle Welds in Vessels (continued)

ALT. EXAM ITEM EXAM EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METilOD METHOD FIG NO. CRITERIA REQUEST C2.32 Pressure vessel VOL IHC-2500-4(c) IkC-3000

> 1/2 in.

Nominal Thickness Nozzle-to-Shell (or Head) Welds When inside of Vessel f.1 Accessible l

C2.33 Presuure Vessel VIS, N/A No leakage

> 1/2 in. VT-2 ,

Nominal Thickness Nozzle-to-Shell (or Head) When Inside of Vessel Is Inaccessible NICLS2 2-34 Rev. 2 1991

i f

2.4.3 Examination Category C-C, Integral Attachments For Vessels, Piping, Pumps, and. Valves I

ALT. EXAM ITEM EXAM EXAM REQUIRED / ACCEPTANCE RELIEF t

.H9 PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REQUEST l C .10' Pressure Vessel SUR IWC-2500-5 IWC-3000.

Integrally Welded [

Attachments C1.20 Piping SUR IWC-2500-5 IWC-3000 Integrally Welded r Attachmenta ~!

t C3.30 Pump .

SUR IWC-2500-5 IWC-3000 t Integrally Welded l Attachments l i

C3.40 Valve SUR IWC-2500-5 1WC-3000 t Integrally Welded [

Attachments ;

I t

. I

.5 ii

'N1CLS2 2-35 Rev. 2 1991 i

i

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r r r 2.4.4 Examination Category C-D, Pressure Retaining Bolting Greater Than 2 in. In Diameter ALT. EXAM ITEM EXAM EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METIIOD MET 110D FIG NO. CRITERIA PIOUEST C4.10 Pressure Vessel VOL IWC-2500-6 IWC-3000 Bolts and Studs r C4.20 Piping N/A N/A N/A Bolts and Studs C4.30 Pump N/A N/A N/A Bolts and Studs C4.40 Valve N/A N/A N/A Bolts and Studs NICLS2 2-36 Rev. 2 1991

'"N d -

2.4.5 Examination Category C-F-1, Pressure Retaining Welds In Austenitic Stainless Steel c - liigh Alloy Piping (Per Code Case N-408)

ALT. EXAM ITEM EXAM EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METIIOD ME7110D FIG NO. CRITERIA REQUEST C5.11 Circumferential Welds In Piping SUR & IWC-2500-7 IWC-3000

> NPS 4 And > 3/8 in. Nominal VOL Wall Thickness ;

C5.12 Longitudinal Welds In Piping > SUR & IWC-2500-7 IWC-3000 HPS 4 And > 3/8 in. Noninal Wall VOL Thickness C5.21 Circumferential SUR & IWC-2500-7 IWC-3000 VOL C5.22 Longitudinal SUR & IWC-2500-7 IWC-3000 VOL C5.30 Socket Welds SUR IWC-2500-7 IWC-3000 NICLS2 2-37 Rev. 2 1991

% -i1 i

2.4.5 Examination Category C-F-1, Pressure Retaining Welds In Austenitic. Stainless Steel or High Alloy. Piping (Per Code Case N-408) (Continued); ;

i.

ALT. EXAM !

ITEM . EXAM EXAM REQUIRED / ACCEPTANCE RELIEF NO. PhTS TO BE EXAMINED METHOD ME.THOD FIG NO. CRITERIA REOUEST .i t

C5.41 Circumferentia1 Branch Connection SUR IWC-2500-9,- IWC-3000- '

Welds of Branch Piping 2,.NPS 2 to -13 C5.42 Longitudinal Branch Connection SUR IWC-2500-12 IWC-3000 f Welds of Branch: Piping'l-NPS 2 and -13 ,

l E

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NICLS2 2-38 Rev. 2 1991 !

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- j 2.4.6 Examination' Category C-F, Pressure Retaining Welds In f Piping (Carbon ct Low Alloy'Eteel)

AI.T. EXAM t ITEM EXAM EXAM REQUIRED / ACCEPTANCE RELIEF f(p. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOUEST C5.11 Nominal Wall Thickness 5 1/2 in. SUR IWC-2"'"-7 IWC-3000 circumferential Piping Welds i C5.12 Nominal Wall Thickness 5 1/2 in. SUR IWC-2500-7 IWC-3000 '

Longitudinal Piping Welds j C5.21 Nominal Wall Thickness > 1/2'in. SUR IWC-2500-7 IWC-3090 Circumferential Piping Welds-C5.22 Nominal Wall Thickness > 1/2 in/ SUR IWC-2500-7 IWC-3000 ;

Longitudinal Piping Welds C5.31 Nominal Branch Pipe Size > 4 in. SUR IWC-2500-9 IWC-3000 Circumferential Pipe Weld to 13, inclusive C5.32 Nominal Branch Pipe Size > 4 in. SUR IWC-2500-12, IWC-3000 NDE-7 Longitudinal Pipe Weld and -13 '

(1) NOTE: Category .C-F utilizes item numbers which are the same as those found in Cacegory C-F-1.

Category C-F will be limited to welds found on the Main Steam System ("SHP" line numbers) '

and Feedwater Systems ("WFPD" line numbers) only.

I NICLS2 2-39 Rev. 2 1991'

I m ;

l 2.4.7 Examination Category C-G, Pressure Retaining Walds In Pumps'And Valves .

i ALT.- EXAM l ITEM EXAM EXAM REQUIRED / ACCEPTANCE RELIEF !

NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOUEST .!

I

'l C6.10 Pump Casing Welds SUR IWC-2500-8 IWC-3000 NDE s NDE-9 C6.20 Valve Body Welds N/A N/A N/A <

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at North Anna Unit 1. '

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I NICLS2 2-40 Rev. 2 1991 i l

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2.4.8 Examination Category C-H, All Pressure Retaining Compot.ents ALT.

ITEM EXAM EXAM TEST ACCEPTANCE FELIEF NO. PARTS TO BE EXAMINED METHOD METHOD REOUIRED CRITERIA REQUEST C7.10 Pressure Vessel VIS, FUNCTIONAL IWC-3000 Pressure Retaining VT-2 PER IWC-5221 Components C7.20 Pressure Vessel VIS, HYDROSTATIC IWC-3000 SPT-8 Pressure Retaining VT-2 PER IWC-5222 Components C7.30 Piping VIS, FUNCTIONAL IWC-3000 Pressure Retaining VT-2 PER IWC-5221 Components C7.40 Piping VIS, HYDROSTATIC IWC-3000 S PT-5, -6 Pressure Retaining VT-2 PER IWC-5222 SPT-7,-8 Components SPT-11 C7.50 Pump VIS, FUNCTIONAL IWC-3000 Pressure Retaining VT-2 PER IWC ,5221 Components C7.60 Pump VIS, HYDROSTATIC IWC-3000 Pressure Retaining VT-2 PER IWC-5222 Components C7.70 Valve VIS, FUNCTIONAL IWC-3000 Pressure Retaining VT-2 PER IWC-5221 Components NICLS2 2-41 Rev. 2 1991

% %J 2.4.8 Examination Category C-H, All Pressure Retainino Components ALT.

ITEM EXAM EXAM TEST ACCEPTANCE RELIEF No. PARTS TO BE EXAMINED METHOD METHOD REO'JiRED CRITERIA REQUEST

~

C7.80 Valve VIS, HYDROSTATIC IWC-3000 SPT-5,-6 Pressure Retaining VT-2 PER IWC-5222 SPT-7,-8 Components

?

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NICLS2 2-42 Rev. 2 1991 ;

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2.5 ISI Class 3 Components - Program Summary 2.5.1 Examination Category D-A, Systems In Support of Peactor Shutdown Function ALT.- TEST ITEM ,

EXAM - EXAM AND EXAM ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED ~ METHOD METHOD REOUIRLrtEWii CRITERIA REQUEST D1.10 Pressure Retaining Components VIS, INSERVICE IWD-3000 VT-2 PER IWD-5221 D1.10 Pressure Retaining Components VIS, HYDROSTATIC IWD-3000 VT-2 PER IWD-5223 D1.20 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Component Supports and VT-3 Restraints D1.30 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Mechanical and Hydraulic VT-3 Snubbers D1.40 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Spring Type Supports VT-3 .,

D1.50 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Constant Load Type Supports VT-3 D1.60 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Shock Absorbers VT-3 l

NICLS3 2-44 , Rev. 2 1991

O: O O 2.5.2 Examination Category D-B, Systems In Support of Emergency Core Cooling, Containment Heat Removal, Atmosphere Cleanup, and Reactor Residual Heat Removal ALT. TEST ITEM EXAM . EXAM AND EXAM ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD REOUIREMENTS CRITERIA REOUEST D2.10 Pressure Retaining Components- VIS, INSERVICE IWD-3000 VT-2 PER IWD-5221 D2.10 Pressure Retaining Componerts VIS, HYDROSTATIC IWD-3000 SPT-9 VT-2 PER IWD-5222 D2.20 Integral Attachment- VIS, IWD-2500-1 IWD-3 000 NDE-10 component Supports and VT-3 Restraints D2.30 Integral Attachment- VIS, IWC-2500-1 IWD-3000 NDE-10 Mechanical and Hydraulic VT-3

. Snubbers D2.40 Integral' Attachment- VIS, IWD-2500-1 IWC-3000 NDE-10 Spring Type Supports VT-3 D2.50 Integral Attachment- VIS, IWD-2 500~-1 IWD-3000 NDE-10 Constant Load Type Supports VT-3 D2.60 integral Attachment- VIS, 1WD-2500-1 IWD-3000 NDE-10 Shock Absorbers VT-3 NICLS3 2-45 Rev. 2 1991

, . .u. -

' ~

1 r

2.5;3 Examination'Categcry D-C, Systems In Support of Residual Heat Removal From Spent Fuel 1 Storage Fool ' ,

ALT. TEST ITEM EXAM EXAM AND EXAM ACCEPTANCE RELIEF i NO. PARTS TO BE EXAMINED _ ' METHOD METHOD REOUIREMENTS CRITERlA': REOUEST

=

'VIS,

~

P3.10 Pressure Retaining Components INSERVICE IWD-3000 VT-2 .PER IWD-5221 D3.10 Pressure Retaining Components._ VIS, HYDROSTATIC IWD-3000 VT-2 PER IWD-5223 D3.20 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Component Supports VT-3 and Restraints D3.30 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Mechanical and Hydraulic VT-3 Snubbers t

IWD-3000 i D3.40 Integral Attachment- VIS, IWD-2500 Spring Type Supports VT-3 D3.50 Integral Attachment- VIS, IWD-2 50 0'-1 IWD-3000 Constant Load Type VT-3 !

Supports .

D3.60 Integral Attachmer.t- VIS, IWD-2500-1 IWD-3000 Shock' Absorbers VT-3 NICLS3 2-46 Rev. 2 1991 i

l . . . . . . . . .

,-s 3 , - s, 2.6 Augmented Inspection Requirements on ISI Class 1, 2, or 3 Systems - Program Summary Table ITEM NO. COMPONENT DESCRIPTION REFERENCE (S) EXAM AND FREOUENCY 1 REACTOR COOLANT PUMPS - FLYWHEEL TECH. SPECS. 4.4.10.1.1 UT IN PLACE AT APPROX.

REG. GUIDE 1.14, REV. 1 3 YEAR INTERVALS.

UT/ PT (FLYWHEEL REMOVED) 10 YEAR INTERVAIEs.

2 REACTOR COOLANT IDOP BYPASS LINES UFSAR 3.6.2.3.1 UT/PT EXAM EVERY WELD EVERY 40 MONTHS.

3 PRESSURIZER SPRAY PIPING IN THE IDWER UFSAR 3.6.2.3.2 UT/PT EXAM SELECTED WELDS CUBICIA: BETWEEN FLOOR ELEVATIONS EVERY 40 MONTHS 262 FT. 10 IN. AND 272 FT. 6 I rl .

4. MAIN STEAM POSTULATED BREAK IDCATIONS UFSAR 3C.2.7 UT/PT EXAM OF 1/3 OF SELECTED WELDS EVERY 40 i MONTHS, WITH 100% OF ALL WELDS COMPIETED BY THE END OF THE INTERVAL.

5. FEEDWATER POSTULATED BREAK IDCATIONS UFSAR 3C.2.7 UT/Pr EXAM OF 1/3 OF SEIMD WELDS .TVERY 40

-' MOtrrHS , WITH 1001 OF ALL WELDS COMPIETED BY THE END OF THE INTERVAL.

6. STEAM GENERATORS - SUPPORTS TECH. SPECS. 4.4.10.1.2 VT-1 EVER7 40 MONTHS 1/3 OF THE MAIN MEMBER WELDS JOINING A572 MATERIAL.

NIAUGTBL 2-46 Rev. 2 1991

O J 2.6. Augmented Inspection Requirements on"ISI Class I, 2, or 3 Systems ITEM NO. COMPONENT DESCRIPTION REFERENCEfSi EXAM AND FREOUENCY

7. ROCKWELL EDWARDS T-58 ANGLE IEINB4-48 RT A SELECTED GROUP OF UNIVALVES VALVES EVERY 18 MONTHS ,

8. SERVICE WATER PIPE WALL THICKNESS STATION PT SEMI-ANNUAL UT THICKNESS MEASUREMENTS 1- PT-75.14 AND DRY FIIM PAINT THICKNESS.

9. REACTOR VESSEL INCORE DETECTOR NRCB 88-09 100% EDDY CURRENT !

THIMBLE TUBES EXAMINATION ON ALL INCORE :

DETEC'It)R TNIMBLE TUBES '

IN SERVICE EACH REWELING

10. REACTOR COOLANT PIPING - LER 82-043 RT EVERY THIRD REWELING THERMAL ' SLEEVES -DATED:8/26/82 OUTAGE.

ABBREVIATIONS USED IEIN = :NkC IE INFORMATION NOTICE '

LER =

LICENSEE EVENT _ REPORT ,

NRCB = NRC IE BULLETIN PT =

PENETRANT TEST / EXAMINATION PT =

PERIODIC TEST (REFERENCE)

^~

RG = NRC REGULATORY GUIDE RT =

RADIOGRAPHY TEST / EXAMINATION UFSAR = UPDATED FINAL SAFETY ANALYSIS REPORT VT ='

VISUAL TEST / EXAMINATION ,

l N1AUGTBL 2-47 Rev. 2 1991 i

I

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

1 4

' 2.7.1 NDE SERIES-RELIEF REQUESTS I

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< N1-NDERR e-48 Rev. 2 1991-p

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

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RELIEF REOUEST NDE-1 )

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N1-NDERR 2_49 Rey, 2 1991

. . _ . . .._-_..-..a_._,-...___;_---__._ _

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

J.

, . 1a RELIEF REOUEST NDE-2 I

(WITHDRAWN) a l

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t N1-NDERR 2-50 Rev. 2 1991

RELIEF REQUEST NDE-3 I. IDENTIFICATION OF COMPONENTS Threads in Flange Ruactor Vessel (1-RC-R-1)

Drawina No. Thread In Flance Mark Not 11715-WMKS-RC-R-1.3 TIF-01 through TIF-58 II. IMPRACTICABLE CODE REQUIREMENTS j Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through Summer 1983 Addenda, Category B-G-1, Item No, B6.40 requires a volumetric examination of the Reactor Vessel Threads In Flange. Virginia Electric and Power Company is employing Table IWB-2412-1, Inspection Program B to schedule examinations.

Relief is requested from the examination frequency requirements specified in Table IWB-2412-1 for the reactor vessel threads in 21ange examination.

III. BASIS FOR REi'"P Relief from the examination frequency requirements is requested based upon the following criteria:

1) Virginia Electric and Power Company currently schedules the reactor vessel flange threads examination to.be performed in concurrence with the automated examination performed on the reactor vessel welds. This permits the examinations to be conducted with more sophisticated (i.e., digital, automated) ultrasonic techniques in lieu of manual techniques.

2) In order to accommodate the automated ultrasonic calibrations, the calibration block is currently being maintained by our Reactor Vessel-ISI contractor at their facility. To examine the percentage of threads in the. flange specified in the second period by Table IWB-2413-1, it would be necessary to either schedule an automated ultrasonic examination solely to examine these threads or to fabricate a calibration block to O

N1-NDERR 2-51 Rev. 2 1991

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

O RELIEF PEOUES'r NDE-3 CONTINUED perform manual ultrasonic examinations._ Virginia Electric and Power Company does not believe that the cost of an additional automated examination is justified-or that a manual examination would be as reliable as an automated examination for those threads.

IV. ALTERNATE PROVISIONS An automated ultrassaic examination shall be performed on 50% of the threads in flange during the first period reactor vessel examination and the remaining 50% of the threads in flango during the end of interval reactor vossol examination.

O O

N1-NDERR 2-52 Rev. 2 1991

b' RELIEF REQJH:ST NDE-4 I. IDENTIFICATION OF COMPONENTS ISI Class 1 Pressure retaining welds in piping II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure 7essel Code, 1983 Edition through Summer 1983 Addenda requires that notes 1(b) and 2 of Category B-J, table IWB-2500-1 be used in the selection of welds for examination.

III. BASIS FOR RELIEF The first interval selection was based upon the 1974 Edition with Summer 1975 Addenda (74/S75) of ASME Section XI. As a result notes 1(b) ari 2 cannot be applied without some programmatic additions an modifications. In addition, although stress and utilization calculations exist for North Anna Unit 1, to correlation exists with actual weld locations. Total reuse of the first interval

("N plan is not desirable, since even though the 74/S75

( ,/ requirements were met, distribution of welds selected did not equitably cover certain line functions and designs.

IV. ALTERNATE EXAMINATION ISI class 1 piping welds will be selected for examination such that 25% of the total number of welds are examined during the interval. The 25% sampling vill include terminal ends as they appear on our plant isometrics as no corresponding stress calculations exist (ref. NUREG-0800, BTP 3.6.2-13). Terminal ends will include extremities of piping runs connected to vessels and pumps. Pipe integral attachments that act as rigid constraints to piping motion and thermal expansion shall have the first weld upstream and downstream of the integral arrachment selected. In piping runs which are maintained pressurized during normal plant conditions for only a portion of the run, the first normally closed valve is a terminal end. The weld on the high pressure side of the valve will be included in tne interval selection. Terminal end welds are identified in the second interval plan by the designation " Terminal End" in the comments column. The welds selected will be evenly distributed based upon line size, line function, and line design to the extent practicable.

(-

\__

I N1-NDERR 2-53 Rev. 2 1991

Thece selected welds will be examined in all future successive inspection intervals to the extent allowed by code editions approved at that time.

O l

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O N1-NDERR 2-54 Rev. 2 1991

RELIEF REOUEST NDE-5 I. IDENTJFICATION OF COMPONENTS Pressure retaining welds in punip casings Pump casings Reactor Coolant Pumps: (1-RC-P-1A, -1B, -1C)

Casing Exam Drawina No. Wold No. Identifier 11715-WMKS-RC-P-1A.1 1 Case 11715-WMKS-RC-P-18.1 1 Case 11715-WMKS-RC-P-1C.1 1 Case II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through Summer 1983 Addendu, Category B-L-1, Item No. B12.10 requires a volumetric examination to be O. performed on 100% of the pressure retaining welds in at least one pump in each group of pumps performing similar l functions in the system (e.g., reactor coolant pumps). In l addition, Category B-L-2, Item No. B12.20 requires a visual (VT-3) examination of one pump casing in each group of pumps performing similar functions.

III. BASIS FOR RELIEF A. pump Casing Weld Two of the North Area Power Station Unit 1 reactor coolant pumps are Westinghouse Model 93 controlled leakage pumps. The Model 93 pump's casing is fabricated by welding two stainless steel castings together. Thus, there is one circumferential pressure i boundaryfweld in the casing that is to be examined in

! accordance with Category B-L-1.

l; Since the installation of these pumps, it has been L recognized that a volumetric examination of the casing

! welds is not practical when employing current l ultrasonic techniques.

O G

l l-l' N1-NDERR 2-55 Rev. 2 1991 t-l

\

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

O V RELIEF REOUEST NDE-5 CONTINUED The physical properties of the stainless steel casting and weld material preclude a meaningful ultrasonic examination. The capability to examine these pump casing welds in the field did not exist until recently.

In the spring of 1981, an examination was performed on one of the reactor coolant pumps at the R.E. Ginna plant using the miniature linear accelerator (MINAC),

which was built under an EPRI sponsored program. This equipment has been made available to other utilities, and currently ennstitutes the only viable examination method for tb iumetric examination of reactor coolant pum

The volumetr_ xamination method is radiographic and is performed b, placing the.MINAC inside the pump casing and placing film on the outside of the pump. To perform the-examination, the pump must be completely disassembled, including removal of the diffuser adapter. This amount of disassembly is far beyond the amount of disassembly performed for normal maintenance.

Insulation must also be removed from the exterior of

()

V the pump casing.

The examination has been performed at four different sites, all of which have the Westinghouse Model 93 pump. The M1NAC examination was performed at Ginna in the spring of 1981, at Point Beach Unit 1 in the fall of 1981, at Turkey Point Unit 3 early in 1982 and at H.

B. Robinson Unit 2 later in 1982. No problems with the welds were found at any of the sites. A review of the original radiographs of the Point Beach Unit 1. pump was performed prior to the MINAC examination, and all the landmarks found were identified during field examination with no apparent change.

The successful performance of this volumetric examination using the MIIAC at four different sites demonstrates that the method is capable.of satisfying ASME Section XI examination requirements. However, the performance of the examination has shown there is a relatively high radiation exposure associated with it.

The total exposure associated with insulation removal, disassembly, examination and reassembly of the pump has averaged about 40 man-rem per pump.

A V

N1-NDERR 2-56 Rev. 2 1991

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l RELIEF REOUEST NDE-5 CONTINUED There have been no detects identified by the four successful examinations performed on these pumps to date. Several unsuccessful attempts have been made to examine these welds at Virginia Power's reactors: a volumetric examination was attempted at North Anna in 1982. A radioactive source was placed within the pump casing and film around the outside. The developcd film did not meet the density requirements for an acceptable examination. This examination was attempted twice at Surry. Both examinations yielded similar results.

B. Pump Casing The pump casing examinations are also not justified from a cost / benefit perspective. The pump disassembly, examination and reassembly is estimated to cost

$750,C70.

IV. ALTERNATE EXAMINATION A visual examination of the qrternal surfaces of one pump's Os casing weld and a surface examination of the weld to the extent practicable of the external casing weld of one pump will be performed to the extent and frequency of Category B-L-2 in lieu of the required Section XI examinations.

NOTE: Similar relief was submitted by letter dated March -

30, 1988 (corrected), serial no. 86-796B, for North Anna Unit 1, interval 1 and approved by NRC letter dated July 17, 1987, serial no.87-443.

O N1-NDERR 2-57 Rev. 2 1991

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

)

_f~

r RELTEP REOUEST NDE-6 i

I. IDENTIFICATION OF COMPONENTS l ISI class 1 Valve Bodies Exceeding 4 in. Nominal Pipe Size II. IMPRACTICABLI CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through Summer 1983 Addenda, Category B-M-2, Item-No. B12.50,- requires a visual examination (VT-3) be performed on the internal pressure boundary surfaces of one valve in each group of valves that are the same construction design and manufacturing method, and that perform similar functions in the system.

1 Because these examinations must be met whether or not the valves have to be disassembled for maintenance, this requirement is considered impractical.

III. BASIS FOR RELIEF The requirement to disassemble primary system valves for r~T the sole purpose of performing a visual examination of the

( ,) internal pressure boundary surfaces has a very smal) potential of increasing plant safety margins and a very disproportionate impact on expenditures of plant manpower and radiation exposure.

The ISI Class 1 systems at North Anna Unit 1 include valves which vary in size, design and manufacturer, but all are produced from either cast stainless steel or cast carbon steel. None of the valve bodies are welded.

The performance of both carbon and stainless cast valve bodies has been excellent in Pressurized Water Reactor (PWR) applications. . Based on this experience and-both industry and regulatory acceptance of these alloys, continued excellent service performance is anticipated.

A more practical approach is to examine the internal pressure boundary of only those valves that require disassembly for maintenance purposes. This methodology would provide a modified sampling program to that required by Section XI while significantly reducing radiation exposure to plant personnel.

l\J N1-NDERR 2-58 Rev. 2 1991

Os RELIEP REOUEST NDE-6 CONTINUED

! Virginia Electric and Power Company feels this approach would provide a reasonable level of assurance that the integrity of the primary system valves is being maintained.

IV. ALTERNATE EXAMINATION The visual examination of the internal pressure boundary surfaces will be performed, to the extent practical, when a valve is disassembled for maintenance purposes.

NOTE: Similar relief was submitted by letter dated March 30, 1988 (corrected), serial no. 86-796B, for North Anna Unit 1, interval 1 and approved by NRC letter dated July 17, 1987.

O O

N1-NDERR 2-59 Rev. 2 1991

O RELIEF REOUEST NDE-7 I. IDENTIFICATION OF COMPONENTS i

Branch connection welds - Main steam relief headers Drawina'No,,. Weld Nos.

l-11715-WMKS-101A-1 SW-52 to SW-56 11715-WMKS-101A-2 SW-15 to SW-17 and SW-40W to SW-41W 11715-WMKS-101A-3 SW-32W to SW-35W and SW-18W

-See Detail A and Section B-B of each drawing.

II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code,

~ 1983 Edition through Summer 1983 Addenda, Category C-F-2, i Item No. C5.31 requires circumferential pipe branch j connection welds be surface examined.

!-[ III. BASIS FOR RELIEF-The design of the main steam relief header branch connection welds calls for-the use of a reinforcement pad.

These pads are fillet welded and completely encase the branch connection welds.

IV. ALTERNATE PROVISIONS A surface-examination of the reinforcement-pad's fillet welds associated with one branch connection weld will be performed during the interval.

l l

O N1-NDERR 2-60 Rev. 2 1991 l _

O RELIEF REOUEST NDE-8 I. IDENTIFICATiGN OF COMPONENTS Pump Casing Welos Outside Recirculation Spray Pumps (1-RS-P-2A and 1-RS-P-2B)

Drawina No. Weld Nos.

11715-WMKS-RS-P-2A SW-1, SW-2, SW-3 LS-6, LS-7, LS-8 LS-9 (Partial Access)

LS-10 (Partial Access) 11715-WMKS-RS-P-2 B SW-1, SW-2, SW-3 LS-6, LS-7, LS-8 LS-9 (Partial Access)

LS-10 (Partial Access)

II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through Summer 1983 Addenda, Category C-G, Item Number C6.10, requires pump casing welds to have a surf ace examination each inspection interval . A surface examination of all of the pumps casing welds is not practicable.

III. BASIS FOR RELIEF Each of the two outside recirculation spray pump casings have a total of five circumferential welds and five longitudinal welds. Three of the circumferential welds (SW-1, SW-2 and SW-3), and three of the longitudinal welds (LS-6, LS-7 and LS-8) arc completely encased in concrete and are not accessible for examination from the outside diameter (O.D.). Of the remaining two longitudinal welds, one weld is partially encased in concrete (LS-9) and one weld is partially covered by a vibration plate (LS-10).

O.D. examinations can be performed on both of these longitudinal welds. The remaining two circumferential welds are completely accessible for examinations from the O.D. Surface examinations f rom the Inside Diameter (I.D. )

are not a practicable alternative. Access to the inside of the pump casings is limited by physical size (24 inch outside diameter), the pump shaft, and the pump shaft O support obstructions.

N1-NDERR 2-61 Rev. 2 1991

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

a RELIEF REOUEST NDE-8 CONTINUED IV. ALTERNATE PROVISIONS A surface examination of the accessible portions of the circumferential and longitudinal welds will be performed to the extent and frequency described in IWC-2500. A remote visual examination (VT-1) of the I.D. of the pump _ casing welds will be performed only if the pump is disassembled for maintenance.

O O

N1-NDERR 2-62 Rev. 2 1991

l 1

t RELIEF REOUEST NDE-9 l

I. IDENTIFICATION OF COMPONENTS Pump Casing Welds Low Head Safety Injection Pumps (1-SI-P-1A and 1-SI-P-1B) i Drawina No. Weld Nos.

. DOC 11715-WMKS-SI-P-1A 1, 2, 3 IS-1, LS-2, LS-3 LS-4 (Partial Access)

L:S-5 (Partial Access) 11715-WMKS-SI-P-1B 1, 2, 3 LS-1, LS-2, LS-3 13-4 (Partial Access)

LS-5 (Partial Access)

II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and_ Pressure Vessel Code, 1983 Edition through Summer 1983 Addenda, Category C-G, Item Number C6.10, requires pump casing welds to have a surface examination each inspection interval. A surface examination of all of the pumps casing welds is not practicable.

III. BASIS FOR RELI4F Each of the two low head safety injection pump casings have a total of five circumferential welds and five longitudinal welds. Three of the circumferential welds (1,2 and 3) and three of the longitudinal welds (LS-1, LS-2 and LS-3) are completely encased in concrete and are not accessible for examination. Of the remaining two longitudinal welds, one weld is partially encased in concrete (LS-4) and one weld is partially covered by a vibration plate (LS-5). Partial Outside Diameter (O.D.) examinations can be performed on both of these longitudinal welds. The remaining two circumferential welds are completely accessible for examinations from the O.D. Surface examinations from the Inside Diameter (I.D.) are not a practicable alternative.

Access to the inside of the pump casings is limited by f-ss physical size (24 inch outside diameter), the pump shaft, and the pump shaft supports.

()

N1-NDERR 2-63 Rev. 2 1991

O RELIEF REQUEST NDE-9 CONTINUED IV. ALTERNATE PROVISIONS A surface exanination of the accessible portions of circumferential and accessible longitudinal welds will be performed to the extent and frequency described in IWC-2500. A remote visual examination (VT-1) of the I.D. of the pump casing welds will be performed only if the pump is disassembled for maintenance.

O O

l N1-NDERR 2-64 Rev. 2 1991

('..;

li RELIEF REOUEST NDE-10 (WITHDRAWN) l l-N1-NDERR 2-65 Rev. 2 1991

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

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O v RELIEF REOUEST NDE-11 I. IDENTIFICATION OF COMPONENTS Ultrasonic calibration blocks II. IMPRACTICABfE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel-Code, 1983 Edition through Summer 1983 Addenda, gives specific requirements for the fabrication of ultrasonic calibration blocks. Specifically, paragraph IWA-2232(a) and IWA-2232(c)(4)

III. BASIS FOR RELIEF North Anna power station was constructed prior to the-issuance and adoption of ASME Section XI. Therefore, ultrasonic calibration blocks were fabricated before the-guidelines of ASME Section XI were developed and approved.

Meeting the requirements of IWA-2232(a) and IWA-2232(c)(4) of the 1986 Code would require us to manufacture new calibration blocks. Using the existing calibration blocks l allows us to correlate ultrasonic data from the first interval inspections as required by IWA-1400(h).

IV. ALTERNATE PROVISIONS The existing ultrasonic calibration blocks will be used for the second inspection interval examinations in lieu of current code requirements. In addition, code case N-461- ,

Alternative Rules for Piping Calibration Block Thickness, will be used as necessary.

Note: It is_our understanding that Code Case N-461 is scheduled for approval in Regulatory Guide 1.147 Revision 8. Any limitations or modifications to this Code Case as indicated in the Regulatory Guide shall be adhered to, i

l O

l N1-NDERR 2-66 Rev. 2 1991

O RELIEF REOUEST NDE-LZ I. IDENTIFICATION OF COMPONENTS ISI Class 1 and Class 2 Welds II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through Summer 1983 Addenda, requires that the entire volume or area of a weld be examined before credit of examination can be given.

III. BASIS FOR RELIEF Throughout the ISI Class 1 and ISI Class-2 systems situations exist where the entire examination volume or area cannot be examined due to interference by another component or part geometry.

IV. ALTERNATE PROVISIONS Code Case N-460 alternative examination coverage for Class O 1 and Class 2 volds, will be utilized in its entirety for determination of examination credit.

Note: It is our understanding that Code Case N-460 is scheduled for approval in Regulatory Guide 1.147 Revision 8. Any limitations or modifications to this code case as indicated in the Regulatory Guide shall be adhered to, l-l l

O N1-NDERR 2-67 Rev. 2 1991

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

t-RELIEF REOUEST NDE-13 I. IDENTIFICATION OF COMPONENTS ISI Class 1 and 2 Piping, Vessel and Component Welds II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, i 1983 Edition through Summer 1983 Addenda, IWA-2600, weld reference system.

III. BASIS FOR RELIEF- l The original construction code used a' North Anna Power Station, ANSI B31.7, 1969 Edition, did not establish a weld l reference system. Immediate establishment of a weld j

l. reference system cannot be practically attained within the :

scope and schedule of existing outages.

IV. ALTERNATE PROVISIONS North Anna Unit 1 has recently updated its weld isometrics,

)

N/

providing a detailed identification of location. It is our intention to use these drawings for tracking and locating welds.

In addition, an welds requiring volumetric examinations are examined a reference will be established for each weld, indicating a zero point and direction of examination.

Welds which contain recordable indications-(RI) shall be marked to ensure location of the indication, using appropriate reference marks. This reference system and marks will be permanently fixed.on the weld.

l O

N1-NDERR 2-68 Rev. 2 1991

i RELIEF REOUEST NDE-14 I. IDENTIFICATION OF COMPONENTS pressure Retaining Welds in the Reactor Vessel and Vessel Nozzle area examined by the automated vessel tool inspection device.

II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through Summer 1983 Addenda, IWA-2600, weld reference system.

III. BASIS FOR RELIEF The automated tool establishes its reference point using an existing zero reference in the reactor vessel. This point allows the device to repeat examination locations without the necessity of any other reference systema. It accomplishes this by the use of an electronic encoder system which provides for sufficient repeatability.

IV. ALTERNATE PROVTSIONS The automated vessel tool examinations will continue to establish its reference system based upon the existing zero reference. No other system is planned or deemed necessary.

O N1-NDERR 2-69 Rev. 2 1991

O RELIEF REOUEST NDE-15 I. IDENTIFICATION OF COMPONENTS i

Nozzle Inner Radius Sections Steam Generators: (1-RC-E-1A, 1-RC-E-1B, 1-RC-E-1C)

Drawina Nqi Inner Radius Identification No.

11715-WMKS-RC-E-1A.2 11NIR and 12NIR (ISI Class 1)

(Steam Generator A) 11715-WMKS-RC-E-3 B . 2 11NIR and 12NIR (ISI Class 1)

(Steam Generator B) 11715-WMKS-RC-E-1C.2 11NIR and 12NIR (ISI Class 1)

(Steam Generator C)

II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure vessel Code, 1983 Edition through Summer 1983 Addenda, Category B-D, Item No.-B3.140, requires the nozzle inside radius sections of the Steam Generators to be volumetrically examined.

Relief is requested from the volumetric examination requirements of the nozzle inner radij for the Steam Generator channel head nozzles.

III. BASIS FOR RELIEF The only viable ultrasonic technique currently available to examine nozzle inner radii that we know of involves-the fabrication of calibration blocks that closely simulates i the O.D. and I.D. nozzle geometry. This is necessary so that search units can be produced that will interrogate the inner radius section at. precise angles. Also, in order to obtain meaningful results, the nozzle material grain structure must be such that an adequate signal-to-noise l ratio can be obtained over a long metal-path distance. For nozzles with a complex 0.D. profile, examination personnel need training on the proper placement and manipulation of the search unit.

O i

N1-NDERR 2-70 Rev. 2 1991

p

~

RELIEF REOUEST NDE-15 ;

CONTINUED The Class 1 nozzles on the North Anna Unit 1 Steam '

Generators are integrally cast into the channel head.

Therefore, the nozzles contain examination limitations such as an irregular o.D. profile, rough surface condition and attenuative grairi structure. Due to the above, we believe that a full scale nock-up of the nozzle would be necessary to develop a viable inner radius technique and to provide adequate training for examination personnel. j The Unit 1 Steam Generators are scheduled to be replaced in .

the second period of Interval 2 with generators that !

contain forged channel heads. Calibration blocks have been !1 ordered to facilitate examination of the replacement ,

generator channel head nozzle inner radii. ;

il IV. ALTERNATE EXAMINATION !i As an alternative to the Section XI required volumetric examination of the Steam Generators six Category B-D nozzle inside radius sections (11NIR and 12NIR on 1-RC-E-2A,-1B and -lC), the areas will be visually examined (VT-1) from the nozzle I.D. using direct or remote techniques per the [

()T

\_ schedule shown in Table IWB-2412-1, Inspection Program B, i l

up until the time that the Steam Generators are replaced.

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l N1-NDERR 2-71 Rev. 2 1991 l

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L .

RELIEF REOUEST NDE-16 I. IDENTIFICATION OF COMPONENTS ,

Nozzle Inner Radius Section Pressurizer: (1-RC-E-2)

Drawina No. Inner Radius Identification Nq.

11715-WMKS-RC-E-2 9NIR II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through Summer 1983 Addenda, Category B-D, Item No. B3.120 requires the nozzle inside radius sections of the pressurizer to be volumetrically examined.

Relief is requested from the-volumetric examination l requirements of the nozzle inner radius for the pressurizer surge line nozzle.

III. BASIS FOR RELIEF

)

The North Anna Unit 1 pressurizer surge nozzle is !l '

surrounded by 78 heater penetrations. In order to access the O.D. of the nozzle to examine the inner radius; Site Engineering recommended that all the heater cables be l disconnected prior to the removal of the insulation. This recommendation is due to the possibility of damage to the heater element connections if the insulation is removed i while the cables are connected.

I As shown on the attached survey of the applicable area, the l dose rate is 500mr in the general area, 900MR at one foot and 3000 to 3500 MR contact. Based upon estimates provided by site Electrical Maintenance, Insulation Removal, and .

ISI/NDE, it would require ten man hours to disconnect and reconnect the heater cables, four man hours to remove and reinstall the reflective insulation and two man hours to prepare and examine the nozzle inner radius. The site ALARA group estimates that the resulting dose would be 11.2 man rom.

O N1-NDERR 2-72 Rev. 2 1991

O RELIEF REQUEST _NDE-16 CONTINUED The UT technique that would be used to examine the nozzle inner radius requires good access to the nozzle 0.D. ir.

crder to properly place and manipulate the search unit. We feel thtt the confined access to the noztle as a result of the pressurizer skirt, surgo line piping and heater penetrations, and the are.a dose xctes and complex nature of the examination will result in a "best effort" examination.

Therefore, it is felt that the gain in system integrity is tiot commensurate with the exposure associated with the examination.

IV. ALTERNATE EXANItJATION A visual (VT-2) examination of the pressurizer surge line nozzle-to-vessel weld will be performed during the normally scheduled system leakage test each refueling. In addition, Techn. cal Specifications require that the Reactor Coolant System Leak Rate be limited to one gallon per minuto unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Additionally, the containment atmosphere particulate radioactivity is monitored every 12 O hours.

!. i

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i l

lO N1-NDERR 2-73 Rev. 2 1991 l _ _ _ . _ _ __

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

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

i 9 ;

2.7.2 SPT SERIES RELIEF REQUESTS i

O til-004 d 2-74 Rev. 2 1991

RELIEF REQUEST SPT-1 I. IDENTIFICATION OF COMPONENTS System : Chemical and Volume Control (CH)

Components: Piping on drawing 11715-CBM-095C-2, Sheet 2 of 2, between the pumps, and the boundaries listed below.

EUHE LINE BOUNDARY ISI CLASS 1-RC-P-1A 2"-CH-214-1502-Q1 1st Flange 2 1 1/2"-CH-398-1502-Q1 1st Flange 1 3/4"-CH-372-1502-Q1 1st Flange 2 1" & 3/4" ~. . . e 1-CH-342 1 1" & 3/4" Aine 1-CH-341 1 1 1-RC-P-1B 2"-CH-215-1502-Q1 1st Flange 2 1 1/2"-CH-397-1502-Q1 1st Flange 1 3/4"-CH-373-1502-Q1 1st Flange 2 1" & 3/4" line 1-CH-364 1 1" & 3/4" line 1-CH-363 1 1-RC-P-1C 2"-CH-216-1502-Q1 1st Flange 2 1 1/2"-CH-396-1502-Q1 1st Flango 1 3/4"-CH-374-1502-01 1st Flange 2 1" & 3/4" line 1-CH-386 1 1" & 3/4" line 1-CH-385 1 II. IMPRACTICAL CODE REQUIRL{ENTS ISI Class 1 System Hydrostatic Test per IWB-5222 Po = 2500 psig To = 496F Test-Pressure = 2550 psig ISI Class 2 System Hydrostatic Test per IWC-5222 Pd a 2735 psig Td = 250F Test Pressure = 3419 psig III. BASIS FOR RELIEF The seal injection flow is provided from the charging pumps to the reactor coolant pump. This flow divides in the pump with part of the flow being introduced to the.RCS, and part of the flow passing over the pump seals and through the various seal returns. Since-the seal injection directly adds to the RCS inventory, and no itermedidate isolation exists, any fs- pressurization above normal charging pressure would require

( ) that the RCS be pressurized to the same amount. This would N1-004d 2-75 Rev. 2 1991

1 RELIEF REQUEST SPT-1 ;

CONTINUED 1 exceed the ASME Class I hydrostatic test pressure (2280 psig) limits on the balance of the reactor coolant system.

IV. ALTERNATE TESTING The normal system leakage test per IWB-5221 with visual (VT-2) examination after each refueling is an adequate alternative to

. verify the integrity of these components. Additionally, Class 2 piping vill be visually (VT-2) examined at normal operating pressure.

l i

1 t

I-l l-\

N1-004d 2-76 Rev. 2 1991

RELIEF REQUEST SPT-2 I. IDENTIFICATION OF COMPONENTS System : Chemical and Volume control (CH)

Components: Piping located on drawing 11715-CBM-095C-2, Sheet 1 of 2, between the valves listed below.

VALVES LINE 1-CH-328 and 1-CH-HCV-1311

- 2"-CH-68-1502-Q1 l 1-CH-325 and 1-CH-496 3"-CH-1-1502-Q1 l l

ISI Class : 1 )

II. IMPRACTICAL CODE REQUIREMENTS .

I System Hydrostatic Test per IWB-5222. Po=2500 psig, To=496 P, !

Test pressure is 2550 psig per IWB-5222. j i

III. BASIS FOR RELIEF O Check valves 1-CH-328 and 1-CH-325 prevent the components listed above from being pressurized to Section XI requirements without pressurizing the reactor coolant system. The code required test pressure of 2550 psig will overpressurize the reactor coolant system.

Also, the power operated relief valves (1-RC-PCV-1456 and 1-RC-PCV-1455C) of the reactor coolant system are designed to limit the pressurizer pressure to a value below the fixed high-pressure-reactor trip setpoint (2385 psig). The relief

-valve setpoints-are 2335 psig. It is not desirable to take the reactor coolant system above-the power operated relief valve setpoint.

IV. ALTERNATE TESTING I

As an alternative, the reactor coolant system will be pressurized to a pressure as close as practical to 2335 psig-but not less than 2300 psig while the reactor-is in a. shutdown condition in order to seat check valves 1-CH-325 and 1-CH-328, i thus creating a pressure boundary. The components listed l- above will then be tested at a pressure between 2300 psig and 2335 psig using a1 charging pump.

, N1-004d 2-77 Rev. 2 1991 l

I O RELIEF REQUEST SPT-2 l

CONTINUED NOTE: Similar relief was submitted by letter dated May 22, 1987, Serial No. 86-796A for North Anna Unit 1, and approved by NRC letter dated July 17, 1987.

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O N1-004d 2-78 Rev. 2 1991

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I RELIEF REQUEST SPT-3 I. IDENTIFICATION OF COMPONENTC I

System : Residual Heat Removal (RH) l Components: Piping located on drawing 11715-CBM-094A-2, Sheet !

1 of 2, between the valves listed below.

VALVES LINE 1-RH-MOV-1701 & 14"-RH-1-1502 1-RH-MOV-1700 ISI Class : 1 II. IMPRACTICAL CODE REQUIREMENTS Class 1 System Hydrostatic Test IWB-5222. Po=2235 psig, To=650 F, Test pressure por IWB-5222 is 2280 psig.

III. BASIS FOR REIIEF During the system hydrostatic test of the primary system, 1-( RH-MOV-1700 and 1-RH-MOV-1701 are closed in order to prevent

, possible overpressurization of the residual heat removal l system. Thus, the portion of the RHR system identified above

! cannot be pressurized with the primary system and due to-system design, it cannot be pressurized without opening one of the MOVs.

IV. ALTERNATE TESTING As an alternative, the components listed above will be tested in accordance with IWC-5222 during the hydrostatic test administered to line 14"-RH-2-602. The test pressure will be 584 psig as' determined by the setpoint of relief valves 1-RH-RV-1721A and 1-RH-RV-17218. This alternative is considered-sufficient since the relief valves are set at 467 psig. As a result, line 14"-RH-1-1502 should not see a pressure-significantly higher than 467 psig. In addition, 1-RH-MOV-1700 and 1-RH-MOV-1701 will not open if the reactor coolant pressure is 660 psig.

Relief was granted to North Anna power Station Unit 1 per-Safety Evaluation Report dated July 13, 1987 (TAC No.-64718) for the same situation described.above.

N1-004d 2-79 Rev. 2 1991 l'

I O RELIEF REQUEST SPT-4 I. IDENTIFICATION OF COMPONENTS System : Safety Injection (SI)

Components: Piping located on drawing 11715-CBM-096B-2, Sheet 4 of 4, between the valves listed below.

VALVEg LINES 1-SI-83, 1-SI-190 and 1-SI-195 6"-SI-131-1502 1-SI-86, 1-SI-192 and 1-SI-197 6"-SI-133-1502 1-SI-89, 1-SI-194 and 1-SI-199 6"-SI-132-1502 1-SI-95, 1-SI-211 and 1-SI-204 6"-SI-19-1502 2"-SI-59-1502 1-SI-99, 1-SI-209 and 1-SI-203 6"-SI-21-1502 2"-SI-61-1502 1-SI-103, 1-SI-213 and 1-SI-205 6"-SI-16-1502 0- 2"-SI-63-1502 ISI Class : 1 II. IMPRACTICAL CODE REQUIREMENTS Class 1 System Hydrostatic Test per IWB-5222. Po=2235 psig, To=160 F, Test Pressure per IWB-5222 is 2432 psig.

III. BASIS FOR RELIEF The first valve in each set of valves listed above prevent the components listed above from being pressurized without pressurizing the reactor coolant system. The power operated relief valves (1-RC-PCV-1456 and 1-RC-PCV-1455C) of the reactor coolant system are designed to limit the pressurizer pressure to a value below the fixed high-pressure reactor trip setpoint (2385 psig). The relief valve setpoints are 2335 psig which is below the test pressure of 2432 psig. It is not desirable to take the reactor coolant system above the power operated relief valve setpoint.

N1-004d 2-80 Rev. 2 1991

O)

-N m RELIEF REQUEST SPT-4 CONTINUED IV. ALTERNATE TESTING As an alternative, the reactor coolant system will bo pressurized to a pressure as close as practical to 2335 psig but not less than 2300 psig while the reactor is in a shutdown condition to create a pressure boundary at the first valve of each set listed above. These components will then be vested l to a pressure beween 2300 psig and 2335 psig using a charging pump. The reactor coolant system will be borated to a concentration equal to or greater than cold shutdown boron concentration.

NOTE: Similar relief was submitted by letter dated May 22, 1987, Serial No. 86-796A for North Anna Unit 1, and approved by NRC letter dated July 17, 1987, i

O N1-004d 2-81 Rev. 2 1991 l

l 1

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

~' RELIEF REQUEST SPT-5 I. IDENTIFICATION OF COMPONENTS System : Chemical and Volume Control (CH)

Components: Piping located on drawing 11715-CBM-095C-2, Sheet 1 of 2, between the valves listed below.

VALVES LIEJJ ,

1-CH-496, 1-CH-HCV-1311, 3/4"-CH-240-1502 l and 1-CH-MOV-1289A 2"-CH-68-1502 3"-CH-1-1502 3"-CH-79-1502 ISI Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Class 2 System Hydrostatic Test per IWC-5222. Since there are no relief valves for the above components, test prassure per IWC-5222 is 3419 psig.

III. BASIS FOR RELIEF Check Valves 1-CH-328, 1-OH-325 and 1-CH-496 prevent the components listed above from being pressurized without pressurizing the reactor coolant system. The code required test pressure of 3419 psig will overpressurize the reactor coolant system.

Also, the power. operated relief valves (1-RC-PCV-1456 and 1-RC-PCV-1445C) of the reactor coolant system are designed to limit the pressurizer pressure to a value bc 7w the fixed-high pressure reactor trip setpoint (2385 ps 7). The relief valve-setpoints are 2335 psig. It is not desirable to take the reactor coolant system above the power operated relief valve setpoint.

IV. ALTERNATE TESTING As an alternative, the reactor coolant system will be pressurized to a pressure as close as practical to 2335 psig but not less than 2300 psig using a charging pump-while the reactor is in a shutdown condition to create a pressure boundary at check valves 1-CH-328 and 1-CH-496. The components listed above will then be tested to a pressure between 2300 psig and 2335 psig using a charging pump.

N1-004d 2-82 Rev. 2 1991

RELIEF REQUEST SPT-S CONTINUED NOTE: Similar relief was submitted by letter dated May 22, 1987, Serial No. 86-796A for North Anna Unit 1, and approved by NRC letter dated July 17, 1987.

O v

i:

l O

'N1-004d 2-83 Rev. 2 1991

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

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

O RELIEF REQUEST SPT-6 I. IDENTIFICATION OF COMPONENTS System : Safety Injection Components: Piping and valves located on drawings 11715-CBM-096A, Sheet 2 of 3, and 11715-CBM-096B, Sheet 4 of 4, listed below. ,

l yALVE CONNECTING LINE VALVE -

l 1-SI-MOV-1890C and 10"-SI-18-1502 l 1-SI-MOV-1890D 10"-SI-238-1502 to 6"-SI-133-1502 1-SI-197 to 6"-SI-132-1502 1-SI-199 to 6"-SI-131-1502 1-SI-195 1-SI-MOV-1890A 10"-SI-15-1502 )

to 6"-SI-16-1502 1-SI-213 1 to 6"-SI-130-1502 1-SI-211 l to 6"-SI-19-1502 ;

1-SI-MOV-1890B 10"-SI-140-1502 O to 6"-SI-21-1502 1-SI-209 1-SI-193 2"-SI-55-1502 SI-194-1-SI-191 2"-SI-53-1502 1-SI-192 1-SI-188 2"-SI-51-1502 1-SI-190 ISI Class : 2 II. IMPRACTICAL CODE REQUIREMENTS Olass 2 System Hydrostatic Test per IWC-5222. Pd = 2485 psig, Design Temperature is'less than 200 F, Test pressure is 2733.5 psig.

III. BASIS FOR RELIEF Check valves 1-SI-83, 1-SI-86, 1-SI-89,-1-SI-95, 1-SI-99 and 1-SI-103 prevent the components listed above from being pressurized without pressurizing the reactor coolant system.

The Code required test. pressure of 2733.5 psig will overpressurize the reactor coolant system.

O N1-004d- 2-84 Rev. 2 1991

O RELIET REQUEST SPT-6 CONTINUED !

The power operated relief valves (1-RC-PCV-1456 and 1-RC-PCV-1455C) of the reactor coolant system are desigiled to limit the pressurizer pressure to a value below the fixed high-pressure reactor trip setpoint (2385 psig). The relief valve sotpointo are 2335 psig which is below the test pressure of 2733.5 poig.

It is not desirable to take the reactor coolant system above the power operated relief valve sotpoint.

IV. ALTERNATE TESTING As an alternative, the reactor coolant system will be pressurized to a pressure as close as practical to 2335 psig but not less than 2300 psig while the reactor is in a shutdown condition to create a pressure boundary at check valves 1-SI-83, 1-SI-86, 1-SI-89, 1-SI-95, 1-SI-99 and 1-SI-103.

These components will then be testod to a pressure betwoon 2300 psig and 2335 psig using a test pump.

NOTE: Similar relief was submitted by letter dated May 22, l

l O 1987, Sorial No. 86-796A for North Anna Unit 1, and approved by NRC letter dated July 17, 1987.

l-l

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l l

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N1-004d 2-85 Rev. 2 1991 l

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1 O RELIEF REQUEST SPT-7

1. IDENTIFICATION OF COMPONENTS System Safety Injection (SI)

Components: piping located on drawings 11715-CBM-096B-2, Shoots 1 of 4, 2 of 4 and 3 of 4, between the sets of valves listed below.

VALVES LINE NUMBERS 1-SI-I 65A, 1-SI-125 12"-SI-123-1502 and 1-SI-123 3/4"-SI-78-1502 1-SI-MOV-1865B, 1-SI-142 12"-SI-124-1502 and 1-SI-140 3/4"-SI-84-1502 1-SI-MOV-1865C, 1-SI-159 12"-SI-125-1502 and 1-SI-157 3/4"-SI-80-1502 ISI Class : 2 II. IMPRACTICAL CODE REQUIREHENTS Class 2 System Hydrostatic Test per IWC-5222. P =2485 psig, 4

T=200 F, Test pressure per the code in 2733.5 psig since there is no overpressure protection for the above components.

III. BASIS FOR REQUEST Check valves 1-SI-125, 1-SI-142, and 1-SI-159 at the Class 1 and 2 system boundaries prevent the pressurization of the above components without pressurizing the primary system. The required test pressure is 2733.5 psig as stated above, ,'hich would overpressurize the primary system.

IV. ALTERNATE TESTING As an alternative, it is r; quested that the Class 2 components listed above be tested to the conditions of IWB-5222 which is required for the adjacent Class 1 piping. The nomins1 operating pressure is 660 psig and temperature is 120 F.

Thus, testing per IWB-5222 would require a test pressure of 724 psig. This should be adequate considering the nominal operating conditions.

NOTE: Similar relief was submitted by letter dated May 22, 1987, Serial No. 86-796A for North Anna Unit 1, and approved by NRC letter dated July 17, 1987.

O N1-004d 2-86 Rev. 2 1991

RELIEF REQUEST SPT-8 i I. IDENTIFICATION OF COMPONENTS Systems Main Steam (SHP)

Decay Heat Release (SPHV)

Feedwater (WFPD)

Chemical Feed (CFPD & SGD)

Blowdown (WGCB)

Sampling (SS)

Components: Secondary side of the Steam Generators and attached piping located on drawings 11715-CBM-070B-2, Shoot 1 of 3, 2 of 3, and 3 of 31 11715-CBM-074A-2, Shoot 1 of 3; 11715-CDM-089B, Shoot 3 of 41 11715-CBM-098A, Sheet 2 of St 11715-CDM-102A-2, Shoot 2 of 2; and 13075-CBM-102C, Shoot 1 -

of 1 between the components listed in Tablo SPT-8.

ISI Class : 2 II. IMPRACTICAL CODE REQUIREMENTS l

() Class 2 Hydrostatic Test per IWC-5222 and IWA-5213(d).

Foodwater components, Pd =1100 psig, T d>200 F, test pressure For l por IWC-5222 would be 1375 psig. For the Chemical Food componento, Pd =1775 poig, T d<200 F, test pressure per IWC-5222 would be 1952.5 psig. The remaining components have P 1085 psig, T d>200 F, test pressureporIWC-5222wouldbe13N=6psig.

III. BASIS FOR REQUEST Westinghouse, the manufacturer of the steam generators, gives specific testing requirements for the steam generator which-must also be applied to the components listoa above becauno these components cannot be isolated from the steam generators.

IV. ALTERNATE TESTING The Westinghouse Technical Manual for the Steam Generators requires the secondary side to be pressurized to 1356 psig,-

held for 30 minutes and then reduced to design pressure (1085 psig) for a sufficient time to permit proper examination of welds, closures and surfaces for leakage or weeping.

O N1-004d 2-87 Rev. 2 1991

O RELIEF REQUEST SPT-8 CONTINUED The secondary side will be held at 1356 psig for 30 ninutes and then reduced to 1085 psig for a minimum of 3 1/2 hours in accordance with Section XI. A VT-2 examination will then be performed on the components described in Table SPT-8.

i NOTEt Similar rollef was submitted by letter dated May 22, ,

1987, Serial No. 86-796A for North Anna Unit 1, and I approved by HRC letter dated July 17, 1987. l 6

O i

9 O

N1-004d 2-88 Rev. 2 1991

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. _ _ _ _ __m. . ._ . _ . . _ _ _ _ _ . _ _ . _ _ _ _ _ . _ . _ _ . _ . _ _ _ . . _ _ . _ , . . . . . _ .

i Table SIT-8 Components TROM To COMPONENT CONNECTED PIfil!G C011EQllDLT 1-EC-E-1A 3 2 "-SilP 6 01 1-MS-SV-101A to 32"-SHP-22-601 1-MS-SV-102A 1-MS-SV-103A 1-MS-SV-104A 1-MS-SV-105A to 6"-SitP-37-601 &

1 "-Sit P- 8 4 - 6 01 1-MS-PCV-101A to 3"-SitP-64-601 & 1-MS-18 1 "-S!!P-7 8 - 6 01 1-MS-327 to 1 1/2"-SilPD-6-601 1-MS-22 to 1/2"-S!!PD-71-601 1-MS-26 1-RC-E-1A 32"-SHP-1-601 1-MS-35 1-NRV-MS-101A 3 "-Sit P-6 0- 6 01 1-MS-344 1-RC-E-1A 3 2 "-S!!P 6 01 to 3 2"-S!!-P-2 2-6 01 O to 3"-SilP-45-601 to 3"-SHP-531-601 to 1"-SHP-518-601 1-MS-344 1-MS-NRV-103A 1-MS-346 1-MS-348 1-RC-E-1A 2"-SS-302-601 1-SS-576 1-RC-E-1A 3 2 "-S!!P 6 01 to 32"-SHP-22-601 to 3"-SDHV-1-601 t o 4 "-S DliV-4 -601 1-MS-20 1-RC-E-1A 16"-WFPD-24-601 1-FW-47 to 3"-WAPD-427-601 1-FW-68 to 3/4"-CFPD-1-601 1-WT-39 1-RC-E-1A 2"-WGCB-4-6G1 1-BD-1 2"-WGCD-5-601 1-BD-4 1"-WGCB-6-601 1-BD-2 1-RC-E-1A 2"-SGD-4-601 1-WT-459

, O N1-004d 2-89 Rev. 2 1991

em

' RELIEF REQUEST SPT-8 Table SPT-B Components CONTINUED FROM TO COMPONEllT CONNECTED PIPING COMPONIlD' 1-RC-E-1B 3 2 "-SilP-2 -6 01 to 32"-S!!P-23-601 1-MS-SV-101B 1-MS-SV-102B 1-MS-SV-103B 1-MS-SV-104B 1-MS-SV-105B to 6"-SilP-38-601 &

1"-SHP-85-601 1-MS-PCV-101B to 3"-SHP-65-601 1-MS-325 1"-Sit P- 8 0- 6 01 1-MS-57 ,

to 1 1/2"-SitPD-8-601 1-MS-60 l to 1/2 "-S11PD-7 3-601 1-MS-64 l

)-RC-E-1B 32"-S!!P-2-601 1-MS-74 1-MS-NRV-101B l

/~' 3"-SHP-61-601 1-MS-353 j Na])

1-RC-E-1B 3 2 "-Slip 6 01 to 32"-S!!P-2 3-601 to 3"-SitP-46-601 1-MS-352 to 3"-SIIP-61-601 1-MS-353 to 3"-SHP-533-601 1-MS-NRV-103B to 1"-S11P-52 0-601 1-MS-356 1-MS-357 1 1

1-RC-E-1B 2"-SS-225-601 &

1"-SS-303-601 1-SS-218 1-RC-E-1B 3 2 "-SilP-2-601

^

to 32"-SIIP-23-601 to 3"-SDliV-2-601 to 4"-SDHV-4-601 1-MS-20 1-RC-E-1B 16"-WFPD-23-601 1-FW-79 to 3"-WAPD-28-601 1-FW-100 to 3/4"-CFPD-2-601 1-WT-51 1-RC-E-1B 2"-WGCD-7-601 1-BD-10 2"-WGCB-8-601 1-BD-13 2"-WGCB-9-601 1-BD-11

() 1-RC-E-1B 2"-SGD-5-601 1-WT-482 N1-004d 2-90 Rev. 2 1991

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

O RELIEF REQUEST SPT-8 Table SPT-8 i Components I CONTINUED FROM TO COMPONENT CONNECTED PIPING f&MPONENT 1-RC-E-1C 32"-SHP-3-601 to 32"-SHP-24-601 1-MS-SV-1010 1-MS-SV-102C 1-MS-SV-103C 1-MS-SV-104C 1-MS-SV-105C to 6"-SHP-39-601 &

1"-SHP-86-601 1-MS-PCV-101C to 3"-SPD-66-601 & 1-MS-95 ;

1"-SE"-62s601 1-MS-23 to 1 '/2"-SHPD-7-601 1-MS-98 to 1/2--SHPD-75-601 1-MS-412 1-RC-E-1C 32"-SHP-3-601 1-MS-112 1-MS-NRV-1C 3"-SHP-62-601 1-MS-362 1-RC-E-1C 32"-SHP-3-601 to 32"-SHP-24-601 to 3"-SHP-47-601 to 3"-SHP-62-601 1-MS-362 to 3"-SHP-532-601 1-MS-NRV-103C to 1"-SHP-519-601 & 1-MS-365 '

1-MS-1048 1-RC-E-1C 2"-SS-227-601 1"-SS-304-601 1-SS-217 1-RC-E-1C 32"-SHP-3-601 to 32"-SHP-24-601 to 3"-SDHV-3-601 to 4"-SDHV-4-601 1-MS-20 1-RC-E-1C 16"-WFPD-22-601 1-FW-111 to 3"-WAPD-29-601 1-FW-132 to 3/4"-CFPD-3-601 1-WT-67 1-RC-E-1C 2"-WGCD-10-601 1-BD-19 2"-WGCB-11-601 1-BD-22 1"-WGCB-12-601 1-BD-20 1-RC-E-1C 2"-SGD-5-601 1-WT-505

(

N1-004d 2-91 Rev. 2 1991

RELIEF REQUEST SPT-9 I. IDENTIFICATION OF COMPONENTS System : Feedwater (WAPD)

Components: Piping located on drawing 11715-CBM-074A-2, Sheets 1 of 3 and 3 Of 3, between the valves listed below.

VALVE CONNECTING LINES VALVE 1-FW-62 3"-WAPD-10-601 to 3"-W1.PD-9-601 1-FW-66 1-FW-64 3"-WAPD-9-601 1-FW-70 1 I

1-FW-93 3"-WAPD-12-601 '

to 3"-WAPD-11-601 1-FW-98 l

1-FW-96 3"-WAPD-11-601 1-FW-102 l 1-FW-126 3"-WAPD-14-601 l O to 3"-WAPD-13-601 1-FW-130 '

1-FW-128 3"-WAPD-13-601 1-FW-134 1-FW-278 4"-WAPD-39-601 to 3"-WAPD-10-601 1-FW-66 ISI Class : 3 II. IMPRACTICAL CODE REQUIREMENTS Class-3 System Hydrostatic Test per IWD-5223 and IWA-5213(d). .

Pd =1400 psig, Td < 200 F, Test Pressure is 1540 psig per IWD- !

5223.

III. BASIS FOR RELIEF Due to check valves 1-FW-132, 1-FW-100, and 1-FW-68, the piping-listed above cannot be pressurized without pressurizing the steam generators. The code required test pressure of 1540 psig would overpressurize the steam generators.

O N1-004d 2-92 Rev. 2 1991

C:)

RELIEF REQUEST SPT-9 CONTINUED IV. ALTERNATE TESTING Since the components linted above cannot be pressurized without pressurizing the steam generators, they must be tested por the required manufacturer's hydrostatic test method.

Thorofore, the proposed alternative examination in the examination described in the Westinghouse Technical Manual for the secondary sido of the steam generators. The examination is to pressurito the secondary side of the steam generators to 1356 psig, hold for 30 minutes, and then reduce to the design pressure (1085 psig) for 3 1/2 hours. A VT-2 examination will then be performed.

NOTE: Similar relief was submitted by letter dated May 22, 1987, Sorial No. 86-796A for North Anna Unit 1, and approved by HRC letter dated July 17, 1987.

O O

N1-004d 2-93 Rev. 2 1991

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I RELIEF REQUEST SPT-10 !,

I l (WIT!!DRAWil) !

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!- - N1-004d 2-94 Rev. 2 1991 -

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,..___._____-.____-_,-w__s--,-m-.._..,_-__-_------.--_____,----_m___.

--.-. m__4. _ _. . . . - , _ _ _ ._ . - _ _ _ _ _ _ . -- --e..

_ - _ _ - - - ~ _ . -

RELIEF REQUEST SPT-11

1. IDENTITICATION or COMPONENTS System : Reactor Coolant (RC)

Components: Partial Ponotration Wolds 0 Dottom of Roactor Vossol Dottom of Reactor Vessel ISI Cl#ss 1 II. IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Prousure Vossol Code, 1986 Edi d or , Category B-E, Item No. 4.13, requires reactor vessel partial panotration wolds to have a visual (VT-2) examination during the system nydrostatic tost of IWD-5222; in addition, Category D-P, Item Hos. D15.10, and B15.11 require a visual (VT-2) examination of the bottom of the reactor vessel ditring the system leakage tost of IWD-5221 and during the system hydrostatic test of IWD-5222, respectively. ,

III. BASIS FOR RELIEP In order to moot the Section XI pressure and temperature requirements for the system leakage and system hydrostatic tests of the reactor vessel, reactor containment-at North Anna Unit 2 is required to be at a subatmosphoric pressure.

Station administrativo procedures require that self contained broathing apparatus be worn for containment entries under these conditions. This requirement significantly complicates the visual (VT-2) examination of the bottom of the reactor vossol during testing. Access to the bottom of the reactor vessel requires that the examiner descend soveral levels by ladder and navigato a small entranco leading to the reactor vossel. In addition to these physical constraints, the examiner must contend with extremo environmental conditions elevated air temperatures due to reactor coolant at temperatures above 500 degrees F and limited air circulation in the vossol cubicle. In addition, the examinor is limited to the approximato 30 minuto capacity of the breathing apparatus for containment entry, the VT-2 examination, and containment exit.

O N1-004d 2-95 Rev. 2 1991

_g

O RELIEF REQUEST SPT-11 coliTIliUED

! IV. ALTER!iATE TESTIllG Technical Specifications require that the Reactor coolant System Leak Rato be limited to 1 gallon por minuto unidentified leakago. This value is calculated at least onco por 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Additionally the containment atmosphoro particulate radioactivity is monitored overy 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The incoro sump room has an level alarm in the control room requiring operator action. Those actions would identify any integrity concerns associated with this area. A VT-2 oxamination will be conducted when containment is at l atmospheric conditions cach refueling for evidence of boric

' acid corrosion, i

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o Ill-004d 2-96 Rev. 2 1991

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_ _ _ _ _w - _ - - _ - - - - - ---

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O VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 l

1 i

INSERVICE INSPECTION PROGRAM

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FOR COMPONENT SUPPORTS SECOND INSPECTION INTERVAL l

O N1-003 3-1 Rev. 2 1993

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1

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SLCTION 3 TABLE OF CONTENTS SECTION E6QE 3.0 INSERVICE INSPECTION PROGRAM FOR COMPONENT SUPPORTS 3-3 l l

3.1 PROGRAM DESCRIPTION 3-3 ,

3.1.1 Gnubber Testing 3-3 3.1.2 Supports Exempt From Examination 3-3 l 3.1.3 Supports Selected For Examination 3-3 i 3.1.4 Sampling Plan 3-4 3.2 PROGRAM

SUMMARY

3-5 3.2.1- Inservice Inspection Program Summary 3-5 3.3 INSERVICE INSPECTION PROGRAM

SUMMARY

TABLE - 3-6 ISI class 1, 2, and 3 Component Supports 3.4 COMPONENT SUPPORT RELIEF REQUESTS 3-9 O

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i O

N1' 003 3-2 Rev. 2 1991

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

4 9.0 INSERVICE INSPECTION PROGRAM FOR COMPONENT SUPPORTS 3.1 PROGRAM DESCRIPTION The Inservice Inspection Program for ISI Class 1, 2 and 3 component supports meets the requirements of Section XI of the ASME Boiler and Pressure vessel Code, 1903 Edition through Summer 1983 Addendum except where those requirements have been determined to be impractical.

Detailed relief requests for these impractical requirements are included in Section 3.4. Programmatic modifications to Section XI requirements are outlined in Sections 3.1.1 through 3.1.4.

3.1.1 This program does not cover inservice testing of snubbers. Snubbers Will be tested in accordance with Technical Specifications.

3.1.2 Component supports exempt from the examination requirements of IWT-2000 are those connected to components and items exempted from examination under IWB-1220, IWC-1220, and IWD-2000. In addition, portions of supports that are inaccessible by being encased in concreto, O buried underground, or encapsulated by guard pipe are also exempt from the examination requirements of IWF-2000. These exemptions are excerpted from proposed Code Case WGCS 89-1(b).

See Relief Request CS-1 for details.

3.1.3 Component supports to be examined shall be the supports of tnose 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 IWB-1220, IWC-1220, IWD-1220.

This selection critoria is excerpted from proposed Code Case WGCS 89-1(b). See Relief Request CS-1 for details.

O N1-003 3-3 Rev. 2 1991

O 3.1.4 The following sampling plan will be employed:

I ISI Class 1 Piping Supports - Examine 25% of supports per interval. Notes 1, 2 and 4. j ISI class 2 Piping Supports - Examine 15% of i supports per interval. Notes 1, 2 and 4. l ISI Class-3 Piping - Supports Examine 10% of supports per interval. Notes 1, 2 and 4.

Supports Other Than Piping Supports - Examine 100% of supports per interval. Notes 3 and 4.

NOTES:

(1) -Supports shall be categorized to identify ,

support types by component support function (e.g., A = supports such as one directional

rod hangeral B = supports such as multi- '

i directional restraints; and C = supports that allow thermal movement, such as springs).

l .(2) The total percentage sample shall be -

comprised of supports from each system (such as Main Steam, Feedwater or RHR),

where the individual sample nizes are >

proportional to the total number of non-exempt-supports of each type and function within each system.

(3) For multiple components other than piping-within a system ofLsimilar design, function '

and service, the supports of only-one of the multiple components are required to be examined.

(4) To the extent-practical, the same supports .

selected for examination during the first inspection interval shall be-examined during each successive inspection interval.

This sampling plan is excerpted from proposed ,

Code Case WGCS 89-1(b).

~O N1-003 3-4 Rev. 2 1991

l 4

3.2 PROGRAM

SUMMARY

3.2.1 The Inservice Inspection Program Plan Summary for Component Supports is presented in Section 3.3 in a tabular format. The compono.7t supports and associated requirements are listed in descending order according to Code Category and Item Numbers. The following information is included in the tables:

A. Code Cateaory - The Section XI Examination Category as defined in Table IWF-2500-1 for Class 1, 2 and 3 component supports.

B. Item Number - The Section XI Item Number as listed in Tablo IWF-2500-1. All Item Numbers are listed for each Code Category.

C. Part Examined - The Section XI description of the area to be examined.

D. Examination Method - Lists the examination method required by Section XI. The abbreviation used is as followst VIS - Visual examination per IWA-2223 E. Alternate Examination Method - Lists the ey. amination method that will be performed as r.n alternative to the Section XI required examination as stated in a referenced relief request.

F. Examinaticn Reauirements/Fingre Number -

Lists the applicable Section XI figure for determining the volume of the component to be examined.

G. Acceptance Criteria - Lists the applicable portion of Section XI for determining the ,

acceptance criteria.

H. Relief Reauest - References a specific relief request contained in Section 3.4.

-O v

N1-003 3-5 Rev. 2 1991

/*

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i 3.3 ISI Class 1, 2& 3 Component Supports i 3.3.1 Examination Category F-A, Plate And Shell Type Supports - Program Summary Table '

P ALT. EXAM ITEM EXAM EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOUEST !

i i

F1.10 Mechanical connections to VIS, IWF-1300-1 IWF-3410 CS-1 ;

! pressure retaining components VT-3 f and building structure l F1.20 Weld connections to building VIS, IWF-1300-1 IWF-3410 CS-1 structure VT-3 ;

i F1.30- Weld and mechanical connections VIS, IWF-1300-1 IWF-3410 CS-1 at intermediate joints in VT-3 6 multiconnected integral and nonintegral supports t l !

F1.40 Component displacement settings VIS, IWF-1300-1 IWF-3410 CS-1 i l of guides and stops, misalignment VT-3 l of supports, assembly of support i i items '

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N1IWF 3-6 Rev. 2 1991 !

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3.3.2 Examination Category F-B, Linear Type Supports ALT. EXAM EXAM REQUIRE / ACCEPTANCE RELIEF EXAM REOUEST ITEM METHOD METHOD FIG NO. CRITERIA NO. PARTS TO BE EXAMINED IWF-1300-1 IWF-3410 CS-1 VIS, F2.10 Mechanical connections to VT-3 pressure retaining components and building structure IWF-1300-1 IWF-3410 CS-1 Weld connections to building VIS, F2.20 VT-3 structure IWF-1300-1 IWF-3410 CS-1 VIS, F2.30 Weld and mechanical connections VT-3 at intermediate joints in multiconnected integral and nonintegral supports IWF-1300-1 IWF-3410 CS-1 Component displacement settings VIS, F2.40 VT-3 of guides and stops, misalignment of supports, assembly of support items Rev. 2 1991 N1IWF 3-7

3.3.3 Examination Category F-C, Component Standard Supports ALT. EXAM EXAM REQUIRE / ACCEPTANCE RELIEF EXAM REOUEST METHOD METHOD FIG NO. CRITERIA NO. PARTS TO BE EXAMIi!ED IWF-1300-1 IWF-3410 CS-1 VIS, F3.10 Mechanical connections to VT-3 pressure retaining components and building structure IWF-1300-1 IWF-3410 CS-1 VIS, f F3.20 Weld connections to VT-3 building structure IWF-1300-1 IWF-3410 CS-1 VIS, F3.39 Weld and mechancial connections VT-3 at intermediate joints in l

multiconnected integral and nonintegral supports VIS, IWF-1300-1 IWF-3410 CS-1 F3.40 Component displacement settings VT-3 of guides and stops, misalignment of supports, assembly of support items IWF-1300-1 IWF-3410 CS-1, VIS, F3.50 Spring type supports, constant VT-3 CS-2 load type supports, shock absorbers, hydraulic and nechanical type snubbers Rev. 2 1991 NIIWF 3-8 i

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COMPONE!1T SUPPORT !

i RELIEF REQUESTS !

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t N1-CSRR 3-9 Rev. 2 1991

O RELIEF REQUEST No. CS-1

1. IDENTIFICATION OF COMPONENTS ISI Class 1, 2 and 3 Component Supports II. IMPRACTICAL CODE REQUIREMERTS The nonexistent or unclear portions of Subsection IWF,Section XI 1983 Edition through Summe; 1983 Addendum detailed in the BASIS F0D F.ELIEF section of this relief request.

III. BASIS FOR RELIEF Subsection IWP of the 1983 Edition through Summer 1983 Addendum of Section XI lacks a complete concise set of rules for the inservice inspection of component supports.

The following areas in particular have been identified as needing clarification:

SUPPORTS EXEMPT FROM EXAMINATION AND TEST IWF-1230 'n the 1983 Edition through Summer 1983 Addendum of Gection XI is "in the course of preparation". The Section 11 Working Group on Component Supports (WGCS) has developed proposed Code Case WGCS 89-1(b) which includes a complete set of exemptions in Section 1230.

SUPPORTS SELECTED FOILfl6MINATIOl{

IWF-2510(a) in the 1983 Edition through Summer 1983 Tddendum of Section XI states: " Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, IWD and IWF during the first inspection interval." These selection requirements are confusing in that the exemptions for these subsections have been modified significantly since the application of ASME Section XI, 1974 Edition with Addenda through Summer 1975 for North Anna Unit 2, Interval

1. WGCS 89-1(b) includes in section 2510 a clear, detailed set of guidelines for examination.

SAMPLING PROGRAM The general philosophy of Section XI has evolved into a sampling program approach where a percentage of like components are examined to determine their suitability for continued service. WGCS 89-1(b) includes in Table 2500-1 a

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N1-CSRR 3-10 Rev. 2 1991

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O specific sampling program for supports.

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N1-CSRR 3-11 ROV. 2 1991

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O RELIEF REQUEST NO. CS-1 CONTINUED It is Virginia Electric and Power Company's position that the portions of WGCS-89-1(b) presented in the Alternato Provisions section of this relief request in conjunction .

with Subsection IWF of the 1983 Edition through Summer 1983 '

Addendum of Section XI provide a complete, coherent and sound set of rulen for the inservice inspection of component supports.

IV. ALTERNATE PROVISIONS In place of IWF-1230, which is under development, the following will be used:

Component supports exempt from the examination requirements of IWF-2000 are chose connected to components and items exempted from examination under IWB-1220, IWC-1220, and IWD-1200. In addition, portions of supports that are inaccessible by being oncased in concrete, buried underground, or encapsulated by guard pipe are also exempt from the examination requirements of IWF-2000.

SUPPORTS EXEMPT FROM EXAMINATION In lieu or IWF-2510(a), the following will be used:

Component supports to be examined shall be the supports of those 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 IWB-1220, IWC-1220, and IWD+1220.

In conjunction with Table IWF-2500-1, Categories F-A, F-B and F-C the following sampling plan will be used:

ISI Class 1 Piping Supports - Examine 25% of supports per inte rval . Notes 1, 2 and 4.

ISI Class 2 Piping Supports - Examine 15% of supports por interval. Notes 1, 2 and 4.

ISI class 3 Piping - Supports Examine lot of supports per inte rval . - Notes 1, 2 and 4. ,

Supports Other Than Piping Supports - Examine 100% of supports per interval. Notes 3 and 4.

N1-CSRR 3-12 Rev. 2 1991

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- RELIEF REQUEST NO. CS-1 CONTINUED NOTES:

(1) Supports shall be categorized to identify support types by component support function (e.g., A = supports such as one directional rod hangers; D = supports such as multi-directional restraints; and C = supports that allow thermal movement, such as springs).

(2) The total percentage sample shall be comprised of supports from each system (such as Main Steam, Foodwater or RHR),

-where the individual sample sizes are proportional to the_ total number of non-exempt supports of each type and function within each system.

(3) For multiple components other than piping within a system of similar design, function and service, the supports of only one of ;

the multiple components are required to be O examined.

(4) To the extent practical, the same supports selected for examination during the first inspection interval shall be examined during each successive inspection interval.

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N1-CSRR 3-13 Rev. 2 1991 1

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O RELIEF REQUEST NO. CS-2 I. IDENTIFICATION OF COMPONENTS ,

ISI Class 1, 2 and 3 Component Supports II. IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vossol Code, 1983 Edition with Addenda through the Summer 1983, describes visual examination is IWA-2210 of the Code.

Examination VT-3 (IWA-2213) and examination VT-4 (IWA-2214) are utilized for inspection as described in subsection IWF Table 2500-2 for Category F-C supports.

Relief is requestod from the requirement of a VT-4 examination por IWA-2214 duo to unnecessary and impractical

.irplication.

III. BASIS FOR RELIEP The VT-4 examination is only required for support examinations on Category F-C components (upring hanger, O snubber, etc.), where operability and functional adequacy need to be determined. It was recognized by the Codo that thoso examinations (VT-3, VT-4) woro cloenly related, and generally performed by the sano individua4 qualified to each discipline. Although not endorsed in 10 CFR 50.5ba, the Wintor 1984 Addendum of the Code combined the VT-3 and VT-4 examinations to a singular VT-3 examination. Applying this reduction administrativo1y would reduco quallrication documents, examination records, review requiremontu, and reporting without eliminating the intent of the examination.

IV. ALTERNATE PROVISIONS It is proposed that the definition of a VT-3 examination as written in the Wintor 1984 Addendum be subntituted for the current VT-3 and VT-4 requirements a) The VT-3 visual examination shall be conducted to determino tho ' general mechanical and structural coridition of components and their supports, such as the verification of clearances, settings, physical displacements, loose or missing parts, debris, corrosion, wear, crosion or the loss of integrity at bolted or welded connections.

N1-CSRR ;-14 Rev. 2 1991

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O RELIEF REQUEST 110. CS-2 CollTIliUED l

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The VT-3 examination shall include examinations for conditions that could affect operability or functional adequacy of snubbers, and constant load and spring type supports.

c) For component supports and component interiors, the visual examination may be performed remotely with or without optical aids to verify the structural integrity of the components.

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fil-CSRR 3-15 Rev. 2 1991

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