ML20206N858
| ML20206N858 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/30/1998 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20206N856 | List: |
| References | |
| PROC-980430, NUDOCS 9812230307 | |
| Download: ML20206N858 (400) | |
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VIRGINIA ELECTRIC AND POWER COMPANY 4
. NORTH ANNA POWER STATION UNIT 2 f INSERVICE INSPECTION PROGRAM FOR l THE SECOND INSPECTION INTERVAL VOLUME 1 1 INSERVICE INSPECTION PROGRAM FOR COMPONENTS AND COMPONENT SUPPORTS
- - ' REVISION 5 April 1998 4
INTERVAL 2 DECEMBER 14,1990 - April 30,2001 4
N2-000 Rev.5 4 i K 339
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, , Summary of Changes To North Anna Unit 2 ISI Program - !
Since Last Subndttal, (Period 2 to present)
- 1. Added the following relief requests:
SPT-15, and SPT-16, Rev. 2 IWE-1 NDE-22 through NDE42 i
- J 2. Withdrew the following relief requests
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SPT-15 i NDE-17 I
- 3. ' Revised the following relief requests:
SPT-14 and SPT-16 NDE-18, NDE-31and NDE 32 :
-4. Added the following Code Cases:
i N-401-1, N-402-1, N-416-1, N-435-1, N-437, N-460, N-461, N-489, N-498-1, 'N-491-1, N-509, N-524, N-535
- 5. Added Section 4 to the Program.
- 6. Added an index for relief requests, pages 49, 50, and 51 in Section 2, and Page 9 in Section 3.
- 7. Extended the interval from 12-14-00 to 4-30-01, per Code Case N-535.
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? VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM SECOND INSPECTION INTERVAL
' DECEMBER 14, 1990 $ April 30, 2001 REVISION 4 DISTRIBUTION RECORD DISTRIBUTION DATE DISTRIBUTION DATE Mn- ENTERED TNTTTAT. NO. RNTERRn TNTTTAT.
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2 22 3 23 4 24 5 25 6 26 l
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l 9 29 10 _ 30 l 11 31 12 32 13 33 14 34 l 15 35 16 36 17 37 18 38 19 39 20 40 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 l thereon,.and the other one'is to be filed seqtantially behind this page I giving you a record of the contents of each distribution.
N2-000 Rev. 5 ill
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e TABLE OF CONTENTS ,
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- SECTION ' TITLE PAGE i Assignment - !
ii . Distribution Record iii . Table of Contents iv . Abstract ,
. 1. Inservice Inspection Program
' General
-2 Inservice Inspection Program for Components 3 Inservice Inspection Program for Component Supports 4- Miscellaneous Interim Relief Requests and Documentation ,
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ABSTRACT vlRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM SECOND INSPECTION INTERVAL DECEMBER 14,1990 TO April 30,2001 !
In accordance with 10CFR50.55a dated January 1,1990, the North Anna Unit 2 (NAPS-2)
Inservice Inspection (ISI) Program was updated to meet the requirements of ASME Section XI, 1986 Edition. This updated program is for the NAPS-2 second ten year inspection interval scheduled to commence December 14,1990 and be completed December 14,2000. In cases where the requirements of Section XI have been determined to be impractical, requests for relief have been developed per 10CFR50.55a(g)(5)(iii).
1 The Inservice Inspection Program is divided into two documents, the Inservice Inspection Program, and the Inservice Inspection Program Plan for Pumps and Valves. The Inservice Inspection Program does not include requirements per Subsections IWE, Requirements For Class MC Components Of Light Water Cooled Power Plants and IWL, Requirements For Class CC Concrete Components of Light-Water Cooled Power Plants. Federal Regulations were changed 4
on September 9,1996 to include these sections in ISI programs. There is a five year grace period to implement these requirements. The programs for these sections of the Code are being developed.
This document provides an overview and summary of the NAPS-2 ISI Program for Subsections
' IWA, IWB, IWC, IWD, and IWF. The boundaries of the ISI Program, component classifications, and the employment of exemptions in IWB-1220, lWC-1220, IWD-1220, and IWF-1230 are shown on the ISI Classification Boundary Drawings (CBDs) listed on pages 1-11 to 1-12. The codings, symbols and text used on the CBDs are detailed on 12050-CBM-L&S-2, Legends and Symbols Drawing Section 1 of this document provides the generalinformation and format regarding this program.
Section 2 of this document provides a program implementation overview of the ISI Program for ISI Class 1,2, and 3 components. A summary table of Section XI requirements applicable to NAPS-2 is provided as well as relief requests for components. Section 3 of this document provides a program implementation overview for ISI Class 1,2, and 3 component supports. A summary table of Section XI requirements applicable to NAPS-2 component supports is provided as well as relief requests for component supports.
N2-000 Rev. 5 iv
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM .
GENERAL SECOND INSPECTION INTERVAL >
N2-001 Rev. 5 Page 1 of 13
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a SECTION 1 TABLE OF CONTENTS
- SECTION PAGE 1.0 INSERVICE INSPECTION PROGRAM - GENERAL 3 l 1.1 ' GENERAL INFORMATION t 3
l 1.1.1 Preservice Examinations 3' l .1.2 Initial Inseivice Inspection Interval 3 1.1.3 Second Inservice Inspection Interval 3 2
1.1.4 Inservice Inspection Program 3 Description 1.2 ' DRAWING LIST - ISI CLASSIFICATION BOUNDARY 11
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1.0 INSERVICE INSPECTION PROGRAM - GENERAL 1.1 GENERAL INFORMATION North Anna Power Station Unit 2 (NAPS-2)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-2 were performed utilizing the requirements of ASME Section XI,1974 Edition with Addenda through Summer 1975.
1.1.2 Initial Inservice Inspection Interval NAPS-2 commercial operation commenced on December 14,1980.
Accordingly, the initial ten year inspection interval was conducted from 12/14/80 to 12/14/90. 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, Article 50.55a (10CFR50.55a), the NAPS-2 Inservice Inspection (ISI)
Program has been updated to the 1986 Edition of ASME Section XI.
l This is the latest edition and addenda of Section XI incorporated into !
10CFR50.55a as of December 14,1989. The second inservice inspection interval commenced on December 14,1990 and will end on December 14,2000, and will be extended, as allowed by Code Case N-535, to April 30,2001 to coincide with a plant outage.
1.1.4 Inservice Inspection Program Description The ISI Program contained herein addresses the inservice inspection and testing ofISI Class 1,2, and 3 components and the associated component supports. Applicable requirements in Subsections IWA, IWB, IWC, IWD, IWF and the Mandatory Appendices of the 1986 l N2-001 Rev.5 Page 3 of 13 1
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' Edition of ASME Section.XI 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-2 ISI program (i.e., its boundary and 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 10CFR50.55a(g)(5)(iii).
l.I.4.1 Exclusion of Subsections IWE and IWL Subsection IWE, . Requirements For Class l MC Components of Light-Water Cooled Power Plants, and IWL, Requirements For Class CC Concrete Components of Light-Water Cooled Power Plants, have not been included in this program. The Final Rule for 10 ;
CFR Part 50, Codes and Standards for Nuclear Power '
Plants, Subsection IWE and Subsection IWL, Federal Register, Volume 61, Number 154, August 8,1996 allows licensees five years to implement these requirements. The ,
programs to satisfy these requirements are being developed.
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l 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 Inservice Testing Program / Plan was submitted separately.
1.1.4.3 Inservice Inspection Plans The inservice inspection plan required by IWA-2420, detailing the components and component supports selected for examination and during the interval will be provided as a separate document.
N2-001 Rev.5 Page 4 of 13
I The inservice inspection plan required by IWA-2420, detailing l
' the components selected for system pressure testing during the interval will be provided as a separate document.
The plant Technical Specification will govern the extent and frequency of examination of steam generator tubing. The steam l generator tube eddy current exa nviation program and plan will be provided as a separate documunt. The steam generator tube ;
examination program is detailed in the Inservice Inspection '
Manual, Section 6.7. The steam generator tube eddy current ;
examination plan will identify the tubes and extent of examination ofeach tube. The steam generator tube eddy current examination plan may contain more tubes than that required by Technical Specification.
1.1.4.4 Inspection Program Employed The ISI Program for North Anna Unit 2 will utilize the interval format ofInspection Program B, as shown in IWA-2432.
1.1.4.5 Weld Reference System The weld reference system is required by ASME Section l XI, IWA-2600. The implementation plan for this requirement is detailed in relief requests NDE-13 and NDE-14.
1.1.4.6 Classification ofComponents A. Classification ofComponents-Design North Anna Unit 2 was issued construction permit >
No. CPPR-78 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 I functions to be performed.
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. The group classifications tabulated in the " Standard Format and Content of Safety Analysis Reports for Nuclear Power Reactors", issued in February 1971, i ,
and in~ Safety Guide No. 26, published in March 1972, incorporated, in most cases, later editions of :
p codes than those in effect when the majority of-
! safety-related equipment was designed. Some of the 4
' equipment that would fall under a " group" as defined in Safety Guide No. 26 was designed to i different codes or different editions of the same code. Tor example, for different components that i would be in the same group, one may be designed to ;
j~ ASME 111-1968, one to ASME III-1971, and one to i
- ASME VIII-1968.
Therefore, pressure-containing components of safety-related systems do not necessarily fall under j the group classification listed above.
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j B. Classification of Components-Inservice Inspection
- . The classification of components for Inservice
[ Inspection was performed by employing the i
guidelines of 10 CFR 50.55a, USNRC Regulatory Guide 1.26 Revision 3, ANSI N18.2-1973, ANSI N18.2a-1975, and NUREG-00800, Standard '
Review Plan 3.2.2-Revision 1, in conjunction with !
the System Quality Group Classification Section of l
! 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.
l p The ISI Classification of each component included in L
NAPS-2 program is shown on the ISI Classification Boundary Drawings (CBDs) listed. The Legends
- . and Symbols ISI Classification Boundary Drawing
- (12050-CBM-L&S-2) details the line codings and r component markings which provide the ISI Classification of all items included within the ISI f Program boundaries. In general, the ISI
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classification of piping is accomplished by line I
, " codings" or symbols shown on .
12050-CBM-L&S-2. ISI Classification of e components which graphically cannot be coded, such as pressure vessels, pumps, strainers, and .
tanks, etc. is shown as text (e.g., ISI Class I A,3E, etc.) either inside the component 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 j Examination
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! IWC-1220. IWD-1220, and IWF-1230 is also detailed by the codings and component markings of 12050-CBM-L&S-2 discussed in section 1.1.4.6.B.
l Because the exemptions ofIWF-1230 are "in the course of preparation", a set of exemptions for component supports developed in proposed Code Case WGCS 89-1(b)is being emp?oyed. Reliefrequest CS-1 details the reasoning ,
for this program modification.
1.1.4.8 Requests For Relief-Components and Component !
Supports l 1
Where the requirements of ASME Section XI have been l
determined to be impractical, requests for relief have been i
developed in accordance with 10 CFR 50,55a(g)(5)(iii). l The impractical requirements are detailed in four sets of reliefrequests: an NDE series for components and 1 nondestructive examination areas, an SPT series for system pressure testing areas, a CS series for component support areas, and a IWE series for. containment liner and containment concrete areas. Relief requests will be prepared in accordance with Section 7.7 of the Inservice Inspection Manual.
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Reliefrequests ahich pertain to a specific ASME Section 'l XI Categor';and Item Number are referenced in the Inservice Inspection Program Summary Tables in Sections 2 *.ad 3 of this document. Relief requests which are programmatic in content will be discussed in the text of .
Sections 1, 2, or 3, but not listed in the Inservice Inspection Program Summary Tables.
1.1.4.9 ASME Section XI Code Cases Incorporated Into Program As allowed by 10 CFR 50.55a(c)(3) and USNRC l Regulatory Guide 1.147, Revision 11, the following Code Cases are being l incorporated into the NAPS-2 ISI Program:
Case N-401 Eddy Current l_
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. (This l Code Case has been annulled but is still being used as allowed by Reg. Guide 1.147 Section D item 3.)
Case N-416 Alternative Pressure l Test Requirement for Welded Repairs or Installation of Replacement items by Welding, Class 1,2, and 3 Section XI, Division 1. (Approved with conditions by NRC Letter 95-41, Dated 1/18/95, see Section 4.0, item 4.1.3)
Case N-435 Alternative Examination l N2-001 Rev 5 Page 8 of 13
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Requirements for Vessels With
- Wall Thickness 2 in. or Less i
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Section XI, Division 1 Case N-437 - Use of Digital Readout and Digital - l .' j Measurement Devices for l
- Performing Pressure Tests, '
Section XI, Division 1 Case N-446 . _ Recertification of Visual l Examination Personnel,Section XI, Division 1.
g Case N-457 - - Qualification Specimen Notch l I Location for Ultrasonic A
Examination ofBolts and Studs
[ Section XI, Division 1. '
L Case N-460 - AlternativeExamination . l i
Coverage for Class l'and Class 2 Welds,Section XI, Division 1 Case N-461 - Alternative Rules for Piping l
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Calibration Block Thickness
- Section XI, Division 1 ;
Case N-489 - Alternative Rules for LevelIII l .
e NDE Qualification Examinations, l Section XI, Divisions 1,2, and 3.
Case N-498-1 Alternative Rules for 10-Year i System Hydrostatic Testing for ,
Class 1,2, and 3 Systems, Section j XI, Division 1.. (Approved by '
NRC Letter 98-007-Dated 12 97).
Case N-509 - Alternative Rules for l the Selection and Examination of Class 1,2, and 3 Integrally -
Welded Attachments,Section XI, Division 1. (Approved with N2-001 Rev. 5 Page 9 of 13
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conditions by NRC Letter 95-429, -
Dated 8/8/95, see Section 2.7.1)
Case N-524 - Alternative Examination i l Requirements for Longitudinal' Welds Class 1 and 2 Piping Section XI, Division 1. (Approved !
by NRC Letter 94-602, Dated 10/03/94, see Section 4.0, item 4.1.1)
Case N-535 Alternative Requirements for -
Inservice Inspection Inteivals,Section XI, Division 1.
(Approved by NRC Letter 98-340 '
dated 5-29-98.
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- 1.1.4.10 Augmented Inservice Inspection Program for ISI Class 1, 2, and 3 Components Augmented Inservice Inspection activities which pertain to components within the scope of the ASME Section }3 program are summarized in Section 2, Table 2.6. A listing i of specific components scheduled to be examined per the ,
augmented program 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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. 1.2 ,' DRAWING LIST
- NORTH ANNA UNIT 2 ,
SECOND INSPECTION INTERVAL l
' ISI CLASSIFICATION BOUNDARY DRAWINGS l t
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NORTH ANNA UNIT 2 INTERVAL 2 ISI CLASSIFICATION BOUNDARY DRAWINGS SORTED BY SERIES LEGENDS AND SYMBOLS bRAWING DRAWING NUMBER SHEET TITLE.
12050-CBM-LsS-2 1 OF 1 LEGEND AND SYMBOLS 11715-CBB SERIES DRAWING HUMBER SHEET TITLE 11715-CBB-04 0D-2 2 OF 3 SYSTEM AIR CONDITIONING CONDENSER WATER 11715-C8M SERIES DPAWING NUMBER SHEET TITLE
- 1. 11715-CBM-0788-2 3 OF d
- 2. 11715-CBM-018B-2 SERVICE WATER SYSTEM 3, 4 OF 4 SERVICE WATER SYSTEM 11715-CBM-088A-2 3 OF 4 4 11715-CBM-105B-2 I1JEL PIT CLNG e REFUELING PUL SY! TEM 2 OF 2 SECONDARY PLANT GAS SUPPLY SYSTEM 12050-CBB SERIES DRAWING NUMBER SHEET TITLE
- 1. 12050-CBB-006A-2 2 OF 3
- 2. 12050-CBB-104A-2 AIR COOLING AND PURGING SYSTEM 1 OF 1 INTERIOR FIRE PROTECTION & HO5E RACK SYS 12050-CBM SERIES DRAWING NUMBER SHEET TITLE
- 1. 12050-CBM-070A-2 3 OF 3
- 2. MAIN STEAM SYSTEM 12050-CBM-070B-2 1 OF 3
- 3. MAIN STEAM SYSTEM 12050-CBM-070B-2 2 OF 3 MAIN STEAM SYSTEM
- 4. 120to-CBM-070B-2 3 OF 3 5, MAIN STEAM SYSTEM 12050-CBM-072A-2 2 OF 3 6, 12050-CBM-074A-2 AUXILIARY STEAM s AIR RDOYAL SYSTH4 1 OF 3 FEEDWATER SYSTEM
- 1. 12050-CBM-074A-2 3 OF 3 tqEDWATER SYSTEM
- 8. 12050-CBM-079A-2 1 OF 5
- 9. COMPONENT COOLING WATER SYSTEM 12050-CBM-079A-2 2 OF S
- 10. COMPONENT COOLING WATER SYSTEM 12057-CBM-079A-2 3 OF 5 11, COMPONENT COOLING WATER SYSTEM 120%-CBM-079A-2 4OF5
- 12. COMPONENT COOLING WATER SYSTEM 11050-CBM-079A-2 5 OF 5 13, COMPONENT COGLING WATER SYSTEM 12050-CBM-079B-2 3 OF 3
- 14. COMPONENT COOLING WATER SYSTEM 12050-CBM-082A-2 1 OF 3 COMPRESSED AIR SYSTEM
- 15. 12050-CBM-082B-2 1 OF 3 16, COMPPESSED AIR SYSTEM 12050-CBM-082B-2 2 OF 3 COMPRESSED AIR SY3 TEM
- 17. 12050-CBM-082C-2 2 OF 2 COMPRESSED AIR SYSTEM
- 18. 12050-CBM-002 F-2 2 OF 2 COMPRESSED AIR SYSTEM
- 19. 12050-CBM-089A-2 3 OF 4 SAMPLING SYSTEM
- 20. 12050-CBM-089B-2 'I OF 1 21, SAMPLING SYSTEM 12050-CBM-090A-2 1 OF 3 VENT & DRAIN SYSTEM 22, 12050-CBM-090A-2 3 OF 3 VENT & DRAIN SYSTEM 23, 12050-CBM-0909-2 1 OF 1 VENT 4 DRAIN SYSTEM
- 24. 12050-CBM-091A-2 1 OF 4 CONT QUENCH & RECIR SPPAY SUB SYS1EM
- 25. 12050-CBM-091A-2 2 OF 4
- 26. CONT QUENCH & RECIR SPRAY SUB SYSTEM 12050-CBM-091A-2 3 OF 4 CONT QUENCH s RECIR SPRAY SUB SYSTEM 27 12050-CBM-091A-2 4OF4 CONT QUENCH & RECIR SPRAY SUB SYSTEM N2-001 Rev. 5 Page 12 of 13
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I NORTH ANNA UNIT 2 INTERVAL 2 ISI CLASSIFICATION BOUNDARY DRAWINGS SORTED BY SERIES CONTINUED l DRAWING NUMBER SHEET TITLE
- 20. 12050-CBM-091B-2 1 OF 1 I
- 29. 12050-CBM-092A-2 CONT QUENCH 4 RECIR SPRAY SUB SYSTEM 1 OF 2 LEARAGE MONITOR SYSTEM
- 30. 12050-CBM-092A-2 2OF2
- 31. CONTAINMENT VACUUM SYSTEM 12050-CBM-093A-2 1 OF 3 32, REACTOR COOLANT SYSTEM-LOOP 1 12050-CBM-093A-2 2 OF 3
- 33. REACTOR COOLANT SYSTEM-LOOP 2 12050-CBM-093A-2 3 OF 3
- 34. REACTOR COOLANT SYSTEM-LOOP 3 12050-CBM-0938-2 1 OF 3
- 35. REACTOR COOLANT SYSTt.M 12050-CBM-093B-2 2 OF 3
- 36. REACTOR COOLANT SYSTEM 12050-CBM-094A-2 1 OF 2 31, RESIDUAL HEAT REMOVAL SYSTEM 120SO-CBM-094A-2 2 OF 2 38, 12050-CBM-095A-2 RESIDUAL HEAT RDOVAL SYSTEM 1 OF 2 CHEMICAL AND VOLN E CONTROL SYSTEM
- 39. 12050-CBM-095A-2 2OF2
- 40. 12050-CBM-0958-2 CHEMICAL AND VOLUME CONTROL SYSTEM 1 OF 2 CHEMICAL AND VOLUME CONTROL SYSTEM
- 41. 12050-CBM-095B-2 2 OF 2 i
- 42. CHEMICAL AND VOLUME CONTROL SYSTEM 12050-CBM-095C-2 1 OF 2
- 43. CHEMICAL AND VOLUME CONTROL SYSTEM 12050-CBM-095C-2 2 OF 2
- 44. CHEMICAL AND VOLUME CONTROL SYSTD1 12050-CBM-096A-2 1 OF 3
- 45. SAFETY INJECTION SYSTEN 12050-CBM-096A-2 2 OF 3
- 46. SAFETY INJECTION SYSTEM 12050-CBM-096A-2 3 OF 3
- 41. SAFETY INJECTION SYSTEM 12050-CBM-096B-2 1 OF 4 SAFETY INJECTION SYSTEM
- 48. 12050-CBM-0968-2 2 OF 4
- 49. SAFETY INJECTION SYSTEM 12050-CBM-0969-2 3 OF 4
- 50. SAFETY INJECTION SYSTEM 120t0-CBM-096B-2 4 OF 4 SAFETY INJECTION SYSTEM
- 51. 12050-C8M-098A-2 2 OF 5 52, STEAM GENERATOR BLOWDOWN SYSTEM 12 050-CBM-098 A-2 3 OF 5
' 5 3. STEAM GENERATOR BLONDOWN SYSTEM 12050-CBM-098A-2 4 OF $
- 54. STEAM GENERATOR BLOtrcWN SYSTEM 12050-CBM-102A-2 2OF2 CHEMICAL FEED SYSTE'E
- 55. 12050-CBM-1028-2 1 OF 1 CHEMICAL FEED SYSTIM 13075-CBM SERIES DRAWING NUMBER SHEET TITLE
- 1. 13075-CBM-093D-2 1 OF 2 RsACTOR COOLANT SYSTEM I
- 2. 13015-CBM-093D-2 2OF2 REACTOR COOLANT SYSTEM i
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VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION -
UNIT 2 INSERVICE INSPECTION PROGRAM FOR COMPONENTS SECOND INSPECTION INTERVAL I
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SECTION 2' l
TABLE OF CONTENTS l
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SECTION - TITLE PAGE' i' 2.0 -
INSERVICE INSPECTION PROGRAM FOR COMPONENTS 3 I
2.1 PROGRAM DESCRIPTION 3 2.1.1 Section XI Requirements 3 2.1.2 Weld Selection for Class 1 Piping 3 2.1.3 . Weld Selection for Class 2 Piping 3 2.2 PROGRAM
SUMMARY
L 4 2.2.1 Inservice Inspection Program Summary Description 4 23' ISI CLASS 1 COMPONENTS - PROGRAM
SUMMARY
TABLE 6 2.4 .
ISI CLASS 2 COMPONENTS '- PROGRAM
SUMMARY
TABLE 32 l 2.5 ISI CLASS 3 COMPONENTS - PROGRAM
SUMMARY
TABLE 44 i
. 2.6 AUGMENTED INSPECTION REQUIREMENTS ON 47 c ISI CLASS 1,2, OR 3 SYSTEMS -
PROGRAM
SUMMARY
TABLE 2.7 COMPONENT RELIEF REQUESTS 49 n
2.7.1 NDE Series Relief Requests 49 2.7.2 SPT Series ReliefRequests 50 N2-002 Rev. 5 Page 2 of 50
2.0 INSERVICE INSPECTION PROGRAM FOR COMPONENTS 2.1 PROGRAM DESCRIPTION 2.1.1 The Inservice Inspection Program for Class 1,2 and 3 components meets the requirements of Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition 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.
2.1.2 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 welds selected include all terminal ends and branch connections. In addition, valves which have reactor coolant on one side and a lower pressure on the opposite side will have the high pressure pipe-to-pipe valve weld included in the interval selection. The remaining balance 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 Stainless Steel piping welds will be selected in accord.mee with Table IWC-2500-1, Category C-F-1, except that RHR, CHR and ECS welds wH1 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 the category will be selected Selections within each system will be prorated among terminal ends, structural discontinuities and line sizes. ISI Class 2 Carbon Steel piping welds will be i selected in accordance with Table IWC-2500-1, Category C-F-2. I l
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2.2 PROGRAM
SUMMARY
2.2.1 The Inservice Inspection Program Summary for the Components is presented in Sections 2.3,2.4 and 2.5 in a tabular format. The applicable NAPS-2 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 2 and are included for reference only. The following information is included in the tables:
A. Code Category - The Section XI Examination Category as defined in Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1 for Class 1,2 and 3 components, respectively.
B. Item Number - The Section XI Item Number as listed in Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1. All item Numbers are listed for each Code Category 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 I VIS - Visual per IWA-2211,12 and 13 E. Alternate Examination Method - Lists the examination method that will be performed as an alternative to the Section XI required examination as stated in a relief request. 1 l
F. Examination Reauirements or Test ' Required / Figure Number - Lists the applicable Section XI figure for determining the volume of the component to be examined.
N2-002 Rev. 5 Page 4 of 50 1
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G. Acceptance Criteria - Lists the applicable portion of Section XI for determining the acceptance criteria.
H. Relief Request Number - References a specific relief request contained in Section 2.7.' Reliefrequests are presented in two series: an NDE-Series for components and nondestructive examination areas and a SPT-Series fo~r system pressure testing areas.
N2-002 -
Rev. 5
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L2.3 ISI Class 1 Components - Program Summary Table >
2.3.1 Examination Category B-A, Pressure Retaining Welds in Reactor Vessel ALT EXAM.
ITEM , EXAM. EXAM REQUIRED / . ' ACCEPTANCE RELIEF !
NO. PARTS TO BE EXAMINJD METHOD METHOD FIG NO. CRITERIA: REOUEST) 1 Bl.11 Recctor Vessel Circumferential Shell VOL - IWB-2500-1 IWB-3510 .
Welds 1
Bl.12 Reactor Vessel Longitudinal Shell VOL IWB-2500 IWB-3510
- Welds l Bl.21 Reactor Vessel Circumferential VOL IWB-2500-3 IWB-3510 i
Head Weld Bl.22 Reactor Vessel Meridional Head Weld VOL IWB-2500-3 IWB-3510 Bl.30 Reactor Vessel Shell-to-Flange VOL IWB-2500-4 IWB-3510 NDE-15 "
Weld B 1.40 Reactor Vessel Head-to-Flange Weld VOL & IWB-2500-5 IWB-3510 SUR B 1.5 i Reactor Vessel Beltline Region Repair VOL IWB-2500-1, . IWB-3510 Welds and -2 N2432 Rev. 5 Page 6 of 50
- . - - - . . _ . . .- _ - , - .- . , , _ _ . - . . . -- - -- _ _ -..aa
a :: I 2.3.2 Examination Category B-B, Pressure Retaining Welds in Vessels Other Than Reactor Vessels
' ALT. . EXAM 4- ITEM EXAM. EXAM REQUIRED /J ACCEPTANCE; RELIEF -
NO. PARTS TO BE EXAMINED METHOD - METHOD FIG NO.- CRITERIA REOUEST ,
B2.11 Pressurizer Circumferential VOL IWB-2500-1 IWB-3511 Shell-to-Head Welds B2.12 Pressurizer Longitudinal VOL- IWB-2500-2 IWB-3511.
. Shell-to-Head Welds t B2.21 Pressurizer Circumferential Head N/A~ 'N/A N/A Welds : j
- B2.22 Pressurizer Meridional Head Welds N/A N/A N/A B2.31 Steam Generator Circumferential N/A N/A N/A !
Head Welds f
-i i
B2.32 Steam Generator Meridional Head N/A N/A N/A ;
Welds !
B2.40 ' Steam Generator Tubesheet-to-Head VOL IWB-2500-6 IWB-3511.'
Weld .j s t NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included l in North Anna Unit 2. ;
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o
_ _ - , , . _ _ . _ . . - . . ,. ._ _._ .. . _ . . . _ . . . . - ... . . . . . . _ . . ~ . . - _ . . . . . . . _ . . . _ . . . . ,
~
2.3.2 Examination C$tegory B-B, Pressure Retaining Welds in Vessels Other Than Reactor Vessels
~
' (continued):
. ALT. EXAM
" ITEM .
EXAM. EXAM REQUIRED / . ACCEPTANCE - RELIEF -
NO. - - PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOUESTJ B2.51 Heat Exchanger Circumferential N/A N/A- N/A Head Welds - .
B2.52 Heat Exchanger Meridional N/A- N/A- -N/A 4 Head Welds B2.60 Heat Exchanger N/A N/A N/A Tubesheet-to-Head Welds .i a
i B2.70 . Heat Exchanger Longitudinal -
N/A N/A N/A j Welds
- B2.80 Heat Exchanger N/A .N/A N/AJ Tubesheet-to-Shell Welds NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included '!
in North Anna Unit 2. i f
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N2-CD2 Rev. 5 Page 8 of 50
_- .. _ _ . . - . . . _ ~ _ _ . . . . . . .-
- 2.3.3 : Examination Category B-D, Full Penetration Wclds of Nozzles in Vessels Inspection Program B ALT. EXAM ITEM ' ..
EXAM.. EXAM- REQUIRED / c ACCEPTANCE RELIEF -!
NO.~ PARTS TO BE EXAMINED METHOD METHOD FIG NO CRITERIA REOUEST L!
B3.90 Reactor Vessel Nozzle-to-Vessel VOL ' IWB-2500-7 IWB-3512 : NDE-15 '1 Welds . !
i I
B3100 Reactor Vessel Nozzle Inside VOL IWB-2500-7 IWB-3512 NDE-15 Radius Section l B3.110 Pressurizer Nozzle-to-Vessel VOL IWB-2500-7 IWB-3512
-?
Welds ;
B3.120 - Pressurizer Nozzle Inside VOL VIS,- IWB-2500-7 IWB-3512 NDE-2 ;
Radius Section VT-2 B3.130 Steam Generator Nozzle-to-Vessel N/A N/A N/A Welds t
B3.140 Steam Generator Nozzle Inside VOL VlS, IWB-2500-7 IWB-3512 hD E-2 Radius Section ' VT-1 B3.150 Heat Exchanger Nozzle-to-Vessel . N/A- N/A-- N/A '4 Welds i 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 2.
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N2-C02 Re% S !
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- 2.3.4 Examination Category B-E, Pressure Retaining Partial Penetration Welds In Vessels ,
JALT. -EXAM- 1 ITEM - EXAM. EXAM- REQUIRED / ACCEPTANCE RELIEF 4
' NO. PARTS TO'BE EXAMINED METHOD METHOD FIG NO. CRITERIA ~ REOUEST B4.11 Partial Penetration Vessel Nozzles VIS, EXTERNAL- . IWB-3522 ,
VT-2 SURFACE -
B4.12 Partial Penetration Control Rod VIS, EXTERNAL IWB-3522 t Drive Nozzles VT-2 SURFACE B4.13 Partial Penetration Instrumentation VIS, EXTERNAL IWB-3522 . SPT-11 Nozzles VT-2 SURFACE B4.20 Pressurizer Heater Penetration VIS, EXTERNAL IWB-3522 Welds VT-2 SURFACE i
k i
N2-002 Rev. 5 Page 10 of 50
w', ' . .
_ = . _
- 2.3.5 Examination Category B-F, Pressure Retaining Dissimilar Metal Welds m
- ALT. EXAM
- ITEM EXAM. ~ EXAM -. REQUIRED / . ACCEPTANCE - RELIEF '
' NO.
' PARTS TO' BE EXAMINED
~ METHOD METHOD FIG NO. CRITERIA REOUEST.
B5.10 Reactor Vessel Nominal Pipe Size r VOL & - VOL IWB-2500 IWB-3514 NDE-15 L 2 4 in. Nozzle-to-Safe - SUR.
' End Butt Welds B5.20 ' Reactor Vessel Nominal Pipe Size N/A N/A .N/A
' 54 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' 2 4 in. Nozzle-to-Safe SUR End Butt Welds .
B5.50 Pressurizer Nominal Pipe Size N/A N/A N/A 5 4 in. Nozzle-to-Safe End Butt Welds B5.60 Pressurizer Nozzle-to-Safe - N/A N/A N/A l End Socket Welds i NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 2.
N2-C02 Rev.S Page1Iof50
_cm.m._ _.._____.______.._.___.._.___m,____._.__m.-___ _ _.m. __ _ . __ ___.____ - _ - _ _ _ s___-_m-w. < _ r .- . . - w ..,,,--.-..,,-a,,-u, ,w.w, v. - a,e..vv -= . - . , .c
7
. 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 REOUEST--
B5.70 Steam Generator Nominal Pipe VOL & IWB-2500-8 . 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 5 4 in. Nozzle-to-Safe -
Enid Butt Welds B5.90. Steam Generator Nozzle-to-Safe N/A N/A- N/A End Socket Welds B5.100 Heat Exchanger Nominal Pipe 'N/A N/A N/A Size > 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 NOTE: "N/A" in the EXAM METHOD column indicates that no applicable components are included in North Anna Unit 2.
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( F24D2 Rev.5 Page 12 of 50 i
. 2.3.5 Examination Category B-F, Pressure Retaining Dissimilar Metal Wolds (continued)
ALT. EXAM.
ITEM 1 EXAM. EXAM. REQUIRED / . ACCEPTANCE . RELIEF >
= NO. PARTS TO BE EXAMINED - METHOD METHOD FIG NO. CRITERIA REOUEST .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 Mctal Butt Welds B5.150 Piping Dissimilar Metal N/A N/A. N/A Socket Welds
.t NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included - i in North Anna Unit 2. ,
i n2-oc2 Rev. s Page 13 of 50 1
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. . _ _ m ___ _ _ ._ . -. .___., m __.-. _ . _ _ . _ _ . ._.m_.- _ . _ _ . . _ _ _ _ _ _ . _ _ _ _ _ . _ . _ . _ _ _ _ _ _._m_..._-____m. m. _ _ ___ _. . __.~._.m. -
_ . ~ ~ . _ . -
._.-m._.
2.3.6 Examination Category B-G-1, Pressure Retaining Bolting, Greater Than 2 in. In Diameter. -
ALT. EXAM L ITEM- EXAM. EXAM- REQUIRED / ACCEPTANCE RELIEF -
NO PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOUEST B6.10 Reactor Vessel 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 B6.40 Reactor Vessel Threads in Flange VOL IWB-2500-12 IWB-3515 NDE-3, -
NDE-15 B6.50 Reactor Vessel Closure Washers, VIS, -Surfaces IWB-3517 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 N/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. METIIOD column indicates that no applicable components are included in North Anna Unit 2.
N2 002 Rev. 5 Page 14 of 50
~ 2.3.6 Examination Catcgory B-G-1, Pressure Retaining Bolting, Greater Than 2 in. In Diameter -
(continued)
ALT. EXAM-
' ITEM -
EXAhL EXAM- REQUIRED /. ACCEPTANCE' RELIEF
- NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO.' CRITERIA REOUEST-
' B6.100 Steam Generator Flange Surface, N/A - N/A .' N/A when connection disassembled m
-: B6.110 Steam Generator Nuts, Bushings, N/A -
N/A N/A -
and Washers B6.120 Heat Exchanger Bolts and Studs N/A- N/A' N/A B6.130 Heat Exchanger Flange Surface, N/A N/A- N/A
' B6.140 -
Heat Exchanger Nuts, Bushings, N/A. N/A' N/A B6.150 Piping Bolts and Studs 'N/A N/A N/A--
B6.160 Piping Flange Surface, N/A N/A N/A' I
when connection disassembled B6.170 Piping Nuts, Bushings, and Washers N/A N/A N/A i
NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 2.
1 N2-002 Rev. 5 Page 15 of 50
_ _ _ _ _ _ . . _ __ _ _ . . _ . . _ _ . _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . = _ _ . _ _ . _ _ _ _ . __ _ _ _ _ . _ _ _ _ _ _ _ ____ _ -.___ _
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 RELIEF .
NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA' REOUEST B6.180 Pumps Bolts and Studs VOL IWB-2500-12 IWB-3515 B6.190 Pumps Flange Surface, VIS, Surfaces IWB-3517 when connection disassembled VT B6.200 Pumps Nuts, Bushings, and Washers VIS, Surfaces IWB-3517 -
.VT ,
B6.210 Valves Bolts and Studs VOL IWB-2500 IWB-3515 B6.220 Valves Flange Surface, VIS, Surfaces IWB-3517 when connection disassembled VT-1 B6.230 Valves Nuts, Bushings, and Washers VIS, Surfaces IWB-3517 VT-1 NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 2.
N2-002 Rev. 5 Page 16 of 50
- o, , - -- , - ~ ~ - , ~ .
. ~ . - - - . . .- .. .- . - _ . - . . -. ~. . . .- .. .
2.3.7 Examination Category B-G-2, Pressure Retaining Bolting,2 in. and Less In Diameter ALT. 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 IWB-3517 :
VT-1 l
. B7.20 Pressurizer Bolts, Studs, and Nuts VIS, Surface IWB-3517 !
VT ;
B7.30 -- Steam Generator Bolts, Studs, VIS, Surface IWB-3517 and Nuts VT-1 :
'3 B7.40 Heat Exchanger Bolts, Studs and Nuts N/A N/A N/A B7.50 Piping Bolts, Studs, and Nuts VIS, Surface IWB-3517 VT-1 B7.60 Pumps Bolts, Studs, and Nuts VIS, Surface IWB-3517 l VT B7.70 Valves Bolts, Studs, and Nuts VIS, Surface IWB-3517 !
VT i B7.80 CRD Housings Bolts, Studs and Nuts VIS, Surface IWB-3517 i VT-1 l t
i NOTE: "N/A" in the EXAM. METIIOD column indicates that no applicable components are included in North Anna Unit 2. j N2-C32 Rev. 5 I t
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- 2.3.8 Examination Category B-H, Integral Attachments for Vessels ALT. EXAM ITEM EXAM. EXAM NO. REQUIRED / ACCEPTANCE RELIEF PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA
~REOUEST B8.10 . Reactor Vessel Integrally Welded N/A N/A N/A' Attachments B8.20 Pressurizer Integrally Welded VOL OR IWB-2500-13, IWB-3516 -
Attachments SUR -14, and -15 B8.30 Steam Generator Integrally Welded VOL OR IWB-2500-13, IWB-3516 Attachments SUR -14, and -15 B8.40 Heat Exchanger Integrally Welded . N/A N/A N/A Attachments NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included -
in North Anna Unit 2.
N2-C32 Rev. 5 Page 18 of 50 ll...- ' ' ' M
. . : . . . . - . ' "' ~ ' ' ' ' .. ' .
~ ~ ~ ' '
.+. ., .. , . . . .
-' 1 2.3.9 Examination Category B-J, Pressure Retaining Welds in Piping j 8 ALT. ' EXAM ;
' ITEM EXAM. EXAM- REQUIRED / ACCEPTANCE. RELIEF -- !
3 J NO. PARTS TO BE EXAMINED - METHOD- METHOD FIG NO. CRITERIA - REOUEST : .
t-
' B9.11 Nominal Pipe Size > 4 in. VOL & rWS-2500 IWB-3514 ' NDE -
Circumferentia' Welds SUR l r
B9.12 - Nominal Pipe Size 2 4 in. VOL & SUR IWB-2500 IWB-3514 NDE Longitudinal Welds
- B9.21 Nominal Pipe Size 5 4 in. SUR IWB-2500-8 IWB-3514 NDE-4 Circumferential Welds l
- - B9.22 Nominal Pipe Size $ 4 in. SUR IWB-2500-8 IWB-3514 . NDE !
Longitudinal Welds i
VOL & SUR B9.3 i Nominal Pipe Size 2 4 in. 1WB-2500-9, IWB-3514 NDE-4 Branch Pipe Connection Welds -10, and il 1
- B9.32 Nominal Pipe Size 5 4 in. SUR IWB-2500-9, IWB-3514 NDE-4 .
Branch Pipe Connection Welds -10, and -11 l
) B9.40 ' Socket Welds SUR IWB-2500-8 IWB-3514 NDE-4 !
f l N2-002 Rev. S ,
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. ~. _ _. - - . ~. . _ - - _ _ . - - . ._ _ . . _ - . . . . _ . . . _ - . _ _ . _ _ _ . -_ _ .. _ . !
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2.3.10 Examination Category B-K-1,' Integral Atta' chments fbr Piping, Pumps, and Valves ALT. EXAM-
. ITEM EXAM. -EXAM REQUIRED /. _. ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA '
REOUEST -
B10.10 Piping Integrally Welded VOL or .IWB-2500-13, IWB-3516' '
Attachments SUR- -14, and -15 B10.20 ' Pur. ps Ip*:grally Welded N/A N/A N/A
- Attach ts B 10.30 Valves le a gally Welded N/A N/A N/A Attachments i
s t
NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included in Noith Anna Unit 2.
N2-002 Rev. 5 Page 20 of 50 ,
23.11 Examination Cctegory B-L-1, Pressure Retaining Welds in Pump Casings -
ALT. EXAM.
ITEM EXAM. . EXAM. REQUIRED / ACCEPTANCE RELIEF .'
i NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA
- :REOUEST -
' B12.10 ~ Pump Casing Welds VOL SUR 'IWB-2500-16 IWB-3518 - NDE-5 l
i M2-002 . . Rev, 5 Page 2I of 50
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- 2.3.'12 Examination Category B-L-2, Pump Casings .
ALT. EXAM ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD- METHOD FIG NO. CRITERIA ~ ,.
REOUEST -
B12.20 Pump Casing VIS, VIS,. Internal' . IWB-3518 NDE -
VT-3 VT-1 Surfaces i
l 4
N2-C02 Rev. 5 Page 22 of 50
2.3.13 Examination Ceegory B-M-1, Pressure Retaining Welds in Valve Bodies
- ALT. EXAM .
ITEM . EXAM. EXAM: REQUIRED / ' - ACCEPTANCE RELIEF _ ;
NO. PARTS TO BE EXAMINED METHOD - METHOD FIG NOc CRITERIA ,
REOUEST B12.30 Valves, Nominal Pipe Size N/A N/A N/A 5 4 in. Valve Body Welds i
B12.40 -- Valves, Nominal Pipe Size N/A . N/A - N/A-
> 4 in. Valve Body Welds i
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2.3.14 Excmination Category B-M-2, Valve Bodies I-ALT. EXAhi ITEM EXAM. EXAM REQUIRED /- ACCEPTANCE RELEF-NO. PARTS TO BE EXAMINED - METHOD METHOD FIG NO. CRITERIA ;
REOUEST B12.50 Valve Body, Exceeding 4 in.- VIS, VIS, Internal . IWB-3519 hD E-6 VT-3 VT-3 Nominal Pipe Size Surfaces N2@2 Rev. 5 Page 24 of 50
-2.3.15 Examination Category B-N-1, Interior of Rmetor Vessel -
~ ALT.
EXAM-ITEM - - EXAM. -- EXAM REQUIRED / .' ACCEPTANCE RELIEF
- NO. ' PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA
- REOUEST
. B13.10 Reactor Vessel- VIS, - Accessible ~ IWB-3520.2 ,
Vessel Interior VT-3 areas- r I
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. N2 002 Rev. 5 t
Page 25 of *0
2.3.16. Examination Category B-N-2, Integrally Welded Core' Support Structures rad Interior
- Attachments to Reactor Vessels ALT. EXAM ITEM EXAM. EXAM . REQUIRED /- : ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA ~
REOUEST B13.20 BWRs Only N/A N/A N/A
. B 13'.30 BWRs Oaly N/A N/A N/A B13.50 Reactor Vessel Interior Attachments VIS, Accessible IWB-3520.1 Within Beltline Region VT-1 - welds B 13.60 Reactor Vessel Interior Attachments VIS, Accessible IWB-3520.2 Beyond Beltline Region VT-3 welds NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 2. .
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N2-002 Rev. 5 Page 26 of 50 D
'23.17 Examination Category B-N-3, Removable Core Support Structures ALT.. EXAM
. ITEM EXAM. EXAM . REQUIRED / ACCEPTANCE RELIEF - '
NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOIES_ T
.B13.40 BWRs Only N/A N/A N/A B13.70 Reactor Vessel Core Support VIS, Accessible IWB-3520.2
.Stmeture VT-3 Surfaces
-s NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 2.
N2 6 Rev. 5 Page 27 of 50
.. - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ = . .
2.3.18 Examination Category B-0, Pressure Retaining Welds in Control Rod Housings ALT. EXAM ITEM ~ EXAM.- EXAM - REQUIRED / ~ ' ACCEPTANCE RELIEF -
NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO: CRITERIA _
s -'REOUEST
- B14.10 Reactor Vessel Welds in CRD Housing-- VOL or IWB-2500-18 IWB-3523 SUR
~
1 N2-002 Rev 5 Page 28 of 50
2.3.19 Examination Category B-P, All Pressure Retaining Components ALT. TEST-ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF NO. ~ PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA - REOUEST B15.10 Reactor Vessel Pressure Retaining VIS, LEAKAGE IWB-3522 SPT-11, Boundary VT-2 PER IWB-5221 SPT-12 B15.11 Reactor Vessel Pressure Retaining VIS, HYDROSTATIC IWB-3522 SPT-11, Boundary VT-2 PER IWB-5222 SPT-12 B15.20 Pressurizer Pressure Retaining VIS, ' LEAKAGE IWB-3522 SPT-12 Boundary VT-2 PER IWB-5221 B15.21 Pressurizer Pressure Retaining VIS, HYDROSTATIC IWB-3522 SPT-12 ,
Boundary VT-2 PER IWB-5222 B 15.30 Steam Generator Pressure Retaining VIS, LEAKAGE IWB-3522 SPT-12 Boundary VT-2 PER IWB-5221 B15.31 Steam Generator Pressure Retaining VIS, HYDROSTATIC IWB-3522 SPT-12 Boundary VT-2 PER IWB-5222 B 15.40 IIeat Exchanger Pressure Retaining N/A N/A N/A :'
Boundary B15.41 lleat Exchanger Pressure Retaining N/A N/A N/A Boundary r
I fr2-CD2 Rev. 5 Pa;;e 29 of 50
p 2.3.19 Examination Categog B-P, All Pressure Retaining Components (continued)
ALT. TEST ITEM EXAM.- EXAM REQUIRED / ACCEPTANCE RELIEF NO. ' PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOUEST B 15.50 Piping Pressure Retaining Boundary .VIS, LEAKAGE IWB-3522 SPT-12 VT-2 PER IWB-5221 -
I B15.51 Piping Pressure Retaining Boundag VIS, HYDRO _ STATIC IWB-3522 - SPT-1,2 -
VT-2 PER IWB-5222 SPT-3,4 SPT-12 B15.60 Pumps Pressure Retaining Boundary VIS, LEAKAGE IWB-3522- SPT-12 VT-2 PER IWB-5221 B15.61 Pumps Pressure Retaining Boundary VIS, HYDROSTATIC IWB-3522 . SPT-1, VT-2 PER IWB-5222 - SPT-12 B15.70 Valves Pressure Retaining Boundary VIS, LEAKAGE IWB-3522 SPT-12 VT-2 PER IWB-5221 B15.71 Valves Pressure Retaining Boundary VIS, HYDROSTATIC IWB-3522 SPT-1,2 VT-2 PER IWB-5222 SPT-3,4 SPT-12 N2-002 Rev. 5 Page 30 of 50
-- .A
, 2.3.20 Examination Category B-Q, Steam Generator Tubing--
ALT. EXAM
. ITEM EXAM EXAM REQUIRED / ACCEPTANCE RELIEF;
- NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOUEST B 16.10 Steam Generator Tubing in Straight N/A N/A N/A Tube Design B 16.20 Steam Generator Tubing in U-Tube VOL Hot Leg IWB-3521 Design and U-Bend NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 2.
I N2-C32 Rev. 5 Page 3I of 50 ,
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__m... m __ __ .- -..... -. - . ._n...___..____.m___.m m._ _ _ _ - _ ,__..m.______.__.___ . _ _ _ . _ _ _ _ _ _ _ _ _ - _ ,- ,~ w -e, -
2.4 ' ISI Class 2 Components - Program Summary Table ,
2.4.1 Examination Category C-A, Pressure Retaining Welds in Pressure Vessels ALT. EXAM 1 ITEM - EXAM EXAM ~ REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOUEST C1.10 Pressure Vessel VOL IWC-2500-1 IWC-3000 Circumferential Shell Welds y C1.20. Pressure Vessel VOL IWC-2500-1 IWC-3000 Circumferential Head Welds C1.30 Pressure Vessel VOL IWC-2500-2 IWC-3000 Tubesheet-to-Shell Weld N2-002 Rev. 5 Page 32 of 50
.A.
2,'4.2 Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels - < . t ALT. EXAM' ITEM - . EXAM. EXAM REQUIRED / ' ACCEPTANCE RELIEF '
NO. ' PARTS TO BE EXAMINED ' METHOD METHOD ' FIG NO. ' CRITERIA - - REOUEST-C2.11 Pressure Vessel - SUR IWC-2500-3 IWC-3000 "
< 1/2 in.
Nominal Thickness -
, . Nozzle-to-Shell (or Head) Weld _
C2.21 Pressure Vessel SUR & IWC-2500-4(a) IWC-3000
> 1/2 in. ~
VOL or (b)
Nominal Thickness Nozzle-to-Shell - ;
. (or Head) Weld -
without Reinforcing Plate C2.22 Pressure Vessel VOL IWC-2500-4(a) IWC-3000
> 1/2 in. Nominal or (b)
Thickness .
Nozzle Inside j 4
Radius Section without Reinforcing ;
. Plate C2.31 Pressure Vessel SUR IWC-2500-4(c) IWC-3000
> l/2 in.
1 Nominal Thickness ,
Reinforcing Plate Welds to Nozzle and Vessel t
N2-002 Rev. S Page 33 of 50 t
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2.4.2 Examination Catcgory C-B', Pressure Retaining Nozzle Welds in Vessels (continued) -
ALT.. EXAM ITEM EXAM EXAM : REQUIRED / ACCEPTANCE : RELIEF
- NO.- - PARTS TO BE EXAMINED METHOD - METHOD FIG NO. CRITERIA REOUEST.'
' C2.32 Pressure Vessel- VOL. IWC-2500-4(c) IWC-3000
> 1/2 in.
Nominal Thickness
- Nozzle-to-Shell (or Head) Welds When inside of Vesselis Accessible C2.33 Pressure Vessel VIS, N/A. No leakage
. > 1/2 in. ' VT-2 Nominal Thickness Nozzle-to-Shell (or Head) When Inside of Vessel Is Inaccessible
. W2C2 Rev. 5 Page 34 of 50
- - .__. -- -- _ _ _ _ - = _ _-_ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ - _ - - _ . _ - _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ . - . . . -
2.4.3' Examination Category C-C, Integral Attachments For Vessels, Piping, Pumps, and Valves -
- ALT. EXAM.
ITEM EXAM EXAM- REQUIRED / ._
ACCEPTANCE RELIEF
- NO. PARTS TO BE EXAMINED METHOD' METHOD- FIG NO. CRITERIA REOUEST C3.10 Pressure Vessel -
SUR IWC-2500-5 -IWC-3512 Integrally Welded -
Attachments C3.20 Piping SUR IWC-2500-5 IWC-3512 Integrally Welded Attachments C3.30 Pump SUR IWC-2500-5 IWC-3512 Integrally Welded Attachments .
C3.40 Valve SUR IWC-2500-5 IWC-3512 Integrally Welded Attachments
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- 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 EXAME4ED METHOD METHOD FIG NO.' CRITERIA REOUEST -.
C4.10 Pressure Vessel VOL IWC-2500 IWC-3512 ~
Bolts and Studs 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 4
N2-002 Rev. 5 Page 36 of 50
, . 2.4.5 Examination Category C-F-1,' Pressure Retaining Welds In Austenitic Strinless Steel'or -
High Alloy Piping .
ALT. EXAM ITEM EXAM- EXAM REQUIRED / ' ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD' METHOD FIG NO. CRITERIA REOUEST-C5.11 Circumferential Welds In Piping SUR & IWC-2500-7 IWC-3514
> NPS 4 And > 3/8 in. Nominal VOL -
Wall Thickness C5.12 Longitudinal Welds In Piping > SUR & IWC-2500-7 IWC-3514 NPS 4 And > 3/8 in. Nominal Wall VOL Thickness C5.21 Circumferential SUR & IWC-2500-7 . IWC-3514 VOL 8 5.22 Longitudinal SUR & IWC-2500-7 IWC-3514 VOL C5.30 Socket Welds SUR IWC-2500-7 IWC-3514 i I
N2-002 Rev. 5 Page 37 of 50 m -- - e-- - see e m-". ,vm
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2.4.5 Examination Category C-F-1, Prcssure Retaining Welds In Austenitic Stainless Steel or High Alloy Piping (Continued)
ALT. EXAM ITEM EXAM ~ - EXAM ~ REQUIRED / dCCEPTANCE- RELIEFi- ,
NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOUEST -
C5.41 - Circumferential Branch Connection SUR- IWC-2500-9, -IWC-3514 Welds ofBranch Piping 2 NPS 2 to -13 C5.42 Longitudinal Branch Connection = SUR IWC-2500-12.. IWC-3514 ~
Welds ofBranch Piping 2 NPS 2 and -13 i
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ec -- e omw +- w rw r t + w e- e er' ae e+s=
_ 2.4.6 Examination Category C-F-2, Pressure Retaining Welds In _ Carbon Stect or Lov/ Alloy Steel Piping ;_
ALT. EXAM
~ ITEM - EXAM EXAM - REQUIRED / ACCEPTANCE RELIEF-NO.- PARTS TO BE EXAMINED METHOD METHOD- FIG NO. CRITERIA REOUEST C5.51 Circumferential Welds In Piping SUR &- IWC-2500-7 - IWC-3514
> NPS 4 And 2 3/8 in. Nominal VOL Wall Thickness C5.52 Longitudinal Welds In Piping > SUR & IWC-2500-7 IWC-3514 ,
NPS 4 And 2 3/8 in. Nominal Wall VOL -
Thickness C5.61 Circumferential N/A IWC-2500-7 IWC-3514 C5.62 Longitudinal N/A IWC-2500-7 IWC-3514 C5.70 Socket Welds N/A IWC-2500-7 IWC-3514 r Note: "N/A" in the EXAM METHOD column indicates that no applicable components are included in North Anna Unit 2.
I N2-C32 Rev 5 Page 39 of 50
___ ._m__._____- _ _ _ _ _ _ _ _ _ _m___ _ _ _ _ _ _ _. . _ _ _ - . . -_ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ ___.____ _ _ _ _ _ _ _ __.-_ _.-_ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ - _ . _ _________-___.______.____.________________m.____-__.m__
2.4.6 Examination Category C-F-2, Pressure Retaining Welds In Carbon Steel or Low Alloy Steel Piping (Continued)-
ALT. EXAM ITEM -
EXAM . EXAM REQUIRED / - ACCEPTANCE RELIEF.
o .NO. PARTS TO BE EXAMINED ' METHOD METHOD ' FIG NO. CRITERIA REOUEST C5.81 Circumferential Branch Connection SUR . IWC-2500-9, IWC-3514 NDE-7 Welds ofBranch Piping 2 NPS 2 'to -13 C5.82 Longitudinal Branch Connection SUR- IWC-2500-12 - IWC-3514 .
' Welds of Branch Piping 2 NPS 2 and -13 i
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_ _ _ _ _ _ _ __=.__m _ _ _ _ __ ____ +._______ __. . _ _ _ +- - - _ - _ _ m___ s __ _ -
_ __ ----m -- -,,. ...- --_ ..
' 2.4.7 Examination Category C-G, Pressure R'etaining Welds In Pumps And Valves'-
ALT. EXAM .
ITEM EXAM EXAM ' REQUIRED /.- . ACCEPTANCE RELIEF :
f-' -
NO. ~ PARTS TO BE EXAMINED METIIOD METHOD FIG NO. CRITERIA REOUEST SUR IWC-2500-8 IWC-3515 NDE '
C6.10 - . Pump Casing Welds
- NDE-9 C6.20 Valve Body Welds N/A N/A~ N/A' NOTE: "N/A" in the EXAM. METHOD Column indicates that no applicable components are included at North Anna Unit 2.
N2-002 Rev. 5 Page 41 of 50
2.4.8 Examination Category C-H,'All Pressure Retaining Components i
ALT. !
. ITEM EXAM' EXAM. TEST ACCEPTANCE RELIEF
< NO.i PARTS TO BE EXAMINED METHOD- METHOD ~ REOUIRED CRITERIA REOUEST .i C7.10 Pressure Vessel i VIS, FUNCTIONALL IWC-3516 - . SPT-12, :
Pressure Retaining VT-2 _ PER IWC-5221 - SPT-13 i l Components C7.20 - Pressure Vessel VIS, HYDROSTATIC ' IWC-3516 . SPT-8, ;
Pressure Retaining VT-2 : PER IWC-5222 - SPT-12,'
Components SPT-13 ,
i C7.30 Piping VIS,- FUNCTIONAL IWC-3516~ . SPT-12, i Pressure Retaining VT PER IWC-5221- SPT-13 Components i
C7.40 Piping VIS, HYDROSTATIC 'lWC-3516 SPT-5,'6 L ,
Pressure Retaining VT-2 PER IWC-5222 SPT-7,8 .- ,
Components SPT-11,
-12, -[
C7.50 Pump VIS, FUNCTIONAL IWC-3516 SPT-12c-Pressure Retaining VT-2 PER IWC-5221 SPT-13
- Components
[
C7.60 Pump VIS, IIYDROSTATIC IWC-3516 - SPT-12, .;
Pressure Retaining VT-2 PER IWC-5222 SPT i Components .
.i C7.70 Valve VIS, FUNCTIONAL IWC-3516 SPT-12, I Pressure Retaining VT-2 PER IWC-5221 SPT-13 !
Components ;
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~2 :4.8 Examination Category C-H, All Pressure Retaining Components (Continued) - -
ALT. -!
ITEM - EXAM- EXAM- TEST- ACCEPTANCE RELIEF
- - NO. ' PARTS TO BE EXAMINED METHOD METHOD REOUIRED CRITERIA REOUEST-
' C7.80 - Valve VIS, HYDROSTATIC . IWC-3516 ' S PT-5,6 -
Pressure Retaining . VT-2 . PER IWC-5222 ' SPT-7,8 Components . SPT-12,~
SPT !
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' -2.5 ISI Class 3 Components - Program Summary . ,
2.5.1 Examination Category D-A, Systems In Support of Reactor Shutdown Function
-- ALT. - TEST' ITEM EXAM EXAM AND EXAM ACCEPTANCE L RELIEF _ - _
NO.' PARTS TO BE EXAMINED - METHOD METHOD ' REOUIREMENTS CRITERIA ' REOUEST:
- Dl:10 Pressure Retaining Components VIS, INSERVICE IWD-3000 VT-2 PER IWD-5221 '
- DI.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 [
D1A0 Integral Attachment- VIS, IWD-2500-1 IWD-3000 l Spring Type Supports VT-3 D1.50 Integral Attachment- VIS, IWD-2500 . IWD-3000 Constant Load Type Supports VT-3 '
DI.60 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Shock Absorbers VT-3 N2-CD2 Rev. 5 :
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Page 44 of 50 [
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...__._.__._._.__________.___-___.______...u_.__.-.m_m__m___.. - -
_-_.-..__ __ m___ _ .2 ____ _ . _ _ - . ____.___. _ _ _ _ __ _ . . _ .___.m.-___.m_..__ _.a___.__.__-__.__.--__.-___._____.__-________.m.m_____.t.___m_________ - - - -
m___mmm______.____.-____._.m.m_..u____.____.-_.____..m__ _ _ _ . - -
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' 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 Components VIS, HYDROSTATIC RVD-3000 SPT-9 VT-2 PER RVD-5222 D2.20 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Component Supports and VT-3 .
I Restraints D2.30 Integral Attachment- VIS, IWC-2500-1 IWD-3000 Mechanical and Hydraulic VT-3 Snubbers D2.40 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Spring Type Supports VT-3 D2.50 Integral Attachment- - VIS, IWD-2500-1 IWD-3000 Constant Load Type Supports VT-3 D2.60 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Shock Absorbers VT-3 ~
N2-002 Rev. 5 ;
Page 45 of 50
._________m__..-__._.=.__m._..m__
_ _ . _ _ . _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ m_ _ ____ _ -- - m _- - _ m ,,_..-r , . _ . , .. . . .mm.
'2.5.3 Examination' Category D-C, Systems In Support of Residual Heat Removal From Spent Fuel :i Storage Pool ALT. TEST ITEM EXAM EXAM AND EXAM- ACCEPTANCE RELIEF.
NO. PARTS TO BE EXAMINED METHOD ~ METHOD REOUIREhENTS CRITERIA REOUEST-D3.10 Pressure Retaining Components VIS, 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-I . IWD-3000 Component Supports VT-3 '
and Restraints D3.30 l< tegral Attachment- VIS, IWD-2500-1 IWD-3000 Mechanical and Hydraulic VT-3 ,
. Snubbers D3.40 Integral Attachment- VIS, . IWD-2500-1 IWD-3000 Spring Type Supports VT-3
-t D3.50 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Constant Load Type VT-3 Supports ,
D3,60 Integral Attachment- VIS, IWD-2500-1 IWD-3000 -
Shock Absorbers VT-3 .:
[
N2C2 Rev. 5 -
Page -16 of 50 i
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l 2.6 :-Augmented Inspection Requirements on ISI Class I, 2, or 3 Systems - Pr ogram Summary Table :
ITEM NO.' COMPONENT DESCRIPTION REFERENCE (S)
' EXAM AND FREOUENCY
- 1. REACTOR COOLANT PUMPS - FLYWHEEL I
- TECH. SPECS. 4.4.10.1.I' UT IN PLACE AT APPROX.
REG. GUIDE 1.14, REV. I 3 YEAR INTERVALS.
UT/PT (FLYWHEEL REMOVED)
'10 YEAR INTERVALS.
- 2. REACTOR COOLANT LOOP BYPASS LINES UFSAR 3.6.2.3.1 UT/PT EXAM SELECTED -
WELDS EVERY 40 MONTHS.
- 3. PRESSURIZER SPRAY PIPING IN THE LOWER UFSAR 3.6.2.3.2 UT/PT EXAM SELECTED CUBICLE BETWEEN FLOOR ELEVATIONS WELDS EVERY 40 MONTHS 262 FT.10 IN. AND 272 FT. 6 IN.
- 4. PRESSURIZER SAFETY VALVE INLET PIPING UFSAR 3.6.2.3.3 UT/PT EXAM SELECTED LINES WELDS EVERY 40 MONTHS
- 5. STEAM GENERATORS - SUPPORTS TECH. SPECS. 4.4.10.1.2 VT-1 EVERY 40 MONTHS 1/3 OF THE MAIN MEMBER WELDS JOINING A572 MATERIAL.
- 6. SERVICE WATER PIPE WALL THICKNESS STATION PT SEMI-ANNUAL UT THICKNESS MEASUREMENTS 1-PT-7.5.14 AND DRY FILM PAINT THICKNESS.
- 7. REACTOR VESSEL INCORE DETECTOR - NRCB 88-09 100% EDDY CURRENT THIMBLE TUBES EXAMINATION ON ALL INCORE DETECTOR THIMBLE TUBES IN SERVICE EACH REFUELING N2-002 Rev. 5 Page 47 of 50
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-2.6- Augmented Inspection Requirements on ISI Class 1,2, or 3 Systems - Program Summary Table (Continued)
ITEM NO. COMPONENT DESCRIPTION REFERENCE (S) EXAM AND FREOUENCY
- 08. REACTOR COOLANT PIPING - LER 82-043 RT EVERY THIRD REFUELING THERMAL SLEEVES DATED 8/26/82' OUTAGE.
- 9. STEAM GENERATOR FEEDWATER NRCNB 79-13 UT SELECTED FEEDWATER NOZZLES PIPING WELDS WITHIN 5 -
YEARS SINCE LAST REPLACEMENT. AFTER-5 OPERATING YEARS REPEAT EXAMINATION EACH REFUELING OUTAGE.
ABBREVIATIONS USED IEIN = NRC IE INFORMATION NOTICE LER = LICENSEE EVENT REPORT hTCB = NRC IE BULLETIN PT = PENETRANTTEST/ EXAMINATION PT = PERIODIC TEST (REFERENCE)
RG = NRC REGULATORY GUIDE RT = RADIOGRAPHY TEST / EXAMINATION UFSAR = UPDATED FINAL SAFETY ANALYSIS REPORT '
VT = VISUAL TEST / EXAMINATION N2-002 Rev 5 Page 48 of 50
s 2.7.1 NDE SERIES RELIEF REQUESTS ReliefReauest Status Letter No.
NDE-1 Withdrawn 91-461 (9/9/91) l ,, NDE-2 Withdrawn 91-705 (11/27/91)
NDE-3 Denied - 92-730 (11/5/92)
NDE-4 Authorized 92-730 (11/5/92)
NDE-5 Granted with 92-730 (11/5/92) >
Conditions
. NDE-6 Granted with 95-429 (8/8/95)
- i. Conditions NDE-7 Granted 92-730 (11/5/92)-
r NDE-8 Granted 92-730 (l1/5/92) i NDE-9 Granted 92-730 (l1/5/92)
- NDE-10 . Withdrawn 91-461 (9/9/91)
NDE-11 Authorized 92-730 (11/5/92)
, NDE-12 Not Required 92-730 (11/5/92)
NDE-13 Granted 92-730 (11/5/92)
- i. NDE-14 Granted 92-730 (11/5/92)
NDE-15 B-A Bl.30 Denied 92-7M (11/5/92)
NDE-15 B-D B3.90 Authorized 92-730 (11/5/92)
NDE-15 B-D B3.100 Authorized 92-730 (11/5/92).
NDE-15 BJ B5.30 Authorized 92-730 (11/5/92)
NDE-15 B-G-1 B6.40 Denied 92-730 (11/5/92)
NDE-16 Granted with 92-730 (11/5/92)
Conditions NDE-17 Withdrawn NDE-18 Granted 95-429 (8/8/95)
'NDE-18 Revised 96-032 (2/7/96)
NDE-19 Granted 95-429 (8/8/95)
NDE-20 Granted 95-429 (8/8/95)
NDE-21 Granted with 95-429 (8/8/95)
Conditions NDE-22 Granted 96-041 (l/17/96)
'NDE-23 Granted 96-549 (10/10/96)
. NDE-24 Granted 96-549 (10/10/96)
' NDE-25 Granted 95-549 (l0/10/96)
NDE-26 Granted 96-549 (10/10/96)
NDE-'27 Granted 96-549 (10/10/96)
NDE-28 Granted 96-549 (10/10/96)
NDE-29 Granted 96-549 (10/10/96)
N2-002 Rev 5 Page 49 of 50
_-p1_
2.7.l NDE SERIES RELIEF REQUESTS (continued)
Relief Reauest Status Letter No.
' NDE-30 Granted 96-549 (10/10/96 NDE-31 Granted 967-357 (26/34/97)
NDE-32, Rev.~ 2 Granted with Conditions97-700 (11/24/97)
NDE-32, Rev. 3 - Withdrawn 98-037A (1I/12/98)
NDE-32, Rev. 4 Granted 98-037A (11/12/98)
NDE-33 Granted 97-457 (7/29/97)
NDE-34 Granted 97-457 (7/29/97)
NDE-35 Granted 97-457 (7/29/97)
NDE-36 Granted 97-563 (9/24/97)
NDE-37 Granted 97-683 (11/14/97)
NDE-38 Granted 97-739 (12/18/97)
NDE-39 Granted 98-059 (01/15/98)
NDE-40 Pending '98-513 (9/18/98)
NDE-41 Pending 98-513 (9/18/98)
NDE-42 Pending 98-513 (9/I8/98)
' 2.7.2 SPT RELIEF REQUESTS Relief Reauest Status Lqtter No SPT-1 Granted with Conditions92-730 (11/5/92)
SPT-2 Granted 92-730 (lI/5/92)
SPT-3 Granted 92-730 (11/5/92)
SPT-4 Granted 92-730 (11/5/92)
SPT-5 Granted 92-730 (11/5/92)
SPT-6 Granted 92-730 (l1/5/92)
SPT-7 Granted 92-730 (1 t/5/92)
SPT-8 Granted 92-730 (11/5/92)
SPT-9 Granted 92-730 (1I/5/92)
SPT-10 Withdrawn 91-461 (9/9/91)
SPT-11 Granted 91-461 (9/9/91)
SPT-12 Part 1 Granted with Conditions92-730 (11/5/92)
SPT-12 Part 2 Denied 92-730 (11/5/92)
SPT-13 Withdrawn 91-461 (9/9/91)
SPT-14 Granted with Conditions96-550 (10/16/96)
SPT-15 Withdrawn 94-319 (6/23/94)
SPT-16 Rev. 2 Granted 97-290 (4/30/97)
N2-002 Rev. 5 Page 50 of 50
BELIEF REOUEST NDE-1 (WATHDRAWN - VP Letter No.91-461 Dated 9/9/91)
Page 1 of 1 l
RELIEF REOUEST NDE-2 (WITHDRAWN - VP Letter No.91-705 Dated 11/27/91)
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E RELIEF REOUEST NDE-3 ,
9 ..
- I. IDENTIFICATION OF COMPONENTS i
4 Threads in' Flange ;
-i i Reactor Vessel (2-RC-R-1) t Drawing No. Thread In Flange Mark No.
- 12050-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,1986 Edition, Categosy 1
! - B-G-1, Item No. B6.40 requires a volumetric examination of the Reactor Vessel Threads
' . In Flange. In addition, deferral of the examination is not permissible. Virginia Electric 1 and Power Company is employing Table IWB-2412-1, Inspection Program B to j schedule examinations.
i Reliefis requested from the' examination frequercy requirements specified in Table
- IWB-2412-1 for the reactor vessel threads in flange examination.
- III. BASIS FOR RELIEF
. l
- - Relief from the examination frequency requirements is requested based upon the following criteria
I 1)' Virginia Electric and Power Company currently schedules the reactor vessel flange !
I threads examination to be performed in concurrence with the automated examination performed on the reactor vessel welds. This permits the examinations i-' to be conducted with more sophisticated (i.e., digital, automated) ultrasonic l E techniques in lieu of manual techniques.
l'
- 2) In order to accommodate the automated ultrasonic calibrations, the calibration l 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 4
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' ;
E, Pope 1 of 2 1.
, I
.- - . _ - - =.. -- - . - . .. - .. ._ _.
RELIEF REOUEST 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 these threads.
IV. ALTERNATE PROVISIONS An automated ultrasonic 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 flange during the end ofinterval reactor vessel examination.
, V. STATUS i Denied - NRC Letter No.92-730 Dated 11/5/92.
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. RFI TFF REOUESTNDE-4
- 1. IDENTIFICATION OF COMPONENTS .
ISI Class 1 Pressure retaining welds in piping L
I II. IMPRACTICABLE CODE REQUIREMENTS
- 'Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition requires that L notes 1(b) and 2 of Category B-J, table IWB-2500-1 be used in the selection of welds for '
~ examination. ;
l l .III. BASIS FOR RELIEF ;
The first interval selection was based upon the 1974 Edition wah Summer 1975 Addenda t (74/S75) of ASME Section XI. As a result notes 1(b) and 2 cannot be applied without 1
some programmatic additions and modifications. In addition, although stress and I utilization calculations exist for North Anna Unit 2, no correlation exists with actual weld locations. Total reuse of the first interval 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. -
3.
k'
- IV.- ALTERNATE EXAMINATION )
p i 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 willinclude terminal ends as they appear on our plant isometrics as no corresponding stress
, calculations exist (NUREG-0800, BTP 3.6.2-13). Terminal ends willinclude 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 1 l' downstream of the integral attachment 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 the 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 j; be evenly distributed based upon line size, line function, and line design to the extent
- practicable. These selected welds will be examined in all future successive inspection j; intervals to the extent allowed by code editions approved at that time.
L V. STATUS j
i Granted - NRC Letter No.92-730 Dated 11/5/92.
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<I' s ~. RELIEF REOUESTNDE-5
'I . / IDENTIFICATION OF COMPONENTS Pressure retaining welds in pump casings Pump casings Reactor Coolant Pumps: ' (2-RC-P-1 A,'-1B, -1C)
Casing Exam.
f Drawine No. Weld No. Identifier
' 12050-WMKS-RC-P-1 A.1 1 Case 12050-WMKS-RC-P-1B.1 1 Case 12050-WMKS-RC-P-1C.1 N/A Case
. II. IMPRACTICABLE CODEREQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition, Category B-L-1, item No. B12.10 requires a volumetric examination to be performed on 100% of the pressure retaining welds in at least one pump in each group of pumps performing similar functions in the system (e.g., reactor coolant pumps). In 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 Anna Power Station Unit 2 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 boundary weld in the casing that is to be examined in ;
accordance with Category B-L-1.
Since the installation of these pumps, it has been recognized that a volumetric examination of the casing welds is not practical when employing current ultrasonic techniques.
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RELIEF REOUEST NDE-5 CONTINUED i 1
1 The physical properties of the stainless steel casting and weld material preclude a j 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 l currently constitutes the only viable examination method for the volumetric examination of reactor coolant pump welds.
i The volumetric examination method is radiographic and is performed by placing the MINAC inside the pump casing and placing film on the outside of the pump.
- To pedorm the examination, the pump must be completely disassembled, including i removal of the diffuser adapter. This amount of disassembly is far beyond the i amount of disassembly performed for normal maintenance. Insulation must also be removed from the exterior of the pump casing.
l The examination has been pedormed at four different sites, all of which have the j Westinghouse Model 93 pump. The MINAC 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 i the welds were found at any of the sites. A review of the original radiographs of .
j- the Point Beach Unit I 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 MINAC at four different sites demonstrates that the method is capable of satisfying ASME i 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 i
pump.
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- RELIEF REOUEST NDE-5 CONTINUED There have been no defects 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 developed 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 notjustified from a cost / benefit perspective. The pump disassembly, examination and reassembly is estimated to cost $750,000.
IV. ALTERNATE EXAMINATION A visual examination of the external surfaces of one pump's casing weld and a surface examination of the weld to the extent practicsW 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. ,
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. 1 V. STATUS I l
Granted with conditions - NRC Letter No.92-730 Dated 11/5/92. Reliefis granted as written provided that the pump has not been disassembled. If the pump has in fact been l disassembled, a full visual (VT-3) of the pump internals shall be conducted as per the code. j l
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RELIEF REOUEST NDE-6 i
I. IDENTIFICATION OF COMPONENTS ISI Class 1 Valve Bodies Exceeding 4 in. Nominal Pipe Size IL IMPRACTICABLE CODE REQUIREMENTS -
)
Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition, 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.
Because these examinations must be met whether or not the valves have to be disassembled for maintenance, this requirement is considered impractical. J III. BASIS FOR RELIEF The requirement to disassemble primary system valves for the sole purpose of performing a visual examination of the internal pressure boundary surfaces has a very small potential ofincreasing 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 2 include valves which vary in size, design s 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 boun:lary 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.
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RFLIEF REOUEST NDE-6 )
CONTINUED l 1
Virginia Electric and Power Company feels this approach would provide a reasonable i level of assurance that the integrity of the primary system valves is being maintained. l IV. ALTERNATEEXAMINATION j The visual examination of the internal pressure boundary surfaces will be performed on one valve within each group of valves that are of the same size, constructional design (such as globe, gate or check valves), and manufacturing method, and that perform similar functions in the system (such as containment isolation and system over protection), to the extent practical, when a valve is disassembled for maintenance purposes.
The examination will be done once during the inspection interval.
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.
V. STATUS Granted with conditions - NRC Letter No.92-730 Dated 11/5/92. Granted svided that, if the valve has not been disassembled, this fact should be reported by the Limensee in the ISI Summary Report at the end of the interval.
Revised in Revision 3 to limit exunination to one valve out of a group of similar valves.
Granted - NRC Letter No.95-429 Dated 8/8/95.
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RET TFF REOUEST NDE-7 i
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I. IDENTIFICATION OF COMPONENTS Branch connection welds - Main neam relief headers 1
Drawinn No. Weld Nos.
12050-WMKS-101A-1 SW-77 to SW-81 12050-WMKS-101A-2 SW-83 to SW-87 12050-WMKS-101A-3 SW-7W to SW-1IW -
See Detail A and Section B-B ofeach drawing.-
II. IMPRACTICABLE CODEREQUIREMENL),
Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition, Category C-F-2, ,
Item No. C5.81 requires circumferential pipe branch connection welds be surface examined. ,
.III. BASIS FORRELIEF 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 stuface examination of the reinforcement pad's fillet weld? associated with each branch connection weld will be performed during the interval. ,
i V. STATUS Granted - NRC Letter No.92-730 Dated 11/5/92.
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RELIEF REOUESTNDE-8 1
I. IDENIIFICATION OF COMPONENTS Pump CasingWelds
[ OutsideRecirculation SprayPumps (2-RS-P-2A and 2-RS-P-2B) i' Drawing No. Weld Nos.
12050-WMKS-RS-P-2A SW-1, SW-2, SW-3 LS-6, LS-7, LS-8 LS-9 (Partial Access)
LS-10(Partial Access) 12050-WMKS-RS-P-2B SW-1, SW-2, SW-3 .
LS-6, LS-7, LS-8 l LS-9 (Partial Access) i o LS-10(Partial Access)
. i II. IMPRACTICABLE CODE REQUIREMENTS
! Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition, Category C-G, Item
- Number C6.10, requires pump casing welds to have a surface examination each inspection i interval. A surface examination of all of the pumps casing welds is not practicable.
, l III. BASIS FORRELIEF i
) Each of the two outside recirculation spray pump casings have a total of five circumferential )
jv welds and five longitudinal welds. Three of the circumferential welds (SW-1, SW-2 and !
4- SW-3), and three of the longitudinal welds (LS-6, LS-7 and LS-8) are completely encased in concrete and are not accessible for examination from the outside diameter (O.D.). Of the ,
F remaining two longitudinal welds, one weld is partially encased in concrete (LS-9) and one j i . weld is partially covered by a vibration plate (LS-10). O.D. examinations can be perfonned on i both of these longitudinal welds. The immining two circumferential welds are completely l accessible for examinations from the O.D. Surface examinations from the Inside Diameter l (I.D.) are not a practicable alternative Access to t}e inside of the pump casings is limited by l physical size (24 inch outside diameter), the pump shaft, and the pump shaft support obstmetions. !
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~.- 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.
V. STATUS-
]
Granted - NRC Letter No.92-730 Dated 11/5/92.
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. RELIEF REOUESTNDE-9 I 1.- tIDENTIFICATION OF COMPONENTS Pump Casing Welds Low Head Safety Injection Pumps '
(2-SI-P-1 A and 2-SI-P-1B) b ~ Drawing No. Weld Nos.
i 12050-WMKS-SI-P-1 A 1,2,3
! LS-1, LS-2, LS-3
- LS-4 (Partial Access) i LS-5 (Partial Access)
- . 12050-WMKS-SI-P-1B 1, 2, 3 l LS-1, LS-2, LS-3 LS-4 (Partial Access)
LS-5 (Partial Access) i II. IMPRACTICABLE CODE REQUIREMENTS
!, Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition, Category C-G, i l 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 RELIEF t
Each of the two low head safety injection pump casings have a total of five circumferential l welds and five longitudinal we.Is. 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 physical size (24 inch outside diameter), the pump shaft, and the pump shaft supports.
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- . RELIEF REOUEST NDE-9 l CONTINUED j
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, - IV.- ALTERNATE PROVISIONS A surface examination of the accessible portions of circumferential and accessible l longitudinal welds will be performed t_o the extent and frequency described in IWC-2500. !
[ A remote visus! xamination (VT-1) of the I.D. of the pump casing welds will be {
performed only if the pump is disasseinbled for maintenance. l V. STATUS .
- Granted - NRC Letter No 92-730 Dated 11/5/92. ;
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~~. BELIEF REOUEST NDE-10 (WITHDRAWN - VP Letter No.91-461 Dated 9/9/91) i l
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- RELIEF REOUEST NDE-11
. I. IDENTIFICATION OF COMPONENTS Ultrasonic calibration blocks
- II. IMPRACTICABLE CODE REQUIREMENTS-
[. Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition, gives specific
- requirements for the fabrication of ultrasonic calibration blocks. Specifically, paragraph IWA-2232(a), IWA-2232(b) and IWA-2232(d)(4) j III. BASIS FOR RELIEF i
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 4
IWA-2232(a), IWA-2232(b) and IWA-2232(d)(4) of the 1986 Code would require us to j manufacture new calibration blocks. Using the existing calibration blocks allows us to correlate ultrasonic data from the first interval inspections as required by IWA-1400(h).
4 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.
i Note: It is our understanding that Code Case N-461 is scheduled for approval in Regulatory Guide 1.147 Revision 8. Any limitations or modi 5 cations to this Code Case as indicated in the Regulatory Guide shall be adhered to.
V. STATUS Authorized - NRC Letter No.92-730 Dated 11/5/92.
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EFT M REOUEST NDE-12 I. IDENTIFICATION OF COMPONENTS 4
ISI Class 1 and Class 2 Welds II. IMPRACTICABLE CODE REQUIREMENTS ,
Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition, 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 attemative examination coverage for Class 1 and Class 2 welds, 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 i Regulatory Guide 1.147 Revision 8. Any limitations or modifications to this Code l
Case as indicated in the Regulatory Guide shall be adhered to.
V. STATUS i
Relief Not Required - NRC Letter No.92-730 Dated 11/5/92.
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. RFTFF REOUEST NDE-13
- I. IDENTIFICATION OF COMPONENTS ISI Class 1 and 2 Piping, Vessel and Component Welds H. IMPRACTICABLE CODEREQUIREMENTS 1 Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition, IWA-2600, weld
- reference system.
III. BASIS FORRELIEF The original construction code used at North Anna Power Station, ANSI B31.7,1%9 Edition, did not establish a weld reference system. Immediate establishment of a weld reference system cannot be practically attained within the scope and schedule of existing outages.
iv. ' ALTERNATE PROVISIONS North Anna Unit 2 has recently updated its weld isometrics, providing a detailed identification
- oflocation. It is our intention to use these drawmgs for trackmg and locating welds.
.In addition, as 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.
V. STATUS Granted - NRC Letter No.92-730 Dated 11/5/92.
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RELIEF REOUEST NDE-H -
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I. IDENTIFICATION OF COMPONENTS Pressure Retaining Welds in the Reactor Vessel and Vessel Nozzle area examined by the l automated vessel tool inspection device. l II. IMPRACTICABLE CODE REQUIREMENTS ;
1 Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition, IWA-2600, weld reference system. ;
I
, III. BASIS FORRELIEF l 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 systems. It accomplishes this by the use of an electronic encoder system which provides for suBicient repeatability.
IV. ALTERNATE PROVISIONS 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.
V. STATUS Authorized - NRC Letter No.92-730 Dated 11/5/92.
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RELIEF REOUESTNDE-15 I. IDENTIFICATION OF COMPONENTS Reactor vessel shell-to-flange weld Reactor vessel nozzle-to-vessel welds Reactor vessel nozzle inside radius sections Reactor vessel nozzle-to-safe-end welds Reactor vessel threads in flange Drawinn No. Mark No.
12050-WMKS-RC-R-1.1 Weld 1 Welds 10,12,14 NIRs 10,12,14 12050-WMKS-RC-R-1.3 (50%) TIF-01 through TIF-58 12050-WMKS-109E-1 Weld 1 12050-WMKS-109F-1 Weld 13 12050-WMKS-109G-1 Weld 25 II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition, Category B-A,
. Item B l.30, Category B-D, Item 3.90, Category B-D, Item E3.100, Categorv B-F, Item B5.10, and Category B-G-1, Item B6.40 requires examinations, which utilize .he automated vessel tool.
Reliefis requested from interval requirements described in IWA-2432 concerning the examination of the reactor vessel.
III. BASIS FOR RELIEF North Anna Unit 2, first interval, began December 14,1980 and concludes December 14, 1990. As part of the first interval inspection, North Anna Unit 2 conducted examinations on the reactor vessel using the automated vessel tool. These examinations were conducted approximately two months prior to the start of the second interval. As only two months remain before the start of the second interval, requiring the automated vessel tool to be brought back to conduct examinations for the first period, second interval is impractical economically, and would unnecessarily impact a subsequent outage.
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RELIEF REOUEST NDE-15 l CONTINUED IV. ALTERNATE PROVISIONS I
Alternatively the required second interval, first period examinations have been combi ied with the requirements of the first interval. This will not eliminate any required examination, as different areas will be examined. This application is implied as acceptable in IWA-2430(d) of the 1986 Edition of ASME Section XI, however this relief request is 1 being submitted as only the reactor vessel examinationc are affected.
I V. STATUS
.1 B-A Bl.30 Denied Letter No.92-730 Dated 11/5/92.
B-D B3.90 Authorized Letter No.92-730 Dated 11/5/92.
I B-D B3.100 Authorized Letter No.92-730 Dated l
- 11/5/92.
i B-F B5.30 Authorized Letter No.92-730 Dated !
11/5/92.
B-G-1 B6.40 Denied Letter No.92-730 Dated 11/5/92.
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RELIEF REOUEST NDE-16 I 6
- 1. IDENTIFICATION OF COMPONENTS Nozzle-to-Vessel Welds
- Nozzlu Inner Radius Section l
Pressurizer: (2-RC-E-2) i Drawing No. -
Weld No. 1
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12050-WMKS-RC-E-2 9 l 9NIR l
- 11. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition, requires in Category B-D, Item No. B3.110 and B3.120, that the pressurizer surge line nozzle-to-vessel weld and nozzle inside radius section be volumetrically examined.
Reliefis requested from these requirements.
III. BASIS FOR RELIEF
- The North Anna Unit 2 pressurizer surge nozzle is surrounded by 78 heater penetrations. ,
Engineering recommends that the heater cables be disconnected prior to the renioval of
' insulation. This recommendation is due to the possibility of damage to the heater
- element connections if the insulation is removed while the cables are connected.
1
- Based upon the most recent survey of the applicable area, the dose rate is 300MR in the general area, 500MR at one foot and 1500 to 2000 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 seven man hours to prepare and examine the nozzle-to-vessel weld and nozzle inside radius section. The resulting dose estimate for these examinations is 15.3 man rem.
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- . RFI TFF REOUEST NDE-16 ~
CONTINUED i
4 Based upon a review of the fabrication' drawings, the estimated percentage of the required volume that could be examined on the pressurizer surge line nozzle-to-vessel weld (9)is as follows:
EXAMINATION ANGLE PERCENTAGE EXAMINED ,
45 Degrees 60 %
60 Degrees 40%
0 Degrees 80 %
i The examination coverage of the nozzle inside radius section (9NIR) would be somewhat larger values, however we feel that the confined access to the nozzle as a .
result of the pressurizer skirt, surge line piping and heater penetrations, t.nd area dose rates would result in only a "best effort" examination in either case. Therefore, it is felt that the gain in system integrity is not commensurate with the exposure received from the examinations.
IV. ALTERNATE EXAMINATION 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, Technical Specifications requires that the Reactor Coolant System Leak Rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Additionally, the containment atmosphere particulate radioactivity is
. monitored every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. No additional alternative requirements are deemed necessary.
.V. STATUS Granted with conditions - NRC Letter Fa.92-730 Dated 11/5/92. Granted provided that a remote visual examination of the inner radius section is conducted in the same period as the ultrasonic inspection would be scheduled by the code.
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4 . RFTM REOUEST NDE-17 .
I. IDENTIFICATION OF COMPONENTS 4
NozzleInnerRadius Sections i
! Steam Generators: (2-RC-E-1 A, 2-RC-E-1B,2-RC-E-1C)
Drawi in No. IDDerRadiusIdentification No. 1 12050-WMKS-RC-E-1A.2 1INIR and 12NIR(ISI Class 1) l
- (Steam Generator A) j i: .
12050-WMKS-RC-E-1B.2 1INIR and 12NIR(ISI Class 1)
(Steam Generator B) l 12050-WMKS-RC-E IC.2 11NIR and 12NIR(ISI Class 1) l 1
(Steam Generator C)
II. IMPRACTICABLE CODE REQUIREMENTS j Section XI of the ASMS Boiler and Pressure Vessel Code,1986 Edition, Category B-D, Item l No. B3.140, requires the nozzle inside radius sections of the Steam Generators to be j volumetrically examined.
Reliefis requested from the volumetric uu.mination requirements of the nozzle inner radii for j the Steam Generator channel head nozzles. i l
III.- BASIS FORRELIEF The North Anna Unit 2 primary nozzles are integrally cast into the channel head. The nozzles I contain inherent examination limitations such as irregular O.D. profile, rough surface condition and attenuative grain structure. The ultrasonic technique used to examine the nozzle inner radii involves the fabrication of a calibration block that closely simulates the nozzle geometry. This is necessary in order to interrogate the inner radius section at precise angles with specifically designed search units.
In orde- to assess the feasibihty of performing examinations on the North Anna Unit 2 primary nozzle inner radii, Virginir. Power performed exammations on a Westinghouse Model 44 1 channel head which will be used to train welders for the Unit 1 steam generator replacement.
1 This channel head is made from the same cast material (/STM 216-WCC) as the Model 51 generators which are currently installed in North Anna Unit 2. We believe that the Page 1 o'3 I
t j
l RELIEF REOUEST NDE-17
- CONTINUED general surface profile and acoustic properties are representative of the Unit 2 generators.
The calibration for this examination was established on our inner radius block for the Unit I replacement generators which is depicted on Attachment 1. This calibration block is made from SA 508, Class 3, forged carbon steel.
Examination Results
- 1. Comparison ofMaterialNoise
. Figures A and B on Attachment 2 depict the respective responses from notches 4 l l and 6 from calibration block VPSGINRI. Both notch responses exhibit a high
, signal to noise ratio with little evidence of materini noise. Figure A on Attachment
?
3 depicts the material noise from the Model 44 primary nozzle at the same sensitivity level. At this sensitivity level, there is no evidence of clad roll. The first indication of sound penetration (Attachment 2, Figure B) appeared at 12db above the reference level when evidence of clad roll was detected.
$ 2. Surface Profile 4- The OD surface of the nozzle had an irregular contour which is typical oflarge
- cast products. Due to the surface contour, it was necessary to apply a lot of
! couplant to maintain contact with the examination surface. The irregular surface l and large amount of couplant required caused an apparent change in the sound a beam angle from point to point over the examination surface. Therefore, we could not determine where the sound beam was directed with respect to the inner radius.
i Conclusion Precise knowledge of the examination angle and a relatively high signal to noise ratio is required to obtain meaningful results when performing nozzle inner radius i examinations. When the beam angle varies it is not possible to locate indications or discriminate between flaws and geometry. Furthermore, it is not practical to design a search unit for examination when the beam angle changes from point to point around the nozzle. The North Anna Unit 2 channel head is a large cast product form. It is felt that the resulting low i
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Page 2 of 3 l l
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EELIEF REOUEST NDE-17 CONTINUED l signal to noise ratio and irregular surface profile make ultrasonic examination of i the nozzle inner radius section impracticable.
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 l 2-RC-E-1 A,-1B and -1C), the areas will be visually examined (VT-1) from the nozzle I.D.
using direct or remote techniques per the schedule shown in Table IWB-2412-1, j Inspection Program B.
j V. STATUS
- Granted - NRC Letter No.92-730 Dated 11/5/92.
Withdrawn - 5/8/96 No longer applicable to replacement Steam Generators 4
i 3
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i Page 3 of 3
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NDE-17 ATTACEMENT 3 Page 1 of 1 Et 0y. RE.CRLLY.D 14 - 2 EF 77.143 + 0.042 1.094 in/DIU h.
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First evidence l l of clad roll 0.......
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General noise l is abcJt 201 of full screen.
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tttt ttiI ttas fff1 1t!s!.eff 9Ie9 e. .e efff 9efe .9ga r1I14 D E P TN = 0 . 0 0 0 Rev. 4 1/1997 l
RELIEF REQUEST NDE-13 (REVISED)
.1. IDENTIFICATION OF, COMPONENTS
' System: Chemicaland Volume Control (CH)
Component: Regenerative Heat Exchanger (1-CH-E-3)
Connecting Circumferential Piping Welds i
(Drawing 12050-WMKS-CH-E-3) .
i Welds /Comoonents Descriotion ' CodeItem# .CJ;Lss 8 tubesheet-to-head . B2.60 1 10 tubesheet-to-head B2.60 1 12- tubesheet-to-head B2.60 1
- 2 circumferentialhead B2.51 1 4 circumferentialhead B2.51 1 6 circumferentialhead B2.51 1 13 nozzle-to-vessel B3.150 1 14 nozzle-to-vessel B3.150 1
- 15 nozzle-to-vessel B3.150 1 16 nozzle-to-vessel B3.150 1 17 nozzle-to-vessel B3.150 1 18 nozzle-to-vessel B3.150 1 13NIR nozzleinsideradius B3.160 1 14NIR nozzle inside radius B3.160 1 15NIR nozzleinside ralius B3.160 1 16NIR nozzleinside radius B3.160 1 17NIR nozzleinside radius B3.160 1 18NIR nozzleinside radius B3.160 1 19 termmal end weld B9.21 1 20 terminal end weld B9.21 1 21- temunal end weld B9.21 1 22 termmal end weld B9.21 1 WS-1 welded attachment B8.40 1 WS-2 welded attachment B8.40 1 WS-3 welded attachment B8.40 1 WS-4 welded attachment B8.40 1 WS-5 welded attachment B8.40 1 WS-6 welded attachment B8.40 1 1 circumferential hee:1 C1.20 2 3 circumferentialhead C1.20 2 5 circumferential head C1.20 2 7 tubesheet-to-shell C1.30 2 9 tubesheet-to-shell C1.30 2 11 tubeshect-to-shell C1.30 2 Page 1 of 6
. ~ ._ _._ _- _ _ . _ _ _ _ . . . _ . . _ . _ _ _ . . . _ . . _ . _ _ . _ _
i:
b RFrMREQUESTNDE-18 (REVISED) ,
L CONflNUED ,
(Drawing 12050-WMKS-011IST)
Welds /CompQncola Description CodeItemi Class f'
' l A' - terminal'end weld B9.21, I (Drawing 12050-WMKS-01112) 46 terminal end weld B9.21 1 p
-II. IMPRACTICAL CODEREQUIREMENTS t Examination Categories B-B, B-D (InWon Program B), B-H, B4, and C-A require that -t
[ volumetric and surface examinations be pdivin.ed as indicated by the Code item numbers above.
- . III. BASIS FORRFIM i
4 The regenerative heat exchanger (2-CH-E-3) provides preheat for the normal charging water going !
? into the Reactor Coolant System (RCS). The preheat is derived from normal letdown water coming i
from the RCS. Charging and letdown constitute the normal chemical and volume control within the
. RCS. The heat exchanger itselfis actually three heat exchangers in series interconnected with piping.
j_ This fact _was previously utilized in limiting examinations to one of the heat exchangers as allowed by the Code. The heat' exchanger has an outside'shell diameter of 9.55-inches The shells were l manufactured with ASTM A351 CF8 type material. The heads were manufactured with ASTM L ' A240 TP304 material. The 3 inch nozzle necks were manufactured with ASTM A182 F304 matenal. '
Until very recently the regenerative heat exchanger was entirely classified AShE Class 2 for inservice inspection activities. However, a reanalysis changed the classi6 cation of the letdown side of the heat
! exchanger to ASME Class 1. This action significantly increases the examination requirements
- - ' associated with this heat exchanger. Nozzles which were previously exempt under Class 2 ;
i requirements are now required to be exammed Additionally all Class 1 nozzles are required to be examined, and the examinations are not limited to one heat exchanger.
' The nozzle-to-vessel welds and nozzle inside radius sections for this vessel were not designed for ultrasonic examination from the outside diameter of the vessel. The small diameter of the vessel and nozzles along with the cast stainless steel vessel shell prevents a meaningful ultrasonic examination of
- these components l' The volumetric examination on the vessel head circumferential welds as required by the Code is limited due to the weld crown, radius of the closure caps, and the nozzles. The Code required !
e volumetric examination of the tubesheet welds is hmited by the weld crown and is obstructed by a support clamp. This clamp must be 1-l 4
Y k
Page 2 of 6 y
RELIEF REQUESTNDE-18 (REVISED)
CONTINUED
.- l mechanically removed prior to the welds' examination. Additionally weld 12 is partially obscured by I' the six integral attachments which are themselves butted up against a clamp. It is estimated that between 21 and 42 percent of the umaferential welds could be examined, and 42 percent of the tubesheet welds could be examined, if the clamps are removed. Weld 12 would be significantly less due to the integral attachment location. Previous partial examinations completed on these welds have identified no problems.
An ALARA evaluation has been conducted on each ' activity associated with these exammations. A -
tab:e is provided documenting these results.' It is estimated that more than 32 man-rem will be required to complete these examinations over the interval. This estunate assumes optimum inspection and preparation times.' If difficulties are encountered, a corresponding increase in dose would be expected. Shielding is not considered practical since the source of radiation is the component j receiving the exammations. Considering the examination limitations previously discussed, expending l this much dose is deemed impractical.
This relief request was originally submitted by letter Serial No.93-018, dated February 16,1993.
The relief was granted ("provided that the lower regenerative heat exchanger receives the Code-required examinations to the extent possible") by letter dated August 7,1995, and its associated safety evaluation report. This request is being revised to add four of six tenninal end piping-to-vessel welds which are required to be selected for examination under Category B-J note 1(a) under item B9.21. These welds were omitted from the original request and need to be addressed in this relief request in addition to those already evaluated. New survey maps of the regenerative heat exchanger indicate higher dose rates than previously estimated (survey attached).
Performing these surface examinations would result in approximately 10.5 man-rem of exposure and would negate, to a large degree, the exposure reduction of the original relief request. This is due to the close proximity of the regenerative heat exchanger to these welds and the need for scaffolding and insulation removal, which were previously elinunated for the regenerative heat exchanger in our original reliefrequest.
L e
Page 3 of 6
_ _ _ - - _ _ _ . _ _ _ _ __ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ~ _ . _ _. . _ _ _ . _ _ _ __.
1 RFIN REQUEST NDE-18 (REVISED)
CONTINUED
- . IV. ALTERNATE REQUIREMENTS i Technical Specifications require that the RCS Leak R*.te be limited to 1 gallon per minute
- unidentified leakage. This value is calculated every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in accordance with Technical Specification requirements. Additionally, the containment atmosphere particulate radioactivity is
, monitored every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Technical Specification requirements. As a result, new leakage is
! rapidly identified and located during operation. Leakage identified from these components can be j easily isolated by two upstream valves with manual operation from within the control room. The -
valves also receive an automatic control signal to close on inventory loss based on pressurizer level.
However, these valves could not be used as the Class 1 boundary valves due to their nonsafety- l related a.tuation. Correspondingly, as a result of the reclassification to Class 1, these components l will receive a system leakage test prior to start up after each refueling outage. During this system )
leakage test the components will receive a visual (VT-2) exammation. The support structures will j receive a visual (VT-3) examination to the extent required by the Code without insulation removal.
Your evaluation of our original relief request, dated August 7,1995, added alternative requirements.
The appropriate portion of the Technical Evaluation Report states:
The licensee stated that previous partial examinations have been completed on these welds.
Consequently, it is concluded that a best-effort volumetric examination of the lower RHX, in addition to system radiation monitoring and the Code-required visual exammations, would provide reasonable assurance of the system's inservice structural integrity. Therefore, it is recommended that relief be granted, pursuant to 10 CFR 50.55a(g)(6)(i), provided the lower RHX vessel receives Code-required volumetric examinations to the extent possible.
We also request that this philosophy ofinspection be extended to the vessel-to-piping termmal end welds on the regenerative heat exchanger (RHX) The two lower RHX vessel-to-piping terminal end welds (22 & 46) will be examined by the surface method as required by the Code.
V. STATUS Pending - Virginia Power Letter No.96-032 Dated 2n/96 l
l Page 4 of 6 ]
i
. RFJIW REQUEST NDE-18 (REVISED)
CONTINUED 2-CH-E-3 EXAMINATIONS MAN-REM ESTIMATE WorkT=* Man-Hours (hrs) Dose Rate (R/hr) Man-Rem i Insulation Remove / Install 5.3 0.500 2.650 Scaffolding _
l Install / Remove 0.0 0.000 0.000 Clamp j Remove / Install 2.0 1.000 2.000 l Weld Prep. 3.5 1.000 3.500 HP Coverage 36.0 0.'610 0.360 Nozzle-to-Vessel Inspection (UT) 8.1 1.000 8.100 1
NozzleId.de Radius l Inspection (UT) 6.6 1.000 6.600 Circumferentialffubesheet Inspection (UT) 5.3 1.000 5.300 Welded Attachment Inspection (PT) 3.0 1.000 3.000 TotalEstimate = 32.305 Page 5 of 6
1 RELIEF REQUESTNDE-18(REVISED)
CONTINUED J
., NORTH ANNA UNIT 2 2-CH-E-3 PIPING TERMINAL ENDS ;
EXAMINATIONS MAN-REM ESTIMATE i l 6 TerminalEnd Welds Work Task Man-Hours (hrs) Dog Rate (R/hr) Man-Rem j
d Insulation Remove / Install 2.0 2.0u0 4.0 i e
Scaffolding Install / Remove 1.0 1.500 1.5 3
Weld Prep. 1.0 2.000 2.0 l PT Exam 6 Welds 1.5 2.000 3.0 i
i TotalEstimate = 10.5 t
4 i
Page 6 of 6
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JOB MAN-REM PROJECTION DATE: 12/04/92
, A: ARA EVALUATION NUMB,ER: UNIT # 2
- JOB DESCRIPTION: ISl/NDE REGEN HEAT EXCHANGER INSPECTIONS WORK ' MAN DOSE MAN-REM / TASK TASK GROUP HOURS RATE WORKGROUP TOTAL 4
TOP Hx: ISI/NDE
- UT (2) NOZ TO VESSEL WELDS 2.7 1.000 2.700
- UT (2) INNER RADIUS WELDS 2.2 1.000 2.200 MID Hx:
- UT (2) NOZ TO VESSEL WELDS ' 2.7 1.000 2.700 l
- UT (2) INNER RADIUS WELDS 2.2 1.000 2.200 BOTTOM Hx:
- UT (2) NOZ TO VESSEL WELDS 2.7 1.000 2.700
- UT (2) INNER RADIUS WELDS 2.2 1.000 2.200
- UT (4) CIRCUMFERENTIAL WELDS 5.3 1.000 5.300
- PT (6) WELDED ATTACHMENT LUGS 3.0 1.000 3.000 23.000 SUPPORT ACTMTIES:
- INSUL. RMVUINSTALL INSUL 5.3 0.650 3.445
- SCAFFOLDING INSTALURMVL CARP. 0.0 0.000 0.000
- WELD PREP PF 3.5 1.000 3.500
- HP COVERAGE HP 36.0 0.010 0.360
- (3) CLAMP RMVUINSTALL PF 2.0 1.000 2.000 9.305
. NOTE. UT INSPECTION FOR CIRCUMFERENTIAL WELDS INCLUDE (3) PASSES: 0,45, AND 60 DEGREES l
MAN-REM TOTAL 32.305 REM MAN-HOUR TOTAL 70 HOURS
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i A
e RELIEF REOUEST NDE-19
- f. - I. - IDENI1FICATION OF COMPONENTS a
Mark / Weld # Line# Drawinn# Class 1 - 12050-WMKS-RC-R-1.2 1
- 10 6"-RC-439-1502-Q1 12050-WMKS-RC-E-2 1
'4 31"-RC-402-2501-Ql 12050-WMKS-0109E-1 1 5 . 31"-RC-402-2501-Q1. 12050-WMKS-0109E-1 1 SW-79 32"-SHP-401-601-Q2 12050-WMKS-0101B 2 i SW-80 32"-SHP-401-601-Q2 . 12050-WMKS-0101B 2 l
- SW-88 32"-SHP-401-601-Q2 12050-WMKS-0101B 2 l
! - SW-89 32"-SHP-401-601-Q2 12050-WMKS-0101B 2 !
1 57H 16"-WFPD-424-601-Q2 12050-WMKS-0102A 2 i 59H 16"-WFPD-424-601-Q2 12050-WMKS-0102A 2 12050-WMKS-CH-P-1B WS-1 2 I WS-2 12050-WMKS-CH-P-1B 2
! WS-3 12050-WMKS-CH-P-1B 2
! WS-4 12050-WMKS-CH-P-1B 2 4A 12050-WMKS-0104DA 12"-RS-408-153A-Q2 2 l ;
i- SW-58 8"-QS-403-153A-Q3 12050-WMKS-0107D ' 2
' SW-76 3"-SI-423-1502-Q2 12050-WMKS-0111 AAJ 2 22 3"-CH-402-1502-Q2 12050-WMKS-0111 AAM 2 LS-5 12050-WMKS-SI-P-1A 2 IL IMPRACTICABLE CODE REQUIREMENTS i- The 1986 Edition of ASME Section XI in tables IWB-2500-l' and IWC-2500-1 does not
! allow any limitations to the required volumetric and surface exammations. Code Case N-460,
- - Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage,ifitisless than 10%.
L III. BASIS FOR RELIEF l
i The components listed above have been examined to the extent practical as required by the
- Code. Due to interferences of other components or weld joint geometry the reduction in 3 - coverage for the listed components was greater than 10%. Tables NDE-19-1, 2, 3a and 3b are ,
[ - provided detailing the hmitations experienced. Amplifying sketches are also provided.
Altemative components could not be substituted for examination due to the mandatory i . selection requirements of the Code, or W- of the prorated selection criteria for piping in Category C-F-1 (Note 2).
Page 1 of 6 4
4 I
. _ - - - - _ _ _ - -- ,-------n . _ _ -, , -n -- , ~ <
RELIEF REOUESTNDE-19 Continued IV. ALTERNATE PROVISIONS It is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements.
V. STATUS Granted - NRC Letter No.95-429 Dated 8/8/95.
o I
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Table NDE-19-1 North ~ Anna Unit 2 -
Examination Coverage Estimates (Vessel)
Category B-A, Item Bl.40 Mark /tdeldt Beam Angle Exam Area Scan Direction 4 Exam Reason For Partial Sketch 6 1 0 Held s Base - 12 Froximity To Flange 1 141d 2 13 And Lifting Lug -
to to 120 45 degrees) 45 Held -5 57 Interference
- 45 Weld 7 99 9 8 99 .'
45 Weld 60 Held 2 7 60 weld 5 98 i 60 Wald 7 99 60 Weld 8 99 45 s 60 Base 2 36 45460 Base 5 91 45460 Base ~7 60 45 s 60 Base 8 Es ,
i UT scan Direction Definitions 2 - Anlat scan flange side of weld 5 - Axial scan head side of wld
? - Ciretualerential scan, clockwise flooking down on head) ,
8 - Circumferential scan, counterclockwise (looking down on head) r 4
1 i
Page 3 of 6
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. Table NDE-19-2
' North Anna Unit 2 Examination Coverage Estimates . (Vessels)
Category B-D, Item B3.110 Markoteldi Beam Angle Exam Area scan Direction i Enam Reason For Partial Sketch 0 10 0 Weld a Base - 80 Nozzle Geometry, . 2 45 Weld 2 85 Cladding Frevents 45 Weld 5 . 25 Extended V-path 45 Weld 7 100 45 Weld 8 100 i
60 Weld 2 90 60 Weld 5 15 60 Weld 1 100 60 Weld 8 100 45 a 60 Base 2 80
- 45 a 60 Base 5 35 45 a 60 Base 7 65 45 a 60 Base 8 65 UT Scan Direction Definitions 2 - Axial sean eessel side of weld 5 - Antal scan nozzle side of weld 1 - Circumferential sean, clockwise when looking in direction of 1semetric flow (weld count) 8 - Circumferential scan, counterclockwise when looking in direction of isometric flow tweld count)
' Page 4 of 6 -
Table NDE-19-3a North Anna Unit 2 Examination Coverage Estimates (Piping & Integral Attachments)
UT Scan Coverage 4 Surface Mark / Weld 8 Category item 8 2, 5, 7 8 Coveraget Reason For Partial Sketch 8 -
4 B-F BS,70 22 100 100 100 'N/A No2 Ele s Weld Crown 3-Geometry, Material Attenuation Prevents Extended V-path i 5 B-F B5.70 100 22 100 100 N/A - Nozzle s Weld crown 3 Geometry, Naterial Attenuation Prevents
- Extended V-path ,,.
SW-19 C-C C3.20 N/A 50 Sopport configuration 4 SW-80 C-C C3.20 N/A 50 Support configuration 4 SW-89 C-C C3.20 N/A 50 Support Configuration 4 SM-89 C-C C3.20 N/A 50 Support configuration 4 57H C-C C3.20 N/A TO Welded Pips Connection 5 Jnterference 59H C-C C3.20 N/A 70 Welded Pipe Connection 5 Interference Ws-i C-C C3.20 N/A $3 Support Configuration 6 WS-2 C-C C3.20 N/A TO Support Configuration 6 WS-3 C-C C3.20 N/A 93 Support Configuration 6 WS-4 C-C C3.20 N/A 03 Support Configuration 6
. UT Sc.an Direction Definitions 2 - Axial scan, 190 degrees from isometric flow direction (weld count).
5 - Aslal scan, the same direction as the isometric flow (weld count).
7 - Circumferential scan, cibekwise rotation when viewing in the direction of isometric flow.
8 - Circumferential scan, counterclockwise rotation when viewing in the direction of isometric flow.
1 Page 5 of 6 l t
t - _ _ _ _____ __ -_ _ _ _ _ _ _ _ _ _ _ _ =.a______ -. = - . + ,e e w aw
%c-Table NDE-19-3b North Anna Unit 2 Examination Coverage Estimates --(Piping &- Integral Attachments)
UT Scan Coverage 4 Surface . _
Mark /Weldt Category Item 8 2 5, 7' 8, . Coveragel meason For Part.1A_ Sketcht 4A C-F-1 C3.11 16 76* 100 100 N/A Interference Frase Two 7 Socket Welds SW-50 C-F-1 C5.11 81 81* 90 90 N/A Interference Train - 8 Adjacent Socket Welds SW-76 C-F-1 - C5.11 70 70* -100 100 N/A Interference Froen 9 Adjacent Socket Weld 22 C-F-1 C5.11 83 83* 100 100 . N/A Valve To Tee Joint 10 Configuration LS-5 C-ti C6.10 N/A 78 . Pump Mount 11 -
Interference
- - Extended V-path from 2 scan used.
Uf Scan Directica Definitions 2 - Azlal scan, 180 degrees frere isometric flow direction tweld countl.
3 - Axial scan, the same direction as the isometric fled tweld count).
7 - Circuaterential scan, clockwise rotation when viewi".g in the direction of isosmetric flow.
8 - Circumferential scan, counterclockwise rotation when viewing in the direction of isometric flow.
I f
Page 6 of 6 4
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RELIEF REOUESTNDE 20 I. IDENTIFICATION OF COMPONENTS Mark / Weld # Linrl_d Drawinr# Can Skach 1 CH-E-2 12050-WMKS-CH-E-2 2 1 2 CH-E-2 12050-WMKS-CH-E-2 2 1 14 RC-E-2 12050-WMKS-RC-E-2 1 2 WS-2 RH-E-1B 12050-WMKS-RH-E-1B 2 3 SW-11 14"-RH-401-1502-Q1 12050-WMKS-109E-2 1 4 SW-12 6"-RC-416-1502-Q1 12050-WMKS-109E-2 1 4 SW-41 6"-RC-422-1502-Q1 12050-WMKS-109E-2 1 4 SW-43 6"-RC-417-1502-Q1 12050-WMKS-109E-2 1 4 SW-42 4"-RC-414-1502-Q1 12050-WMKS-109E-2 1 5 II. IMPRACTICABLE CODE REQUIREMENTS The 1986 edition of ASME Section XI in Tables IWB-2500-1 and IWC-25f 0-1 does not allow any limitations to the required volumetric and surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage,ifit is less than 10%. III. BASIS FORRELIEF The components listed above have been exammed to the extent practical as required by the Code. Due to interferences of other components or weld joint geometry the reduction in coverage for the listed components was greater than 10%. Tables NDE-20-1,2, 3, and 4 are provided detadmg the limitations experienced. Amplifying sketches are also provided. Alternative components could not be substituted for exammation due to the mandatory selection requirements of the Code. IV. ALTERNATE PROVISIONS It is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements. V. STATUS Granted - NRC Letter No. 95-429 Dated 8/8/95. Page 1 of 5
Table NDE-20-1 North Anna Unit 2' Examination Coverage Estimates (Class 1 Vessels) Category B-D, Item B3.110 Mark / Weld # Beam Angle Exam Area S_can Direction % Exam Reason For Partial- Sketch # 14 0 Weld & Base - 60 Nozzle Geometry and 2 45 Weld 2 80 Cladding Prevents 45 Weld 5 5' Extended V-Path 45 Weld 7 74 45 Weld 8 74 -I 60 Weld 2 95 60 . Weld 5 2 60 Weld 7 74 60 Weld 8 74 45 & 60 Base 2 88 45 & 60 Base 5 11 45 & 60 Base 7 50 45 & 60 Base 8 50 UT Scan Direction Definitions , 2 - Axial scan flange side of weld 5 - Axial scan head side of weld 7 - Circumferential scan, clockwise (looking down on head) 8 - Circumferential scan, counterclockwise (looking down on head) Page 2 of 5 I
. . _ . _ . _ _ _ _ . ...____._________.________________________..______________._._______m - - _ - - -
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Table NDE-20-2 North Anna Unit 2 Examinatior Coverage Estimates (Class-1 Piping) Category B-J, Item Number B9.31 UT Scan Coverage % Surface Drawing Mark / Weld # Category Itemli 7 8_ Coverage % Reason For Partial Sketch # 2_ 5_ 109E-2 SW-11 B-J B9.31 0 90 27 27 100 Branch Connection 4 109E-2 SW-12 B-J B9.31 90 0 27 27 100 Branch Connection: 5-B9.31 90 0 27 27 100 Branch Connection S 109E-2 SW-41 B-J 109E-2 SW-42 B-J B9.31 53 27 50 50 100 Branch Connection 6 109E-2 SW-43 B-J B9.31 90 0 27 27 100 Branch-Connection S UT Scan Direction Definitions 2 - Axial scan, 180 degrees from isometric flow direction (weld. count). 5 - Axial scan, the same direction as the isometric flow (weld count). 7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow. 8 - Circumferential scan, counterclockwise rotation when viewing in the direction of isometric flow. Page 3 of 5
t Table NDE-20-3 North Anna Unit 2 - Examination Coverage Estimates (Class-2 Vessels)- Category C-A, Item Number C1.20-UT Scan Coverage % .
^
Drawing Mark / Weld # Category Item # 2 5 1 8 Reason For Partial- Sketch # CH-E-2 1 C-A C1.20 100-100 76 76 Support Lugs 1-C1.20 87 76 -91 91 Support Lugs 1 -- 'CH-E-2 2 (45 Scan) C-A
- 2 (60 Scan) 87 86 i i
i UT Scan Direction Definitions 1 i 2 - Axial scan, head side of weld i 5 - Axial scan, flange side of weld 7 - Circumferential scan, clockwise (looking down on head)- 8 - Circumferential scan, counterclockwise (looking down on head)_ ; i Page 4 of 5 ; i k
+
Table NDE-20-4 - North Anna Unit 2 Examination Coverage Estimates (Integral Attachments) Category C-C, Item Number C3.20 Drawing Mark / Weld # Category Item #' Surface Coverage % Reason For Partial- < Sketch # 76% Concrete Support ilmits 3 RH-E-1B WS-2 C-C C3.20 l i m i t s - a c c e s s -.- I 4 e h t Page 5 of 5
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t RELIEFREOUESTNDE-21 . I. IDENTIFICATION OF COMPONENTS Class 1,2, and 3 Integrally Welded Attachments II. IMPRACTICABLE CODE REQUIREMENTS ~ E-isiistion Categories B-H, B-K-1, C-C, D-A, D-B, and D-C of ASME Section XI,1986 Edition, with regard to Integrally Welded Ate =dw-s. i III. BASIS FORRELIEF Code Case N-509, Alternate Rules for the Selection and Examination of Class 1, 2, and 3 Integrally Welded Attedww.iits, Section XI, Division 1, is not currently approved by
. Regulatory Guide 1.147 for use. 10 CFR 50.55a(a)(3) footnote 6 notes that the use of other Code Cases may be authorized by the Director of the OfHee of Nuclear Reactor Regulation upon request pursuant to 10 CFR 50.55a(a)(3). As such, Code Case N-509 is requested for use on North Anna Unit 2 in the second inspection interval The current Code requires a certain size base material design thickness before examination is required on Class 1 or 2 integrally welded attadw-is. This size limitation apparently arbitrary with no technical basis. The current Code also has no inspection requirements for .
Class 1 integrally welded httachments for piping, pumps, and valves (B-K-1) for the third inspection interval of Inspection Program B (North Anna's). Additionally, there is no selection' criteria for Class 3 nonexempt integrally welded attachments, requiring 100% examination. These de6ciencies have been corrected in Code Case N-509. IV. ALTERNATE PROVISIONS Code Case N-509 will be used in its entirety. Code Case references to the 90 Addendum of ASME Section XI are the same as the provisions in Code Case N-491, which has been implemented by our support program. V. STATUS Granted with conditions - NRC Letter No. 95-429 Dated 8/8/95. Granted provided 10% of all non-exempt Code Class 1,2, and 3 integral attachments are examined Page 1 of 1 f
. , . - .r - --.- - _ . ., - , , . ., - -..-r
l PFIM REOUESTNDE-22
- 1. IDENTIFICATION OF COMPONENTS prawing Line # Weld # Cal.
12050-WMKS-RC-E-1 A.2P . 29"-RC-401-250lR-Q1 _N-SE3 IIN B-F 12050-WMKS-RC-E-1A.2P 31"-RC-402-250lR-Q1 N-SE291N - B-F 12050-WMKS-RC-E-1B.2P 29"-RC-404-250lR-Q1 N-SE311N B-F 12050-WMKS-RC-E-1B.2P 31"-RC-405-250lR-Q1 N-SE291N B-F 12050-WMKS-RC-E-1C.2P 29"-RC-407-2501R-Q1 N-SE3IIN B-F 12050-WMKS-RC-E-1C.2P ' 31"-RC-408-2501R-Ql N-SE291N B-F , H. IMPRACTICAL CODEREQUIREMENTS ASME Section XI,1986 Edition, requires full coverage of the lower 1/3t volume of B-F welds as depicted on Figure IWB-2500-8. Code Case N-460, Altemative Exammation Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, ifit is less than 10%. l III. BASIS FORRELIEF i The Category B-F welds listed above are the r.ezie-to-safe end welds on the replacement steam generators for North Anna Unit 2. The extent of examination for the axial scans'from the nozzle side of the weld was limited as depicted on Figure NDE-22-1. The limitation was caused by the nozzle outside : radius which restricts movement of the transducer on the nozzle side of the weld. The Category B-F welds listed above were exammed with focused dual element longitudinal wave transducers. The use of focused longitudinal waves was necessary because the weld joint is carbonfmconel/ stainless design. The size of the search unit that can be used is dictated by focal length and frequency required to examme the particular weld thickness. The smallest practical size search unit possible was used to conduct the above examinations. As shown by Figure NDE-22-1,100% of the required volume was examined in the axial direction from the safe end side of the weld and in both circumferential directions. It is not possible to extend the beam path to examine the weld in two directions from one side of the weld due to the necessity to use focused longitudinal waves to obtain a meaningful examination of the welds. No other. supplemental ultrasonic means of examination is practical to examine additional weld volume for the Category B-F welds listed above. Page i page 2 1
FFT TEF REOUEST NDE-22 Continued IV. ALTERNATE PROVISIONS It is proposed that the Category B-F examinations already completed at the reduced coverage be counted as meeting the Code requirements for preservice inspections as well as future inservice i inspections. V. STATUS fl i '- l I Granted - ViriiuJ. Power Letter No. 96-041 Dated 1/17/96. 1 j i l l I 1 Page 2 page 2 .
i l 2 RELIEF REOUEST NDE-23 j. I. IDENTIFICATION OF COMPONENT Mark / Weld # Lind Drawinn# CJan i 26 3"-SI-417-1502-Ql . 12050-WMKS-103BV 2 II. IMPRACTICABLE CODEREQUIREMENTS i ) The 1986 edition of ASME Section XI Table IWC-2500-1, examination category C-F-1, item number C5.21 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, ifit isless than 10%. III. BASIS FOR RELIFF The component listed above is a three inch pipe to tee weld. This component has been examined to the extent practical as required by the Code. The Code required volumetric examination coverage was reduced due to interferences from an adjacent pipe. The extent of volumetric examination which was completed is detailed in Table NDE-23. An extended beam path was used to examine the component in the tangential direction from the pipe side. The required surface e :nination had no limitations. Figure NDE-23-1 is provided detailing the limitations experienced. IV. - ALTERNATEPROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting I the Code requirements. V. STATUS 16(/ Granted - %L Fuwer Letter No. 96-549 Dated 10/10/%. Page 1 of 2
' Table NDE-23-1 North Anna Unit 2' Examination Coverage Estimates 12050-THCS-103BV Category C-F-1, Item C5.21 UT Scan
- Coverage 4 Serface Examination
- 5 8 Coverage 4 peason For Partial ,.
Mark /Weldt 2, 7 . 26 85.2 85.2 100 100 100 An adjacent pipe prohibits the 2 and 5 scan for 1.625 inches cut of 11 1menes. UT Sean Direction Definitions > 2 - Antal scan, 180 degrees from isometric flow direction. ' 5 - Asial scan, the same direction as the isometric flow. 7 - Circumferential scan, clockwise rotation h viewtog in the direction of isometric flow. 9 - Circumferential scan, counterclockwise rotation een vie' tag in the direction of isometric flow. t k l t Page 2 of 2 ,
.. g . .
3 -SI-457-l.502-01 LADJ ACENT BU I 'NO T -6 INTERSECTING. PIPE 1RUN-i NOT SHOWN ON 12050-Ut1KS-103BV - 3 -SI-417-1502-01 .,
+ 5 SIDE '2 SIDE F L OW->
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WELD.26 j 1: .625" OUT OF 1 I . -l RESTRICTED BY
- 3"-SI-457-1 502-01 ]
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2 -SI-453-1502-01 ! , A_n l e Figure N DE 1 II j 12050-Wr1KS-l 03BV WELD 26. A _ _ _ . . _ _ . _ _ _ [
d r 6 J ~
. RMI TFF REOUEST NDE-24 i ,
- I. IDENTIFICATION OF COMPONENT L
jr Mark / Weld # - Liud Drawing # Gaas
. SW-23 6"-RC-418-1502-Ql . 12050-WMKS-109F-2-- 1
- SW 12"-RC-423-1502-Q1 12050-WMKS-109F-2 1 SW-45 6"-RC-419-1502-Q1 12050-WMKS-109F-2 i II. IMPRACTICABLECODEREQUIREMENTS The 1986 edition of ASME Section XI Table IWB-2$00-1, examination category B-J, item .
i number B9.31 does not allow any limitations to the required volumetric or surface examinations. i- ~ Code Case N-460, Altemative Emidi don Coverage for Class 1 and Class 2 Welds, allows a - reduction in coverage, ifit is less than 10%. . III. BASIS FOR RELIEF 4 The components listed above have been examined to the extent practical as required by the Code. The Code required volumetric examination coverage was reduced due to nozzle configuration, ;
- weld joint geometry, and the material type from which the components are consuucted. The scope I of volumetric examination overage completed for the above listed welds is listed in Table NDE-l
!. 24-1. The required surface examinations had no limitations. Figure NDE-24-1 is provided detalhng the limitations experienced Altemative components could not be substituted for j exanunation due to the mandatory selection requirements of the Code. i IV. ALTERNATE PROVISIONS l- It is proposed that the exammations already completed at the reduced coverage be counted as meeting the Code requirements. 7 V. STATUS !: IJC ^j Granted - VuyJ.Tseer Letter No. 96-549 Dated 10/10/96 l 1 l ? Page 1 of 2 t. 1 m , +- ~ . , - - -
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Table NDE-24-l' , North Anna Unit 2 Examination' Coverage Estimates' 12050-MMKS-109F-2 Category B-J,' Item B9.31 1 UT Scan Coverage t Surf ace Examination Mark / Weld 8 2 5 7 $_ Coverage t meason IFor Partial ,I SW-23 90 0 28 28 100 Nozzle a weld joint configuratlon and materlat type, ASTM A-351 austenitic steel casting, limit the use of an extended V-path examination. Due to . change in ccaliguration around the nozzle the percent of volume varied around the circumference f remi 60s at 0* and ISC* to 90% at 90* and 270*. Approximately 80% of the lower 1/3 was covered in the 2 direction. SW-43 83 0 20 28 100 Nozzle a weld joint configuration and material type, ASTM A-351 austenttic steel casting, limit the use of an extended V-path naekination. e Due to change in configuration around the nozzle the percent of volume varied around-the circumference front $2% at 0* and 100* to 634 at 90' and 270*. , Approminately 83% of the lower 1/3 was covered in the 2 direction, su-45 76 0 to 28 100 Nozzle a weld joint configuration and material type, ASTM A-351 austenttle steel casting, 11mit the use of an entended V-path esamination. Due to change in configuration around the nozzle the percent of volume varied around , the circumference f rom 564 at O' and 100* to 924 at 90* and 270*. Approximately 76% of the lower 1/3 was covered la the 2 direction. UT scan Direction Definitions 2 - Antal scan, 160 degrees from isometric flow direction. 5 - Axial scan, the same direction as the isometric flow.
? - Circumferential scan, clockwise rotation toten viewing in the direction of isometric flow.
8 - Circumferential scan, counterclockwise rotation when viewing in the direction of isometric flow. s t t t Page 2 Of 2 f
. . , _ . , . . . _ ~ _ . - . - . . . . _ .. _ _.... ._. . . _ . _ . . . . _ . _ . - .
6 -RC-418-1502-01 iSW-231 12 -RC-423-1502-01 ! ISV-431 FLOW I i 6 -RC-419-1502-01 isv-4si \
%U TYPICAL SW-23, SV-43
' ' AND SW-45 l 5 SIDE 'N0ZZLE I80 o 2 SIDE 29 -RC-404-250i R-01 k
( SW-231 2 SIDE 27 1/2*-RC-406-2501 R-QI FLOV iSv-43 a Su-45) 4 1 L V t //A i rigure \ J E-2' 12050-Ut1KS-109F_-2 SV-23, SV-43, & SW-45 b k
. _ ~ _ . _ ._ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _. . .
RELIEF REOUEST NDE-25 1
- 1. IDENTIFICATION OF COMPONENT Mark / Weld # Drawinn# Qass l 2 12050-WMKS-RH-E-1A 2 H. IMPRACTICABLECODEREQUIREMENTS j 3
The 1986 edition of ASME Section XI Table IWC-2500-1, examination category C-A, item l number C1.10 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Altemative Examination Coverage for Class 1 and Class 2 Welds, allows a
)
reduction in coverage, ifit is less than 10%. , l III. BASIS FORRELIEF The component listed above has been examined to the extent practical as required by the Code. This examination was limited due to interferences from saddle plates around the inlet and outlet nozzles. The weld was examined with a 45* transducer and a 60 transducer. An extended beam path was used with both transducers. The reduction in coverage of the volumetric examination is detailed in Table NDE-25-1. Figure NDE-25-1 is provided detaihng the hmitations experienced IV. ALTERNATE PROVISIONS It is proposed that the examination completed at the reduced coverage be counted as meeting the Code requirements. V. STATUS Ji M, l Granted - Vop .I' ewer Letter No. 96-549 Dated 10/10/% 1 I Pope 1 of 2 l I
I 1 J Table NDE-25-1 North Anna-Unit 2
. Examination-Coverage Estimates 12050-WMKS-RH-E-1A Category-C-A, Item C1.10 UT scan Coverage t Markosoldt 2 5 7 0, Peason For Partial 2 91.2 91.2 100 100 Saddle plates for the inlet and outlet nozzles 11 alt the 2 and 5 scan for 25.6 inches out of it .94 inches. An extended beam path was used for the examination.
UT Scan Direction Definitions 2 - Axial scan head side of weld 5 - Axial scan vessel side of weld 1 - Circumferential mean, clockwise when looking down on the vessel 9 - Circumferential scan, counterclockwise e en looking down on the vessel Page 2 of 2
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RFLTFF REOUEST NDE-26 I. IDENTIFICATION OF COMPONENT Mark / Weld # Lind Drawinn# Class
- SW-14 6"-RC-438-1502-Ql 12050-WMKS-110A-1 1 SW-19 6"-RC-439-1502-Q1 12050-WMKS-110A-1 1 . II. IMPRACTICABLE CODE REQUIREMENTS The 1986 edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.11 does not allow any hmitations to the required volumetric or surface examinations. Code Case N-460, Alternative Ewrietion Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if ,
it is less than 10%. III. BASIS FORRELIEF l The components listed above have been examined to the extent practical as required by the Code. Due to a 3.5 inch diameter branch connection located in the at the center line of each weld only 83.3% of the j required volume and surface of each weld was cardisi. The reduction in coverage is detailed in Table - NDE-26-1. Figure NDE-26-1 is provided detadmg the hmitations expenenced These welds are required
. to be examined as part of an augmented inspection program. Performing additional examinations on welds which would allow greater coverage would require additional radiation dose and expense with very littleincrease safety; l
IV. ALTERNATEPROVISIONS i 1t is proposed that the examinations already completed at the reduced coverage be counted as meeting l the Code requirements. l 1 V. . STATUS
)ib I Granted - Virgin}ai Power-LetterNo. 96-549 Dated 10/10/96
]
i Page 1 of 2
Table NDE-26-l' North Anna Unit 2 Examination Coverage Estimates 12050-WMKS-110A-1 Category B-J, Item B9.11 UT Scan Coverage 4 Surface Examination Mark / Weld 8 2 5 '1 8 Coversee 4 Reason For Partial ,I SW-14 83.3 83.3 83.3 83.3 83.3 Branch connection restricts 3.5 inches out of 21 inches. i SW-19 83.3 83.3 '83.3 83.3 83.3 Branch connection restricts 3.5 inches out of 21 inches. UT Sean Direction Defint*lons 2 - Axial scan, 180 degrees from isometric flow direction. 5 - Axlal scan the same direction as the isometric flow. 7 - Cirewaferential scan, clockwise rotation een viewing in the direction of isometric flow. 8 - Circumferential scan, counterclockwise rotation e en viewing in the direction of isometric flow. ; 6 i Page 2 of 2
6"-R C - 438- 1 502-01 (SV-1 41 l 6"-R C - 439- 1 502-01 (SW-19)
! l SW-14 SW-19 SOCKET WELD 3.5" DI ANETER I 2050-WNKS-l l OA-1 SW-14 & SW-19 rigure \ J 26
_ _ _ - . . _ _ _ _ _ _ - _ _ _ _ _ _ - - _ _ _ _ _ _ _ . . - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ - _ _ _ _ _ _ - - _ _ - - _ _ - _ - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ - _ _ - - - _ _ _ - _ - _ _ - _ _ _ _ _ _ _ _ _ _ - - _ - _ - _ _ - _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ =
RELIEF REOUESTNDE-27
.I. IDENTIFICATION OF COMPONENT Mark / Weld # Line# Drawing # Qus SW-16 6"-RC-438-1502-Q1 12050-WMKS-110A-1 1
, SW-24 6"-RC-439-1502-Q1 12050-WMKS-110A-1 1 II. IMPRACTICABLE CODE REQUIREMENTS The 1986 edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.11 does not allow any limitations to the required volumetric or surface exammations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, ifit is less than 10%. III. BASIS FOR RELIEF The components listed above have been examined to the extent practical as required by the Code. Due to l interference by an existing pipe support, only 6 inches out of 21 inches were examined. The reduction in coverage is detai'ed in Table NDE-27-1. Figure NDE-27-1 is provided detathng the limitations ; experienced. These welds are classified as terminal ends and are required to be exammed by the ISI Program. l IV. ALTERNATEPROVISIONS It is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements. V. STATUS
') : 1.
Oranted - WE Pctsr Letter No. 96-549, Dated 10/10/96 l l l l Page 1 of 2
. . . . _ , . . - . ~ . .. .. .. . .-. - , .
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.a; Table NDE-27-1 North Anna Unit 2 Examination Coverage Estimates 12050-WMKS-110A-1 Category B-J, Item B9.11 UT Scan Coverage 9 Surface Examination ,
Reason For Partial ,a Mark / Welds 2, 5 7 8, coverage 9 sW-16 29 29 29 29 29 Pipe support limits examination to 6 laches out of 20.8 laches. , l SW-24 29 29 29 29 29 Pipe support limits eramination' to E inches out of 20.8 inches. l , UT Scan Direction Daflattions 2 - Axial scan, 180 de9rees from isometric flow direction. 5 - Antal scan, the s m direction as the ison tric flow. 1 - Circumferential scan, clockwise rotation wher; viewing in the direct 16s if isometric flow. 8 - Circumferential scan, counterclor.kwise rotation when viewing in the direction of isometric flow. f Page 2 of 2 __- __ _ _ _ _ . _ _. . _ . _ _ . _ _..- _ _ _ _ . _ _ _ _ _ _ _ _ _ - m _ . _ __ .
~~
790 N S ~ ~, 7-W; l 6* SUPPORT ENCIRCLES 270 DEGREES
. l, 6"-RC - 438-1502-01 (SV-l 6) '
6 -RC-439-1502-01 iSW-24) l SUPPORT 1 i 12050-WP1KS-11 OA-1 SW-16 & SW-24
- icure N _ _1 - 2 7 ,
t t
4
)
RELIEFREOUESTNDE-28 l
~~I. . IDENTIFICATION OF COMPONENT Mark / Weld # Line# Drawina# Class 11 6"-RC-438-1502-Q1 12050-WMKS-RC-E-2 1 12 6"-RC-437-1502-Q1 12050-WMKS-RC-E-2 1
, II. IMPRACTICABLECODEREQUIREMENTS The 1986 edition of ASME Section XI Table IWB-2500-1, examination category B-D, item ; number B3.110 does not allow any limitations to the required volumetric or surface exanunations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a ! reduction in coverage, ifit is less than 10%.~ , III. BASIS FOR RELIEF The components listed above have been examined to the extent practical as required by the Code. , The Code required volumetric examination coverage was reduced due to nozzle configuration and weld joint Geometry. The scope volumetric examination coverage completed for the above listed welds is listed in Table NDE-28-1. Figure NDE-28-1 is provided detaihng the limitations experiencM. Altemative components could not be substituted for examination due to the , mandatory selection requirements of the Code. , IV. ALTERNATEPROVISIONS It is proposed that the exammations already completed at the reduced coverage be counted as meeting the Code requirements. V. STATUS ()l; '_ Granted -Vo@.4. P=crLetterNo 96-549 Dated 10/10/96. Page 1 of 2
~
Table NDE-28-1 North Anna Unit 2 ' Examination Coverage Estimates (Vessel) Category B-D, Item B3.110 , Mark /Meldt Deam Angle Exam Area Scan Direction 1 Exam Reason For Partial 11 a 12 0 Weld & Base - 66 ho?zle Geometry 45 Weld 2 90 Cladding Prevents 45 Weld 5 16 Estended V-Path Weld 7 90 45 45 Weld 0 90 .I 60 Weld 2 96 60 Weld 5 16 60 Weld 7 90 60 Weld 8 90 45 s 60 Base 2 39 45 a 60 Base 5 24 45469 Base 1 50 45 s 60 Base .p 50 UT Scan Direction Definitions 2 - Axial sean flange side of weld 5 - Axial sean head side of weld 7 - Circtenferential scan, clockwise flooking down on head) 8 - Circumferential scan, counterclockwise (looting down on head) . I i s v f f Page 2 of 2 I - - _~ _ _ _ - - _ _ - _ . _ - _ - _ _ _ _ _ - _ - _ _ - - _ _ _ _ - _ - - - _ - - _ _ - _ _ _ _ _ _ _ _ - - _ - _ - _ _ _ _ . . _ - - .. - .- -
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~. RFI TcF REOUEST NDE-29
- 1. IDENTIFICATION OF COMPONENT ,
Mark / Weld # - Lind Drawinn# Class
. '52H 8"-QS-403-153A-Q3 12050-WMKS-107D 2 I
II. IMPRACTICABLE CODEREQUIREMENTS l l The 1986 edition of ASME Section XI Table IWC-2500-1, cumination category C-C, item I number C3.20 does not allow any hmitations to the required volumetric or surface examinations. Code Case N-460, Alternative E-isiation Coverage for Class 1 and Class 2. Welds, allows a reduction in coverage, ifit is less than 10%. III. BASIS FOR RFT _TFF )
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The weld listed above has been examined to the extent practical as required by the Code. Due to a o pipe support only five inches out of six inches (83%) of each of the four integral attachments that i are associated with weld 52H are accessible for an inservice examination. Figure NDE-29-1 is provided detading the hmitations experieaced. ' Alternative components could not be substituted for exammation due to the mandatory selection requirements of the Code. IV. ALTERNATEPROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as . meeting the Code requirements. V. STATUS in i 9 Granted - Virginia-Power Letter No. %-549 Dated 10/10/96 1 4
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RFT IFF REOUEST NDE-30 I. IDENTIFICATION OF COMPONENTS
. Integral Attachments for Vessels, Piping, Pumps and Valves PumpsIntegrallyWelded Attachments Drawing No. Mark / Weld No.
12050-WMKS-CH-P-1A WS-3
- 12050-WMKS-CH-P-1A WS-4 12050-WMKS-CH-P-1B WS-3 12050-WMKS-CH-P-1B WS4 H. IMPRACTICABLE CODEREQUIREMENTS The 1986 edition of ASME Section XI in Table IWB-2500-1, examination category C-C, item number
- C3.30 does not allow any hnutations to the required surface examinations. Code Case N-460, Alternative Examination coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, ifit is less than 10%. 'III. BASIS FORRELIEF The integral attachment welds listed above have been exammed to the maximum extent practical as required by the Code. The Code required surface examination was reduced due to a support pad which the integral attachment rests on and the pump end flange. The support pad prohibits access to the underside of the integral attachment. The end flange prohibits access to one of the outer edges of each j integral attachment on the 'A' pump. The end flange on the 'B' pump limits a portion of the base material required to be examined. ,
I The limitation on integral attachment welds WS-3 and WS-4 on 2-CH-P-1A was 41% of tht, exammation area as required (59% of the required area was exammed). Figure NDE-30-1 is provide j detaihng the linutations experienced. The limitation on integral attachment welds WS-3 and WS-4 on 2-CH-P-1B was 18.5% of v.he examination area as required (81.5% .of the required area was examined). Figure NDE-30-3 is provided detailing the hmitations experienced. l Page 1 of 2
i 1 RFIIFF REOUEST NDE-30 Continued l IV. ALTERNATEPROVISIONS l
; I It is proposed that the exanunations already completed at the reduced coverage be counted as meeting the Code preservice requirements.
V. STATUS i tME Granted-Y J., ruwerLetterNo. 96-549 Dated 10/10/96. 5
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i a i l 1 Jk i 1 r. ( L 4 i-Page 2 of 2 1 r l
4 b 4- E O D FLANGE 3 I /8' ++" 2- = + 3 3/16-WS-04 , WS-03 , p_ . ( h 4- . D INACCESSIBLE 1- ' AREA TYPICAL OF 2 - 7 3/ 4 ---* A-A END VIEV 0F 2-CH-P-l A 4 FIGURE NDE-30-1 INTEGRAL ATTACHNENTS VS-3 AND WS-4
--_ . . __ .-__ __ _.__ _ _ ___ l
AREA 0F COVERAGE Y EDG hF WELD DUE TO END FLANGE. VS9 07 '*F + 2 ' '2~+ -12 2 '# VS-04[E "[_ .: A 4- Qh INACCESSIBLE ~T < AREA " TYPICAL OF 2 _ g , , g. _ . A-A END VIEW OF 2-CH-P-1 B FIGURE NDE-30-2 INTEGRAL ATTACHMENTS VS-3 AND VS-4
-I VirginiaElectric & Power Company
.34 orth Anna Power Station Unit I and Unit 2 Second 10 YearInterval Request for ReliefNumber NDE-31 Revision 1 I. IDENTIFICATION OF COMPONENTS Mark / Weld # Lind Drawing #
Joint FW-1SW, 71 4"-WS-46-163-Q3 11715-CBM-78A-2 SHT. 4 BW ll715-WS-19E 87,91 4"-WS-46-163-Q3 11715-CBM-78C-2 SHT. 2 BW 11715-WS-19F 89,59 4"-WS-56-163-Q3 11715-CBM-78C-2 SHT. 4 BW 11715-WS-18F 85 4"-WS-56-163-Q3 11715-CBM-78A-2 SHT. 4 BW 11715-WS-18F 89 4"-WS-57-163-Q3 11715-CBM-78A-2 SHT. 4 BW l1715-WS-16E 58 2"-WS-60-163-Q3 11715-CBM-78G-2 SHT.1 BW l1715-WS-1060B j 76 2"-WS-61-163-Q3 11715-CBM-78C 2 SHT.1 i BW I 11715-WS-16B 1 66* 2"-WS-62-163-Q3 11715-CBM-78G-2 SHT.1 BW l1715-WS-1062B l 67 2"-WS-62-163-Q3 11715-CBM-78G-2 SHT.1 SW 11715-WS-1062B 91 2"-WS-65-163-Q3 11715-CBM-78G-2 SHT.1 BW , 11715-WS-1064B 9W 3"-WS-74-163-Q3 11715-CBM-78G-2 SHT.1 BW l1715-WS-1074A 71* 3"-WS-75-163-Q3 11715-CBM-78G-2 SHT.1 BW 11715-WS-1075A l Page 1 of 7
- m. _ _ - , ,. _ . _ _ _ . _ __ _ _ _ _ _ _ . _ . _ . . _ . . _ _ _
i 46*,59~ . 3"-WS-76-163-Q3 11715-CBM-78G-2 SHT.1 BW . 11715-WS-1076A 73 2"-WS-450-163-Q3 11715-CBM-78G-2 SHT. 2 SW l1715-WS-2450B . 86 2"-WS-451-163-Q3 11715-CBM 78G-2 SHT. 2 SW ll715-WS-2450B , 97 2"-WS-461-163-Q3 11715-CBM-78G-2 SHT. 2 - BW l1715-WS-16B , 10 2"-WS-775-163-Q3 11715-CBM-78C-2 SHT. 2 SW 20 2"-WS-945-153A-Q3 11715-CBM-78G-2 SHT. 2 SW l1715-WS-2951 A e 40 2"-WS-954-153 A-Q3 11715-CBM-78G-2 SHT. 2 SW l1715-WS-2951 A l Mark / Weld # Lind Drawing # Jsini 7 2"-WS-954-153 A-Q3 11715-CBM-78G-2 SHT. 2 SW. I1725-WS-2954A I 43 4"-WS-H48-163-Q3 11715-CBM-78A-2 SHT. 4 BW 12050-WS-2H48A (a) The above welds are Class 3, moderate energy piping in the Service Water (SW) system and; (b) Provide cooling water from the service water to instrument air compressors and charging pump lube oil coolers for both units and return service water back to the return headers. Normal flow is 20 to 100 gpm at an operating pressure of 100 psig. The design pressure is 150 psig and design temperatureis 150 F. (c) Joint type - BW butt welded and SW socket welded.
- These welds were repaired before radiographic examination could be performed.
II. IMPRACTICABLE CODE REQUIREMENTS l Five (5) of the above welds had external evidence of through-wall leakage, i.e. extemal moisture. The i remaining welds were stained. Virginia Electric and Power Company decided to proceed under the assumption all of the above welds contain through-wall flaws. Although this evidence ofleakage was not ! Pope 2 of 7 I
detected during the conduct of a system pressure test, the requirements of IWA-5250 of the 1983 Edition and Summer 1983 Addenda and the 1986 Edition are applicable to Unit I and Unit 2 respectively. The speci6c Code requirement for which rcliefis requesui is l'WA-5250(a)(2).
"IWA-5250 Corrective Measures-
'(a) The source ofleakage detected during the conduct of a system pressure test shall be located and evaluated by the Owner for corrective measures as follows:.
(2) repairs or replacements of components shall be performed in accordance with IWA-4000 or IWA-7000, respectively." Articles IWA-4000 and IWD-4000 of ASME Section XI Code repair requirements would require removal of the flaw and subsequent weld repair. When the first through-wall leak, FW-18W on line 4"-WS-46-163-Q3, was identified, Code repairs were
- considered impractical to perform. In order to perform Code repairs the "A" service water header would have required removal from service. The "B" service water header was already out of service during this time for piping upgrades. Taking both service water headers out of service to perform Code repairs would have required both units to be shut down. 1 Subsequent to the detection of the initial through-wall leak, additional areas were identiSed as having evidence of through-wall leaks. Virginia Electric and Power Company decided tc replace all welds having evidence of through-wall leakage in a planned evolution to reduce the number of action statements and service water system manipulations.
III. BASIS FOR RELIEF REQUEST , This relief request is submitted in accordance with NRC Generic Letter 90-05, " Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2, and 3 Piping". The following infnation and
- justification is provided in accordance with the guidelines ofPart B and C ofEnclosure 1 to GL 90-05.
Scone. Limitations and SoeciBc Considerations Scope The scope consists of the welds listed above in piping with evidence of possible through-wall leaks in the Service Water system at the North Anna Power Station Unit I and Unit 2. The material of the piping is stainless steel ASME SA-312 type 316L with 316 or inconel weld filler metal for pipe dass 163 and ASME SA-312 type 304 with 304 filler metal for pipe class 153A. 4 Limitations Based on radiographic examinations and exanunation of removed portions of piping from replacements, Microbiological Influence Corrosion (MIC) is the cause. The MIC caused flaws originated on the inner diameter of the pipe and were detected during plant operation. The intent of this request is to obtain relief for the period of operation with the identiSed through-wall flaws until repair could be 1 accomplished without a forced shutdown by following the guidance ofNRC Generic Letter 90-05 to the - Page 3 of 7
0 extent practical. This period extended from detection of the first leaking weld on October 31,1996 to i the repair of all welds =p ofhaving through-wall flaws was completed on December 14,1996. Soecific Considerations i System interactions, i.e. consequences of floodmg and spray on equipment was evaluated. The flaws , were located on the piping such that potential through-wall leakage will not affect plant equipment. The structural integrity of the butt welds were evaluated based on radiographic examination results for the required design loading conditions, including dead weight, pressure, thennal expansion and seismic (DBE) loads. The methods used in the structural integrity analysis consisted of an area reinforcement, fracture mshanics, and limit load analyses. Each indication was considered to be through-wall due to the inability of either radiography or ultrasonics to determme indication depth. A summary of the flaw i evaluation is provided in Attachment 1. All butt welds analyzed were found to be acceptable except for two, weld 58 on line 2"-WS-60-163-Q3 and weld 9W on line 3"-WS-74-163-Q3. These two welds were l
- found to be unacceptable due to the extent of the indication identified by radiographic exammation.
i Almost all of the identified defects were conservatively identified as MIC. The welds were removed and cut open for analysis. The analysis determined that a large amount of the areas reported as MIC by i radiography were actually construction defects, slag and lack of penetration, etc, d The welds that were found to be unacceptable were declared inoperable and repaired within the limiting conditions of operation as defined in the plant's Technical Specifications. 2 Radiography of the socket welds was attempted but did not yield meaningful results. Since the flaws could not be characterized for socket welds a structural analysis was not performed. The socket welds were monitored for leakage until replaced. All socket welds were replaced or removed from service within 15 days from the date of discovery. Three (3) butt welds, weld 66 on line 2"-WS-62-163-Q3, weld 71 on 3"-WS-75-163-Q3, and weld 46 on 3"-WS-76-163-Q3, were adjacent to planned replacements and were replaced before radiography was performed. The structural integrity for all welds identified with evidence of through-wall leakage were monitored by the following methods:
- Weekly visual monitoring of through-wall flaw and leakage.
. Walkdown of the accessible portions of the service water system. This walkdown was performed on November 25,1996 and November 26,1996. All subject welds were replaced before the next scheduled monthly system walkdown.
. Radiographic examination of all but three (3) butt weld locations was performed. This exammation was not repeated since the subject welds were replaced before the next three (3) month RT surveillance was due. Socket welds were not radiographed.
The temporary non-code repair was to leave the welds as they are found, subject to monitoring and meeting the criteria for consequences and for structural integrity as described above. Evaluation l Ps084of7
L i Flaw Detection Durina Plant Operation and Imoracticahty Determination l l . l The flaws were detected when Unit I was in service. When the initial flaw on the "A" train of Senice
-Water Syste...was detected, October 31,1996, service water piping on the "B" train associated with the
! component cooling heat exchangers was being refurbished. This work required one train of service water to be isolated for a length of time that would exceed the seven (7) day action statement of Tech. Spec. 3.7.4.1.d. By letter datui October 11,1995, the NRC issued Techinal Specification Amendment Nos. l
- 194 and 175 for North Anna Power Station, Units 1 and 2 respectively. These amendments allowed one j train of service water to be isolated for 49 days. The "B" train of service water was taken out of service on October 21,- 1996 for piping upgrades. Performing an immediate Code repair would have required the
[; "A' train to be taken out of service which would require Unit I to be shut down. l ~ Augmented inspections and a walkdown of the accessible portion of the service water system were i performed to assess the integrity of the system. 'Ihis resulted in additional welds being identified as d having evidence of possible leakage. Virginia Electric and Power Company decided it was impractical to
- immediately replace all of the subject welds. Code repairs were performed within 44 days from the date
- of discovery under controlled conditions by use oflimited scheduled service water outages.
~
. Root Cause Det htion and Flaw CharacterizatinD I ' The Service Water system at North Anna Power Station has previously experienced MIC. The
- radiograph examinations of the service water welds with through-wall leaks revealed small voids .
= surrounded by exfoliation, which is typical of MIC. No other type of operationally caused defects were i' identified by the radiographs. Additionally, examina.tions performed by a Virginia Electric and Power l Company staff metallurgist of a sample of the piping segments removed to repair the leaking welds confirmed the presence ofMIC. 1 Flaw Evaluation
- Flaw evaluation for butt welds subjected to radiographic exammation was performed as described in ;
Attachment 1. The flaws were evaluated by three types of analyses, area reinforcement, lindt load i- analyses, and fracture mechanics evaluation using the guidance from NRC Gen ric Letter 90-05. Because of the inability for either radiography or ultrasonic techniques to determine the extent of wall . degradation, the structurd assessment considered each indication to be through wall. Additionally, the
- radiography is not conclusive in differentiating purely MIC conditions from conditions such as slag and incomplete root penetration, which has been aggravated by corrosion during service. Therefore, these areas were also considered fully degraded for the structural assessments. This resulted in two welds i being rejected by the structural acceptance criteria weld 58 on line 2"-WS-60-163-Q3 and weld 9W on j, line 3"-WS-74-163-Q3. The lines containing these two welds were declared inoperable and the action was taken per the plant's Technical Specifications. Supplemental examinations of weld 58 and weld 9W, j_ after removal from the piping system, determined MIC as only part of the problem. Pre-existing ,
j conditions from the time ofinstallation were also a major contributor. . ] The analysis determine each butt weld listed in the scope was capable of maintaining their stmetural j- integrity untilit was repaired. This is based on the results from the analysis. l 1 j Page 5 of 7 , i !
1
- i. 1. Ductile teanng will not occur at a postulated two (2) inch hole when the piping is subjected to
[ t the design pressure..This applies to each pipe size under the scope of this relief request. i 2. The limit load analysis shows that there is at least a margin of 5 against a ductile rupture for the , i most hmiting case analyzed
- 3. A hner.r elastic fracture mechanics analysis shows that the applied stress intensity factor at the analyzed flaws is below the allowable stress intensity factor per the guidance of NRC Generic Letter 90-05. Therefore, a brittle fracture is unlikely.
IV. AUGMENTEDINSPECTION To assess the overall degradation of the service water system augmented radiographic and visual inspections were perfonned. After the initial through-wall flaw was identified six (6) additional locations i on lines having the same size and function were examined using radiography. This sample group l also identified welds degraded by MIC. An additional sample of five (5) welds was examined using ) radiography and fbur (4) out of the five (5) welds were identified as having MIC. Any indication of MIC l was treated as a through-wall defect and analyzed for structural stability as described in Attachment 1. 1 All augmented weld locations were found to be structurally acceptable. J l In addition, a walkdown of the accessible portions of the service water system was performed and ! identified 17 welds with evidence ofleakage. Radiography was used to determine the extent of MIC for butt welds. Butt welds identified with MIC were evaluated for structural integrity as desenhd in Attachment 1. As stated previously, all but two (2) butt welds were found to be acceptable. Socket weld flaws could not be characterized by radiography or ultrasonics. Therefore, an analysis could not be performed. V. ALTERNATE PROVISIONS It is proposed that the operation of the Service Water System from October 31,1996 through December 14,1996 with the identified possible through-wall flaws, subject to monitoring and meeting the criteria for consequences and for structural integrity as described above be accepted as an altemative to IWA 5250(a)(2). Operation in this mode continued until the subject welds were replaced. Each subject weld was replaced by December 14,1996. During the above period, structural integrity of the Service Water System was continuously monitored by the following methods until the repairs required by IWA 5250(a)(2) are completed.
. Weekly visual monitoring of all areas with possible evidence ofleakage.
. Walkdown of the accessible portion of the service water system at least monthly.
The proposed alternative stated above ensured that the overall level of plant quality and safety were not compromised. VI. STATUS Page 6 of 7
Granted - NRC Letter No. 97-357, Dated 6-4-97.
Attachment:
1.FlawEvaluationMethods and'Results ,
References:
- 1. USAS B31.1 Power Piping 1%7 Edition
- 2. EPRIReportNP-6301-D,"DuctileFractureHandbook"
- 3. Nuclear Regulatory Commission Generic Letter 90-05 " Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2, and 3 Piping" Page 7 of 7
-- . - .. -- - . . . . - - - . - .~ -.
l i l i ReliefRequestNDE-31
. Attachment 1 l
Flaw Evaluation Methods and Results 1 Introduction I Butt welds identified by radiography as having MIC were analyzed for structural integrity by three methods, area reinforcement, limit load analysis, and linear elastic fracture mechanics evaluation. Area Reinforcement Analysis The area reinforcement analysis is used to determine if adequate reinforcing exists such that ductile tearing would not i occur. The guidelines 'f ANSI B31.1 paragraph 104,3.(d) 2 (reference 1) are used to determine the Code required reinforcing area. The actual reinforcing area is calculated and is checked against the required reinforcement area. The Code required reinforcement area in square "mches is defined as: I 1.07(t.)(di) , ' Where t. is the code mmimum wall, and di is the outside diameter ' 3e Code reinforcement area required is provided by the available material around the flaw in the reinforcing zone. l l The results of this analysis determined that for the subject piping, 2", 3" and 4", a two (2) inch diameter hole would l have acceptable reinforcement. l Limit Load Analysis The structural integrity of the piping in the degraded condition was established by calculating the mimmum margin of safety based upon a Limit Load Analysis. These methods are documented in EPRI report NP-6301-D (Ductile Fracture Handbook)(reference 2). The limit load analysis of the postulated flawed sections were performed with a material flow stress of 45.98 ksi representing the midpoint of the ultimate strength and yield point stress for the SA312-TP316L stainless steel material at the design temperature of150 F. The flawed sections were subjected to deadweight, thermal, and seismic DBE loading. Page 1 of 4 1
The allowablelimit loadis given by, M. = 2 srR.2t(2cos(b)-sin (Q))in-Ibf st = flow stress = 0.5 (Sy + S.) psi Sy = yield stress psi - , S.= ultimate stress psi i i R. = mean radius = D .t 2 ; p , e , TI *(R'o P}tF 2^ 4 e erf
- R,e t R; = internal radius = D - 2 t inches 2
P' = pressure = 150 psig F = axialload Ibs D ' = Outside diameterinches t - = pipe thickness inches 0 = half angle of the crack (radians) = crack length 2 R. MR = Resultant Moment MR = 4MY'+ MZ'+ T' MY = Bending Moment MZ = Bending Moment T = Torsion The calculated factor ofsafetyis, FS = % (MR)- A summary of the results are listed in Table 1. Fracture Mechanics Evaluation A linear elastic fracture mechanics analysis was performed for circumferential through-wall crack using the guidance provided in NRC Generic Letter 90-05. The stmetural integrity of the piping in the degraded condition was established by calculating the stress intensity factor ratio based upon a Fracture Mechanics evaluation. This method is documented in EPRI r eport NP-6301-D (Ductile Fracture Handbook) (reference 2). Pope 2 of 4
. . ~. . ._ .- _ _ _ - _. _ ._ _ _ . _ . _ . _ . _ _ . _ . _ _ . . _
A through-wall circumferential crack was postulated for every area containing MIC. The cracks were subjected to a ;
.esign pressure loading of 150 psig in hadition to the deadweight, normal operating thennal and seismic DBE loadings.
For the purpose of this evaluation a generic allowable stress intensity factor of Kac = 135 ksioin was used for the materialperNRC GL 90-05. The applied stress intensity factor for bendmg, K , is found by: Km = [se(p A-Q)'3] F6 , The applied stress intensity factor for internal pressure, K,, is found by: L = s.-(p R.-Q)"d F.
~ The applied stress intensity factor for axial tmsion, Krr is found by:
- Krr = sc(p R.-Q)*S F: -
The stress intensity factor for residual stresses, Km is found by: Km = S-(p R.-Q)"' Fi Total applied stress intensity Kr includes a 1.4 safety factor and is calculated by:
/g = 1.4-(Km + K, + Krr) + Km The allowable stress intensity factor is taken from Generic Letter 90-05.
Km = 135 ksiQin . Stress Intensity Factor Ratio is defined as: SR = Er_ Kn 1 A summary of the results are listed in Table 1. l l i 1 1 I l l Pape3of4 l 1
-t . . i . _mm m. .m. . . , - . - . . .
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~ '
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Table 1 _
SUMMARY
OF FLAW EVALUATION RESULTS FOR SERVICE WATER WELDS' x ,
'., E
, . Allowable .
Sending Bending -ResultIng . Limit- Factor Applied
. Allowable i Crack Amlal . Torsion Moment Moment Moment Lead M. of N, - _ Kae terti pos.' Line Nos. Length Load Ibs T ft-lbs MY ft-lbs - MZ f t-lbs MR ft-lbs ft-lbf. Safety' ks1 Yin kaliin t
.s9 4*-Ws-56-163-Q3 4.0 98 27 313 51 310.215 7099 24.014 123.8 135 120.6 e2veloping cale 1 3.376 1155 . 539 942 995 2472.0 9133 6.204 135 43 4*-MS-H40-163-Q3 1.6 .519. 813 1076 561 1461.0 13100 9.969 50.02 _ _ 135 ' , 2._' 59 - . 3*-MS-76-163-Q3. 2.876 703 21 55 97 113.468 .4542.5 40.032 96.06 135 - tzveloping calc 2 2.25 96 140 149 144 .250.074 1203.33 5.13 109.70 135 '76 2*-MS-61-163-Q3 1.25 240 30 44 102 115.065 1564.17 13.597 55.65 135 , tiotss:
- 1. Enveloping Calc. 1 includes welds Iv-lett 71, 97, and 91 on line 4*-MS-46-163-C3, welds 59 and 85 on line 4*-us-56-163-Q3, and weld 89 on line 4*-es-57-163-Q3. '
Enveloping Calc. 2 Includes welds 91 en hine 2*-NS-65-163-Q3 and weld 97 on line 2"-MS-461-163-Q3.
- 2. Limit load f actor of safety is Allowable Limit Load /ptesulting Moment {
t [ r k i P I t I kYk _-e.. e -,_- .-a-x _ e -.--.. ._, _m ,. -ww -._,_#o_ m__
Virginia Electric & Power Company North Anna Power Station Unit 1 and Unit 2 Second 10 Year Interval Request for ReliefNumber NDE-32 R.evision 2 Ic IDENTIFICATION OF COMPONENTS Drawine # Service Water System 11715-CBB-40D-2 SHTS,1 and 2 11715-CBM-78A-2 SHTS. I and 4 11715-CBM-78B-2 SHTS.1, and 3 11715-CBM-78C-2 SHT. 2 11715-CBM-78G-2 SHTS. I and 2 11715-CBM-78H-2 SHT.1 Components within the scope of this Request for Reliefinclude the welds and associated piping which comprise the moderate energy stainless steel piping of the Service Water System (SW). This piping system provides cooling water from the Service Water Reservior to safety related equipment and retum the Service Water back to the return headers. Normal operating pressure is 100 PSIG. The design pressure is 150 PSIG and the design temperature is 150 F. This is an ASME, Section XI, Class 3 system. Attachment 2 provides an identification of each piping segment within the ] scope of this Request for Relief. The piping segments are identified by their l line number designation which is a unique identifier. The graphics represented on the associated drawings of each piping segment along with the associated line number designation provide a defining boundary for each pipe segment. The identifica' ion of piping segments as components is appropriate as both the welds and piping forming the piping segments are subject to developing through wallleaks.
- 11. IMPRACTICABLE CODE REQUIREMENTS The Service Water System has experienced through-wall leakage caused by Microbiological Influenced Corrosion (MIC). Chemical treatment of the Service Water System has not been effective in eliminating MIC. The Service Water System is being monitored for MIC. Identification of additional through- ,
I wall leakage is anticipated. Through-wall leakage must be located and evaluated in accordance with the requirements eflWA-5250 of the 1983 Edition and Summer 1983 Addenda for Udt I and 1986 Edition for Unit 2. The specific Code requirement for which reliefis requested is IWA-5250(a)(2). Page 1 of 7
i "IWA-5250 Corrective Measures: (a) The source ofleakage detected during the conduct of a system pressure test shall be located and evaluated by the Owner for corrective measures as follows:. (2) repairs or replacements of components shall be performed in accordance with IWA-4000 or IWA-7000, respectively," Articles IWA-4000 and IWD-4000 of ASME Section XI Code repair requirements would require removal of the flaw and subsequent weld repair Code repairs for through-wall leaks require the line to be isolated and drained. , Taking a train of service water out of service in some instances is a major l' evolution and requires entering a Technical Specification action statement. Welds and piping with through-wall flaws caused by MIC can typically be !
- shown to have adequate structural integrity to remain in service. This type of through-wall flaw is unpredictable but not normally subject to catastrophic failure, it is impractical to require a Ca>- nair withir the time specified by the Technical Specification Limiting C aoition for Operation every time a through-wall flaw is identified.
Generic Letter 90-05, " Guidance for Performing Temporary Non-Code Repair ; of ASME Code Class 1,2, and 3 Piping", provides guidance for submitting l relief requests to allow continued operation with a through-wall flaw. Submitting a relief request for each instance of through-wall leakage caused by MIC is an administrative burden and causes additional unnecessary reviews for , the NRC. Implementing GL 90-05 each time a through-wall flaw is identified is I also impractical. , This relief request establishes a plan for continued operation with through-wall flaws in stainless steel piping in the Service Water System based upon the guidance of GL 90-05 to the extent it is believed practical. This relief request a will be implemented upon receiving NRC approval. In the interim, GL 90-05 . will be followed for through-wall flaws and relief requests will be submitted, 4 111. ISI BASIS FOR RELIEF REQUEST 1 This relief request is submitted in a format laid out in NRC GL 90-05. The following information and justification is provided in accordance with the guidelines of Part B and C of Enclosure I to GL 90-05. J. l Page 2 of 7
, Scope. Limitations and Specific Considerations Scone The scope consists ofwelds and stainless steel piping, pipe class 153A and 163. with evidence of possible through-wall leaks in the Service Water System at North Anna Power Station Units I and 2. Limitations Based on radiographic examinations and laboratory examinations of removed portions of piping from replacements, North Anna Power Station is experiencing MIC in its stainless steel piping. The MIC caused flaws originate on the inner diameter of the pipe. The Service Water System is common to both Units. As long as one Unit is in Mode 1,2,3, or 4 both trains of service water must be operable. If both Units are in Mode 5 or 6 then one train of Service Water must be operable. The intent of this reliefis to permit continued operation with the identified through-wall flaws until repairs are accomplished in a scheduled service water outage. Soecific Considerations System interactions, i.e. consequences of flooding and spray will be evaluated. The flaws located on piping, such that potential through-wall leakage could affect plara safety related equipment will be declared inoperable and the appropriate Technical i Specification action statement entered. ' l Butt welds and piping accessible to radiography with through-wall flaws will be evaluated for structural integrity within 14 days of identification for all design loading conditions, including dead weight, pressure, thermal expansion and seismic (DBE) loads. The methods used in the stmetural integrity analysis will consist of area reinforcement. fracture mechanics, and limit load analyses. These methods are detailed in Attachment 1. The welds that are found to be unacceptable will be declared inoperable and the appropriate Technical Specification action statement entered. A 3/4" hole will be postulated for any location with a through-wall flaw that can not be characterized volumetrically by ultrasonics or radiography, socket welds and welds that are inaccessible for radiography. Laboratory examination of cut sections of MIC degraded socket weld samples indicate that flaws are enveloped within the l 3/4" size. A leaking socket weld location will be analyzed by treating the cross section as equivalent to the cross section of the attached pipe with a 3/4" hole. The methods used in the stmetural integrity analysis will consist of area reinforcement, fracture mechanics, and limit load analyses. These methods are detailed Page 3 of 7
1 m Attachment 1. A through-wall flaw size is postulated in order to perform a structural analysis. Additional monitoring is performed for a period of two (2) months on socket welds to assure the degradation mechanism is behaving in a manner expected for a MIC flaw. The structural integdty for all welds identified with evidence of through-wall ; leakage will be monitored by the following methods: '
. Weekly visual monitoring of through-wall flaws from the time of identification until completion of structural integrity analysis. If the welds are determined to be structurally acceptable then the visual monitoring frequency <
will be decreased to once every six weeks. !
. Weekly visual monitoring of through-wall flaws in socket welds and butt welds inaccessible to radiography for a period of two (2) months. If there is i i
no significant change in the leakage rate the monitoring frequency will be decreased to once every six weeks until the welds are repaired. 1 A significant change is defined as a 0.5 gpm increase in the leakage rate from ' the initial observed leakage condition for each weld. Should any location , r reach the threshold of a significant change the weld will be reassessed for stmetural integrity and flood / spraying consequences.
. A total leakage rate limit of 1.0 gpm for a single supply or retum line to an i individual component will be established. If this total leakage rate limit is ;
exceeded then an evaluation will be performed to determine if design senice i water flow is available to affected components. Inadequate senice water supply will cause the associated service water lines and equipment to be j declared inoperable and appropriate action will be taken according to ) Technical Specifications. The temporary non-code repair will be to leave the welds as they are found, subject j to monitoring and meeting the criteria for consequences and for stmetural integrity ' as described above. Evaluation Flaw Detection During Plant Operation and imoracticality Determination l l Page 4 of 7 4
i y ! The Service Water System is a common system for both Units at North Anna Power Station. Both trains are required to be operational or the appropriate Technical SpeciScation action statement be entered. The through-wall flaws on Service Water lines in senice are anticipated based on the North Anna Power Station history ofMICc Virginia Electric and Power Company requests to evaluate the flaws and leave acceptable through-wall flaws in service in order to perform Code repairs in controlled conditions during scheduled service water outages. Root Cause Determination and Flaw Characterization The Senice Water System at North Anna Power Station has previously experienced MIC. j Radiograph examinations of senice water welds having evidence of through-wall leakage ! revealed small voids surrounded by exfoliation, which is typical of MIC. No other type of l inservice defects were identified by the radiographs near the areas with through-wall leaks. ' Additionally, a visual examination performed by a Virginia Elecuic and Power Company staff metallurgist of a sample of piping segments removed to repair the leaking welds confirmed the presence ofMIC. Butt welds identified with through-wall leakage and accessible for radiography will be radiographed and evaluated for stmetural integrity within 14 days of discovery. " Through-wall flaws that cannot be characterized by radiography, socket welds and inaccessible butt welds, will be characterized as a 3/4" hole for each area ofleakage. Flaw Evaluation Flaw evaluation for welds with through-wall leakage will be performed as described in Attachment 1. The flaws in butt welds that can be characterized by radiography will be evaluated by three types of analyses, area reinforcement, limit load analyses, and fracture mechanics psing the guidance from NRC Generic Letter 90-05. The fhws in welds that cannot be chaiacterized by radiography, i.e. socket welds and inaccessible butt welds, will be evaluated by the same analysis by assuming a 3/4" hole for each point ofleakage within a weld with through-wall leakage. Socket welds will be analyzed by treating the cross section at the socket weld as equivalent pipe cioss section. IV. AUGMENTED INSPECTION An augmented inspecuon program will monitor a sample of butt welds in the Senice Water System using radiography. Radiography will be performed every three (3) months. The frequency of radiography will be assessed after a year and may be adjusted for each location based on the results of the radiographs. Page 5 of 7
- - - . . --.- - -. _.~ _- - .. - .-. - .- - . ..- _.. ....- ~ - - ..- .
I V. ALTERNATE PROVISIONS As an alternative to performing Code repairs in accordance wkh IWA-5250(a)(2) to through.
- wall flaws in the Service Water System the inrough-wall flaws will be left as is. The through-wall flaws will be monitored for leakage and must meet the criteria for flooding and spraying consequences and for stmetural integrity as described to remain in service. Operation in this
, rnode will continue until the subject welds are replaced. All welds identi6ed with through-wall j flaws will be replaced within 18 months from the time of discovery. The structural integrity of the Service Water System will be monitored by the followmg methods until the repairs required by IWA 5250(a)(2) are completed. i.'
. Weekly visual monitoring of through-wall flaws from the time of identification until l- completion of structural integrity analysis. If the welds are determined to be structurally i acceptable then the visual monitoring frequency will be decreased to once every six I l . weeks.
L i All welds identified as having a through-wall flaws will be assessed for structural
)
- integrity within 14 days of detection. Butt welds will be radiographed, if accessible, to '
- characterize the flaws. Socket welds and butt welds inaccessible to radiography will be
) assessed for stmetural integrity by assuming a conservative large hole. Welds [ determined to be structurally adequate will be included in the above monitoring program. l Identification of a structurally inadequate weld will result in the associated piping to be l declared inoperable and the appropriate Technical Specification action statement to be l taken. i j . Weekly visual monitoring of through-wall flaws in socket welds and butt welds 1 inaccessible to radiography for a period of two (2) months. If there is no significant 2 change in the leakage rate the monitoring frequency will be decreased to once every six weeks until the welds are repaired. A significant change is defined as a 0.5 gpm increase in the leakage rate from the initial observed leakage condition for each weld. Should any location reach the threshold of a significant change, the weld will be reassessed for structural integrity and flood / spraying consequences. I 1
. A walkdown of the accessible stainless steel portions of the Service Water System will I be performed every six weeks. This inspection frequency is based on a 12 week Maintenance Rule schedule which reduces the time equipment is out of senice for testing and maintenance. Two one week windows, six weeks apart, are available within this schedule to perform service water repairs. Performing inspections within this schedule will allow repairs to be made in a timely manner and reduce the time safety Page 6 of 7 I
1 l y -- - -- 4,- +
~. . __ . _ _ _ _ . - _ _. ._ . _ _ . - _ _ _ _-
1 I 1 related equipment is out of service. The frequency of the walkdowns will be assessed ! after a year and adjusted based on the results of the inspections.
. A total leakage rate limit of 1.0 gpm for a single supply or return line for an indisidual component will be established. If this total leakage rate limit is exceeded then en evaluation will be perforTned to determine if design service water flow is available to .
affected components. Inadequate service water supply will cause the associated service ! water lines and equipment to be declared inoperable and appropriate action will be taken according to Technical Specifications.
. ' An augmented inspection program will monitor a sample of butt welds in the Service
- Water System using radiography. Radiography will be performed every three (3) !
months. The frequency of radiography will be assessed after a year and may be adjusted , for each location based on the results of the radiographs. The proposed altemative stated above will ensure that the overall level of plant quality and safety will not be compromised. . VI IMPLEMENTATION SCHEDULE This altemative to Code requirements will be followed upon receiving NRC approval for the remainder of the second ten-year inspection intervals. The Unit I second ten-year inspection interval will end on December 24,1998 ad the Unit 2 second ten-year interval will end on December 14,2000. Vll. STATUS Granted With Conditions - NRC Letter No. 97-700 Dated 11/24/97. Conditions: A minimum of ten welds (10) must be radiographed Attachments:
- 1. Flaw Evaluation Methods and Results
- 2. Drawing /Line Number Designations
References:
- 1. USAS B31.1 Power Piping 1967 Edition
- 2. EPRI Report NP-6301-D, " Ductile Fracture Handbook"
- 3. Nuclear Regulatory Commission Genetic Letter 90-05 " Guidance for Performing Tempoiary Non-Code Repair of ASME Code Class 1,2, and 3 Piping" Page7 C 7
. . .. . . . . _ _ _ _ .-._~.___.____-__.._m _ - _
i ReliefRequest NDE-32, Rev. 2 Attachment 1 1 Flaw Evaluation Methods and Results ! l Introduction l Butt welds identified as having possible through-wall leaks will be radiographed, if accessible. Flaws in i butt welds that are inaccessible for radiography will be postulated as a 3/4" hole for each area identified with a through-wall flaw. All butt welds will be analyzed for structural integrity by three methods, area
- reinforcement, limit load analysis, and linear elastic fracture mechanics evaluation.
Flaw size in socket welds identified as having possible through-wall leaks cannot be characterized by nondestructive examination. A conservatively large hole, 3/4", will be postulated for each area identified with a through-wall flaw. The postulated flaw will be analyzed for structural integrity by .n treating the cross section as equivalent to the cross section of the attached pipe. Area Reinforcement Analysis ' The area reinforcement analysis is used to determine if adequate reinforcing exists such that ductile tearing would not occur. The guidelines of ANSI B31.1 paragraph 104.3.(d) 2 (reference 1) are used to determine the Code required reinforcing area. The actual reinforcing area is calculated and is checked against the required reinforcement area. The Code required reinforcement area in square inches is defined as: 1.07(tm)(di) Where tm is the code minimum wall, and di is the outside diameter The Code reinforcement area required is provided by the available material around the flaw in the reinforcing zone. , Limit Load Analysis The structural integrity of tlie piping in the degraded condition will be established by calculating the minimum margin of safety bs. sed upon a Limit Load Analysis. These methods are documented in EPRI report NP-6301-D (Ductile Fracture Handbook) (reference 2). MR = 4MY'~ MZ'+ T' Page 1 of 3
1 The limit load analysis of the postulated flawed sections will be performed with a material flow stress representing
- the midpoint of the ultimate strength and yield peint stress. The flawed sections will be subjected to deadweight, thermal, and seismic DBE loading.
The allowable limit load is given by, . Ma = 2 sf Rm2 t-(2cos(b)-sin (Q)) in-lbf- - sf = flow stress = 0.5 (Sy + Su) psi Sy = yield stress psi Su = ultimate stress psi Rm = mean radius of the pipe '
,, e n *(Rf
- P)+F 2 decrf
- R.,* I Ri = internal radius of the pipe P = pressure psig F = axial load in Ibs -
t = pipe thickness = inches D = Outside dia neter inches - 0 = half angle of the crack (radians) = crack length 2Rm MR = Resultant Moment MY = Bending Moment MZ = Bending Moment T ' = Torsion The calculated factor ofsafetyis, FS = Ma (MR) The minimum factor of safety of 1.4 is required to be qualified for continued operaticn. Fracture Mechanics Evaluation f A linear elastic fracture mechanics analysis will be performed for circumferential through-wall crack using the guidance provided in NRC Generic Letter 90-05. The structural integrity of the piping in the degraded condition wts established by calculating the minimum margin ofsafety based upon a Fracture Mechanics evaluation. This method is documented in EPRI report NP-6301-D (Ductile Fracture Handbook)(reference 2). Page 2 of 3
i
. A through-wall circumferential crack will be postulated for every area containing MIC. The -
cracks will be subjected to a design pressure loading in addi; ion to the deadweight, normal operating thermal and seismic DBE loadingr. For the purpose of this evaluation a generic allowable stress intensity factor of KIC = 135 ksi (in.)', will be used for the stainless steel material per NRC GL 90-05. ! The applied stress intensity factor for bending, KIB, is found by: - KIB = [sb-(p Rm-Q)0.5] Fb - . The applied stress intensity factor for internal pressure, KIP, is found by: KIP = sm-(p Rm-Q)0.5 Fm 1 The applied stress intensity factor for axial tension, KIT is found by: KIT = st-(p Rm-Q)0.5 Ft
]
I The stress intensity factor for residual stresses, KIR is found by: KIR = S-(p Rm-Q)0.5 Ft
.i Total applied stress intensity KT includes a 1.4 safety factor and is calculated by:
i KT = 1.4-(KIB + KIP + KIT) + KIR - The allowable stress intensity factor is taken from Generic Letter 90-05. 1 KALL = 135 ksiGin Stress Intensity Factor Ratio is defined as: SR = KT
-KALL
.1 The stress intensity factor ratio shall be less than 1.0 for continued operation. Page 3 of 3
)
Virginia Electric & Power Company North Anna Power Station Unit I and Unit 2 Second 10 Year Interval Request for Relief Number NDE-32 Revision 3
- 1. IDENTIFICATION OF COMPONENTS Drawine #
Service Water System 11715-CBB-40D-2 SHTS. I and 2 1i715-CBM-78A-2 SHTS. I and 4 i1715-CBM-78B-2 SHTS. I and 3 11715-CBM-78C-2 SHT. 2 11715-CBM-78G-2 SHTS. I and 2
'1715-CBM-78H-2 SHT.1 Components within the scope of this Request for Reliefinclude the welds and associated piping which comprise the moderate energy stainless steel piping of the Service Water System (SW). This piph? system provides cooling water from the Service Water Reservoir to safety relate,u equipment and return the Service Water back to the return headers. Normal operating pressure is 100 PSIG. The design pressure is 150 PSIG and the design temperature is 150 F. This is an ASME, Section XI, Class 3 system.
Attachment 2 provides an identification of each piping segment within the scope of this : Request for Relief. The piping segments are identified by their line number designation which is a unique identifier. The graphics represented on the associated drawings ofeach piping segment along with the associated line number designation provide a defining boundary for each pipe segment. The identification of piping segments as components is l appropriate as both the welds and piping forming the piping segments are subject to ; developing through wall leaks. l
- 11. IMPRACTICABLE CODE REQUIREMENTS ;
- The Service Water System has experienced through-wall leakage caused by Microbiological Influenced Corrosion (MIC). Chemical treatment of the Service Water System has not been effective in eliminating MIC. The Service Water System is being monitored for MIC. Identification of additional through-wall leakage is anticipated. i Through-wall leakage must be located and evaluated in accordance with the requirements ;
ofIWA-5250 of the 1983 Edition and Summer 1983 Addenda for Unit I and 1986 Edition ! for Unit 2. The specific Code requirement for which reliefis requested is j
' IWA-5250(a)(2). 1 i
Page1 of 7
- i. "IWA-5250 Corrective Measures:
(a) The source ofleakage detected during the conduct of a system pressure test shall be located and evaluated by the Owner for corrective measures as follows:...
- . (2) repairs or replacements of components shall be performed in accordance with
[ IWA-4000 or IWA-7000, respectively." l Anicles IWA-4000 and IWD-4000 of AShE Section XI Code repair requirements would require removal of the flaw and subsequent weld repair. ' [ Code repairs for through-wall leaks require the line to be isolated and ' drained. Taking a i train of service water out of service in some' instances is a major evolution and requires entering a Technical Specification action statement. Welds and piping with through-wall : flaws caused by MIC can be shown to have adequate structural integrity to remain in service. This type of through-wall flaw is unpredictable but normally not catastrophic. It
- is impractical to force a Code repair within the time required by the Technical Specification Limiting Condition for Operation everf time a through-wall flaw is identified.
Generic Letter 90-05, " Guidance for Performing Temporanj Non-Code Mr.; pair of ASME Code Class 1,2, and 3 Piping", provides guidance for submitting rel!ef requests to allow continued operation with a through-wall flaw. Submitting a relief request for each instance of through-wall leakage caused by MIC will be an administrative beiden and cause additional reviews for the NRC. Implementing GL 90-05 each time a through-wall flaw is identified is impractical. This relief request establishes a plan for continued operation with through-wall flaws in stainless steel piping in the Service Water System based upon the guidance of GL 90-05 to the extent it is believed practical. This relief request will be implemented upon receiving NRC approval. In the interim, GL 90-05 will be followed for through-wall flaws and separate relief requests will be submitted. 111. ISI B ASIS FOR RELIEF REQUEST This relief request is submitted in a format laid out in NRC GL 90-05. The following , information and justification is provided in accordance with the guidelines of Part B and C of Enclosure 1 to GL 90-05. Scope. Limitations and Soecific Considera.tign.g i i Page 2 of 7 l i
f I Scope , The scope consists of welds and stainless steel piping, pipe class 153 A and 163, with - evidence of possible through-wall leaks in the Service Water System at Nonh Anna Power l l Station Units 1 and 2.
- 3 Limitations :
! Based on radiographic examinations and laboratory examinations of removed portions of piping from replacements, North Anna Power Station is experiencing MIC in its stainless i . steel piping. The MIC caused flaws originate on the inner diameter of the pipe. The , i Service Water System is common to both Units. As long as one Unit is in Mode 1,2,3, [ or 4 both trains of service water must be operable. If both Units are in Mode 5 or 6 then
- one train of Service Water must be operable. The intent of this reliefis to permit 4- continued operation with the identified through-wall flaws until repairs are accomplished ,
in a scheduled service water outage. 1 i Soecific Consideration._s 1 , ' System mteractions, i.e. consequences of flooding and spray will be evaluated. Piping with through-wall leakage that could affect plant safety related equipment will be declared inoperable and the appropriate Technical Specification action statement entered. Welds containing evidence of through wall flaws will be either repaired or assessed for structural integrity within 14 days of detection. Butt welds and piping remaining in service after leakage is detected for longer than 14 days and accessible to volumetric examination by Ultrasonic (UT) or Radiographic (RT) examination methods, will be evaluated for structural integrity for all design loading conditions, including dead weight, pressure, thermal expansion and seismic (DBE) loads. The methods used in the structuralintegrity analysis will consist of area reinforcement, fracture mechanics, and limit load analysis. These methods are detailed in Attachment 1. The welds that are found to be unacceptable will be declared inoperable and the appropriate Technical Specification action statement entered. A 3/4" hole will be postulated for any location with a through-wall flaw that can not be characterized volumetrically by RT or UT, socket welds and welds that are inaccessible for RT or UT. Laboratory examination of cut sections of MIC degraded socket weid samples indicate that flaws are enveloped within 3/4" size. A leaking socket weld location will be analyzed by treating the cross section as equivalent to the cross section of the attached pipe with a 3/4" hole. The methods used in the structural integrity analysis will consist of area reinforcement, fracture mechanics, and limit load analysis. These methods are detailed in Attachment 1. A through-wall flu size is postulated in order to perform a stmetural analysis. Additional monitoring is performed for a period of two (2) months on socket welds to assure the degradation mechanism is behaving in a manner expected for a MIC flaw. Page 3 of 7
l The structural integrity.for all weldfidentified with evidence of through-wat leakage will be monitored by the following methods: o Weekly visual monitoring of through-wall fla ws from the time ofide:itification until ; repair of the weld or completion of the structuralinteg,rity analysis. Repair of the ! weld or completion of the structural analysis is required within 14 days of detecting l a through wall flaw. If the welds are determised to be structurally acceptable then I the visual monitoring frequency will be decreased to once a month l o Weekly visual monitoring of tiuough-wall flaws in socket welds nd butt welds inaccessible to RT or UT examination for a period of two (2) menths. If there is, no ! significant change in the leakage rate the mon toring frequency will be decreased to monthly until the we!ds are repaired. 1 A significant change is defined as a 0.5 gpm increase in the leakage rate from the initial observed leakage condition for each wel:1. Should any lacation reach the threshold of a significant change the weld will be reassessed ihr structural integrity I and flood / spraying consequences o A total leakage rate limit of 1.0 gpm for a single supply or return line to an individual component will be established. If this total scakare rate limit is excee. led then an evaluation will be perfonned to determne if design service water flow ts available to affected components. Inadequate service wate r supply will cause the associated service water lines and equipment to be decl.ared inoperable and appropriate action will be taken according to Technical Specifications. The temporary non-code repair will be to leave the welds as they are found, subje et to monitoring and meeting the criteria for consequences and fbr :.tructural integrity as desciibed above. Eslu_ation Flaw Detection Dulingflant Op1 ration ani]montgliglity Ittigrmination The Service Water System is a coramon system for both if aits, at North Anr a Power Station. Both trains are required to be operational or the appropriate Tech deal Specification action statement be entered. The through-v all flaws on Sernce Water lines in service are anticipated based on the North Anna Powe" Station history of MIC. Virginia Electric and Power Company requests to evaler te the flaws and '. eave acceptable through-wall flaws in service in order to perform Code z ept. irs in control.ed conditions during schedaled sersice water outages. Page 4 of 7
'i 4 1 i 1:
!L Flaw characterization of MIC has traditionally been performed by radiography and has [ wide acceptance by the. industry as an appropriate technique. Virginia Power has also developed an ultrasonic technique which is as effective as radiography for detection and
;. length sizing ofMIC indications. This ultrasonic technique additionally has depth sizing !
I O capabilities. The acceptabililty of ultrasonics as an alternative to radiography is f documented in a report titled " Ultrasonic Examination Technique for Detection of I Microbiologically Induced Corrosion in North Anna Stainless Steel Service Water Piping" , dated December 29,1997. Virginia Power proposes to use either radiography or ultrasonics or both to characterize flaws. ] Root Cause Determination and Flaw Characterization [! The Service Water System at North Anna Power Station has previously experienced MIC. i Radiographic examinations of service water welds having evidence of through-wall
- j. leakage revealed small voids surrounded by exfoliation, which is typical of MIC. No other l 4 '
type ofinsenice defects were identified by the radiographs near the areas with j 4 through-wall leaks. Additionab a visual examination performed by a Virginia Electric l 4 and Power Company staff metailurgist of a sample of piping segments removed to repair l the leaking welds confirmed the presence of MIC. I 1 l l' , Flaw Evaluation
- Flaw evaluation for welds with through-wall leakage will be perforn'ed as described in !
7 Attachment 1. The flaws in butt welds that can be characterized by RT or UT l l examination methods will be evaluated by three types of analyses, area reinforcement, limit i load analysis, and fracture mechanics using the guidance from NRC Generic Letter 90-05.
- l The flaws in welds that can not be characterized by RT or UT examination, i.e. socket i welds and inaccessible butt welds, will be evaluated by the same analysis by assuming a !
3/4" hole for each point ofleakage within a weld with through-wall leakage. Socket ! welds will be analyzed by treating the cross section at the socket weld as equivalent pipe 1 cross section. l ~ l Page 5 of 7 1 N . = ,, - ,- 4 ~ -p, - - .-
L i IV. AUGMENTED INSPECTION j .-
- l. An augmented inspection program will monitor a sample of butt welds in the Service -
j' Water System using RT or UT examination methods will be performed every three (3) -
- months. The frequency of examination will be assessed after a year and may be adjusted j' for each location based on the results of the examinations. -
V. ALTERNATE PROVISIONS As an alternative to performing Code repairs in accordance with IWA-5250(a)(2) to
- through-wall flaws in the Service Water System the through-wall flaws will be left as is l The through-wall flaws will be monitored for leakage and must meet the criteria for
[ flooding and spraying consequences. Structural integrity must be determined as described herein to remain in service beyond 14 days from detection. If structural integrity is determined, operation in this mode will continue until the subject welds are replaced. All welds identified with through-wall flaws will be replaced within 18 months from the time ofdiscovery. The structural integrity of the Service Water System will be monitored by the following methods until the repairs required by IWA 5250(a)(2) are completed.- o Weekly visual monitoring of through-wa:1 flaws from the time ofidentification until repair or completion of structural integrity analysis. If the welds are determined to l . be structurally acceptable thn the visual monitoring frequency will be decreased to once a month. , i o All welds identified as having through-wall flaws and not repaired within 14 days of detection will be assessed for stmeturalintegrity within 14 days of detection. Butt l welds will be examined by RT or UT methods, if accessible, to characterize the ! flaws. Socket welds and butt welds inaccessible to RT or UT will be assessed for
]
structural integrity by assuming a conservative 3/4" diameter hole. Welds j determined to be structurally adequate will be included in the above monitoring j program. Identification of a stmeturally inadequate weld will result in the associated !' piping to be declared inoperable and the appropriate Technical Specification action statement to be tak'en. o~ Weekly visual monitoring of through-wall flaws in socket welds and butt welds inaccessible to RT or UT examination for a period of two (2) months. If there is no significant change in the leakage rate the monitoring frequency will be decreased to monthly until the welds are repaired. A significant change is defined as a 0.5 gpm increase in the leakage rate from the initial observed leakage condition for each weld. Should any location reach the l Page 6 of 7
)
m.. _ . . . _ _ - _ _ _ . _ . . . _ _ . _ - _ _ _ _ ._ _ _ . _ - _ _ . _ _ _ _ _ ._-. _ _ . l i ] threshol6 of a significant change the weld will be reassessed for structural integrity l and flood / spraying consequences. { ' l o Monthly walkdown of the accessible stainless steel portions of the Service Water
- System will be performed. The frequency of monthly walkdowns will be assessed after a year and adjusted based on the results of monthly inspections. ;
a e o A total leakage rate limit of 1.0 gpm for a single supply or return line for an j individual component will be established. If this total leakage rate limit is exceeded
. then an evaluation will be performed to determine if design service water flow is available to affected components. Inadequate service water supply will cause the associated service water linyand equipment to be declared inoperable and appropriate action will be taken according to Technical Specifications. ;
i o An augmented inspection program will monitor a sample of butt welds in the Service Water System using RT or UT examination methods. Examinations will be i performed every three (3) months. The frequency of examinations will be assessed ! after a year and may be adjusted for each location based on the results of the examinations. The proposed alternative stated above will ensure that the overall level of plant quality and safety will not be compromised. <
- VI IMPLEMENTATION SCHEDULE I This alternative to CodeIrequirements will be followed upon receiving NRC approval for ,
, the remainder of the second ten-year inspection intervals. The Unit I second ten-year i inspection interval will end on Debember 24,1998 and the Unit 2 second ten-year interval , will end on December 14,2000. - 4-Vll STATUS - Withdrawn Virginia Power Letter 98-037A dated 11-12-98 l , Attachments'
- 1. Flaw Evaluation Methods and Results 2 Drawing /Line Number Designations 4
i i
References:
- 1. USAS B31.1 Power Piping 1967 Edition i 2. EPRI Report NP 6301-D, " Ductile Fracture Handbook"
- 3. Nuclear Regulatory Commission Generic Letter 90-05 " Guidance for Performing Temporary
, Non Code Repair of ASME Code Class 1,2, and 3 Piping" , Page 7 of 7 ! t
l Virginia Electric & Power Company l Nonh Anna Power Station Unit I and Unit 2 Second 10 Year Interval l Request for ReliefNumber NDE-32, Revision 4 j I. IDENTIFICATION OF COMPONENTS Drawing # Service Water System ll715-CBB-40D-2 SHTS. I and 2 11715-CBM-78A-2 SHTS. I and 4 11715-CBM-78B-2 SHTS.1, and 3 11715-CBM-78C-2 SHT. 2 11715-CBM-78G-2 SHTS. I and 2 11715-CBM-78H-2 SHT.1 Components within the scope of this Request for Reliefinclude the welds and associated piping which comprise the moderate energy stainless steel piping of the Service Water System (SW). This piping system provics cooling water from the Service Water Reservoir to safety related equipment and return the Service Water back to the return headers. Normal operating pressure is 100 PSIG. The design pressure is 150 PSIG and the design temperature is 150*F. This is an ASME, Section XI, Class 3 system. Attachment 2 provides an identification of each piping segment within the scope of this Request for Relief. The piping segments are identified by their line number designation, which is a unique identifier. The graphics represented on the associated drawings of each piping segment along with the associated line number designation provide a defining boundary for each pipe segment. The identification of piping segments as components is appropriate as both the welds and piping forming the piping segments are subject to developing through well leaks.
- 11. IMPRACTICABLE CODE REQUIREMENTS The Service Water System has experienced through-wall leakage caused by Microbiological Influenced Corrosion (MIC). Chemical treatment of the Service Water System has not been effective in eliminating MIC. The Service Water System is being monitored for MIC. Identification of additional through-wall leakage is anticipated.
Through-wall leakage must be located and evaluated in accordance with the requirements ofIWA-5250 of the 1983 Edition and Summer 1983 Addenda for Unit I and 1986 Edition for Unit 2. The specific Code requirement for which reliefis requested is IWA-5250(a)(2). Page 1 of 7 l l 0
i i l "IWA-5250 Corrective Measures: (a) The source ofleakage detected during the conduct of a system pressure test shall be located and evaluated by the Owner for corrective measures as follows:.. (2) repairs or replacements of components shall be performed in accordance with IWA-4000 or IWA-7000, respectively." Articles IWA-4000 and IWD-4000 of ASME Section XI Code repair requirements would require removal of the flaw and subsequent weld repair, i
- Code repairs for through-wall leaks require the line to be isolated and drained. Taking a train of service water out of service in some instances is a major evolution and requires
- entering a Technical Specification action statement. Welds and piping with through-wall flaws caused by MIC can typically be shown to have adequate structural integrity to remain in service. This type of through-wall flaw is unpredictable but not normally subject to catastrophic failure. It is impractical to require a Code repair within the time specified by the Technical Specification Limiting Condition for Operation every time a through-wall flaw is identified.
i , i Generic Letter 90-05, " Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2, and 3 Piping", provides guidance for submitting relief requests to allow , continued operation with a through-wall flaw. Submitting a relief reguest for each j- instance of through-wall leakage caused by MIC : an administrative burden and causes i additional unnecessary reviews for the NRC. Implementing GL 90-05 each time a
- through-wall flaw is identified is also impractical.
, This relief request (NDE-32, Revision 4) establishes a plan for continued operation with l through-wall flaws in stainless steel piping in the Service Water System based upon the guidance of GL 90-05 to the extent it is believed practical. This relief request will be
- implemented upon receiving NRC approval. In the interim, relief request NDE-32, j Revision 2 will be followed for through-wall flaws in this system.
4 [ 111. ISI BASIS FOR RELIEF REQUEST j This relief request is submitted in a format laid out in 'NRC GL 90-05. The following [ information and justification is provided in accordance with the guidelines of Part B and C of Enclosure 1 to GL 90 05. i Sep.p_e Limitations and Specific Considerations I Scope The scope consists of welds and stainless steel piping, pipe class 153 A and 163, with evidence of possible through-wall leaks in the Service Water System at North Anna Power Station Units 1 and 2. l l Page 2 of 7 ]-
. - - _ ~
. ~ _ _ _ _ - - _ ._ _ . ._ .____ _ _ ___.._ _ _ .,
l Limitations - Based on radiographic examinations and laboratory examinations of removed portions of ! piping from replacements, North Anna Power Station is experiencing MIC in its stainless ' steel piping. The MIC-caused flaws originate on the inner diameter of the pipe. The Service Water System is common to both Units. As long as one Unit is in Mode 1,2,3, or 4 both trains of service water must be operable. If both Units are in Mode 5 or 6 then l one train of Service Water must be operable. The intent of this reliefis to permit i continued operation with the identified through-wall flaws until repairs are accomplished in a scheduled service water outage. Specific Consideratiom ' System interactions, i.e. consequences of flooding and spray, will be evaluated. Piping with l through wall leakage that could affect plant safety related equipment will be declared inoperable and the appropriate Technical Specification action statement entered. l Welds containing evidence of through wall flaws will be either repaired or assessed for stmetural integrity within 14 days ofdetection. Butt welds and piping remaining in service after leakage is 1 detected for longer than 14 days and accessible to volumetric examination by Ultrasonic (UT) or l Radiographic (RT) examination methods, will be evaluated for structural integrity for all design loading conditions, including dead weight, pressure, thermal expansion and seismic (DBE) loads. . The methods used in the stmetural integrity analysis will consist of area reinforcement, fracture mechanics, and limit load analysis. These methods are detailed in Attachment 1. The welds that are found to be unacceptable will be declared inoperable and the appropriate Technical Specification action statement entered. A 3/4" hole will be postulated for any location with a through-wall flaw that can not be characterized volumetrically by ultrasonics (UT) or radiography (RT), socket welds and welds that are inaccessible for UT or RT. Laboratory examination of cut sections of MIC degraded socket weld samples indicate that
~f laws are enveloped within the 3/4" size. A leaking socket weld location will be analyzed by treating the cross section as equivalent to the cross section of the attached pipe with a 3/4" hole. The methods used in the structural integrity analysis will consist of ara reinforcement, fracture mechanics, and limit load analyses These methods are detailed in Attachment 1. A through-wall flaw size is postulated in order to perfomi a structural analysis. Additional monitoring is performed for a period of two (2) months on socket welds to assure the degradation mechanism is behaving in a manner expected for a MIC flaw.
The stmetural integrity for all welds identified with evidence of through-wall leakage will be i monitored by the following methods:
. Weekly visual monitoring of through-wall flaws from the time ofidentification until )
repair of the weld or completion of the structural integrity analysis. Repair of the l weld or completion of the structural analysis is required within 14 days of ' detecting a through wall flaw. If the welds are determined to be structurally Page 3 of 7
l- acceptable, then the visual monitoring frequency will be decreased to once every six weeks. 4 L e Weekly visual monitoring of through-wall flaws in socket welds and butt welds t inaccessible to RT or UT exammation for a period of two (2) months. If there is no ! significant change in the leakage rate, the monitoring frequency will be decreased to
- once every six weeks until the welds are repaired. - A signi6 cant change is dermed as a
- 0.5 gpm increase in the leakage rate from the initial observed leakage condition for j each weld. Should any location reach the threshold of a significant change the weld
, will be reassessed for structural integrity and flood / spraying consequences. t ! . A total leakage rate limit of 1.0 gpm for a single supply or return line to an individual 4 component will be established. If this total leakage rate limit is exceeded then an 1 evaluation will be performed to determine if design service water flow is available to , affected components. Inadequate service water supply will cause the associated i service water lines and equipment to be declared inoperable and appropriate action will - j be taken according to Technical Specifications. i !- The temporary non-code repair will be to leave the welds as they are found, subject to , , monitoring and meeting the criteria for consequences and for structural integrity as described i above. i Evaluation Flaw Detection During Plant Operation and Imoracticality Determination i The Service Water System is a common system for both Units at North Anna Power Station. ! Both trains are required to be operational or the appropriate Technical Specification action j statement is entered. The through-wall flaws on Service Water lines in service are anticipated i I based on the Nonh Anna Power Station history of MIC. Virginia Electric and Power Company requests to evaluate the flaws and leave acceptable through-wall flaws in service in order to perform Code repairs in controlled conditions during scheduled service water outages. Flaw characterization of MIC has traditionally been performed by radiography and has wide acceptance by the industry as an appropriate technique. Virginia Power has also developed an ultrasonic technique, which is as effective as radiography for detection and length sizing of MIC indications. This ultrasonic tecimique additionally has depth sizing capabilities. The acceptability of ultrasonics as an alternative to radiography is documented in a report titled " Ultrasonic Examination Technique for Detection of Microbiologically Induced Corrosion in North Anna Stainless Steel Service Water Piping" dated December 29,1997. Virginia Power proposes to use either radiography or ultrasonics or both to characterize flaws. i l Page 4 of 7 a
4 3 Root Cause Determination and Flaw Characterization i j The Senice Water System at North Anna Power Station has previously experienced MIC. Radiograph j examinations of service water welds having evidence of through-wall leakage revealed small voids 4 ' surrounded by exfoliation, which is typical ofMIC. No other type ofinsenice defects were identified by the radiographs near the areas with through-wall leaks. Additionally, a visual examination performed by a Virginia Electric and Power Company staff metallurgist of a sample of piping segments removed to repair the leaking welds confumed the presence ofMIC. Flaw Evaluation Flaw evaluation for welds with through-wall leakage will be performed as described in Attachment 1. The flaws in butt welds that can be characterized by RT or UT examination methods will be evaluated by three types of analyses, area remforcement, limit load analyses, and fracture mechanics using the guidance from NRC Generic Letter 90-05. The flaws in welds that cannot be characterized by RT or in examination, i.e., socket welds and inaccessible butt welds, will be evaluated by the same anuysis by assuming a 3/4" hole for each point ofleakage within a weld with through-wallleakage. Socket welds will be analyzed by treating the cross section at the socket weld as equivalent pipe cross section. IV. AUGMENTED INSPECTION An augmented inspection program will monitor a sample of ten (10) butt welds in the Senice Water System using RT or UT examination methods. RT or UT examination methods will be performed every three (3) months. The frequency of radiography will be assessed after a year and may be adjusted for each location based on the results of the radiographs. V. - ALTERNATE PROVISIONS As an altemative to performing Code repairs in accordance with IWA-5250(a)(2) to through-wall flaws in the Service Water System the through-wall flaws will be left as is. The through-wall flaws will be monitored for leakage and must meet the criteria for flooding and spraying consequences. Structural integrity must be determined as described herein to remain in service beyond 14 days from detection. If stmetural integrity is determined, operation in this mode will continue until the subject welds are replaced. All welds identified with through-wall flaws will be replaced within 18 months from the time ofdiscovery. The stmetural integrity of the Senice Water System will be monitored by the following methods until the repairs required by IWA 5250(a)(2) are completed. Weekly visual monitoring of through-wall flaws from the time ofidentification until repair or completion of structural integrity analysis. If the welds are determined to be stmeturally acceptable then the visual monitoring frequency will be decreased to once every six weeks. Page 5 of 7 4 e -~4 +.. -, - , . -m, < .-, - . - - _ _ - - , ~ , - . - - - - - + -
- - , . - + --
w - - . -
l All welds identified as having through-wall flaws and not repaired within 14 days of detection, will be anaauaA for stmeturalintegrity within 14 days of detection. Butt welds will be examined by L RT or UT methods, if accessible, to characterize the flaws. Socket welds and butt welds maccessible for RT or UT examinations will be assessed for structural integrity by assuming a ; conservative %" diameter hole. Welds determined to be stmeturally adequate will be included in i the above monitoring program. Identification of a stmeturally inadequate weld will result in the ! associated piping to be declased inoperable and the appropriate Technical Specification action statement to be taken. 4
. Weekly visual monitoring of through-wall flaws in socket welds and butt welds inaccessible to RT or UT examination for a period of two (2) months. If there is no significant change in the leakage rate, the monitoring frequency will be decreased to once every six weeks until the welds are repaired. -A significant change is defined as a 0.5 gpm increase in the leakage rate from the initial observed leakage condition for each weld. Should any location reach the threshold of a significant ,
change, the weld will be reassessed for stmetural integrity and flood / spraying consequences ' l A walkdown of the accessible stainless steel portions of the Senice Water System will be
- performed every six weeks. This inspection frequency is based on a 12 week Maintenance Rule e schedule, which reduces the time equipment is out of service for testing and maintenance. Two one week windows, six weeks apart, are available within this schedule to perform service water repairs.
Performing inspections within this schedule will allow repairs to be made in a timely manner and reduce the time safety related equipment is out of service. The frequency of the walkdowns will be assessed after a year and adjusted based on the results of the inspections. A total leakage rate limit of 1.0 gpm for a single r,pply or return line for an individual component will be established. If this total leakage rate limit is exceeded then an evaluation will be performed to determine if design service water flow is available to affected components. Inadequate service water supply will cause the associated service water lines and equipment to be declared inoperable and appropriate action will be taken according to Technical Specifications.
- An augmented inspection program will monitor a sample of ten (10) butt welds in the Senice I Water System using RT or UT examination methods. Examinations will be performed every three (3) months. The frequency of radiography will be assewd after a year and may be adjusted for each location based on the results of the radiographs.
The proposed alternative stated above will ensure that the overall level of plant quality and safety will not , be compromised. Page 6 of 7
i VI IMPLEMENTATION SCHEDULE This alternative to Code requirements will be followed upon receiving NRC approval for the remainder of the second ten-year inspection intervals. The Unit I second ten-year m' spection interval will end on
. April 30,1999 and will be extended, as allowed by Code Case N-535, to April 30,2000 to coincide with a plant outage. The Unit 2 second ten-year interval will end on December 14, 2000 and will be extended, as allowed by Code Case N-535, to April 30,2001 to coincide with a plant outage. The NRC in a letter dated May 29,1998 approved code Case N-535, for both units.
VII STATUS Pending - Virginia Power Letter 98-037A dated I l-12-98 ,. Attachments:
- 1. Flaw Evaluation Methods and Results
. 2. Drawing /Line Number Designations
References:
- 1. USAS B31.1 Power Piping 1967 Edition -
- 2. EPRI Report NP-6301-D, " Ductile Fracture Handbook"
- 3. Nuclear Regulatory Commission Generic Letter 90-05 " Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2, and 3 Piping" Page 7 of 7
).
Attachment 1 ReliefRequest NDE-32, Revision 4 Flaw Evaluation Methods and Results Introduction Butt welds identified as having possible through-wall leaks will be volumetrically examined by radiographic (RT) or ultrasonic (UT) methods, if accessible. Flaws in butt welds that are inaccessible for examination will be postulated as a 3/4" hole for each area identi6ed with a through-wall flaw. All butt welds will be analyzed for stmetural integrity by three methods, area reinforcement, limit load analy sis, and linear elastic fracture mechanics evaluation. Flaw size in socket welds identified as having possible through-wall leaks cannot be characterized by nondestructive examination. A conservatively large hole, 3/4", will be postulated for each area identified with a through-wall flaw. The postulated flaw will be~ ! analyzed for structural integrity by treating the cross section as equivalent to the cross section ofthe attached pipe. Area Reinforcement Analysis - The area reinforcement analysis is used to determine if adequate reinforcing exists such that ductile tearing would not occur. The guidelines of ANSI B31.1 paragraph 104.3.(d) 2 (reference 1) are used to determine the Code required reinforcing area. The actual reinforcing area is calculated and is checked against the required reinforcement area. The Code required reinforcement area in square inches is defined as: 1.07(tm)(d1) Where tm is the code minimum wall, and di is the outside diameter The Code reinforcement area required is provided by the available material around the flaw in the reinforcing zone. Limit Load Analysis The structural integrity of the piping in the degraded condition will be established by calculating the minimum margin of safety based upon a Limit Load Analysis. These methods are documented in EPRI report NP-6301-D (Ductile Fracture Handbook) . (reference 2). MR = 4MY'* MZ'+ 7" Page 1 of 3
1 l The limit load analysis of the postulated flawed sections will be performed with a material flow stress representing the midpoint of the ultimate strength and yield point stress. The flawed sections will be subjected to deadweight, thermal, and seismic DBE loading. The allowablelimitloadis given by, Ma = 2 sf Rm2 t-(2cos(b)-sin (Q)) in-lbf sf = flow stress = 0.5 (Sy + Su) psi Sy = yield stress psi Su = ultimate stress psi Rm = mean radius of the pipe p _ e , fl (Rf
- P)+F 2 4*ar*R.*t Ri = internal radius of the pipe P = pressure psig F = axial load in Ibs t = pipe thickness = inches D = Outside diameter inches 0 = half angle of the crack (radians) = crack length 2Rm
- MR = Resultant Moment MY = Bending Moment MZ = Bending Moment T = Torsion The calculated factor'ofsafety is, FS = .hia (MR)
The minimum factor of safety of 1.4 is required to be qualified for continued operation. Eracture Mechanics Evaluation A linear elastic fracture mechanics analysis will be performed for circumferential through- I wall crack using the guidance provided in NRC Generic Letter 90-05. The stmetural 1 integrity of the piping in the degraded condition was established by calculating the minimum margin of safety based upon a Fracture Mechanics evaluation. This method is documented ; in EPRI report NP-6301-D (Ductile Fracture Handbook) (reference 2). Page 2 of 3 l l l
1 ' A through-wall circumferential crack will be postulated for every area containing MIC. The cracks will be subjected to a design pressure loading in addition to the deadweight, normal operating thermal and seismic DBE loadings. For the purpose of this evaluation a generic allowable stress intensity factor of KIC = 135 ksi (in.)" will be used for the stainless steel material per NRC GL 90-05. The applied stress intensity factor for bending, KIB,-is found by: KlB = [sb-(p Rm-Q)0.5] Fb The applied stress intensity factor for internal pressure, KIP, is found by: KIP = sm-(p Rm-Q)0.5 Fm ' The applied stress intensity factor for axial tension, KIT is found by: KIT = st-(p Rm-Q)0.5 Ft The stress intensity factor for residual stresses, KIR is found by: KIR = S-(p Rm-Q)0.5 Ft Total applied stress intensity KT includes a 1.4 safety factor and is calculated by: KT = 1.4-(KIB + KIP + KIT) + KIR The allowable stress intensity factor is taken from Generic Letter 90-05. KALL = 135 ksiGin Stress Intensity Factor Ratio is defined as: SR = KL KALL The stress intensity factor ratio shall be less than 1.0 for continued operation. Page 3 of 3
l ATTACHMENT 2 ReliefRequest NDE-32 Revision 4 List of drawings containing the Service Water System and the associated line number designations for
- pipe class 153A and 163.
DRAWING 11715-CBB-040D-2, SHEET 1 1-1/4"-WS-G37-153A-Q3 4"-WS-G01-163-Q3 3/4"-WS-F83-163 4"-WS-F99-163-Q3 3/4"-WS-F82-163-Q3 DRAWING 11715-CBB-040D-2, SHEET 2 1 1/4"-WS-H78-153 A-Q3 1-1/4"-WS-H81-153 A-Q3 DRAWING 11715-CBM-078A-2, SHEET 1 3/4"-WS-G31-163-Q3 3/4"-WS-F67-163-Q3 3/4"-WS-H77-163-Q3 4"-WS-F64-163-Q3 4"-WS-H76-163-Q3 3/4"-WS-F80-163-Q3 3/4"-WS-G30-163-Q3 3/4"-WS-F68-163-Q3 3/4"-WS-339-163-Q3 4"-WS-F65-163-Q3 3/4"-WS-G36-163-Q3 3/4"-WS-F69-163-Q3 3/4"-WS-930 163-Q3 8"-WS- 93-163-Q3 1/2"-WS-F61- a a -Q3 8"-WS- 94-163-Q3 2"-WS-D72-163-Q3 4"-WS-F62-163-Q3 3/4"-WS-F78-163-Q3 3/4"-WS-F66-163-Q3 4"-WS-F63-163-Q3 3/4"-WS-F79-163-Q3 4"-WS-G35-163-Q3 %"-WS-F81-163-Q3 l DRAWING 11715-CBM-078A-2, SHEET 4 8"-WS-515-163-Q3 8"-WS-516-163-Q3 8"-WS-513-163-Q3 8"-WS-514-163-Q3 4"-WS-H48-163-Q3 3/4"-WS-F64-163-Q3 3/4"-WS-H52-163-Q3 3/4"-WS-H53-163-Q3
. 4"-WS-H50-163-Q3 3/4"-WS-H66-163-Q3 3/4"-WS-H54-163-Q3 4"-WS-H51-163-Q3 ,
3/4"-WS-H67-163-Q3 3/4"-WS-H55-163-Q3 > 3/4"-WS-G32-163-Q3 3/4"-WS-G33-163-Q3 8"-WS-115-163-Q3 8"-WS-116-163-Q3 ( 8"-WS-113-163-Q3 4"-WS- 46-163-Q3 4"-WS- 47-163-Q3 2"-WS-926-163-Q3 Page 1 of 5
DRAWING.11715-CBM-078A-2, SHEET 4, (Continued) 3/4"-WS-H60-163-Q3 ' 3/4"-WS-H61-163-Q3 - 3/4"-WS-H62-163-Q3 3/4"-WS-H63-163-Q3 4"-WS- 56-163-Q3 . 4"-WS- 57-163-Q3 4"-WS-H49-163-Q3 %"-WS-H65 163-Q3 l 8"-WS-114-163-Q3
. DRAWING ll715-CBM-078B-2, SHEET 1 1-1/2"-WS-346-163-Q3 1"-WS-347-163-Q3 1"-WS-G06-163-Q3 1-1/2"-WS-347-163-Q3 1-1/2"-WS-348-163-Q3 1"-WS-349-163-Q3 1"-WS-G05-163-Q3 1-1/2"-WS-349-163-Q3 1-1/2"-WS-350-163-Q3 - 1"-WS-351-163-Q3 1"-WS-G04-163-Q3 1-1/2"-WS-351-163-Q3 1-1/2"-WS-352-163-Q3 .1"-WS-353-163-Q3 1"-WS-G03-163-Q3 1-1/2"-WS-353-163-Q3 l
DRAWING 11715-CBM-078B-2, SHEET 3 1-1/2"-WS-724-163-Q3 1"-WS-725-163-Q3 ' 1"-WS-933-163-Q3 1-1/2"-WS-725-163-Q3 l-l/2"-WS-726-163-Q3 1"-WS-727-163-Q3 1"-WS-924-163-Q3 1-1/2"-WS-728-163-Q3 1"-WS-729-163-Q3 1"-WS-935-163-Q3 1-1/2"-WS-729-163-Q3 1-1/2"-WS-730-163-Q3 1"-WS-731-163-Q3 1"-WS-936-163-Q3 1-1/2"-WS-731-163-Q3 1-1/2"-WS-727-163-Q3 I DRAWING 11715-CBM-078C-2, SHEET 2 4"-WS- 46-163-Q3 1"-WS- 85-163-Q3 3/4"-WS-A47-163-Q3 1"-WS-485-163-Q3 1"-WS- 81-163-Q3 1"-WS-487-163-Q3 1"-WS- 77-163-Q3 1"-WS-489-163-Q3 1"-WS-477-163-Q3 1"-WS-491-163-Q3 1"-WS-481-163-Q3 3"-WS- 75-163-Q3 - 3"-WS- 7N 33-Q3 3"-WS- 76-163-Q3 4"-WS- 47-163-Q3 3/4"-WS- 79-163-Q3 3/4"-WS-A49-163-Q3 3/4"-WS-381-163-Q3 1"-WS- 82-163-Q3 2"-WS- 80-163-Q3 1"-WS- 78-163-Q3 3/4"-WS- 83-163-Q3 1"-WS-478-163-Q3 3/8"-WS-383-163-Q3 Page 2 of 5 l
- .- .-. -- . ~ . - . _ - - -_
l 11715-CBM-078C-2, SHEET 2 (Cont'd) 1"-WS-482-163-Q3 3/8"-WS-382-163-Q3 3"-WS- 74-163-Q3 2"-WS-376-163-Q3 l 4"-WS- 56-163-Q3 3/8"-WS-397-163-Q3 ! 3/4"-WS-A48-163-Q3 3/8"-WS-398-163-Q3 l 1"-WS- 90-163-Q3 2"-WS-377-163-Q3 3/4"-WS-C06-163-Q3 3/8"-WS-C01-163-Q3 1"-WS- 92-163-Q3 3/8"-WS-399-163-Q3
' 1"-WS- 86-163-Q3 3/4"-WS-378-163-Q3 3/4"-WS-C01-163-Q3 2"-WS- 84-163-Q3 1"-WS-488-163-Q3 3/4"-WS-379-163-Q3 l 3/4"-WS-913-163-Q3 1"-WS- 88-163-Q3 1 1"-WS-490-163-Q3 3/4"-WS-380-163-Q3 - l' 1"-WS- 78-163-Q3 3/4"-WS- 83-163-Q3 1"-WS-492-163-Q3 3/8"-WS-383-163-Q3 4"-WS- 57-163-Q3 3/4"-WS-A50-163-Q3 '
3/4"-WS-773-163-Q3 1"-WS- 89-163-Q3 2"-WS-772-163-Q3 3/4"-WS-400-163-Q3 3/8"-WS-910-163-Q3 3/4"-WS-774-163-Q3 3/8"-WS-914-163-Q3 2"-WS-775-163-Q3 2"-WS-776-163-Q3 3/8"-WS-913-163-Q3
~'
3/8"-WS-916-163-Q3 3/8"-WS-915-163-Q3 2"-WS-777-163-Q3 3/4"-WS-779-163-Q3 1"-WS-486-163-Q3 3/4"-WS-909-163-Q3 3/8"-WS-912-163-Q3 DRAWING 11715-CBM-078G-2, SHEET 1 2"-WS-D46-153A-Q3 2"-WS-C88-153 A-Q3 1"-WS-D50-153A-Q3 2"-WS-C81-153 A-Q3 3/4"-WS-D39-153 A-Q3 2"-WS-C87-153 A-Q3 1"-WS-D30-153A-Q3 2"-WS- 63-163-Q3 3/4"-WS-D41-153A-Q3 3/4"-WS-D61-163-Q3 3/4"-WS-D55-163-Q3 2"-WS- 62-163-Q3
' 1"-WS-D31-153 A-Q3 2"-WS-C80-153 A-Q3 3/4"-WS-D43-153 A-Q3 3/4"-WS-C67-153A-Q3 l
3"-WS- 73-163-Q3 3/4"-WS-C73-153 A-Q3 2"-WS- 54-163-Q3 3/4"-WS-C76-153A-Q3 2"-WS- 52-163-Q3 3/4"-WS-C70-153A-Q3 ; 3/4"-WS-D67-163-Q3 2"-WS-C86-153 A-Q3 ) 2"-WS- 50-163-Q3 2"-WS- 79-153 A-Q3 3"-WS- 74-163-Q3 2"-WS-C85-153A-Q3 Page 3 of 5 l
~.
11715-CBM-078G-2, SHEET 1 (Continued) 2"-WS- 55-163-Q3 3/4"-WS-D62-163-Q3 3/4"-WS-D54-163-Q3 2"-WS- 60-163-Q3 2"-WS- 53-163-Q3 3"-WS- 75-163-Q3 3/4"-WS-D68-163-Q3 _ 3/4"-WS-D69-163-Q3 2"-WS- 51-163-Q3 2"-WS- 61-163-Q3
' 3/4"-WS-D56-163-Q3 3/4"-WS-D70-163-Q3 2"-WS-C83-153 A-Q3 3"-WS- 76-163-Q3 -
,2"-WS-C89-153 A-Q3 2"-WS-C78-153A-Q3 3/4"-WS-D60-163-Q3 - 3/4"-WS-C66-153A-Q3 2"-WS- 64-163-Q3 3/4"-WS-C72-153A-Q3 2"-WS- 65-163-Q3 3/4"-WS-C75-153 A-Q3 2"-WS-C82-153A-Q3 3/4"-WS-C69-153 A-Q3 3/4"-WS-C68-153 A-Q3 2"-WS-C84-153 A-Q3 3/4"-WS-C74-153A-Q3 3/4"-WS-C77-153A-Q3 3/4"-WS-C71-153A-Q3 DRAWING 11715-CBM-078G-2, SHEET 2 2"-WS-D46-153 A-Q3 3/4"-WS-D65-163-Q3 3/4"-WS-D71-153A-Q3 3/4"-WS-D66-163-Q3 1"-WS-D47-153A-Q3 3/4"-WS-934-153A-Q3 3/4"-WS-D33-153A-Q3 2"-WS-948-153 A-Q3 3/4"-WS-D51-163-Q3 3/4"-WS-940-153 A-Q3 1"-WS-D48-153 A-Q3 1-1/2"-WS-976-153 A-Q3
- 3/4"-WS-D35-153 A-Q3 1-1/2"-WS-982-153 A-Q3 3/4"-WS-D52-163-Q3 3/4"-WS-943-153 A-Q3 1"-WS-D49-153 A-Q3 3/4"-WS-937-153A-Q3 3
3/4"-WS-D37-153 A-Q3 2"-WS-954-153 A-Q3 3/4"-WS-D53-163-Q3 2"-WS-947-153A-Q3 3"-WS- 73-163-Q3 1-1/2"-WS-977-153 A-Q3 3/4"-WS-D63-163-Q3 1-1/2"-WS-963-153A-Q3 , 3" WS- 74-163-Q3 2"-WS-953-153 A-Q3 2"-WS-454-163-Q3 3/4"-WS-D58-163-Q3 , 2"-WS-455-163-Q3 2"-WS-462-163-Q3 2"-WS-452-163-Q3 . 2"-WS-463-163-Q3 2"-WS-453-163-Q3 2"-WS-946-153A-Q3 2"-WS-450-163-Q3 1-1/2"-WS-979-153A-Q3 . 2" _WS-451-163-Q3_ l-1/2"-WS-978-153A-Q3 2"-WS-949-153 A-Q3 2"-WS-952-153A-Q3 1-1/2-WS-981-153 A-Q3 2"-WS-945-153A-Q3 1-1/2"-WS-965-153 A-Q3 1-1/2"-WS-980-153A-Q3 2"-WS-955-153A-Q3 1 1/2"-WS-9@l53A-Q3 i Page 4 of 5
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l DRAWING 11715-CBM-078G-2, SHEET 2 (Continued) i 3/4"-WS-D57-163-Q3 2"-WS-460-163-Q3 2"-WS-464-163-Q3 2"-WS-945-153 A-Q3 2"-WS-465-163-Q3 2"-WS-944-153 A-Q3 3"-WS- 75-163-Q3 1-1/2"-WS-975-153A-Q3 3"-WS- 76-163-Q3 1-1/2"-WS-971-153 A-Q3 3/4"-WS-D59-163-Q3 2"-WS-950-153A-Q3 l 2"-WS-461-163-Q3 2"-WS-951-153A-Q3 I
)
i DRAWING 11715-CBM-078H-2, SHEET 1 j 1"-WS- 9-163 1"-WS- 10-163 3/4"-WS-E03-163 3/4"-WS-F45-163 l 3/4"-WS-F44-163 2"-WS-E64-163 l
' 1"-WS-G07-163 1/2"-WS-E68-163 I 3/4"-WS-E08-163 1"-WS-D97-163 l 1"-WS-947-163 2"-WS-D91-163 !
1"-WS-G50-163 1"-WS-H48-163 . 1"-WS-G52-163 l l l l I l l l l Page 5 of 5
Virginia Electric & Power Comp 2.ny North Anna Power Station Unit 2 Second 10 YearInterval .. Request for ReliefNumberNDE-33
- 1. IDENTIFICATION OF COMPONENTS Mark / Weld # Lind Drawinn# Qan 9 27%"-RC-403-250lR-Q1 12050-WMKS-109E-1 1-20 31"-RC-405-2501R-Q1 12050-WMKS-109F-1 1 II. IMPRACTICABLE CODE REQUIREMENTS The 1986 edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.11 does not allow any limitations to the required volumetric or surface exammations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, ifit is less than 10%.
IB. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED
' Reliefis requested from exanuning the Code required volume for the identi6ed pipe-to-pump welds.
IV. BASIS FOR RELIEF L The components listed above have been examined to the extent practical as required by the Code. The Code required volumetric exammation coverage was reduced due to weld joint geometry, and the material type from which the components are constructed. The scope of volumetric examination covuage completed for the above listed welds is listed in Table NDE-33-1. Figures NDE-33-1 and NDE-33-2 are provided detailing the limitations experienced. These welds are classified as terminal ends and are required to be examined by the ISIProgram. V. ALTERNATEPROVISIONS It is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements. In addition:
- 1. . A visual (VT-2) examination will be performed during the normally scheduled system leakage tes; each refueling outage;
- 2. Technical Speci6 cations requires that the reactor coolant system leak rate be limited to one gallon :
per minute unidenti6ed leakage. This value is calculated at least once pa 72 hours; and Page 1 of 3
- 3. The containment atmosphere particulate radioactivity is monitored every 12 hours.
The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised. VI. STATUS Granted - NRC Letter No. 97-457 Dated 7/29/97. t NDE 33 Pope 2 of 3
e t 1 Table NDE-33-1 North Anna Unit 2 ^ Examination Coverage Estimates Category B-J, Item B9.11-
?
UT . Coverage t Surface Examination % Mart / welds 2 5 7 0 Cov* rage t Peason for Partial Examination O 97 0 50 5e 100 .p orrie and weld joint conf ;suratica and material type (ASTM n-351 austeettic steel casting 11mit the use of an extended V-path examination. The ?seld was esamined to the maximum extent practical using 45* and 60* RTD search units f t.m the loop pipe side. Approxicately 974 ' of the lower 1/3 of the weld eras covered in the 2 direction. 20 0 100 100 100 100 Norrie and weld joint configuration and materlat type (ASTM A-351 austealtic steel rasting) !! nit the use of an extended V-path examination. The weld was examined to the maximuss estent practical using 45* and 60* RTD search units frees the loop pipe side. Approximately 100% of the lower 1/3 of . - the weld was covered in the 5 direction. i UT Scan Direction Definitions 2 - Amial scan, 100 degrees from isometric flow direction tweld countl. 9 - Axial scan, the same direction as the isometric flow tweld count). 7 - Circumferential scan, clockwise rotatios when viewing la the direction of isoeetric flow. 8 - Circumferential sean, counterclockwise rotation when viewing in the direction of isometric flow. 1 Page 3 of 3 i
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Virginia Electric & Power Company North Anna Power Station Unit 2
.- Second 10 YearInterval Request forReliefNumberNDE-34 Il IDENTIFICATION OF COMPONENT Mark / Weld # Lind Diawmn# _ Class SW-13 '6"-RC. 437-1502-Q1 12050-WMKS-Il0A-1 1 II.- IMPRACTICABLE CODE REQUIREMENTS The 1986 edition of ASME Seedon XI Table IWB-2500-1, examination category B-J, item number B9.11 does not allow any limitations to the required volumetric or_ surface examinations. Code Case N460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, ifit is less than 10%.
III. CODE REQUIREMENT FROM WHICH. RELIEF IS REQUESTED Reliefis requested from examining the Code required volume for the identified pipe-to-flange weld. IV. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. Due to interference by an existing pipe support, only 6 inches out of 21 inches were examined The reduction in coverage is detailed in Table NDE-34-1. Figure NDE-34-1 is provided detathng the limitations expenenced. This weld is classified as a terminal end and is required to be examined by the ISI Program. V. ALTERNATEPROVISIONS It is proposed that the exammation already completed at the reduced coverage be counted as meeting the Code requirements. In addition:
- 1. A visual (VT-2) examination will be perfonned during the normally scheduled system leakage test each refueling outage;
- 2. Technical Specifications requiru i n the reactor coolant system leak rate be knuted to one gallon per minute unidentified leakage. 'Ihi. wae is calculated at least once per 72 hours; and
- 3. The containment atmosphere particulate radioactivity is monitored every 12 hours. ;
Page 1 of 3 1 4
]
The proposed alternative exammations stated above will ensure that the overall level of plant quality and safety will not be compromised. VI. STATUS Granted - NRC Letter No. 97-457 Dated 7/29/97. a E P u 4 1 6 i NDE.35 Page 2 of 3 i 1
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North Anna Unit 2 Examination Coverage Estimates 12050-IfMKS-110A-1 Category B-J, Item B9.11 UT scan Coverage 4 Surface Examination - Mark /Neidt 2 5 7 8 Coverage 4 Reason For Partial ,5 SW-1328 28 25 25 28 Pipe support limits examination to 6 inches out of 20.8 inches. UT scan Direction Definitions 2 - Amial scan, 100 degrees from isometric flow direction. 5 - Axial scan, the same direction as the isometric flow. 7 - Circumferential scan, clockwise rotation when eiewing la the direction of isometric flow. 8 - Circumferential scan, counterclockwise rotation when viewing in the direction of isometric flow. Page 3 of 3
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b - North Anna Powe: Station Unit 2 Second 10 WarInterval >
. Request forRelief Number NDE-35
- I. IDENTIFICATION OF COMPONENT Mark /Weldt Drawinn* .Clau
^
, 1 12050-WMKS-RC-R-1.1 1 , II. IMPRACTICABLE CODE REQUIREMENTS The 1986 edition ofASME Section XI Table IiVB-2500-1, examination category B-A, item number Bl.40 does not allow any limitations to the requircd volumetne or surface examinations. Code Case N-460, Alternative Examination Coverage for Class t and Clast 2 Welds, allows a reduction in coverage, ifit is ' hss than 10%. III. CODE REQUIREMENT FROM WHICH FELIEF IS REQUESTED Reliefis requested from examming the Code required volume for the identified head-to-flange weld. IV. BASIS FOR RELIEF The component listed above has been exrnined to the extent practical as required by the Code. Due to the i joint configuration and a lifting lug the rec uired volume could not be examined. The reduction in coverage H is detailed in Table NDE-35-1. Figures NDE-35-1 and NDE-35-2 are provided detailing the limitations experienced.
- V. ALTERNATEPROVISIONS It is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements. In addition:
- 1. A visual (VT-2) exammatior, will t'e performed during the normally scheduled system leakage test each refueling outage;
- 2. Technical Specifications requirer that the reactor coolant system leak rate be limited to one gallon per minute unidentified lea' cage. This value is calculated at least once per 72 hours; and 3.- The containment atmosphere particulate radioactivity is monitored every 12 hours.
l 1 Page 1 of 3
. . . -. - -. - . . ~ . . . .. . .. .-.. .- .
9 g 4 fI - The proposed alternative examinations stated above~will ensure that the overall level of plant quality i and safety willnot be compromised. VL - ' STATUS l Gran'ted - NRC Letter No. 97-457 Dated 7/29/97. i' 1
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4 NDE-35 Page 2of 3 ! I i I a
Table NDE-35-1 North Anna Unit 2 Examination Coverage Estimates (Reactor Vessel) Category B-A, Item Bl.40 Mark /Weg team Angle Emait Area Scan Direction 1 Exam Reason For Partial' Weld s Base 96 Joint configuration and material type (ASTM SA-513 GR. B 1 (120* - 200*) O - with stataless steel claddingt limit the use of an 45 Weld 2 49 45 Weld' 5 96 V-path exasleistloa. L11t leg restricts Uf scans la all 45 Weld 7 95 directions. 45 Weld a 95 60 Weld 2 15 60 Weld 5 96 95 ", 60 Weld 1 60 Weld 0 95 45 s 60 Mase 2 56 45 s 60 ease 5 96 45 a 60 Base 7 95 45 s 60 Base e 95 b Surface coverage 961 UT Sean Direction Definitions 2 - Antal scan flange side of weld 5 - Axial scan head side of weld 7 - Circumferential scan, clockwise flooking down on headi 8 - Circumferential scan, counterclockwise (looking down on headi t t 4 Page 3 of 3
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h Virginia Electric & Power Company North Anna Power Station Units 1 and 2 Second 10 YearInterval Request for ReliefNumber NDE-34 (Unit 1) Request for ReliefNumber NDE-36 (Unit 2) I. IDENTIFICATION OF COMPONENTS hbrk/ Weld # Lind Drawinn# Jsint Unit 1 I
. 6 2"-WS-C82-153 A-Q3 11715-CBM-78G-2 SHT,1 SW 11715-WS-2C82A 19W 4"-WS-57-163-Q3 11715-CBM-78C-2 SHT. 2 BW l1715-WS-16D Unit 2
! base metal 2"-WS-776-163-Q3 11715-CBM-78C-2 SHT. 2 pipe adjacent to weld 56 (a) The above welds are Class 3, moderate energy piping in the Service Watu (SW) ; system and; (b) Provide cooling water from the service water to instrument air compressors, and charging pump lube oil coolers for both units and retum service water back to the retum headers. Normal flow is 20 to 100 gpm at an operating pressure of 100 t psig. The design pressure is 150 p:ig and design temperature is 150 F. (c) Joint type - butt weld (BW) and socket weld (SW). II, IMPRACTICABLE CODE REQUIREMENTS The above welds had extemal evidence of through-wall leakage, i.e., stains Virginia Electric and
. Power Company decided to proceed under the assumption that each of the above welds contain through-wall flaws. Although this evider.cc ofleakage was not detected during the conduct of a system pressure test, the requirements ofIWA-5250 of the 1983 Edition and Summer 1983 Addenda and the 1986 Edition are applicable to Unit I and Unit 2, respectively. The speciSc Code requirement for which reliefis requested is IWA-5250(a)(2) for the 1983 Edition and Summer 1983 Addenda and IWA-5250(a)(3) for the 1986 Edition.
Page 1 of 6 s I
.l l
"IWA-5250 Corrective Measures (a) The source ofleakage detected during the conduct of a syrtem pressure test shall be located and evaluated by the Owner for corrective measures as follows: ..
(2) or (3) repairs or replacements of components shall be performed in accordance with IWA- l 4000 orIWA-7000, r@vely." '
' Articles IWAA000 and' LWD-4000 of ASME Section XI Code repair requirements would require ;
removal of the flaw and subsequent weld repair, i Virginia Electric and Power Company decided to replace each weld having evidence of through-wall
. leakage in a planned evolution to reduce the number of action statements and service water system manipulations. ;
III. BASIS FORRELIEF REQUEST This relief request is submitted in accordance with NRC Generic Letter 90-05, " Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2, and 3 Piping." The following information and justi6 cation are provided in accordance with the guidelines of Part B and C of Enclosure 1 to GL 90-05.
' Scone. Limitations and Soecific Considerations i Scope !
The scope consists of the welds identified in Section I with evidence of possible through-wall leaks in the shared Service Water System for North Anna Power Station Unit I and Unit 2. The material of the piping is stainless steel ASME SA-312 type 316L with 316 weld filler metal for pipe class 163 and ASME SA-312 type 304 with 304 filler metal for pipe class 153 A. l Limitations , i Based on radiographic examinations and laboratory exammations of removed portions of piping from l replacements, Microbiological Influence Corrosion (MIC) was determined to be the cause of the flaw. ! The MIC induced Saws originated on the inner diameter of the pipe and were detected during plant I operation. The intent of this request is to obtain relief for the period of operation from the identification ;
. of a through-wall flaw until repair is accomplished. To the extent practical, the repair will be !
accomplished in accordance with the guidance of NRC Generic Letter 90-05. This period extended from identification of the first leaking weld on February 10,1997 to the repair of each weld suspected of having through-wall flaws was completed. The' flaws at weld 6 and adjacent to weld 56 were repaired by February 20,1997. Weld 19 was repaired by March 18,1997. Soecific Considerations Page 2 of 6
i } System interactions, i.e., consequences of flooding and spray on equipment were evaluated. The flaws were lo .ated on the piping such that potential through-wall leakage would not affect plant equipment. , The structuralintegnty ofbutt weld 19W was evaluated based on radiographic exammation results for the required design loadmg conditions, including dead weight, pressure, thermal expansion and seismic , l (DBE) loads. The methods used in the structural integnty analysis consisted of an area reinforcement, fracture mechanics, and limit load analyses. Each indication was considered to be through-wall due to the inability of either radiography or ultrasonics to determine indication depths A summary of the flaw
- evaluation is provided in Attachment 1. Butt weld 19W on line 4"-WS-57-163-Q3 was analyzed and
- found acceptable. The radiography for the area adjacent to weld 56 on line 2"-WS-776-163-Q3 I
showed the possibility of MIC for 77% of the circumference This length'of MIC exceeded the I established allowable limit and the weld was declared inoperable at that time. The line was isolated and , L the weld was repaired prior to retuming the line to service. No additional structural integrity analysis was perfonned on this flaw. i ^ [ Radiography of socket weld 6 was nct attempted since radiographs of socket welds do not yield j J meaningful results. Since the flaws cannot effectively be charactenzed for socket welds, a 3/4" hole : i was postulated. The socket weld was replaced nine (9) days after the evidence of leakage was l detected, before a complete structural integrity analysis could be completed. The socket weld was l l monitored for leakage weekly until replaced. : i ! The structural integrity for each weld identified with evidence of through-wall leakage was monitored j by the following methods:
. Weekly visual monitoring of through-wall flaws and leakage.
!
- Radiographic examination of butt weld 19W and the area adjacent to socket weld 56 was performed. The area adjacent to socket weld 56 was replaced on Febmary 19,1997. Weld 19W
! was replaced on March 18,1997. i i Generic Letter 90-05 allows two options for temporary non-code repairs of Class 3 piping in moderate energy systems, (1) non-welded repairs, and (2) leaving the piping as-is if there is no leakage and the i flaw is found acceptable by the "through-wall flaw" approach discussed in Section C.3.a. The ,. temporary non-code repair was to leave the welds as they were found, subject to monitoring and !' meeting the criteria for consequences and for structural integrity as described above.
- i i Evaluation l 1 Flaw Detection Durina Plant Ooeration and Imoracticality Determination i
The subject welds were identified as having evidence of through-wall leakage during a Service Water
- System walkdown unducted on February 10,1997, when both Units were operating. During the past i
! several months Virginia Electric and Power Company has been monitoring, evaluating, and replacing 4 through-wall leaks in the Service Water System csused by MIC. Removing portions of the Service ,
l l Page 3 of 6 i
Water System which may have leaked in the past prior to performing a structural analysis could reduce the margin of safety by unnecessarily isolating portions of the Service Water System that are structurally sound and capable of performing their intended safety function. Therefore, performing Code repairs immediately was considered impractical. Root Cause Deternunation and Flaw Characterization The Service Water System at North Anna Power Station has previously experienced MiC. The radiograph examinations of the service water welds with indications of through-wall leaks revealed small voids surrounded by exfoliation, which is typical of MIC. No other type of operationally caused defects were identified by the radiographs. Additionally, an examination performed by a Virginia Electric and Power Company staff metallurgist of a piping segment removed for repair cordirmed the presence ofMIC. l Flaw Evaluation l Flaw evaluation for butt weld 19W and the additional sample ofwelds subject to augmented inspection was performed as described in Attachment 1. The flaws were evaluated by three types of analyses, area reinforcenent, limit load analysis, and fracture mechanics evaluation using the guidance from NRC Generic Letter 90-05. Because of the inability for either radiography or ultrasonic techniques to determine the extent of wall degradation, the structural assessment considered each indication to be through wall. Areas identi6ed by radiography as incomplete fusion or incomplete penetration were analyzed by conservatively assuming a twenty five percent (25%) reduced pipe wall thickness all around the cross-section. The radiography for the area adjacent to weld 56 on line 2"-WS-776-163-Q3 showed the possibility of MIC for 77% of the circumference. This length of MIC exceeded the established allowable limit and the weld was declared inoperable at that time. The line was isolated and the weld was repaired prior to retuming the line to service. No additional structural integrity analysis was performed. The analyses determined butt weld 19W in line 4"-WS-57-163-Q3 and butt welds subjected to augmented examination were capable of maintainmg their structural integrity until they were repaired. This is based on the results from the analysis:
- 1. Ductile tearing will not occur at the flaw locations when the piping is subjected to the design pressure.
- 2. The limit load analysis shows that there was at least a factor of safety of 4.0 agamst a ductile rupture for the most limiting case analped.
- 3. For the subject welds a linear elastic fracture mechanics analysis shows that the applied stress intensity factor at the analyzed flaws is below the allowable stress intensity factor per the guidance ofNRC Generic Letter 90-05. Therefore, a brittle fracture was unlikely.
Page 4 of 6
l I l One weld, IW on line 4"-WS-57-163-Q3, radiographed as part of the augmented inspection did ! exceed the allowable stress intensity by twelve percent (12%) against a built in safety margin of ) forty percent (40%) added in the calculation of stress intensity. The radiograph of this weld ! showed incomplete penetration for two inches (2") out of a total circumferential length of ! 14.137", but was conservatively analyzed with a seventy five percent (75%) wall thickness all ) around the weld. Additionally, a very conservative through-wall flaw evaluation method was ; performed for a thin wall degradation situation. This weld has not leaked in the past. Therefore, a failure by brittle fracture is unlikely to occur. IV. AUGMENTED INSPECTION i To assess the overall degradation of the Service Water System augmented radiographic examinations were performed. After the initial through-wall flaws were identiSed, five (5) additional locations on lines having the same function were examined using radiography. All welds in this sample group had evidence of MIC but no evidence of through-wall leakage. Any indication of MIC was treated as a through-wall defect and analyzed for stmetural stability as described in Attachment 1. All augmented weld locations were found structurally acceptable. V. ALTERNATE PROVISIONS As an alternative to performing Code repairs in accordance with IWA-5250(a)(2) for Unit I and IWA-5250(a)(3) for Unit 2 on through-wall flaws in the Service Water System, it is proposed to allow the through-wall flaws to remain in service until a scheduled code repair, unless the structural integrity has been determined to be unacceptable. This attemate provision applies to the subject welds, weld 6 on line 2"-WS-C82-153A-Q3, weld 19W on line 4"-WS-57-163-Q3, and line 2"-WS-776-163-Q3 adjacent to weld 56, from identification of the first leaking weld on February 10,1997 to the repair of each weld suspected of having a through-wall flaw is completed. Piping adjacent to weld 56 was replaced on Febmary 19,1997. Weld 6 was replaced on February 20,1997. Weld 19# was replaced on March 18,1997. The through-wall flaws which have been replaced were subject to monitoring and met the criteria for flooding and spraying consequences and for structural integrity as described above. The proposed altemative stated above ensures that the overall levels of plant quality and safety will not be compromised. VI. STATUS Granted - NRC Letter No. 97-563 Dated 9/24/97.
Attachment:
- 1. Flaw Evaluation Methods and Results e Page 5 of 6
r Refereacct
- 1. USAS B31.1 Power Piping 1%7 Edition
- 2. 'EPRIReportNP-6301-D,"DuctileFractureHandbook"
- 3. Nuclear Regulatory Commission Generic Letter 90-05 " Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2, and 3 Piping" Page 6 of 6
l 1 i Attachment 1 ReliefRequest NDE-36 l Flaw Evaluation Methods and Results ; Introduction Butt welds identified by radiography as having MIC were analyzed for structural integnty by three methods, area reinforcement, limit load analysis, and linear elastic fracture mechanics evaluation. Area Reinforcement Analysis The area reinforcement analysis is used to determine if adequate reinforcing exists such that ductile , tearing would not occur. The guidelines of ANSI B31.1 paragraph 104.3.(d) 2 (reference 1) are used to determine the Code required reinforcing area. The actual reinforcing area is calculated and is checked against the required reinforcement area. The Code required reinforcement area in square inches is de6ned as: 1.07(t.)(d i ) Where t is the code minimum wall, and d iis the outside diameter The Code reinforcement area required is provided by the available material around the flaw in the reinforcing zone. The results of this analysis determined that for the subject four inch (4") piping, a four inch (4") diameter hole would have acceptable reinforcement. Limit Load Analysis The structural integrity of the piping in the degraded condition was established by calculating the minimum margin of safety based upon a Limit Load Analysis. These methods are documented in EPRI report NP-6301-D (Ductile Fracture Handbook) (reference 2). l The limit load analysis of the postulated flawed sections were performed with a material flow stress representing the m;dpoint of the ultimate strength and yield point stress for the SA312-TP316L ] stainless steel matedal at the design temperature of 150 F. l l Page 1 of 4
- The flawed sections were subjected to deadweight, thermal, and seismic DBE loading.
The allowablelimitload is given by, I
. M. = 2 srR.2 t (2cos(b)-sin (Q)) in-lbf sr = flow stress = 0.5 (Sy + S.), psi l l Sy = yield stress, psi l l
S = ultimate stress, psi 4 i R. = mean radius of the pipe (inches) p e D.(Rf.P)+F
+
2 .4.af.R.. ,
.R; = internal radius of the pipe (inches) :
P = pressure (psig)
- F = axialload (Ibs)
~
D = Outside diameter (inches) _ t pipethickness(inches) 0 = half angle of the crack (radians) = crack length 2A MR = Resultant Moment from the above mentioned loading conditions MR = 4MY'+ MZ'+ T'
' hW = Bending Moment MZ = Bending Moment
- T = Torsion - ,
The calculated factor ofsafetyis, FS =.% (hm)- The minimum factor of safety of 1.4 is required to be qualified for continued operation. A summary of the results is listed in Table 1. Fracture Mechanics EvaluatiOD A knear clastic fracture mechanics analysis was performed for circumferential through-wall crack using t he gu idance prov eid d in NRC Generic Letter 90-05. The structural integnty of the piping in the degraded condition was established by calculating the stress intensity factor ratio based upon a Fracture Page 2 of 4 c.
Mechanics evaluation. This method is documented in EPRI report NP-6301-D (Ductile Fracture Handbook)(reference 2). A through-wall circumferential crack was postulated for every area containmg MIC. The cracks were subjected to a design pressure loading of 150 psig in addition to the deadweight, normal operating thermal and seismic DBE loadings. For the purpose <
- this evaluation a generic allowable stress intensity factor ofKe = 135 ksioin was used for the mateaal per NRC GL 90-05.
The applied stress intensity factor for bending, Km, is found by: Km = (se(p R.-Q)"] F. The applied stress intensity factor for internal pressure, Kr, is found by: Kr = s.-(phQ)" F. The applied stress intensity factor for axial tension, Krr is found by: Krr = sc(pAQ)" Fi The stress intensity factor for residual stresses, Km is found by: Km = S-(pAQ)" F i Total applied stress intensity Kr includes a 1.4 safety factor and is calculated by: Kr = 1.4-(Km + Kr + Krr) + Km The allowable stress intensity factor is taken from Generic Letter 90-05. Km = 135 ksioin for stainless steel. Stress Intensity Factor Ratio is defined as: SR = Kr. Kn The stress intensity factor ratio shall be less than 1.0 for continued operation. A summary of the results are listed in Table 1. Page 3 of 4
A i .
.TableJ1
SUMMARY
_OF. FLAW EVALUATION RESULTS FOR-SERVICE WATER: WELDS -l t Allowable Bending : Bending Resulting' Limit.- Factor Agiplied - A11 d le- ,L Crack- - Azlal Torsion ; Moment , Moment ' Moment'. Load M. .cf K, Kc i teeli pos. Line Nos.'
~
Length in Load Ibs T ft-Ibs NY ft-lbs ' M2 ft-lbs' MR ft-lbs Et-lbf - Safet/ kalY!n keilla-4*-MS-51-163-Q3- 0.625 208 110 695 316 '. 800 . 1.522x10' 19.03- 29.16 . 135 - - 1 90s
-f Notss: i
- 1. Limit load factor of safety.is Allowable Limit Load /pesultin, Moment. !
4' ~y
,k I
t 4 t 2 4 r
-l
.g
~t
~.
r I m ___ . __ ,_1._ .r_ _ _ _ . _ _ _ , _._m . __ ---- -. , v. . ,,-.+m, - - - . . - - - - _ _ -_.,=m-- -- . . _ - - -- ,_- O , ._-__m_& ,_ m ,.__mu _ - m_- _ _ ,..-
~. Virginia Electric & Power Company North Anna Power Station Unit 2 Second Ten Year Interval
^ ReliefRequest NDE-37 i . I .' . IDENTIFICATION OF COMPONENT Mark No. Gupponent No. Drawing No. _ Clam ', N-01 thru N-58 .1-RC-R-1 12050-WMKS-RC-R-1.4 1 , l The above are reactor vessel closure head nuts. II. . CODE REQUIREMENTS The 1986 Edition of ASME Section XI Table IWB-2500-1, examination category B-G-1, item number B6.10 requires a surface examination of the reactor vessel closure head nuts. III. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Reliefis requested from performing the Code-required surface examination on the above identified reactor vessel closure head nuts. IV. BASIS FOR RELIEF The 1989 Addenda of ASME Section XI Table IWB-2500-1, examination category B-G-1. item number B6.10 has changed the requirement from a surface examination to a visual (VT-1) examination. Extensive cleaning of these nuts is required for a surface examination to be performed. This extensive cleaning results in additional costs and the inefficient use of available manpower resources. Due to design factors, the stripping areas of the female threads in a nut are approximately 1.3 times the areas of the mating male threads (see ASME Bl.1, Unified Inch Screw Threads). Accordingly, if a defect were to be developed during service, they would occur in the threads of c the bolt or stud before developing in the nut's threads because of higher stresses in the male threads. When reactor vessel head fasteners are tightened for closure or loosened for opening, the studs are tensioned and the nuts are run on the threads with no load as the load is taken by the stud or bolt through the tensioning device. Page 1 of 2 i
, V. - PROPOSED ALTERNATE REQUIREMENT It is proposed that the requirements of the 1989 Addenda of ASME Section XI Table IWB-2500-1, examination category B-G-1, item number B6.10 (visual, VT-1) be substituted for the Code surface examination. In addition:
- 1. A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refueling outage;
- 2. Technical Specifications require that the reactor coolant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hours; and 3 The containment atmosphere particulate radioactivity is checked every 12 hours.
The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised. VI. STATUS Granted - NRC Letter No. 97-683 Dated 11/14/97. [ , 1 I l l 1 l Page 2 of 2 4
-k+
i VirginiaElectric & Power Company North Anna Power Station Units I and 2 j Second 10 YearInterval , Request for ReliefNumber NDE-43 (Unit 1) -l Request for ReliefNumber NDE-38 (Unit 2) ) l I. IDENTIFICATION OF COMPONENTS-4 Mark / Weld # Line# Drawina# 10101 l f
- 42A 2"-WS-80-163-Q3 11715-CBM-78C-2 SH. 2 SW L 11715-WS-1078C 10 2"-WS-948-153A-Q3 11715-CBM-78G-2 SH. 2 SW l l
12050-WS-2948A 36 2"-WS-954-153 A-Q3 11715-CBM-78G-2 SH. 2 SW 12050-WS-2954A 90 4"-WS-46-163-Q3 11715-CBM-78C-2 SH. 2 BW
- 11715-WS-19F -
3W 4"-WS-56-163-Q3 . I1715-CBM-78C-2 SH. 2 BW ; j 11715-WS-18F 4 4W 4"-WS-56-163-Q3 11715-CBM-78C-2 SH. 2 BW ; 11715-WS-18F , 69 4"-WS-F64-163-Q3 11715-CBM-78A-2 SH.1 BW 11715-WS-2D88B I T (a) The above welds are Class 3, moderate energy piping in the Service Water (SW) system; i (b) Line 2"-WS-80-163-Q3 is the supply to the Unit 1 instrument air (1- ! IA-E-lC) heat exchanger. Line 2"-WS-948-153 A-Q3 is the supply to the Unit 2 charging pump gear box cooler (2-CH-E-1C1) and Unit 2 seal coolers 2-CH-E-1C2A and 2-CH-E-1C2B. Line 2"-WS-954-153 A-Q3 is the return from the Unit 2 charging pump gear box cooler (2-CH-E-1C1) and Unit 2 seal coolers 2-CH-E-1C2A and 2-CH-E-
- IC2B. Line 4"-WS-46-163-Q3 provides cooling water to the Unit I charging pump lube oil coolers and instrument air compressors. Line
- 4"-WS-56-163-Q3 is the return from the Unit I charging pump lube oil coolers and instrument air compressors. Line 4"-WS-F64-163-Q3 is the return from the Unit I air conditioning condenser. The nominal operating pressure and temperature is 75 psig and 95"F, respectively; and 4 (c) Joint type - butt weld (BW), and socket weld (SW). k Page 1 of 6 . i 4
l t II. CODE REQUIREMENTS i The above welds had external evidence of through-wall leakage, i.e., active leaks or stains. Virginia Electric and Power Company decided to proceed under the assumption' that each of the above welds contain through-wall flaws. Although this evidence ofleakage was not detected during the conduct of a system pressure test, it is being treated as such, and the requirements ofIWA-5250 of the 1983 Edition and Summer 1983 Addenda is applicable to Unit 1. The requirements ofIWA-5250 of the 1986 Edition is applicable to Unit 2. ,
"IWA-5250 Corrective Measures:
- (a) The source ofleakage detected during the conduct of a system pressure test shall be located and evaiuated by the Owner for corrective measures as follows
- . .
1 (2 or 3) repairs or replacements of components shall be performed in accordance with IWA-4000 or IWA-7000, respectively." Articles IWA-4000 and IWD-4000 of ASME Section XI Code repair requirements would . require removal of the flaw and subsequent weld repair. I l i III. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED ; Reliefis requested from performing the above Code required repair of the above identified ! welds until the effected piping system can be taken out of service. The specific Code requirement for which reliefis requested is the 1983 Edition and Summer 1983 Addenda, IWA-5250(a)(2) for Unit 1, and the 1986 Edition, IWA-5250(a)(3) for Unit 2. IV. BASIS FOR RELIEF REQUEST This relief request is submitted in accordance with NRC Generic Letter 90-05 (GL 90-05),
" Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2, and 3 Piping." The following information and justification are provided in accordance with the guidelines ofPart B and C of Enclosure I to GL 90-05.
Scone. Limitations and Soecific Considerations Scope The scope consists of the welds identified in Section I with evidence of possible through-wall leaks in the service water system for North Anna Power Station Units 1 and 2. The material of the piping is stainless steel ASME SA-312 type 316L for welds 42A,90,3W, 4W and 69. The material of the piping for weld 10 is ASME SA-376 type 304. The mate-rial of the piping for weld 36 is ASME SA-312 type 304. Page 2 of 6
Limitations Based on radiographic examinations and laboratory examinations of removed portions of piping from previous replacements, Microbiological Influence Corrosion (MIC) was deter-mined to be the cause of the flaws. Additionally, laboratory examinations of weld 94 shows evidence ofMIC. Radiographs ofwelds 90,3W, and 4W show indications of MIC. The MIC induced flaws originated on the inner diameter of the pipe and were de-tected during plant operation. The intent of this request is to obtain relief for the period of operation from the identification of a through-wall flaw until repair was accomplished. To the extent practical, the repair was accomplished in accordance with the guidance of NRC Generic Letter 90-05. This period extends from identification of the first leaking weld on August 6,1997 to the repair of each weld suspected of having through-wall flaws is completed. Allidentified welds suspected of having through-wall flaws were repaired by , August 20,1997, except weld 69. Soecific Considerations System interactions, i.e., consequences of flooding and spray on equipment were evaluated. The identified flaws were located on the piping such that potential through-wall leakage would not affect plant equipment. The structural integrity of the butt welds was evaluated based on radiographic examination results, the required design loading conditions, including dead weight, pressure, thermal expansion and seismic loads. The methods used in the structural integrity analysis consisted of an area reinforcement, fracture mechanics, and limit load analysis. Each indication was considered to be through-wall due to the inability of either radiography or ultrasonics to determine indication depth. A summary of the flaw evaluation is provided in Attachment 1. All welds were analyzed and found acceptable, except weld 90. Radiography of socket weld 42A on line 2"-WS-80-163-Q3, weld 10 on line 2"-WS-948- { 153A-Q3, and weld 36 on line 2"-WS-954-153A-Q3 were not attempted because radio- . I graphs of socket welds do not yield meaningful results. Additionally, flaws cannot be l characterized for socket welds. Therefore, complete structural integrity analysis was not performed. Lines 2"-WS-80-163-Q3,2"-WS-948-153A-Q3, and 2"-WS-954-153A-Q3 were removed from service and the socket welds were replaced by August 20,1997, fourteen (14) days after the evidence ofleakage was detected. Weld 90 on line 4"-WS- 1 46-163-Q3 was removed from service after the weld was radiographed. Because of the j inability of both RT and UT to give reliable through-wall depth for MIC indications, all MIC indications was considered through-wall. This conservative assumption caused the weld (weld 90) to fail the assessment requirements of GL 90-05. The weld (weld 90) was replaced on August 14,1997 one (1) day after the weld was radiographed and removed from service. Welds 3W and 4W on line 4"-WS-56-163-Q3 showed evidence of acceptable MIC as determined by radiography and structuralintegrity analysis. However, Page 3 of 6 l I 4
l these welds were replaced as a conservative measure on August 12,1997 one (1) day after the welds were radiographed and removed from service. The structural integrity for each weld identified with evidence of through-wall leakagi (and remaining in service) was monitored weekly by visual monitoring of through-wall flaws to determine any degradation of structural integrity. I l Generic Letter 90-05 allows two options for temporary non-code repairs of Class 3 piping in moderate energy systems, (1) non-we!ded repairs, and (2) leaving the piping as-is if there is no leakage and the flaw is found acceptable by the "through-wall flaw" approach discussed in Section C.3.a. Th'e temporary non-code repair approach selected was to l leave the welds as they wtre found, subject to monitoring and meeting the criteria for l l consequences and for structural integrity as described above until replaced. Evaluation Flaw Detection Durina Plant Ooeration and Imoracticality Determination l l The subject welds were identified as having evidence of through-wall leakage during a ! Service Water System walkdown conducted on August 6,1997, when both Units were l ] operating. During the past several months Virginia Electric and Power Company has been monitoring, evaluating, and replacing through-wall leaks in the Service Water System j l caused by MIC. Removing ponions of the Service Water System, prior to performing a l l structural integrity analysis, due to MIC can unnecessarily reduce the margin of safety by l I l isolating portions of the Service Water System that are structurally sound and capable of performing their intended safety function. Therefore, performing Code repair; immediately was considered impractical for welds 42A,10,36, and 69. Root Cause Determination and Flaw Characterization The Service Water System at North Anna Power Station has previously experienced MIC. The radiograph examinations of the service water welds with indications of through-wall leaks revealed small voids surrounded by exfoliation, which is typical of MIC. No other type of operationally caused defects were identi6ed by the radiographs. Flaw Evaluation Flaw evaluation for the welds was performed as described in Attachment 1. The flaws were evaluated by three types of analyses, area reinforcement, limit load analysis, and fracture mechanics evaluation using the guidance from NRC Generic Letter 90-05. Because of the inability for either radiography or ultrasonic techniques to determine the extent of wall degradation, at the identified location, the structural assessment considered each indication to be through- wall.
; Page 4 of 6
l I' The analyses determined that weld 69 is capable of maintaining its structural integrity until it is repaired. The following is based on the results from the analyses: I
- 1. Ductile tearing will not occur at the flaw locations when the piping is subjected to the design pressure from the area reinforcement calculation.
- 2. The limit load analysis shows that there is enough margin against a ductile rupture for the most limiting case analyzed.
- 3. For the subject welds a linear elastic fracture mechanics analysis shows that the applied stress intensity factor at the analyzed flaws is below the allowable stress intensity factor per the guidance ofNRC Generic Letter 90-05. Therefore, a failure by brittle fracture is unlikely to occur.
V. . AUGMENTEDINSPECTION To assess the overall degradation of the service water system augmented radiographic examinations were performed. After the initial through-wall flaws were identified, five (5) , additional locations on lines having the same function were examined using radiography. Two (2) of the five (5) welds had evidence of MIC, (weld 2W on line 4"-WS-56-163-Q3 and weld 94 on line 4"-WS-46-163-Q3) without showing evidence of through-wall leakage, i.e. stains. Weld 2W was found structurally acceptable by radiography and struc-turalintegrity evaluation, and not replaced. Weld 94 failed structuralintegrity evaluation, and was replaced on August 14,1997 one (1) day after the weld was radiographed and re-moved from service. Weld 6W on line 3"-WS-75-163-Q3 was replaced for case of constmetion. The remaining two welds which did not show evidence ofMIC on the i radiographs were act replaced, (welds 68 and 85 on line 4"-WS-F64-163-Q3).
' Because weld 94 on line 4"-WS-46-163-Q3 failed structural integrity evaluation five (5) additional locations on lines having the same function were examined using radiography.
All of the five welds were found acceptable by radiography and stmetural integrity , analysis. VI. ALTERNATE PROVISIONS j As an alternative to performing Code repairs in accordance with IWA-5250(a)(2) for Unit I and IWA-5250 (a) (3) for Unit 2 on through-wall flaws in the Senice Water System, it is proposed to allow the through-wall flaws to remain in service until a scheduled code repair, unless the structural integrity hat been determined to be unacceptable. This alternate provision applies to the subject welds from identification of the first leaking weld on August 6,1997 to the repair of each weld suspected of having a through-wall flaw. All through-wall flaws had been repaired by August 20,1997, except weld 69. Page 5 of 6
. . . - - - =. .
The proposed alternative stated above ensures that the overall levels of plant quality and safety will not be com' promised. i' VII. IMPLEMENTATION SCHEDULE Repairs of the effected welds were completed by August 20,1997, except for weld 69. Weld 69 was evaluated to assure it met the criteria for flooding and spraying consequene-es. A weekly visual inspection will be performed until weld 69 is replaced. Ifit is not replaced within 90 days (by November 4,1997) from the walkdown date of August 6, 1997 it will be radiographed to determine its structural integrity per Station Procedure O-PT-75.24. VIII. STATUS Granted - NRC Letter No. 97-739, Dated 12-18-97
References:
- 1. USAS B31.1 Power Piping Code - 1967 Edition
- 2. EPRI Report NP-6301-D, " Ductile Fracture Handbook"
- 3. Nuclear Regulatory Commission Generic Letter 90-05 " Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2, and 3 Piping" r
Page 6 of 6 l l
h 4 1 Attachment 1 l ReliefRequest NDE-38 l
- 1 1' Flaw Evaluation Methods and Results i .
- Introduction Butt welds identified by radiography as having MIC were analyzed for structural integrity by three methods, area reinforcement, limit load analysis, and linear elastic fracture mechanics evaluation.
Area Reinforcereent Analysis \ I I- The area reinforcement analysis is used to determine if adequate reinforcing exists such that ductile tearing would not occur. The guidelines of ANSI B31.1 paragraph 104.3 (d) 2 (reference l
- 1) are used to determine the Code required reinforcing area. The actual reinforcing area is calculated and is checked against the required reinforcement area. ;
The Code required reinforcement area in square inches is defmed as:
- 1.07(t )(di) .
, l ! Where t,is the code minimum wall, and d iis the outside diameter k j . The Code required reinforcement area is provided by the available material around the flaw in the [ reinforcing zone. i The .esults of this analysis determined that for the subject four inch (4") and three inch (3") pipes, i a hole size of 2.2" and 1.7" respectively will be contained by the reinforcement provided by the . E excess material in the near vicinity. , 4 ~ Limit Load Analysis
- j. The structural integrity of the piping in the degraded condition was established by calculating the j' minimum margin of safety based upon a Limit Load Analysis. These methods are documented in
- i. EPRI report NP-6301-D (Ductile Fracture Handbook) (reference 2).
The limit load analysis of the postulated flawed sections were performed with a material flow {. ' stress representing the midpoint of the ultimate strength and yield point stress for the SA312- . - TP316L stainless steel material at the design temperature of 150 F. i sa4 4 i Page 1 of 4
- - - ._ = _ .- - - . _ _ . - .
4 The flawed sections were subjected to deadweight, thermal, and seismic DBE loading. The allowable limit load is given by,
. M. = 2 srR.' t-(2cos(b)-sin (Q)) in-lbf sr = flow stress = 0.5 (Sy + S.), psi Sy = yield stress, psi S. = ultimate stress, psi
.R. = mean radius of the pipe (inchet.)
p _ O , Tl*(R!e P)+F 2 4eeri
- R,e t R. = internal radius of the pipe ('mches)
P = pressure (psig) F = arialload (Ibs) D = Outside diameter (inches) t = pipe thickness (inches) 0 = half angle of the crack (radians) = crack length 2 R. -l l MR = Resultant Moment from the above mentioned loading conditions e MR = 4MY MZ' + T' MY = Bending Moment ;
'MZ = Bending Moment j T = Torsion l l
The calculated factor of safety is, FS = }.1,
.(MR) .
The minimum factor of safety of 1.4 is reqtiired to be qualified for continued operation. A summary of the results is listed in Table 1. 2 Fracture Mechanics Evaluation A linear elastic fracture mechanics analysis wa~s performed for circumferential through-wall crack , using the guidance provided in NRC Generic Letter 90-05. The structural integrity of the piping in the degraded condition was established by calculating the stress intensity factor ratio based upon a Page 2 of 4
i l Fracture Mechanics evaluation, This method is documented in EPRI report NP-6301-D (Ductile Fracture Handbook)(reference 2). A through-wall circumferential crack was postulated for every area containing MIC. The cracks ; were subjected to a design pressure loading of 150 psig in addition to the deadweight, normal operating thermal and seismic DBE loadings. For the purpose of this evaluation a generic l allowable stress intensity factor ofKo = 135 ksiDin was used for the material per NRC GL 90-05. l The applied stress intensity factor for bending, Km, is found by:
~ ' Km = s6-(p R.-Q)'50.5 F6 . The applied stress intensity factor for internal pressure, Km, is found by:
K, = s.-(p' R.-Q)'5 F. i The applied stress intensity factor for axial tension, Krr is found by: Krr = si(p R.-Q)'5 Fi The stress intensity factor for residual stresses, Km is found by: Km = S-(p R.-Q)'5 Fi Total applied stress intensity Kr includes a 1.4 safety factor and is calculated by: KT = 1.4-(Km + Ky + Krr) + Km
. The allowable stress intensity factor is taken from Generic Letter 90-05. l KAu. = 135 ksiDin for stainless steel.
I Stress Intensity Factor Ratio is defined as: SR = h KAM, i The stress intensity factor ratio shall be less than 1.0 for continued operation. A summary of the results are listed in Table 1. l I Page 3 of 4
1 Table l'
SUMMARY
OF FLAW EVALUATION RESULTS FOR-SERVICE WATER WELDS Flaw . . Max. Max. Max. Allowable Sending Bending Resulant Limit Factor App 11ed Allowebte ' Length :- Actual Max. Max. Analyzed. Flaw Axial forsion Moment Moment Moment Load M. of K, Fee
. Length in Length in Load Ibs T ft-1bs MY ft-Ibs- MZ ft-1bs MR ft-Ib3 ft-lbf Safety' ' ksidin . ks1 Yin :
Meld Mos. Line Nos. - - - 40 - 4*-MS-46-163-Q3 2.12 3.0625 Note 2 ' - - - - - 94 . 4"-WS-46-163-Q3 2.12 S.375 Note 2 : '_ - - 2.12 0.25 450 160 611 412 193.141 11950 .15.066 61.91 135 3W 4*-WS-56-163-Q3 61.5 - 135 4W .4*-WS-56-163-Q3 2.12 0.4315 100 - 21 421 152 459.45 9259 20.152' 252- 630 301- 142.291 ' 11940 '16.009 61.095 135 69 4*-NS-F64-163-Q3 2.12 0.150 596 Notss
- 1. Limit load factor of safety is Allowable Limit Load / Resultant Mosnent. . .
- 2. Weld 90 and 94 failed the structural integrity evaluation because the actual flaw tength was greater than the analyzed flaw length. The analyzed flaw length was
- bounded by-the 154 circumferential length as maximum thru-wall flaw tengths permitted by NPC Generic Letter GL 90-05. .
4 i t i t t i 1 I t Page 4 of 4
l
- Virginia Electric & Power Company North Anna Power Station Units 1 and 2
. Second 10 YearInterval Reauest for ReliefNumber NDE-44 (Unit 1)
Request for ReliefNumber NDE-39 (Unit 2) l i I. IDENTIFICATION OF COMPONENTS Mark / Weld # Liaq# Drawina# Loi_n,t n 14W 2"-WS-775-163-Q3 11715-CBM-78C-2 SH. 2 SW 12050-WS-2485E 53W 2"-WS-776-163-Q3 11715-CBM-78G-2 SH. 2 SW 12050-WS-2482C FW55 4"-WS-F65-163-Q3 11715-CBM-78A-2 SH.1 BW l1715-WS-2D89B FW67 4"-WS-47-163-Q3 11715-CBM-78C-2 SH. 2 BW 11715-WS-17F FW83 3"-WS-75-163-Q3 11715-CBM-78C-2 SH. 2 BW 11715-WS-1075A I FW65 4"-WS-56-163-Q3 11715-CBM-78C-2 SH. 2 BW 11715-WS-18E FW61 4"-WS-56-163-Q3 11715-CBM-78A-2 SH. 2 BW l1715-WS-18D FW66 4"-WS-56-163-Q3 11715-CBM-78A-2 SH. 2 BW 11715-WS-18D 8 4"-WS-H48-163-Q3 11715-CBM-78A-2 SH. 4 BW 12050-WS-2H48A 11A 4"-WS-H48-163-Q3 11715-CBM-78A-2 SH. 4 BW 12050-WS-2H48A (a) The above welds are Class 3, moderate energy piping in the Service Water (SW) system; (b) Line 2"-WS-775-163-Q3 is the cross-connection between instrument air heat exchangers 2-IA-E-1B and 2-IA-E-1C. Line 2"-WS-776-16;,-03 is the cross-connection between instrument air heat exchangers 2-IA-E-1 A and 2-IA-E-1B. Line 4"-WS-F65-163-Q3 is the return from the Unit 1 air conditioning condenser. Line 4"-WS-47-163-Q3 provides cooling water to the Unit I charging pump lube oil coolers and instrument air heat exchangers. Line 3"-WS-75-163-Q3 is the return line from the charging pump lube oil coolers. Line 4"-WS-56-163-Q3 is the return from the Unit I charging pump lube oil coolers and instrument air compressors. Line 4"-WS-H48-163-Q3 provides cooling water to the Unit 2 air conditioning condensers. The nomi-nal operating pressure and temperature is 75 psig and 95'F, respectively; and Page 1 of 5
(c) Joint type - butt weld (BW), and socket weld (SW). II. CODE REQUIREkENTS The above welds had external evidence of through-wall leakage, i.e., active leaks or stains. Virginia Electric and Power Company decided to proceed under the assumption that each of the above welds contain through-wall flaws. Although this evidence ofleakage was not detected during the conduct of a system pressure test, it is being treated as such, and the requirements of IWA-5250 of the 1983 Edition and Summer 1983 Addenda are applicable to Unit 1. The re-quirements ofIWA-5250 of the 1986 Edition are applicable to Unit 2.
"IWA-5250 Corrective Measures:
(a) The source ofleakage detected during the conduct of a system pressure test shall be located and evaluated by the Owner for corrective measures as follows:... (2 or 3) repairs or replacements of components shall be performed in accordance with IWA-4000 or IWA-7000, respectively." Articles IWA-4000 and IWD-4000 of ASME Section XI Code repair requirements would require removal of the flaw and subsequent weld repair. III. CODE REQUIREhENT FROM WHICH RELIEF IS REQUESTED Reliefis requested from performing the above Code required repair of the above identified welds until the affected piping system can be taken out of service. The specific Code requirement for which reliefis requested is the 1983 Edition and Summer 1983 Addenda, IWA-5250(a)(2) for Unit 1, and the 1986 Edition, IWA-5250(a)(3) for Unit 2. IV. BASIS FOR RELIEF REQUEST This relief request is submitted in accordance with NRC Generic Letter 90-05 (GL 90-05),
" Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2, and 3 Piping." The following information and justification are provided in accordance with the
.- guidelines ofPart B and C ofEnclosure 1 to GL 90-05. Scone. Limitations and Soecific Considerations Scope The scope consists of the welds identified in Section I with evidence of possible through-wall leaks in the service water system for North Anna Power Station Units 1 and 2. The material of the piping is stainless steel ASME SA-312 type 316L. Limitations Based on radiographic examinations and laboratory examinations of removed portions of piping from previous replacements, Microbiological Influence Corrosion (MIC) was determined to be the cause of the flaws. Radiographs of welds FW67, FW83, FW65, FW61, FW66, 8, and 11 A Page 2 of 5
! show indications ofMIC. The MIC induced flaws originated on the inner diameter of the pipe and were detected during plant operation. The intent of this request is to obtain relief for the l period of operation frbm the identification of a through-wall flaw until repair was accomplished. l [ To the extent practical, the repair was accomplished in accordance with the guidance of NRC j i Generic Letter 90-05. This period extends from identification of the first leaking weld on September 9,1997 to when the repair of each weld (suspected of having through-wall flaws) was ! l completed. All identified welds suspected of having through-wall flaws were repaired by l 3 . September 25,1997.
- Soecific Considerations j i
! System interactions, i.e., consequences of flooding and spray on equipment were evaluated. The l ! identified flaws were located on the piping such that potential through-wall leakage would not j
- affect plant equipment. j l
i i )- The structural integrity of the butt welds was evaluated based on radiographic examination results, the required design loading conditions, including dead weight, pressure, thermal expansion l ! and seismic loads. The methods used in the structural integrity analysis consisted of an area rein- i i forcement, fracture mechanics, and limit load analysis. Each indication was considered to be i through-wall due to the inability of either radiography or ultrasonics to determine indication ! depth. A summary of the flaw evaluation is provided in Attachment 1. All welds were analyzed l l and found acceptable, except welds FW65 and 8. j 1 \ j Radiography of socket weld 14W on line 2"-WS-775-163-Q3, and weld 53W on line 2"-WS. l 776-163-Q3 were not attempted because radiographs of socket welds do not yield meaningful l results. Additionally, flaws cannot be characterized for socket welds. Therefore, complete struc-i turalintegrity analysis was not performed. Lines 2"-WS-775-163-Q3, and 2"-WS-776-163-Q3 1 j were removed from service and the socket welds were replaced by September 25,1997, sixteen j (16) days after the evidence ofleakage was detected. Because of the inability of both RT and UT to give reliable through-wall depth for MIC indica-tions, all MIC indications were considered through-wall. This conservative assumption caused weld 8 on line 4"-WS-H48-163-Q3 and weld FW65 on line 4"-WS-56-163-Q3 to fail the as-sessment requirements of GL 90-05. Weld 8 was replaced on September 23,1997 two (2) days after the weld was radiographed and rem ved from service. Weld 11 A on line 4"-WS-H48-163-Q3 was replaced at the same time as wel( 8. Weld FW65 on line 4"-WS-56-163-Q3 5, s replaced on September 16,1997. Weld FW55 on hae 4"-WS-F65-163-Q3 did not show evidence of MIC on the radiographs. Therefore, no structuralintegrity analysis was performed on weld FW55. However, weld FW55 was replaced as a cons nvative measure on September 23,1997 two (2) days after the weld was radiographed and removed from service. Welds FW67 (on line 4"-WS-47-163-Q3), FW83 (on line 3"-WS-75-163-Q3), FW61 (on line 4"-WS-56-163-Q3), and FW66 (on line 4"-WS-56-163-Q3) showed evidence of acceptable MIC as determined by radiography and structuralintegrity analysis. However, these welds were replaced as a conservative measure on September 16,1997 Page 3 of 5
The structural integrity for each weld identified with evidence of through-wall leakage (and
; remaining in service) was monitored weekly by visual monitoring of through-wall flaws to determine any degradhtion of structural integrity.
f Generic Letter 90-05 allows two options for temporary non-code repairs of Class 3 piping in
- mcderate energy systems, (1) non-welded repairs, and (2) leaving the piping as-is if there is no f leakage and the flaw is found acceptable by the "through-wall flaw" approach discussed in Section C.3.a. The temporary non-code repair approach selected was to leave the welds as they were i found, subject to monitoring and meeting the criteria for consequences and for structural integrity as described above until replaced.'
i' Evaluation L [ Flaw Detection During Plant Ooeration and Imoracticality Determination j The subject welds were identified as having evidence of through-wall leakage during a Service Water System walkdown conducted on September 9,1997, when both Units were operating. t During the past several months Virginia Electric and Power Company has been monitoring, lt evaluating, and replacing through-wall leaks in the Service Water System caused by MIC. Removing portions of the Service Water System, prior to performing a stmetural integrity
- analysis, due to MIC can unnecessarily reduce the margin of safety by isolating portions of the
- Service Water System that are structurally sound and capable of performing their intended safety j function. Therefore, performing Code repairs immediately was considered impractical.
Root Cause Determination and Flaw Characterization
- The Service Water System at North Anna Power Station has previously experienced MIC. The
- ~ radiograph examinations of the service water welds with indications of through-wall leaks revealed small voids surrounded by exfoliation, which is typical of MIC. No other type of
- operationally caused defects were identified by the radiographs.
i Flaw Evaluation j Flaw evaluation for the welds was performed as described in Attachment 1. The flaws were evaluated by three types of analyses, area reinforcement, limit load analysis, and fracture i mechanics evaluation using the guidance from NRC Generic Letter 90-05. Because of the inability for either radiography or ultrasonic techniques to determine the extent of wall degradation, at the identified location, the structural assessment considered each indicatioa to be e through- wall. i V. AUGMENTED INSPECTION i l To assess the overall degradation of the service water system augmented radiographic examina-j tions were performed. After the initial through-wall flaws were identified, five (5) additianal i locations on lines having the same function were examined cing radiography. One (1) of the five i (5) welds (weld FW74 on line 4"-WS-F65-163-Q3) had evidence of MIC, without showing evi-dence of through-wall leakage, i.e. stains. Weld FW74 was found structurally acceptatle by radi-Pa084of5
ography and structural iritegrity evaluation, and not replaced. Weld FW56 on line 4"-WS-F65-163-Q3 was replaced for ease of constmetion, i.e., it is on the same elbow as FW55. The remaining three weldiivhich did not show evidence ofMIC on the radiographs were not replaced, (welds FW59, FW60 and FW73 on line 4"-WS-F65-163-Q3). VI. ALTERNATE PROVISIONS As an alternative to performing Code repairs in accordance with IWA-5250(a)(2) for Unit I and IWA-5250 (a) (3) for Unit 2 on through-wall flaws in the Service Water System, it is proposed to allow the through-wall flaws to remain in service until a scheduled code repair, unless the structuralintegrity has been determined to be unacceptable. This alternate provision applies to the subject welds from identification of the first leaking weld on September 9,1997 to the repair of each weld suspected of having a through-wall flaw. All through-wall flaws had been repaired by September 25,1997. The proposed alternative stated above ensures that the overall levels of plant quality and safety will not be compromised. VII. IMPLEhENTATION SCHEDULE Repairs of the affected welds were completed by September 25,1997. VIII. STATUS Granted - NRC Letter No. 98-059, Dated 1-15-98.
References:
- 1. USAS B31.1 Power Piping Code - 1967 Edition
- 2. EPRI Report NP-6301-D, " Ductile Fracture Handbook"
- 3. Nuclear Regulatory Commission Generic Letter 90-05 " Guidance for Performing Temporary Non-Code Repair of AShE Code Class 1,2, and 3 Piping" s
Page 5 of 5
Attachment 1 Relief Request NDE-39 Flaw Evaluation Methods and Results Introduction Butt welds identified by radiography as having MIC were analyzed for structural integrity by three methods, area reinforcement, limit load analysis, and linear elastic &acture mechanics evaluation. Area Reinforcement Analysis The area reinforcement analysis is used to determine if adequate reinforcing exists such that ductile tearing would not occur. The guidelines of ANSI B31.1 paragraph 104.3.(d) 2 (reference 1) are used to determine the Code required reinforcing area. The actual reinforcing area is calculated and is checked agains: the required reinforcement area. The Code required reinforcement area in square inches is defined as: 1.07(t.)(d i ) Where t is the code minimum wall, and d iis the outside diameter The Code required reinforcement area is provided by the available material around the flaw in the reinforcing zone. The results of this ana,1vsis determined that for the subject four inch (4") and three inch (3") pipes, a hole size of 2.2" and 1.7" ' -De etively -dll be contained by the reinforcement provided by the excess material in the near vicinity. Limit Load Analysis ~ The structural integrity of the piping in the degraded condition was established by calculating the minimum margin of safety based upon a Limit Load Analysis. These methods are documented in EPRI report NP-6301-D (Ductile Fracture Handbook) (reference 2).
. The limit load analysis of the postulated flawed sections were performed with a material flow stress representing the midpoint of the ultimate strength and yield point stress for the SA312-TP316L stainless
. steel material at the design temperature of 150 F.
The flawed sections were subjected to deadweight, thermal, and seismic DBE loading The allowable limit load is given by, M. = 2 seR.2 t-(2cos(b)-sin (Q)) in-lbf ) Page 1 of 4 l l
sr = flow stress = 0.5 (Sy + SJ, psi Sy = yield stress, psi S. = ultimate stress, psi R. = mean radius of the pipe (inches) pO D+e(R'
- P)+F 2' . 4 e af
- R,e t .
R; = internal radius of the pipe (inches) P = pressure (psig) F. = axialload (lbs) D = Outside diameter (inches) t ' = pipe thickness (inches) . ; O = half angle of the crack (radians) = crack leneth 2 R. MR = Resultant Moment from the above mentioned loading conditions , MR = JMY' + MZ' + 7" MY = Bending Moment MZ = Bending Moment T = Torsion t The calculated factor of safety is, FS = M (MR) The minirtsm factor of safety of 1.4 is required to be qualified for continued operation. A summary of the results is listed in Table 1. Fracture Mechanics Evaluatioji A linear elastic fracture mechanics analysis was performed f6r circumferential through-wall crack using the guidance provided in NRC Generic Letter 90-05. The structural integrity of the piping in the degraded condition was established by calculating the stress intensity factor ratio based upon a Fracture Mechanics evaluation. This method is documented in EPRI report NP-6301-D (Ductile Fracture Handbook)(reference 2). A through-wall circumferential crack was postulated for every area containing MIC. The cracks were subjected to a design pressure loading of 150 psig in addition to the deadweight, normal operating thermal and seismic DBE loadings. For the purpose of this evaluation a generic allowable stress intensity factor of Kie = 135 ksioin was used for the material per NRC GL 90-05. The applied stress intensity factor for bending, Km, is found by: Page 2 of 4 4
,- -m. - , - - m <-..- .--
4
- Km = s6-(p R.-Q)'d F6 t or for internal pressure, Kr, is found by
The applied stress intensity fa'c~ K, = s.-(p R.-Q)'d F.
- The applied stress intensity factor for axial tension, Krr is found by
Krr = sc(p R.-Q)'d F i The stress intensity facsor for residual stresses, Km is found by: . Km = S-(p R.-Q)'d F i Total applied stress intensity factor Kr includes a 1.4 safety factor and is calculated by: KT = 1.4-(Km + Ke + Krr) + Km The allowable stress intensity factor is taken from Generic Letter 90-05. Kut. = 135 ksioin for stainless acel. 1 Stress Intensity Factor Ratio is defined as: SR = Kr. Km The stress intensity factor ratio shall be less than 1.0 for continued operation. A summary of the results are listed in Table 1. 1 4 4 l l Pa083of4 l
L Table 1-
SUMMARY
OF FLAW EVALUATION RESULTS FOR SERVICE WATER WELDS Flaw Max. Mas. Max. Allowable Length. Actual Max. Man. Sending Bending Resulant Limit Factor Applied A11cneble Analyzed Flaw Antal Torsion Moment Moment Moment Load M. of : Kr Kse - Length la Length in' MY ft-lbs M2 ft-lbs MR ft-lbs it-lbf Safety' ks1 Min ' ksidia . Wold Mos. Line Nos. Load Ibs T ft-lbs Ew65 (*-NS-56-163-Q3 2.12 3.25 wate 2 - - - - - O 4*-WS-H48-163-Q3 2.12 2.25 Note 2 - - -- - - 1.936 117 57 319 324.55 1.197x10' 36.8 62.24 135 tw67 4*-MS-47-163-03 2.12 le 32.4' 135 fwS3 3*-MS-75-163-Q3 1.65 0.937 122 7 62 109 199.03 6.452x10' 54.54 140 454 490.82 1.196s10' 23.99 63.99 135 FW61 4*-MS-56-163-93 2.12 0.437 151 _152 1.125 418 102 506 664.80 1.094x10* 16.46 42.26 135 fw66 4*-MS-56-163-03 1.125 138 12.23 135 11A 4*-NS-H48-163-Q3 2.12 1.125 293 674 240 666 977.46 1.196x10' 66.82 Notost =
- 1. Limit load f actor of safety is Allowable Limit toad / Resultant Moment. .
- 2. Weld tw65 sad 8 f ailed the structural integrity evaluation because the actual flaw length was greater than the anatyred flaw length. The analyzed flew tength was bounded by the 151 circumferential length as maximum thru-wall flaw lengths permitted by MRC Generic Letter GL 90-C5.
i Page 4 of 4
- j. ;
i I Virginia Electric & Power Company
;. - North Anna Power Station Unit 2
. Second Ten Year Interval j Request for ReliefNo. NDE-040 j' l 1. Identification of Component: I Drawing No. Weld No. Line No. Qas j i
*32 12050-WMKS-0109G-1 31"-RC-308-2501R-Ql 1A 1 g *33 12050-WMKS-0109G-1 271/2"-RC-409-250lR-Q1 1A
)
j 11. Code requirements: The 1986 Edition of ASME Section XI Table IWB-2500-1, examination category B-J, j item number B9.11 requires a surface and volumetric examination of the weld and i adjacent base metal as defined by Figure IWB-2500-8. The Code does not allow any l reductions to the required surface and volumetric examinations. Code Case N-460, Alternative Exa nination Coverage for Class 1 and Class 2 Welds, allows a reduction in j coverage, ifit is less than 10 percent. Ill. Code Requirement from Which ReliefIs Requested: i Reliefis requested from fully performing the Code-required (1986 Edition of ASME l i Section XI Table IWB-2500-1, examination category B-J, item number B9.11) volumetric
- examination on the pipe to pump welds identified above.
IV. Basis for Relief: h The components listed above have been examined to the extent practical as required by F the Code However, due to the configuration of the weld (pipe to reactor coolant pump) along with the material type, the required volumetric coverage could not be obtained. The ' extent of volumetric and surface coverage is detailed in Table NDE-40-1. Figures NDE-40-1 and NDE-40-2 are provided as graphic detail of the limitations experienced. These
- welds are terminal end welds and, as such, all welds of this type are scheduled for examination. Therefore, substitution with another weld is not feasible.
t 4 .V. Proposed Alternate Examination: l It is proposed that the volumetric examination completed at the reduced coverage be accepted as meeting the Code requirements. In addition: Page 1 of 5 4
i
- 1. A visual (VT-2) examination will be performed in accordance with Code requirements-during the normally scheduled system leakage test each refueling outage.
- 2. Technical Specifications require that the reactor coolant system (RCS) leak rate be limited to one gallon per minute unidentified leakage. The RCS leakage is calculated at least once per 72 hours in accordance with Technical Specifications.
- 3. The containment atmosphere particulate radioactivity is checked every 12 hours in accordance with Technical Specifications.
The proposed alternatives continue to ensure that the overall level of plant quality and safety will be maintained.
- Relief was approved for identical welds on loops A and B by the NRC in a letter dated July 29,1997.
VI. Status: Pending - Virginia Power Letter 98-513 Dated 9-18-98. l 1 l Page 2 of 5
- .. m _ , _ _ . _ . .
Table NDE-40-1 North Anna Unit 2 . Examination Coverage Estimates Category B-J, Item B9.11 UT [ Cescrage % Surface Esasnhietten Weld No. J J J S Coversee % Reeman for Partial Esasubnatten i 33 . 100 0 55 55 100 The weld was not accessette fresa the 5 side due to the cenageretten of the reerter coelunt paw The beams path eende not be estended to emendsee the weld be two dim 14esas fresse alee 2 side becessse time pipemg umsterlei is type ASTM AJ51 sustenitic steel casting,which requires the use of focused I,wases. Focused I,weves casuset be estended beyond the Aret sound leg. Tine weld uns esannined to the nessinsema entent practical using 45*L and 60*L RTD search em:00s frees egne leep , pipe side. Appreshnetely 100% of the lower IG etthe weld was covered in the 2 directleen. 32 0 100 100 100 100 The weld was not necessible frena itse 2 side due to the configerstlen of time reacter coolant punny. The beams path esedd i not be entended to esasuine the weld In two directions frema the 5 side because the piping amaterialis type ASTM AJ51 sustenleic steel resthig, which rquires the use of focused 1,weves. Focused I,weves cosmest be estesided beyeend the Aret seemed leg. The weld was examshied to time suosinamen estent practical seeing 45*L SWS demi trW search imnet Ikeen the loop pipe side. Appresimentely 100% of the lower 10 etthe weld was revered in the 5 directlen. i UT Scan Directlen Defindelens [ 2 - Asimi seen, ISO degrees fresa Isonnetric flew dimtlen. 4 5 - Antal scan, Gee sanne directlen as the loosnetric flow. 7 - Clmmunferentini scan, clockwise rotatlose when slewiseg in the direction etiseenetric flow. 5 - Orcesuferential scan, cosmeterclockwise rotation winen viewing in the direction of Isesnet ric flow. l 5 6 Page 3 of 5 t L
)
Figure NDE-40-1 Weld 32 on Line 31"-RC-408-250lR-Q1 . 2,c,.,c Drawing: 12050-WMKS-0109G-1 m
'ssacas snnot t
Search Unit Search Unit 4 y 4 Degree % Bam 6 Degree Angle Beem RMw CN % 31"-RC-408-2501R-Q1 2-RC-P Pipe Side of Weld n
- 10 10t Exanndian Vdume o
Page 4 of 5 2 Side 6 Side
Figure NDE-40-2 Weld 33 on Line 271/2-RC-409-2501R-Q1 Drawing 12050-WMKS-0109G-1 2 RCD tC 7 4 i 4 45' Angie Beem Path Reactor CooleN Punp 27 trr-RC-@9-2501R-Q1 2-RC-P-1C Pipe Side at Weld , skse at weed . 45* Angie Beam Path 60* Anght Beem Pani Lower 113 Examinshon Volume 2 Side 5 Side Page 5 of 5 , i i
? - _ _ - _ - _ . _ _ _ _ _ _ - _ - _ - - - _ - - - -_- -- . - _ _. - - .- _ _ _ _ _ . ..__----a _ _ _ _ - - _ _ - _ - _ _ _ _ _ - _ _ _ _ - _ - -
i l l Virginia Electric & Power Company North Anna Power Station Unit 2 , Second Ten Year Interval I Request for ReliefNo. NDE-041 l
- 1. Identification of Component:
Weld No. Drawing No. Line No. fJLus SW-35 12050-WMKS-0109G-2 29"-RC-407-250lR-Q1 1A SW 12050-WMKS-0109G-2 29"-RC-407-250lR-Ql 1A SW-47 12050-WMKS-0109G-2 27%"-RC-409-250lR-Q1 1A SW 12050-WMKS-0109G-2 27%"-RC-409-2501R-Ql 1A SW-49 12050-WMKS-0109G-2 27%"-RC-409-250lR-Q1 1A II, Code requirements: The 1986 Edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.31 requires a surface and volumetric examination of the weld and adjacent base metal as defined by Figure IWB-2500-9. The Code does not allow any reductions in the required surface and volumetric examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in ! coverage, ifit is less than 10 percent. l 111. Code Requirement from Which Reliefis Requested: Reliefis requested from fully performing the Code-required (1986 Edition of ASME ! Section XI Table IWB-2500-1, examination category B-J, item number B9.31) volumetric examination on the pipe branch connection welds identified above. IV. Basis for Relief: The components listed above have been examined to the extent practical as required by l the Code. However, due to the configuration of the weld joint (branch connection) along , , with the material type, the required volumetric coverage was not obtained. The extent of l volumetric and surface coverage is detailed in Table NDE-41-1. Figures NDE-41-1, ) through NDE-41-5 are provided as graphic detail of the limitations experienced. These l welds are branch connection welds and, as such, all welds of this type are scheduled for examination. Therefore, substitution with another weld is not feasible. Page 1 of 8 1
- V. Proposed Alternate Examination:
It is proposed that the volumetric examination completed at the reduced coverage be accepted as meeting the Code requirements. In addition:
- 1. A visual (VT-2) examination will be performed in accordance with Code requirements during the normally scheduled system leakage test each refueling outage.
- 2. Technical Specification requires that the reactor coolant system (RCS) leak rate be limited to one gallon per minute unidentified leakage. The RCS leakage is calculated at least once per 72 hours in accordance with Technical Specifications.
- 3. The containment atmosphere paniculate radioactivity is checked every 12 hours in accordance with Technical Specifications.
J The proposed alternative continues to ensure that the overall level of plant quality and i safety will be maintained. Relief was approved for similar welds on loop A by the NRC in a letter dated August 8, 1995. VI. Status: Pending - Virginia Power Letter 98-513 Dated 9-18-98. l I 1 h Page 2 of 8 i
)
_ _ _ . . . ._ . _ . _ _~ . _ _ . _ _ . _ . _ . . _ .. .. . _ m Table NDE-41-1 North Anna Unit 2 . Examination Coverage Estimates Category B-J, Item B9.31 , UT , Ceserege % Surface Examinetten WeW No. 2 5 7 J Ccsersee */. Ressen for Partial Emandnetten SW-35 77 0 30 30 100 Due to the weW geeneetry It is not feasible to scan frene the =m.iner pipe side, Le, time required lower 1/3 mree of alie weW le l not reachable with the sound beene patti freni this direction. The bessa path coedd not be entended to esambie the weW in two directness frene the 2 side because h piping smoterialis type ASThl A.351 austematic steel casting, wench regadres the , use et focused 1,wases. Focused I,weves esanot be estended beyond the Arst seemed leg. The weW was erandseed to she nueshimana entent practical using 45*L RTD search unit freni the large pipe side. Appresimmtely 77% of the lower IG et l h weW was covered with h 2 senso SW,36 0 87 30 30 100 thee to the weW geesnetry it b not feestble to scan freni flee smaller pipe side, Le, the regadred lower 10 ores of the weW le not reachable with flee seemed beena path firesse this directlen. The benen path conde not be estesided to esenhoe h weld ha two directions fresa flee 5 sWe because time piping neuterlet is type ASThI A.351 eastenitic steel costbeg, widch regadres the use of focused I,weves. Focused I,weves esanot be entended beyond the first sound leg. The weW was enesubmed to the naaminium extent practical using 45'L RTD search useet froen & Imrge pipe sWe. Appresinnately 87% of time lower 10 et the weld was covered with h 5 scest + SW-47 47 0 33 33 100 thic to the weW reeenetry it is not feasible to scan from the saneller pipe side, Le, time required lower 10 area of time weW to seet reachable with the sound bessa path fhien tids direction. The besma path could not be estended to esannhee the weW km two directlens from the 2 side because flee piphag sonaterial is type ASThl A.351 austenleic steel casting, widch requires the use of focused I,weves. Focused I,weves comunet be estesided beyond the Erst sound leg. The weW was enemmened to the meniniani estent practical usbeg 47'L RTD search unit fkesa the large pipe side. AppreW 47% of the lower IG et , the weW was covered with the 2 scese. SW-48 53 35 50 50 100 Due to the weW geometry it is not feasible to achieve the required coverage. The bessa path wee entended to e=* IIne weW isi two directions. The weW was emendned to the see:Innum esteset practical ushag 9.25* 45* mand 60' search amate, Apprensniately 53% of h lower 10 et the weld was covered he h 2 directless, and Appreshnistely 35% of the lesser IG . of the weW was revered in the 5 direction. l SW-49 75 9 45 45 ISO Due to the weW geannetry it is not feasible to scan freni the snieller pipe side Le, time regsdred Bewer IG eres of the weld is ~ : seat reachable with the sensed beasse path firens tids directiesi. Tlie bessa path couW not be entended to emendne the weW be ! two directieses from the 2 side because the piping meterial is type ASTM A.351 easteedste steel casting,which requires the i use of focused I,weves. Focused I,weves enneet be extended beyond the first sound leg. The weW was ezesnheed to the nes Innene extent practical ushig 47*L RTD search endt freen & Berge pipe side. Appreshisately 75% of k lower 10 of - i h weW was covered with the 2 senso UT Scan Directlen Deftmittens 2 - Asimi semet,190 degrees from isesnetric Sow directlen. S - Aximi scan, the sense direction as the inesnetric flow. 7 - Orcumferesitial scan, clockwise rotation when viewing in the direction ofisometric flow. 8 - Orcumferential scen, counterclockwise rotation when slewing in the directlen of Isometric flow. , f Page 3 of 8 1
!l . f h t a P m e 3 n e /i o B 1 t a e r ei n e lg n wm oa d i S A L x e e 2 e r g e D 5 4 _ 4 4 4
/
e d iS 5 1 % 1 5 4 EW 8 DS f o Ns 4 e ed rl g a u gWe P i F 1 Q-R J 1 0 pw d e d e 5 2-lo i S iS 7 F 0 5 2 4-r C R-W " 9 2 d le _ W . 1, _ 0-0E 2 5WS 1 1 2 4-C R-
"6
l g Is 11lI ! e A 1 1 Y N N 4 ?> si . z a: 3
.2 I, ni m W 3 m
e P
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Figure NDE-41-4
- u. - - -
Weld SW-48 5 Side 5 Side 4"-RCA15-1502-01. Weld SW-48 45 Degree Angle 80 Degree Asigle Bee , Path Bemm Path Search Unit Fkm ; i
\ %
2 Skle 1
]
) _
5 Side s 77%*-RC-409-2501R-Q 1 h L '
\ 2 Side N
2 Side
\ Lower 1/3
' examination g
wiume
!! should be noted, due to joint configuration, that comage was not consistert for 360 degrees around the ciretrnfeence. That is, etwerage in ;
some areas were greater then that shown, while in other arem N ctr.t: rage was less than tha! showrt See Ts* NDE-41-1 for comrage l percentages l Page 7 of 8
l : . ! (l 1 ' !! ll ; ;i , ; ! i ma P m e B e oh m e e treiu tam n e lg d n wmlo i Loav A S s e e 2 e p e
- D 7
4 t in - U h c r a 4 e . S 4 _ 4
/
e d i S _. 5 5
- (
1 9 44- - 8 EW D S f 8 o _ N e g el d P a r e u gW i F 7 _ 1 Q- - R . 1 i 1 0 5 - e e 2 m k d i s id S _ F s 2 M C i R-7 2
\w t
k e W , 1 0
. 2 9 0 4- . 5W 1
0 S 2 4-C R 6
! Virginia Electric & Power Company North Anna Power Station Unit 2 Second Ten Year Interval Request for ReliefNo. NDE-042
,1. Identification of Component:
i
; Weld No. Drawina No. CJag WS-01 12050-WMKS-CH-P-1C 2 WS-04 12050-WMKS-CH-P-1C 2 II. Code requirements:
The 1986 Edition of ASME Section XI Table IWC-2500-1, examination category C-C, item number C3.30 requires a surface examination of the weld and adjacent base metal as .
- defined by Figure IWC-2500-5. The Code does not allow any reductions in the required l F surface examination. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, ifit is less than 10 percent.
j- .III. Code Requirement from Which ReliefIs Requested: ) Reliefis requested from fully performing the Code-required (1986 Edition of ASME Section XI Table IWC-a00-1, examination category C-C, item number C3.30) surface i examination on the integrally welded attachments identified above. IV. Basis for Relief: [ The components listed above have been examined to the extent practical as required by the Code. However, due to the configuration of the support the required surface coverage could not be obtained. The extent of surface coverage is detailed in Table NDE-42-1. Figures NDE-42-1 and NDE-42-2 are provided as graphic detail of the limitations F- experienced. Substitution with another integrally welded attachment on this or another charging pump'would not necessarily improve the examination coverage since similar geometric conditions are expected. i.
. V. Proposed Alternate Examination:
It is proposed that the examination completed at the reduced coverage be accepted as i meeting the Code requirements.
\
l Page 1 of 5 } e n
, - - . - - , . . ,y - . , .
1 l l l l i The proposed examination coverage will ensure that the overall level of plant quality and ! safety will be maintained. : Relief was approved for identical welds on 2-CH-P-1B by the NRC in a letter dated August 8,1995. l 1 VI. Status: ) Pending - Virginia Power Letter 98-513 Dated 9-18-98. 1 l j l l l I l l l l l l l l Page 2 of 5
Table NDE-42-1 North Anna Unit 2 Examination Coverage Estimates (integrally Welded Attachments) Category C-C, Item C3.30 - Weld No, Surface Examination Coverare% Reason for Partial WS41 82 The bottom of the welded support is not accessible for examination. WS 04 70 The bottom of the welded support is net accessible for exanunation, and base nrtal is limited by a nance connection , L Page 3 of 5
Figure NDE-42-1 Integrally Welded Attachment WS-01 Drawing 12050-WMKS-CH-P-1C
"# f '
)] y x
/
A, V l l .I I A 2-CH-P-1C
/ \ l 4 > !
InaccessitAe Area inaccessible Area is towed in. Inaccessible area extends from the left at the base metal fillet weld interface and inchdes one-half Inch of base metat on the right side of the support. i i Page 4 of 5 ,
Figure NDE-42-2 Integrally Welded Attachment WS-04 Drawing 12050-WMKS-CH-P-1C WS-04 ,g b V
\ End View dL 2-C H P.1 C x /
JL inaccessibe Area inaccessibe Area is the area inside the box. It extends up the right side of the welded attachment and includes 07 of base rnetal. The access to the right side is restricted due to a f!ange. Page5of5
RELIEF REOUEST SPT-1 I. IDENTIFICATION OF COMPONENTS 4 System: Chemical and Volume Control (CH) Components: Piping on drawing 12050-CBM-095C-2, Sheet 2 of 2, between the pumps, and the boundarieslisted below. PUhF LINE BOUNDARY ISI CLASS 2-RC-P-1A 2"-CH-414-1502-Q1 1st Flange 2 1 1/2"-CH-798-1502-Q1 1st Flange 1 4 3/4"-CH-772-1502-Q1 1st Flange 2 1" & 3/4"line 2-CH-274 1 1" & 3/4" line 2-CH-275 1 4-2-RC-P-1B 2"-CH-415-1502-Ql 1st Flange 2
- 1 1/2"-CH-797-1502-Q1 1st Flange 1 3/4"-CH-773-1502-Ql 1st Flange 2 1" & 3/4" line 2-CH-298 1 1" & 3/4" line 2-CH-299 1
; 2-RC-P-1C 2"-CH-416-1502-Ql 1st Flange 2
] 1 1/2"-CH-796-1502-Ql 1st Flange 1 d 3/4"-CH-774-1502-Ql 1st Flange 2 1" & 3/4" line 2-CH-321 1 1" & 3/4" line 2-CH-322 1
- II. IMPRACTICAL CODE REQUIREMENTS i-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 = 2735 psig Td = 250F Test Pressure = 3419 psig 3
Page 1 of 2 0
1 l l RELIEF REOUEST SPT-1 F CONTINUED III, BASIS FOR RELIEF The sealinjection flow is provided from the charging pumps to the reactor coolant pump. This
' flow divides in the pump with pan 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 immediate isolation exists, any pressurization above normal charging pressure would require that the RCS be pressurized to the same amount. This would 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 will be visually examined (VT-2) at normal operating pressure.
- V. STATUS Granted with conditions - NRC Letter No. 92-730 Dat6d 11/5/92. Granted provided the requirements for system hydrostatic testing in IWA-5213, " Test Condition Holding Time" are met prior to po" forming the VT-2 visual examination.
I 1 1 Page 2 of 2
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RFIIEF REOUEST SPT-2 l
- 1. IDENTIFICATION OF COMPONENTS Systemi Chemical and Volume Control (CH)
Components: Piping located on drawing 12050-CBM-095C-2, Sheet 1 of 2, between the valveslisted below. VALVES LINE 2-CH-341 and 2-CH-HCV-2311 2"-CH.468-1502-Ql 2-CH-358 and 2-CH-340 3"-CH-401-1502-Q1 ISI Class: 1 II. IMPRACTICAL CODE REQUIREMENTS System Hydrostatic Test per IWB-5222. Po=2500 psig, To=496*F, Test Pressure is 2550 psig - , per IWB-5222. III. BASIS FOR RELIEF Check valves 2-CH-341 and 2-CH-358 prevent the components listed above from being . pressudzed to Section XI requirements without pressurizing the reactor coolant systera. The ; cede required test pressure of 2550 psig will oveipressudze the reactor coolant system. Also,' the power operated relief valves (2-RC-PCV-2456 and 2-RC-PCV-2455C) 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. ALTERNA'E 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 rer.ctor is in a shutdown condition in order to seat check valves 2-CH-358 and 2-CH-341, thus creating a pressure boundary. The i components listed above will then be tested at a pressure between 2300 psig and 2335 psig using a chargmg pump. l Page 1 of 2
e W i RELIEF REOUEST SPT-2 CONTINUED NOTE: Similar reliefwas submitted by letter dated May 22,1987, Serial No. 86-796A for
. Nonh Anna Unit 1, and approved by NRC letter dated July 17,1987.
V. - STATUS Granted NRC Letter No. 92-730 Dated 11/5/92. l l l l i I l l 1 1 1 I Page 2 of 2
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i l 1 RELIEF REOUEST SPT-3
' If IDENTIFICATION OF COMPONENTS System: ResidualHeat Removal (RH) ,
Components: Piping located on drawing 12050-CBM-094A-2, Sheet 1 of 2, between the valves listed below, i VALVES LIE 2-RH-MOV-2701 & 14"-RM-401-1502 RH-MOV-2700 ISI Class: 1 H. IMPRACTICAL CODE REQUIREMEFTTS Class 1 System Hydrostatic Test IWB-5222. Po=2235 psig, To=650'F, Test pressure per :
- IWB-5222 is 2280 psig.
III. BASIS FORRELIEF During the system hydrostatic test of the primary system, 2-RH-MOV-2700 and 2-RH-MOV-2701 are closed in order to prevent possible overpressurization of the residual heat removal system. Thus, the portion of the RHR system identi6ed above cannot be pressurizd with the primary system and due to system design, it cannot be pu.cd.zal without opening one of the MOVs. IV, ALTERNATETESTING
~ As an altemative, the core.ponents listed above will be tested in accordance v ith IWC-5222 during the hydrostatic test .dministered to line 14"-RH-402-602. The test pressure will be 584 psig as determined by the setpoint of relief valves 2-RH-RV-2721A and 2-EH-RV-2721B. This ahernative is considered sufficient since the relief valves are set at 467 pig. As a result, line 14"-RH-401-1502 should not see a pressure signi6cantly higher than 467 psig. In addition, 2-RH-MOV-2700 and 2-RH-MOV-2701 will not open if the reactor coolant pressure is 660 psig.
Relief was granted to North Anna Power Station Unit 1 per Safety Evalus tion Report dated July 13,1987 (TAC No. 64718) for the same situation described above I V. STATUS - Granted - NRC Letter No. 92-730 Dated 11/5/92. Page 1 of1
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RELIEF REOUEST SPT-4 I. IDENTIFICATION OF COMPONENTS System: SafetyInjection(SI) Components; Piping located on drawing 12050-CBM-096B-2, Sheet 4 of 4, between the valves listed below. VALVES LINES 2-SI-92,2-SI-90 and 2-SI-91 6"-SI-531-1502 4 2-SI-100,2-SI-98 and 2-SI-99 6"-SI-533-1502 2-SI-106,2-SI-104 and 2-SI-105 6"-SI-532-1502 j 2-SI-125,2-SI-l12 and 2-SI-123 6"-SI-416-1502 j 2"-SI-463-1502 2-S1-113,2-SI-l17 and 2-SI-l11 6"-SI-419-1502 2"-SI-459-1502 2-SI-l18,2-SI-124 and 2-SI-l16 6"-SI-421-1502 2"-SI-461-1502 ISI Class: I j l
- 11. 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. Thr., power operated relief valves (2-RC-PCV-2456 e.nd 2-RC-PCV 2455C) of the reactor coolant system are designed to limit the pressurizer pressure to a value below the fixed high-pressure reactor l trip setpoint (2385 psig). The relief valve setpoints are 2335 psig which is below the test i pressure of 2432 psig. It is not desirable to take the reactor coolant system above the power operated reliefvalve setpoint. l l Page 1 of 2 ,
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RELIEF REOUEST SPT-4 CONTINUED IV. ALTERNATE TESTING As an alternative, the reactor coolant system will be pressurized to a pressure as close as 4 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 tested to a pressure between 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. V. STATUS Granted - NRC Letter No. 92-730 Dated 11/5/92. 1 i Page 2 of 2
l 1 S BELIEF REOUEST SPT-5
- 1. IDENTIFICATION OF COMPONENTS l l
System: Chemical and Volume Control (CH) ) Components: Piping located on drawing 12050-CBM-095C-2, Sheet 1 of 2, between the ; valves listed below. I VALVES . LINES 2-CH-358, 2-CH-HCV-2311, 3/4"-CH-640-1502 and 2-CH-MOV-2289 A 2"-CH-468-1502 3"-CH-401-1502 3"-CH-479-1502 , 3"-CH-819-1502 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 pressure per IWC-5222 is 3419 psig. III. BASIS FOR RELIEF , Check Valves 2-CH-341,2-CH-340 and 2-CH-358 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 (2-RC-PCV-2456 and 2-RC-PCV-2445C) 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 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 2-CH-341 and 2-CH-358. The components listed abeve will then be tested to a pressure between 2300 psig and 2335 psig using a charging pump. Page 1 of 2
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RELEF REOUEST SPT " 4
' CONTINUED l, . NOTE: Similar relief was submitted by letter dated May 22,1987, Serial No. 86-796A for
, Nonh Anna Unit 1, and approved by NRC letter dated July 17,1987. 4 $ V. STATUS $ Granted - NRC Letter No. 92-730 Dated 11/5/92, i-i t 4 i J 4 l J i Page 2 of 2
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RELIEF REOUEST SPT-6 I. IDENTIFICATION OF COMPONENTS System: SafetyInjection Components: Piping and valves located on drawings 12050-CBM-096A, Sheet 2 of 3, and 12050-CBM-096B, Sheet 4 of 4, listed below. VALVE CONNECTING LINE VALVE 2-SI-MOV-2890C & 10"-SI-418-1502 2-SI-MOV-2890D 10"-SI-624-1502 to 6"-SI-533-1502 2-SI-91 to 6"-SI-532-1502 2-SI-105 to 6"-SI-531-1502 2-SI-99 2-SI-MOV-2890A 10"-SI-415-1502 to 6"-SI-416-1502 2-SI-l12 to 6"-SI-419-1502 2-SI-ll7 to 6"-SI-530-1502 2-SI-214 to 6"-SI-421-1502 2-SI-MOV-2890B 10"-SI-540-1502 to 6"-SI-421-1502 2-SI-124 2-SI-89 2"-SI-451-1502 2-SI-90 2-SI-97 2"-SI-453-1502 2-SI-98 2-SI-103 "-SI-455-1502 2-SI-104 ISI Class: 2 II. IMPRACTICAL CODE REQUIREMENTS Class 2 System Hydrostatic Test per IWC-5222. P, = 2485 psig, Design Temperature is less than 200*F, Test pressure is 2733.5 psig. III. BASIS FOR RELIEF Check valves 2-SI-92,2-SI-100,2-SI-106,2-SI-125,2-SI-113 and 2-SI-l18 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. Pape 1 of 2 4
RELIEF REOUEST SPT-6 CONTINUED The power operated relief valves (2-RC-PCV-2456 and 2-RC-PCV-2455C) 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 2733.5 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 while the reactor is in a shutdown condition to create a pressure boundary at check valves 2-SI-92,2-SI-100,2-SI-106, 2-SI-125,2-SI-l13 and 2-SI-ll8. These components will then be tested to a pressure between 2300 psig and 2335 psig using a test pump. 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. V. STATUS-Granted - NRC Letter No. 92-730 Dated 11/5/92. Page 2 of 2
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i I I RELIEF REOUEST SPT-7 I. IDENTIFICATION OF COMPONENTS ) i System: SafetyInjection (SI) 2 Components: Piping located on drawings 12050-CBM-096B-2, Sheets I of 4,2 of 4 and i 3 of 4, between the sets of valves listed below. 1 VALVES LINE NUMBERS 2-SI-MOV-2865A, 2-SI-151 12"-SI-523-1502 , and 2-SI-149 3/4"-SI-478-1502 2-SI-MOV-2865B, 2-SI-168 12"-SI-524-1502 and 2-SI-166 3/4"-SI-484-1502 2-SI-MOV-2865C,2-SI-l85 12"-SI-525-1502 i
- and 2-S1-183 3/4"-SI-480-1502 4
. ISI Class: 2 l II. IMPRACTICAL CODE REQUIREMENTS Class 2 System Hydrostatic Test per IWC-5222. Pa=2485 psig, T=200 F, Test pressure per the code is 2733.5 psig since there is no overpressure protection for the above components.-
.III. BASIS FOR REQUEST Check valves 2-SI-151,2-SI-168, and 2-SI-185 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, which would overpressurize the primary system.
IV. ALTERNATE TESTING j l As an alternative, it is requested that the Class 2 components listed above bE tested to the conditions ofIWB-5222 which is required for the adjacent Class 1 piping. The nominal 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. I Page 1 of 2 I 1
RELIEF REOUEST SPT-7 . ~ CONTINUED NOTE: Similar reliefwas 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. V. STATUS
' Granted - NRC Letter No. 92-730 Dated 11/5/92.
I l i l 1 l i Page 2 of 2
RFT IFF REOUEST SPT-8 I. IDENTIFICATION OF COMPONENTS Systems: Main Steam (SHP) Decay Hest 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 12050-CBM-070B-2, Sheet 1 of 3,2 of 3, and 3 of 3; 12050-CBM-074A-2, Sheet 1 of 3; 12050-CBM-089B, Sheet 3 of 4; 12050-CBM-098A, Sheet 2 of 5; 12050-CBM-102A-2, Sheet 2 of 2; and 12050-CBM-102B-2, Sheet 1 of I between the components listed in Table SPT-8.
. ISI Class: 2 II. IMPRACTICAL CODE REQUIREMENTS Class 2 Hydrostatic Test per IWC-5222 and IWA-5213(d). For Feedwater components, ,
1 Pa=1100 psig, T4>200 F, test pressure per IWC-5222 would be 1375 psig. For the Chemical Feed components, P4=1775 psig, T4<200*F, test pressure per IWC-5222 would be 1952.5 psig. The remaining components have P4=1085 psig, T4>200*F, test pressure I per IWC-5222 would be 1356 psig. 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 listed above because these components cannot be isolated from the steam generators. l 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. Page 1 of 5
RFT TRF REOUEST SPT-8 CONTINUED The secondary side will be held at 1356 psig for 30 minutes and then reduced to 1085 psig for a minimum of 31/2 hours in accordance with Section XI. A VT-2 examination will then be performed on the components described in Table SPT-8. 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. V. STATUS Granted - NRC Letter No. 92-730 Dated 11/5/92. j I l l l Page 2 of 5
RFIJFF REOUEST SPT-8 -Table SPT-8 Components FROM TO COMPONENT CONNECTED PIPING COMPONENT 2-RC-E-1A 32"-SHP-401-601 2-MS-SV-201 A to 32"-SHP-422-601 - 2-MS-SV-202A 2-MS-SV-203A 2-MS-SV-204A 2-MS SV-205A to 6"-SHP-437-601 & 1"-SHP-484-601 2-MS-PCV-201A to 3"-SHP-464-601 & 2-MS-18 1"-SHP-478-601 2-MS-335 to 1 1/2"-SHPD-406-601 ' 2-MS-22 to 1/2"-SHPD-471-601 2-MS-26 2-RC-E-1A 32"-SHP-401-601 2-MS-502 2-NRV-MS-201A 3"-SHP 460-601 2-MS-344 ; 2-RC-E-1A 32"-SHP-401-601 to 32"-SHP-422-601 to 3"-SHP-445-601 2-MS-344 to 3"-SHP-562-601 2-MS-NRV-203A to 1"-SHP-555-601 2-MS-346 2-MS 348 2-RC-E-1 A 2"-SS-620-601 & 1"-SS-753-601 2-SS-83 2-IiC E-1A 32"-SHP-401-601 to 32"-SHP-422-601 l to 3"-SDHV-401-601 to 4"-SDHV-404-601 2-MS-20 1 2-RC-E-1A 16"-WFPD-424-601 2-FW-62 to 3"-WAPD-427-601 2-FW-70 to 3/4"-CFPD-401-601 2-WT-42 2-RC-E-1A 2"-WGCB-404-601 2-BD-4 2"-WGCB 405-601 2-BD-1 1"-WGCB-406-601 2-BD-2 2-RC-E-1A 2"-SGD-404-601 2-WT-426 Page 3 of 5
_ . __ _ . . - _ . . ~ _ _ _ .. . _ _ , . . . _ . . . . .- __ .. ._ 4 . RRI TEF REOUEST SPT Table SPT-8 Components - CONTINUED 1 FROM TO ! CONNECTED PIPING COMPONENT COMPONENT
)
2-RC-E-1B 32"-SHP-402-601 to 32"-SHP-423-601 2-MS-SV-201B 2-MS-SV-202B 2-MS-SV-203B 2-MS-SV-204B 2-MS-SV-205B to 6"-SHP-438-601 & 1"-SHP 485-601 2-MS-PCV-201B to 3"-SHP-465-601 2-MS-333 1"-SHP-480-601 2-MS 57 to 1 1/2"-SHPD-408-601 2-MS-60 to 1/2"-SHPD-473-601 2-MS-64 2-RC-E-1B 32"-SHP-402-601 2-MS-73 2-MS-NRV-201B 3"-SHP-461-601 2-MS-353 t 2-RC E-1B 32"-SHP-402-601 to 32"-SHP-423-601 to 3"-SHP-446-601 2-MS-352 3' to 3"-SHP-461-601 2-MS-353 to 3"-SHP-563-601 2-MS-NRV-203B to 1"-SHP-503-601 2-MS-356 2-MS-357 2-RC-E-1B 2"-SS-625-601 & 2 1"-SS-754-601 2-SS-84
- 2-RC-E-1B 32"-SHP-402-601 to 32"-SHP-423-601 to 3"-SDHV-402-601 to 4"-SDHV-404-601 2-MS-20 2-RC-E 1B 16"-WFPD-423-601 2-FW-94 to 3"-WAPD-428-601 2-FW-102
,. to 3/4"-CFPD-402-601 2-WT-54 2-RC-E-1B 2"-WGCB 407 601 2-BD-13 2"-WGCB-408-601 2-BD-10 2"-WGCB-409-601 2-BD-11 2-RC-E-1B - 2"-SGD-405-601 2-WT-427 Page 4 of 5
RELIEF REOUEST SPT Table SPT-8 Components . CONTINUED FROM- TO COMPON_EE[ CONNECTED PIPING COMPONENT 2-RC-E-lC 32"-SHP-403-601 to 32"-SHP-424-601 2-MS-SV-201C 2-MS-SV-202C 2 MS-SV-203C 2-MS-SV-204C 2-MS SV-205C I to 6"-SHP-439-601 & 1"-SHP-486-601 2-MS-PCV-201C ! to 3"-SHP-466-601 & 2-MS-95 1"-SHP-482-601 2-MS-331 to 1 1/2"-SHPD-407-601 2-MS-98 to 1/2"-SHPD-475-601 2-MS-102 2-RC-E-1C 32"-SHP-403-601 2-MS-111 2-MS-NRV-201C 3"-SHP-462-601 - 2-MS-362 2-RC-E-lC 32"-SHP-403-601 to 32"-SHP-424-601
- to 3"-SHP-447-601 2-MS-TV-213C to 3"-SHP-462-601 2-MS-362 to 3"-SHP-564-601 2-MS-NRV-203C to 1"-SHP-504-601 & 2-MS-366 1"-SHP-557-601 2-MS-365 2-RC-E-1C 2"-SS-627-601 1"-SS-755-601 2-SS-85 i
i 2-RC-E-1C 32"-SHP-403-601 to 32"-SHP-424-601 to 3"-SDHV-403-601 l to 4"-SDHV-404-601 2-MS-20 l 2 RC-E-1C 16"-WFPD422-601 2-FW-126 to 3"-WAPD-429-601 2-FW-134 to 3/4"-CFPD-403-601 2-WT-70 2-RC-E-1C 2"-WGCB-410-601 2-BD-22 2"-WGCB-411-601 2-BD-19 l 1"-WGCB-412-601 2-BD-20 l 2-RC-E-1C 2"-SCD-405-601 2-WT-428 Page 5 of 5 1
RELIEF REOUEST SPT-9 I.' IDENTIFICATION OF COMPONENTS System: Feedwater (WAPD) l . Components: Piping located on drawing 12050-CBM-074A-2, Sheets 1 of 3 and 3 of 3, between the valves listed below. VALVE CONNECTING LINES VALVE 2-FW-64 3"-WAPD-410-601 to 3"-WAPD-409-601 2-FW-66 2-FW-66 3"-WAPD-409-601 2-FW-70 2-FW-93 3"-WAPD-412-601 to 3"-WAPD-411-601 2-FW-98 2-FW-98 3"-WAPD-411-601 2-FW-102 2-FW-128 3"-WAPD-414-601 to 3"-WAPD-413-601 2-FW-130 2-FW-130 3"-WAPD-413-601 2-FW-134 2-FW-278 4"-WAPD-439-601 ) to 3"-WAPD-409-601 2-FW-66 ISI Class: 3 II. . IMPRACTICAL CODE REQUIREMENTS Civ 3 System Hydrostatic Test per IWD-5223 and IWA-5213(d). Po=1400 psig, T4 < 20L F, Test Pressure is 1540 psig per IWD-5223. III. BASIS FOR RELIEF j
' Due to check valves 2-FW-134, 2-FW-102, and 2-FW-70, the piping listed above cannot )
be pressurized without pressurizing the steam generators. The code required test pressure j I of 1540 psig would overpressurize the steam generators. i Page 1 of 2 j i
RELIEF REOUEST SPT-9
~
CONTINUED IV. ALTERNATE TESTING Since the components listed above cannot be pressurized without pressurizing the steam generators, they must be tested per the required manufacturer's hydrostatic test method. Therefore, the proposed alternative examination is the examination described in the Westinghouse Technical Manual for the secondary side of the steam generators. The examination is to pressurize the secondary side of the steam generators to 1356 psig, hold for 30 minutes, and then reduce to the design pressure (1085 psig) for 31/2 hours. A VT-2 examination will then be performed. 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. V. STATUS Granted - NRC Letter No. 92-730 Dated 11/5/92. Page 2 of 2
I RELIEF REOUEST SPT-10 (WITHDRAWN - VP Letter No. 91-461 Dated 9/9/91) Page 1 of 1
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_ RELIEF REOUEST SPT-11 I. IDENTIFICATION OF COMPONENTS System: Reactor Coolant (RC) ; e , Components: Partial Penetration Welds @ Bottom of Reactor Vessel 1 ISI Class: 1 II. IMPRACTICAL CODE REQUIRILMENTS 1 l J
. Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition, Category B-E, !
Item No. 4.13, requires reactor vessel partial penetration welds to have a visual (VT-2)
- examination during the system hydrostatic test ofIWB-5222; in addition, Camgory B-P, ;
Item Nos. B15.10, and B15.11 require a visual (VT-2) examination of the bottom of the reactor vessel during the system leakage test oflWB-5221 and during the system hydrostatic test ofIWB-5222, respectively. IIL BASIS FOR RELIEF In order to meet the Section XI pressure and temperature requirements fc r the system
- Jeakage and system hydrostatic tests of the reactor vessel, reactor containment at North Anna Unit 2 is required to be at a subatmospheric pressure. Station admiaistrative procedures require that self contained breathing apparatus be worn for containment entries t nder these conditions. This requirement significantly complicates the visual (VT-2) examination of the bottom of the reactor vessel during testing. Access to the bottom of i the reactor vessel requires that the examiner descend several levels by ladder and navigate ;
a small entrance leading to the reactor vessel. In addition to these physical constraints, the examiner must contend with extreme environmental conditions: elevated a.r temperatures due to reactor coolant at temperatures above 500 degrees F and limited air circulation in j the vessel cubicle. In addition, the examiner is limited to the approximate 30 minate capacity of the breathing apparatus for containment entry, the VT-2 examinttion, and containment exit. J I Page 1 of 2 , 4 1
l 1 1 l 1 ! *; RELIEF REOUEST SPT-11 CONTINUED ! IV. ALTERNATE TESTING Technical Specifications require that the Reactor Coolant System Leak Rate be limited to 1 gallon per minute unidentified leakage. This value is calculated at least once per 72 hours. Additionally the containment atmosphere particulate radioactivity is monitored a every 12 hours. The incore sump room has a level alarm in the control room requiring l' operator action. These actions would identify any integrity concerns associated with this area. A VT-2 examination will be conducted when containment is at atmospheric conditions each refueling for evidence of boric acid corrosion. V. STATUS i Granted - NRC Letter No. 92-730 Dated 11/5/92. 3. e i i i 2 1 1 l l l Page 2 of 2 l l l l l
.. .. .. . . ~ . . - .- . . - - - . - . . - . . - . - . - . - . . . . - . . . - -
4 d., e
. RELIEF REOUEST SPT-12 I. ' IDENTIFICATION OF COMPONENTS
. System- : Reactor Coolant (RC) .
Charging (CH) SafetyInjection(SI) (Note: Components located inside containment which are normally tested in subatmospheric
- conditions)
Components: Pressure Retaining Bolting ISI Class: I and 2 II. IMPRACTICAL CODE REQUIREMENTS Subparagraph IWA-5242(a) requires, for systems borated for the purposes of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for visual examination VT-2. III. BASIS FORRELIEF. f A majority of these systems are located in containment. In cases where there is no intermediate isolation from the reactor coolant system the system pressure test is performed when the i reactor coolant is greater than 500 degrees F and the containment is subatmospheric. Removing and reinstalhng insulation under these conditions is difficult to perform and deemed
~ impractical when compared to the existing VT-2 program. -
IV. ALTERNATIVE TESTING It is proposed that bolted connections on Class I systems containing boric acid be examined each refueling outage at zero or static pressure. The examination would be performed with the insulation removed. Class 2 bolting will be examined similarly once a period. This alternative only applies to systems that can only be pressure tested under subatmospheric conditions. All bolted pressure retairung connections where the bolting material is determmed to be austenitic, martensitic, or precipitation hardened stainless steels, or made from high strength , nickel based alloys, will not be inspected with them' sulation removed. 1 Page 1 of 2 l l
I l 1 RELIEF REOUEST SPT-12
- CONTNUED 1
This alternative goes beyond our response to IE Bulletin 82-02, Degradation of Threaded
- Fasteners in the Reactor Coolant Pressure Boundary of PWR Plants. In our response to IE
- Bulletin 82-02 we agreed to examine pressure retaining bolting on lines 4 inch NPS and larger j each refueling outage. In addition to our response to NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Camponents in PWR Plants, we
] committed to performing a visual examination of all accessiole portions of systems contauung boric acid anytime the unidenti6ed leak rate exceeds a predetermined value, at every cold i shutdown prior to decontaminating the containment, and during every reactor startup from l l Mode 5. In addition the Code required testing will still be conducted with a VT-2 Examination ; C without removing theinsulation. l d V. STATUS i l Class 1 and 2 bolted connections inside containment that can only be tested under i subatmospheric conditions - Granted with conditions - NRC Letter No. 92-730 Dated 11/5/92. . i. Granted with the following conditions:
- 1) for the system pressure test associated with plant start up, the system shall be held at nominal operating pressure for at least 4 hours for insulated systems and 10 minutes for j noninsulated systems before perfoaning the VT-2 visual examination, and j 2) the proposed altemative of removing the insulation each refueling outage for Class 1, i and once per inspection period for Class 2 bohed connections, during zero or static pressure, be expanded to include all Code-required bolted ccnnections, tested during subatmospheric conditions.
I l Class 1 and 2 austeitic, martesitic, precipitation hardened stainless steels, or high strength nickel-based alloy bolting materials - Denied - NRC Letter No. 92-730 Dated 11/5/92. 4 b L .h I 1 t Pape 2 of 2
BELIEF REOUEST SPT-13 NRAWN - NRC Letter No. 91-461 Dated 9/9/91)
=
1 l Page 1 of 1
RELIEF REOUEST SPT-14 Revision 1 I. Identification of Component Class 1,2 and 3 pressure retaining bolting 1 Impractical Code requirements I
- II.
IWA-5250 (a) (2) states, "ifleakage occurs at a bolted connection, the bolting shall be removed, VT-3 visually examined for corrosion, and evaluated in accordance with IWA- l 3100;" III. Basis for Relief Leaking conditions at a bolted connection may be an important variable in the degradation of fasteners. However, leakage is not the only variable, and some cases may not be the degradation mechanism. Other variables to be considered are: bolting materials, leaking medium, duration of the leak, and orientation of the leak (not all bolts may be wetted). These variables are importt.nt to consider before disussembling a bolted connection for a visual VT-3 examination. Removal of bolting at a mechardeal connection may not be the most prudent decision and may cause undue hardship without a compensating. increase in the level of quality or safety. Virginia Power proposes an alternative to the requirements ofIWA-5250 (a) (2) that will provide an equivalent level of quality and safety at Class 1, 2, and 3 bolted connections. IV. Alternate Requirements Leakage discovered at a bolted connection by visual VT-2 examination during a system pressure test will be evaluated to determine the susceptibility of the bolting to corrosion and potential failure. This evaluation will consider the following variables:
- 1. Location ofleakage;
- 2. History ofleakage;
- 3. Fastener materials;
- 4. Evidence of corrosion with the connection assembled;
- 5. Corrosiveness of the process fluid;
- 6. History and studies of simibt fastener material in a similar environment; and
- 7. Other components in the vicinity that may be degraded due to the leakage.
When evaluation of the above variables is concluded and the evaluation determines that the leaking condition has not degraded the fasteners, then no further action is necessary. Page 1 of 2
If evaluation of the variables above indicates the need for further evaluation, or no evaluation is performed, then the bolt closest to the source ofleakage will be removed.
' The bolt will receive a visual VT-3 examination, and be evaluated in accordance with
! IWA-3100 (a). This visual VT-3 examination may be deferred to the next outage of suffi-i cient duration if the evaluation supports continued service. When the removed bolting 4 shows evidence of rejectable degradation, all remaining bolts shall be removed and receive 1 a visual VT-3 examination and evaluation in accordance with IWA-3100 (a). V. STATUS
' Granted with conditions - Virginia Power Letter No. 96-550 Dated 10/16/96.
Granted provided that all seven evaluation factors listed above are considered as part of the leakage evaluation. , 4 l l 4 4
- 4 f -l l
Y l' 4 1 I 4 s l l Page 2 of 2 I
~
a
. RFI TEF REOUEST SPT-15 4
I. . IDENTIFICATIUd OF COMPONENTS 4 L Class 1,2, and 3 components
' II. IMPRACTICAL CODE REQUIREMENTS f
. IWA-4000 and IWA-5214 require a hydrostatic pressure test in accordance with IWB-5000, l IWC-5000, or IWD-5000 following welded repairs or installation of replacement items by welding.
1 is III. BASIS FORRFIIFF l In past situations our utility has been required to defer or ask relief from ASME Section XI
- hydrostatic tests following repair or replacement activities due to various reasons, which identified a basis ofimpracticality. This has ranged from boundary valve isolation problems to incorporation of the steam generators in the test boundary. These situations have necessitated
- in some cases immediate communication with and approval from the NRC, so that start-up l delays or LCO conditions could be avoided. Test deferrals, like those associated with the steam generator, eventually must be conducted, and are considered inordinately burdensome, considering that the 10-year hydrostatic tests have been eliminated for Class 1 and 2 systems !
- with the approval in Regulatory Guide 1.147, Code Case N498," Alternative Rules for 10-
- year Hydrostatic Pressure Testing for Class 1 and 2 Systems, Sedon XI, Division 1 " The i Code has recognized that alternative rules should be available to hydroaatic testing to allow an I option to the owner. They have developed Code Case N-416-1, "Altemative Pressure Test ;
. . Requirement for Welded Repairs or Installation of Replacement Items by Welding." This Code l Case as of this writing has been passed by Section XI and has been sent up to Main Committee J i for approval. Accordingly, it is considered impractical to maintain only the hydrostatic test option. l IV. ALTERNATE TESTING In situations following welded repairs or installation of replacement items by welding, when the . hydrostatic test required by IWA-4000 or IWA-5214 is not performed, the following
. altemative requirements shall be applied: .
L i
- Pge 1 W2 i f-i
RELIEF REOUEST SPT-15 (CON'T)
- 1) NDE shall be performed in accordance with the methods and acceptance criteria of the applicable Subsection of the 1989 Edition of ASME Section III. Additionally, where no constmetion NDE is required on partial and full penetration welds greater than 1 inch nommal pipe size, these welds shall receive a surface exammation as a nuntmum.
- 2) Prior to or irmnediately upon retum to service, a VT-2 visual exammation shall be performed in conjunction with a system pressure test, using the 1986 Edition of Section XI, in accordance with IWA-5000, at nominal operating pressure and tempera-ture.
- 3) Use of this alternative shall be documented on the NIS-2 Form.
If the original Code Case N-416 was used to defer a Class 2 hydrostatic test, the deferred test may be eliminated when the requirements of this attemative testing have been met.
- V. STATUS Status
- Withdrawn - VP Letter No. 94-319 Dated 6/23/94. i i
l t 1 5 l Page 2 of 2 l
- Virginia Electric & Power Company North Anna Unit 2 -
- . Second 10-YearInterval Request for ReliefNo. SPT-16, Revision 2 !
I. IDENTIFICATION OF COMPONENTS r ia Class 2 piping that penetrates the containment vessel where the piping and isolation valves are part of the j containment system but the balance of the piping is outside of the scope of Section XI. Drawing Test boundary Penetration Number j- 12050-SPM-096A-2 SH. 3 1"-SI 450-1502-Q1,3"-SI-568-1502-Ql,3"-SI-417-1502- 7 Q1,3"-SI-417-1502-Q1 i I 12050-SPM-096B-2 SH. 4 7 3"-SI-417-1502-Ql between 2-SI-93 and FMon 7 . E 12050-SPM-079B-2 SH. 3 f 6"-CC-752-151-Q2 13 12050-SPM-095C-2 SH.1 3"-CH 479-1502-Ql between 2-CH-MOV-2289A and 2- 15 CH-335 [ l 12050-SPM-095B-2 SH.1 3"-CH-499-153A-Q1 between 2-CH-MOV-2381 and pene- 19 [ tration 19
- 12050-SPM-095C-2 SH. 2 3"-CH-499-153A-Q1 between 2-CH-MOV-2380 and pene- 19 tration 19 and %"-CH-799-153A-Ql between 2-CH-331
] and w.Gon 19 1 12050-SPM-096A-2 SH. I 1"-Sly 3-602-Q2 between penetration 20 and 2-SI-47 20 g: 12050-SPM-096B-2 SH. I 1"-SI-413-602-Q2 between 2-SI-136 and penetration 20 20 j 12050 SPM-096A-2 SH. 3 3"-SI-538-1502-Ql between 2-SI-MOV-2836 and pene- 22 i tration 22
- 12050-SPM-096B-2 SH. 4 3"-SI-538-1502-Q1 between 2-SI-85 and penetration 22 22
! 12050-SPM-079A-2 SH. 2 8"-CC-678-151-Q2 25 i 12050-SPM-079A-2 SH. 4 8"-CC-688-151-Q2 26 ' 12050-SPM-079A-2 SH. 3 8"-CC-739-151-Q2 27 12050-SPM-090A-2 SH. I 2"-DG 435-153A-Q2 33 12050 SPB-104B-2 SH.1. 4" line between 2-FP-79 and 2-FP-81 34 12050-SPM-082B-2 SH. 2 1"-ARC-401-153A-Q2 between 2-RM-TV-200A and 2-IA- 43 428 12050-SPM-082B-2 SH. 2 1"-ARC-402-153A-Q2 between 2-RM-TV-200B and 2- 44 RM-TV-200C 12050-SPM-082B-2 SH. 2 1"-ARC-402-153A-Q2 between 2-RM-TV-200B and 2- 44 RM-TV-200C Pape 1 of 5
Drawing Test boundary Penetration Number 12050-SPM-082B-2 SH. 2 1"-ARC-402-153A-Q2 between 2-RM-TV-200B and 2- 44 RM-TV-200C 12050-SPM-095C-2 SH. I 2"-CH-666-1502-Q2 between 2-CH-332 and 2-CH-FCV- 46 2160 12050-SPM-082A-2 SH. I 2"-ACC-421-153A-Q2 between penetration 47 and 2-IA- 47 250 12050-SPM-082B-2 SH. I 2"-ACC-421-153A-Q2 between penetration 47 and 2-IA- 47 TV-202A 12050-SPM-096B-2 SH. I 1"-SI-498-601-Q2 between 2-SI-HCV-2936 and 2-SI-TV- 50 201 12050-SPM-096B-2 SH. I 1"-SI-517-1501-Q2 between 2-SI-132 and 2-SI-TV-200 53 12050-SPM-089B-2 SH. 2 _" -SS-749-ICN9-Q1 between 2-SS-TV-206A and 2-SS- 56B TV-206B 120's-SPM-089B-2 SH. 2 _" -SS-750-ICN9-Ql between 2-SS-TV-202A and 2-SS- 56C TV-202B 12050-SPM-089A-2 SH. 3 _" -SS-622-ICN9-Q2 between 2-SS-TV-212A and 2-SS- 56D TV-212B 12050-SPM-089B-2 SH,1 _" -SS-402-ICN9-Q2 between 2-SS-TV-201 A and 2-SS- 57C TV-201B 12050-SPM-096A-2 SH. 2 10"-SI-415-1502-Q1 and 6"-SI-416-1502-Ql 60 12050-SPM-096B-2 SH. 4 6"-SI-416-1502-Q1 between 2-SI-126 and penetration 60 60 12050-SPM-096A-2 SH. 2 10"-SI-464-1502-Q1 and 6"-SI-421-1502-Q1 61 12050-SPM-096B-2 SH. 4 6"-SI-421-1502-Q1 between 2 SI-128 and penetration 60 61 12050-SPM-096A-2 SH. 2 6"-SI-531-1502-Q1,10"-SI-418-1501-Q1, and 10"-SI-624- 62 1502-Ql 12050 SPM-0968-2 SH. 4 6"-SI 531-1502-Ql,6"-SI-50.-1502-Ql between 6"-SI- 62 531-1502-Q1 and 2-SI-105, and 6"-SI-533-1502-Q1 between 6"-SI-531-1502-Ql and 2-SI 99 12050-SPM-096B-2 SH. 2 8"-QS-439-153A-Q2 between 2-QS-MOV-201B and 2-QS- 63 22 12050-SPM-096B-2 SH. 2 8"-QS-437-153A-Q2 between 2-QS-MOV-201 A and 2-QS- 64 11 12050-SPM-091 A-2 SH. 4 12"-RS-407-153A-Q2 and 8"-RS-J73-153A-Q2 66 12050-SPM-091B-2 SH.1 8"-RS-373-153A-Q2,4"-RS-457-153A-Q2,8"-RS 456- 66 153A-Q2, and 6"-RS-182-153A-Q2 Page 2 of 5
Drawing Test boundary Penetration Number 12050-SPM-091 A-2 SH. 4 12"-RS 408-153A-Q2 and 8"-RS-J74-153A-Q2 67 12050-SPM-091B-2 SH.1 8"-RS-J74- 153 A-Q2, 4"-RS-461 -153 A-Q2, 8"-RS-460- 67 153A-Q2, and 6"-RS-J83-153A-Q2 12050-SPM-091A-2 SH. 4 10"-RS-410-153A-Q2 between 2-RS MOV-256B and 2- 70 RS-30 12050-SPM-091 A-2 SH. 4 10"-RS-409-153A-Q2 between 2-RS-MOV-256A and 2- 71 RS-20 11715-SPM-078B-2 SH. 3 16"-WS-627-151-Q2 between 2-SW-MOV-203D and 2- 79 SW-104 11715-SPM-078B-2 SH. 3 16"-WS-625-151-Q2 between 2-SW-MOV-203C and 2- 80 SW-94 11715-SPM-078B-2 SH. 3 16"-WS-623 151-Q2 between 2-SW-MOV-203B and 2- 81 SW-84 11715 SPM-078B-2 SH. 3 16"-WS-621-151-Q2 between 2-SW-MOV-203A and 2- 82 SW-74 11715-SPM-078B-2 SH. 3 16"-WS-622-151-Q2 83 11715-SPM-078B-2 SH. 3 16"-WS-624-151-Q2 84 11715-SPM-078B-2 SH. 3 16"-WS-626-151-Q2 85 11715-SPM-078B-2 SH. 3 16"-WS-628-151-Q2 86 12050-SPM-072A-2 SH. 2 6"-AJA-410-151-Q2 89 11715-SPM 106A-2 SH. 3 ,_"- HC-75 lCN9-Q2 between 2-HC-TV-200A and 2-HC- 98A TV-200B 11715 SPM-088A-2 SH.3 6"-RP-454-152-Q2 and 6"-RP-444-153A-Q2 103
-11715-SPM-088A-2 SH. 3 6"-RP-449-152-Q2 104 11715-SPM-106A 2 SH. 2 ," HC-413-ICN6-Q2 between 2-HC-TV-203B and 2-HC -
109 154-Q2, and 2%"-HC-440-154-Q2 between 2"-HC-3-l! 4-Q2 and 2-HC-TV-207B, and 2-HC-3-154-Q2 12050-SPM-096A-2 SH. 3 3" SI-457-1502-Ql 113 12050-SPM-096B-2 SH. 4 3"-SI-457-1502-Ql between 2-SI-l19 and penetration i 13 113 12050-SPM-096A-2 SH. 3 3"-SI-539-1502-Ql 114 12050-SPM-096B-2 SH. 4 3"-SI-539-1502-Ql between 2-SI-107 and penetration ! 14 114 II. IMPRACTICABLE CODE REQUIREMENTS l l Page 3 of 5
- Table IWC-2500-1, Examinatisn Category C-H, Items C7.30 and C7.70 requires a system pressure test each inspection period nnd Items C7.40 and C7.60 requires a system hydrostatic test each inspection interval. .
III. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED l Reliefis requesed from performing the Code-required hydrostatic test at the end of the inspection interval and the Code-required system pressure test dudng each period for the contaimnent penetrations listed. IV. BASIS FORRELIEF The sole safety function of the piping and associated valves listed is to provide contamment isolation. The components listed are part of the containment system. Containment penetrations are classified as Class 2 per ANSI 18.2, " Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants", i section 2.3.1.2 (1). For the subject perneons the connecting piping beyond the containment isolation valves serves no safety function and is danified as nonclass by the classification criteria used by Virginia Electric and Power Company for North Anna Unit 2. The ASME Section XI pressure testing requirements have verified leak-tight integrity by an over pressure test every ten years and a nominal operating test every inspection period. The 10-year hydrostatic tests were considered inordinately burdensome for the marginal benefit in safety they assure and have been eliminated by Code Case N-498, " Alternative Rules for 10-year Hydrostatic Pressure Testing for Class 1 and 2 Systems, Section XI, Division 1", which has been approved by Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability ASME Section XI Division 1. The 10-Year hydrostatic test is now conducted at nominal operating pressure. - The subject penetrations are Type C pressure tested to a peak contamment internal pressure of greater than or equal to 44.1 psig. This test is performed to satisfy Technical Specification Suiveillance Requirement 4.6.1.2 which requires all containment penetrations to be leak rate tested as required by 10 CFR 50, Appendix J, Option B, as modified by approved exeniptions, and in accordance with the guideline contained in Regulatory Guide 1.163, dated September 1995. The testing frequency of 10 CFR 50, Appendix J, Option B is performance based and can vary from 2 years to 5 years or three refueling cycles. This frequenev will not coincide with the inspection penod frequency required in Table IWC-2500-1 for system p sure tests and therefore, the ASME Code in effect at North Anna will require additionalleak tightness testing. The ASME Section XI Code has acknowledged that testing of these components beyond the requirements of Appendix J is not necessary and issued Code Case N-522, " Pressure Testing of Containment Penetration Piping", to define its position. NUREG-1493, "Pedormance-Based Contamment Leak-Test Program", concluded that prescriptive leak rate testing could be replaced with pedormance based requirements with only a marginal and acceptable impact on safety. The total cost of Type B (electrical penetrations) and Type C testing all containment penetrations (approximately 90 penetrations) was estimated to be $87,500 per outage for North Anna as reported in NUREG-1493. NUREG-1493 estimates that 5% of the total cost of Type B & C testing could be saved if the acceptance criteria wete relaxed. Performing ASME Section XI pressure testing Page 4 of 5
_ __ . _ _ _ _ . _ . _ _ ~ . _ . _ . _ . _ _ _ __ _ _ . _ . - - _ _ _ . i beyond the requirements of 10 CFR 50, Appendix J, Option B testing would cause Virginia Electric & Power Company to incur additional cost with a marginal gain in safety, i V. PROPOSED ALTERNkTIVE As an alternative to the testing frequency and pressures required by Table IWC-2500-1, Examination Category C-H, Items C7.30, C7.40, C7.60, and C7.70, the subject penetrations and associated piping and valves, will be pressure tested at peak containment calculated pressures to the requirements of 10 ! CFR Appendix J, as allowed by Code Case N-522. Testing will be performed in accordance with Techni-cal Specification Surveillance Requirement 4.6.1.2 which requires all containment penetrations to be leak i rate tested as required by 10 CFR 50, Appendix J, Option B, as modi 6ed by approved exemptions, and in accordance with the guideline contained in Regulatory Guide 1.163, dated September 1995. , Methods fer the detection and location ofleakage at containment isolation valves and the pipe segments between the containment isolation valves will be identi6ed in procedures. j All subject penetrations will be Type C tested at least once every 60 months. VI. IMPLEMENTATION SCHEDULE The Technical Specifications were revised on 2/9/96 to incorporate 10 CFR 50, Appendix J, Option B. The subject containment penetrations were Type C tested in the second period. The third period starts on 12/14/97. Tes: intervais for valves having two consecutive periodic As-found Type C tests where the results are within the allowable administrative limits may be increased up to a maximum of 60 months. The subject val ies have satisfied this criteria and are not scheduled to be tested during the third period. VII. STATUS l Granted - NRC Letter No. 97-290 Dated 4/30/97 l 1 1 l 1 1 Page 5 of 5 l
1 'I VIRGINIA ELECTRIC AND POWER COMPANY
- NORTH ANNA POWER STATION UNIT 2 4
l I INSERVICE INSPECTION PROGRAM i 1 FOR COMPONENT SUPPORTS ! SECOND INSPECTION INTERVAL N2 003 Rev. !. Page 1 of 9
l SECTION 3
= TABLE OF CONTENTS j.
SECTIQN TITLE PAGE 3.0 INSERVICE INSPECTION PROGRAM FOR 3 COMPONENT SUPPORTS 3.1 PROGRAM DESCRIPTION 3 3.1.1 Snubber 3 3.1.2 Supports Exempt From Examination 3 3.1.3 Supports Selected For Examination 3 3.1.4 Sampling Plan 3 I 3.2 . PROGRAM
SUMMARY
' 4 3.2.1 Inservice Inspection Program Summary 4 3.3 INSERVICE INSPECTION PROGRAM
SUMMARY
TABLE 6 ISI Class 1,2, and 3 Component Supports
. 3.4 COMPONENT SUPPORT RELIEF REQUESTS 9 i
.)
i t i
'\:.
' N2-003 Rev.5 Page 2 of 9
i 3.0 INSERVICE INSPECTION PROGRAM FOR COMPONENT SUPPORTS 3.1 PROGRAM DESCRIPTION I The Inservice Inspection Program for ISI Class 1,2 and 3 component supports meets the i requirements of Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition except where these 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 ofIWF-2000 are thosc connected to components and items exempted from examination , under I%-1220, IWC-1220, and IWD-2000. In addition, portions of supports that are inaccessible by being encased in concrete, buried underground, or - encapsulated by guard pipe are also exempt from the examination requirements ofIWF-2000. These exemptions are excerpted from proposed Code Case 3 WGCS 89-1(b). See Relief Request CS-1 for details. 3.1.3 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, IWD-1220. This selection criteria is excerpted from proposed Code Case WGCS 89-1(b). See Relief Request CS-1 for details. 3.1.4 The following sampling plan will be employed; ISI Class 1 Piping Supports - Examine 25% of supports per interval. Notes 1, 2 and 4. ISI Class 2 Piping Supports - Examine 15% of supports per interval. Notes 1, 2 and 4. N2-003 Rev. 5 Page 3 of 9
4. ISI Class 3 Piping - Supports Examine 10% of supports per interval. Notes 1, 2 nd 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 hangers; B
= supports such as multi-directional restraims; and C = supports that allow thennal movement, such as springs). )
1
\
(2) The total percentage sample shall be comprised of supports from each system (such as Main Steam, Feedwater or RHR), where the individual i sample sizes are proponional to the total number of non-exempt supports i of each type and function within each system. l ~ 4 (3) For multiple components other than piping within a system of similar j: design, function and service, the supports of only one of the multiple ) components are required to be examined. l l (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). l l 3.2 PROGRAM
SUMMARY
l 3.2.1 The Inservice Inspection Program Plan Summary for Component Supports is l presented in Section 3.3 in a tabular format. The component suppons and
. j associated requirements are listed in descending order according to Code Category and Item Numbers. The following information is included in the l tables:
A. Code Category - The Section XI Examination Category as defmed in Table IWF-2500-1 for Class 1,2 and 3 component suppons. 1 I B. Item Number - The Section XI Item Number as listed in Table l IWF-2500-1. All Item Numbers are listed for each Code Category. l C. Part Examined - The Section XI description of the area to be examined. I N2-003 Rev. 5 ; Page 4 of 9 l
W D. Examination Method - Lists the examination method required by Section XI. The abbreviation used is as follows: VIS - Visual examination per IWA-2213 1 E. Alternate Examination Method - Lists the examination method that will be performed as an alternative to the Section XI required examination as stated in a referenced relief request. 'I F- Examination Reauirements/ Figure 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. 4 i N2-003 Rev. 5 Page 5 of 9
.3 ISI Class 1,2 &_3 Component Supports
.3.1: Examination Categodr F-A, Plate And Shell Type Supports - Program Summary Table
' ALT. EXAM TEM EXAM . EXAM- REQUIRED / - ACCEPTANCE RELIEF O. PARTS TO BE EXAMINED METIlOD METHOD FIG NO. CRITERIA REOUEST 1.10 Mechanical connections to VIS, IWF-1300-1 IWF-3410 CS-1 pressure retaining components VT-3 and building structure 1.20 Weld connections to building VIS, IWF-1300-1 IWF-3410 - CS-1 structure VT-3 _
1.30 Weld and mechanical connections _ VIS, IWF-1300-1 IWF-3410 CS-I - at intermediatejoints in VT-3 multiconnected integral and nonintegral suppons 1.40 Component displacement settings VIS, IWF-1300-1 IWF-3410 - CS-1 ofguides and stops, misalignment VT-3 ofsuppons, assembly ofsupport items 24X13 Rev.5 Page 6 of 9
[. ' ~
+
.3.2 - Examination Category F-B, Linear Type Suppons ALT. ERM
-TEM EXAM EXAM . REQUIRE / ACCEPTANC. ERELIEF .
O. ' PARTS TO BE EXAMINED METHOD METHOD FIG NO.- CRITERIA ~ REOUEST '
' 2.10 Mechanical connections to ' VIS, IWF-1300-1 IWF-3410 CS pressure retaining components VT-3 ;
and building structure , 2.20 Weld connections to building VIS, . IWF-1300-1 IWF-3410 CS-1 structure VT-3 2.30 Weld and mechanical connections VIS, IWF-1300-1 IWF-3410 CS-1 at intermediatejoints in VT-3 multiconnected integral and nonintegral suppons , 2.40 Component displacement settings VIS, IWF-1300-1 IWF-3410 CS-1 of guides and stops, misalignment VT-3 of supports, assembly of suppon items 2-003 Rev.5 Page 7 of 9 ,
+
a
'1
.3.3 - Examination Category F-C, Component Standard Supports ALT. EXAM
.. TEM EXAM ' EXAM REQUIRE / ' ACCEPTANC- ERELIEF O. PARTS TO BE EXAMINED METHOD METHOD- FIG NO.' CRITERIA REOUEST -
- 3.10 Mechanical connections to VIS, IWF-1300 IWF-3410 CS-1 pressure retaining components VT-3 .
and building structure . . 3.20 Weld connections to VIS, IWF-1300-1 IWF-3410 CS-1 building structure VT-3 3.30 Weld and mechancial connections VIS, IWF-1300-1 ' IWF-3410 CS-1 at intermediatejoints in VT-3 multiconnected integral and ; nonintegral supports 3.40 Component displacement settings VIS, IWF-1300-1 IWF-3410 CS-1 ofguides and stops, misalignment VT-3 of supports, assembly ofsupport items 3.50 Spring type supports, constant VIS, IWF-1300-1 IWF-3410 CS-1 load type supports, shock VT-3 absorbers, hydraulic and mechanical type snubbers 2-003 Rev.5 Page 8 of 9
3.4 COMPONENT SUPPORT RELIEF REQUESTS ReliefRequest Status Letter No. CS-1 Authorized 92-730 (11/5/92) l l i l i l N2@3 Rn6 Page 9 of 9
4 4 ; 4 RELIEF REOUEST NO. CS-1 1 I. IDENTIFICATION OF COMPONENTS ISI Class 1,2 and 3 Component Supports II. IMPRACTICAL CODE REQUIREMENTS The nonexistent or unclear portions of Subsection IWF, Section XI 1986 Ediuon detailed in the BASIS FOR RELIEF section of this relief request. III. BASIS FOR RELIEF ; Subsection IWF of the 1986 Edition of Section XI lacks a complete concise set of
- rules for the inservice inspection of component supports. The following areas in l particular have been identified as needing clarification-SUPPORTS EXEMPT FROM EXAMINATION AND TEST
[ l IWF-1230 in the 1986 Edition of Section XI is "in the course of preparation". The
- Section XI Working Group on Component Supports (WGCS) has developed proposed l
4 Code Case WGCS 89-1(b) which includes a complete set of exemptions in Section l 1230.
~ SUPPORTS SELECTED FOR EXAMINATION IWF-2510(a) in the 1986 Edition of Section XI states: " Component supports selected for examination shall be the supports of those components that are required to be i 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 i 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.
l SAMPLING PROGRAM The general philosophy of Section XI has evolved into a sampling program approach where a percentage oflike components are examined to determine their suitability for continued service. WGCS 89-1(b) includes in Table 2500-1 a specific sampling t program for supports. A Page 1 of 3 i
RELIEF REOUEST NO. CS-1 CONTINUED It is Virginia Electric and Power Company's position that the portions of WGCS-89-1(b) presented in the Alternate Provisions section of this relief request in conjunction with Subsection IWF of the 1986 Edition of Section XI provide a complete, coherent and sound set of rules for the inservice inspection of component supports. IV. ALTERNATE PROVISIONS In place ofIWF-1230, which is under development, the following will be used: Component supports exempt from the examination requirements ofIWF-2000 are those 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 encased in concrete, buried underground, or encapsulated by guard pipe are also exempt from the examination requirements ofIWF-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 l under IWB-2500, IWC-2500, and IWD-2500 by volumetric, surface or visual (VT-1 l 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. 1 In conjunction with Table IWF-2500-1, Categories F-A, F-B and F-C the following l sampling plan will be used; j l ISI Class 1 Piping Supports - Examine 25% of supports per interval. Notes 1,2 and 4. ISI Class 2 Piping Supports - Examine 15% of supports per interval. Notes 1,2 and 4. 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. l Page 2 of 3
RELIEF REOUEST 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; B = 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, Feedwater 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 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. V. STATUS Authorized - NRC Letter No. 92-730 Dated 11/5/92. Page 3 of 3 l I
d 4 2 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 ) J INTRIM RELIEF REQUESTS AND MISCELLANEOUS DOCUMENTATION SECOND INSPECTION INTERVAL 1 N2 m Rev. 5
~. .. - . . . -
SECTION 4 TABLE OF CONTENTS ^ i SECTION TITLE P_ gig 4.0 INSERVICE INSPECTION PROGRAM 1 MISCELLANEOUS INTERIM RELIEF REQUESTS AND DOCUMENTATION 4.1 INTERIM RELIEF REQUESTS 2 , 4.1.1 Letter 93-754 Approved Code Case N 524 (94-602 Dated 10-03-94) 4.1.2 Letter 94-008 Pending ! 4.1.3 Letter 94-319 Limited Approval l Code Case N-416-1 (95-41 Dated 1-18-95) 4.1.4 Letter 95-602 Withdrawn (95-602A Dated 6-10-96) 4.1.5 - Letter 97-552 Granted Code Case N-498-1 (NRC L',r. 98-007 Dated 12-29-97) 4.-1.6 Letter 98-176 Approved Code Case N-535 (NRC. Ltr. 98-340 Dated 5-29-98) 4.1.7 Letter 98 187 Approved g Letter 98-187A
- Relief for CRDM repair (NRC I/.r. 98-247 Dated 4-20-98) 1 4.2 MISCELLANEOUS DOCUMENTATION i (None at this time) l 6
l N2-004 Rev. 5 Paga 2 of 2
November,1998 Fo North Anna Power Station Unit 2, Interval 2 i t Summary of Changes To Plan Changes Are Noted In The Plan In The Revision Column i I Sorted By Drawing and Mark Number k i W_____. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -_ _ _ _____ _ _ _ _ -_< _ m _______ ____ __._,.__ _____ __ - ________ __.____.__.__.__.__.m. . ________ -_m_ _ . -_ _ __
Droidag No. Mort No. IJsse Number Caeegory' leene No. Immelen Receed Period Meeland 11715-CBM-078A-2 Sil 4 SW IJNES TO CIII11ERS . 19 NA 6673 I VT-2 ; Comesments' RESCIIEDULE AFTER COMPLETION. AfUST BE DONE ONCE EVERY 18 MONTilS + ll78%WMKS-0105A 2-WS-R-6 1r-WS-510-151-Q3 F-B F2.0 AB I. 3 VT-3 : Commernes - ~A11 ARES. New with Rev. II to the plan: Scheduled in Period 3 due to reevaluation of the Class 3 total support population. 4 Il71%WMKS-0105A 2-WS-R4A 18*-WS-510-151-Q3 F-B F2.0 , AB' 2 3 VT Comennenes ' A 1IARES. New with Rev. II to the plan: Scheduled in Period 3 due to reevaluation of the Class 3 total support population. Il715-WMKS-0105A 40J 18'-WS-510-151-Q3 D-A DI.20 AUX 244 3 .I \T-3 i . Comuments R-6 NOT SELECTED. CilANGED ITEM hMtBER TO AGREE uTTII PRESSURE TESTING PROGRAM IN REV 8. 4 i il71%WMKS-0105AMA !!M 18'-WS-D.80-151-Q3 D-A DI.20 SW POUND 7648 0 VT-3 Comennents Pil-900 i NOT SELECTED. CIIANGED ITEM hMiBER TO AGREE WITil PRESSURE TESTING PROGRAM IN REV. 8. l I!7tSWMKS-0105AMA 12M t r-WS-D-81-15143 D-A DI.20 SW POUND 4 I VF-3
. Comennents Pll-9002 NOT SEIICTED. CIIANGED ITEh! NUMBER TO AGREE WITII PRESSURE TFSTING PROGRAM IN REV. 8.
Il71SWMKS-Ol05AMA 25M 2f-WS-D-78-151-Q3 D-A DI.20 SW POUND 7 1 \T-3 Comuments Pil-9048 NOT SELECTED. CilANGED ITEM NMIBER TO AGREE WITII PRESSURE TESTING PROGRAM IN REV. 8. [ ll715-WMKS-0105AMA 26M 2f-WS-D-78-151-Q3 D-A DI .20 SW POUND 8 I VT-3 C -.:. Pil-9048 NOT SELECTED. CllANGED ITEM NUMBER TO AGREE WITil PRESSURE TESTING PROGRAM IN REV. 8. t il7tSWMKS-0105AMA 39M 24' WS-D-78-151-Q3 D-A ' DI.20 SW POUND 16 I VT-3 , Comuments CI!ANGED h1 ARK NUMBER FROM ? TO 39hl IN REV. 6. Pil-9037 NOT SELECTED. CIIANGED ITEM NMiBER TO AGREE WITil PRESSURETESTING PROGRAM IN REY. 8. I1715-WhiKS-0105AMA PII-9001 18'-WS-D-80-15 l-Q3 F-A FI O 7645 0 VF3 { s C-- A SUPPORTilAANC MOVED TO UNIT 2 F10 Il715-WMKS-0105AMA PII-9002 18'-WS-D-81-151-Q3 F-A 7646 0: VT-3 C. . :_ SUPPORT HAANC MOVED TO UNIT 2 7 Il71%WMKS-0105 AMA Plf-9009 18*-WS-D-80-151-Q3 F-B F2 0 7644 0- VT-3 [ C :. SUPPORTliARES MOVED TO UNIT 2
!!7tSWMKS-0105AMA PII-9010 18*-WS-D-81-151-Q3 F-B F2.0 7643 0 VT-3 .[
C _ SUPPORT HARES MOVED TO UNIT 2 , I1715-WMKS-0105AMA Pff-9017 I8'-WS-D-81-151-Q3 F-B F2.0 7654 'O \T-3 l Casaments SUPPORT IIARES. EXPANDED GANG SUPPORT IN REV 7 TO INCLUDE EACil llNE. ;
.L i
W of Changes Sorted by Druedag sad Mark Na, NAPSU22 Database Page f of 146 PnntDate: I#1898 j i
Drawing No- Alset No- IJne Numtwr Caeegory teens Ne- lewstion Record Perled Method . Il785-WMKS-Ol05AMA Pit-9087 18'-WS-D-80-151-Q3 F-B F2.0 - 7653. 0 \T-3 Ceaunents SUPPORT llARES. EXPANDED GANG SUPPORT IN REY. 7 TO INCLUDE EACII LINE.
~~
Il715-WhfKS-0105 AMA Pil-9018 18*-WS-D-80-151-Q3 F-B F2.0 .7652 6 \T-3 Comuments SUPPORT llAGUD2. EXPANDED GANG SUPPORT IN REV.7 TO INCLUDE EACll llNE. Il719-WMKS-0105AMA Pil-9037 2f WS-D-78-151-Q3 F-A Fl .0 7642 3 \T-3 C a:s SUPPORT IIAANC MOVED TO UNIT 2. New with Rev. II to the plan: Scheduled in Period 3 due to reevaluation of the Class 3 total support population. ' il715-WMKS-Ol05AMA Pil-9038 18*-WS-D-80-151-Q3 F-B F2.0 7650 0 Ceaunents SUPPORT IIARES. ADDED IN REV. 8 EXPANDED GANG SUPPORT TO INCLUDE EACil PIPE. I!719-WhfKS-0105AMA PII-9038 18'-WS-D-81-151-Q3 F-B F2.0 7658 0 Comuments SUPPORT liARES. ADDED IN REV. 8 EXPANDED GANG SUPPORT TO INCLUDE EACl! PIPE. Il719-WMKS-Ol05AMA Pil-9048 2f-WS-D-78-151-Q3 F-B F2.0 7727 0 Comunents ll715-WMKS-0105AMB IIM 24*-WS-D-85-151-Q3 D-A DI.20 SW POUND 18 2 VT-3 Comunents PII-9047 NOT SELECTED, CIIANGED ITEM NUMHER TO AGREE WITII PRESSURE TESTING PROGRAM IN REV. 8. Il719-WMKS-010$ AMB 12M 2f-WS-D-85-151-Q3 D-A DI .20 SW POUND 19 2 VT-3 Comunents PII-9047 NOT SELECTED. CilANGED ITEM NMtBER TO AGREE WITil PRESSURE TESTING PROGRAM IN REV. 8. Il715-WMKS-0105AMD lit 18*-WS-D-93-151-Q3 D-A DI.20 SW POUND 20 2 VT-3 Comuments Plf-9008 NOT Sell.CTED. CIIANGED ITEM NUMBER TO AGREE WITII PRESSURE TESTING PROGRAM IN REV. 8. Il715 WMKS-0105AMB 25M 2f-WS-D-85-151-Q3 D-A DI.20 SW POUND 28 2 \T-3 Conunents CilANGED MARK hufBER FROM 7 TO 25M IN REV. 6. Pil-9036 NOT SELECTED. CIIANGED ITEM NUMBER TO AGREE WITII PRESSURE TESTING PROGRAM IN REV. 8. I1715-WMKS-0105AMB 211 18'-WS-D-94-151-Q3 D-A DI.20 7525 0-Comnr=nts PII-9007 NOT SELECTED. CIIANGED ITEM NUMBER TO AGREE WITII PRESSURE TESTING PROGRAM IN REV. 8. Il715-WMKS-0105 AMB 3M 24'-WS-D-85-151-Q3 D-A DI.20 SW POUND 21 2 VT-3 Comuments PII-9032 NOT SELECTED. CllANGED ITEM NUMBER TO AGREE WITil PRESSURE TESTING PROGRAM IN REV. 8. II715-WMKS-0105AMB 4M 2f-WS-D-85-151-Q3 D-A DI.20 SW POUND 22 2 \T-3 C. a:2 PII-9032 NOT SELECTED. CIIANGED ITEM NUhtBER TO AGREE WITII PRESSURE TESTING PROGRAM IN REV. 8. Il715-WMKS-0105AMB SM 24'-WS-D-85-151-Q3 D-A DI.20 SW POUND 23 2 VT-3 C a:a Pit-9032 NOT SELECTED. CIIANGED ITEM NUMBER TO AGREE WITII PRESSURE TESTING PROGRAM IN REV. 8. Sununary of Cluunges Sorted by Draning and Mark No, NAPSU22 Database Page 2of146 Pnnt Date: 11/18 93
m _ - _. . _. m.~ . . - . . . - . . . . . _ _ . . . . .- i 4 h
._ --- _rnur :--
MS No . Merk No. . I.ine Numtwr u .. ry iten No. ' laation Record Pes %I . IV.+ ed . ,
- Il715-WhtrS-0105AktB 6ht 2f-WS-D-85151-Q3 IE ~~ DI 20 SW POUND 24 2 VT-3
~ comunieges Fil-9032 NOT SELECTED. CIIANGED ITEht NUhtBER TO AGREE WITil PRI3St'RE TESTING PROGRAh! IN REY. 8.
! I1715-WhtKS-0105AhtB 7ht 2f-WS-D-85 151-Q3 D-A DI.20 Skt POUND 25 2 VT-3 Canisments Pil-9032 NOT SELECTED. CIIANGED ITEh! NUhf BER TO AGREE WITil PRESSURE TESTING PROGRAh! IN REV. 8.
- - Il7tSWhlKS-0105AhlB Mhf 2f-WS-D-85-151-Q3 D-A DI.20 SW POUND 26 -- 2 VT-3 !
Ceniments Pil-9032 NOT SELECTED. CIIANGED ITEh! NUhtBER TO AGREE WI f11 PRESSURE TESTING PROGRAh! IN REV. 8. Il115-WhtKS-0105 AhtB 9ht 2f-WS-D-85-151-Q1 D-A DI.20 : SWPoudD 27 2 VT-3 Con swats Pil-9032 NOT SEIICTED. CIIANGED ITEkt NUhlBER TO AGREE WITII PRESMJRE TEST 1NG PROGRAh! IN REV. F. < ll715-WhlKS-0105Ah!B Pii-9007 18'-WS-D-94-151-Q3 FA F1.0 7526 0 C- . I!715-WhtKS-0105 AhtB PII-9008 18"-WS-D-93-151-Q3 F-A Fl.0 7527 0 VT 1 Ceaunents 4 Il715-WhtKS-0105AhtB Pil-9015 18'-WS-D-94-151-Q3 F-H F2.0 75'8 0
-C. t Il715-WhtKS-010$AhtB PII-9016 IT-WS-D-93-151-Q3 F-B F2.0 7529 0 . NT-3 C - 3 Il715-WhtKS-0105AhfB PH-9032 2f-WS-D-85-151-Q3 F-A Fl .0 7530 0 VT-3 O. _ ;
ll715-WhtXS-0105AhtB I'll-9036 24* WS-D-85-151-Q3 F-A Fl.0 7531 0 \T-3 C ; ll71SWhtKS-0105AktB PII-9047 2f-WS-D-85-151-Q3 F-B F2.0 7532 .0 \T-3 , C - Il71SWh!KS4105B 191I I T-WS-500-131.Q3 D-A DI.20 AUX 244 29 2 VT-3 e C -3 R-12 NOT SELECTED CIIANGED ITEh! NUitBER TO AGREE WITil PRESSURE TESTING PROGRAhlIN REV. 8. Il7t SWh!KS-0105B 2-WS-R-12 t r-%T,-500-151-Q3 F-B F2.0 AB 30 3 \T-3 i Canuments A11 ARES. New with Rev.1 I to the plan Schefuled in Period 3 due to reevaluation ofthe Class 3 total support population. I1715 Wh!KS-0105B 2.WS-R-202 I F-WS-500-15 I-Q3 F-C F3.0 3I 3 VT-3 Comuments AllARES. New with Rev 1I to the plan: Scheduled in Period 3 due to reevaluation of the Class 3 total support population. i L y of LW Sorted by Drewhig and Mark No, NAPSU22 Database Page 3 of 146 PnnrDare: 11/1898 s._ _ . _ _ _m _ _ - _ _ _ _ _ _ _ _ - __. _ -- r _ ..r m - _ -- 4-. ~ __ _ - _ - _ _ __ .
.. u _. . .m_. . - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
r
= = = = .- -. = .
i Drawing No. - Mark No. IJne Naniher Category Itein No. Iscation ' Record Period Metised *
"Il715-WMKS-0105C 3611 20'-WS-405-151-Q3 D-A . DI.20 SWrli 40 - O- VT-3 0 ,n CIIANGED FROM PFRIOD 2 TO PERIOD 0 IN REV.7. RELIEF REQUEST NDE-21 allow USE OF CODE CASE N-509 TO EXAMINE 10%CFTIIE INTEGRAL AlTACHMENTS. A-25 NOT SELECTED, CliANGED ITEAR NUMBER TO AGREE WITit PRESSURE TESTING PROGRAM IN REY.8.
Il785-WMKS-0105C 3 71I 20-WS-407-151-Q3 D-A DI .20 SWPli 41. O VT-3 Comunents CllANGED FROM PERIOD 2 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 TO EXAMINE 10% OF Tile INTEGRAL ATTACIIMENTS. A-23 NOT SELirTED. CIIANGE9 ITEM NUMBER TO AGREE WITII PRESSURE TESTING PROGRAM IN REV. 8. Il7I5-WMKS-0105R 31]I 24'-WS-425-151-Q3 D-B D2.20 IS 7647 0-Comuments ADDED IN REV. 7 NOT PlcKED UP WITil ADDITION OF EXEMPT ATTACIIMENTS. IS SIf0WN ON A UNIT I DRAWING. CilANGED ITEM NL44V1 TO AGREE WITil 1 PRESSURE TESTING PROGRAM IN REV 8.
-Il71%WMKS-Oll8J Ill 18'-CC-401-151-Q3 D-A DI.40 AUX 244 44 0 VT-3 Comunents (S11-171 NOT SELECTED). CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REY. 7. RELIEF REQUEST NDE-21 ALIDW USE OF CODE CASE N-509 TO EXAMINE IC% OFTIIE -
INTEGRAL ATTACllMENTS CllANGED ITEM NUMBER TO AGREE WITit PRESSURE TESTING PROGRAM IN REV. 8. II715-WMKS-Cll8J - lit 18'-CC-402-151-Q3 D-A DI.40 AUX 244 45 0 . VT-3 C_ ;s (511-172 NOT SELECTED) CllANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 ALLOW USE OF CCDE CASE N-509 TO EXAMINE 10% OF Tite INTEGRAL ATTACIIMENT S. CII ANGEO ITEM NUMBER TO AGREE WITil PRESSURE TESTING PROGRAM IN REV. 8. Il7tSWMKS4tl8J 2-CC-A-272 30'-CC470-151-Q3 F-A FI O AB 47 0 C .cs B'IIAGUD2. CllANGED 10 AN EQUIPMENT SUPPORT WITII REV.1010 FIAN. SUPPORT WAS REPLACED IN PERIOD 3. NOT REQUIRED TO BE EXAMINED IN TIIE SAME . PERIOD AS REPLACEMENT. Il71%WMKS-Oll8J 2-CC-A-272 30'-CC472-151-Q3 F-A Fl.0 AB 48 0 C_ -O BilAGUD2. CIIANGED TO AN EQUIPMENT SUPPORT WITII REY.10 TO PLAN. SUPPORT WAS REPLACED IN PERIOD 3. NOT REQUIRED TO BE EXAMINED IN Tile SAME PERIOD AS REPLACEMENT. , ll715-WMKS-OlI8J 2-CC-R-175 18TC-402151-Q3 F-A Fl.0 AB 51 3 VT-3 Ceaunenes B11AGUD2. New with Rev. II to the plair Scfwduled in Period 3 due to reevaluation of the Class 3 total support population. Il715-WMKS-Oll8J 2-CC-R-259 30'-CC470-151-Q3 F-A Fl.0 AB 54 0 1 0 - ---c BilAGUD2. CIIANGED TO AN EQUIPMENT SUPPORT WITII REV.10 TO PLAN. SUPPORT WAS REPLACED IN PERIOD 3. NOT REQUIRED TO BE EXAMINED IN TIIE SAME ' I PERIOD AS REPIACEMENT. II715-WMKS-Oll8J 2-CC-R-259 30'-CC472-151-Q3 F-A Fl.0 AE 55 0 C .4. BilAGUD2. CIIANGED TO AN EQUIPMENT SUPPORT WIT 11 REV.10 TO PLAN. SUPPORT WAS REPLACED IN PERIOD 3. NOT REQUIRED TO BE E! . MINED IN TIIE SAME PERJOD AS REPLACEMENT. I1715-WMKS-OllEJ NCC-R-291 30'-CC470-15 I-Q3 F-A FI.0 AB 56 0 Comuments BHAGUD2. CIIANGED TO AN EQUIPMENT SUPPORT WITil REY.10 TO PIAN. SUPPORT WAS REPIACED IN PERIOD 3. NOT REQUIRED TO BE EXAMINED IN TIIE SAME j PERIOD AS REPLACEM!' ;T. Il715-WMKS-Oll8J 2-CC-R-291 30'-CC472-151-Q3 F-A FI O AB 57 0 l Cenimients B11AGUD2. CIIANGED TO AN EQUIPMENT SUPPORT WITil REV.10 TO PIAN. SUPPORT WAS REPLACED IN PERIOD 3. NOT REQUIRED TO BE EXAMINED IN TIIE SAME f PERIOD AS REPIACEMENT. k @ N .
, . - 4,-.., . . - . , , _ . , m_ _ .___.___.x_______ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _
Drning No. Stark No. I ine Number Category item No. tocation Recerd Pes %I Stethod il71SWhtKS f 1, 2-CC-Sil-171 18*-CC-401-151-Q3 F-C F3 0 AD 58 3 VT-3 Cenunents C 11 KVAR New with Rev.1I to the plan Scheduled in Period 3 due to reevaluation of the Clan 3 total support population.
~
Il715-WhtKS-011FI 211 18'-CC-61 %I 51-Q3 D-A filT AUX 244 46 0 VT-3 Conunents (S11-177 NOT SELECTED). CilANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQLTST NDE-21 ALLOW USE OF CODE CASE N-509 TO EX AhIINE 10*6 OF TIIE INTI GRAL ATTACIIKIENTS CllANGED ITDI NUhtBER TO AGREE WITil PRESSURE TESTING PROGR 91 IN REV. 8.
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Il71%WitKS4118J 311 18'-CC 402-151-Q) D-A D120 AUX 244 63 0 VT-3 Ceaunents (R 175 NOT SELECTED). CIIANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 TO EXAhtINE 10*& OF TIIE INT EGRAL AlTACllitENTS. Cl!ANGFD 11 B1 NUstBER TO AGREE WITit PRESFURE TESTING PROGRAh! IN REV. 8. Il715-WhtKS4118J 311 18'-CC-614-151-Q3 D-A D L20 AUX 244 64 0 KT-3 Comments (R-177A NOT SELECTTD) CllANGED FROK1 PERIOD 3 TO I'ERIOD 0 IN REY. 7. RI LIEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 TO EXAh!!NE 10*6 OF TIIE INTEGRAL AlTACithtENTS. CIIANGED ITDI NUh1BER TO AGREE WITil PRESSURE TESTING PROGRAh!IN REV. 8. Il715WitKS-Oll8J WS-I 2-CC-E-2A D-A DI.10 AUX 244 65 0 VT-3 C. ..ts (R-259 NOT SELECTED). CilANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 TO ELutINE 10*6 OF TIIE INTEGRAL ATTACI!K!ENTS. CIIANGED FROh! PERIOD 0 TO PERIOD 3 IN REV. 8. FOOTNOT E 3 OF CODE CASE N-509 REQUIRES ALL TIIE ATTACllh!ENTS OF ONE VESSEL TO BE EXAhtINED. CIIANGED ITEh! NUhtBER TO AGREE WITII PRESSURE TESTING PROGR Ah! IN REV. 8. WITII REV.10 TO PLAN: CilANGED FROh! PERIOD 3 TO PERIOD 0. HEAT EXC11 ANGER AND INTEGRAL ATTACItilENT WERE REPLACED IN 1997. INSERK ICE INSPECTION IS NOT REQUIRED IN TIIE PERIOD OF REPLACEktENT. Il715 WhtKS-Oll83 WS-I 2-CC-E-211 D-A DI .10 AUX 244 66 0 KT-3 Comments (R-259 NOI SELECTED) CilANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 allow USE OF CODE CASE N-509 TO EXAstINE !O*4 OF TIIE INTEGRAL ATTACilh!ENTS. CIIANGED ITEh! NUNIBER TO AGREE WITil PRESSURE TESTING PROGRAh! IN REV. 8. II715-WhU $ % 181 WS-2 2-CC-E-2A D-A D1.10 AUX 244 67 0 VT-3 Comments (A-272 NOT SELECTED). CilANGED FROKI PERIOD 3 TO PERIOD 0 IN REY. 7. RELIEF REQUEST NDE-21 ALIDW USE OF CODE CASE N-509 TO EXAht!NE 10*iOF TIIE INTEGRAL ATTACithtENTS CitANGED FROh! PERIOD 0 TO PERIOD 3 IN REV. 8. FOOTNOTE 3 OF CODE CASE N-509 RFQUIRES ALLTIIE ATTACllhtENTS OF ONE VESSEI.TO BE ELutINED. Cll ANGED ITEh! NUh!BER TO AGREE WITil PRESSURE TESTING PROGRAh! IN REV. 8. Cll ANGED FROh! PERIOD 3 TO PERIOD 0 WITII REV.10 TO PLAN. IIEAT EXCIIANGER AND INTERGRAL ATTACllhtENT WERE REPLACED IN 1997. NO INSERVICE INSPECTION IS REQUIRED IN TIIE PERIOD OF REPIACEhtENT. I171SWh1KS-Oll81 WS-2 2-CC-E-2B D-A DI.10 AUX 244 68 0 VT-3 Comments (A-272 NOT SELECTED). CIIANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 allow USE OF CODE CASE N-509 TO ELu!INE 10*4 OF TIIL INTEGRAL ATTACllh!ENTS. CllANGED ITBI NUhtBER TO AGREE WITil PRESSURE TESTING PROGRAh!IN REV. 8. 1871SWhtKS-Oll8J WS-3 2-CC-E-2A D-A DI.10 AUX 244 69 0 KT-3 C. r-.a (R-291 NOT SELECTED). CIIANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 ALIDW USE OF CODE CASE N-509 TO EXAh!INE 10*.0F TIIE INTEGRAL ATTACItilENTS, Cll ANGED FROh! PERIOD 0 TO PERIOD 3 IN REY. 8. FOOTNOTE 3 OF CODE CASE N-509 REQUIRES ALL TIIE ATTACithtENTS OF ONE VESSEL TO BE EXAhtINED. CllANGED ITB! NUhtBER TO AGREE WITil i RESSURE TESTWG PROGRAh!IN REV. 8. CIIANGED FRO:I PERIOD 3 TO PERIOD 2 WITII REV.10 TO PLAN ItEAT EXCIIANGER AND INTEGRAL ATTACithtENT WERE REPLACED IN 1997. NO INSERVICE INSPECTION IS REQL7 RED DURING PERIOD OF REPLACEhtENT. Il7thWhtKS-OlI8J WS-3 2-CC-E-2B LKA DI.10 AUX 244 70 0 VT-3 Comments (R-291 NOT SELECTED). CIIANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 A11DW USE OF CODE CASE N-509 TO ELut!NE 10*sOF TIIE INTEGRAL ATTACithtENTS. CilANGED ITDI NUhtBER TO AGREE %TTil PRESSURE TESTING PROGRAh! IN REV. 8. Il715-WhtKS-Oll8K-2 2-CC-R-18 24'-CC-405-151-Q3 F-A F10 AUX 244 73 3 VT-3 Cenenents BilAGUD3 Summary eK1: antes Sorted by Drawing and 31 art No., NAPSU22 Database Page 5of 146 Prmt Dare. 1//la93 - - _ _ - .- _- - ~ . _ _ _ . -- _ _ _ _ _ . . _ _ _ _ _ _ _ _
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in8 New Mark Lhie Nuniber Caterary Iteen No. - Location Recaril - Pested Meelied It'71%WhtKS-OlisK-2 ! 2-CC-R-19 . 25-CC-405-151-Q3 F-Il F2.0 AUX 244 74 3 VT-3 Comunients A11 ARES Il71%WklKS-Oll8K-2 2 CC-s-20 24'-CC405-151-Q3 F-Il F2.0 AUX 244 75 3 VT-3 Comuments AllARES t l71%WhtKS-Cll8K-2 3 611 24'-CC-405-151-Q3 D-A DI.20 AtrX 244 78 0 VT-3 '; Comineents (R 18 NOT SELECTED). CilANGED FROh! PERIOD 3 TO PERIOD 0 IN REV /. REUEF REQUEST NDE-21 ALLOW USE OF CODE CASF N-509 TO EXAht!NE 10% OF TIIE INTEGRAL ATTACitktENTS. CIIANGED ITEh! NUhtBER TO AGREE WITII PRESSURE TESTING PROGRAh! IN REV. 8. Il715 WhtKS-Oll8K-2 R-15 18'-CC.21-151-Q3 F-B F2 0 '7649 0 KT-3 Comunients SLTPORT IIARES. Af0VFD FROh! Tile UNIT I DATABASE TO TIIE UNIT 2 DATABASE. UNIT BREAK ON Whf KS DID NOT AGREE WITil CBht. DUR SUBhtITTED. REV. 7 . .11715-WhtKS-Cll8N-3 1611 24'-CC-417-151-Q3 D-A DI.20 AUX 244 85 0 VT-3 Comuments (R-23 NOT SELEC1TD). CII ANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 7. REUEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 TO EXAhi!NE 10% OF TIIE INTEGRAL ATFACithf ENTS. CIIANGED ITEh! NUhlBER TO AGREE WITil PRESSURE TESTING PROGRAh! IN REY. 8. Il71%WhtKS-Oll8N-3 1711 24*-CC417-151-Q3 D-A DI.20 AtrX 244 86 0 TT-3 C ./s (R-23 NOT SELECTED) CII ANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 7. REUEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 TO EXAhtINE 10% OF TIIE INTEGRAL ATTACithtENTS. CitANGED ITEh! NUh!BER TO AGREE WITil PRESSURE TESTING PROGRAhl IN REY. 8. Il715-WitKS-Oll RN-3 25J 18'-CC419-151-Q3 D-A DI 40 AUX 244 87 0 KT-3 ; Comunents (511-1ii ??OT SELECTED) CIIANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 7. REUEF REQUEST NDE-21 AI LOW USE OF CODE CASE N-509 TU EXAhlINE 10% OF TIIE INTEGRAL ATTACIthf ENTS. CilANGED ITEh! NUhtBER TO AGREE WITII PRESSUR.E TESTING PROGRAh! IN REV. 8. l ^ 1871 %WhNS-Ol l8N-3 263 18'-CC-420-151-Q3 D-A DI.40 AUX 244 88 0 VT-3 Coinsments 61I-I12 NOT SELECTED). CllANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 7. REUEF REQUEST NDE-21 allow USE OF CODE CASE N-509 TO EXAhflNE 10% OF T11E INTEGRAL ATTAcilhtENTS. CllANGED ITEh! NUhtBER TO AGREE WITII I-RESSURE TESTING PROGRAh!IN REV.1 Il715-WhtKS-OllbN-? 23 24'-CC417-151-Q3 D-A DI.40 AUX 244 89' 0 VT-3 C_ 3 gSil-112 NOT SELECTED). CIIANGED FROh! PERIOD 3 TO PERIOD 0 IN REV.7. RELIEF REQUEST NDE-21 ALIJ0W USE OF CODE CASE N-509 TO EXAht!NE 10% OF TIIE INTEGRAL ATTACith!ENTS. CIIANGED ITEht NUh!BER TO AGREE %TTIl PRESSURE TESTING PROGRAM IN REV. 8. j II71%WhtKS4118N-3 911 24'-CC-417-151-Q3 D-A DI.30 AUX 244 98 0 KT-3 , I C- .3 (115S-400 NOT SELECTED). CIIANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 AllJOW USE OF CODE CASE N-509 TO EXAMINE 10% OF TIIE INTEGRAL ATTACilh!ENTS. CilANGED ITEh! NUhtBER TO AGREE WITil PRESSURE TESTING PROGRAM IN REV. 8. i il73 %WhtKS-RC-P-I AI l-RC-P-I A Af0 TOR SERIAL # IS-8IP355 I RC A-CUBE 7691 1 tJT C -. IJT IN PLACE AT APPROXIhfATELY 3 YEAR INTERVAIA IS-dlP355(tJTC 5900004373) I-PT4410.1. NAPS T.S. 4.4.10.1.1 REO. GUIDE 1.14 REV I,8-75,10 YEAR DONE 547. { Ef0 TOR WAS REhf0VED IN 91 AND K10VED TO SPARE SPARE WAS LATER INSTALLED IN UNIT 2 A. FUIURE EXAhlINATIONS WILL BE TRACKED IN TIIE UNIT 2 DATA l BASE. 3S-8 t P355(LTFC 5900004377) WAS INSTAI I Fn IN UNIT I A WO108378. I171%WhtKS-RC-P-1 A1 1-RC-P-1 A Kf0 TOR SERIAL # 3S-8IP355 1 7716 I ITT t C. .3 UT IN PLACE AT APPROXIhtATELY 3 YL'.R INTERVALS, MOTOR SERIAL # 3S-81P355 (UTC 5900004377),flYWIIEEL SER. #15-81P355 l-PT-44.10.I, NAPS T.S. 4.410.1.1 REG. Gl'IDE I 14 REV 1,8-75. htOTOR WAS INSTALLED IN UNIT 2C AND WAS AtOVED TO SPARE UNDER WO10590710S0. htOT"R WAS INSTALU:D IN UNIT I A IN 2SI UNDER WO 108378. LAST 10 YEAR DONE IN 336 WIIEN IT WAS IN UNFT 2 C. , b Seminsary of Otantes Sorted by Urmwin8 and Mark No., NAPSU22 Database Page 6 of 146 Femt Date: 1//18 93 ~
_ . - - ; =-- - - _ _ .DrawintNo. hlark No. Line Number Category item No- Location Record Period hiethod e l715 WhlKS-RC-P-I A I l-RC-P-I A klOTOR SERIAL a 3S-81P355 I A-CUBE 7693 2 UT Comments LAST EXAh! PERFORh!ED 1/27/91,ITT IN PLACE AT APPROXIhl ATELY 3 YEAR INTERVAIS. SIOTOR SERIAL # 3S-81P355 (tTTC 5900004377)JLYWIIEEL SER. *IS-8tP355 I-PT. 44.10.1. N APS T.S. 4.4 10.1.1 REO. GUIDE I.14 REY 1. 8 75. KIOTOR WAS INSTALLED IN t'N!T 2C AND WAS k!OVED TO SPARE UNDER WO t0590710.90. MOTOR WAS INSTAI. LED IN UNIT I A IN 2.91 UNDER WO 108378. LAST 10 YEAR DONE IN 3-86 WIIEN IT WAS IN UNIT 2 C. I l719-Wht KS E-P-I D. I I-RC-P ID hlOTOR SERIAL # 35-81P777 i B-CUBE 7694 i PTiUr Comments 1AST 3 AND to YEAR EXAh! PERFORhtED 191 IN UNIT I B UNDER WOIO8583. IT WAS REhtOVED IN I/93 UNDER WO 152237 IT WAS SIIIPPED TO WESTINGIIOUSE ON 4.93 UNDER WO 16n690 AND TIIEN INSTALLED IN UNIT 2 C BY WO OC26158. ELut!NADON WILL IIE TRACKED UNDER TIIE UNIT 2 DATA BASE. ITT IN PLACE AT APPROX 1hlATELY 3 YEAR INTERVALS. 35-81P777(t,7C 5900004375),1-PT-44.10.1. NAPS T.S. 4.4.10.l.1 REG. GUIDE I.14 REV l. Il715-WhlKS-RC-P IC.I I-RC-P-IC htOTOR SERI AL # IS-85P398 1 C-CUBE 7695 1 LTr C_ . :.:, trT IN PLACE AT APPROXIhtATELY 3 YEAR INTERVAL.S. IS-85P398,1-PT-44.101 NAPS T.S. 4.4.10.I.1 REG. GUIDE I.14 REV t,8-75 WO I 34634 VERFIES SERIAL NUhtBER.
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12050-CBht-093 A SIIT I LINE TO 2-RC-193 14 A-LOOP 101 1 PT Comments REhtOVED IN Tile 1993 OUTAGE. No LONGER REQUIRED IO BE ELu!INED. I2050-CBht493A StIT I LINE TO 2-RC.194 14 A-Imp 7702 3 PT Comments TYPE 1, NP-2700, RECOhthtENDS INSPECTIONS CONTINUE, INSPECTION FREQUENCY TO BE DETERA!!NED BY TIIE STATION. EXAhtINATIONS WILL BE SCIIEDUED EVERY OLTAGE UNTIL A DESCISION IS AIADE BY TIIE STATION. 12050-CBht-093 A SIIT I LINE TO 2-RC-194 14 NA A-Loop 7701 3 PT Comments TITE I, NP-2700, RECOhth! ENDS INSPECTIONS CONTINUE, INSPECTION FREQUENCY TO BE DETERAIINED BY TIIE STATION. EXAh!! NATIONS WIII DE SCIIEDUED EVERY OLTTAGE t'NTIL A DESCISION IS htADE BY T!!E STATION 12050.CBhl493A SIIT I LINE TO 2-RC-195 14 A-Imp 7703 3 PT Comments TYPE 1 NP-2700, RECOkthtENDS INSPECTIONS CONTINUE, INSPECTION FREQUENCY TO BE DETERh!!NED BY TIIE STATION. EXAhtINATIONS WillBE SCIIEDULED EVERY OLTTAGE UNTIL A DESCISION IS h!ADE BY DIE STATION. 12090-CBht493A SIIT I LINE TO 2-RC-195 14 NA A-Imp 7700 3 PT Comments TTTE 1. NP-2700, RECOkth1 ENDS INSPECTIONS CONTIN 1.*E, INSPECTION FREQUENCY TO BE DETERh!!NED BY TIIE STATION. EXAktINATIONS Will BE SCIIEDULED EVERY OLTTAGE UNTIL A DESCISION IS hlADE BY TIIE STATION. 5% CBht-093A SIIT I LINE TO 2-RC-196 14 A-LDOP 108 i PT Comments REktOVED IN TIIE 1993 OLTTAGE. NO LONGER REQUIRED TO BE ELutINED. 12050< Bht-093 A SIIT 2 LINE TO 2-RC-197 I4 B-LOOP I10 i PT Comments REhtOVED IN TIIE 1993 OITTAGE. NO LONGER REQUIRED TO BE EXAh!INED. I2050-CBht493 A SIIT 2 LINE TO 2-RC-198 14 B-Imp 7704 3 PT Comments TYPE 1,NP-2700 RECOkthtENDS INSPECTIONS CONTINUE, INSPECTION FREQUENCY TO BE DETERhtINED BY TIIE STATION. EXAhtINATIONS WILL BE SCIIEDULED EVERY OtJTAGE UNTIL A DESCISION IS ktADE BY TIIE STATION. 12050-CBht-093 A SIIT 2 LINE TO 2-RC-198 14 NA B-tmp 7699 3 PT Comments TTTE I, NP-2700 RECOkthtENDS INSPECTIONS CONTINUE, INSPECTION iREQUENCY TO DE DETERh!!NED BY DIE STATION EXAAtINATIONS WILL BE SCllEDULED EVERY OUTAGE l'NTIL A DESCISION IS 51ADE BY TIIE STATION.
%sumary of Otanges Sorted by Drawing and Mark No NAPSU22 Database Page 7of 146 Prmt Date- 11/1898
Denning Na, Mark No. IJne Number Category Item No. I ocarian Recoril Period Method I20$0-CUA1493 A SIIT 2 UNETO RC-199 I4 B-leop 7705 3 FT Comments TYPE I, NP-2700, RECOhlhlENDS INSPECTIONS CONTINUE INSPI CTION FREQUENCY TO BE DETERkIINED BY TIIE STATION. EXAhflNATIONS WILL BE ScilEDUIID EVERY OLTTAOE ONTIL A DESCISION IS klADE BY Tile STATION. 12090CBhl493 A SIIT 2 LINE TO 2-RC-199 14 NA B-loop 7710 3 PT Cornments TYPE I. NP-2700, RECOMkiENDS INSPECTIONS CONTINUE INSPECrlON TREQUENCY TO BE DETERhllNED BY TIIE STATION. EXAht! NATIONS WILL BE SCliEDULED EVERY OUTAGE UN ;L A DESCISION IS hlADE BY TIIE STATION. 12050-CUhl493 A SitT 2 UNE TO 2-RC-200 14 B-lJ)OP 115 I PT Comments REhlOVED IN TiiE 1993 OtrTAGE. NO LONGER REQUIRED TO BE EXAhflNED. 12090.CBhl493 A SIIT 3 LINE TO 2-RC-201 14 C-II)OP 117 I PT Comments REhlOVED IN Tile 1993 01TrAGE. NO LONGER REQUIRED TO BE EXAh11NED. 12050-CBM.093 A Slit 3 IINE TO 2-RC-202 14 C-loop 7706 3 PT Comments TYPE I, NP-270G,8ECOhlMENDS INSPECTIONS CONTINUE, INSPECTION FREQUENCY TO BE DETERhtlNED BY TIIE STATION. EXAhtINATIONS WILL BE SCIIEDULED EVERY OUTAGE UNTIL A DESCISION 15 hlADE BY T!!E STATION. 12050-CBit-093 A SitT 3 UNE TO 2-RC-202 14 NA C-loop 7709 3 PT C. - -.:s TYPE I. NP-2700, RECOMhlENDS INSPECTIONS CONTINUE, INSPECTION FREQUENCY TO BE DETERhlINED BY THE STATION. EXAMINATIONS WILL BE SCllEDULED EVERY OUTAGE UNTIL A DESCISION IS MADE BY TI.E STATION. 12050-CBM-093 A 51IT 3 LINE TO 2-RC-203 14 C-Imop 7707 3 PT Comments TITE I. NP-2700, RECOMMENDS INSPECTIONS CONTINUE, INSPECTION FREQUENCY TO BE DETERhllNED BY TIIE STATION. EXAMINATIONS WILL BE SCIIEDULED EVERY OUTAGE UNTIL A DESCISION IS MADE BY TIIE STATION. I2050-CB\1493 A SIIT 3 LINE TO 2-RC-203 14 NA C-Loop 7708 3 IT C. u T)TE I, NP-2700, RECOklMENDS INSPECTIONS CONTINL'E. INSPEC70N FREQUENCY TO BE DETERhtINED BY THE STATION. EXAMINATIONS WILL BE SCIIEDULED EVERY OUTAGE UNTIL A DESCISION IS MADE BY TIIE STATION. 120'0-CBNf 493 A SIIT 3 UNE TO 2-RC-204 14 C-LOOP 124 i PT Comments REMOVED IN Tile 1993 OtrTAGE. NO LONGER REQUIRED TO BE EXAMINED. 12050-CBM-096EL2 5113 UNE TO 2-SI-173 2'-S' o M-60243 10 RC216 142 0 trT Comments Remowd from the plan with liev.1I to the Pfart Reference memo Throckmorton to Davis dated 3-31-98. 120$0-ECl4105E R-54 8*-WS-513-151-Q3 17 NA MSVII 7737 3 VT-3 Comments New wrth Rev. I1 to the Plan- Perform VT-3 exa ninstion. Augmen'ed Program per QAE 88-60-06. 12050-FM-4A 2-MS-GOV-1 B 3 TB 6656 2 VT AMT/PT Comments ENAMINE STEM, SEAT, DISC. REPLACED WITII SPARE IN 95 OUTAGE UNDER WO 29982241. Summary etOnanges Sorted by Draning and Mari No-.NAPSU22 Database Page 8of 146 Pnnr Date: 11/18 93
_ - - - - ~ , . ..ms - - - _ - - - - -- - - - - - - - - - - - - - - - 1 i
- DraSing New Mark No. Une Number Category Itern No. Location Record Period Method t
12030-FM-4A 2-klS-GOV lX 3 NA TB 7735 3 VT/ SURFACE Comunents New with Rev. I I to P an: l Added a!! turbine govemor valves to ensure documentation of examinations is captured for at least one valve, i e., the last two characters in the mark No. is IX, which referes to all govemor valves. 2-hlS-GOV-l A was examined in 1998. One valve nmst be disassembled evers 40 monGes and a visual and surface examination of all valve seats, disks and stems must be perforrned if unacceptable flaws or excessive corrosion are found all other sahrs of that type shall be inspected. (unless the nature of the problem can be attnbuted to a sersice condition specific to that valve). 12050-FM-4A 2-hlS.IV-lX 3 TB 7472 3 VT/ SURFACE Comments kIINOR WORD CllANGE NEW WITil REY. II TO PLAN: 2-PT-47. Ewry 40 months disassemble one reheat intercept valve inspection cycle may be extended to 60 months prmided there is no indication ofcperational distress. Scheduled esery outage te collect exams performed for normal maintenance. "C" AND *D" vahes were examined 6/6S5. One vsee must be disassembled every 40 months and a visual and surface examination of all valve seats, disks an.1 stems must be performed. If unacceptable flaws or excessive corrosion are found, all other valws of that type shall be inspected, (unless the nature of the problem can be attributed to a service condition specific to that valve). 120$0-Fhl-4 A 2 MS-RSV-ID 3 TB 6664 2 VT&hfT/PT Comuments EXMl!NE SEAT, SEAT, AND DISC. SCIIEDULED FOR TO REMOVED, SIIIPPED TO WESTINGilOUSE AND REINSTALLUNDER WO304627-01. I 12050-FM-4 A 2-MS-RSV-IX 3 TB 7474 3 Vr/ SURFACE Comuments Minor ucrd change new with Rev 1I to plan: 2-PT-47. Ewry 40 months disassemble one reheat intercept valve. Inspection cycle may be extended to 60 months provided there is no indication of operational di tress. Scheduled eury outage to coIIect exams performed for normal maintenance "D" valves was examined 5/15/95. One vahr nmst be disassembled every 40 morehs and a visual and surface examination of all vahr seats, disks and stems rnust be performed. If unacceptable flaws er excessive corrosion are found, all other vahrs of that type shall be inspected,(unless the nature of the problem can be attributed to a service condition specific to that valw) 12050-ni-4 A 2-MS-TV-IC 3 NA TB 7473 2 VT AMT/PT Comments PERFORM SURFACE EXAh!INATION OF STEM, DISO, AND SEAT. INSPECTION DURING TIIE 95 OUTAGE UNDER WORK ORDER 265366-0 t, Don't know what is hagmening with this record. Showed up during the 1998 refueling with an examination date. Ilowever the site states that they did nd examine this valve. Therefore, examination date of 4-14-98 removed from this record. 120$0-FM-4 A 2-MS-TV IX 3 7728 3 VT/ SURFACE Comunen's Mm<r word change with Rev. I1 to plan: PERFORM SURFACE EXAhllNATION OF STEM, DISC, AND SEAT of any one valve. 2-MS-TV-1 A was examirwd during the 1998 outage. One valve must be disassembled every 40 months and a visual and surface examination of all valve seats, disks and stems must be performed. If unacceptable flaws or excessive corrosion are found, all other vahrs 4 of that type shall be inspected (unless the nature of the problem can be attributed to a service condition specific to that valve)L 12050-FM-4F llP TURBINE 2 NA TB 7327 3 VARIOUS Ceaunents 5 YEAR OVERil AUL DONE IN 93. NEXT SCIIEDULED FOR 98. > 12090-FM-4F LOW PRESSURE st. 2 TB 160 2 MT OR PT C :s WI LOW PRESSUAE TURBINE IS SCIIEDULED FOR INSPEC IlON DURING 95 OLTTAGE. UNDER WO 304817-01. PERFORM NDE AS REQUIRED BY hlCM-1404-1, MCM-1402-2, & MCM-1404-3, EXAMINE LTPER AND LOWER, ,
- 1) STAT!ONARY BLADE ROW OF Tile OLTFER1NNER CYLINDER,2) OUTER / INNER CYLINDER IlORIZONTAL JOINT FAS'ITNERS,3) INLET FLOW GUIDE,4) STATIONARY ;
BLADE ROWS OF TliE LTPER AND LOWER BLADl! RINGS,5)INNERINNER CYLINDER TO OUTER / INNER EXPANSION JOINT,6) TOP-IIAT TO OUTER SHELL EXPANSION JOINT,7) INNER CYLINDER TOP-ilAT,8) EACll COUPLING BOLT AND NtTT i 12050-FM-4F LOW PRESSURE . _. 2 TB 7391 2 VARIOUS i Cemements #2 IhW PRESSURE TURBINE IS SCitEDULED FOR INSPECTION DURING 95 OUTAGE. UNDER WO 304742-01, PERFORM NDE AS REQUIRED BY MCM-1404-1. MCM-1402-2, & 4 MCM-1404-3, EXAMINE UPPER AND LOWER, l) STATIONARY DIADE ROW OF Tile OUTER 1NNER CYLINDER,2) OUTER / INNER CYLINDER IIORIZONTAL JOINT FASTENERS,3) INLET FLOW GUIDE,4) STATIONARY BLADE POWS OF TIIE UPPER AND LOWER BIADE RINGS,5) INNER 1NNER CYLINDER TO OUTER / INNER EXPANSION JOINT,6) TOP-IIAT TO OtTrER SIIELL EXPANSION > JOINT,7) INNER CYLINDER TOP-IIAT,8) EACil COUPLING DOLT AND NtTT ! h---ry of C1 manges Soeted by Drawing and Mark No ,NAPSU22 Database Page 9of 146 Prrnt Dore: 11/18193
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'I'W No. Mark No. .. IJne Number Category Item No. . tecation - . Record Perted f hieshed .
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12090-FM-4F LP Accessible 2 NA- TB 7734 3 . VT/ SURFACE Comuments 11 Twbine No. I: Peiform visual and surface examinations of all accessible locations en the steam turbine assernbly.
' 12050-FM 4F LP Turbine Rotor I - I!otor No. TN-12832 2 NA TB 7733 3 . VF/SURFUF Comuments LP Turbine No.1: Perform visual, surface and volumetric examinations. The turbine rotor serial No. TN-12832 is scheduled for UF e---- = of the disc bore and ke3way,(last -
performed on 6 this is a 60 month examinwinn). Other inaccessible locations should be examined by visual and'or surface methods. l i2050-WhlRS-0101 A-1 - 27 . 32'-SitP-401-601-Q2 C-F-2 C5.51 168 2 MT/UT
- tenumenes WEFCB () CilANGED FRONI PERIOD O TO PERIOD 2 IN REV. 5. . REPL ACING 10l A-310.
42050-WMKS-0101 A-1 6 211 ' 32"-SilP 401-601-Q2 C-C C3.20 7533 0 [ 6
- Commemroes IISS-38B. NOT SELECTED j 12050-WMKS4101 A-l 13-26W(27) 37-SitP-401-601-Q2 C-F-2 C5.52 7227 2 MT/UT - {
~C. - :- WEFCB 0 27 - 59 ADDED IN REV. 2. CHANGED FROM PERIOD 0 TO PERIOD 2 IN INTERIM CILANGE 9542. REPLACING LS-lI4W(8). WHICH IS RESTRICTED BY A PIPE BREAK RESTRAINT SilOWN ON FV-80A. , 52050-WhlKS-0101 A-I - 13-29W(SW-75) 3T-SitP-422401-02 C-F-2 C5.52 7295 0 Casmunenes WEPLIC() SW SW-75 ADDED IN REV. 2. CIIANGED FROM C5.82 TO C152 IN REV.7 NOT A BRANCil CONNECTION [ i 12090-WilKS-0101 A-1 - LS-32W(2) 32'-SIIP-422401-Q2 C-F-2 C5.52 18"' 0 a Comumenes WEPCB 0 2 - SW lW ADDED IN REV. 2. CIIANGED FROM C5 82 TO C5.52 IN REV. 7 NOT A BRANCll CONNECTION. ; ' 12090-WMKS4101 A LS-96(SW-94) 32'-SIIP-401-601-Q2 C-F-2 C5.52 MSVH 7233 0 MTMF-I l Ceumments WEPSEM 0 EXAMINE BOT 11 ENDS OF TIIE ELBOW, ADDED IN REV 2.CIIANGED FROM LS-96(94) TO LS-96(SW-94) WITH REV.10 TO PLAN AND MOVED FROM PERIOD 3 ' i TO PERIOD 0 SUBSTITVIED WITH 101 A-2 LS-95(l).13 %S4)lS RESTRICTED BY A PIPE COLLAR. 12050-WMKS4101 A-1 SW-3W(SW-81) 3T-SilP-422401.Q2 C-F-2 C5.81 197 0 { Ceemments WEPDC 0 CIIANGED hlARK NUMBER TO INCLUDE WELD NUMBER FOR REINFORCING PAD. REV. 7. l r i 12050-WMRS-0101 A-l SW-4W(SW-80) 37-S!!P-422401-Q2 C-F-2 C5.81 196 2 MT
- Ceaumenes SW-80 INACCSSDLE E" %IINE WELDS SW-96 & SW-4W IN llEU OF SW-80. ADDED IN REV 2. CHANGED MARK NUMBER TO INCLUDE WELD NUMBER FOR REINFORCING PAD. REV. 7. .
12050-WMKS-0101 A-l SW-5W(SW-79) 37-SHP-422401-Q2 C-F-2 C5.8I 195 0- . C -t WEPDC 0 CIIANGED MARK NUMBER TO INCLUDE WELD NUMBER FOR REINFORCING PAD. REV. 7. .i i 12090-WMKS4101 A-I SW4W(SW-78) 37-SIIP-422401-Q2 C-F-2 C5.81 194 0 -
- Comumenes WEPDC () CllANGED MARK NUMBER TO INCLUDE WELD NUMBER FOR REINFORCING PAD. REV. 7.
-I i 12090-WMKS-0101A-1 SW-7W(SW-77) 37-SitP 422401-Q2 C-F-2 C5.81 193 0 -
- ~eaumemes WEPBC () CIIANGED MARK NUMBER TO INCI UDE WELD NUMBER FOR REINFORCING PAD, REV. 7.
'PrmtDame' 1#18W I I %mummary of Changes Sorted by Drautmg med Mark No.,NAPSU22 Delahase Page 10of 46 i
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- Ikweine Nec Mark No . Line Ninisher Category Item Ne- Location Record Period Method 12050-WMKS-0101 A-1 SW-92 32"-SifP 403401-Q2 C-C C3.20 7534 -0 Ceauseenes ~ R-216. SELECTED FOR PERIOD 2 e-, t+- , -- t 120$0-Whf ES-0101 A-1 SW 32"-SIIP422401-Q2 C-C C3.20 7535 0 s
Consomments 115S-2I3 A. NOT SELEC LED 120$0-WMKS4101 A-1 SW-95 32"-SIIP-42251-Q2 C-C C3 20 7536 0 C- .L IISS-213fL NOT SELECTED 120$0-WMKS-0101 A-1 SW-95(SW-8 *) 3T-SilP-422401-Q2 C-F 2 C5.8I 7413 0 4 Cesamients WEPBCi) CIIANGED ' G NUMBER TO INCLUDE WELD NUMBER FOR REINFORCING pal? REY. 7. 12050-WMKS-0101 A-1 SW-96(SW-80) 32*-SIIP-422401-Q2 C-F-2 C5.81 7412 2 Ceauenents SW-80 INACCSSBLE EXAMINE WELDS SW-96 & SW-SW IN LIEU OF SW-80. ADDED IN REV 2. CilANGED MARK NUMBER TO INC'I.UDE WELD NUMBER FOR REINFORCING
. PAD REV 7.
I2090-WhlKS410l A-1 SW-97(SW-79) 3T-SIIP422401-Q2 C-F-2 C5.8I 74II 0 Ceauseents WEPBC 0 CllANGED htARK NUMBER TO INCLUDE WELD NUMBER FOR REINFORCING PAD. REY. 7. 120$0-% hlESC101 A-1 SW-98(SW-78) 3T-SitP-422401-Q2 C-F-2 C5.81 74I0 0 LN WEPBC O CllANGED MARK NUMBERTO INCLUDE WELD NUMBER FOR REINFORCING PAD. REV 7. . 120$0 WMKS410l A-l S W-99(SW-77) 37-SIIP-422401-Q2 C-F-2 C5 81 7409 0 Conuments WEPBC () CilANGED MARK NUMBER TO INCLUDE WELD NUhlBER FOR REINFORCING PAD. REY. 7, 12040-WMKS-0101 A-2 1211 32"-SitP402401-Q2 C-C C3.20 7537 0 Cenumments llSS-30fL NOT SELECTED 12030-WMKS-0101 A-2 51 32'-SilP-402401-Q2 C-F-2 C5.51 213 2 MT/UF C ;;. WEPCB 0. CilANGED FROM PERIOD 0 TO PERIOD 2 IN INTERill tilANGE 95-02. REPLAGNU 5W-88 ON SAME DRAWING WlIICIIIS RESTRICTED BY A PIPE BREAK RESTRAINT 12050-WMKS-0101 A-2 95J 32"-SilP-423401-Q2 C-C C3.20 7538 0 Ceamerats IISS-212A NOT SELECTED 12050-WMKS4101 A-2 961 32"-SIIP-423401-Q2 C-C C3.20 - 7539 0 C. -; 11S5-212I1 NOT SELECTED I2050-WMKS-0101 A-2 LS-110W(SW-12D) 3T-SIIP423401-Q2 C-F-2 C5.52 7297 0 4' Comunesets WEPBC 0 SW 12D ADDED IN REV 2 ClIANGE FROM C5.82 TO C5.52 IN REV.7. NOT A BRANCIICONNECTION. I 12050-WMKS4101 A-2 LS-Il4W(8) 37-SIIP-423401-Q2 C-F-2 C5.52 225 0 MT/UT Comunents WEPCB 0 BETWEEN WELDS 8 - SW-99W. EXAMINE Tif E BRANCl! END. ADDED IN REV. 2. CIIANGE FROM C5.82 TO C5 52 IN REV 7 NOT A BRANCil CONNECTION ! , CllANGED FROM PERIOD 2 TO PERIOD 0 IN INT. 95-02. RESTRICIED BY A PIPE BREAK RESTRAINT FV-80A. REPLACED WTI'll LS-26W(27) ON 10I A-I I Seminineary of Osmages Sorted by Drewhig and Mark No , NAPSU22 Detebase Page ff of 146 Pnnt Date: 11/18 93 ___ - _ - _ - _ - - _ _ - - _ _ _ . - - _ _ - - -_ ---- . - ._.._ . . - - ~ -
Drawing Nn. blark NE IJne Number Category item No. tecation Record Period Afethed 12050-WhlKS-010l A-2 13-95( [ 32'-Sitr-402401-Q2 C-F-2 C5.52 227 3 hfT/UT Comments ' WEPSEh! O. Cl!ANGE D FROh! PERIOD 0 TO PERIOD 3 WITil REV 10 TO PLAN, SUBSTITUFING FOR FOR LS-96(SW-94)ON 101 A-1 WillCllIS RESTRICTED BY PIPE CCiIAR. 12050-WktKS-Ol01 A-2 SW-10D(SW-83) 32'-SitP-423401-Q2 C-F-2 C5.81 7406 0 Comments WEPBC 0 CitANGED kl ARK N1'h1BER TO INCLUDE WELD NMtBER FOR REINFORCthG PAD. REV. 7. 12050-WhtKS-0101 A-2 SW-I D(SW-87) 32iSitP-423401-Q2 C-F-2 C5.81 7404 0 Comments WErBC 0 CIIANGED hlARK NUhtBER TO INCLUDE WFLD NUhlBER FOR REINFORCMG PAD. REV. 7. 12090 WhtKS-0101 A-2 SW-2D(SW-86) 32*-SilP-421401-Q2 C-F-2 C5 81 235 0 Comments WEPBC 0 CIIANGED ktARK NUhlBER 10 INCLUDE WELD NUhlBER FOR REINFORCING PAD. REY. 7. 12050-WhlKS-010l A-2 SW-3D(SW-85) 32*-SilP-423401-Q2 C-F-2 C5.81 234 0 Comments WEPDC 0 CllANGED hlARK NUhlBER TO INCLUDE WELD N13fBER FOR REINFORCING PAD. REY. 7. 12090-WhtKS-010l A-2 SW-4D(SW-84) 32*-SIIP 423401-Q2 C-F-2 C5.81 233 0 Comments WEPBC O CllANGED hl ARK NUhlBER TO INCLL'DE WELD NUhtBER FOR REINFORCING PAD. REV. 7. 12050-WhtKS-0101 A-2 SW-5thSW-83) 3 slip-123401-Q2 C-F-2 C5.81 232 0 Comments WEPBC () CIIANGED hlARK NUh!BFR TO INCLUDE WELD NUhfBER FOR REINFORCING PAD. REY. 7. 12050-Wh!KS-Ol0i A 2 SW4D(SW-87) 32'-SitP-423401-Q2 C-F-2 C5.81 236 0
. Comments %TPBC 0 Cll ANGED hl ARK NUhlBER TO INCLUDE WELD NUhlBER FOR REINFORCING PAD. REY. 7.
12030-WhtKS-010l A-2 SW-7D(SW-86) 32*-SIIP-423401-Q2 C-F-2 C5.81 7405 0 Comments WEPBC () Cl! ANGED htARK NUhtBER TO INCLUDE WELD NUhtBER FOR REINFORCING PAD. REV. 7. 12050-WhtKS-0101 A-2 SW-88 32*-SIIP-423401-Q2 C-F-2 C5.51 237 0 aft a tTF Comments ADDED IN REV 2 WEPCB 0. CIIANGED FROh! PERIOD 2 TO PERIOD 0 IN INTER!ht ClIANGE 95-02 RESTRICFED BY A PIPE BREAK RESTRANT. REPLACED WITIl WELD 51 ON SANIE DRAWING. 12050-WhfKS-010l A-2 SW-89 32"-SitP-402401-Q2 C-C C3.20 7540 0 Comments R-215. NOT SELECTED 12090-WNtKS-010l A-2 SW-8D(SW-85) 32*-SIIP-423401-Q2 C-F-2 C5.81 7408 0 Comments WEPBC 0 CIIANGED hiARK huf BER TO INCLUDE WELD NMfBER FOR REINFORCING PAD. REV. 7. 12050-Whf KS-010l A-2 SW-9D(SW-84) 32*-SilP-423401-Q2 C J-2 C5.81 7407 0 Ceaunents WEPBC 0 CllANGED hlARK NUhlBER TO INCLUDE WELD NMtBER FOR REINF0F.CING PAD. REV. 7. I2050-WitKS-0101 A-3 10 32*-SIIP-403401-Q2 C-F-2 C5.51 241 0 hlT & ITI' Comments ADDED IN REY 2. WEPCB O. lARGE SUPPORT COLIAR RESTRICTS ELhillNATION. CIIANGED FROh! PERIOD I TO PERIOD 0 IN REV. 5. REPLACED %Tril 27 ON 101 A-l. Summary of Ganges Sorted by Druning and Alark No., NAPSU22 Database Page 12of 146 Pnnr Date: 11/1a ps
4
' Jrmutng No. Mark No. Line Numher Cate8ary Iteen No. Imation Record Perted Method -
MSVII 252
~ - 12050-WKlKS4101 A-3 . 2-SIIP-R-601 . 32*-SIIP-40340i-Q2 F-B F2.0 0.
C_ . = AllARES Cl{ANGED FROM PERIOD 3 TO PERIOD 0 IN R EV. 7. SAMPLES SIZE h!UST BE PROPORTIONAL TO SYSTEKI AND SUPPORT TYPE. 13090 WhlKS-0101 A-3 311 32*-SIIPUO3-60l-Q2 C-C ~ d.20 754I O Camunents IISS-23R NOT SELECT!D
-- i2050-WMKS 101A-3 LS-53W(SW-5W) 32'-S!!P-424-601-Q2 ' C-F-2 C5.52 7299 0 Ceaunents WEPOC 0 SW-17W- SW-5W ADDED IN REV. 2. CllANGE FROM C5.82 TO C5.52 IN REY 7. NOT A BRANCll CONhTCTION.
12050-%1tKS-0101 A-3 LS-5N(21W) 37-SilP424-6014)2 C-F-2 C5.52 7300 0 l Comuments WEPCB 0 21W - SW-22W ADDED IN REY. 2. CIIANGE FROM C5 82 TO C5.52 fN REV. 7. NOT A BRANCil CONNECTION 11050-WMKS4101 A-3 SW-16W 32"-SIIP403-601-Q2 C-C C3.20 7542 0 Ceauments R-214. NOT SELECTED s2050-WMKS 030?
- 3 SW-18W 32*-SIIP-424-601-Q2 C-C C3 20 7543 0 P -
!!!S-2ii A. NOT SELECTED 12050-WL!KS-OiGi A-3 SW-19W 32*-SilP424-601-Q2 C-C C3.20 7544 0
. C. IISS-21iB. SELECTED FOR PERIOD 3 12050-WMKS.clo t *-3 SW-23W(SW-llW) 3r-SilP-424-60l-Q2 C-F-2 C5.81 268 0 t a WEPDC 0 Cl!ANGED M ARK NMIBER TO INCLUDE WEW NUhtBER FOR REINFORCING PAD. REV. 7. ,
120$0 WMKS-0101 A-3 SW-24W(SW-10W) 32'-SfiP424-601-Q2 C-F-2 C5.81 ~ 267 0 , Ceemmerets WEPDC 0 CllANGED M ARK NUMBER TO INCLUDE WELD NUMBER FOR REINFORCING PAD. REV. 7. 12030-WMKS4101 A SW-25W(SW-9W) 32'-SIIP-424-601-Q2 C-F-2 C5.81 MSvil 278' 3 MT Ceemeento SW-9W INACCESSIBLE. EXAMINE WELD 5 $W-25W AND SW-30W IN LIEU OF SW-9W. CIIANGED MARK NUMBER TO INCLUDE WEID NUMBER FOR REINFORCING PAD. t REV.7-i 12050 WMKS4t01 A-3 SW-26W(SW-8W) 32*-S!!P424-601-Q2 C-F-2 C5.81 277 0 Ceauncats WEPDC () CilANGED MARK NMIBER TO INCLUDE WEID NM!BER FOR REINFORCING PAD. REV. 7. ,
?
4 a MN-WMks4tet A-3 SW-27W(SW-7W) 32'-SitP424-601-Q2 C-F-2 C5.81 276 0 l Comments WEPBC O CIIANGED MARK SMIBER TO INCLUDE WELD NUMBER FOR. REINFORCING PAD. REV. 7.
!2050-Wtt KS-310l A-3 S X-25W(SW-1)W) 32'-SIIP-424-601-Q2 C-F-2 C5.81 7403 0 1
Cm WEF3C 0 CilANGED MARK NUMBER TO INCLUDE WELD NUMBER FOR REINFORCINO PAD. REV. 7. 4 1204-%3bl01 A-3 SW-29W(SW-10W) 32*-SHP424-601-Q2 C-F-2 C5 51 7402 0 Comument WEPDC 0 CilANGED MARK NUMBER TO INCLUDE WELD NUMBER FOR REINFORCINO PAD. REV.7. } k Senumarye8tasmges Sorted by Drawhng a=4 Mast New.NAPSU22 Detsbane Page 13 of 146 Prrn D ae: 11/18 98 t
, . . -. .- __ , - . . ..--a - - . ,
_ - - __ . . - _ _ . . . ._. _ _m m . .. .. .~.. - _ , . _ .- -. ___..m . l__- ,_ _ _ . _ _ _ - _ - . _ _ _ ~ ._ Dr= ming No. Mark Nx !A , Number Category leem No. Imation Reeerd Period Method __ 4 12630-Wh*NS-3101 A-3 SW-30W(SW-9W) 32NS18P 424-601-Q2 C-F-2 C5.81 MSVII . 7401 3 - MT
, C. L SW-?W !NACCESS!BLE. EXAMINF WEl.DS SW-25W AND SW-30W IN L!EU OF SW-9W. CIIANGED MARK FF.iSER TO INCLUDE WELD NUlfBER FOR REINFORCING PAD.
REY. 7. .. 12030-WMKS-0101 A-3 SW-31W(Sb'-8W) 3I-hitP-424401-Q2 C-F-2 C5.Sl 7400 0 '- , _C e WEPDC () CIIANGED MARK NUMBFR TO INCLUDE WELD NUKIBER FOR REINFORCING PAD. REY.7. i 12050 WMKS-0101 A-3 SW-32W(SW-7W) 32'-SIIP-424401-Q2 C-F-2 C5.81 7399 0
- Camets W F Pfr() CliANGED hlARK NUh!BER TO INCLUDE WELD NUMBER FOR REINFORCING PAD. REV. 7.
12050-WMM-a?9E-4 SW-5 (BPL 343) 32'-SilP-45940 7 SB 7218 I UT/hfT Cosaments EXAMINE I;VERY 40 hlONTIIS:33*.0F Al L SEI ECTED WELDS. WITil 100*6 OF AIL WELDS COMPLETED BY END INTERVAL. 5-12-98 changed BPL from 334 to 343 per new mith Alex and UFSAR. '[ 120Kr-WMKS 010l$4 SW-5 (BPL 343) N'41?P 459-601 7 SB 6650 1 ITTAfT CN LXAMINE EVERY 40 MONTilS: 33*6 OF ALL SELECTED WELDS. WIT 11100'e OF ALL WELDS COMPT.ETED PY END INTERV/d. REMOVED FROh! AUGMENTED PROGRAM IN ' i REV. 2 RFCORD WILL REhlAIN IN PLAN TO SIIOW EXAhflNATION IIISTORY. 5.!2-98 changed BPL from 334 to 343 per meetmg with Alex and UFSAR. -
- i. 12050 WMKS4101 A4 SW-53 (BPL 336) 32'-S!!P-459401 7 NA 3B 6651 1 ImMT.
Commments EXAMINE EVERV 40 MONTilS: 33% OF ALL SEUCTED WELD % WITil 100's OF ALL WELDS COMPLETED BY END INTERVAL , 12050-WMKS-0101 A4 SW-53 (BPL 336) 32'-SIIP-459401 7 NA SB 7512 1 t?TIMT Commenta EXAMINE EVERY 40 MONTilS: 33% OF ALL SELECFED WELDS. WITII 100% OF ALL VTLDS COMPLETED BY END INTFRVAL REMOVED FROM AUGMENTED PROGRAM IN ^i REY. R. RECORD Will REM AIN IN TIAN TO SiiOW EUMINAllON illSTORY New with Rev. I I to plan: Old record in database showed that a IT exes. was peformed in 1992. Ilowever, there is no supportmg exam report. Therefwe, the weld is scheduled for examination at the mxt (1999) refueling outage; MIATT exasrioa 12050 WMKS-0101A-4 SW-55 (BPL 105) 32'-SitP-457401 7 NA FIS 6644 3 UT/MT 4 Cosen, ems EXAMINE EVERY 40 MONTilS: 33% OF ALL SELLCIID WELDS. WITil IGO's OF ALL WELDS COMPLETED BY END INTERVAL REMOVED IN REV. B. ADDED BACK IN INTERIM C11ANGE 96-04. WAITING ON NRC APPROVAL BEIURE REMOVING FROM PLAN. , 12051 WMKS4iol A-4 SW-55 (BPL 201) 32'-SIIP-45840 I 7 NA SB 6648 3 UT,MT C .aa EXAMINE EVERY 40 MONTilS: 31% OF ALL SELECTED WEl DS. WITil 100% OF ALL WELDS COMPLETED BY END INTERVAL REhf0VED IN REV. 8. ADDED PACK IN INTERIM CHANGE 96-04, WAITING ON NRC APPROVAL PEFORE REMOVING FROM PLAN.
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(203C-WMKLO101 A4 SW-7 (BPL 209) 32'-SI8P-458-6GI 7 NA TB 6649 3 UTiMT Ca mmenta EXAMINE EVERY si MO'3T33S. 33% OF ALL SELECTED WELDS. 4TTil 100*6 OF ALL WELDS COMPLETED BY END INT ERVAI. REMOVED IN REY. 8. ADDED DACK IN INTERIM CIIANGE 9404. WAITING ON NRC MPROVAL 11EFORE REMOVING FROM PLAN. 12050 WMK5-0101 A-4 SW-8 (BI'L 116) 32'-SIIP-45740I 7 NA TB 6645 3 . UTIMT C .Js EXAMINE EVERY 40 MONTIIS: 33% OF ALL SELECTED WELDS. RTTil 100% OF ALL WELDS COMPIITliD BT EMD INTERVAL REMOVED IN REV 8. ADDED BACK IN INTERIM C!!ANGE 96 04. WAITING CN NRC APPROVAL 11EFORE REMOVING FROM PL?L W yew from 1998 to I*99 wih RcV. !! ?* Man. 12050-WMKS 0 01B I (35W) 32*-SIIP401401-Q2 C-F-2 C5.51 RC291 279 i 58T A tTr o Commento 100% REPLACED BY SGRP. NEW WELD NUMBER 35W. REV. j 7 i s.mm.ry or o =nces sorted 65Dr=s g and Mark New NAP 5t!22 Database Page 14of 146 Pna;Date: 11/1 & 99 f
Drawing %. Mark No. Line Ni nber Category item No. I uration Record hrid Alethod 120%WMKS-0101B 2-SilP-Sit-46 32istIP-401401-Q2 F-C F3.0 RCT 7433 3 VT-3 Cemments C11AVAR. LHACCEPTABLE SPRINO SETTING AND I OOSF J ut N1TT FROh! 95 EXAhliN ATION. REE.MilNATION REQUIRED DY IWF-2420(b)IN Tile NEXT PERIOD-ADDED IN REV. 7. I2050-WMKS-0101B 35W 32%51IP-401401-Q2 C-F-2 C5.5 I RC291 7440 0 MT Airr Comments REPIACED BY SGRP. OLD WELD NUMBER I. REV. 7. OLD WF LD EX LMINED IN Tile FIRST PERIOD. 120%WMKS-0101B 37W 32'-SIIP-401401-Q2 C-r-2 C5.51 7441 0 Coenments NEW WELD FROM SGRP. REV. 7 I2030-WhtKbO101 D 771 32iSilP .an t.ec;-Q2 C-C C3.20 RC291 300 0 AIT Comments 100's CIIANCFD htChi PEIGOD 3 TO PERIOD 2 IN REV. 3. TO EXAht!NE WITil 781. CilANGED FROM PERIOD 2 TO PERIOD 0 REV. 7. RELIEF REQUEST NDE-2i ALLOW USE OF CODE CASE N-509 Wit!CII ONLY REQUIRES 10'e' ',F TIIE INTEGRAL ATTACllMENTS TO BE EXAMINED. R-43 NOT SELECTED. I2050 WMKS-010'B 78J 32isilP-401401-Q2 C-C C3.20 RC291 3cl 0 MT Commeras 100* Cl(ANGED FROM PERIOD 2 TO PERIOD 0 REV. 7. RELIEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 WIIICII ONLY REQUIRES 10% OF Ti!E INTEGR AL ATTACliMENTS TO BE EXAMINED.R-43 NOT SELECTED I2050-WMKS-0101B LS-IDW(37W) 3T-s!!P.40!401 -02 C-F-2 C3.5 2 3n6 0 Conunents WEPCB () FW SW-86 ADDED IN REV. 2 C58230E3 Tiii~. INTERSECTION WELD NUMBER TO 37W AFTER SGRP IN REV. 7.
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12G30-WMES DIMS LS-10WA(37W) 32iSliP-401-6f?l-Q2 C-F-2 C5.52 7655 0 Comments ADDED IN REV. AFTER SGRP. NEED NEW WELD NUMBER WAITING ON DRAWING REY. *r ADDFD LWIT TiiEN. 12050 WMKS-0101B LS-10WA(SW-R5) 32iSIIP-401601Q2 C-F-2 C5.52 765I 0 Coniments ADDED IN REY. 7 AFTER SGRP. NEED NEW WELD NUMBER WAITINC ON DMWING REV. "W ADDED UNIT TIIEN. 12050 WMKS-OlolB SW-83 35-SitP-401401-02 C-C C3.20 RC291 333 0 MT (% :::Go 100% (IISS-207 SFLECTED FOR PERIOD 3) PRESERVICE MT. CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 7. REllEF P1 QUEST NDE-21 ALLOW USE OF CODE CASE N-509 TO EXAMINE !O*6 OF TIIE INTEGRAL ATTAcilMFETS. 12050 WMKS-0101B SW-84 32iSilP-401401-Q2 C-C C3 20 RC291 334 0 MT Comments 100% CllANGED FROM PERT 6D 2 TO PERIOD 0 REV. 7. RELIEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 WIIICil ONLY REQt ' IRES 10*s OF Tile INTEGRAL ATTACilMENTS TO BE EXAMINED.115S-208 NOT SELECTED. I2050 WMKS-0101B SW-% 32*-31IP-401401-Q2 C-C C3.20 RC291 340 0 MT Conments 100*. (SIM6 SELECTED FOR PERIOD 2) Cil ANGED FROM PERIOD 2 TO FERIOD 0 REV. 7. RELIEF REQUEST NDE-2i ALLOW USE OF CODE CASE N-509 WIIICII ONLY REOUiRES 10*iOF Tile INTEGRAL ATTACilMENTS TO BE EXAMINED. 12090-WMKS-010lc Il5W 32iSIIP-402401-Q2 C-F-2 C5.51 RC291 345 0 Comn cnts REMOVED FROM PERIOD I IN REV. 2.100% REPLACED BY SGRP OLD WELD 28. REV. 7. IM30-WMKS-0101C ll7W 32iSIIP-402401-Q2 C-F-2 C5.51 RC291 7442 0 C -- cs ADDED BY SGRP. REV. 7. NOT ADDED BY SGRP ACCORDING TO REV. 2 OF TIIE DRAWING. DELETED IN REV. 8. sammary of Changes Sarted by Drswing and Mark No-. NAPSU22 Database Page 15 of 146 Prmt Doce: 1l'I& 98 _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - - _ _ _ _ _ _________ _ _ - ___ ___ _ _ _ _ _ _ - .___ . _ _ -- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ . _ - _ _ . _ _ _ . _ _ = .
Drawing No. Alark E n m Categerv Nela location Record [eM hlethod 12050-Wh1KS-Ol0lc 7911 32.SitP-402-601-Q2 C-C C320 RC291 3*3 0 hfT Comments 100%(Sil47 NOT SELECTED) PRESERVICE EXANIINATION CllANGED FROM PERIOD 3 TO PERIOD 0 IN REV. E REllEr RFOWST NDE-21 ALIDW USE OF CODE CASE N-509 TO EXAMINE 10*.0F Tile INTEGRAL ATTACllMENTS. 12050-WMKS-010lc LS-10lW(ll7W) 3T.SilP-402-601-Q2 C-F-2 C5.52 355 0 Comments WEFCil() SW SW-82 ADDED IN REY. 2 Cll ANGED Tile INTERSECTION WEl D c' ROM SW-80 TO ll7W AFTI.R SGRP REV 7. 12090-WhlKS-010lc LS-10lWA(ll7W) 37-SilP-402-601-Q2 C-F-2 C5.52 7660 0 Comments ADL'ED AFTER SGRP REV.7. 12050-WMKS-Olo tC LS-10lWA(SW-80) 37-SitP-402-601 Q2 C-F-2 C5.5 2 7659 0 Coenments ADDED AFTER SGRP REV.7. -
~
12050 WMKS-010lc LS-96(I15W) 37-SilP-402-601-Q2 C-F-2 C5.52 360 0 Comments WEPSEM (). CIIANGED Tile INTERSECTING WFLD NUh1BER FRONf 26 TO 115W AFTER SGRP IN REV. 7. 12090-WMKS-0101C SW-84 37.SIIP-402-601-Q2 C-C C3.20 RC291 366 0 MT Comments 100% Cil ANGED FROM PERIOD 2 TO PERIOD 0 REV. 7. RELIEF REQUEST NDE-2I Al LOW USE OF CODE CASE N-509 WillCil ONLY REQUIRES 10's OF Tile INTEGRAL ATTACllMENTS TO BE EXAMINED.115S-206 NOT SELECTED 12090-WMKS4)l0lc SW-85 37-SilP-402-601-Q2 C-C C3.20 RC262 367 0 MT Comments 100*. WELD IS AT PENETRATION 75 (NOT SELECTED)IIAS NOT BEEN EXAMINED CIIANGED FROM PERIOD 3 TO PEntlOD 0 IN RFV. 7. RELIEF REQUEST NDE-2l ALLOW USE OF CODE CASE N-509 TO EXAMINE 10*4 OF Tile INTEGR AL ATTACllMENTS. 12090-WMKS-Ol01D ISN 37-SIIP-403-601-Q2 C-C C3.20 RC291 370 0 MT Comments 100**(S1148 NOT SELECTED) EXAMINED IN 84. CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REY. 7. RELIEF REQUEST NDE-21 ALIEW USE OF CODE CASE N-509 TO EXAMINE 10*.OF Tile INTEGRAL ATTACIIMENTS. I2050-WMKS-0101D 57W 32*-51iP-403-601-Q2 C-F-2 C5.5 i RC291 382 0 Comments REMOVED FROM PERIOD I IN REV. 2.100% REPLACED BY SGRP. 0LD WELD 48. REV. 7. 12090-WMKS-010lD 59W 37-SIIP-403-601-Q2 C-F-2 C5.51 7443 0 Comments ADDED BY SGRP. REV. 7. 12050-WMKS-0101D LS-25W(57W) 3T-SilP-403-601-Q2 C-F-2 C5.52 390 0 Commenta WEPSEM () INTERSECTION WELD NUMBER CllANGED AFTER SGRP. REV. 7 12090-WMKS-010lD LS-34W(59W) 37-SilP-403-601-Q2 C-F-2 C5.52 393 0 Comments WEPCB () 49 - 17W ADDED IN REV. 2. CIIANGED Tile INTERSECTION WELD NUMBER FROM 49 TO $9W AFTER SGRP IN REV. 7. 12050-WMKS-010lD LS-34WA(49) 32*-SitP 403-601-Q2 C-F-2 C5.52 7657 0 Comments ADDED IN R.EV. 7 AFTER SGRP. NEED NEW WELD NUMBER WAITING ON DRAWING REV. "A* ADDED UNIT THEN. Summary cf Changes Sorted sy Draning and hf ark No, NAPSU22 Database Page tr -f le Prmt Dare: 11/1/t9s
mm _ s- m. .m- - - - - - - - _ - - - - - - - - _ --- - - - - -- - - - - - - - - - - - -- - - - - - -- i tag Na - Mark No. Line Number Category - Item No. - tecation . Record Period Metined 550-WhtKS-010lD LS-34WA(59W) 37-SitP403401-Q2 C-F . C5.52 7656 0 asumenes ADDED IN REV. 7 Fil.R SGRP. 2050-WKtKLOl01D SW-10W 3T-SIIP-403401-Q2 C-C C3.23 RC291 407 0 hfT asuments 100*i LiiANGED FROh! PERIOD 2 TO PERIOD 0 REY. 7. RELIEF RFQUEST NDE-21 ALLOW USE OF CODE CASE N-509 WillCII ONLY REQt4RES 10*6 OF TIIE INTEGRAL ATTACith!ENTS TO BE EMt!NED I155-202B NOT SELECTED. . '050.WKtKS0101D SW-12W 32'-SiiP-403401-Q2 C-C - C3.20 . RC291 409 0 LIT asumenes , 100*6 (IISS-203 NOT SELECTED). CilANGED FRONI PERIOD 1 TO PERIOD 3 IN REV. 3. TO ALLOW EXAh! TO BE PERFORhfED WITil ADIACENT ATTAClikfENT. IIAS NOT BEEN EXAhtINED PREVIOUSLY. CilANGED FRONI PERIOD 3 TO PERIOD 0 IN REV. 7. REUEF REQUEST NDE-21 ALIDW USE OF CODE CASE N-509 TO EXAhtlNE 10*4 OF TIIE INTEGRAL ATTACilklENTS. !'30WhlKS-0101D - SW-13W .32'-SitP-403401-Q2 C-C . C3.20 RC291 - 410 0 eft -
=s 100*6(115S-204 NOT SELECTED) PRESERVICE EXAhlINATION. ClIANGED FROh! PERIOD 3 TO PERIOD 0 IN REY. 7. RELIEF REQUEST NDE-21 AllMW USE OF CODE C KSE N-309 TO EXAhflNE 10*6 OF TIIE INTEGRAL ATTACith!ENTS.
2090-WMKS-010lD SW-7W 37-SiiP.403401-Q2 C-C C3 20 RC291 418 0 MT onuments 100% ClIANGED FROh! PERIOD 2 TO PERIOD 0 REY. 7. EELIEF REQUESr NDE-21 ALLOW USE OF CODE CASE N-509 WillCII ONLY REQUIRES 10*.0F THE INTEGRAL ATTACllhtENTS TO DE EXAhlINED. S11-49 NOT SELEC1 ED.
- '050-WktKS-010lD SW-8W 37-SitP-403401-Q2 C-C C3.20 RC291 419 0 MT a 100*6(IISS-20I A.B NOT SELECTED) IIAS NOT BEEN EXAh!INED PREVIOUSLY. CIIANGED FROM PERI'OD 3 TO PERIOD 0 IN REV. 7. REUEF REQUEST NDE-21 ALIEW USE OF CODE CASE N-509 TO EXAMINE 10*.OF Tite INTEGRAL ATTACIIMENTS. -;
'090-WMKS-010lO SW-9W 37-SitP-401401-Q2 C-C C320 RC291 421 C. hFF enuments 100% CILANGFD FROM PERIOD 2 TO PERIOD 0 REV. 7. RELIEF REQUEST NDE-21 ALIDW USE OF CODE CASE N-509 WillCH ONLY REQUIRES 10*6 OF T1IE INTEGRAL ATTACHMENTS TO BE EXAh!INED. IISS-202A NOT SELECTED.
! '050-%3tKS410lGA 2311 6"-SitP-437401-Q2 C-C C3.20 7545 0 , unemenes 511-il8. NOT SELECTED ! "30WMKS-OlolGB 2311 6"-SIIP-438401-Q2 C-C C3.20 7546 I esamients Sil-117. SELECTED FOR PERIOD 3
'090 %3tKS-OI01GC 23ft 6*-SIIP-439401-Q2 C-C C3.20 7547 0 muessents Sil-116. NOT SELECTED '050.WMKS-0102A l(NEW WELD 75) 16'-RTPD-424401C-Q2 20 C5.51 RC291 6674 1 UT
- mumments INDICATIONS WERE FOUND IN "A* AND "C" UNIT I IN 1993. FEEDWATER NOZZLE STUDY REPORT RECOMMENDS AIJF EVEhY REFUELING STARTING WITil TIIE 1993 REFUELING OUTAGE. REPLACED BY SGRP OLD % ELD 1 NEW WELD 75. REV. 7.
'950-%3tKS 0102A l (NEW WELD 75) 16'-%TPD-42440lC-Q2 20 C5.51 RC291 7311 2 MT(LD.)
meurenes INDICATIONS WERE FOUND IN "A" AND "C" UNIT I IN 1993. FEEDWATER NOZZLE STUDY REPORT RECOMMENDS A UT EVERY REfUEllNG STARTING %TTH Ti!E 1993 REFUELING OUTAGE. IF A REPLACEhtENT IS NEEDED TIIEN TIIE CRAFT SilOULD BE INFORhtED OF 'IllE IMPORTANCE OF REDUCING GEOMETRIC DISCONTINUITIEa PERFORM AN MT OF T11E ACCESSIBLE PORTION OF THE NOZZLE AND Ti!E FIRST 3 LNCHES OF IHE EIJ+0W FROM TIIE CUT. REV. 6 REPLACED BY SGRP. Om WELD 1 NEW WEW 75. REV. 7.
, etChanges Sected ley Drawing med Med No NAPSU22 Detaliese Page 17ef'146 Pnnt Date: 11/13 98
Drawing No, Mark No. I ine Number Category item No. Location Record Period Method
~
12050-WhtKS-0102A 2-WFPD-Sit-37 16'-HTPD-424401-Q2 F-C F3.0 RC291 495 0 VT-3 Comments C11AVAR. CllANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 5. ONLY NEED TO EXAMINE I5*.0F SUPPORTS ON UNES REGIVING NDE. 12090-WMKS-nl02A 4311 IF-WFPD-414-601-Q2 C-C C3.20 RC291 498 0 MT Comments 100'. (R-35 NOT SEl.ECTED.) COMMON WITil 4611 4511 IS ON TIIE t*PSTREAM SIDE. CllANGED FROM PERIOD 2 TO PERIOD 0 REV. 7. REUEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 WIIICII ONLY REQUIRES 10*.OF TIIE INTEGRAL ATTACIIMENTS 10 DE EXAktINED. 12090-WMKS-0102 A 4411 16'-WTD-424401-Q2 C-C C3.20 CC291 499 0 h!T Comments 100%(R-35 NOT SELECTED.) COMhlON WITil 4511 4611 IS ON TIIE DOWNSTREAM SIDE. CliANGED FROM PERIOD 2 TO PERIOD 0 REV. 7. REUEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 WillC!! ONLY REQUIRES 10% OF TIIE INTEGRAL ATTACllMENTS TO BE EXAh!INED. 12090-WMKS-0102A 4511 16-WFPD-424401-Q2 C-C C3.20 RC291 500 0 hfT Conaments 100's(R-34 SELECTED FOR PERIOD 3) COMMON WITil 4611. 451IIS TIIE ATTACIIVENT ON TIIE UPSTREAM SIDE. DIFFICULT TO EXAMINE. CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 ALU3W USE OF CODE CASE N-50910 EXAMINE 10% OF Tile INTEGRAL ATTACIIMENTS. 12050-WMKS-0102 A 4611 16'-%TPD-424401-Q2 C-C C3.20 RC291 501 0 MT Comments 100%(R-34 SELECTED FOR PERIOD 3) COMMON WITI! 451L 4611IS TIIE A1TACllMENTON Tile DOWNSTREAM SIDF DIFFICULT TO EXAMINE.CliANGED FROhf PERIOD 3 TO PERIOD 0 IN REY. 7. REUEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 TO EXAMINE 10% OF TIIE INTEGRAL ATTACHMENTS. 12050-WMKS-OlG2 A Soll 16"-WFPD-424-601-Q2 C-C C3.20 7548 0 Comments !!SS-231. SELECTED FOR PERIOD 1 12040-WMKS-0102A Sill 16"-%TFD-424401-Q2 C-C C3.20 7549 0 Comments IISS-232. NOT SELECTED ' 12090-WMKS-0102A 521 16'-WFPD-424401-Q2 C-C C3.20 RC291 506 0 hlT Commems 100*&(!!SS-200 NOT SELECTED) 52J IS COMMON WITIl 5511,6011. AND 6IIL REINFORCING PIATE WAS CUT IN FOUR PIECES BY EDCR 1587G-2. 521IS TIIE CIRCUhtFERENTIAL WELD. EXMINED INT. I PER. 3. CUANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 AUAW USE OF CODE CASE N-509 TO EXAktINE 10% OF TIIE INTEGRAL ATTACll\ TENTS. 12090-WMKS-0102A 53J 16'-WFPD-424-601-Q2 C-C C3.20 RC291 507 0 MT Cocaments 100% 53J IS COMMON WITil 5611,6211, AND 63IL REINFOkC!NG PIATE WAS CLTF IN FOUR PIECES BY EDCR 1587G-2. 531IS TIIE CIRCUMFERENTIALWELD. CIIANGED FROM PERIOD 2 TO PERIOD 0 REV. 7. REUEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 WIIICII ONLY REQUIRES 10% OF THE INTEGRAL ATTACllMENTS IISS-200 NOT SELECTED.TO BE EXA? LINED. 12030-WMKS-0102A 5511 16'-%TPD-424-601-Q2 C-C C3 2* RC291 510 0 MT Comments 100% (IISS-200 NOT SELECTED) COMMON Willi 521,60!!,6IIL REINFORCING PIATE WAS CLT INTO 4 PIECES BY EDCR P1587G-2. 551IIS FIRST INTERIOR WELD LTSTREAM. EXAMINED IN INT. I PER. 3. CilANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-549 FO EXAMINE 10% OF Tile INTEGRAL ATTACIIMENTS. 17050-WMKS-0102A 5611 16*-WFPD-424-601.Q2 C-C C3.20 RC291 511 0 MT Comments 100% COMhf0N WITII 53J. 621L 63 f L REINFORCING PLATE WAS CUF IN 4 PIECES BY EDCR-15870-2. 561I IS TIIE FIRST INTERIOR WELD ON TIIE UPSTREAM SIDE. CILANGED FROM PERIOD 2 TO PERIOD 0 REV. 7. REUEF REQUEST NDE-2I allow USE OF CODE CASE N-509 WillCII ONLY REQUIRES 10% OF TIIE INTEGRAL ATTACIIMENTS TO BE EXAMINED. IISS-202 NOT SELECTED. Summary erEhanges Sorted by Drawing and Mark No,NAPSU22 Database Page 18of 146 Prrar Date: 11// & 98
y I Druntag No. - Mark No. Line Number Caterary item No. Locatiese Receral Period - Metised . 12050-WhtKS-Ol02A 60ll 16*-WFPD-42440142 C-C C3.20 RC291 515.. O. AIT ! Comisments 100% (ItSS-201 NOT SELECTED)COkthtON WITil 523,5511. AND 6III REINFORCING Pl. ATE WAS CITFIN 4 PIECES BY EDCR PI587G-2. 60!!IS Ti!E SECOND INTERIOR VERT: CAL WELD ON TIIE UPSTREAAt SIDE. SEE WFPD-206A SIIEET 2 I OR DETAILS. ClIANGED FRONT PERIOD 2 TO PERIOD 3. IN REV. 3. CIIANGED FROh! PERIOD 310 PERIOD 0 IN REV 7. RELIEF REQUEST NDE-2i ALLOW USE OF CODE CASE N-509 TO EXAhflNE 10% OF TIIE INTEGRAL ATTACithtENTS.. 12050-WhtKS-0102A 6111 16'-WTPD-424-601-Q2 C-C- C3.20 - RC291 516 0. eft C. a:s 100% (IISS-201 NOT SELECTED) COitNION WITil 521,5511. AND 6011. REINFORCING PLATE WAS CUF IN 4 PIECES BY EDCR P!587G-2. 6IIIIS T1tETillRD INTERIOR , i, VERTICAL WEtD ON Tile UPSTREAh! SIDE SEE %TPD-2%A SIIEET 2 FOR DETAILS. ClIANGED FROil PERIOD 2 TO PERIOD 3 IN REV. 3. CIIANGED FROkt PERIOD 3 TO i PERIOD 0 IN REV. 7. REIJEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 TO EXANtINE 10% OF Ti!E INTEGRAL ATTAClikIENTS. 12050-% K!KS4102A 6211 IC-WFPD-424401-Q2 C-C C3.20 RC291 517 0 aft Cosa:mems 100% (11S5-203 NOT SELECTED.) CoitN10N WITl! 531,5611. AND 6311. REINFORCING PAD WAS CITF IN 4 P!ECES BY EDCR-l587G-2. 6211 IS TIIE SECOND INTERIOR WELD FROAl Tile UPSTREAh! SIDE CllANGED FROh! PERIOD 1 TO PERIOD 2 IN REV. 3. CIIANGED FROkt PERIOD 2 TO PERIOD 0 REV. 7. RELIEF REQUEST NDE-2i ALLOW USE OF CODE CASE N-509 WIIIC!! ONLY REQt PRES 10% OF TIIE INTEGRAL ATTACllk!ENTS TO BE EXAht!NED. 12050-WhtKS-0102A 6311 - 16*-%TPD-42440I-Q2 C-C C3.20 RC2*1 518 0 htT Counmients 100% (IISS-203 NOT SELECTED.) COMhtON RTFil 53J,5611. AND 6211 REINFORCING PAD WAS CLTF IN 4 PIECES BY EDCR-15870-2. 6311 IS Ti!E TIIIRD INTERIOR WELD FROkt TIIE LTSTREAh! SIDE. CilANGED FROkt PERIOD I TO PERIOD 2 IN REY. 3. CllANGED FROM PERIOD 2 TO PERIOD 0 REY. 7. RELIEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 WillCII ONLY REQUIRES 10% OF TiiE INTEGRAL ATTACIIk1ENTS TO BE EXAMINED. . l 12050 WhtKS-0102A 6611 IC-%TPD-424401-Q2 C-C C3.20 RC291 519 0 MT-Camimients 100% (511-36 NOT SELECTED) EXAMINED IN INTERVAL I PERIOD 3. CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REY. 7. RELIEF REQUEST NDE-21 AllDW USE OF CODE CASE N-509 TO EXAktINE 10% OF Tite INTEGRAL ATTACllMENTS. 12050-41tKS4102A 75 IC-WFPD-42440 lC-Q2 C-F-2 C5.51 ' RC291 468 0 Connaients REMOVED FROM PERIOD I IN REV. 2. 100% REPLACED BY SGRP. OLD WELD NUMBER I. REV. 7. 12050 41tKS-Ol02A 75 16*-WFFD-424401C-Q2 20 C5.51 RC291 7482 3. UT
- Comiments REPLACED IN 95. PERFORM ITF AFFER 5 YEARS. Perform UT u.-.- am per Angrnented Inspectaan Manual, Attachmmt 20.
120$0-411bl02A 76 16-WFPD-424-601-Q2 C-F-2 C5.51 471 0 1 C a WEPCD OL CllANGED FROM 15 TO 76 AFTER SGRP. REY. 7 12050 %1tKS-0102A 77 16*-RTPD-42440lC-Q2 C-F-2 C5.51 472 0 C. A WEPCB 0 REPLACED BY SGRP OLD WELD 16 REY. t 7. F 12050-WMKS-0102A 78 IC WFPD-424401C-Q2 C-F-2 C5.51 . RC291 473 0 MT A UF l
-F C a 100% CilANGED FROM PERIOD 2 TO PERIOD 0 IN REV. 6. WELD WILL BE REPLACED BY SGRP NOT REQUIRED TO BE EXAMINED IN TIIE PERJOD OF REPLACEMENT.
NEW WELD NUMBER 78 OLD WELD NUMBER 18. REV. 7. i 12050 WMKS-0102A SW-39 16*-WFPD-424401-Q2 C-C ~ C3.20 7550 0 C c. S11-32. NOT SELECTED . I 12090 WMKS-0102A SW-40 16"-%TPD-d40142 C-C b3 20 7551 0 Commments Sil-30. NOT SELECTED t i _ _ y Samt, nary etChanges sortest by Drauslag med Mark New.NAPSU22 Database Page 19 of 146 Prust Dare: 11/1893
Drs=lms No. . Mark New , IJne Number rate 2*r? Itesa No. I,ecaelen . Record Perted Metlied 12050-WhlKS-0102A SW.-41 16'-WFPD-424401-Q2 C-C - C3.20 RC262 - 531 0 MT-Comuments 100% (R-43 NOT SE1 ECTED.). AIAJOR WELD PREP NEEDED. WAITING ON NRC APPROVAL OF CODE CASE N509 TO REDUCE Tile NUhlBER OF C-C EXAMINATION. CllA'iGED FROM PERIOD I TO PERIOD 2 IN REY. 5. CitANGED FROh! PERIOD 2 TO PERIOD 0 REV. 7 REIJEF REQUEST NDE-21 ALIDW USE OF CODE CASE N-509 WHICII -J ONLY REQUIRES 10% OF Tile INTEGRAL ATTACllhlENTS TO BE EXAhlINED. i
- 12090 WhlKS-0102B 1 A(NEW WELD 40) 16tWFPD-423-601C-Q2 20 C5.51 . RC291 - 6675 1 IJF . ,
C. . -= INDICATIONS WERE FOUND IN "A" AND"C" UNIT I IN 1993. FEEDWATER NOZZ.LE STUDY REPORT RECOhlMENDS A UT EVERY REFUELING STARTING %TTil TIIE 1993 RERTLING OUTAGE. i 12090-41tKS-0102B I A(NEW WELD 40) 16*-WFPD-423401C-Q2 C-F-2 C5.51 RC291 540 .I MT A UT l Comanents 100% REPl. ACED BY SGRP. OLD WEW ! NEW WELD , 40. 120$0-WMKS-0102B IA(NEW WELD 40) 16tWFPD-42340lC-Q2 20 C5.51 RC291 7310 . 2 MT(1 D.) > Ceauments INDICATIONS WERE FOUND IN *A" AND "C" L' NIT I IN 1993. FEEDWATER NOZZIA STUDY REPORT RECOMMENDS A UT EVERY REFUELING STARTING WITil Tile 1993 - REFUELING OLTFAGE. IF A REPLACEklENT IS NEEDED TilEN TIIE CRAFT S!!OUW BE INFORMED OF TIIE IMPORTANCE OF REDUCING GEOMETRIC DISCONTINUITIES. PERFORM AN MT OF Tile ACCESSIBLE PORTION OF TIIE NOZZLE AND TIIE FIRST 3 INCIIES OF TtIE ELBOW FROM TIIE CUT REV. 6. REPIACED BY SGRP. OW WELD 1 A
'?
NEW WELD 40. REV. 7. E0'50 %TIK%l02B 3211 16'-WFPD-423401-Q2 C-C C3.20 RC291 551 -0 MT Comuments 100% (Sil-4i NOT SELECTED) EXAhlINED INT. I PER. 3. CllANGED FROh! PERIOD 3 TO PERIOD 0 IN REY. 7. RELIEF REQUEST NDE-21 ALIDW USE OF CODE CASE N-509 TO EXAMINE 10% OF TiiE INTEGRAL ATTACilMENTS. ; 12050-WMKS-0102B 40 16tWFPD-423401C-Q2 20 C5.51 RC291 7481 3 , IJF
-C ./. REPLACED IN 95. PERFORM LTF AFTER 5 YEARS. Perform UT examination pn Augmented Inspection Manual, Attachment 20.
1 120*0-WMI 5-0102B 21 16* WFPD-423401C-Q2 C-F-2 C5.51 535 0 Ceaunents WEPCB() REPLACED BY SGRP OLD NUMBER 13A. REY. 7. 12090-WMKS-0102B 42 16tWFPD-423401C-Q2 C-F-2 C5.51 RC291 536 3 MT/tTF C_ a 100% REPLACED BY SGP OLD WELD 14. REV. 7 120$0-WMKS4102B 43 16'-%TPD-423401C-Q2 C-F-2 C5.51 537 0 > C 2 WEPCB O. REPLACED BY SGRP OLD WElf NUMBER 16. REV. 7. 12050-%"MKS4102B SW-27 16'-WFPD-423401-Q2 C-C C3 20 RC291 559 0 MT C- .c_ 100%(R-41 A NOT SELECTCDJ ATTEMPTED IN 92. WELD PREP NEEDED TO PERFORM EXAM. CHANGED FROM PERIOD 1 TO PERIOD 2 IN REV,5. WAITING ON NRC APPROVAL OF CODE CASE N509 TO REDUCE Tile NUMBER OF C-C EXAMINAITONS. CI1ANGED FROM PERIOD 2 TO PFRIOD 0 REV 7. RELIEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 WIIICll ONLY REQUIRES 10% OF TIIE INTEGRAL ATTACIIMENTS TO BE EXAMINED. 12050-WMKS-0102C I(NEW WELD $7) 16'-%TPD-42240IC-Q2 20 C5.5I RC29I 6676 1 tTF C . IND: CATIONS TERE FOUND IN "A" AND *C" UNIT I IN 1993. FEEDWATER NOZZLE STUDY REPORT RECOMMENDS A LTF EVERY REFUELING STAR 11NG WITH THE 1993 REIUELING OtJFAGE. REPLACED BY SGRP OLD WELD I. 1
-m etChanges sorted by Druwing and Mark No NAPSU22 Detsbane Page 20cf f46 PrmtDare: ff/1893 4
~
m.. ..4 . . , . , , .
, _m , .. _ _ _ _ _ _ _ _ . _ _ - _ _ _ . _ _ . . _ _ _ _ _ . . _ . _ . . _ _ .
Drawing No. ; Most No. IJnc Numiher - Category teesn No. Location Record Per'el Method 120$0-WhtKS 0102C 1 (NEW WELD $7) 16'-WFPD-422401C-Q2 20- C5.5I RC291 7309 2 MT(1.D) C. = INDICATIONS WERE FOUND IN "A" AND "C" UNIT I LN 1993. FEEDWATER NOZZLE STUDY REPORT RECOkth! ENDS A UT EVERY REFUELING STARTING %TFIl Tite 1993 REFUELING OUTAGE. IF A REPLACEkIENT IS NEEDED TIIEN TIIE CRAFT Silot 'l D BE INFORhtED OF Tile IEIPORTANCE OF REDUCING GEOklETRIC DISCONTINUITIES. PERFORht AN eft OF Tile ACCESSIBLE PORTION OF TIIE NOZZLE AND TIIE FIRST 3 INCllES OF Tile ELBOW FROkt TIIE CUF. REV. 6. " REPLACED BY SGRP. REY.7. 12050 WklKS4IO2C ' 3 811 16*-WFPD-422-601-Q2 C-C C3.20 RC291 582 0 kit -. Comuments 100*6(R-40 NOT SELECTED) PRESERYlCE EXAkilNATION. Cil ANGED FROkt PFRIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509
- TO EXAk11NE 10*6 OF Tile INTEGRAL ATTACllk!ENTS.
CC C3.20 RC291 583 0 . StT I
- 12050-WhtKS-0102C 3911 I&-WFPD-422401-Q2 Comuments 100*6(R-40 NOT SELECTED) PRESERVICE EXAhllNATION. CII ANGED FROkt PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE 21 ALIJDW USE OF CODE CASE N-509 TG EXAMINE 10*6 OF Tile INTEGRAL ATTACllktENTS.
12050-Wh!KS-CIO2C - 4011 16"-WFPD-422401-Q2 C-C C3.20 7552 0-Comuments llSS-234. NOT SELECTED I2050-WhlKS-0102C 4Ill 16"-WFPIM22401-Q2 C-C C3 20 7553 0 C- = 115S-233. NOT SELECTED L 12050-WhtKS-0102C 423 16"-WFPD-422-601-Q2 C-C C3.20 7554 0 O. a 115S-210. NOT SELECTED 12050-Wh!KS-Ot02C 4411 16"-WFPIM22401-Q2 C-C C3.20 7555 0 ; C -. IIFS-210. NOT SELECTED C-C C3.20 7556 0 ~i 12050 WhlKS4I02C 4411 16" WFPD-422401-Q2 t i Commernes IISS-211. SELECTED FOR PERIOD 3 I2050-WhlKS4102C - 4511 16" WFPD-4224014)2 C-C C3.20 7557 0 Comuments IISS-211. SELECTED FOR PERIOD 3 12050-WitKS4102C 57 I&-WFPD-422401C-Q2 C-F-2 C5.51 RC291 560 0 C .c.- REktOVED FROkt PERIOD 1 IN REV. 2.100*k REPLACED BY SGRP OLD WELD 1. REV. 7.
!2050-WhtKS4102C 57 le-WFPIM22-601C-Q2 20 C5.51 RC291 7480 3 . tTF Comuments REPLACED IN 95. PERFORM UF AFTER 5 YEARS. PerformITF exammahan per Augmented Inspection klanual. Attach:nent 20.
12050-WMKS4102C 58 IC-WFPD-422-601C-Q2 C-F-2 C5 51 RC291 567 0 Comumenes REktOVED FROkt PERIOD 3 IN REV. 2. 100*k REPLACED BY SGRP OLD WELD 19. REV. 7. 12050-WhtKS4102C 59 IC-WFPD-422-60lC-Q2 C-F-2 C5.51 566 0 C a WEPCB 0. REPLACED BY SGRP. OLD WELD 18. REV. 7. e
-y of Changes Sorted ley Drewlms and Mark No, NAPStJ22 Database Page 21 of 146 Pnnt Dare: 11/1898
Dnning No. hlark No. IJne Numtwr Category leem No- location Record Period hiethod 12050-WhtKS-Ol02C 60 IC %TPD-422401C-Q2 C-F-2 C5.51 RC291 565 3 EfTATT Ceaunents 100*u REPLACE D 11Y SGRP. OLD WEI D 16A New uith Rev. II: Added "C" to line number to be in agreement mth drawing. 120$0-WhlKS-0102C SW-3 5 16"-WFPD-422401-Q2 C-C C3.20 7558 0 Commenes Sit-38 SEl.ECTED FOR PERIOD 2. 12050-WhtKS-0102C SW-36 16'-%TPD-422401-Q2 C-C C3.20 RC291 599 0 aft Comments 100*. (R-38A NOT SELECTED ). ATTEkiPTED IN 92. ADDITIONAL WEID FREP IS NEEDED TO PERFORh! EXAkt CllANGED FROh! PERIOD I TO PERIOD 2 IN REV. 5. WAITING ON NRC APPROVAL ON CODE C ASE N509 TO REDUCE TlIE NUhtBER Ol' C-C EXAktIN AITONS. CIIANGED FROh! PERIOD 2 TO PERIOD 0 REV. 7. RELIEF REQUEST NDE-21 allow USE OF CODE CASE N-509 WilICII ONLY REQUIRES 10*a OF Tile INTEGRAL ATTACithfENTS TO BE EXAktINED.
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12050-WhtKS4102D 16 (BPL 251) 6'-%TPD-415401 8 NA SB 7211 1 RT/hfT Comments EXAMINE EVERY 40 htONTilS: 33*.OF All SELECTFD WEIDS WITII 100*s OF ALL WELDS COktPLETED BY END INTERVAL Changed line size and number from 16" to 6" with Rev. I1, Interval 2. to the Plan. 12050-WhtKS-0102D 16 (BPL 251) 6-%TPD-415-601 8 NA SB 6618 I RT!MT Comments EXAhtINE EVERY 40 h!ONTils. 33*.OF A!15 ELECT ED WELDS, WITII 100*.OF ALL WELDS COhtPLETED BY END INTERVAL PERFoldhi aft /RT IF RTIS AVAILABLE. IF NO RT IS AVAILABI.E IllEN DEFER TILL NEXT OUTAGE AND PERIORh! hlTVF ON BPL 195. REhlOVED FROh! AUGhtENTED PROGRAh!!N REV. 8. RECORD Will REh!AIN IN PLAN TO SilOW EXAhlINATION 111 STORY. Changed line size and number from 16* to 6' with Rev. I I to the Plan. 12050-WMKS-0102D 27(llPL 551) 6*-%TPD-419401 8 SB 6627 2 RT/hfT Comments EXAMINE ENTRY 40 htONT!il 33*.0F ALL SELECTED WELDS WITil 100*& OF ALL WELDS COh!PLETED BY END INTERVAL CIIANGED FROh! PERIOD 3 TO PERIOD 2 IN REY. 6. REPIACING IIEADER BRANCil CONNECTION. WAii1NG ON UFSAR CllANGE TO BE SUBMITTED TO ALLCW SURFACE EXAhflNATION TO I1E REMOVED FROM AUGh!ENTED PROGRAM IN REV. 8. RECORD WIII REh! AIN IN PLAN TO SilOW EXAktINATION It! STORY. SUBSTITUTED FOR VOLUhfETRIC. 120$0-WMKS-0102D 5 (BPL 851) 6-%TPD-4 t l401 8 NA SB 6625 1 UTikfT Comments EXAMINE EVERY 40 htONTilS: 33*.0F AIL SELFCTED WELDS WITil 100's OF ALL WELDS COktPLETED BY END INTERVAL 12050-WMKS-0102D 5 (BPL 851) 6-WFPD-411401 8 NA SB 6636 I RT/hfT Comments EXAhtINE EVERY 40 MONTils. 33*.0F A!1 SELECTED WELDS, WITIl 100*40F ALL WELDS COMPLETED BY END INTERVAL PERFORht hfT/RT IF RT IS AVAILABE. IF NO RT AVAILABLE DEFER TILL NEXT OUTAGE '
- PERFORh! aft,UT ON BPL 178 REMOVED FROM AUGMENTED PROGRAM IN REV. 8. RECORD WILL REMAIN IN PLAN TO SilOW EXAhlINAT10N IllsTORY.
12090 WMKS-0102D SW-12u (BPL 882) 6-Wh o-4 la-901 8 SB 6641 2 RT/hfT Commento EXAMINE EVERY 40 MONTilS: 33*.0F ALL SELECTED WELDS WITII 100*sOF ALL WELDS COMPLETED BY END INTERVAL REMOVED FROM AUGMENTED PROGRAhiIN REV 8. RECORD WILL REhtAIN IN PIAN TO SilOW EXMtINATION IIISTORY. I:050-WMK4)l02D SW-127 (BPL 582) 6-WFPD-418-901 8 SB 6611 3 MT/UT Coenments EXAMINE EVERY 40 MONTilS: 33*.0F ALL SELECTED WELDS, WITII 100*a OF ALL WELDS COMPIEa LD BY END INTERVAL REMOVED IN REV. 8. ADDED BACK IN INTERIM ClLANGE 96-04. WAITING ON NRC APPROVAL BEFORE REMOVING FROM PLAN. New uith Rev. II to the plan: Changed par from 1998 to 1999. 12090-WMKS-0102D SW-128 (BPL 282) 6'-WFPD-414-901 8 SB 7212 I RT/MT Commento EXAMINE EVERY 40 MONTilS: 33*.OF All SELECTED WELDS, WITil 100*& OF AIL WEIDS COMPLETED BY END INTERVAL Changed line number to 6*-%TPD 4I4-901 with Rev. I1. Interval 2 Plan. Summary of Osages Sorted by Drawing and hlark No NAPSU22 Database Page 22 of 146 Pn=r Date: 11/18 93
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Drawing Na- Mark No. IJne Nu nher Category Item No. location Record Period Method 12050-WhlKS-OiO2i'5
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SW-128 (BPL 282) 6* WFPl$)l4-901 b~ SB 6622 I RT/MT Comments EXAMINE EVERY 40 MONTilS: 33*6 OF ALL SElJCTED WELDS WITil 100*.01' ALL WELDS COMPLETED BY END INTERVAL REMOVED FROM AUGMENTED PROGRAM IN R EY. 8. RE CORD WILL REM AIN IN PLAN 10 SIlOW EXAMINATION !!! STORY Changed line number to 6*-WFPD-414-901 from 16"-%TPD-414-901 with Rev. II to the Plan 12050 WMKSTOIO25 SW-129 (BPL 325) 16' WTPD407-901 8 NA SB 6623 3 KfT Conunents EXAMINE EVERY 40 MONTilS: 33*.0F All SELECTED WELDS, WITil 100*.0F ALL WELDS COMPLETED BY END INTERVAL MOVED FROM PERIOD 2 TO PERIOD 3 IN REY. 6. WAITING ON UFSAR CIIANGE TO BE SUBMITTED TO ALLOW SURFACE EXAMINATION. REhf0VED IN REV. 8. ADDED BACK IN INTERIM CllANGE 96-04. WAITING ON NRC APPROVAL BEFORE REMOVING FROM Pl.AN. New with Rev.1I to the Plan: Using the LTSAR 3C.2.7.1 coupled with the Relief Request NDE-7 for Code exammations, and the design geometry of this ucid, i c., reinforcing plate wekt to pipe, which covers the actual twanch connection piping ueld it has been determined that the most etTective examination method is a surface cumination of the reinfarcing plate welds. 12050-WMKS-0102 D SW-130 (BPL 325) IF-WFPD407-901 8 NA SB 7213 3 MT Comments ELt\ TINE EVERY 40 MONTilS: 33*.OF ALL SELECTED WELDS. WITil 100*iOF All WELDS COMPLETED BY END INl ERVAL CllANGED FROM PERIOD 2 TO PERIOD 3 IN KEV. 6. WAITING ON UFSAR Clif.NGE TO DE SUBMITTED TO ALLOW SURFACE EXAMINATION TO BE SUBSTITirTED REMOVED IN REV. 8. ADDTD BACK IN INTERIhl CIIANGE 96-04 WAlTING ON NRC APPROVAL HITORE REMOVING FROM PLAN. New with Rev. II to the Plan: Using the LTSAR 3C.2.7.1 coupled with the Relief Request NDE-7 for Code exarninations, and the design geometry of this weld, i e., reinforcing plate weld to pipe, which covers the actual branch connection piping weld 11 has been determined that the most efTective cumination method is a surface examination of the rtinforcing plate welds. 12050-WMKS-0102D SW-131 (BPL 225) I&-WFPD-412-901 8 NA SB 6616 3 MT Commenta EXAhlINE EVERY 40 MONTIIS: 33*.0F Al L SE1 ECT ED WELDS, WITil 100*.0F ALL WELDS COMPLETED BY END INTERVAL CIIANGED FROM PERIOD 2 TO PERIOD 3 IN REV. 6. WALLING ON UFSAR CIIANGE TO BE SUBMITTED TO ALLOW SURFACE EXAMINATION TO BE SUBSTITUTED. REMOVED IN REV. 8. ADDED BACK IN INTERIM CIIANGE 96-04. WAITING ON NRC APPROVAL Bfl' ORE REMOVING FROM NtN. New with Rev. II to the Plan: Using the UFSAR 3C.2.7.1 coupled with the Relief Request NDE-7 for Code cuminations, and the design geometry of this weld. i c., reinforcing plate weld to pipe, which covers the actual branch connection piping weld It has been determined that the most effective examination methat is a surface examination of the remforcing plate welds. Changed year to 1999 from 1998. 120N-WMKS-0102D SW-132 (BPL 225) 1&-WFPD-412 901 8 NA SB 7216 3 MT Comments ELLMINE EVERY 40 MONTilS: 33*4 OF ALL SELECTED WELDS, WIT 11100's OF ALL WELDS COMPLETED BY END INTERVAL CIIANGED FROM PERIOD 2 TO PERIOD 3 IN REY. 6. W AITING ON UFSAR Cil ANGE TO BE SUBMITI ED TO AllOV! SURFACE EXAMINATION TO BE SUBSTFIUTED. REMOVED IN REV. 8. ADDED BACK IN INTERIM CilANGE 96-04. WAITING ON NRC APPROVAL BEFORE REMOVING FROM PLAN. New with Rev.1I to the Plan: Using the UFSAR 3C.2.7.1 coupled with the Relief Request NDE-7 for Code cuminations, and the design geometry of this weld, i e., reinforcing plate weld to pipe, which covers the actual branch connection piping weld. It has been determined that the most effective eummation method is a surface examination of the reinfercing plate welds. Changed year to 1999 from 1998. 1550-WMKS-0102D SW-133 (BPL 230) 16*-WFPD-408-901 8 NA SB 6611 3 MT Comments EXAMINE EVERY 40 MONTilS: 33*.0F ALL SELECTED WELDS, WITil 100*6 OF ALL WELDS COMPLETED BY END INTERVAL MO\ ED FROM PERIOD 1 TO PERIOD 3 REPLACED BY BPL 787. DEFERING BPL 225 TO PERIOD 3 TO SEE Tile RESULTS OF TYPE I STUDY ON Tile NEED TO EXAMINE BPL 225. INTFRIM CII ANGE 93-03 REMOVED IN REV. 8. ADDED BACK IN INTERIM CIlANGE 96-04. WAITING ON NRC APPROVAL BEFORE REMOVING FROM PIAN. New with Rev.1I to the Plan: Using the LTSAR 3C.2.7.I coup led with the Relief 4 uest 4 NDE-7 for Code exammations, and the design geometry of this weld, i e., reinforemg plate weld to pipe, uhich covers the actual branch connection piping weld. It has been determined that the most efTective enmination method is a surface examination of the reinforcing plate welds Changed year from 1998 to 1999. 12050 WMKS-0102D SW-134 (BPL 230) 16*-WFPD-408-901 8 NA SB 7217 3 MT Comments EXAMINE EVERY 40 MONTilS: 33*4 OF ALL SELECTED WELDS. WITil 100*.0F ALL WELDS COMPLETED BY END INTERVAL MOVED FROM PERIOD I TO PERIOD 3 REPLACED BY BPL 787. DEFERING BPL 225 TO PERIOD 3 TO SEE TIIE RESULTS OF T)TE I STUDY ON TIIE NEED TO EXAMINE BPL 225. INTERIM CHANGE 93-03 REMOVED IN REV. 8. ADDED BACK IN INTERIM CllANGE 96-04. WAITING ON NRC APPROVAL SEFORE REMOVING FROM PLAN. New with Rev.1I to the Plan: Using the UFSAR 3C.2.7.1 coupled with the Relief Request NDE-7 for Code examinations, and the design geometry of this weld, i.e., reinforcing plate weld to pipe, which covers the actual branch connection piping weld it has been determined that the most effective examination method is a surface examination of the reinforcing plate welds Changed year from 1998 to 1999. 12050-WMKS-0102D SW-19 (BPL 178) 6'-%TPIM15 601 8 NA SB 7210 1 UrafT Comments EXAMINE EVERY 40 MONTilS. 33*.0F ALL SELECTED WELDS, WITil 100*.0F ALL % ELDS COMPLETED BY END INTERVAL CII,tNGED MARK Nt%!BER AND DRAWING NUMBER IN REV. 5. Changed line number to 6" WFPD415-601 from 16*-WFPD4IL60I with Rev i1, Interval 2, to the Plan Sammmars of Ganges Setted by Drawing and Mark No., NAPSU22 Database Page JJ of l#6 Pnnt Date: IF18 98
Drawing No- Mark No. IJne Numher _ Category item No. Iocerion Record Period Method 12050-WhlKS-0102D SW-19 (WL 178) 6'-WFPD-415-601 8 NA SB 66 ' I UT/ HIT Comments EXMIINE EVERY 40 AIONFilS: 33% OF ALL SELEC1ED WELDS. WITII 100*.0F ALL WELDS COMPLETFD BY ENDINTERVAL CP W AIARK NUhlBER AND DRAWING NUhlBER IN REV 5 REMOVED IROM AUGMENTED PROGRAh! IN REV. 8. RECORD WILL REMAIN IN PLAN TO SilOW EXAMINAl' .RY. Changed line number to 6"- WFPD-41540i from 16%TPD-41340I uith Rev.1I to the Plan 12030-WMKS-0102D SW205kB3 473) F-WFPD-419401 8 NA SB 7213 2 LTF/MT Comments EXAMINE EVERY 40 MONIIIS: 33*.OF ALL SELECTED WELDS, WI fil 100*6 OF ALL WELDS COMPLETED BY END INTERVAL CHANGED FROh! PERIOD 3 TO PERIOD 2 IN REV. 6. REPLACING llEADER BRANCll CONNECTIONS. WAITING ON UFSAR CIIANGE TO BE SUBMflTED TO ALLOW SUBSTITUTION OF SURFACE REMOVED FROM AUGMENTED PROGRAM IN REV. 8. RECORD Will REM AIN IN PLAN TO SilOW EXAMINATION IIISTORY. EXAMINATION FOR VOLUMETRIC. Changed line number to 6"-WFPD-419-601 from 16*-%TPD-41746I uith Rev. I I to the Plan. 12050-WMKS-0102D SW-8 (BPL 763) 6*-WFPD-4 II40I 8 NA SB 6632 I UT/MT Comments EXAMINE EVERY 40 MONTilS: 33*4 OF ALL SELECTED WELDS, WITil 100*6 OF ALL WELDS COMPI.ETED BY END INTERVAL REMOVED FROM AUGMENTED PROGRAM IN REY. 8. RECORD WILL REMAIN IN PLAN TO SIIOW EXAhrINATION IIISTORY. Changed line number to 6"-WFPD-4II401 from 16"-WFPD-409401 with Rev,1I to the Plan. 11050-WMKS-0102D SW-8 (UPL 763) 6'-WFPD-411401 8 NA SB 7214 2 LTF/MT Comments EXAMINE EVERY 40 MONTHS: 33*4OF ALL SELECTED WELDS WITII 100% OF ALL WELDS COMPLETED BY END INTERVAL REMOVED FROM AUGMENFED PROGRAM IN REV. 8. RECORD WILL REhl AIN IN PLAN TO SIIOW EXAMINATION IllSTORY. Changed line number to 6"-WFPIblI5401 from 16* WFPD-413401 with Rev. II to the Pfart 12050-WMKS-0102E-1 2-WCMU-R-30 6-WCMU-418-151-Q3 F-B F2.0 AFPII 605 0 VT-3 Comments AllARES, EXAMINED IN 90 NRI CHANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 5. SUPPORT NOT ON A LINE SUIUECT TO ANOTIIER TYPE OF EXAMINATION. 12050-WhlKS-0102E-2 2-WCh!U-R-27 6'-WCMU-412-151-Q3 F-B FI O 156 0 Comments B11AGUD2 CIIANGED FROM NONCLASS TO CLASS 3 CREDIT LEFT BLANK FOR POPULATION LISTING REV. 7. EXAMINED IN 95 AS AUGMENTED. NO SECTION XI CREDIT TAKEN. 12090-WMKS-0102F-I 1611 3'-WAPD-409401-Q3 D-B D2.20 AFPH 616 3 \T-3 Comments 100%(2-WAPD-A-16 SELECTED FOR PERIOD 3). CilANGED ITEM NUMBER TO AGREE WITH PRESSURE TESTING PROGRAM IN REV. 8. New with Rev. II to plan: Changed line No. from 3* WAPD-410-601-Q3 to 3* WAPD-409401-Q3 to agree with drawing. 12050-WMKS-OI02F-1 2-WAPD- A-16 3'-WAPD-40940l-Q3 F-A Fl .0 AFPli 621 3 \T-3 Comments B flAANC EXAMINE INTEGRAL ATTACHMENT 16I1. New with Rev. II to plan: Changed line No. from 3*-WAPD-410401-Q3 to 3*-WAPD-409-601-Q3 to agree with drawing 12090 WMKS4102F-1 2-WAPD-R-10 6-WAPD-402401-Q3 F-A FI O AFPH 622 3 VT-3 Comments BilAGUD2. New with Rev.1I to the plan: Scheduled in Period 3 due to reevaluation of the Class 3 total support population. 12050 WMKS-0102F-1 2-WAPD-R-2 I 3'-WAPD-439401-Q3 F-A Fl.0 630 3 \T-3 Cenuments B11AGUD2. New with Rev.1I to the plan: Scheduled in Period 3 due to reevaluation of the Class 3 total support population. 12090-WMKS-0102F-1 2-WAPD-R-9 3'-WAPD-413-601-Q3 F-A FI.0 AFPil 634 3 Vf-3 Comments B1tAGUD2. New with Rev.1 I to the plan- Scheduled in Period 3 due to reevaluation of the Class 3 total support population. 12050-WMKS-0102F-I 2011 6-WAPD-401401-Q3 D-B D2.20 AFPH 617 0 VF-3 Conunents 100*6(R-15B NOT SELECTED). Cl!ANGED FROM PERIOD 3 TO PERIOD 0 IN REY. 7. RE1JEF REQUEST NDE-2I ALLOW USE OF CODE CASE N-509 TO EXAMINE 10*6 OF THE INTEGRAL ATTACHMENTS. CllANGED ITEM NUMBER TO AGREE VTril PRESSURE TES1TNG PROGRAM IN REV. 8
%ssenary of Ganges Sorted by Drawing and Mark No., NAPSU22 Database Page 24 of 146 Pnnt Dare.- I//1893
Droming Na Mark No. . I.ine Nwnher Csee Iteam Na lecesien Record Pesied Meelmed 12050-WhlES-Ol02F-1 2411 6*-WAPD402-601-Q3 D-B D2.20 AFPil 618 2 \T-3 __. Casemienes 100%(R-1SA NOT SELECTED.) CIIANGED ITEh! Nt'MBER TO AGREE WIT 11 PRESSURE TESTING PROGRAM IN RTV. 8 12050-WMKS4102F-1 3311 - 3'-WAPD413 601-Q3 D-B D2.20 AFPit 635 i VI-3 Ceauments 100*. A-11 NOT SELECTED CllANGED ITEM NUh!BER TO AGREE %TTil PRESSURE TESTING PROGRAM IN REV. 8. IM90-Wh!KS4102F-t 3611 3* WAPD412-601-Q3 D-B D2.20 AFPli 636: 2 \T-3 C -.=- 100*. A-14 NOT SELECTED. ClIANGED ITEM NUhlBER TO AGREE %TFli PRESSURE TESTING PROGRAh! IN REV. 8. 12050-Wh!KS-0102F-10 37J I*-WAPD423-151-Q3 D-B D2.20 AFril 7372 3 \T-3 ADDED IN REVA I.'O SIZE EXEMPTION FOR ALN FEEDWATER LINES. (A4231 SELECTED FOR PERIOD 3) Ciln GED ITEM NUMBER TO AGREE %7Til PRESSURE TT. STING
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.C . PROGRAM IN #EV. 8. 12050-%1tKS-0102F-10 A-123-1 l'-WAPD423-151-Q3 F-A Fl.0 AFPfl 7371 3 \T-3 C a ADDED IN REY.6 NO SIZE EXEh!PT10N FOR AUX FEEDWATER LINES. 12050-WMKS-0102F-10 R-423-2 1* WAPD423-151-Q3 F-B fio AFPII 7373 0 C = ADDED IN REV.6. NO SIZE EXEMPTION FOR At'X FEEDWATER LINES. 12050.%3tKS-0102F-10 R423-3 I*-WAPD423-151-Q3 F-B F2.0 AFPli 7374 0 Ceaunents ADDED IN REV. 6. NO SIZE EXEMPTION FOR AUX FTEDWATER LINES. 12090-% MKS-0102F-10 ' R-431-1 l*-WAPD424-151-Q3 F-B F2.0 AFPII 7369 0 C . ADDED IN REY 6. NO SIZE EXEMPTION FOR AUX FEEDWATER LINES. 12050-%1tKS4102F-Il 2411 l'-WAPIM24-151-Q3 D-B D2.20 AFPII 7370 0 C .c. ADDED IN REY. 6. NO SIZE EXEMPTION FOR AUX FEEDWATER UNES. (A-424-ISELECTED FOR PERIOD 3) CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 TO EXAMINE 10*.OF THE INTFiiRAL ATTACilMFNFS. CIIANGED ITEM NUMBER TO AGREE WITH PRESSURE TESTING PROGRAM IN REV. 8. 13050-WMKS-0102F-11 A-424-1 I*-WAPD424-151-Q3 F-A Fl.0 AFPH 7366 3 \T-3 C = ADDED IN REV. 6. NO SIZE EXEMPTION FOR AUX FEEDWATER LINF1 12090-%1tKS-0102F-il R-424-2 1* WAPD-424-151-Q3 F-B F2.0 AFPli 7367 0 C -.:_ ADDED IN REV. 6. NO SIZE EXEMPTION FOR AUX FEEDWATER llNES. 12050-WMKS-Ol02F-Il R-424-3 1*-WAPD424-151-Q3 F-B F2.0 AFPli 7368 0 C - . -- ADDED IN REV. 6. NO SIZE EXEMPTION FOR AUX FEEDWATER UNES. 12050-%11KS-0102F-Il R430-1 1*-WAPD-430-151-Q3 F-B F2.0 AFPII 7365 0 C a ADDED IN REY. 6. CilANGED TIIE CLASS CODING FOR TIIE Full FIDW TEST LINE FROM NONCLASS TO CLASS 3. W etChanges Sorted by Draulng and Mark No NAPSU22 Deennese Page 25of f46 PnntDate: 11/18 98
Drawing No. Mark No. Line Number Caterary item No. Im ation Record Period Mettned 120$0-WMKS-0102F-12 R-1006 6'-WAPD-451-601-Q3 F-B F2.0 AFPil 7337 0 Commeents ADDED IN REY. 6. At W FEEDWATER LINES LESS TIIAN 4* AR E NOT EXEMPT. Cll ANGED DRAWING FRONI 215I A TO 102F-I2., EXAMINED IN 90 NRI
~
12030-WitKS-0IC2F-12 R-1007 6'-WAPD-451-601-Q3 F-B F2.0 ' AFPil 7338 0 Comments ADDED IN REV. 6. AUX FE EDWATER LINES LESS TIIAN 4* ARE NOT EXEMPT. CIIANGED DRAWING FROM 2451 A TO 102F 12., EXAMINED IN 90 NRI 12050 WMKS-0102F-12 R-I008 6'-WAPD-45 I-601-Q3 F-B F2.0 AFPII 7339 0 Comments ADDED IN REV. 6. AUX FEEDWATER UNES LESS TIIAN 4* ARE NOT EXEAIPT. CllANGED DRAWING FROM 2451 A TO 102F-12., EXAMINED IN 90 NRI 12050-WMKS 0102F-13 R-IOOI 4'-WAPD-452-601-Q3 F-B F2.0 AFPil 7340 0 Coenments ADDED IN REY. 6. AUX FEEDWATER LINES LESc. TIIAN 4* ARE NOT EXEMPT. CIIANGED DRAWING FROh! 2452A TO 102F-12. 12050 WMKS-0102F-13 R-1002 4'-WAPD-452-601-Q3 F-B F2.0 AFPil 7341 0 Comunents ADDED IN REV. 6. AUX FEEDWATER LINES LESS TilAN 4* ARE NOT EXEMPT. CilANGED DRAWING FROM 2452A TO 102F-12. 12050-WMKS0102F-13 R-1003 4' WAPD-453-601-Q3 F-B F2.0 AFPil 7342 0 Comments ADDED IN REV. 6. AUX FFEDWATER LINES LESS TIIAN 4* ARE NOT EXEMPT. CIIANGED DRAWING FROM 2452A TO 102F-12. 12050 W".lKS4107F-13 R-1004 4'-WAPD-453-601-Q3 F-B F2.0 AFPII 7343 0 Comments ADDED IN REV. 6. AUX I'EEDWATER UNES LESS TIIAN 4* ARE NOT EXEMPT. CIIANGED DRAWING FROM 2452A TO 102F-12. 120$0-WMKS4102F-13 R-1005 4*-WAPD-453-601-Q3 F-B F2.0 AFPII 7344 0 Comments ADDED IN REV. 6. AUX FEEDWATER UNES LESS TilAN 4* ARE NOT EXEMPT. CllANGED DRAWING FROM 2452A TO 102F-12. 12090 WMKS-0102F-2 2tJ 6'-WAPD-401-(01-Q3 D-B D2.20 AFPII 637 0 VT-3 Comments 100%(A-19 NOT SELECTED). CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 7. REUEF REQUEST NDE-2i AllJDW USE OF CODE CASE N-509 TO EXAMINE 10% OF TIIE INTEGRAL ATTACIIMENTS. CilANGED ITEM NUMBER TO AGREE WITil PRESSURE TESTING PROGRAM IN REV. 8. 12050-WMKS-0102F-3 39J 6'-WAPD 402-601-Q3 D-B D2.20 ~ AFPH 645 2 \T-3 Conunents 100% A-26 NOT SELECTED. CilANGED ITEM NUMBER TO AGREE WITII PRESSURE TESTING PROGRAM IN REV. 8. 12050-WMKS-0102F-5 2-WAPD-R-24 6'-WAPD-403-601-Q3 F-A F10 AFPli 647 0 VF-3 Comments IlllAGUD2 CIIANGED FROM PERIOD 3 TO PERIOP O IN REV. 5. SUPPORT NOT ON A UNE SUBJECT TO ANOTTIER TYPE OF EXAMINATION. 12050-WMKS-0102F-6 2811 l'-WAPD-432-151-Q3 D-B D2.20 7559 0 :. Comments A-432-2 NOT SELECTED. CIIANGED ITEM NUMBER TO AGREE WITII PRESSURE TESTING PROGPAM IN REV. 8. 12050-WMKS-0102F-6 A-432-2 l*-WAPD-432-IS I-Q3 F-A Fl.0 AFPil 7390 0 Comments ADDED IN REV. 6. NO SIZE EXEMPTION FOR AUX FEEDWATER UNES. 12050 WMKS-0102F-6 R-415-1 l'-WAPD-415-ISI-Q3 F-B F2.0 Af?II 7388 0 - Comments ADDED IN REV. 6. NO SIZE EXEMITION FOR AUX FEEDWATER LINES. Summary ordianges sorted by Drawing and Mart No NAPSU22 Database Page 26of N6 Pnnr Date: 11/18 93 y-__-
n a. Drening No. Mark No. I.ine NamIwr .. . Cseegory iteen No. leession . Record Perled - Meesime 12050-WhlKS-0102F-6 R-418-1 ItWAPIM18-151-Q3 F-B . F2.0 .AFFH 7383~ 0 Ceausients ADDED IN REV.6.. NO SIZE EXEntPTION FOR AtN FEEDWATER UNES. . 120$0-WhlKS-0102F-6 R-418-2 l'-WAPD418-151-Q3 . F-B F2.0 AFPH .7384 _0 Ceausnees ADDED IN REV.6. NO SIZE FXEMPTION FOR AUX FEEDWATER UNES. 12050-Whf KS-0102F-6 R-418-3 - l*-WAPD-418-151-Q3 F-B ' F2.0 AFPH 7385 0 C t ADDED IN REV 6. NO SIZE EXF.hlPTION FOR AUX FEEDWATER UNES. 12050 WhlKS-0102F-6 R-4184 l'-WAPIM18-151-Q3 F-B ' F2.0 AFPil -7386 0. C. t ADDED IN REV.6. NO SIZE EXEhlPTION FOR AUX FEEDWATER UNES. 12050-WhlKS-0102F-6 . R-418-5 1*-WAPIM 18-151-Q3 F-B F2.0 AFPli 7387 0 Comunents ADDED IN REV 6. NO SIZE EXEhlPTION FOR ALW FEEDWATER UNES. 12050-WhlKS-0102F-6 R-432-1 ItWAPIM32-151-Q3 T-B F2.0 AFPII 7389 0 C.. _.:s ADDED IN REY. 6. NO SIZE EXEMPTION FOR AUX FEEDWATER UNES. 12050-WhlKS-0102F-7 R-416-1 l'-WAPD-416-151-Q3 F-B F2.0 AFPII 7382 0 Cesnaients ADDED IN REV. 6. NO SIZE EXEh!PTION FOR AUX FEEDW ATER UNES. ' 12050-%1tKS 0102F-7 R-420-1 l'-WAPD-420-151-Q3 F-B F2.0 AFPIl 7379 0 Comsnents ADDED IN REV. 6. NO SIZE EXEh!PTION FOR AUX FEEDWATER UNES. 12050-Wh!KS-0102F-7 R-420-2 ItWAPD-420-151-Q3 F-B F2.0 AFPli 7380 0 C. ;. ADDED IN REV.6. NO SIZE EXEh!PTION FOR AUX FEEDWATER UNES. 12050-WhlKS-0102F-7 R-420-3 ItWAPD-420-151-Q3 F-B F2.0 AFPH 7381 0 Comunents ADDED IN REV. 6. NO SIZE EXEMPTION FOR AUX FEEDWATER UNES. 12050-WMKS-0102F-8 R-417-1 ItWAPD-417-151-Q3 F-B F2.0 AFPII 7378 0 C ;/.: ADDED IN REV. 6. NO SIZE EXEMPTION FOR AUX FEEDWATER UNES-12090-WMKS-0102F-8 R-421-1 l'-WAPD-421-151-Q3 F-B F2.0 AFPil 7375 0 Comunents ADDED IN REY. 6. NO SIZE EXEMPTION FOR AUX FEEDWATER UNES. 1205051KS-0102F-8 R-421-2 l'-WAPIM21-151-Q3 F-B F2.0 AFPII 7376 0 Conunents ADDED IN REV. 6. NO SIZE EXEhiPTION FOR AUX FEEDWATER LINES. 12090-WMKS-0102F-8 R-421-3 l'-WAPD-421-151-Q3 F-B F2.0 AFPli 7377 0 Conenents ADDED IN REV. 6. NO SIZE EXEMPTION FOR AUX FEEDWATER LINES. Samenery of Onsages Sorted by Drening and Mark No NAPSU22 Database Page 27of 146 Prrst Date: 11/18 98
~
-_ =_
IW New Mark No. 13ne Number Category item No. Iecation Record Perbi ' MetInd . I 12050-WMKS-Ol02F-9 R-419-1 2' WAPD-419-151-Q3 F-B F2.0 M Pil 7336 0 Ceaunents ADDED IN REY. 6. AUX !TEDWATFR IJNES LESS TilAN 4* ARE NOT EXEMPT. CIIANGED DRAWING FROh! 2419A TO 102F-9. 12050-WMKS4102F-9 R-419-2 2'-WAPD-419-151-Q3 F-B F2.0 AFPil 7335 .0 i Comunents ADDED IN REY. 6. AUX FEEDWATER I.INES LESS TIIAN 4 ARE NOT EXEMPT. CIIANGED DRAWING FROM 2419A TO 102F-9. 12090-WhlKS-0102F-9 R-419-3 2*-WAPD-419-151-Q3 F-B F2.0 AFPli 7334 0 C -= ADDED IN REV. 6. AUX FEEDWATER LINES LESS TllAN 4* ARE NOT EXEMPT. CIIANGED DRAWING FROM 2419A TO 101r-i. l 12050-WMKS-0102FG 33tl . 4'-WAPD-419401-Q3 D-B D2.20 AFPli 615 .I VT-3 j Conuments 100's A-618 NOT SELECTED CIIANGED ITEM NUMBER TO AGREE WITil PRESSURE TESTING PROGRAM IN REV. 8.
- 12090-WMKS-0103 AA 121I 6'-SI-416-1502-Qt ~ C-C C3.20 RC216 657 0 PT ,
Comunents 100's. R-124. NOT SELECTED CllANGED FROM PERIOD 2 TO PERIOD 0 REV. 7 RELIEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 WIIICl! ONLY REQUIRES 10*6 OF THE INTEGRAL ATTACIIMENTS TO BE EXAMINED. . -i 12090 WMKS-0103AA 2-SI-R 121 6'-SI-416-1502-Q F-B F2.0 RC241 668 3 VT-3 Canunents A11 ARES. ADDEDTO PERIOD 3 IN REV. 7. GROUPED St TPORTS BY SYSTEM AND TYPE St NEEDS 7 MORE SUPPORTS . 120SO-WMKS-0103 AD 2-51-113 6'-SI-419-1502-QI B M-2 B12.50 B-LOOP 767 0 ' VT-3 I C -c
. REQ MAINTENANCE DISASSEMBLY ONLY; 100's INTERNAL SURFACES. IF NOT EXAMINED IN THIS INTERVAL REPORT IACK OF EXAMINATION ON TIIE LAST NIS-1 .
REPORT FOR Tile INTERVAL GROUP A VALVE- 6"IIIGliIIEAD SI { 12050-WMKS-0103AD 2-51-117 6'-SI-419-1502-QI B M-2 B12.50 B-LOOP 771 0 VT-3 ; Comunents REQ. MAINTENANCE DISASSEMBLY ONLY; 100% INTERNAL SURFACES. IF NOT EXAMINED IN TIIIS INTERVAL REPORT LACK OF EXAMNATION ON TIIE IAST NIS-1 ; REPORT FOR Tile INFERVAL GROUP B VALVE - 6" IDW HEAD Si t 12050-WMKS-Ol'OAD 2-SI-S-8C 6'-SI-419-1502-QI F-B F2.0 RC216 798 3 VT-3 ! C .a AllASUPC. CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 5. ONLY NEED TO EXAMINE 15% OF SUPPORTS ON LINES RECEIVING ANOTIIER TYPE OF EXAM. Cl!ANGED BACK TO PERIOD 3 IN REV. 7. SUPPORTS nROLTED BY SYSTEM AND TYPE NEED 7 MORE SUPPORTS FOR SI 12050-WMKS-0103AD 46 6'-SI-419-1502-QI C-F-l C5.Il B-IDOP 801 2 PT/UT l Ceaunents CllANGED FROM PERIOD 1 TO PERIOD 2 IN INTERIM CilANGE 93-02. REPLACED WITI8104C-16. WILL ALIDW Tile LONG SEAM TO BE DONE WITil THE [' CIRCUMFERENTIAL 12090-WMKS-0103AF 16A 2'-SI-.s63-1502-QI BJ B9.40 RC216 865 3 PT Commento OLD. REPLACED IN 95 BY DCP 94-008. CHANGED FROM 16 TO 16A REV. 7. y 12090-WMKS-0103 AF 17A 2*.SI-463-1502-QI B-J B9.40 867 0 Comunento REPLACED IN 95 BY DCP 94-008. CIIANGED FROM WELD NUMBER 17 TO 17A. REV. 7. 12050-WMKS-0103 AF ISA 2'-SI-459-1502-Qt BJ B9.40 869 0 ; Canunento REPLACED IN 95 BY DCP 94-008. CIIANGED FROM WELD NUMBER 18 TO I8A REV 7- , 5
.is- t Sununary of Changes Sorted by Drawing and Mark No NAPSU22 Database Page 28of H6 PrmrDare: 11/18 98 [
. _ . . - - _ __ - - -- ._- _ _ _ - - _ - - - - = _ _ _ _ _ _ - _ - - _ __ - __ _ ___--_-__ _ __ _ _ _ - _ _____ - - -__.- _ -
i s i v I i Drening No. hierk No. I.ine Number Catetary item No- Location . Reconi Period Method ; [
- 12050-WhtKS-0103 AF 19A 2' 5I-459-1502-QI B-J B9.40 870 0 Comments REPLACED IN 95 BY DCP 94-008. CII ANGED I ROh! WELD NUh!BER 19 TO 19A. REV 7.
12050-Wh!KS-0103AF $9 2'-St-459-1502-Q1 B-J B9.40 7450 0 - Comnients ADDED IN 95 BY DCP 94-008. REV. 7. , t 12050-WhtKS-0103AF 60 2*-SI-459-1502-QI B-J B9.40 7451 0
- Comments ADDED IN 95 BY DCP 94-008. REV. 7-12050 Whf KS-0103 AO 2-SI-118 6'-RC-416-1502-QI B-kl-2 1312.50 A-IDOP 948 0 VT-3 Ceaunents REQ htAINTENANCE DISASSEh!BLY ONLY; 100*6 INTERNAL SURFACES. IF NOT EXAhi!NED IN TIIIS INTERVAL REPORT LACK OF EXAhlINATION ON Ti!E LAST NIS-1 REPORT FOR TIIE INTERVAL GROUP A VALVE - 6" IIIGil IIEAD SI 12050-WhlKS-0103 AG 2-SI-124 6'-St-421-1502-QI B-hl-2 B12.50 A-LOOP 954 2 \T-3 !
Comments REQ. KIANTENANCE DISASSEkIBLY ONLY; 100*. INTERNAL SURFACES. IF NOT EXAhtINED IN THIS INTERVAL REPORT LACK OF EXAkIINATION ON TifE LAST NIS-1 , REPORT FOR Tile INTERVAL GROUP B VALVE -6" LOW IIEAD SI 12050-WhiKS-0103 All 2-SI-ll2 6*-St-416-1502-QI B-hl-2 B12.50 C-LOOi; 992 0 VT-3 t Comments REQ. hiAINTENANCE DISASSEhtIILY ONLY; 100*ilNTERNAL SURFACES. IF NOT EXAhflNED IN TIIIS INTERVAL REPORT LACK OF EXAhtINATION ON TIIE LAST NIS-1
' REPORT FOR TIIE INTERVAL GROUP B VALVE - 6" LOW ItEAD Si !
, 12050-WhlKS-0103All 2-51-125 6'-SI-416-1502-QI B-hl-2 B12.50 C-LOOP 996 2- \T-3 ' Comments REQ. htAINTENANCE DISASSEhtBLY ONLY; 100's INTERNAL SURFACES !F NO F EXAh!INED IN TIIIS INTERVAL REPORT LACK OF EXAhflNATION ON TIIE IAST NIS-I - REPORT FOR TlIE INTERVAL GROT? A VALVE - 6" 111G11 IIEAD St i B-J A-LOOP 2 PT ' 12050-WhfKS-Ol03AJ-l SA 2*-SI-461-1502 4 1 B9.40 1061 Comments NEW. TIIIS WAS REPLACE IN 95. OLD WELD NUhtBER 8. NOT REQUIRED TO BE EXAh!!NED IN TIIE PERIOD TilAT IS WAS REPLACED. SECTION XI CREDIT FIAG SET 10 "Y" AND EXAh! DATE SET TO I/1/11 SO POPULATION COUNTS WILL BE CORRECT. NOTES REVISED IN REV. 7. 12050-Whf KS-0103 AJ-l 9A 2*-SI-461-1502-QI B.J B9.40 1062 0 t Comments REPLACED IN 95 BY DCP 94-008. OLD WELD NUh!BER 9. REV. 7. ; 12050-WhtKS-0103 AJ-2 SW-lW 3'-SI-457-1502 9 1 B-J B9.21 1107 2 IT Comments REPLACING 103AJ-2 SW-96 WIIICII WAS LIhtITED DUE TO A PIPE SUPPORT. INTERIhf CIIANGE 95 l 12050-WhtKS-0103AJ-2 SW-96 3*-SI-457-1502-QI B-J B9.21 RC216 1131 0 PT j i Comments NEW. WELD IS RESTRICTED BY PIPE SUPPORT SUBSTITUTED WITli 103Al-2 SW-lW. INTERIhl CllANGE 95 t 12050-Wh1KS-0103 AP 2-CM-R-12 2*-Cll-492-1502-Qt F-B F2.0 RC216 1846 3 \T-3 Comuments AllARES. C11ANGED FROKI PERIOD 0 TO PERIOD 3 IN REV. 7. SAhlPLE SIZE AfUST BE PROPORTIONAL TO SYSTEh! AND TYPE. 12030-WhfKS-0103AR 2-Cll-A-4 2*-Cll 494-1502-Q1 F-A F1.0 - RC216 1280 3 \T-3 Ceniments BilAANC. CllANGED FROh! PERIOD 0 TO PERIOD 3 IN REV 7 SAhfPLE SIZE h1UST BE PROPORTirNAL TO SYSTEh! AND TYPE OF SUPPORT-Sammary of Clienges Sorted by Drawing and hferk No, NAPSt'22 Database Page 29of146 Pnnt Date: 11/1893 r
Drawing No. Mark No. l.ine Number C e em No. location Receed Per% d hiethod 12050-WMKS4103 AR 2-CII-R4 2*-CII-494-1502-QI F-B F2 0 RC216 1290 3 NT-3 Comments AltARES. CIIANGED FROM PI RIOD 0 TO PERIOD 3 IN REY. 7. SAMPl.E SIZF Mt'ST BE PROPORMON ALTO SYSTEh! AND TYPE OF SUPPORT. 12050-WMKS-0103 AR 59A I l'2'-Cll-797-1502-Ql 11 3 !h40 ILIJOEP 1357 i PT Commenes NEW. CllANGED NUMBER FROh! SW-99 TO 59A IN REV. 7 WELD Nt'MBFR WAS CilANGED UNDER REPAIR PROGRAM 94-146 DRAWING IIAS BEEN REVISED. 12050-WMKS-0103 AT 2-Cll-A-8 2'-Cll-496-1502-Q1 F-A Fl .0 RC216 1379 3 VT-3 Comments Ill!AANC. CilANGED FROM PERIOD 0 TO PERIOD 3 IN REV. 7. SAhlPI E SIZ.E MUST BE PROPORTIONAL TO SYSTEM AND TYPE OF SUPPORT. 12050-WMKS4103 AT 2-Cil-R 15 2'-Cil-496-1502-QI F-B F2.0 RC216 1385 3 \T-3 Comments AllARES. CIIANGFD FROM PFRIOD 0 TO PERIOD 3 IN REV. 7. SAMPLE SIZE kit'ST BE PROPORTIONALTO SYSTEM AND TYPE OF SUPPORT. 12050-WMKS-0103 AZ IB 2*-RC418-1502-QI B-3 B9.21 1504 2 PT Comments CIIANGED FROM PERIOD 010 PERIOD 2 IN INTERIM CllANGE 95-02. REPLACINO 30A ON SAME DRAWINO WillCIIIS RESTRICTED BY PIPE SUPPORT-12050-WMKS-0103 AZ 30A 2*-RC418-1502-QI B-J B9 21 RC216 1537 0 PT Comments ClIANGED FROM PERIOD 2 TO PERIOD 0 IN INTERIM CIIANGE 95-02. REPLACI D WITil iB ON S AME DRAWING 30A IS RESTRICTED 13Y A PIPE SUPPORT. 12050-% MKS-0103BA 2-RC-IISS417.01 3'-RC417-1502-QI F-C F3.0 B-LOOP 1570 0 VT-3 Comments DllAIISB IF PIPE CLAMP BOLTS ARE NOT VISIBLE INSULATION hlUST BE REMOVED. CllANGED FkLM PERIOD 3 TO PERIOD 0 IN REV. 7. SAMPLE SIZE MUST BE PROPORTIONAL TO SYSTEM AND TYPE OF SUPPORT. 12050-WMKS-0103BA 2-RC-IISS417.03 3'-RC417-1502-Q1 F-C F3 0 B-LOOP 1571 0 VT-3
^ Comments D11 AllSB IF PIPE CLAMP BOLIS ARE NOT VISIBLE INSULATION MUST BE REMOVED. CitaNGED FROM PERIOD 3 TO PERIOD 0 IN REV. 7. SAMPLE SIZE MUST BE PROPORTIONALTO SYSTEM AND TYPE OF SUPPORT.
12050-WMKS-0103BB 2-SI-105 6'-St-532-1502-QI B-M-2 B12.50 RC241 1612 0 VT-3 Comments REQ. MAIN ENANCE DISASSEMBLY ONLY; 100% INTERNAL SURFACES. IF NOT EXAMINED IN TIIIS INTERVAL REPORT LACK OF EXAMINATION ON 11IE LAST NIS-1 R EPORT FOR TiiE INTERVAL GROUP B VALVE. 6" LOW IIEAD SI 12050-WMKS-0103BB 2-SI-91 6'-SI-531-1502-QI B-M-2 B12.50 RC241 1615 2 \T-3 Comments REQ. M AINTENANCE DISASSEMBLY ONLY; 100% INTERNAL SURFACES. IF NOT EXAMINED IN Tills INTFR VAL REPORT LACK OF EXAMINATION ON Tile IAST NIS-1 REPORT FOR Tile INTERVAL GROUP B VALVE - 6" LOW IIEAD SI 12030 WMKS-010311B 2-51-99 6'-SI-533-1502-Q1 B-M-2 B12.50 RC24I 1618 2 VT-3 Commenu REQ. MAINTENANCE DISASSEM13LY ONLY; 100% INTERNAL SURFACES. IF NOT EXAMINED IN TIIIS INTERVAL REPORT LACK OF EXAMINATION ON TIIE LAST NIS-1 REPORT FOR Tile INTERVAL GROUP B VALVE - 6* LOW IIEAD SI 12050-WMKS-0103BB 2-SI-R-102 6'-SI-532-1502-QI F-A F10 RC241 1626 0 VT-3 Comments 1111AGUD2. CilANGED FP.OM PERIOD 3 TO PERIOD 0 IN REV. 7 S AMPLE SIZE MUST BE PROPORTIONAL TO SYSTEM AND TYPE OF SUPPORT. 12050-WMKS-0103BC 12A 2'-SI-455-1502-QI C-F-1 C5.30 1674 0 Commenu WEPSOK OREPL\CED IN 95 BY DCP 94-008. CIL\NGED FROM WELD NUMBER 12 TO 12A REV. 7. Summary of Ganges Sorted by Drawing and Mark No NAPSl!22 Database Page 30of 146 Pnnt Date: 11/18 98
Drawing No. Meet New . Line Numbe Category iteni No. . Iscation - Record Perfd - Method
' 12050 WhtKS-0103BC 13 (NEW WELD 74) ' 2*-51455-1502-QI C-F-1 C530 RC216 1675 l' FF '
~ Canuments REPLACED IN 95 BY DCP 94-008. CilANGED FRONI WEI D NUhlBER 13 TO 74.
12050-Wh!KS-0103BC - 16B(NEW WELD 70) 2*-SI-45IIIO22E ~ C-F-1 C530 1676 I PT Commenents ' WEPSOK OREPLACED IN 95 BY DCP 94-008. CIIANGl D FROkt WELD NUh!BER 16 TO 70 REV. 7. 12030-WhlKS-0103BC 2-St-R-18 2'-SI-455-1502-Q1 F-A Fl.0 ' RC216 1695 .3 VF3- r ! Conwnents BilAGUD2CIIANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 5. ONLY NEED TO EXAhlINE 15% OF SUPPORTS ON LINES RECEIVING ANOTHER TYPE OF EXAhl ADDED t BACK TO PERIOD 3 IN REV. 7. GROUPED SUPPORTS BY SYSTEkl AND TYPE St NEEDS 7 hlORE SUPPORTS . 12030-WKtKS-0103BC 2-S!-R-21 2*-SI-455-1502-QI F-B F2.0 RC216 1697 3 VT-3 i Conuments AllARES. CIIANGED FROh! PERIOD 3 TO PERIOD 0 IN REY. 5. ONLY NEED TO EXAhflNE 15% OF SUPPORTS ON LINES RECEIVING ANOTIIER TYPE OF EXAM. ADDED BACK TO PERIOD 3 IN REV. 7. GROUPED SUPPORTS BY SYSTEhl AND TYPE St NEEDS 7 KIORE SUPPORTS 12050-Wh!KS-0103BC 67 2'-SI-455-1502-QI C-F-1 C530 RC216 7515 0. PT Comunents ADDED IN 95 BY DCP 94-008. REV. 7. ; 12030-Whf KS-0103BC 68 2'-SI 455-1502-Q1 C-F-I C530 RC216 7452 0 PT Conunents ADDED IN 95 BY DCP 94-008. REV. 7. ; f 12050-WhlKS-0103BC 69 2'-SI-4 55-1502-QI C-F- 8 C530 1708 0 f' Ceaunents WEPSOK 0 REPLACED IN 95 CIIANGED KIARK NUNIBER FROh! 37A TO 69 REV. 7 12050-WKIKS-0103BC 71 2'-SI-455-1502-QI C-F-1 C530 RC216 7453 0 PT , I Commeents ADDED IN 95 BY DCP 94-008. REV. 7. 12090-WhtKS-0103BC 72 2'-SI-455-1502-QI C-F-1 C530 RC216 7454 0 PT
-[
C -c ADDED IN 95 BY DCP 94-008. REV. 7- .[ f 12050-WhiKS-0103BC 73 2'-SI-455-1502-QI C-F-1 C530 RC216 7455 0 PT , Comunents ADDED IN 95 BY DCP 94-008. REV. 7. 12050-Wh1KS-0103BC 75 2'-SI-455-1502-QI C-F-l C530 RC216 7456 0 PT C ./ . ADDED IN 95 BY DCP 94-008. REY. 7. , 12090-WhlKS-0103BD-1 10W 2'-SI-451-1502-QI C-F-1 C530 7458 0 t 4 Comuments ADDED IN 95 BY DCP 94-008. REV. 7. 12050 WhfKS4103BD-I llW 2'-SI-451-1502-QI C-F-1 C330 7457 0 i Cosmnenta ADDED IN 95 BY DCP 94-008. REV. 7. 12090-Whf KS-0103BD-1 4W 2'-SI-451-1502-Q1 C-F-1 C530 7461 0
)
Conunents ADDED IN 95 BY DCP 94-008. REV 7. , Samunary of Changes Sorted by Drawing and Mark No . NAPSU22 Database Page 31of 146 Pnnt Date H/l&98
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ._____________m __ _ _ _ _ _ _ _ _ . _ . _ _ _ . _ _ _ _ _
. Draning No- Mark No. Line Number Category iteni No- Location Record Period Mettied 12050-WMKS-0103BD-1 SW 2*-SI-4 51-1502-Q1 C-F-l C5.30 7462 0 Ceaunents ADDED IN 95 BY DCP 94-008. REV 7.
~ ~
, 12050-WMKS-0103BD-1 6W 3SI-451-1502-QI C-F-1 C5 30 1732 0 Comuments WEPSOK () REPLACED IN 95 BY DCP 94-008. CilANGED FROM WELD NUhlBER 29 TO 6W. I 1 12090-WMKS-0103 BD-1 7W 2*-SI-451-1502-QI C-F-l C5.30 1731 0 Comunents WEPSOK (). REPLACED IN 95 BY DCP 94-008. CII ANGED FROM WELD NUMBER 28 A TO 7W. 12050-WMKS-0103BD-l 8A 2*-SI-451-1502-QI C-F-1 C5.30 1752 0 C. - c; WEPSOK () REPLACED IN 95 BY DCP 94-008. CllANGED FROM WELD NUMBER 8 TO 8A. REV. 7. 12050 WMKS-0103BD-1 RW 2*-SI-451-1502-QI C-F-1 C5.30 7460 0 Ceaunents ADDED IN 95 BY DCP 94-008. REV. 7. 12030-WMKS-0103BD-1 9A 2*-SI-451-1502-QI C-F-1 C5.30 1753 0 Comuments WEPSOK ()REFLACED IN 95 BY DCP 94408. CIIANGED FROM WELD NUMBER 9 TO 9A REV. 7. I 12050-WMKS-0103 BD-1 9W 2*-SI-451-1502-QI C-F-1 C5.30 7459 0 Comuments ADDED IN 95 BY DCP 94-008. REV. 7.
'E 12050-WhlKS-Ol03BE 2-SI-92 C-SI-531-1502-QI B-M-2 B12.50 - A-LOOP 1849 0 VT-3 l Conunents REQ MAINTENANCE DISASSEMBLY ONLY; 100% INTERNAL SURFACES. IF NOT EXAMINED IN DIIS INTERVAL REPORT IACK OF LXAMINATION ON DIE LAST NIS-I REPORT FOR T!IE INTERVAL GROUP A VALVE - 6" 1I101I IIEAD SI ;
12050-WMKS-0103BF 2.CII-R-13 2'-Cll-410-1502-QI F-B F2.0 RC216 1889 3 VT-3 , Comuments AllARES. CII ANGED FROM PERIOD 0 TO PERIOD 3 IN REV. 7. S AMPLE SIZE h!UST BE PROPORTIONAL TO SYSTEM AND TYPE OF SUPPORT. : 1205v*iMKS-0103BM 2-SI-SII-76 6'-SI-531-1502-QI F-C F3.0 RC216 2105 0 VF.3 l t Comnues CllAVAR CllANGED FROM PERIOD 3 TO PERIOD 0 IN REV.7. SAMPLE SIZE MUST BE PROPORTIONALTO SYSTEM AND TYPE OF SUPPORT. j 12050-WMKS-0103BN 2-SI-106 6*-SI-532-1502-Q t B-M-2 B12.50 C-LOOP 2136 0 VT-3 I Conunents REQ. MAINTENANCE DISASSEMBLY ONLY; 100% INTERNAL SURFACES. IF NOT EXAMINED IN TIIIS INTF.RVAL REPORT LACK OF EXAMINATION ON TIIE LAST NIS-1 , REPORT FOR TIIE INTERVAL GROUP A VALVE - 6* IIIGli IIEAD SI i
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12030-WMKS-0103BN 24J 6*-SI-532-1502-QI B-K B10.20 RC216 2132 0 PT t Canunenta 100%. CilANGED FROM UT OR PT TO PT IN REY. 2. (2-SI-R-112) CIL\NGED FROM PERIOD 3 TO PERIOD 0 REV. 7. RELIEF REQUEST NDE-21 ALIDW USE OF CODE CASE N- t 509 WillCII ONLY REQUIRES 10% OF TIIE INTEGRAL ATTACliMENTS TO BE EXAMINED. R-112 SEECTED FOR PERIOD 3. CODE CASE AI.SO CIIANGED T1IE CATEGORY TO B-K, j 12050-WMKS-0103BP 2-SI-100 6*-SI-533-1502-Q1 B-M-2 B12.50 B-LOOP 2192 3 VT-3 Coni nents REQ. MANTENANCE DISASSEMBLY ONLY; 100% INTERNAL SURFACES. IF NOT EXAMINED IN TIIIS INTERVAL REPORT LACK OF EXAMINATION ON TIIE LAST NIS-l REPORT FOR Tile INTERVAL GROUP A VALVE - 6* IIIGII IIEAD SI Ii Sumanary of Cleanges Sorted by Draning and Mark No,NAPSU22 Database Page 32of f 46 Prmt Date: 11/1898
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Dining No. Alesi No. IJne Num5r Category Item No. lacation . Record Period Meelsed 12050-Wh1KS-0103BP 24A 6'-SI-533-1502-QI B-J B9.11 2187 0 Cesnsments REPLACED IN 95 BY DCP 95-158. OLD WELD NUh!BER 24 REV ' 7. 12050-WhfKS4103BP 2A 6*-SI-533-1502-QI B.J B9.11 2182 0 C_ . ;s REPLACED IN 95 BY DCP 95-I$8 OI.D WELD NUhtBER 2 REY. 7. , 12030-WhlKS-010311P 50 6'-SI-533-1502-Qi B-J 89.1I 7467 0 , t
. Cee-neents ADDED IN 95 BY DCP 95-158. REV. 7.
12050 WhlKS-0103BV 12B 2*-SI-453-1502-Q t C-F-1 C330 2235 0 Coenments ,WEPSOK 0 REPLACED IN 95 BY DCP 94-008. CllANGED FROh! WELD NUh!BER 12A TO 12B. REY. 7, 12050-WhlKS-0103BV 13B 2*-51-453-1502-0 1 C-F-1 C330 RC216 2236 2 PT Cesnments WEPSOK 0. TI!!S WAS REPLACED IN 95 UNDER DCP 94 008 NOT REQUIRED TO DE EXAh!INED IN TIIE PERIOD TilAT IT WAS REPLACED. CREDIT FIAG SET TO "Y" SO POPULATION REPORT WILL SilOW Tile RIGitT PERIOD PERCENTAGE. CIIANGED FROkt WELD NUhlBER I3A TO 13B REV. 7.12/31/95 IS A DUhthiY DA1T.To htAKE REPORTS WORK. 12050-WhlKS-0103BV 2-SI-R-6 2*-SI-453-1502-QI F-A Ft.0 RC216 2250 3 VT-3 > Comments B11AGUD2. ADDEDTO PERIOD 3 IN REY. 7. GROLTED SLTPORTS BY SYSTEh! AND TYPE SI NEEDS 7 hf0RE SUPPORTS. , 12090-WKtKS-0103BV 2A 2'-SI-453-1502-QI C-F-1 C530 2238 0 Cesnenents WEPSOK OREPLACED IN 95 BY DCP 94-008. CILANGED FROh! WELD NUh1BER 2 TO 2A REV. 7. 12030-Wh!KS-0103BV 3A 2'-SI-453-1502-QI C-F-I C530 2255 0 Conuments WEPSOK OREPLACED IN 95 BY DCP 94-008. C1t ANGED FROM WELD NUh!BER 3 TO 3A. REV. 7. 12050-WhtKS-0103BV 65 2*-S!-453-1502-QI C-F-1 C530 .7466 0 Comuments ADDED IN 95 BY DCP 94 008. REV. 7. ! 12050-WhtKS-0103BV 66 2*-SI-453-1502-QI C-F-1 C530 7463 0 Comunents ADDED IN 95 BY DCP 94-008. REV. 7. El 12050-WitKS-01038V 67 2*-SI-453-1502-QI C-F-l C530 7514 0 Cosenents WEPSOK OREPLACED IN 95 BY DCP 94-008. CIIANGED FROh! WELD NUhfBER SW-S i TO 67 REV.7. 12050-WhtKS-0103BV 68 2*-SI-453-1502-QI C-F-1 C530 7464 0 Comments WEPSOK OREPLACED IN 95 BY DCP 94-008. CIIANGED FROM WEll) NUKfBER SW-51 TO 67 REV. 7. j 12030-Wh1KS-0103BV 69 2'-SI-453-1502-QI C-F-1 C530 7465 0 C- ^ WEPSOK OREPLACED IN 95 BY DCP 94408. CIIANGED FROh! WELD NUkiBER SW-51 TO 67 REV,7. 4 i P Sanunary of Changes Sorted by Drawing and 51att No., NAPSU22 Database - Page 33 of 146 IhntDate: 11/18 98 1
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- __m .._ - . . . . - _ _ . _ _ _ . _ . _ _. - __
L Drawing No. Alerk No- IJnc Nurnber ('ategar3 Item No. . Location Recer i Period - hfetImed 12050-WhlKS-0103F loli 18' CC-731 151-Q3 D-A DI.20 RC216 2694 I VT-3 Comnients 100*.A-26E NOT SELECTED. Cil ANGED ITLht NUhlBER TO AGREE WITII PRESSURE TESTING PROGRAh! IN REV. 8. 12050-WhtKS-0103F 1411 f r-CC-731-151-Q3 D-A DI .40 RC216 2695 0 VT-3 '!
- Comunents 100*.(Sil-232 NOT SELECTED) CIIANGED FROh! PER]OD 3 TO PERIOD 0 IN REY. 7. RELIEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 TO EXAh!INE 10*4 OF TIIE ' -f INTEGRAL ATTAClikIENTS. Cll ANGED II Eh! NUhlBER TO AGREE WITII PRESSURE TESTING PROGRAh! IN REV. 8.
, t 2050-WhIKS-0103F 2-CC-R-21E I Y-CC-731-15 I-Q3 F-B F2 0 RC2I6 2698 3 \T-3 Comenients A 1IASLTC. New with Rev. II to the gian: Sciwduled in Period 3 due to reevaluation of the Class 3 total support population.
. 12050-WhiKS-0103F 2 CC-R-22E t r-CC-731-151-Q3 F-B F2.0 RC216 2699 3 VT-3 ,
t Commsents AIIASLTC. New with Rev II to the plan Scheduled in Period 3 due to reevaluation of the Class 3 total support populatiers. l I 12090-WhlKS-0103G 1511 1r-CC-779-151-Q3 D-A DI.20 RC216 2708 2 \T-3 4 Cemenients 100% R-230 NOT SELECTED. CllANGED ITEh! NUhlBER TO AGREE WITil PRESSURE TESTING PROGRAh! IN REV. 8. 12090-WhtKS-01030 161I t r-CC-729-151-Q3 D-A Dt.20 RC216 2709 1 VT-3 Comunents 100% R-229 SELECTED FOR PERIOD 1. Clt ANGED ITEhl NUhfBER TO AGREE WITil PRESSURE TESTING PROGRAh! IN REV. 8. 12030-WhlKS-0103G 1 711 18'-CC-729-151-Q3 D-A , DI.20 RC216 2710 0 VT-3 Comunents 100%(R-26B NOT SELECTEDL CilANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-2I ALLOW USE OF CODE CASE N-509 TO EXAhflNE 10% OF Tile INTEGRAL ATTACithtENTS. CilANGED ITEh! NUhtBER TO AGREE WITil PRESSURE TESTING PROGRAh! IN REV. 8. . i 12050-WhlKS-Ol03G 2-CC-R-24B 18'.CC-729-151-Q3 F+B F2.0 RC229 2719 3 VT-3 ; Comineents AllAStTC. New with Rev. I I to the plan: Scheduled in Period 3 due to reevaluation of the Class 3 total support population. 12090-WhtKS-0103G 2-CC-R-25B IT-CC-729-151-Q3 F-B F2 0 RC229 2720 3 \T-3 Ceumients AllASUPC. New with Rev. II to the plan: Scheduled in Period 3 due to reevaluation of the Class 3 total surport population. 18050-WklKS-0103G 2111 10'-CC-729-151-Q3 D-A DI .40 RC216 2711 I hT-3 C /a 100% Sil-231 SELECTED IUR PERIOD I. CIIANGED ITEh! NUhtBER TO AGREE WITil PRESSURE TESTING PROGRAh! IN REV. 8. r 12090-WhlKS-0103L 16II t r-CC-726-151-Q3 D-A DI.20 RC216 2765 2 \T-3 Ceaunenta 100% A-26D NOT SELECTED. CII ANGED ITEh! NUhtBER TO AGREE WITil PRESSURE TES11NG PROGRAh! IN REV. 8. ; 12090-WhtKS4103L 1 71I IY-CC-726-15 I-Q3 D-A D1.20 RC216 2766 0 hT-3 Cenernents 100%(Ril-94 NOT SELECT ED). CIIANGED FROkt PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-2I ALLOW USE OF CODE CASE N-509 TO EXAhflNE 10% OF T!!E INTEGRAL ATTACIlk!ENTS. CilANGED ITEh! NUitBER TO AGREE WITII PRESSURE TESTING PROGRAh! IN REV. 8. ; 12090-WhlKS-0103hl 2111 18"-CC-727-151-Q3 D-A DI.20 RC216 27'9 2 \T-3 ; + Comnients 100% A-26C NOT SELECTED. CIIANGED ITEh! NUhtBER TO AGREE %TTII PRESSURE TESTING PROGRAh! IN REV. 8. 12030-Wh1KS-0103ht 2211 18'-CC-727-151-Q3 D-A DI.20 RC241 2780 I VT-3 l Comunients 100% R-95 SELECTED FOR PERIOD 1. CILANGED ITEh! NUitBER TO AGREE WITil PRESSURE TESTING PROGRAh! IN REV. F Semnenary of Changes Sected by Drewhig and Mark No, NAPSU22 De* abase Tage 34 of 146 PrrnrDare: 11//8 93 >
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Ihwaint No. Mark No- Category . Itemi No. Imation Reeerd - . Pesied Metsund
~ 12050-WMKS-0103M 26II 18*-CC-727-15 I-Q3 D-A DI.20 RC241 278I I VT-3 Conuments 100% R-95 SELECTED FOR PERIOD I. CII ANGl"D i l EM NUMBER TO AGREE WITit PRESSURE 11 STING PROGRAM IN REY. 8 12050-WhfRS-0104B-l 1811 8~-St-449-153 A-Q2 C-C C3.20 ~360 0 Ceseneents A-43. NOT SELECTED 12050-WMKS-OI04B-1 2-SI-R-31 10'-SI-542-151 A-Q2 F-B F2.0 SFGD 2808 .O VF-3 Conunes.es- A IIARES. CllANGED FROAl PERIOD 2 TO PERIOD 0 IN REV. 3. ONLY NEED TO ELuflNE 15% OF SUPPORTS ON LINES RECEIVING ANOTIIER TYPE OF EXAM *,XAMINED IN 90 LOOSE Lui NUF, 12050-WMKS-OI048-1 2-St-R-33 r-SI449-153 A-Q2 F-I3 F2 0 SFGD 2809 0 VT-3 Conunents A11 ARES. C11ANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 5. ONLY NEED TO ELuf!NE 15% OF SUPPORTS ON LINES RECEIVING ANOTIIER TYPE OF EXAM.
12050-WMKS-OI04B-I 2-51-511-32 8'-SI449-153 A-Q2 F-C F3.0 SFUD 2814 0 VT-3 Conunents C11AVAR CIIANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 5 ONLY NEED TO EXAMINE 15% OF SUPPORTS ON LINES RECEIVING ANOTIIER TYPE OF EXAM. I2050 WMKS-0104B.I 2-51-511-32 r-SI449-153 A-Q2 F-C F3 0 SFGD 7422 0 VF-3 Cesuments C11AVAR CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 5. ONLY NEED TO ELutINE 15% OF SUPPOR13 ON LINES RECEIVING ANOTIIER TITE OF EXAkt. 12050-WMKS-0104B-1 LS-46W(SW-18W) 10'-St-542-153A-Q2 C-F-1 C512 2825 0 Cosnments WEPSEhl IDNO SEAMS WELDS WERE BROKEN IX)WN BY INTERSECTION IN REV. 5 12050-WMKS-Ol04B-l LS-46W(SW-19W) 10'-SI-542-153 A-Q2 C-F-1 C5.12 6736 0 Conannents WEPSEM LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV 5 12050 WMKS-0104B-l IS50W(SW-17A) r-St-449-153 A-Q2 C-F-1 C512 6737 0. C .3 WEPSEh! LONG SEAMS WEIDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104B-l IS50W(SW-17W) r-SI449-153A-Q2 C-F-1 C5.12 2826 0 C_ .3 WEPSEM LONO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12050-WMKS-0104B-1 LS-57W(16) 8'-SI-449-153A-Q2 C-F-l C5.12 6738 0 Ceaunents WEPSEM IDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS4104B-l LS-57W(SW-16W) r-SI-449-153A-Q2 C-F-1 C5.12 2827 0 Ceaunents WEPSEM LONG SEAMS WEIDS WERE l BROKEN DOWN BY INTERSECFION IN REV. 5 12030-WMKS-0104B-1 LS-78(SW-74) 10*-SI-464-153A-Q2 .C-F-1 C5.12 2828 0 Ceaunents WEPSEM IDNG SEAMS WEIDS WERE BROKEN DOWN BY INTERSECFION IN REV 5 Senunary of Changes Sorted by Druning and Mark No., NAPSU22 Databew Page JJ of 146 Pemt Date 11/18 94 ________..J
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Drawing No. Mark No. Ilne Number Category Item No. Location Reconi Period Method 12090-WMKS-01041LI IS-78(SW-75) 10'-SI-464-153 A-Q2 C-F-1 C5.12 6739 0 Comments WEPSEM IONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12050-WAIKS-0105 LS-79(SW-6 I} 10'-SI-464-153 A-Q2 C-F I C5. I 2 6740 0 Comments WEPSEM LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. $
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12050-WAtKS-0104B-1 LS-79(SW-76) 10*-SI-464-153 A-Q2 C-r-1 C512 2829 0 Comments WEPSEM LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104B-1 LS-80(SW-62) 10'-SI-464-153A-Q2 C-F-I C5.12 SFGD 72 5 0 PT,UT Comments WEPSEM. ADDEDIN REV.5 12050-WMRS-01048-1 LS-80(SW-63) 10'-SI-464-153 A-Q2 C-F-1 C512 SFGD 2830 3 IT MF Comments WEPSEM. CriANGED FROM PERIOD 0 TO PERIOD 3 IN INTERIM CII ANGE 9002, REPLACES 107B LS-70 11u50-WMKS-0104B-1 LS-81(52B) 10*-SI-464-153 A-Q2 C.F-1 C5.12 6741 0 Comments WEPSEM LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-01048-I LS-81(SW-77) 10'-SI-464-153 A-Q2 C-F-1 C5.12 2831 0 Comments WEPSEM LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104B-1 IS-85(SW-84) 10*-SI-542-153 A-Q2 C-F-1 C5.12 6742 0 Comments WEPSEM LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-WMKS-0104B-1 IS-85(SW-85) 10'-SI-542-153 A-Q2 C-F-1 C5.12 2832 0 Comments WEPSEM LDNG SEAMS WELDS WERE BROKEN IX)WN BY INTERSECTION IN REV. 5 12050-WMKS-01048-1 LS-86(1 A) 10'-SI-542-153A-Q2 C-F-1 C5.12 2833 0 Comments WEPSEM LONG SEAMS %TLDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050 WMKS-0104B-1 LS-86(SW-66) 10'-SI-542-153 A-Q2 C-F-1 C512 6743 0 Comments WEPSEM IDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104B-1 LS-89(SW 7I) 10*-51-464-153 A-Q2 C-F-1 C5.I2 2834 0 Comments LOCATED BETWEEN WELDS SW SW-71. ADDED IN REV. 3-LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 Summary of Changes Sorted by Drawing and Mark No NAPSU22 Database Page Jrof 146 Pnat Date: 11/1A98
m E Druning No. Maris No. . IJne Nurnber Category item No - lecarian Record Perted - Method 12050-WL KS-0104B-1 LS-89(SW-72) 10'-SI 464-153A-Q2 - C-F-le C5.12 6744 0 Ceaunents LOCATED BETWEEN WELDS SW SW-71. ADDED IN REY. 3. LONG SEAMS WELDS WERE BROKEN DOWN BYINTFRSFCTION IN REY. 5 ; 12090-WMKS-0104B-1 IS-90(SW-57) 10'-SI 464-153A-Q C-F-I . C5.12 6745 0 . Conwnents ' LOCATED BEDVEEN WELDS SW SW-57-SW-83. ADDED IN REV. 3. LONG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104B-1 LS-90(SW 73) 10*-SI-464-153 A-Q2 C-F-1 C5.12 2835 0 Cenunents LCCATED BETWEEN WELDS SW SW-57-SW-83. ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTEP5ECTION IN REV. 5 12050-WMKS-0104B-1 13-90(SW-83) 10*-S1-464-153 A-Q2 C-F 1 C5.I2 7045 0 : Conunents LONG SEAMS WEf DS WERE BROKEN DOWN BY INTERSECTION IN REV 5 [ 12050-WMKS-0104B-l 13-91(SW-58) 10'-SI-464-153 A-Q2 C-F-1 C5.12 2836 0 . Comunents ' IDCATED BETWEEN WELDS SW SW-58 -SW-67. ADDED IN REV. 3. t IANG SEAMS WELDS WERE BROKEN IX)WN BY INTERSECTION IN REV. 5 12050-WMKS-0104B-1 LS-91(SW-67) 10'-St-464-153 A-Q2 C-F- 1 C5.12 7046 0 Comunents LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECDON IN REV. 5 12030-WMKS-Ol04B-1 13-91(SW-74) 10*-SI-464-153A-Q2 C-F-1 C5.12 6746 0 5 Canunents IECATED BETWEEN WELDS SW SW-58 -SW-67. ADDED IN REY. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 l 12050 WMKS-0104B-1 SW-88 6"-SI-421-1502-Qt C-C C3.20 7561 0 Cenunents PEN-61. NOT SELECTED 12050-WMKS-0104B-2 2-SI-A-42 8'-SI-440-153A-Q2 F-A Fl.0 SFGD 2876 0 VT-3 Canunents B11AANC. CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 5. ONLY NEED TO EXAMINE 15'6 OF SUPPORTS ON LINES RECEIVING ANOTIIFR TYPE OF EXAM.
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12050-WMKS-0104B 2 2-SI-IISS-809A 10'-SI-541-153A-Q2 F-C F3.0 SFGD 2882 0 VT-3 Conunents D11AIISB. CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REV 5.. ONLY NEED TO EXAMINE 15's OF SUPPORTS ON LINES RECEIVING ANOTIIER TYPE OF EXAM. 12030-WMKS4104B.2 2-SI-IISS-810A 8'-SI-440-153 A-Q2 F-C - F3.0 SFGD 2884 0 VT-3 g Conuneet D11AllSB. CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 5. ONLY NEED TO EXAMINE I 5% OF SUPPORTS ON LINES RECEIVING ANOT1IER TYPE OF EXAAL 13050-WMKS-0104B-2 2-S1-511-35 10'-SI-425-153A-Q2 F-C F3.0 SFGD 2889 0 VF-3 Comunents C/IIAVAR. CIIANGED FROM PERIOD 2 TO PERIOD 0 IN REV. 5. ONLY NEED TO EXAMINE 15'e OF SUPPORTS ON LINES RECElv!NG ANOTIIER TYPE OF 8'XAM -[ 4 12030-WMKS-0104B-2 2-S1-511-35 10'-SI-425-153A-Q2 F-C F3.0 SFGD 7419 0 VT-3 i Conunents C11AVAR. CIIANGED FROM PERIOD 2 TO PERIOD 0 IN REV. 5. ONLY NEED TO EXAMINE I5'& OF SUPPORTS ON LINES RECEIVING ANOTIIER TYPE OF EXAM , Sununary of Changes Sorted by Draning and Mark No.,NAPSU22 Database Page 37of146 Pnnt Dare: l #18 93 ; t
4 Deswbeg No, Mark No. . Line Number Category I em Na Imcation Receril .Feded Metteed 12050-V'MKS4104B-2 3211 8 -SI-440-153 A-Q2 C-C C3 20 7562 0 , - Comats A-42. NOT SELECTED 12050-WklK' -0104B-2 39 . 3-SI423-153 A-Q2 C-F-1 ' C55 2907 2. PT MF. C -n WEPCB () CIIANGED FROh! PERIOD 0 TO PERIOD 2 IN REV. 6 REPLACING 44 ON 104B-2. WilL ALLOW LONO SEAh!S IS-14W & LS-83W TO BE DONE %Trl! CIRC. %TLD. 12050-WhlKS41048-2 40 10*-SI423-153A-Q2 C-F-l 3 .11 2909 2 PTAJT
. Comuments WEPCB(). CilANGED FROh! PERIOD 0 TO PERIOD 2 IN REV. 6 REPLACING 46 ON 104B-2. WILL ALLOW LONO SEAM IS-S3W TO BE DONE WITH CIRC WELD. . I 12050-WMKS-Ol04B-2 44 10'-SI424-1502-Qt C-F-I C5. I l SFOD 2913 0 PTiUT -C_ :: WEPCB (1 CIIANGED FROM PERIOD 2 TO PERIOD 0 IN REV.6. REPLACED BY 39 ON 104B-2. WILL ALLOW LONO SEAM TO BE DONE Wrill CIRC. WELD.
12050-WMKS-0104B-2 46 10'-SI-624-1502-QI C-F-1 C5.I l SFGD 2915 0 PTMF Comuments CllANGED FROM PERIOD 2 TO PERIOD 0 IN REV. 6. REPLACED BY 40 ON 1048-2. WILL ALLOW LONO SEAM TO BE DONE WITII CIRC. WELD. 1205^-WMKS-Ol04B-2 7011 10*-SI424-1532 4 1 C-C C3 20 7563 0 . t Con .c aos S11-59. NOT SELECTED 12030-WMKS-0104B-2 LS-29W(50A) 10'-SI-425-153 A-Q2 C-F-I C5.I2 2928 0 Ceaunents %T,PSEM LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-Ol04B-2 LS-29W(SW-21W) 10'-SI-425-153A-Q2 C-F-1 C5.12 6747 0 Canunents WEPSEM IDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV 5 12050-WMKS-0104B-2 LS-30W(SW-22W) 10*-SI-425-153A-Q2 C-F-1 C5.12 2929 0 : C. 2; WEPSEkl LONO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12050-WMKS-Ol04B-2 LS-30W(SW-23W) 10'-SI-425-153 A-Q2 C-F-l C5.12 6748 0 - Canunents WEPSEM LONO SEAMS WELDS WERE ! BROKEN DOWN BYINTERSECTION IN REV. 5 12050-WMKS-0104B-2 LS-31W(SW-72) 10'-SI-425-153 A-Q2 C-F-I C3.12 2930 -0 i Comuments WEPSEh! LONO SEAMS WELDS WERE BROKEN DOWN BY INTERSECrlONIN REV.5 , 12050-WM KS-0104B-2 C-F-1 C5.12 6749 0 I.S-31W(SW-73) 10'-SI-425-153 A-Q2 Comumenta WEPSEM LONG SEAMS WEIDS %TRE l BROKEN DOWN BY INTERSECTION IN REY. 5 i 12090-WMKS-0104B-2 IS-32W(SW-74) 10'-SI-425-153A42 C-F-1 C5.12 2931 0 Canunents WEPSEM LONO SEAMS WELDS WERE . BROKEN DOWN BY INTERSECTION IN REV. 5 .! Senunary of Changes Sorted by Drawing and Mar %e,NAPSU22 Database Page 38of 146 Prmt Date: 11/1898
branbeg Na. M ark No. Line Nuniber . Category item No. teration Record Perled Method
- 12050-WMKS-0104B-2 IS-32W(SW-75) !0'-SI-425-153A-Q2 C-F-1 . C512 -6750 0 Comuments WEPSEM LONO SEAMS WELDS WERE :
BROKEN DOWN BY INTERSECTION IN REV 5
~
120M-WMKS41048-2 IS-33W(SW-28W) 10*-SI-415-1502-QI C-F-1 C5.12 2932 0 C. ;a WEPSEh! LONG SEAMS %TLDS %TRE BROKEN DOWN BY INTERSECTION IN REV. 5 12050 WMKS-0104B-2 IS-33W(SW-76) 10'-SI-415-1502-QI C-F I C5.12 6751 0 C WEPSEM IJDNO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 t 2050-WMKS-0104B-2 IS-34W(SW-70) . r-SI-440-153A-Q2 C-F-1 - C5.12 6752: 0 C. WEPSEM WNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104B-2 IS-34W(SW-71) 8'-SI-440-153 A-Q2 C-F-1 C5.12 2933 0 iC ;t WEPSEM LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12050-WMKS-0104B-2 LS-35W(31) r-SI-440-153A-Q2 C-F-l C512 6753 0 C. ; WEPSEM LONG SEAMS WELDS WERE BROKEN D0%W BY INTERSECTION IN REV.5 12050-WMKS-0104H-2 IS-35W(SW-69) r-SI-440-153 A-Q2 C-F-1 Cil2 2934 0 Cemunents WEPSEM LONG SEAMS WELDS %ERE ' BROKEN DOWN BY INTERSECI' ION IN REV. 5 12050-WMKS-0104B-2 LS-39W(SW-36W) 10'-SI-541-153 A-Q2 C-F-1 C5.12 2935 0
- C 3 WEPSEM LONO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104B-2 IS-39W(SW-79) 10'-SI-541-153A-Q2 C-F-1 C512 6754- 0
' C- _L WEPSEAf IDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV.5 12050-WMKS-0104B-2 13-40W(SW-37W) 10'-SI-541-153A-Q2 C-F-1 C5.12 2936 0 .C _L WEPSEM LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 ,12050-WMKS-0!04B-2 LS-40W(SW-38W) 10*-SI-54 I-153A-Q2 C-F-l C512 6755 0 =C. L WEPSEM LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTIONIN REV.5 t
- 12050-WMKS-0104B-2 LS-43W(SW-20W) 10'-SI-541-153A-Q2 C-F-1 C5.12 6757 0 Comunents WEPSEM LONG SEAMS WFIDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 [
I Sununary of Changes Sorted by Druning and Mark No., NAPSU22 Database Page 39of 146 Pnnt Date: 11/I8 93
A' Drawing No- Mark No. Line Number - Catetery item No. Location Record Peded Method . _a.._-~=_ 12050-WMKS-0104B-2 LS-43W(SW-26W) 10*-SI-425-153 A-Q2 C-F-l C5.12 .2937 0
- Comments LOCATED BETWEEN WEL3S SW 75- SW 71 -SW-26W. ADDED IN REY. 3. Ii LONG SEAhls WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-O'li452 LS-43W(SW-42W) 10'-SI-541-153 A-Q2 'C5i ' C5,12 2938 0 Comments WEPSEhl IJDNG SEAMS WELDS WERE BROKEN D0%W BY INTERSECTION IN REY. 5 ,
L 12050-Wh!KS-0104B-2 LS-43W(SW-71) 8*-SI-440-153A4)2 C-F-1 C5.12 7047- .O Cesuments LONG SEAMS WELDS WERE BROKEN IX)WN BY INTERSEC'IlON IN REY. 5 12050-WM KS-0104b LS-43W(SW-75) 10'-St-425-151A-Q2 C-F-1 C5.12 6756 0 Coenments LOCATED BETWEEN WELDS SW-75-SW-714W-26W. ADDED IN REV.3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104B-2 LS-44W(21) 10*-Sl425-153 A-Q2 C-F-1 C5.12 - 6758 0 < Comments LOCATED BETWEEN WELDS 21 -SW SW-27W. ADDED IN REV. 3. , LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12050-WMKS-0104B-2 IS-44W(SW-27W) 10*-SI-425-151A-Q2 C-F-1 . C5.12 2939 0 4 Ceaunents LOCATED BETWEEN WELDS 21 -SW-78 -SW-27W. ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 ; 12050-WMKS-0194B-2 LS-44W(SW-78) 10'-SI-541-153 A-Q2 C-F-1 C5.12 7048 0-Comunents WNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 120$0-WMKS-0104B-2 LS-52W(SW-67; 8*-SI 440-153 A-Q2 C-F-l C5.12 6759 0 Comunents WEPSEM IDNG SEAMS WELDS WERE , BROKEN DOWN BY INTERSICTION IN REV.5 12050-WMKS-0104B-2 13-52W(SW-68) 8-SI-440-153 A-Q2 C-F-1 CS I2 2940 0 : C ;3 WEPSEM LONO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV.5 t 12050-WMKS4)l04B-2 IS-80W(13) 10'-SI-541-153A-Q2 C-F-1 C5.12 2941 0 Comunests LOCATED BETWEEN WELDS 13 - SW-4IW - SW-45W. ADDED IN REV. 3. AS LS-55W CHANGED To LS-80W IN REV. .-
- 4. LONO SEAMS WEI.DS WERE BROKEN DOWN BY INTERSECTION IN REV. 5
- 12050-WMKS-0104B-2 LS-80W(SW-41W) 10'-St-541-153 A-Q2 C-F-1 C5.12 6760 0 Comuments I.DCATED BE TW 3N WELDS 13 - SW-41W- SW-45W. ADDED IN REV. 3. AS LS-55W CIIANGED TO LS-80W IN REV.
- 4. LONO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104B-2 IS-80W(SW-45W) 10'-SI-542-153 A-Q2 C-F-1 C5.12 7049 0 C_ .. " . LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 -
12050-WMKS-0104B-2 IS-81W(33) 10'-St-623-153A-Q2 C-F-1 C5.12 7050- 0 ComunentJ LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5
%munary of C1 manges Sorted by Drawing asul Meet No., NAPSU22 Database Page 40of 146 PrmtDate: 11/1898
- ._ _ ~ - . _ _ __ _. - ~- _ _ _ _ _ _
Drawing No- s Mark No. tjue Number - Category Item No- . Imcation Record Peded Method 12050-WMKS-0104B-2 LS-81W(48) 10*-51-541-15 Q2 C-F-I C5.12 2942 0 Comments LOCATED BETWEEN WFI DS 48 33. ADDED IN REY. 3. AS LS-56 CllANGED TO LS-81W IN RLV.
- 4. .
LONG SF AMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV 5
~
12050-WMKS-0104B-2 LS-81W(49) 10* SI-541-153 A-Q2 ' C-F-1 C5.12 676l 0 Caniments LOCATED BETWEEN WELDS 48 33. ADDED IN REV. 3. AS LS-56 CitANGED TO IS81W IN REV.
- 4. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-Ol04B-2 LS-82W(41) 10%51-623-153 A-Q2 C-F-1 C5.12 o762 0 Comme 2ts LOCATED BETWEEN WELDS 41 -42. ADDED IN REV. 3 AS LS-57W CIIANGED TO LS-82W IN REV.
- 4. LONG SEAMS WEl.DS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-OI04B-2 IS82W(42) 10%SI423-153A-Q2 C-F-1 C5.12 2943 0 Comments I.DCATED BETWE EN WELDS 4I - 42. ADDED IN R EV. 3. AS LS-57W CilANGED TO LS-82W IN REY.
- 4. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104B-2 LS-83W(39) 10*-SI-623-153 A-Q2 C-F-I C5.12 SFGD 2944 2 PT/UT Comments LOCATED BETWEEN WELDS 39 - 40. ADDED IN REY. 3. AS LS-58W CIIANGED TO LS-83W. IN REV. 4. CllANGED FROM PERIOD 0 TO PERIOD 2 IN INTERIM Cl!ANGE 93-
- 02. w!LL ALLOW Tile LONG SEAM WELD FO BE DONE WIT 11 Tile CIRCUMFERENTIAL WELD 39. REPLACES 104C-2 LS-53.
VERIFIEDIN TIIE FIELD ON 10'2694. 12050-WMKS4104B-2 IS-83W(40) 10*-SI423 153 A-Q2 C-F-1 C5.12 SFGD 6693 2 PTeUF - Comments LOCATED BETWEEN WELDS 39 40. ADDED IN INTERIM CIIANGE 93-02. WILL AttJDW TIIE LONG SEAAI WELD TO BE DONE WITH 11tE CIRCUMFERENTIAL WELD 40. REPIACES LS-53 ON 104C-2. 12050-WMKS-0104B-2 LS-84W(39) 10'-SI-623-153A-Q2 C-F-1 C5.12 SFGD 2945 2 PT!UT Connnents IDCATED BEEWEEN WELDS 38 - 39. WEPCl3() ADDED IN REV. 3. AS IS$9W Cl!ANGED TO LS-84W IN REV. 4. CllANGED FROM PERIOD 0 TO PERIOD 2 IN INTERIM CilANGE 93-02, WILL ALLOW TIIE IJONG SEAM WELD TO BE DONE WITil TIIE CIRCUMFERENTIAL WELD 39. 12050-WMKS-0104B-2 SW-21W(36) 17-St423-153A-Q2 C-F-1 C5.12 6763 0 Comments WEPSEM 0 CIIANGED FROM C5.11 TO C5.12 IN REV. 4 LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 120%-WMKS-0104B-2 SW-21W(37) 10'-SI-623-153A-Q2 C-F-1 C5.12 2948 0 Comments WEPSEM O CllANGED FROM C5.Il TO CS 12 IN REV. 4 IJDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104B-2 SW-22W(34) 10'-51-623-153 A-Q2 C-F-1 C5.12 6764 0 Comunents WEPSEM () Ci!ANGED FROM C5.I l TO C5.12 IN REV. 4. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. $ 12050-WMKS4104B-2 SW-22W(35) I0%SI-623-153 A-Q2 C-F-I C5. I2 2950 0 Comments WEPSEM () CIIANGED FROM C5.1 I TO C5.12 IN REV. 4. LONG SE A3!S WELDS WERE BROKEN DOWN BY INTERSECFION IN REV. 5 Summary of Clienges sorted by Drentig and Mark No,NAPSU22 Database Page 41 of 146 Prmt Date 11/18 98
Drewkeg No. - Mark No. IJne Number Catetory ~ Itcen No. . Imation Record Perled - Metlied
' 12050-WhlRS-0104B-2 SW-42W 6"-SI-416-1502-Qt C-C C3.20 - 7564- 0 Comunents PEN-60. NOT SELECTED
~~
- 18090-WhiKS-0!J453-2 SW-54W 6*-SI-531-1502.QI C-C ~ "C3 20 7565 0
- Comunents PEN-62 NOTSELECTED 120$0-WklKS-Ol04C-1 6 IT-SI-401-153A-Q2 C-F-I C5. l l SFGD VLVPIT 2993 1 ITUr Conenents ~ Cll ANGED FROh! PERIOD 2 TO PERIOD I IN INTERlhl CllANGE 93-02. WILL ALIDW Tile LONG SEAh! TO BE DONE WITil TIIE CIRCUhlFERENTIAL 12050-WhlKS-0104C-1 IA52(27) 12'-SI-402-153 A-Q2 C-F-l C5.12 2996 0 PTUr Comunents ~
LOCATED BETWEEN WELDS 27 SW-37. ADDED IN REV 3. CIIANGED FROh! PLRIOD I TO PERIOD 0 IN INTERIhl Cl[ANGE 93-02. REPLACED BY 1A4C-1 IS64(10) AND LS44(II). LONG SEAhls WELDS WERE BROKEN DORW BY INTERSECTION IN REV. 5 12050-WhiKS-Ol04C-1 IS-52(28) 12*-SI-402-153 A-Q2 C-F-1 ' C5,12 6765 0 PTUr Coninients LOCATED BETWEEN WELDS 27 SW-37. ADDED IN REY. 3. CIIANGED FROh! PERIOD I TO PERIOD 0 IN INTERIhl CllANGE 93-02. REPLACED BY I A4C-l LS-64(IO) AND IS44(lI). LONG SEAhls WELDS WERE BROKEN DOWN IlY INTERSECTION IN REV. 5 12030-WhlKS-0104C-I LS-52(SW-37) IT-St-414-153A-Q2 U-F-1 C5.12 7051 0 Coensnents IDNG SEAhlS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV 5 12030-WMKS-0104C-1 IS41(I) IT-SI-401-1 $3A.Q2 C-F-l C3.12 2997 0 Comunents WEPSEh!() l ' LONG SEAMS WFLDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-Ol04C-1 IS41(SW-49) 12*-SI-401-153 A-Q2 C.F-1 C5.12 6766 0 Comunents WEPSEh!O ' IDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WklKS-0104C-1 LS42(SW-49) 12'-SI-401-153 A-Q2 C-F-I C512 2998 0 Comunents WEPSEM 0 LONO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-WMKS-0104C-1 IS42(SW-50) IT-St-401-153A-Q2 C-F-1 C5.12 6767 0 Conunents WEPSEM 0 LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 120$0-WMKS-0104C-l LS43(39) IT-SI-401-153A-Q2 C-F-l C512 6768 0 Conuments WEPSEM () IDNO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104C-1 LS43(SW-50) 12'-51-401-153 A-Q2 C-F-l C3.12 2999 0 C. /- WEPSEh!O LONG SEAMS WEIDS WERE BROKEN DOWN BYINTERSECTION IN REV.5 Seunnaary of Gianges Sorted by Drawhig and Mark Na, NAPSU22 Database Page 42 of 146 Prmt Date: 11/14vs
.. . = =: : - -
Dnming No. M ari No. IJne Number Category item No. lawation Record Peeled hiethod 12050-WMKS-0104C-1 LS44(10) I T-SI-401-i $ 3A-Q2 C-F-1 C5.12 SFGD VLVPIT 3000 0 ITUr Conunents CllANGED FROM PERIOD 3 To rt RIOD 1 IN INTERIM CltANGE 93 02. REPIACED WITil 107E LS44W(SW44). ADDED INTERSECTION CIRCUMFERENTIAL WELD TO TIIE MARK NUMUER. INTERIM CIIANGE 9342. COULD NOT LOCATE DURING 93 OUTAGE. CilANGE D I ROM TERIOD I M PERIOD 0 IN REV. 5. REPLACED BY LS45(II) 104C-l. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104C-1 IS64(1I) ~~ lT-SI-401-153A-Q2 " C-F-I C5. I2 ~ SFGD VLVPIT 6691 0 ITit.TF Conunents CilANGED FROM PERIOD 3 TO PERIOD I IN INTERIM CllANGE 93 02. REPLACED WITIl 107E LS44W(SW44). ADDED INTERSECTION CIRCUMFERENTIALWELD TO THE MARK NUhlBER. INTERIM ClIANGE 93-02. COULD NOT LOCATE DURING 93 OUTAGE. CIIANGED FROM PERIOD 1 TO PERIOD 0 IN REV 5. REPLACED WITIIIS 7t(24).LONG SEAMS WELDS WERE IIROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104C-1 LS-65(l l) IT-SI-401 153 A-Q2 C-F- 1 C5.12 SFGD 3001 0 PTMF Comments WEPSEM O. CllANGED FROM PERIOD 0 TO PERIOD i IN REV. 5. REPLACING LS64(10)ON 104C-1 WillCII COULD NOT BE LOCATED IN 93 OUTAGE. I.DNO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5. CIL\NGED FROM PERIOD 2 TO PERIOD 0 IN REY. 6. REPIACED BY LS44(SW-46) 104C-2. WELD IS IN TIIE WALL 12050-WMKS-0104C-1 1.S46(SUMP) 1T-SI-403.I 53 A-Q2 C-F- 1 C5.12 6769 0 Comments WEPSEM 0 IDNO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 I2050-WMKS-0104C-1 IS66(SW-52) 12*-SI-403-153A-Q2 C-F-1 C5.12 3002 0 Comments WEPSEM 0 IDNO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12090-WMKS-0104C-1 IM7(SW-53) 12'-St-403-153A-Q2 C-F-1 C5.12 3003 0 Comments WETSEM O . LNG SE/ MS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WA'KS-0104C-1 IS67(SW-54) 12'-SI-403-153 A-Q2 C-F-1 C5.12 6770 0 Comments WEPSEM 0 LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104C-1 IS68(SW-54) 12'-SI-403-153A-Q2 C-F-l C5.12 3004 0 Comments WEPSEM 0 LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECT!ON IN REV 5 12050-WMKS-0104C-1 LS48(SW-55) 12*-SI-403-153 A-Q2 C-F-1 C5.12 6771 0 Comments WEPSEM () IDNO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104C-1 IS69(SW-55) IT-SI-403-153 A-Q2 C-F-1 C5.12 3005 0 Comments WEPSEM() IDNO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-WMKS-0104C-1 IM9(SW-56) IT-SI-403-153 A-Q2 C-F-I C5.12 6772 0 Conenents WEPSEM () LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12030-WMKS-0104C-1 LS-70(SUMP) 12'-SI-403-153A-Q2 C-F-1 C5.12 6773 0 Commenta WEPSEM O LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 Smumary of Gianges Sosted by Drawing and Mark Net NAPSU22 Database Page 4J of Id6 rnst Date: 11/1898
6 1 Draning Ns Mark No- IJne Number Category . ' Item No- Imestion Record Perled Method 4 12050-WMKS-0104C-1 IS-70(SW-57) 12'-51-403-l 53A-Q2 C-F-1 C5.12 3006 0 Comunants _ WEPSEM 0 tDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV 5 12050-WMKS-0104C-1 LS-7t(24) 12*-SI-402-153 A-Q2 C-F C5.12 SFGD VLVPIT 3007 0 PTiUT C.- .e WEPSEM (). CIIANGED FPOM PERIOD 0 TO PERIOD 2 IN REY. 5 REPLACING SW64(II)WillCl! COULD NOT BE IDCA1T.D IN TIIE 93 OtJFAGE IDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5. CIIANGED FROM PERIOD 2 TO PERIOD 0 IN REV. 6. REPLACED BY 13-11(2) ON 104C-2. WELD 2 IS AIREADY SCIIEDULED, WILL ALLOW LONG SEAM TO BE DONE WITil CIRC. WE1D. 12050-Wh!KS-0104C-1 - IS-71(PEN 68) 12*-St-402-153 A-Q2 ~ ~ ~ C-F-1 ~ ~ 3I2 SFGD VLVPIT 7220 0 Conuments WEPSEM (). LONG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5. 12050-WMKS-0104C-1 LS-72(24) 12'-51-402-153A-Q2 C-F-1 C5.12 . SFGD VLVPIT 3008 0 PTATF , Comments CIIANGED FROM PERIOD 2 TO PERIOD 0 IN INTERIM ClIANGE 93-02. REPLACED WITil LO4C-2 LS-61(19) AND 1341(20). WILL ALLOW TIIE IDNG SEAM WELD TO BE DONE ! WITil TIIE CIRCUMFERENTIAL WELD.LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 . 12050-WMKS-0104C-1 LS-72(25) 12*-SI-402-! 53 A-Q2 C-F-1 C3.12 SFGD VLVPIT 6774 0 PTUF Comunents CllANGED FROM PERIOD 2 TO PERIOD 0 IN INTERIM C!!ANGE 93-02. REPLACED WITil LD4C-2 LS-6I(19) AND IS-6I(20). WILL ALLOW TIIE LONG SEAM WELD TO BE DONE WITIl TIIE CIRCUMFERENTIAL WELD.LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV,5 ,
.12050-WMKS-0104C-1 15-73(40) 12*-SI-402-153A-Q2 C-F-I - C5.12 3009 0 [
Comunents WEPSEM () LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 I2030-WMKS-0104C-1 LS-73(SW-59) I2*-51-402-I 53A-Q2 C-F-1 C5.I2 6775 0 Comunents WEPSEM O LDNG SEAMS WEIDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 l 12050 WMKS-0104C-1 IS-74(SW-54) 12"-SI 402-153A-Q2 C-F-1 C5.12 3010 0 [ Comuments WEPSEM 0 IDNG SEAMS WELDS WERE , BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104C-1 IS-74(SW-60) 12*-SI-402-153A-Q2 C-F-1 C5.12 6776 0 4 ! C- .c WEPSEM () LONG SEAMS WELDS WERE DROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104C-1 LS-75(34) 12'-SI-402-153 A4)2 C-F-1 C5.12 6777 0 ! Conuments WEPSEM () LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV 5 ; 12050-WMKS-0104C-1 IS-75(SW-60) 12*-SI-402-153A-Q2 C-F-1 C5.12 3011 0 1 Comuments WEPSEM 0 LONG SEAMS WFlDS WERE - BROKEN DOWN BYINTERSECTION IN REV.5 12050-WMKS-0104C-1 IS-76(6) 12'-SI-401-153A-Q2 C-F-1 C5.12 SFGD 3012 1 PTATF ( C_ . ; :s LOCATED BETWEEN WELDS 8 17. ADDED IN REV. 3. ADDED INTERSECTION CIRCUMFERENTIAI WELD TO THE MARK NUMBER. INTERIM CIIANGE 93-02. ,
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I Cenunary of Changes Sorted by Drewheg and Mark No NAPSU22 Detsbase Page 44 of 146 Prmt Dare: 11/l& 98
- . .-- _ _. - - - - - __ _ -__._-____ _ -__ _ __ _ _ _ I
i r,I Draning No. Alark No. I.in hm'5r' n Item No. IecU Record Period hiethod 12050-WhlKS-0104C-1 IS-76(8) I2 -SI-401-153A-Q2 C-F-1 C5.12 SFGD 6690 I PT!UF t Comments ADDED IN INTERIM CII ANGE 93-0210 lNDICAT E Wil AT END OF 111E I ONG SEAh! TO DO.
^
12050-WhlKS-0104C-2 2-SI-R-53 10'5I428 I55A-Q3 d~~ F2.0 SFGD 3063 0 VT-3 Comments A11 ARES. CllANGED FROh! PFRIOD 2 TO PER?OD 0 IN REY. 5 ONLY NEED TO EXAhlINE 15*6 OF SUFPORTS ON LINES RECEIVING ANOTl!ER TYPE OF EXAM. 12050-WMKS-Ol04C-2 2-St-R-57 10'-S1429-153 A422 F-A FI .0 ValvePit 3066 3 VT-3 Comments Bil AGUD2. A6.ied new to the plan Oh Pev. I I to increase percentage of class 2 supports to 15% per relief CS-1. 120$0-WMKS4104C-2 2311 id5429-153A-Q2 C-C C3.20 SFGD 3052 0 PT Comme 3ts 100's NEAR TIIE LADDER TO TIIE VALVE PIT. Sit-55 NOT SELECFED CilANGED FROkl PERIOD 3 TO PERIOD 0 REV.7. RELIEF REQUEST NDE-21 ALLDW USE OF CODE CASE N-509 WIIICll ONLY REQt'IR ES 10% OF TIIE INTEGRAL ATTACllh!ENTS TO BE EXAkilNED. I2050-WM KS-0104C-2 LS-10(4) 10'-SI-628-153 A-Q3 C-F-1 C5.12 SFGD 3G92 2 PT/ITF Comments LOCATED BETWEEN WELDS 4 - 5 WEPCB O ADDED IN REV,3. CllANGED FROM PERIOD 0 TO PERIOD 2 IN REY. 5. REPLACING LS43W(SW43) 107E. MILLTEST REPORT BQOI. RT REPORT OF LONG SEAh! WITil MILI. TEST REPORT TAPE SXBR FRAME 821. IDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-Ot04C-2 IS-10(5) 10*-SI428-153 A-Q2 C-F-I C5.12 SFGD 6734 2 PT/UT Comments LOCATED BETWEEN %T.LDS 4 - 5 CllANGED FROM PERIOD 0 TO PERIOD 2 IN REY. 5. REPLACING LS43W(35) ON 107E. MII1 TEST REPORT BQ01. RT REPORT OF LONO SEAh! WITil MILL TEST REPORT TAPE 5XBR FRAME 821. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5
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12050-WMKS-0104C-2 LS-II(2) 10*-SI428-153A-Q3 C-F I C5.12 3093 2 PT/UF Comments LOCATED BETWEEN WELDS 2 - 3. WEPCB 0 ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5. CIIANGED FROM PERIOD 0 TO PERIOD 2 IN REV. 6. REPLACING LS-71(24)ON 104C-l. %TLD 2 IS ALREADY SCIIEDULED. FIELD KTRIFIED. 12050-WMKS-0104C-2 L&ll(3) 10'-S1428-153A-Q3 C-F-1 C5.12 6778 0 Comments LOCATED BET %IEN WELDS 2 - 3. WEPCB () ADDED IN REV 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS4104C-2 IS27(2) 10E 529-153A-Q2 C-F-1 C5.12 SFGD 3094 2 PT!1TF Comments LOCATED BETWEEN WELDS 2 - 3. WEPCB O ADDED IN REV. 3. CilANGED FROM PERIOD 0 TO PERIOD 2 IN INTERIM CIIANGE 93-02. ADDED INTERSECTION CIRCUMFERENTIAL WELD TO TIIE MARK NUMBER. INTERIM CilANGE 93-02. FIELD VERIFIED. 12050-WMKS-0104C-2 LS-27(3) 10'-SI429-153 A-Q2 C-F-1 C5.12 SFGD 6694 2 PT/UF Comments LOCATED BETWEEN WELDS 2 -3. WEPCB O ADDED IN INTERIM CilANGE 93-02 ADDED INTERSECTION CIRCUMFERENTIAL WELD TO TIIE MARK NUMBER. FIELD VERIFIED. 1203C-WMKS-0104C-2 LS-28(4) 10'-51429-153A-Q2 C-F-1 C5.12 3095 0 Comments LOCATED BETWEEN WELDS 4 - 5. ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-WMKS-0104C-2 LS-28(5) 10iSI429-153A-Q2 C-F-1 C5.12 6779 0 Comments LOCATED BETWEEN WELDS 4 - 5. ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN R EV. 5 Summary of Changes Sorted by Drawing and Mart Na. NAPSU22 Database Page 45 of 146 PnneDate: 11/18 93
.k Drawing No. Stark No . Line Neniher gn Itene No. . termelon Record. Period Method 12050 Wh!KS-OI04C-2 IS29(5) 10'-SI429-153 A-Q2 C-F-1 C3.12 3096 0 Comunents . LOCATED BET % TEN WELDS 5 - 7. ADDED IN REV. 3. 1DNG SEAhtS WEIDS WFRE BROKEN DOWN BY INTERSECTION IN REY 5 12050-WhtKS-0104C-2 ' LS-29(7) 10'-S!429-153A-Q2 CI-I ' C5.12 6780 0 Conunents LOCATED BET % TEN WELDS 5 - 7. ADDED IN REY. 3. -LONG SEAhtS WELDS WERE IIROKEN DOWN BY INTERSECTION IN REV. 5 12050-Wh!KS-Ol04C-2 LS-30(16) 10'-SI429-151A-Q2 C-F-1 C5.12 6781 0 Comunents LOCATED BETWEEN WELDS 16 - 17. ADDED IN REY. 3. LONG SEAktS WELDS WERE BROKEN DOWN BY INTERSECT 10N IN REY. 5 12050-WktKS-0104C-2 LS-30(17) 10'-SI429-153A-Q2 C-F-1 C5.12 3097 =0 Conwnents LOCATED BETWEEN WELDS 16 - 17. ADDED IN REV. 3. IDNG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WhtKS-0104C-2 1.3-31(14) 10'-SI429-153A-Q2 C-F-1 C5.12 6782 0 ' Casanoents LOCATED BETWEEN WELDS 14 - 15. ADDED IN REV. 3. LONO SEAh15 WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WhtKS-0104C-2 LS-31(15) 10*-SI429-153A-Q2 C-F-I C5.12 3098- 0 Ceaunents LOCATED BETWEEN WELDS 14 - 15. ADDED IN REV. 3. LONG SEAhts WELDS WERE BROKEN DOWN BY INTERSECTION LN REV. 5 -
12030-Wh1KS-Ol04C-2 LS-32(12) 10'-SI429-153 A-Q2 C-F-I C5.12 6783 0 Counnents LOCATED BE1TvTEN WELDS 12 - 13. ADDED : N REV. 3. LONG SEAktS WELDS WERE BROKEN DOWN BY INT _RSECTION IN REV. 5 12030-WhtKS-0104C-2 LS-32(13) 10*-S1429-153A-Q2 C-F-1 C3.12 3099 0 C :s LOCATED BETWEEN WELDS 12 - I 3. ADDED IN REV. 3. LONG SEAhls WELDS WERE BROKEN DOWN BY INTERSECTION IN REV,5 12050-WhtKS-0104C-2 1&43(3) 12'-SI-414-153 A-Q2 C-F-l C512 3100 0 Comunents WEPSEh!O IDNO SEAktS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV.5 12050-WhlKS-0104C-2 IS43(SW-38) 12'-SI-414-153A-Q2 C-F-l C5.12 6784 0 , Comunents WEPSEh!() IJONO SEAhtS WELDS %TRE BROKEN DOWN BY IVTERSECTION IN REV. 5 12090-WhlKS-0104C-2 IE-44(9A) 12*-SI-414-153A-Q2 C-F-1 C5.12 3101 0 Canuments WEPSEht () IDNO SEAhtS WELDS WERE BROKEN DOWN BY INTERSECT 10N IN REV.5 12050-WhfKS-0104C-2 LS-44(SW-32) 12*-St 414-153A-Q2 C-F-I C5.12 6785 0 Canunents WEPSEh!O IDNO SEAh!S %TLDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 Sinnenary of Changes Sorted by Drawing and Wrk No., NAPSU22 Database Page 46 of 146 PnarDare.* 11/I898
Drawing No. Mark No. Iine Number Category item No- Location _ _ _ _ - _ _ Record Period Method 12090-WMKS-0 iO4C-2 13-45(7) I 2'-51-414-153 A-Q2 C-F-1 C512 3102 0 Conunents WEPSEM () LONG SEAMS WELDS WERE BROKEN DOWN BY IN1ERSECTION IN RI Y 5
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I 2050-WM KS-0104C-2 M-45(SW-39) I T-SI-45 4-153 A-Q2 C-F- l C512 6786 0 Comments WEPSEM () IDNG SEAMS WEIDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104C-2 13-46(28) ~ I T-SI-414-153 A-Q2 C-F-1 C5.12 6787 0 Conunents WEPSEM () IDNG SEAh!S WELDS WERE BROKEN IX)WN BY INTERSECTION IN REV. 5 12090SM KS-0104C-2 LS46(29B) I T-SI-414-153 A-Q2 C-F- 1 C5.12 3103 0 Comments WEPSEM () IDNO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-WMKS-0104C-2 LS-47(SW-33) 12*-SI-414-153 A-Q2 C-F-l C5.12 3104 0 Comments WEPSEM () LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12030-WMKS-Ol04C-2 LS-47(SW-40) ~ 12'-St-414-153 A-Q2 C-F 1 C5.12 6788 0 Comments WEPSEM () IDNO SEAMS WELDS WERE BROKEN IX)WN BY INTERSECTION IN REY. 5 IS030-WMKS-0104C-2 IS48(15 A) tr-SI-414-153A-Q2 C-F-1 C5.12 6789 0 Comments WEPSEM () 1DNG SEAMS WEIDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12050-WMKS-0104C-2 LS-48(SW-42) IT-St-tl4-151 A-Q2 C-F-l C5.12 3105 0 Comments WEPSEM() LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12090-WMKS-0104C-2 IS49(19) 12*-SI-414-153 A-Q2 C F-1 C512 3106 0 Comments WEPSEM () IDNO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12090-WMKS-0104C-2 LS-49(SW-35) tr-SI-414-153A-Q2 C-F-1 C512 6790 0 Comments WEPSEM () LONG SEAMS WEIDS WERE EROKEN DOWN BY INTERSECTION IN REY. 5 12050-WMKS-Ol04C-2 LS-50(20) 12'-SI-414-153 A-Q2 C-F-I C512 SFGD VLVPIT 3107 0 PT/tJT Comments CIIANGED FROM PERIOD 3 TO PERIOD 0 IN INTERIM CII ANGE 93-02. REPLACED BY 107B LS-74(14). WILL AllDW TIIE IDNO SEAM WELD TO BE DONE WITil Tile CIRCUMFERENTIAl WELD.LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104C-2 LS-50(SW-36) 12'-SI-414-153 A-Q2 C-F-1 C512 SFGD VLVPIT 6791 0 PT/ITF Comments CIIANGED FROM PERIOD 3 TO PERIOD 0 IN INTERIM CIIANGE 93-02. KEPLACED BY 107B LS-74(14)t WIII ALLOW TIIE IDNG SEAM WEID TO BE DONE Willi TIIE CIRCUMFERENTIAL WELD.LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 Summary of Ganges serted by Drawing and Mark No,NAPSU22 Database Page 47of 146 PnntDate: 11/18 98
4 L Drawing No. Mark No- time Nusnher - Category I.ene No. Lacstlen Record Pested Meehed
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12050-WMKS-Ol04C-2 IS$1(23) 12"-SI-414-153 A-Q2 C-F-1 C5.12 3108 0 Comuments WEPSEM O _ IDNG SEAMS WELDS WERE i BROKEN DOWN BY INTERSECTION IN REY.5 t ' 12050-WMKS-0104C-2 LS-51(SW-37) 12"-SI-414-153 A-Q2 C-F-l C5.12 6792 0 , C._ a WEPSEh! O IDNG SEAMS WELDS WERE r T BROKEN DOWN BY INTERSECTION IN REV. 5 h 12050-WMKS-0104C-2 LS-53(1) 12'-SI-414-153 A-Q2 C-F-1 C5.12 6793 0 PT/UT r Conunents LOCATED BETWEEN WELDS 14 - 1. ADDED IN REV. 3. CilANGED FROM PERIOD 2 PERIOD 0 IN INTERIM CIIANGE 93-02 REPLACE 0 Wml 104B-2 LS-83W(39) AND IS 83W(40). Will ALLOW TIIE LONG SEAM WELD TO BE DONE WITII TIIE CIRCt 4fFERENTIAL WELD. IDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5
. 12050 WMKS-0104C-2 LS-53(14) 12'-SI 414-153A-Q2 C-F-1 C5.12 3109 0 PTitJF I ADDED IN REV. 3. CilANGED FROM PERIOD 2 PERIOD 0 IN INTERIM CIIANGE 93-02 REPIACED WITI! 104B-2 IS83W(39) AND LS-Comuments LOCATED BETWEEN WELDS 14 - 1.
83W(40) WILL ALLOW TIIE LONG SEAM WE1D TO DE DONE WITil Ti!E CIRCUMFERENTIAL WELD. IDNG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0104C-2 LS41(19) 12'-SI-405-153 A-Q3 C-F-1 C5.12 SFGD 3110 2 PTAJF t f C _- LDCATED BETWEEN WEIDS 19 - 20. WEPCB () ADDED IN REY. 3. CIIANGED FROM PERIOD 0 TO PERIOD 2 IN INTERIM CIIANGE 93 02 ADDED INTERSECTION CIRCUMFERENTIALWEID TO TIIE klARK NUMBER. INTERIM CIIANGE 93 02. ; 12030-WMKS-0104C-2 LS41(20) 12'-SI-405-153 A-Q3 C-F-1 C5.12 SFGD 6692 2 PTUT ; r t C.. a IDCATED BETWEEN WELDS 19 - 20. WEPCB O ADDED IN INTERIM CilANGE 9342. ADDED INTERSECTION CIRCUMFERENTIAL WELD TO TIIE MARK NUMBER. INTERIM CIIANGE93-02. REPLACES LS-72 ON 104C-1. j f 12050-WMKS-0104C-2 LS42(1) 10*-SI428-153A-Q2 C-F-1 C5.12 7052 0 j C- = IDNG SEAMS WEIDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 t 12050-WMKS-0104C-2 LS42(17) 12*-SI-405-153A-Q3 C-F-1 C5.12 6794 0 PTUT f C = LOCATED BETWEEN WELDS 17- I8. WEPCB 0 ADDEDIN REY. 3. CIIANGED FROM PERIOD 1 TO PERIOD 0 IN INTERIM Cl!ANGE 93-02. REPIACED WITTI 107E LS43W(SW-63). WILL ALLOW T11E LONG SEAM WEID TO BE DONE WITil A CIRCUMFERENTIAL WFLD, ; LONG SEAMS WEIDS WERE BROKEN DOWN BY INTERSECFION IN REV. 5 12050-WMKS-0104C-2 LS42(18) 12'-SI-405-153A-Q3 C-F-1 C5.12 3tli 0 PT<UF Conunents LOCATED BETWEEN WELDS 17 - 18. WEPCB 0 ADDED IN REY. 3. CllANGED FROM PERIOD 1 TO PERIOD 0 IN INTERIM CILANGE 93-02. REPLACED WITil 107E LS43W(SW-
- 63) Will ALLOW TIIE LONG SEAM WELD TO BE DONE WITil A CIRCUMFERENTIAL WELD. -!
LONO SEAMS WELDS WERE BROKEN DOWN BY INTERSECFION IN REV. 5 12050-WMKS-0104C-2 1543(17) 12'-SI-405-153A-Q3 C-F-I C5.12 3112 0 Comunents LOCATED BETWEEN WELDS 41 A- 17. WEPCB O ADDED IN REV. 3. LONG SEAMS WELDS %TRE BROKEN DOWN BY INTERSECTION IN REV. 5 ' Sununary of E1 enges Sorted by Drawing and Mark No., NAPSU22 Database Page 48of 146 PnnrDate: 11//8 98 _ _ _ . _ . _ . _ _ _ _ . . _ _ _ . _ _ _ _ _________._______._____________________m______ _ _ _ _ _ _ . _ _ _
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1 . _x -- a r_ Doming No. Stark No. . IJne Number Category item No. Location Reccrd Period Method 12050-WhlKS-Ol04C-2 LS-63(41 A) 12*-SI-405-1 UUQ3 C-F-1 C512 6795 0 Canments LOCATED BETWEEN WELDS 4I A- 17. WEPCB() ADDED IN REV 3. LONO SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WhfKS-0104C-2 IS44(40A) 12'-SI-405-153 A-Q3 C-F-1 C5.12 3 13 0 PT,UT-0,45 Comments LOCATED BETWEEN WELDS SW 46 - 40A. ADDED IN REV. 3. LONO SEAKIS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050 WhlKS-0104C-2 IS-64(SW-46) 12*-SI-405-153 A-Q3 C-F-1 C5.12 6796 2 PT/UT Comments LOCATED BETWEEN WELDS SW 40A. ADDED IN REV 3. LONG SEAhfS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5. CIIANGED FROh! PERIOD 0 TO PERIOD 2 IN REV. 6. REPLACING LS45(II) 104C-2. SW-46 IS ALREADY SCIIEDULED. 12050 WhlKS-0104C-2 LS-74(21 A) 12*-SI-405-153 A-Q3 C-F- 1 C5.12 6797 0 Comments LOCATED BETWEEN WELDS 21 A - 22C. 4TPCB () ADDED IN REV. 3. LDNG S *.AhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WhlKS-0104C-2 IS-74(22C) 12'-SI 405-153 A-Q3 C-F-1 C5.12 3114 0 Comments LOCATED BETWEEN WELDS 2 t A - 22C. WEPCB () ADDED IN REV. 3. IDNG SEAhls WELDS WERE BROKEN DOWN BY INTERSECTION IN REV.5 12050-WhlKS-0104C-2 LS-9(6) 10*-51428-153 A-Q3 C-F-1 C5.12 3115 0 Comm2nts LOCATED BETWEEN WELDS 6 - 7. WEPCB () ADDED IN REY. 3. LONG SEAhls WELDS WERE BROKEN DOWN BY INTERSECTION IN REV 5 12050-Wh!KS-0104C-2 13-9(7) 10'-SI428-153 A-Q3 C-F-1 C512 6798 0 Comments LOCATED BETHIEN WELDS 6 - 7. WEPCB () ADDED IN REV. 3. LONG SEAhfS WELDS WERE BROKEN DOWN BY INTFRSECTION IN REV. 5 12050-WhlKS-0104C-2 SW-25(8) 10'-S1429-153 A-Q2 C-F-l C5.12 6799 0 Comn2nts WEPSEh! LONG SEAhfS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. $ 12050-WMKS-0104C-2 SW-25(9) 10*-SI429-153 A-Q2 C-F-1 C5.12 3116 0 Comments %TPSEh! IJONG SEAhfS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WhfKS-0104C-2 SW-26(II) 10'-51429-153A-Q2 C-F-I C5.12 SFGD 3tl7 2 PT!!JT Comments WEPSEht. CIIANGED FROh! PERIOD 0 TO PERIOD 2 IN INTERikt CilANGE 93-02. WILL ALLOW TIIE IDNG SEAh! WELD TO BE DONE Wml TIIE CIRCUhfFERENTIAL WELD 11. ADDED INTERSECTION CIRCUhfFERENTIAL WELD TO TIIE htARK NUhlBER INTEPJh! CIIANGE 93-02. 12050-Whf KS-0104C-2 SW-26(9) 10*-S!429-153 A-Q2 C-F-1 C5.12 SFGD 7221 0 PT<UT Comments WEPSEht. ADDED INTERSECTION CIRCUhfFERENTIAL WELD TO TIIE hiARK NUhlBER. REV. 5 12050-WAIKS-0104C-2 SW-34(15A) 12'-SI-414-153 A-Q2 C-F-1 C5.12 SFGD VLVPIT 6800 i PT/UT Comments LONG SEAhfS WELDS %TRE BROKEN DOWN BY INTERSECTION IN REY. 5 Summary of Changes Sorted by Drawing and Blark No., NAPSU22 Database Page 49of 146 Prmt Dare: 11/189s I I 9 l l M
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IW New - - . - - - - _ . Mark No. I.ine Nuneber Categen item No. Location Record Perled Method -[ 12050-WhlKS-0104C-2 SW-34(17) 12*-51-4 I4-153A4)2 C-F-l C5.12 SFGD VLVPIT 3120 I PTiUT C .J. IDNG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5
. lS050-WhlKS-OI04DA 2 RS-5-622 - 12*-RS-407-153 A-Q2 _ F-B iib ~ SFGD VLVPIT 3134 0 YT-3 - Canunents A IIASUPC. CIIANGED FROM PERIOD 2 TO PERIOD 0 IN REV. 5. ONLY NEED TO EXAhlWE 15*4 OF SUPPORTS ON LINES RECEIVING ANOTilER TYPE OF EXAM. .12030-Wh!KS4104DA 5A 12*-RS-408-153 A-Q2 - C-F-1 -C511 - SFGD VLVPIT 3138 .O PT/IJr '-
C ./. CilANGED FROM PERIOD 2 TO PERIOD 0 IN REV. 6.142 TOTAL RS WELDS DO 7 5*. = 1I,17 SCIIEDULED. REDUCE Tile SCIIEDULED WEIDS TO 14 TO ALIDW 3 BUFFER WELDS. . 12050-WMKS-0104DA LS-43(1) 12*-RS-407-153 A-Q2 C-F-1 C5.12 3148 0 Conap-Ws WEPSEM O IDNG SEAMS WELDS WERE f BROKEN DOWN BY INTERSECTION IN REV. 5 ! 12050-WMKS-0104DA IS-43(SW-23) 12'-RS-407-153 A-Q2 C-F-1 ~ C512 6801 0 t C C WEPSEM 0 LDNG SEAhlS WELDS WERE ! BROKEN DOWN BY INTERSECTION IN REV. 5 ,
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12050-WMKS-0104DA LS-44(SW-23) 12 -RS-407-153 A-Q2 C-F-1 C512 6802 -0 Caennients WEPSEh!() IDNG SEAhfS WELDS WERE . BROKEN DOWN BY INTERSECTION IN REV. 5 t 120$0-WMKS-0104DA ES-44(SW-24) 12*-RS-407-153A-Q2 C-F-1 C512 3142 0 t Comuments WEPSEM () LONG SEAMS WELDS WERE , BROKEN DOWN BY INTERSECTION IN REV. 5 [ 12030-WhlKS-OI04DA IS-45(7A) 12'-RS-407-153 A-Q2 C-F-I C5.12 6803 0 '[ Conenents LONG SEAMS WELDS WERE I WEPSEh! O , BROKEN DOWN BY INTERSECrlON IN REV. 5 ; 12030-WMKS-0104DA LS-45(SW-24) IT-RS-407-153A-Q2 C-F-1 C5.12 3143 0 C ..n WEPSEhl 0 tDNG SEAhfS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 ; 12050-WklKS-0IO4DA LS-46(6A) 12*-RS-407-153 A-Q2 C-F-I C5.12 3144 0 Comunents WEPSEh!() 1DNG SEAhfS WELDS WERE ; BROKEN DOWN BY INTERSECTION IN REV. 5 ; 12030-WMKS4104DA IS-46(SW-25) 12*-RS-407-153 A-Q2 C-F-1 C512 6804 0' Comnients WEPSEM 0 f.DNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 ! 12050-WMKS-0104DA LS-47(SW-25) 12 -RS-407-153A-Q2 C-F-1 C3.12 SFGD VLVPIT 3145 0 PTMT Ceninients COULD NOT LOCATE IN 92. CIIANGED FROM PERIOD I TO PERIOD 2 IN REV. !
- 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 [
Samaniary of Onantes Sorted by Dreatng and Mark No NAP 3U22 Database Page 50of 146 Prmt A'Wer 11/18 98 6
s - Drawing No. Mark No. Line Nennber Category Iten No. ' Location . Record Period Metlend .
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12050-WMKS-0104DA LS-47(SW-26) . I2*-RS-407-153A-Q2 C-F-I C5.12 SFGD VLVPIT . 6805 O PT/UT Coniements COULD NOT LOCATE IN 92. CIIANGED FROM PERIOD I TO PFRIOD 2 IN REV,
- 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5
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12050-WMKS-0104DA LS-48(PEN 66) I T-RS-407-153 A-Q2 'b5 C5.12 6806.. O Coninnents - WEPSEM O IANG SEAhtS WELDS WERE ' BROKEN DOWN BY INTERSECTION IN REV. 5 I2050-WhlKS4104DA LS-48(SW-26) 12'-RS-407-153 A-Q2 C-F-I C5.12 . 3146 0 Conimients WEPSEM () LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12050-WMKS-0104DA LS-49(SUMP) 12*-RS-424-153A-Q2 C-F-1 C5.12 6807 0 Conunents WEPSEM() IDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12050-WMKS-0104DA LS-49(SW-29) IT-RS-424-153 A-Q2 C-F-1 C5.12 3147 0 Conineents . WEPSEM O IDNG SEAMS WELDS WERE BROKEN DOWW BY INTERSECTION IN REV. 5 12050-WMKS-OI04DA LS-50(SW-30) IT-RS-424-153 A-Q2 ' C-F-1 C512 3I48 0 Conimients WEPSEM O IANO SEAMS WEIES WERE BROKEN DOWN BY INTERSECFION IN REV. 5 12050-WMKS 0104DA IS-50(SW-31) 12*-RS-424-153 A-02 C-F-1 C5.12 6808 0 Cosianents WEPSEM 0 LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV.5 12050-WMKS-0104DA LS-5 t(SW-31) IT-RS-424-153A-Q2 C-F-1 C5.12 3149 0 , Cenernents WEPSEM () IDNO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV.5 12050-WMKS4104DA IS-51(SW-32) 12*-RS-424-153A-Q2 C-F-1 C5.12 6809 0 Cosnsnents WEPSEM 0 LONG SEAMS WELDS WERE BROKEN DOwW BY INTERSECTION IN REV. 5 13030-WMKS-0104DA 13-52(3) 1T-RS-424-153A-Q2 C-F-1 C5.12 6810 0 Conunents WEPSEM 0 LONO SEAMS WELDS %TRE BROKEN DOkN BY INTERSECTION IN REV. 5 [ 12050-WMKS-0104DA IS-52(SW-32) 12*-RS-424-153A-Q2 C-F-1 C5.12 3150 0 Ceauseents IDNG SEAMS WELDS WERE l WEPSEM 0 BROKEN DOWN BY INTERSECTION IN REV.5 12050-WMKS-0104DA 13-53(3) 12*-RS-424-153A-Q2 C-F-1 C5.12 3151 0 l C ;/- WEPSEM 0 IDNO SEAMS WEl.DS WERE l BROKEN DOWN BY INTERSECTION IN REV.5 i Sunusesry of Clasages Sorted by Drawing and Mark No., NAPSU22 Datahame Page 51of N6 Pnnt Date: 11/1R 98
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Drawing Na Alark No. line Number Category Item No. Iewation Record Period Metted ~
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i ' 2050-WhfKS-0104DA LS-53(SW-33) 12*-RS224-153A-Q2 C-F-I- - C5.12 6811 0 C. -.3 WEPSEh! O LONG SEAkiS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12030-walks 4)l04DA ' ~ I.S-54(SW-33) ii-RS-424-153A-Q2 C-F-1 ' C5512 3152 0 Ceaunents WEPSEh! O LONO SEAhtS WEIES WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-WhtKS-OlG4DA LS-54(SW-34) 12*-RS-424-153 A-Q2 C-F-1 C5.12 ~ 6812 0 Cenaments . WEPSEh!() IDNO SEAMS WELDS WEkE ' BROKEN DOWN BY INTERSECTION IN REV. 5 12030-WktKS4104DA LS-55(SW-34) 12*-RS-424-153 A-Q2 C-F-1 C512 3153 0 Ceaunents WEPSEkl O LONO SEAktS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12050-WhtKS-0104DA IS-55(SW-35) 12*-RS-424-153A-Q2 C-F-1 C512 6813 O Ceaunents WEPSEh! O LONO SEAkiS WELDS WERE DROKEN DOWN BY INTERSECTION IN REV. 5 12050-WhtKS-0104DA IS-56(SUhtP) 12*-RS-424-153 A-Q2 C-F-1 C512 6814 0 Conunents WEPSEkt () , LONO SEAhts WELDS WERE BROKEN DOWH BY LNTERSECTION IN REV. 5 12030-Whf KS-0104DA LS-56(SW-37) 12'-RS-424-153 A4)2 C-F-l C512 3154 0 Ceaunents WEPSEh! O LONG SEAkiS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 3 12050-Whf KS-0104DA 13-57(SW-38) 12*-RS-408153 A-Q2 C-F-1 C5.12 3155 0 Comunents WEPSEh! O LONG SEAhtS WFLDS WERE BROKEN DOWN BY INTERSECTION IN REV.5 12050-WEtKS-0104DA IS-57(SW-39) 12*-RS-408-153A4)2 C-F-I C5.12 6815 0 Ceaunents WEPSEh! O IDNO SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV.5 12050-WhlKS-0104DA IS-58(SW-39) 12*-RS-408-153 A-Q2 C-F-1 C5.12 SFGD VLVFIT 6816 0 PTMF Comunenta IDNG SEAMS WEIES WERE BROKEN DOWN BY INTERSECTION IN REV. 5. CitANGED FROh! PERIOD 31U PERIOD 0 IN REV. 6. REPIACED BY LS-74(19) 104L 12030-Wh!KS-0104DA LS-58(SW-40) 12*-RS-408-153A-Q2 C-F-1 C5.12 SFGD VLVPIT 3156 0 PTMF Connnents CIIANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 6. REPLACED BY LS-74(SW-73). , 12030-WMKS-0104DA IS-59(5A) 12'-RS-408-153A-Q2 C-F-1 C5.12 SFGD VLVPIT 3157 0 l'F/UF Comuments CilANGED FROM PERIOD 2 TO PERIOD 0 IN REV. 6. 142 TOTAL RS WELDS D07.5% = 11,17 SCIfEDULED. REDUCE TIIE SCIIEDULED WELDS TO 14 TO ALLOW 3 BUFFER WELDS.
+
Susannery of Changes Sorted by Drening and Mark No,NAPSU22 Database Page 51of146 Pnnt Dore: 11/18 98
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= - - = = = . - = . = = = --
3rawing No. Mark No- IJne Number ('ategory item No. location Reconi Period hiethod
- _ .: =:-
' 2050-WhlKS-0104DA IS-59(SW 40) I T-RS-408-153 A-Q2 C-F-1 C5.12 SFGD VLVPIT 6817 0 IT/lJr omments CllANGED FROM PERIOD 2 TO PERIOD 0 IN REV. 6. I42 'IOITI RS WELDS DO 7.5% = 11,17 SCllEDI FLED REDt'CE TIIE SCIIEDULED WEIES TO 14 TO allow 3 BUFFER WELDS.
' 2050-WMKS-0104DA IS-60(4A) 12'-RS-408 19 A-Q2 C-F-1 C5.12 6818 0
'omments WEPSEM () LONG SEAhlS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5
' 2050-Wh!KS-0104DA LS-60(SW-41) 12'-RS-408-153 A-Q2 C-F-l C5.12 3158 0
'emmento WEPSEM () LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSFCTION IN REV. 5 12030-WMKS-0104DA LS-61(SW-41) 12*-RS-408-153 A-Q2 C-F-l C5.12 3159 0
'onunents WEPSE*.I () LONG SEAMS WELDS WERE BROKEN DOWH BY INTERSECTION IN REV. 5 2050-Wh!KS-0104DA 13-6 t(SW-42) IT-RS-408-153 A-Q2 C-F-I C5.12 6819 0
'emments WEPSEM 0 IDNG SEAMS WELDS WERE BROKEN DOWW BY INTERSECTION IN REV. 5 2050-WMKS-0104DA 13-62(2) IT-RS 408-153A-Q2 C-F-I C5.12 6820 0 m cata WEPSEM () LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 2030-WMKS-0104DA LS-62(SW-42) IT-RS-408-153 A-Q2 C-F-I C5.12 316" 0
'emments WEPSEM () IONG SEAMS WELDS WERE BROKEN DOWN BYINTERSECTION IN REV. 5 2030-WMKS-0104DA LS-63(SW-28) 17-RS-424-153 A-Q2 C-F-1 C5.12 6821 0 omments LOCATED BETWEEN WELDS SW SW-29. WEPCB () ADDED IN REV. 3.
LONG SEAMS WELDS WERE BROKEN DOWN DY INTERSECTION IN REY. 5 2050-WhlKS4)IO4DA f.L63(SW-29) 12'-RS-424-153 A-Q2 C-F-I C5.12 3161 0
'omments LOCATED BETWEEN WELDS SW SW-29. WEPCB () ADDED IN REY. 3.
LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 20SO-WMKS-0104DA IS-64(SW-36) IT-RS-424-153 A-Q2 C-F-1 C5.12 6822 0 onunento L(X'ATED BETWEEN WELDS SW SW-37. WEPCB () ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV 5 2050-WMKS-0104DA LS-64(SW-37) IT-RS-424-153 A-Q2 C-F-1 C5.12 3!62 0 omments LOCATED BETWEEN WELDS SW SW-37. WEPCB () ADDED IN REV 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV 5 2090-WMKS-0104DB 15W -35W(15W) 8*-RS-J74-153A-Q2 C-F-1 C5.12 6823 0 cmments MTR CERTS COULD NOT BE LOCATED TO VERIFY IONG SEAM ASSUME IS IS PRESENT BUT DO NOT EXAMINE. ADDED IN REV.
- 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV 5 wmmary of Osages Sorted by Drawing and Mark No NAPSU22 Database Page 53 of 146 Prmt Date: 11/1898
Drwning No. Alast No. IJne Number Category itemFe. tecation Record ' Pesied Method 12050-WktKS 0104DB 15W - 35W(35W) 8'-RS-374-15 3 A-Q2 C-F-1 C512 3I85 0
.. Connnents htTR CERTS cot'LD NOT BE LOCATED TO VERilT 1.ONG SEAh!. ASSUhtE LS IS PRESENT in'T DO NOT EXAktINE. ADDED IN REV.
- 3. LONG SEAhls WFI D1 WERE BROKEN DOWN BY INTERSECDON IN REV 5 12050-WhtKS-0104DB I Its E i6 6'-RS-JR3-153 A-Q2 F.B ~id I SFGD VLVPIT 3193 0 VT-3 Cenuments AllARES ClIANGED FROh! PERIOD 3 TO PERIOD 0 IN REY. 5. SUPPORT IS NOT ON A LINE SUBJECT TO ANOTifER WPE OF EXAh!! NATION 12050-Wh!KS-Ol04DB 20ht 8"-RS-460-153 A92 C-C C3.20 7566 0 C L A413. NOT SELECTED IdJ50-WhfKS-Ol04DB 35W - 16H16W) 8'-RS-J74-153 A-Q2 C-F-1 C5.12 7054 0 C L LONG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030 Wh!KS-0104DB 35W - 16W(35W) 8'-RS-J7A-153 A-Q2 C-E .1 C512 7053 0 Comnients ' DNG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WktKS-OI04DC likt 8"-RS-4 56-153 A-Q2 C-C C3 20 7567 0 C -. L A410 NOTSELECTED 12050-WhtKS-0104E 2-RS-R-9 10'-RS-409-153 A-Q2 F-A F10 SFGD 3227 0 VT-3 C_- L llllAGUD2 Cls ANGED F ROkt PERIOD 3 TO PERIOD 0 IN REV. 5. ONLY NEED TO EXAhtINE I5*6 OF SUPPORTS ON LINES RECEIVING ANOTIIER TYPE OF EXAkt.
12050 WhlKS-0104E 63 10'-RS-409-153A-Q2 C-F-1 C5.I l SFGD 3229 3 PTAJT Comments PER NRC REQUEST. PERFORhl A VOLUhlETRIC EXAktINATION 12030-WhlKS-0104E LS-72(SW-71) 10'-RS-409-153A-Q2 C-F-1 Cil2 SFGD 6824 2 iT(Tr Connnents IJDCATED BETWEEN WELDS SW SW-71. WEPCB 0 ADDED IN REV.
- 3. LDNO SEAhtS WELDS WEPI BROKEN DOWN BY INTERSECTION IN REV. 5. DO WIDI CIRC. WELD SW-71.
12030-WitKS-Ol04E LS-73(SW48) 10"-RS-409-153 A-Q2 C-F-1 C5.12 3232 2 PTAJT Comments LOCATED BETWEEN WELDS SW48 - SW49. WEPCH O ADDED IN REV. 3. LONG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5. CHANGED FROhf PERIOD 0 TO PERIOD 2 IN REY. 6. REPLACING 104L LS-74(19). SW49 IS ALREADY SCIIEDULED. 12050-WhtKS-0104E IS73(SW49) 10'-RS-409-153A-Q2 C-F-1 C5.12 6825 2 PTATT' Comments IDCATED BETWEEN WELDS SW48 - SW49. WEPCB 0 ADDED IN REV. 3. EDNG SEAh!S WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5. CIIANGED FROh! PEkIOD 0 TO PERIOD 2 IN REV. 6. REPLACING 104L LS-74(SW-73) WIIICII WAS ktOVED TO PERIOD 3. DO WIT!! CIRC WELD SW49. 12050-WhlKS-0104E IS74(20) 10'-RS-409-153A-Q2 C-F-1 C5.12 6826 0 Canunents LOCATED BETWEEN WELDS 20 - SW47. WEPCB 0 ADDED IN REV. 3. LONG SEAh!S WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-Whf KS-0104E IS-74(SW47) 10'-RS-409-153 A-Q2 C-F-1 C512 3233 0 Commenta IJDCATED BETWEEN WELDS 20 - SW47. WEPCB () ADDED IN REV. 3. LON3 SEAh!S WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 Summary of Gianges Sorted by Drawing ami Mark No., NAPSU22 Database Page 54 of 146 Pnnt Date: 11/I8 9# ! l 4 - __u
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Devering No. Mask No. : IAie Nennber Cateter3 Itens No. Imcseina Record Peeted Mettned
~ ' l2O30-WhtKS-0104 F . 36 8'-QS-439-153 A-Q2 C-F-1 C5. I I SFGD 3248 3 ITATF 'C - - - PER NRC REQUEST, PERFORkt VOLUhtETRIC EXAktINATION.
I 030-Wh!KS-0104F 70ll 8'-QS-404-153 A-Q3 C-C C3 20 7568 0 Comuments A-14. NOT SElICIED 12050-WhtKS-Ol04F IS10W(27) 8'-QS-404-153 A-Q3 C-F-1 C5.12 6827 0
- Comuments LOCATED BETWEEN WELDS SW 27. WEPCB 0 ADDED IN REY. 3.
IANG SEAkiS WELD 5 WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-Wh!KS-0104F IS10W(SW-96) F-QS-404-153 AQ3 C-F-I C5.12 3251 0 Comuments LOCATED BETWEEN WELDS SW-% - 27. WEPCB 0 ADDED IN REV. 3. LONG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5
- 12050-WhlKS-OI04F LS-IlW(26) 8'-QS-404-153 A-Q3 C-F-I C5.12 3252 0 C -.
LOCATED BETWEEN WELDS SW 26. ADDED IN REV 3. LONO SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WkIKS-Ol04F LS-IlW(SW-95) 8'-QS-404-153 A-Q3 C-F-1 C5.12 6828 0' Comumento LOCATED BETWEEN WELDS SW 26. ADDED IN REV. 3. LONO SEAktS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-Wh!KS-0104F LS-3W(SW-97) 8'-QS-404-153A-Q3 C-F-1 C5.12 SFGD 3253 PTilJF 3_ Comuments IMCATED BETWEEN WELDS SW-97. SW-98. WEPCB 0 ADDED IN REV. 3. LONG SEAhls WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. S. CHANGED FROh! PERIOD 0 TO PERIOD 3 IN REV. 6. REPLACING LS-12W(SW-87). SW-97 IS SCIIEDULED FOR PERIOD 3. WILL ALLOW A LONG SEAh! TO BE DONE WITII CIRC. WELD-12030-WhtKS-0104F LS-3W(SW-98) 8'-QS-404-153 A-Q3 C-F-1 C5.12 6829 0 PT,UT-0,45 C ce LOCATED BETWEEN WELDS SW SW-98. WEPCB (ADDED IN REV. 3. LONG SEAh!S WELDS WERE BROKEN IX)WN BY INTFRSECTION IN REV. 5 I2050-Wh!KS-0104F LS-4W(28) F-QS-404-153 A-Q3 C-F-1 C5.12 6830 0 Cosnaments LOCATED BETWEEN WELDS SW 28. % EPCB 0 ADDED IN REV. 3. LONG SEAhtS WELDS WERE BROKEN D0%W BY INTERSECTION IN REV. 5 12030-WhtKS-0104F LS-4W(SW-99) 8'.QS-404-153A-Q3 C-F-1 C512 3254 0 C- J_ LOCATED BETWEEN WELDS SW 28. WEPCB 0 ADDED IN REV. 3. LONG SEAhtS WELDS WERE BROKEN DOWN BY INTFRSECFION IN REV. 5 12030-WhtKS-0104F IS5W(31) 8*-QS-404-153 A-Q3 C-F-I C512 'N35 0-Casumments LONG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECFION IN REV. 5 12030-WhtKJ-0104F IS5W(SW-lW) 8*-QS-404-153 A-Q3 C-F-1 C5.12 3255 0 C ^ LOCATED BETWEEN WELDS SW-lW- SW-2W. WEPCB 0 ADDED IN REV.
- 3. LONG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV.5 Sussunary of Changes Seeted by Drusing and Mark No.,NAPSU22 Database Page 55 of f 46 Prmt Date: 11//8 98
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Dewning No. Alset No. I ine Nuenber Category item No. Imentian Record Period hiethod
.12050-Wh!KS-0104F LS-5W(SW-2W) ~~ 8*-QS-404-15 3 A-Q3 C-F-1 C5.12 SFGD 6831 3 PT/UT Coenments LOCATED !!ETWEI.N WEl.DS SW-IW + SW-2W. WEPCB () ADDED IN REV. 3. LONG SEAktS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5. CHANGED FROh!
PERIOD 0 TO PERIOD 3 IN RI.V. 6 RLPLACING Lt12W(SW-86) ON 10711 SW-2W IS SCIIEDUI.ED FOR PERIOD 3 WILL AllDW A IDNG SEAh! TO BE DONE %TTil TIIE CIRC- - WELD.
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12050 WhtKS4)l04G 3 811 ~ ~~ 8'-QS-403-153 A-Q3 ~ C-C C3.20 7569 0 Comunents A-16. NOT SELECTED , 12050-WhtKS-0104G L%84(2) r-QS403-153A-Q3 C-F-1 C5.12 3273 0 Cosnsnents LOCATED BETWEEN WELDS SW 2. WEPCB() ADDED IN REY. 3. ' IDNG SEAhtS WELDS WERE IIROKEN DOWN BY INTERSECTION IN REV. 5 i 12050-WhlKS-0104G LS-84(SW-78) 8'-QS403-153A-Q3 C-F-1 C5.12 S832 0 Comisments LOCATED BETWEEN WELDS SW-78 -2. WEPCB () ADDED IN REV. 3. LONG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WklKS-0104G LS-85(SW-79) 8'-QS403-153 A-Q3 C-F-1 C5.12 3274 0 Comuments LOCATED BETWEEN WELDS SW SW-80. WEPCB () ADDED IN REV. 3. LONG SEAh!S WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 120$0-WhtKS-01040 LS-85(SW-80) r-QS-403-153Aq3 C-F-1 C5.12 6833 0
^
-s l C_ LOCATED BETWEEN WELDS SW-79 -SW-80. WEPCB() ADDED IN REY. 3.
LONG SEAh!S WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-Wh!KS-0104G IS.86(3) 8'-QS-403-153A-Q3 C-F.I C5.12 SFGD 6834 0 IT/tTF Comuments LOCATED BETWEEN WELDS SW 3. WEPCB () ADDED IN REY. 3. LONG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5. CIIANGED FRGht PERIOD 2 TO PERIOD 0 IN REV. 6. REPLACED BY LS-7W(SW-89) SW-89 IS ALREADY SCIIEDULED. WILL ALLOW LONG SEAh! AND CIRC. WELD TO BE DONE TOGET!!ER. t 12050 WhtKS-0104G LS-86(SW-80) r-QS-403-153A4)3 C-F-1 C5.12 SFGD 3275 0 ITMF Comunents LOCATED BETWEEN WELDS SW-80 -3. WEPCB() ADDED IN REV. 3. VERIFIED WITil ET. CIIANGFD FROh! PERIOD 2 TO PERIOD 0 IN REV. 6. REPLACED WITil IS-7W(SW- *
- 90) ON 1071I. WILL ALLOW LONG SEAh! TO BE DONE WITII CIRC. WELD.
12030-Wh!KS-0104G LS-87(4) - T-QS-403-153A-Q3 C-F-1 C5.12 6835 0 . f Comuments LOCATED BETWEEN WELDS SW SW-82. WEPCII() ADDED IN REV. 3. ; LONG SEAhfS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 i 12050-Wh!KS-0104G LS-87(SW-81) r-QS-403-153A-Q3 C-F-l C5.12 SFGD 3276 3 PT/tJF , Conisments LOCATED BETWEEN WELDS SW SW-82. WEPCB () ADDED IN REV. 3. LONG SEAh!S WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5. ADDED IN REV. 6. SW- [ 81 IS ALREADY SCIIEDULED. 'HIIS EXAktINATION WILLCOVER LS-87(SW-81). 12050-Whf KS-0104G LS-87(SW-82) r-QS-403-153 A-Q3 M-F-1 C5.12 7056 0 Comuments LONO SEAhls WELDS WERE BROKEN DOWN BY IN'IERSECTION IN REV. 5 I2030-WAIKS-0IO40 LS-88(SW-82) r-QS-403-153 A-Q3 C-F-1 C5.12 3277 0 IT,UT-0,45 C- a LOCATED BETWEEN WELDS SW SW-83. WEPCB 0 ADDED IN REV. 3. j LONG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 i Sununerr of Changes Sorted by Drnesing and Meek No,NAPStJ22 Databane Page $6of N6 PnntDate: 11/18 94
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._ _._ m : - _. - - - - - - - -
__ Drawing New Mark No. I ine Number Category item No. Laration Herord - Pesied Meelied
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12090 WhtKS.0104G LS-8R(SW-83) r-QS403-153A-Q1 C-F-1 C5.12 6816 0 PT.tJT 0,45 C -=s IDCATED BETWEEN WELDS SW SW-83. WEPC110 ADDED IN REV. 3. ' LONG SEAhtS WELDS WERE BROKEN IX)WN BY INTERSECTICI IN REV. 5 ' 12050-WktKS-0104G IS-91(SW-72) T QS403-153 A-Q3 C F-1 C512 3278 0 Comunents LOCATED BETWEEN WELDS SW SW-73. WEPCB () ADDED IN REV. 3 LONG SEAkiS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-Whf KS-0104G IS-91(SW-73) 8'-QS-403-153A-Q3 C-F-1 C512 6837 0 Comments t OCATED BETWEEN WELDS SW SW-73. WEPCB () ADDED IN REV. 3. LONG SEAh!S WELDS WERE BROKEN DOWN !!Y INTERSFCT10N IN REV. 5 12050-Whf KS-0104G LS-92(SW-74) r-QS-403-153 A-Q 3 C-F-1 C5.12 SFGD 3279 0 PTUr i Conunents IPCATED BETWEEN WELDS SW SW-75. WEPCB 0 ADDED IN REV. 3. VERIFIED WITil ET. CitANGED FROh! PERIOD 2 TO PERIOD 0 IN REV. 6 REPIACED WITII 107J IS-47(SW42). SW42 IS ALREADY SCitEDULED FOR PERIOD 2 WILL ALLOW LONG SEAh! TO DE DONE WITII Tile CIRC. WELD. 12050-WhtKS-0104G IS-92(SW-75) r-QS403-153 A-Q3 C-F-1 C5.12 SFGD 6838 0 PTitTF Conunents LOCATED BET % TEN WELDS SW SW-75. WEPCB O ADDED IN REV. 3. IDNG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV 5. CIIANGED FROh! PERIOD 2 TO PERIOD 0 IN REV. 6. REPLACED BY 107L IS-37(SW-33) SW-33 IS ALREADY SCllEDULED. WILL ALIDW LONG SEAh! TO BE DONE WITli TIIE CIRC. WELD. 12050-WhfKS-0104G IS-93(SW-76) r-QS-403-153 A-Q3 C-F-1 C5.12 3280 0 .{ C_ :s LOCATED BETWEEN WELDS SW-76-SW-77. WEPCilO ADDED IN REV 3. LONG SEAh1S WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 j 12050-Whf KS-0104G LS-93(SW-77) r-QS403-153 A-Q3 C-F-1 C5.12 6839 0 C- :s LOCATED BETWEEN WELDS SW SW-77. WEPCB 0 ADDED IN REV. 3. LONG SEAhfS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-Wh!KS-0104G SW-81 T-QS-403-153 A-Q3 C-F-1 C5.11 SFGD 3290 3 PT,tJT Conunents WEPCB 0 CIIANGED FROh! PERIOD 0 TO PERIOD 3 IN REV. 6. REPIACING SW-82. %TLL ALIDW LONG SEAh! LS-87 TO DE DONE WITil CIRC. WELD. 12050-Wh!KS-0104G SW-82 T-QS-403-153A-Q3 C-F-1 C511 SFGD 3291 0 PTitJ1 Conumenta WEPCB () . CIIANGED FRONI PERIOD 3 TO PERIOD 0. REPLACED WITil SW-81 ON 104G WILL ALIDW LDNG SEAh! TO BE DONE WIT 11 CIRC. WELD. [ t 12050-WhtKS-0104L LS-74(19) 10'-RS-410-153 A-Q2 C-F-I C5.12 SFGD 3299 3 PT/tJF Comments IDCATED BETWEEN WELDS 19 - SW-73. %IPCB 0 ADDED IN REV. 3. CIIANGED FRONT PERIOD 2 TO PERIOD 3 IN REV. 6 REPLACED BY 104E LS-73(SW-69). SW-69 IS ALREADY SC11EDULED AND REPLACING 104DA IS-58. 12050-WhtKS-0104L IS-74(SW-73) 10'-RS-4 t o-153A-Q2 C-F-1 C5.12 SFGD 6840 3 PTitJr . i Comments IDCATED BETWEEN WELDS 19 - SW-73. WEPCB O ADDED IN REV. 3. LONG SEAh!S WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5. CilANGED FROht PERIOD 2 TO PERIOD 3 IN REV. 6. REPLACED BY 104E LS-73(SW-68) AND REPLACING 104 DAIS-58. DO WITil SW-73. , 12050-Wh!KS-0104L LS-75(SW-71) 10'-RS-410-153 A-Q2 C-F-1 C5.12 6841 0 Comments IDCATED BETWEEN WELDS SW SW-71. WEPCB () ADDED IN REV. 3. IDNG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 f Sumnary of Changes Sorted by Drawing anJ Mark No NAPSIJ22 Database Page 57of146 PnntDate: 11/18 93 , f
Drawing No- hlark No- 1.ine .N umber Category Item No. Incation Record Period %fethod 13050-WhtKS-0104L LS-75(SW-72) i R I I 3 A-Q2 C-F-I Cf.12 3300 0 Comments LOCATED flETWEEN WEl DS SW 72 - SW-71. WEPCB() ADDED IN REY 3. LONG SEAhtS WELDS WERE IIROKf;N DOWN IlY INTERSECTION IN REV. 5 120SO-Whf KS-OI04L IS76(SW-69) 10'-RS-4 t o-153 A-Q2 C-F-I C512 6842 0 Comments LOCATED BETWEEN WELDS SW SW-69. Wl; PCB () ADDED IN REV. 3. LONG SEAhtS WELDS WER E BROKEN DOWN BY INTERSECTION IN REV. 5
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12050-Wkf KS-0104L IS76(SW-70) 10ASUlo-153 A-Q2 C-F-1 C5.12 3301 0 Comments LOCATED BETWEEN WELDS SW SW-69. WEPCB () ADDED IN REV 3 LONG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5
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12050-Whf KS-0105 A-1 12J 16'-WS-431-151-Q3 D-A DI.20 QSPII 3475 I VT-3 Comments 100*. A-23 NOT SELECTED. CllANGI D 1113I NUhlBER TO AGREE WITil PRESSURE TESTING PROGRAh! IN REV. 8. 120$0-Wh!KS-0105 A-I 13J 16' WS-432-151-Q3 D-B D2_20 QSPil 3476 0 VT-3 Comments 100*.(A-12 NOT SELECTED) CIIANGED FROh! PERIOD 3 TO PERIOD O IN REV. 7. RELIEF REQUEST NDE-21 ALLOW l'SE OF CODE CASE N-509 TO EXAhfINE 10*boF THE ' INTEGRAL ATTACithtENTS. CIIANGED 11Eh! Nt'htBER TO AGREE WTTil PRESSURE TESTING PROGRAh!IN REV. 8.
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12050-WhtKS-0105 A-I 2-WS-A-3 16*.WS-43 3-151-Q3 F-A F10 3482 3 VT-3 Comment 3 h10DIFIED BV DCP 89-43-311 HAANC. ELulINED IN 90 h!!SSING ANCIlOR BOLT AND NITT AAI New with Rev. II to the plan: Scheduled in Period 3 due to reevaluation of the Class 3 total sugyort population. 12050-WhtKS-0105A-1 2 71I 24*-WS-432-151-Q3 D-B D2.20 QSPil 3477 0 AT-3 Comments 100*.(A-12 NOT SELECTED). CIIANGED FROh! PERIOD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 ALIDW USE OF CODE CASE N-509 TO EXAhflNE 10's OF TIIE i INTEGRAL ATTACllhf ENTS. CIIANGED ITEh! NUhfBER TO AGREE WITII PRESSURE TESTING PROGRAh! IN REV. 8. 12050-WhlKS-Ol05 A-1 2811 16*-WS-431-I S I-Q3 D-A DI.20 QSPil 3478 1 AT-3 Comments 100*4 A-23 NOT SELECTED 12050-WhtKS-0105 A-1 3]I W-WS-4 30-151-Q3 D-A DI.20 QSPIf 3491 2 VT-3 Comments 100*s A-21 NOT SELECTED. CilANGED ITI31 NUhlBER TO AGREE WITil PRESSURE TESTING PROGRAhlIN REV. 8, ISO 90-WhtKS-0105 A-1 3J 16'-WS-43 3-151-Q3 D-A DI.20 QSPII 3492 2 VT-3 Comments 100*4 R-5 NOT SELECTED. CIIANGED ITEh! NI3 iller IN REV. 8 TO AGREE WITil PRESSURE TESTING PROGRAh!. 12050-Whf KS-0105 A-1 41I 16'-WS-433-151-Q3 D-A DI.20 QS'll 3493 I AT-3 Comments 100's A-3 NOT SELECTED. CIIANGED ITEh! NUhtf1ER IN REV. 8 TO AGREE %TTil PRESSURE TESTING PROGRAh!. I2050-Wh!KS-0105A-1 41I 24'-WS-428-151-Q3 D-B D2.20 QSPII 3494 2 AT-3 Comments 100*6 R-16 NOT SELECTED. CilANGED ITEh! NUhlBER IN REV. 8 TO AGREE %TTI! PRESSURE TESTING PROGRAht. New with Rev. II to plan: Changed Category to D-B from D-A and Item No. to D2.20 from DI.20 to agree with the SPT program. 12050-WhtKS-0105A-2 IJ 24'-WS-426-151-Q3 D-A DI.20 QSPII 3495 1 AT-3 Comments 100*4 R-8 NOT SELECTED. CIIANGED ITEh! NUhli1ER IN REV. 8 TO AGREE WITil PRESSURE TESTING PROGRAhi Summary of E1anges Sorted by Draning and Stark No, NAPSU22 Database Page 58of 145 Pn=r Date: J1/1898
rr _ -
' prening No. ' hierk No. I.ine Numtwr Category item No. tecation Record Period Method ' 12050-WhfKS-0105A-2 4til 24'-WS-428-151 D-B D2.20 QSPIl 3502 0 VT-3 :
Conunents 100*6(R-17 NOT SELECTED). CIIANGED FROkt PERIOD 3 IO PT RIOD 0 IN REV. 7. REtJEF REQUEST NDE-21 ALIDW USE OF CODE CASE N-509 TO EXAhflNE 10%OF T1fE i INTEGRAL ATTACllhtENTS. CIIANGED ITEhl NUhlBER 10 AGREE WITil PRESSURE TESTING PROGRAki!N REV 8.
'I 2050.WhtKS-0105 ARE-l 2-WS-Pit-1043 27-WS-E57-15II)I F-B F2 0 SW POUND 3325' O VT-3 Ceaunents AllARES CIIANGED FROh! PERIOD 31T.)
PERIOD 0 IN REV. 5. SUPPORT IS NOT ON A LINE SUIUECT TO INOTIIER TYPE OF EXAhlINATION 12050-Wh1KS-0105 ARE-3 2-WS-Pii-1022 8'-WS-Il2-151-03 F-A FI O SW POUND 3348 0 VT-3 ' i Conuments B11AGUD2 CilANGED FROM PERIOD 2 TO PERIOD 0 IN REV. 5. SUPPORT IS NOT ON A LINE SUIUECT TO ANOTifER TYPE OF EXAh!INATION 820$0-WhtKS-0105ARE-3 2-WS-Pil-1026 20*-WS-E57-151-Q3 F-B F2.0 SWPOUND 3351 0 \T-3 Comments A11 ARES Cl!ANGED FROh! PERIOD 2 TO PERIOD 0 IN REV 5. SUPPORT IS NOT ON A LINE SUIUECi TO ANOTilER TYPE OF EXAh!INATION 82050-WhlKS-0105 ARF-1 2-WS-PII-2032 27-WS-E23-151-Q3 F-A Fl.0 SW POUND 3357- 0 VT-3 Comunents BilAGUD2 CIIANGED FROh! PERIOD 2 TO . PERIOD 0 IN REV 5. SUPPORT IS NOT ON A LINE SUIUECT TO ANOTilER TYPE OF EXAhtINATION 12050-Wh!KS-0105 ARF-3 2-WS-Pil-2020 10'-WS-I40-151-Q3 F-A Ft.0 SW POUND 3386 0 YT-3 Comments B1tAGUD2 CIIANGED FROh! PERIOD 2 TO PERIOD 0 IN REV. 5. SUPPORT IS NOT ON A LINE SUBJECT TO ANOTIIER TYPE OF EXAh!INATION , 12050-Wh!KS-0105 ARG-2 2-WS-Pit 7006 12*-WS-E20-15 I-Q3 F-A FI O SW POUND 34II O VT-3 Comments B1IAGUD2 CilANGED FROh! PERIOD 2 TO PERIOD 0 IN REV. 5. SUPPORT IS NOT ON A LINE SUIUECT TO ANOTIIER TYPE OF EXAMINATION 12050-Wh!KS-0105 ARG-3 2-WS-Plf-7015 8'-WS-214-I 51-Q3 F-A Fl .0 SW POUND 3421 0 \T-3 Comunents B11AGUD2 CllANGED FROh! PERIOD 2 TO PERIOD 0 IN REV. 5. SUPPORT IS NOT ON A LINE SUBJECT TO ANOTIIER TYPE OF EXAMINATION 12050-WMKS-0105 ARIt-1 2-WS-Pil-8035 27-WS-E24-151-Q3 F-A FI O 3440 0 VF-3 Canunents BilAGUD2 . CIIANGED FROM PERIOD 2 TO PERIOD 0 IN REV 5. SUPPORT IS NOT ON A LINE SUBJEC7 TO ANOT "!R TYPE OF EXAh!INATION 12050-WMKS-0105 ARII-2 2-WS-Pil-8008 17 WS-218-151-Q4 FU Fl.0 3456 0 VT-3 Comunents BilAGUD2 CIIANGED HtOM PERIOD 3 TO PERIOD 0 IN R EV. 5. SUPPORT IS NOT ON A LIKE SUBJECT TO ANOTIIER TYPE OF EXAMINATION 12050-WMKS-0105ARii-3 2-WS-Pil-8018 12'-WS-E21-151-Q3 F-A Ft.0 3467 0 VF-3 CoMes B11AGUD2 CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 5. SUPPORT IS NOT ON A LINE SUBJECT TO ANOTIIER TYPE OF EXAMINATION 12050-WMKS-Ol05 ARil-3 2-WS-PII-8023 C-WS-315-151-Q3 F-A Fl.0 3472 0 VF-1 Conunents BilAGUD2 CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REY. 5. SUPPORT IS NOT ON A [JNE SUBJECT TO ANOTilER TYPE OF EXAMINATION Senumery erChanges Sorted by Druning and Mark No , NAPSU22 Database Page 59of146 PrmtDate: 1//1898 p
throwing No. Mark No. - . IJne Numiber - Cseegory Itene No. Imation Record Peded - Meelmed 12090-WMKS4105B-I 3911 24%WS-434-151-Q3 D-A DI .20 QSPl! 3509 I \T-3 f Comuments 100*4 R-29 NOT SELECTED CilANGED ITEM NUhlllER IN REV. 8 TO AGREE WITil PRESSt *RE TESTING PROGRAM
.120SO-WMKS-0105B-l 5J 24%WS-436-151-Q3 D-A DI.20 QSPfl 3510 2 \T-3 '[
C -e 100's R-36 NOT SELECTED. CliANGED ITEM NUhlBER IN REV. 8 TO AGREE WITil PRESSURE TESTING PROGRAM
' 12050-WMKS4i105B-2 111 16tWS-441-15l-Q3 D-B D2.20 QSPII 3511 0 NT-3 Comissents 100%(R-17 NOT SELECTED) CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 7. REllEF REQUEST NDE-21 ALLOW USE OF CODE CASE N-509 TO EXAMINE 10% OF TIIE INTEGRAL ATFACliMENTS. CllANGED ITEM NUMBER TO AGREE WITil PRESSURE TESTING PROGRAM IN REV. 8. .
t 12050-WMKS-0105B-2 2-WS-R-34 24'-WS-436-151-Q3 F-A FI O QSPH 3528 0 VT-3 C. an RllAGUD2, EXAMINED IN 90 NRI . CitANGED i FROM PERIOD 3 TO PERIOD 0 IN REV. 5. SUPPORT IS NOT ON A UNE SUBJECT TO ANOTIIER T)TE OF EXAMINATION I2050-WMKS41058-2 2J 16tWS-441-151-Q3 D-B D2.20 QSPII 3512 2- . \T-3
, Comuments 100'. A-25 NOT SELECTED. Cil ANGED ITEM NUhtBER IN REV. 8 TO AGREE WITil PRESSURE TESTING PROGRAM. New with Rev. II to plan- Changed Category to D-3 from D-A 4 and Item No. to D2.20 from DI .20 to agree with the SIT program. !
i 12050 WMKS-Ol"B-2 311 16tWS-438-151-Q3 D-A DI.20 QSPil 3522 3 \T-3 l C- at l'00*.(2-WS-A-40 SELECTED FOR PERIOD 3) ClIANGED ITEM NUhtDER IN REY. 8 TO AGREE Wil ni ?RESSURE TESTING PROGRAM. [ 12090-WMKS-0105B-2 6J 16*-WS-440-151-Q3 D-A DI.20 QSPII 3523 2 \T-3 [ Comuments 100*. A-33 NOT SEI E CTFD. CIIANGED ITEM NUMBER IN REV. 8 TO AGREE %TTII PRESSURE TESTING PKOGRAM. 12030-WMKS-0105B-2 7J 16*-WS-439-151-Q3 D-A DI.20 QSPil 3524 i \T-3 l t C- --
. 100% A-42 NOT SELECTED CIIANGED ITEM NUMBER IN REV. 8 TO AGREE WITII PRESSURE 1T. STING PROGRAM.
12050 WMKS-0105D A-P-4 24"-WS-425-15 I-Q3 F-A F10 7719 0 VT-3 ! t Ceaunents ADDED IN INTERIUM CllANGE 97 01 WAS DISCOVERED MISSING FROM Ti!E PROGRAM. NOT ON A IlNE SUBJECT TO ANOTIIER TYPE OF EXAMINATION. DOES NOT NEED .i TO BE SELECTED. 120S0-WMKS-0105D R-329 24*-WS-425-151-Q3 F-A FI O 7720 0 \T-3 C. - . _ ADDE ~)lN INTLRIUM CIIANGE 97-01 WAS DISCOVERED MISSING FROM Tile PROGRAM. NOT ON A LINE SUBJECT TO ANOTi!ER T)TE OF EXAMINATION. DOES NOT NEED ' TO BE SELECTED. i 12090-WMKS-0105DA 2-WCMU-R-13 6%WCMU-412-151-Q3 F-A Fl.0 YARD TUNNEL 3530 0 \T-3 [ C ". B11AGUD2 CIIANGED FROM PERIOD 2 TO PERIOD 0 IN REV. $. SUPPORT IS NOT ON A IlNE SUBJECT TO ANOTIIER TYPE OF EXAMINATION 82050-WMKS-0105DA 2-WCMU-R-9 6%WCMU-412151-Q3 F-A FI O YARD TUNNEL 3541 0 \T 3 , C BilAGUD2 CHANGED FROM PERIOD 2 TD PERIOD 0 IN REV. 5. SUPPORT IS NOT ON A IJNE SUBJECT TO ANOTHER T)TE OF EXAMINATION 12050-WMKS-0107AB 2-QS-R-601 6'-QS-440-153B-Q3 F-B F2.0 YARD 3586 0 \T-3 Comuments A11 ARES. CIIANGED FROM PERIOD 3 TO PERIOD 0 IN REV 5. ONLY NEED TO EXAMINE 15% OF SUPPORTS ON LINES RECEI\TNG ANOTIIER TYPE OF EXAM Semannery of Changes sorted by Dreateg and Mast No, NAPSU22 Database Page 60of f46 PnerDarer ff/fam T
Drawing Ne- Mark No. IJne Niember Category Itene No. Location Reeerd Period Method ; 12050-WMKS-0107AB 4 411 6"-QS432-153A-Q3 C-C C3.20 .7570 0 Cesunients . Rll-4 NOTSELECTED
~ ~ . I20$0-WMKUlohIll LS-52(18) C-QS-432-153 A-Q3 C5-l C5.12 3601 0 Comunents LOCATED BETWEEN WELDS 35 - 18. WEPCB 0 ADDED IN REV. 3 LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0107AB LS-52(35) . OQS-432-153 A-Q3 C-F-I C5.12 6843' O t Conienents IJOCATED BETWEEN WELDS 35 - 18. WEPCB () ADDED IN REV. 3.
LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 , 12050-WMKS-0107AB LS-53(18) 6-QS-432-153A-Q3 C-F-1 C3.12 3602' O , Cosansents IDCATED BETWEEN WELDS I 8 - SW-49. WEPCB 0 ADDED IN REY. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY IKTERSECTION IN REY. 5 120$0-WMKS 0107AB IS53(SW49) 6-QS-432-153 A-Q3 C-F- 1 C5.12 6844 0 Cesnments toCATED BETWEEN WELDS I8 - SW-49 WEPCB 0 ADDED IN REV. 3. LDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-WMKS 0107AB LS-53(SW-50) 6'-QS-433-153A-Q3 C-F-I C5.12 7057 0 Canunents IDNG SEAMS WELDS WERE BROKEN DOWW BY INTERSECTION IN REV. 5 12030-WMKS-0107AB LS-54(36) 6-QS-432-153 A-Q3 C-F-1 C5.12 6845 0 Cesusnents IDCATED BETWEEN WELDS SW 36. WEPCB 0 ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSEC110N IN REV. 5 12050-WMKS-OlG7AB IS$4(SW-49) 6'-QS-432-153A.Q3 C-F- 1 C5.12 3603 0 Coensnents IJOCATED BEDVEEN WELDS SW 36. WEPCB 0 ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 L 12050-WMKS-0107AB IS$5(27) OQS-440-1531LQ3 C-F-1 C5.12 6846 0 ; Casanients LDCATED BETWEEN WELDS 28 - 27. WEPCB 0 CERTS ON TAPE 4XBR FRAME 2004 ADDED IN REV.
- 3. IDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 120%WMKS-0107AB IS$5(28) 6'-QS-440-1538-Q3 C-F-1 C5.12 3604 0 -i Cesuneents LOCATED BETWEEN WELDS 28 - 27. WEPCB 0 CERTS ON TAPE 4XBR FRAME 2004 ADDED IN REV.
- 3. 1DNG SEAMS WEIDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 ,
i 12050-WMKS-0107AB LS-56(25) 6'-QS-440-153 B-Q3 C-F-1 C5.12 6847 0 . I Conenents LOCATED t!ETWEEN WELDS 26 - 25. WEPCB () CERTS ON TAPE 4XBR FRAME 1537 ADDED IN REV.
- 3. IDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 y 12050-WMKS-0107AB LS-56(26) F-QS-440-153 B-Q3 C-F-I C5.12 3605 0 Conanents LOCATED BETWEEN WELDS 26 - 25. WEPCB()CERTS ON TAPE ?BR FRAME 1537 ADDED IN REV.
3 IDNG SEAMS WELDS WERE BROKEN DOWN BY IN'ITRSECTION IN REV. 5 i sananary of Gianges soeted by Drawing and Mark No., NAPSU22 Davbese Page 61of f 46 Pnnt Date: 11/1893
m- = . =: = ===- Drawing No. Alart No. 1.Ine Number Category item No. Imathm Hecord Period blethod 12050-WMKS-0107AB 15-57(23) 6*-QS-440-153IkQ3 C-F-1 C5.12 6848 0 Conunents LOCATED BETWEFN WEl_DS 24 - 23. WEPCI!() CERTS ON TAPE 4X11R !RAME 2004 ADDED IN REV
- 3. LONG SEAAls WEIDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WhlKS-0107AB LS-57(2
- n 6* QS-440-1531kQ3 C-F-1 C5.12 3606 0 Comments LOCATED BETWEEN WELDS 24 - 23. WEPCB () CERTS ON TAPE 4XilR FRAME 2004 ADDED IN REY.
- 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0107AB LS-58(17) 6*-QS-433-153 A-Q3 C-F-I C5.12 6849 0 Comments LOCATED BETWEEN WELDS 17 - SW-51. WEPCB () ADDED IN REV. 3.
LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WKfKS-0107AB 15-58(21) 6'-QS-440-153 B-Q3 C-F-1 C5.12 3608 0 Comments IDCATED BETWEEN WELDS 49 - 50. WEPCB () CERTS ON TAPE 6XF R FRAME 1954 ADDED IN REV.
- 3. LONG SEAhls WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0107AB LS-58(50) 6'-QS-440-153B-Q3 C-F-I C5.12 6850 0 Comments LOCATED BETWEEN WEI.DS 49 - 50. WEPCB () CERTS ON TAPE 6XBR FRAME 1954 ADDED IN REV.
- 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-WMKS-0107AB LS-5?(SW-51) 6*-QS-433-153 A-Q3 C-F1 C5.12 3607 0 Comments LOCATED BETWEEN WELDS 17 - SW-51. WEPCB () ADDED IN REV. 3.
LONG SEAMS WELDS WERE BROKEN DOWN BY ;NTERSECTION IN REV. 5 12050-WMKS4107AB LS-59(51) 6'-QS-440-153fkQ3 C-F-l C5.12 3609 0 Comments LOCATED BE1 TEEN WELDS 23 - 31. WEPCB ()CERTS ON TAPE 4XBR FRAME 2004 ADDED IN REV.
- 3. IDNG SEAM WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-WMKS-0107AB IS$9(TANK) 6'-QS-440-153B423 C-F-1 C5.12 6851 0 Comments LOCATED BETWEEN WELDS 23 - 31. WEPCB () CERTS ON TAPE 4XBR FRAME 2004 ADDED IN REV.
- 3. LONG SEAMS WELDS WERE BROKEN C')WN BY INTERSECTION IN REV. 5 12030-walks-0107B 2-SI-A-600 10'-SI-408-153 A-Q3 F-A FLO 362h 0 Conunents IllIAANC. CIIANGED LINE NUMBER TO AGREE Wrrli DRAWING WITil REV.10 TO PLAN.
12050-WMKS-0107B 2-SI-R-216 10*-SI-408-153A-Q3 F-B F2.0 QSPII 363J 3 VT-3 Comments AllARES. CIIANGED FROM PERIOD 2 TO PERIOD 0 IN REV. 5. ONLY NEED TO EXAMINE 15?sOF SUPPORTS ON LINES RECEIVING ANOTIIER TYPE OF EXMt. ADDED BACK TO PERIOD 3 IN REV. 7. GROUPED SUPPORTS BY SYSTEM AND TYPE SI NEEDS 7 MORE SUPPORTS. Cli ANGED LINE NUMBER TO AGREE WITil DRAWING WITII REV.10 TO PLAN. 12030-WMKS-0107B 2-St-R-217 10'-SI-408-153 A-Q3 F-A FI O QSPII 3631 0 VF-3 Comments ILilAGUD2. CilANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 5. ONLY NEED TO EXAMINE 15?s OF SUPPORTS ON LINES RECEIVING ANOT11ER TY PE OF EXAM 12030-WMKS-0107B 3011 10"-SI-408-153A-Q3 C-C C3.20 7571 0 Comments A-600. NOT SELECTED Summary of Changes Sorted by Drawing and blark No., NAPSU22 Database Page 62 of 146 Pnnr Date: 11/18 93
- _ _ _ _ _ _ _ _ _ _ . . _ _ . , _ ~ _ _ _ - . _ _ _ _ _ _ _ .-
L t Drawing No. Mark No. IJae Number Category leem No. - Incesian Record Pesied - Meelied
~
12050-Whf KS4107B LS45(24A) 16*-SI-407153Aq3 C-F-l C5.12 YARD TUNNEL - '3643 - 3 PTitJT -
- Cesamments ! OCATED BETWEEN WELDS 4 A - 24 A WEPCB () CERTS ON TAPE 6XBR TR uf f' 2854 ADDED IN REV. 3. ADDED INTERSECTION CIRCUhfFERENTIAL WEl.D TO TIfE htARK NUMBER. INTERiht CIIANGE 93-02. Do WITIl CIRC. WELD 24A
.12090-Wh1KS4IO7B IS45(4A) 16'-SI-407-153 AQ3 C-F-I C5.12 QSPII 7224 0- PT4JT Ceauments IDCATED BETWEEN WELDS 4 A - 24A WEPCB () CERTS ON TAPE 6XBR FRAhlE 2854 ADDED IN REV. 5.
~
12090-WhlKS-01078 LS46(3) 16*-SI-407-153A-Q3 ' C-F-1 C5.12 3644 0
.C =2 LOCATED BETWEEN WELDS SW 3. WEPCB () ADDED IN REV. 3.
LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12090-Whf KS-OI078 IS-66(SW-59) 16*-SI-407-153A-Q3 . C-F.I C5.12 6852 -0 4_ Comennenes LOCATED BETWEEN WELDS SW 3. WEPCB () ADDED IN REV. 3. . i LONG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 l 12050-WMKS-0107B IS47(SW-59) 16-SI-407-153A-Q3 C-F-1 C512 3645 0 PT,tTF-0,45 , Cosmanenes LOCATED BETWEEN WELDS SW40 - SW-59. ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 I 12090 WMKS-Ol07B LS47(SW-60) R &-SI-407-153 A-Q3 C-F-I C5.12 6853 0 PT.lJF-0,45 C_ - :; LOCATED DETWEEN WELDS SW40 - SW-59. ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV,5 12030-WMKS-OI07B LS48(14) IF-SI-407-153A-Q3 C-F-I C512 3646 0 PT,tJT-0,45 f Ceaunents LOCATED BENEEN WELDS I4 - SW40. ADDED IN REV. 3. 'IDNG ' SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12050-WMKS-0107B LS48(SW40) 16'-SI-407-153A-Q3 C-F-1 C3.12 6854 0 Irr,1TT-0,45 Comannents LOCATED BETWEEN WELDS 14 - SW40. ADDED IN REY. 3. WNO SEAMS WELDS WERE BROKEN DOWN BY INTERSECUON IN REV. 5 12090-WMKS-0107B LS49(14) 16'-S1-407-153A-Q3 C-F-l C5.12 6855 3 PT/tJT Caenmients LOCATED BETWEEN WELDS 2 - 14. WEPCB () ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5. CIIANGED FROM PERIOD O 'IO
- PERIOD 3 HTTil REV.10 TO PLAN, REPLACES 13-74(14). TIIIS WILL ALLOW IDNG SEAM R) BE DONE IN CONJUCTION WITII A CIRC. WELD AS WAS ORGINALLY INTENDED.
12090-WMKS4107B 1S49(2) IF-SI-407-153A-Q3 C-F-1 C5.12 '3647 0 C --- :; LOCATED BETWEEN WEWS 2 - 14. WEPCB () ADDED IN REV.3 . LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 [ 12090-WMKS-OI07B 13-70(25B) 16'-SI-407-153A-Q3 C-F-1 C5.12 3648 0 PTitJT Commments IDCATED BETWEEN WELDS 25B - 26B. WEPCB () CERTS ON TAPE 6XBR FRAME 2646 ADDED IN REV. 3. CIIANGED FROM PERIOD 3 TO PERIOD 0 IN INERIM CHANGE 93- t 02 WILL allow THE IDNG SEAM WELD TO BE DONE WrrH THE CIRCUMFERENHAL WEll). ; LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 ; i t i l Semanary eruimages Sorted by Drawing and Mast No, NAPSU22 Datatene Page 63 of f 46 Prmt Dare- 11/18 98 j I [
-= = . - - -
norswing No. Mark No- IJne Number Category Item be. Location Record Period Methed - 2050-WMKS-0107B LS-70(268) . 16'-SI-407-153A413 CF1 C5.12 6856 0 PTeUT Coensaenes LDCATED BETVTEN WELDS 25 H - 268. WEPCB () CERTS ON TAPE 6XBR FRAME 2646 ADDED IN REV. 3 CllANGED FROM PERIOD 3 TO FERIOD 0 IN INTERIM CIIANGE 93
- 02. WILL ALLOW Tite I.ONG SEAM WELD TO BE DONE WITil TIIE CIRCUMFERENTIAL WELD.
LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV 5 12050-Wh1KS410B IS-7t(26b) 16*-St.407-153 A-Q3 C-F-l C5.12 3649 0 PT/UT Casusnents LOCATED BETWEEN WEIDS 250 - 26B. WEPCI)() CERTS ON TAPE 6XBR FRAME 2646 ADDED IN REV. 3. CilANGED FROM PERIOD 3 TO PERIOD 0 lN INTERIM CIIANGE 93-
- 02. WILL ALLOW Tile LONG SEAM WELD TO BE DONE WITil TIIE CIRCUMFERENTIAL WELD.
LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0107B LS-71(27A) 16'-SI-407-153A-Q3 C-F-1 C5.12 6857 0 PT/UT Cosnments IDCATED BETWEEN WLLDS 25B - 26B. WEPCB () CERTS ON TAPE 6XBR FRAME 2646 ADDED IN REV. 3 CIIANGED FROM PERIOD 3 TO PERIOD 0 IN INTERIM CilANGE 93-
- 02. WILL allow Ti!E LONG SEAM WELD TO BE DONE WITli TIIE CIRCUMFERENTIAL WELD.
LONG SEAMS WELDS WERE 11ROKEN DOWN BY INTERSECTION IN REV. 5 12030-WMKS-0!O7B LS-72(35) 10'-SI-408-153 A-Q3 C-F-I C5.12 . 3650 : O Comuments IDCATED BETWEEN WELDS 36 - 35. WEPCB D ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-WMKS-0107B LS-72(36) 10'-SI-408-153 A-Q3 C-F-1 C5.12 6858 0 Cesuments LOCATED BETWEEN WELDS 36 - 35. WEPCB O ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECFION IN REV. 5 12050.WMKS-0107B LS-73(34) 10"-SI-408-153 A-Q3 C-F-1 C5.12 3651 0 Comments LOCATED BETWEEN WELDS 34 - SW-58. WEPCB O ADDED IN REV. 3. LONG SEAMS WEIDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 13050-WMKS-Ol07B L'-73(SW 5*) 10'-SI-408-153A-Q3 C-F-1 C5.12 6859 0 Comunents LOCATED BETWEEN WELDS 34 - SW-58. WEPCB 0 ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-WMKS 0107B LS-74(I4) 10'-SI-408-153 A-Q3 C-F-1 C5.12 QSPil 3652 0 PT/UF Comnients LOCATED BETWEEN WELDS 14 - SW-57. WEPCB 0 ADDED IN REV. 3. Cl!ANGED FROM PERIOD 0 TO PERIOD 3 IN INTERIM CIIANGE 93-02. ADDED INTERSECTION CIRCUMFERENTIAL WELD TO Tile MARK NUMBER. WILL ALLOW TIIE LONO SEAM WELD TO BE DONE WITil TIIE CIRCUMFERENTIAL WELD. REPLACES 104C-2 LS-50. DO WITil CIRC WELD I4. CIIANGED FROM PERIOD 3 TO PERIOD 0 WITil REV.10 TO PIAN. Tile INTENDED WELD I4 IS ON LINE 16*-SI-407-153 A-Q3 RECORD NUMBER 3616 WHICIIIS SCIIEDULED FOR PERIOD 3. 12050-WMKS4107B LS-74(SW-57) 10'-SI-408-153A-Q3 C-F-1 C5.12 QSril 7225 0 PT/UT C - ca IDCATED BETWEEN WELDS 14 - SW-57. WEPCB O ADDED IN REV. 3. CIIANGED FROM PERIOD 0 TO PERIOD 3 IN INTERIM CIIANGE 93-02. ADDED INTERSECTION CIRCUMFERENTIAL WELD TO TIIE MARK NUMBER. WILL ALIDW THE IDNO SEAM WELD TO BE DONE WITII TIIE CIRCUMFERENTIAL WELD. REPLACES 104C-2 LS-50. 12050-WMKS-0107B LS-75(17) 10'-SI-408-153 A-Q3 C-F-1 C5.12 6860 0 Conuments LOCATED BETWEEN WELDS SW-56 -SW-55. WEPCB() ADDED IN REV 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 Senunary of Changes Sorted by Drawing and Mark No, NAPSU22 Detsbese Page 64 of 146 Pner Date: 11/1898
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Drawing No. Mark No. IJne Numtwr Categen Itens No. 14 cation Record Petied . Meetied 12090-WhlKS-0107Il LS-75(SW-56) 10'-SI-408-153A-Q3 C- -1 C512 3653 0 Comuments 1.OCATED BETWEEN WELDS SW-56-SW-55. WEPCB 0 ADDED IN REV 3 LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12050 WhlKS4107B IS76(SW-53) 10'-SI-408-153A-Q3 C-F-I C512 6861 0 Conunents LOCATED BETWEEN WELDS SW SW-53.WEPCB 0 ADDED IN REV. 3. IDNG SEAkiS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030 "'11KS-0107B LS-76(SW-54) IO*-SI-408-153 A-Q3 C-F-1 C5.12 3654 0 Cosw.ents li'CATED BETWEEN WELDS SW SW-53. WEPCB O ADDED IN REV. 3. IL.4G SEANIS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-Wh!KS-0107B LS-77(SW-52) 10'-SIA08-153A-Q3 C-F-1 C5.12 6862 0 i Comuments Lt- BETWEEN WELDS SW SW-52. WEPCB 0 ADDED IN REV. 3. ; LOM ' WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-WMKS-01078 IS77(SW-53) 10'-SI-408-153 A-Q3 C-F-I C5.12 3655 0 Comuments LOCATED BETWEEN WELDS SW SW-52. WEPCB 0 ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECFION IN REV. 5 12050-WMKS-0107B IS-78(19) 10'-SIA08-153A-Q3 C-F-1 C5.12 3656 0 Comuments LOCATED BETWEEN WELDS 19 -37. WEPCB() ADDED IN REV. 3. WNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECFION IN REV. 5 + 12050-WhlKS-0107B LS-78(37) 10'-51408-153A-Q3 C-F-1 C5.12 6863 0 C. -= LOCATED BETWEEN WELDS 19 - 37. WEPCB O ADDED IN REV. 3. LONG SEAMS WELDS WERE 6 ) KEN DOWN BY INTERSECTION IN REY. 5 12030 WMKS-0107B LS-79(16) 10'-SI408-153 A-Q3 C-F-1 C5.12 6864 0 Comuments LOCATED BETWEEN WELDS 38 - 16. WEPCB 0 ADDED IN REV. 3. IDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12030-WMKS-0IO7B LS-79(38) 10' SI-408-153 A-Q3 C-F-1 C5.12 3657 0 Comunents LOC ATED BETWEEN WELDS 38 - 16. WEPCB 0 ADDED IN REV 3. IANG SEAMS WELDS WEPI BROKEN DOWN BY INTERSECTION IN REV. 5 12050 WMKS4107D 2-QS-A-234 8'-QS403-153A-Q3 F-A Fl.0 -3671 2 VT-3 C_ = Il1IAANC. ClIANGED FROM PERIOD 0 TO PERIOD 3 IN REV. 5 REMOVED SUPPORTS FROM EXAMINA"aION PLAN TIIAT ARE NOT ON IJNES RECEIVINO NDE. TIIIS SUPPORT WAS ADDED TO ACHIEVE I5's OF CIASS 2 SUPPORTS. 12030-WMKS-0107D 2211 8'-QS403-153A-Q3 C-C C3.20 7572 0 C. = A-199. NOT SELECTED I2050-WMKS-0107D 5411 8*-QS403-153A-Q3 C-C C3.20 7574 0 C c A-234 SELECTED FOR PERIOD 2 Senumery of Climages Sorted by Drawing and Mark No., NAPSU22 Database Page 65of 96 PrretDate: Jul898
Drawing No- Mark No- . IJne Number Category Iteni No. Location Record Pested Metbd 12030-WMKS-0107D LS-IW(30) 6'-QS412-153 A.Q3 C-F-l C5.t2 6865 0 C - -- . . :. - IDCATED BETWEEN WELDS 31B - 30. WEPCB 0 ADDED IN REY. 3. LONG SEAMS WEIDS WEPE BROKEN DOWN BY INFERSECTION IN REV. 5
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' 12050-WhlKS-0107D IS-lW(31B) - ~ 6*-QS-412-153 A.Q3 C-F-I C5.12 3683 0 Comunents . LDCATED BETWEEN WELDS 31 B - 30. WEPCD 0 ADDED IN REV. 3.
LONO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5
, 12050-WMK!4107D 13-89(19) 8*.QS-403-153 A43 C-F-1 C5.12 6866 0 C -.2 LOCATED BETWEEN WEIDS 19. SW47. WEPCB O ADDED IN REV. 3.-
LONO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS4107D LS-89(SW47) 8*-QS-403-153A-Q3 C-F-1 C512 3684 0 Comuments LOCATED BETWEEN WELDS 19 -SW47. WEPCB() ADDED IN REV. 3. LONO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 120$0-WMKS-0107D LS-90(SW48) r-QS403-153 A-Q3 C-F-1 C5. D . 3685 0 Ceaunents LOCATED BETWEEN WELDS SW48 - SW49. WEPCB() ADDED IN REV 3. ' LONO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-WMKS-0107D IS-90(SW49) V-QS-403-153A-Q3 C-F-I C5.12 6867 0 Ceaunents LOCATED BET %IEN WELDS SW48 - SW49. WEPCB O ADDED IN REV. 3. LONO SEAMS WELDS WERE BROKEN DOWN BY INTERSECITON IN REV. 5 12030-WMKS-0107D . IS-94(SW-59) r-QS403-153 A-Q3 C-FI C5.12 3686 0
,C ./. IDCATED BETWEEN WELDS SW SW40. % EPCB () ADDED IN REV. 3.
LONO SEAMS WEIDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WLKS-0107D LS-94(SW40) r-QS-403-153A-Q3 C-F-1 C5.12 6868 0 Comuments IDCATED BETWEEN WELDS SW SW40. WEPCB 0 ADDED IN REV. 3. LONO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV 5 ; I 12050-WMKS-0107D IS-95(SW41) r-QS403-153 A-Q3 C-F-1 C512 3687 0 PT tH-0,45 C_ -; LOCATED M. TWEEN WELDS SW41 - SW62. WEPCB 0 ADDED IN REV. 3. LONG SEAMS WEIDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 e 13050-WMKS-0107D LS-95(SW42) r-QS403-153 A-Q3 C-F-I C5.12 6869 0 PT tJT-0,45 C. ./. LOCATED BETWEEN WELDS SW41 - SW62. WEPCB () ADDED IN REV. 3. IDNO SEAMS WELDS WERE BROKEN DOWN BY INIERSECTION IN REV 5 , 12050-WMKS-0107D LS-96(SW42) r-QS-493-IP S-Q3 C-F1 C5.12 3688 0- i Comunents LOCATED BETWEEN WELDS SW42 - SW43. WEPCB 0 ADDED IN REV. 3. IJ1NG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. $ . 12030-WMKS-0107D IS-96(SW43) r-QS403-153A-Q3 C-F-1 C5.12 6870 0 ; Comunents IDCATED BETWEEN WEIDS SW42 - SW43. WEPCB 0 ADDED IN REV. 3-LONO SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 l Sunumery of Changes Sorted by Drawing and Mark No., NAPSU22 Database Page 66of N6 Prmt Date: 11/18 98 f __. _ _ _ _ _ _ . _ _ _ . - - __=___ -- ___ _ _ _ _ . - - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ - _ - _ _ _ _ - _ _ _ = _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - - - _ _ _ _ - _ _ -
W -.h' - -- .. -
- Drawlseg No- Mark No. IJne Number Caterary leem No. Locatiem . Record Period Meelsed 12050-WMKS-Ol07D LS-97(18) 8'-QS-403-153 A-Q3 C-F-1 C5.12 36R9 0 Comunents LOCATED BETWEEN WELDS 18 - SW44. WEPCB 0 ADDED IN REV. 3.
I ONG SEAhtS WELDS WERE BROKEN IX)WN BY INTERSEC110N IN REY. 5 12030-WMKS-0107D IS-97(SW44) 8*-QS-403-153 A-Q3 C-F-l C5.12 6871 0 Comunents LOCATED BETWEEN WELDS 18 - SW-64. WEPCB 0 ADDED IN REV. 3. LONG SEAhtS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12a30-WMKS-0107D LS-98(SW-65) 8*-QS-403-153 A-Q3 C-F-1 ~ C5.12 3690 0- PT,UT-0,45 Coennierts LOCATED BETWEEN WELDS SW SW-66. WEPCB () ADDED IN REV. 3. IJONG SEAMS WELDS WERE BR.OKEN DOWN BY INTERSECTION IN REY. 5 12050-WMKS-0107D LS-98(SW-66) 8'-QS-403-153 A-Q3 C-F-1 C5.12 6872 .O PT,UT-0,45 Comenients LOCATED BETWEEN WELDS SW SW-66. WEPCB O ADDED IN REV. 3. IENG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0107D LS-99W(SW-55) 6*-QS-412-153 A-Q3 C-F-1 C512 3691 0 Comsnents LOCATED BETWEEN WELDS SW SW-56. WEPCB () ADDED IN REY.3. IJONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0107D 13-99W(SW-56) 6*-QS-412-153 A-Q3 C-F-1 C5.12 6873 0 Ceaunents LOCATED BETWEEN WELDS SW SW-56. WEPCB () ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0107DA 1011 8*-SIIP-472-60 l-Q3 D-A DI.20 AFPli 3710 I NT-3 Comments 100% INSULATION NEEDS TO BE REMOVED. R-5 NOT SELECTED. CIIANGED ITEh! J7 UMBER TO AGREE WITII PRESSURE TESTING PROGRAM IN REV. 8. 12030-WMKS-0107DA 1311 10'-SIIP-471601-Q3 D-A DI.20 AFPII 37tl 2 VT-3 Ceaunents 100*6. R-8 SELECTED FOR PERIOD 2. CIIANGED ITEM NUMBER TO AGREE WITil PRESSURE TESTING PROGRAM IN REV. 8. 12050-WMKS-0107DA 2-SIIP-RII-29 8*-SilP-476-601-Q3 F-C F3.0 YARD TUNNEL 3716 0 VT-3 Comsnents AllARES, EXAMINED IN 90 NRL New with Rev. I I to the plan: removed from plan (in Period 3) due to reevaluation of the Class 3 total support population. 12030-WMKS-0107DA 21J 8"-SilP-477-601-Q3 D-A DI.20 YARD 1UNNEL 3712 0 VT-3 Comments 100%(R11-28 NOT SELECTED). CIIANGED FROM PER!OD 3 TO PERIOD 0 IN REV. 7. RELIEF REQUEST NDE-21 allow USE OF CODE CASE N-509 TO EXAMINE 10% OF111E INTEGRAL ATTACIIMENTS. CIIANGED ITEM NUMBER TO AGREE %TTII PRESSURE TESTING PROGRAM IN REV. 8. , 12030-WMKS-0107DA 22J 8'-SitP-476-601-Q3 D-A DI.20 YARD TUNNEL 3713 3 \T-3 Comunents 100's(RH-29 SELECTED FOR PERIOD 3). CIIANGED ITEM NUMBER TO AGREE %7Til PRESSURE TESTING PROGRAM IN REV. 8. 12050-WMKS-0107DA 28J 10*-SHP-475-601-Q3 D-A DI.20 YARD TUNNEL 3714 I NT-3 Canunents 100% INSULATION NEEDS TO BE REMOVED. RII-37 NOT SELECTED. CIIANGED 111M NUMBER TO AGREE %7Til PRESSURE TESTING PROGRAM IN REY. 8.
- 12050-WMKS-0107E 2-SI-R-175 8'-SI-440-153A-Q2 F-A Fl.0 QSPli 3722 0 VT-3 Conunents B11AGUD2. CilANGED FROM PERIOD 3 TO PERIOD 0 IN REV. 5. ONLY NEED TO EXAMINE I 5% OF SUPPOR13 ON 1.INES RECEIVING ANOTIIER TYPE OF EXAhE Sasnmery of C1senges Sorted by Drawing and Mark No, NAPSU22 Database Page 67of146 Pnne Date
- 11/1893 I l
Drawing No. Mark No. I Ine Number Category Item No. Imration Record Period Afethod 120$0-WMKS-0107E 2-SI-R-224 r-SI-440-153 A-Q2 F-A FI O QSPil 3728 0 %T-3 Comments 1111AGUD2. CitANGED FROM PFRIOD 2 TO PERIOD 0 IN REV. 5 ONI_Y NEED TO ELulINE 15'.OF SI'PPORTS ON IJNES RECEIVING ANOTI!ER TYPE OF EXAkt 12050-WMKS-0107E LS-58W(38) r-St-440-153 A-Q2 C-F-1 C5.12 3739 0 Comments LOCATED BETWEEN WELDS SW 38. ADDED IN REV. 3. IDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5
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12050-WMKS-0107E IS-58W(SW-551 r-SI-440-I 53 A-Q2 C-F.I C5.12 6874 0 Comments LOCATED BETWEEN WELDS SW 3R. ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REY. 5 12090-WMKS-0107E LS-59W(SW-56) r-SI-440-153 A Q2 C-F-1 C5.12 3740 0 Comments LOCATED BENEEN WELDS SW 57 - SW-56. ADDED IN REV. 3. IDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12030-WMKS-0107E IS-59W(SW-57) 8'-SI-440-153A-Q2 C-F-1 C5.12 6875 0 Comments LOCATED BETWEEN WELDS SW SW-56. ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSECFION IN REV. 5 12050-WMKS-0107' LS-60W(37A) 8*-SI-440-153 A-Q2 C-F-1 C512 3741 0 Comments IDCATED BETWEEN WELDS SW 37A. ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY LNTERSECTION IN REV. 5 12050-WMKS-0107E IS40W(SW-58) 8'-SI-440-153A-Q2 C-F-1 C5.12 6876 0 Comments LOCATED BETWEEN WELDS SW 58- 37A ADDEDIN REV. 3. IENG SEAMS WELDS WERE BROKEN DOWW BY INTERSECTION IN REY. 5 12050-WklKS-0107E LS41W(SW-59) 8'-SI-440-153 A-Q2 C-F-I C5.12 3742 0 Comments LOCATED BETWEEN WELDS SW40 - SW-59. ADDED IN REV. 3. IDNG SEAMS WELDS WERE BROKEN DOWN BY INTERSECIION IN REV. 5 12050-WMKS-0107E LS41W(SW40) 8'-SI-440-153 A-Q2 C-F-1 C512 6877 0 Comments LOCATED BENEEN WELDS SW40 - SW-59. ADDED IN REV. 3. LONG SEAMS WELDS WERE BROKEN DOWN BY INTERSEC110N IN REV. 5 12030-WMKS-0107E LS42W(SW41) r-SI-440-I 53A-Q2 C-F-1 C5.12 3743 0 Comments LOCATED BET % TEN WELDS SW42 - SW41. ADDED IN REV. 3. IDNG SEAMS %TLDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0107E LS42W(SW42) Y-SI-440-153 A-Q2 C-F-1 C5.12 6878 0 Comments LOCATED BENEEN WELDS SW42 -SW41. ADDED IN REV. 3. IANG SEAMS WELDS WERE BROKEN DOWN BY INTERSECTION IN REV. 5 12050-WMKS-0107E IE43W(SW43) 8'-SI-440-153 A-Q2 C-F- 1 C5.12 3744 0 PTUF Comments LOCATED BETWEEN WELDS 35 - SW43. ADDED IN REY. 3. CIIANGED FROM PERIOD 0 TO PERIOD I IN INTERIM CIIANGE 9342. ADDED INTERSECTION CIRCUMFERENTIALWELD TO Tite MARK NUMBER. INTERIM CIIANGE 934}}