ML20065S720
| ML20065S720 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/21/1990 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20065S722 | List: |
| References | |
| PROC-901121, NUDOCS 9012240102 | |
| Download: ML20065S720 (126) | |
Text
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1 VIRGINIA ELECTRIC AND POWER: COMPANY NORTH ANNA POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM FOR
'THE SECOND INSPECTION INTERVAL VOLUME 1
. INSERVICE INSPECTION PROGRAM FOR COMPONENTS'AND COMPONENT SUPPORTS REVISION 1.-
SEPTEMBER-1990 INTERVAL 2 DECEMBER 24,'1988 DECEMBER 24, 1998 i
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VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 i
INSERVICE INSPECTION PROGRAM l
O SECOND INSPECTION INTERVAL DECEMBER 24, 1988 - DECEMBER 24, 1998 REVISION 1 DISTRIBUTION RECORD l
DISTRIBUTION DATE DISTRIBUTION DATE NO.
ENTERED INITIAL NO.
ENTERED INITIAL 1
21 2
22 3
23 4
24 5
25 6
26 l
7 27 8
28 9
29 10 30 11 31 12 32 13 33 14 34 15 35 16 36 l
17 37 18 38 19 39 20 40 Future distributions to this program two copies of the distribution memo, plan will be accompanied by one of which is to be returned per instructions thereon, and the other one is to he O
filed sequentially behind this page giving you a record of the contents of each distribution.
11 N1-000 Rev. 1 1990
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TABLE OF CONTENTS i
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SECTION TITLE PAGE i
Assignment 11 Distribution Recotd-111 Table of Contents iv Abstract 1
Inservice Inspection Program -
General 2
Inservice Inspeccion Program for Components 3
Inservice Inspection Program for Component Supports i
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N1-000 Rev. 1 1990 l
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' ABSTRACT
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VIRGINIA ELECTRIC AND POWER COMPANY:
NORTH ANNA POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM 1
SECOND INSPECTION INTERVAL DECEMBER 24,_1988 TO' DECEMBER 24, 1998 In accordance with 10 CFR 50.55a dated January 3.
38,.the North Anna Unit 1 (NAPS-1) Inservice inspection (ISI) Irtgram was updated'to meet the requirements of ASME:Section XI, 1983_ Edition with Addenda through Summer 1983.
This updated program is for the NAPS-1 second ten year inspection interval scheduled to commence December 24, 1988 and be completed' December ~ 24,'1998.-
These dates reflect a first interval extension of 201 days documented in our letter to the NRL dated 8/25/88, Serial No. 1 486.
In cases-where the requirements of Section XI have been determined to be-impractical, requests for, relief have been developed per 10 CFR 50.55a(g) (5) (iii).
This program is divided into two volumes.
Volume 1 contains the Inservice Inspection Program, and Volume-2, which was previously submitted, contains the Inservice Testing Program.
The Inservice Inspection Program does not-include requirements per. Subsection IWE, Requirements For Class MC Components Of Light Water Cooled-Power Plants.
Current Federal Regulations do not require these rules to be included in ISI programs.
t This document provides an overview and cummary of the NAPS-1 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,-IWC-1220, IWD-1220, and IWF-1230 are shown on the ISI_ Classification Boundary-Drawings (CBDs) listed on pages 1-11 to 1-14.
The codings, symbols and text used on the CBDs are detailed on 11715-CBM-L&S-2,-Legends and Symbols Drawing.
Section 1 of this document provides the general information and format regarding this program.
Section 2 of this document provides a program implementation overview of the.ISI Program for ISI Class 1, 2,
and 3 components.
A summary table of Section XI requirements applicable to NAPS-1 is provided as well as relief requests for components.- Section 3 of this document provides1a program implementation overview for ISI class 1, 2,
and 3 component supports.
A summary table of Section XI requiremente applicable to NAPS-1 component supports is provided as well as relief requests for component supports.
iv N1-000 Rev. 1 1990
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VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION
-UNIT 1 INSERVICE INSPECTION PROGRAM GENERAL SECOND INSPECTION INTERVAL-1 O
N1-001 1-1 Rev. 1 1990_
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SECTION 1 l TABLE OF CONTENTS SECTION PAGE 1.0 INSERVICE INSPECTION PROGRAM--- GENERAL-1 1.1 GENERAL INFORMATION 1-2 1.1.1 Preservice Examinations 1-2 1.1.2 Initial Inservice Inspection Interval 2-~
1.1.3 Second Inservice Inspection Interval'-
1 1.1.4 Inservice Inspection Program-1-2 '-
Description 1.2 DRAWING LIST - ISI CLASSIFICATION BOUNDARY 1-11 DRAWINGS O
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N3-001 1-2 Rev. 1 1990 L.
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1.0 INSERVICE INSPECTION PROGRAM - GENERAL 1.1 GENERAL INFORMATION North Anna Power Station Unit 1 (NAPS-1) is located on Lake Anna in Louisa County, Virginia.
The plant employs a Pressurized Water Reactor-(PWR) and associated Nuclear Steam Supply System components provided by Westinghouse Electric Corporation.
1.1.1 Preservice Examinations Preservice examinations at NAPS-1 were performed utilizing the requircments of ASME Section XI, 1974 Edition with Addenda through Summer 1975.
1.1.2 Initial Inservice Inspection Interval NAPS-1 commercial operation commenced on June 6, 1978.
Accordingly, the initial ten year inspection interval started on 6/6/78.
This interval, however, was extended 201 days to 12/24/88 as documented by letter to the NRC dated 8/25/88, serial no.88-486.
Examinations 7s during the first inspection interval were also
)
performed per ASME Section XI, 1974 Edition with v'
Addenda through Summer 1975.
Certain system pressure testing requirements were completed per ASME Section XI, 1977 Edition with Addenda through Summer 1979.
1.1.3 Second Inservice Inspection Interval As mandated by the Code of Federal Regulations, Title 10, Part 50, Section 50.55a (10 CFR 50.55a), the NAPS-1 Inservice Inspection (ISI)
Program has been updated to the 1983 Edition through the Summer 1983 Addendum of ASME Section XI.
This is the latest edition and addenda of Section XI incorporated into 10 CFR 50.55a as of December 24, 1987.
The second inservice inspection interval is scheduled to commence on December 24, 1988 and be completed on December 24, 1998.
As allowed by the Code of Federal Regulations Title 10, Part 50, Section 50. 55a (g) 4 (iv), the NAPS-1 Inservice Inspection (ISI) Program shall utilize the 1986 Edition of ASME Section XI for recertification of Level III NDE Personnel as l ('T required in paragraph IWA-2300a(1) only. (5 year G
1 N1-001 1-3 Rev. 1 1990
1.1.3 Second Inservice Inspection Interval (Continued) recertification) 1.1.4 Inservice Inspection Program Description =
The ISI Program contained herein addresses the inservice inspection and testing _of ISI Class 1,
.2, and 3 components and the associated component supports.
Applicable requirements in Subsections IWA, IWB, IWC, IWD, IWF and the Mandatory Appendices of the 1983 Edition of ASME Section XI through the. Summer 1983 Addendum have been incorporated into our corporate and site ISI programs and procedures.
Any programmatic modifications to these requirements'are discussed in this document.
This document is not intended to provide specific information on the implementation of the ISI Program.
The intent of this document-is to provide specific information on the scope of the NAPS-1 ISI program-(i.e., its boundary and compliance with Section XI) and identify those g-sg g
j Section-XI requirements which are deemed impractical.
Requests for relief for these impractical requirements have been developed per 10 CFR 50.55a(g) (5) (iii).
1.1.4.1 Exclusion of Subsection IWE.
Subsection IWE, Requirements For Class MC Components of Light-Water Cooled Power Plants, is not-included'in this-program per-the Final Rules in the Federal Register, Volume 53, page 16053, which specifically excludes the requirements of Subsection IWE from 10 CFR 50.55a.
1.1.4.2 Exclusion of Subsections-IWP and IWV TSubsections IWP and IWV, Inservice Testing of Pomps and Inservice Testing of Valves in Nuclear. Power-Plants are not included in this program.
The IWP l
and IWV. program was submitted-separately.
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.N1-001
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i 1.1.4.3 Inservice Inspection Plan The inservice inspection plan required by:IWA-2420, detailing the-components and_ component _ supports selected for examination during the interval will be provided as a separate document.
1.1.4.4 Inspection Program Employed The ISI Program for North Anna Unit 1 will utilize the interval format of Inspection' Program B,-as shown in IWA-2432.
1.1.4.5 Weld Reference System The weld reference system required by IWA-2600 is_a.recent addition to.the rules of ASME Section XI.
The implementation plan for this requirement is detailed in relief requests NDE-13 and_NDE-14, shown on pages 2-69 and 2-70 respectively.
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1.1.4.6 Classification of Components A.
Classification of Components-Design North Anna Unit 1 was issued construction permit No. CPPR-77 in February 1971.
The station design
' incorporates the codes and-standards that were in effect when the equipment-was purchased._ -The:
codes and standards used for.the design, fabrication, erection, and testing of safety related components are_ commensurate with the importance of the safety functions to be performed.
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_N1-001 5 Rev. 1 1990
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A.
-Classification of-' Components-Design (Continued)'
The group classifications. tabulated
-in:the:" Standard-Format'and Content of Safety Analysis Reports for-Nuclear Power Reactors", tissued;in February 1971,:and'in. Safety. Guide No.-26~, published ~in March 1972,-
incorporated, in-most cases,:later-editions-of-codes than those in effect when the majority ofisafety-related equipment was designed.
Some.of the equipment that would fall under a-" group":as defined <in Safety Guide No. 26 was designed to:
differenticodes or different editions.of_the same-code.'
For
. example,: for' different - components that=would be in the same group, oneLmay be designed to ASME III-1968, one to-_ASME III-1971,-and=one to_ASME VIII-1968.
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Therefore,. pressure-containing-
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components of safety-related' systems do not necessarilyLfall-under the group classification--
r listed above.
B.
ClassificationJof Components-.
Inservice Inspection The classification of~ components-
-for: Inservice Inspection-was; performed by employing the guidelines of lo:CFR 50.55a,JUSNRC Regulatory Guide 1.26 Revision 3,.
ANSILN18'.2-1973,7 ANSI.N18.2a-1975, and NUREG-0800,1 Standard Re'iiew
' Plan 3.2.2-Revisionil, in conjunction with the System Quality
' Group Classification Section of the.
North Anna, Power Station UFSAR,-
Section 3.2~2.-
Quality? Groups A,=
B, and C, as discussed;in Regulatory-Guide 1.26!are l
-considered the same as ISI. Classes 1,
2, and 3 for the purposes of:
this program.
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N1-001 1-6
'Rev. 1 1990
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B.
Classification of Components-Inservice Inspection (Continued)
The ISI Classification of each component included in NAPS-1 program is shown on the ISI Classification Boundary Drawings (CBDs) listed on pages 1-11 to 1-14.
The Legends and Symbols ISI Classification Boundary Drawing (11715-CBM-L&S-2) details the line codings and component markings which provide the ISI Classification of all items included within the ISI Program boundaries.
In general, the ISI classification of piping is accomplished by line " codings" or symbols shown on 11715-CBM-L&S-2.
ISI Classification of components which graphically cannot be coded, such as pressure vessels, pumps, strainers, and tanks, etc. is shown as text (e.g., ISI Class 1A, 3E, etc.) either inside the component f) graphics or adjacent to the b/
component mark number.
Classification changes are typically shown at the seat of a valve, with the ISI Class shown on either side of the classification
" break line".
1.1.4.7 Components and Component Supports Exempt from Examination The application of the exemptions l
allowed per IWB-1220, IWC-1220, IWD-1220,-and IWF-1230 is also detailed by tne codings and component markings of 11715-CBM-L&S-2 discussed in section l
1.1.4.5.2.
Because the exemptions-of l
IWF-1230 are "in the course of preparation", a set of exemptions for component supports developed in a proposed code case, WGCS 89-1(b) is i
being employed.
Relief request CS-1 details the reasoning for this program modification.
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N1-001 1-7 Rev. 1 1990
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l.1.4.8 Requests For Relief-Components and-Component Supports 1
Whereithe requirements of ASME Section XI have been determined ~to be impractical, requests for relief have.
been developed in accordance with 10 CFR 50.55a(g) (5) (iii).
The. impractical requirements are detailed in-three sets i
of relief requests:
an NDE series for components'and nondestructive.
examination areas, an-SPT series for system pressure 1 testing. areas, and a CS series =for component support areas..
.Each reliefErequest is formatted as follows:
-I.
IDENTIFICATION OF COMPONENTS II. IMPRACTICAL CODE REQUIREMENTS III. BASIS FOR RELIEF IV.
ALTERNATIVE EXAMINATION ~
7s (OR TESTING)~
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Relief requests which pertain to a specific ASME Section-XI Category and Item Number are referenced in the Inservice Inspection Program Summary-Tables in Sections 2 and 3 of this-document. ' Relief requests which are
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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.
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l N1-001 1-8 Rev. 1 1990
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1.1.4.9 ASME Section XI Code Cases Incorporated Into Program As allowed by 10 CFR 50.55a(c) (3) and USNRC Regulatory' Guide 1.147, Revision 7, the following Code Cases are being incorporated into the NAPS-1 ISI Program:
Case N-401 - Eddy Current Examination,Section XI, Division 1.
Case N-402 - Eddy Current Calibration Standard Material,Section XI, Division 1.
Case N-406 - Alternative Rules for Replacement,Section XI, Division 1.
Case N-408 - Alternative Rules for Examination of Class 2 Piping Section XI, Divisioni.
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Case N-416 - Alternative Rules For Hydrostatic Testing of Repair or Replacement of Class 2 Piping,Section XI, Division 1.
Case N-426 - Extent of VT-1 Examinations, Category B-G-2 of Table IWB-2500-1,Section XI, Division 1.
l Case N-446 - Recertification of Visual
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Examination Personnel,Section XI, Division 1.
l Case N-457 - Qualification Specimen Notch Location.for Ultrasonic Examination of Bolts and StudsSection XI, Division 1.
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LI N1-001 1-9 Rev. 1 1990
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f 1.1.4.10-' Augmented-Inservice--Inspection Program
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for ISI: Class'l', 2,;and 3 Components:
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-: Augmented'-Inservicef Inspection
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activities which pertain-toJcomponents 1
within the scope of-the ASME--Section' XI program are summarized in Section.
2,: Table-2.6.
=A listing'ofispecific 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 LJ.ST NORTH ANNA UFIT 1 SECOND INSPECTION-INTERVAL ISI CIASSIFICATION BOUNDARY DRAWINGS O
l O N1-001 1-11 Rev. 1 1990
NORTH ANNA UNIT 1 INTERVAL 2 ISI CLASSIFICATION BOUNDARY DRAWINGS
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SORTED BY SERIES LEGENDS AND SYMBOLS DRAWING
- : DRAWING NUMBER
- SHEET TITLE 1.
11715-CBM-L&S-2
- 1 OF 1 : LEGEND AND SYMBOLS 11715-CBB SERIES
- : DRAWING NUMBER
- SHEET TITLE 1.
11715-CBB-006A-2 : 1 OF 3 : AIR COOLING AND PURGING SYSTEM 2.
11715-CBB-040D-2 : 1 OF 3 : AIR CONDITIONING CONDENSER WATER SYSTEM 3.
11715-CBB-102B-2 : 1 OF 1 : INTERIOR FIRE PROTECTION & HOSE RACK SYS 11715-CBM SERIES
- : DRAWING NUMBER
- SHEET TITLE 1.
11715-CBM-070A-2 : 1 OF 3 : MAIN STEAM SYSTEM 2.
11715-CBM-070A-2 : 3 OF 3 : MAIN STEAM SYSTEM 3.
11715-CBM-070B-2 : 1 OF 3 : MAIN STEAM SYSTEM 4.
11715-CBM-070B-2 : 2 OF 3 : MAIN STEAM SYSTEM 5.
11715-CBM-070B-2 : 3 OF 3 : MAIN STEAM SYSTEM 6.
11715-CBM-072A-2 : 2 OF 3 : AUXILIARY STEAM & AIR REMOVAL SYSTEM
[#l 7.
11715-CBM-074A-2 : 1 OF 3 : FEEDWATER SYSTEM
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8, 11715-CBM-074A-2 : 3 OF 3 : FEEDWATER SYSTEM 9.
11715-CBM-078A-2 : 1 OF 4 : SERVICE WATER SYSTEM
- 10. 11715-CBM-078A-2 : 3 OF 4 : SERVICE WATER SYSTEM
- 11. 11715-CBM-078A-2 : 4 OF 4 : SERVICE WATER SYSTEM
- 12. 11715-CBM-078B-2 : 1 OF 4 : SERVICE WATER SYSTEM
- 13. 11715-CBM-078B-2 : 2 OF 4 : SERVICE WATER SYSTEM
- 14. 11715-CBM-078C-2 : 1 OF 2 : SERVICE WATER SYSTEM I
- 15. 11715-CBM-078C-2 : 2 OF 2 : SERVICE WATER SYSTEM
- 16. 11715-CBM-078G-2 : 1 OF 2 : SERVICE WATER SYSTEM 17, 11715-CBM-078G-2 : 2 OF 2 : SERVICE WATER SYSTEM
- 18. 11715-CBM-078H-2 : 1 OF 1 : SERVICE WATER SYSTEM
- 19. 11715-CBM-078J-2 : 1 OF 1 : SERVICE WATER SYSTEM
- 20. 11715-CBM-078K-2 : 1 OF 1 : SERVICE WATER SYSTEM
- 21. 11715-CBM-079A-2 : 1 OF 3 : COMPONENT COOLING WATER SYSTEM
- 22. 11715-CBM-079A-2 : 2 OF 3-: COMPONENT COOLING WATER SYSTEM
- 23. 11715-CBM-079A-2 : 3 OF 3 : COMPONENT COOLING WATER SYSTEM
- 24. 11715-CBM-079B-2 : 1 OF 5 : COMPONENT COOLING K.TER SYSTEM
- 25. 11715-CBM-079B-2 : 2 OF 5 : COMPONENT COOLING WATER SYSTEM
- 26. 11715-CBM-079B-2 : 3 OF 5 : COMPONENT COOLING WATER SYSTEM
- 27. 11715-CBM-079B-2 : 4 OF 5 : COMPONENT COOLING WATER SYSTEM l
- 28. 11715-CBM-079B-2 : 5 OF 5 : COMPONENT COOLING WATER SYSTEM l
- 29. 11715-CBM-079C-2 : 1 OF 5 : COMPONENT COOLING WATER SYSTEM
- 30. 11715-CBM-079C-2 : 3 OF 5 : COMPONENT COOLING WATER SYSTEM
- 31. 11715-CBM-079C-2 : 4 OF 5 : COMPONENT COOLING WATER SYSTEh
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- 32. 11715-CBM-079C-2 : 5 OF 5 : COMPONENT COOLING WATER SYSTEM
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- 33. 11715-CBM-079D-2 : 4 OF 5 : COMPONENT COOLING WATER SYSTEM l-12
s NORTH: ANNA UNIT 1 INTERVAL 2 ISI CLASSIFICATION' BOUNDARY DRAWINGS.
SORTED BY SERIES-CONTINUED' 11715-CBM SERIES
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- SHEET TITLE
- 34. 11715-CBM-082A-2 : 1 OF 3 : COMPRESSED AIR SYSTEM
- 35. 11715-CBM-082F-2 : 1 OF 1 : COMPRESSED-AIR: SYSTEM
- 36. 11715-CBM-082N-2 : 1 OF 3 : COMPRESSED AIR SYSTEM j
37.-11715-CBM-082N-2 : 3 OF 3,: COMPRESSED AIR SYSTEM 1
- 38. 11715-CBM-088A-2 : 10F 4 : FUEL PIT CLNG-& REFUELING PUR. SYSTEM'
- 39. 11715-CBM-088A-2 : 2 0F 4 : FUEL PIT CLNG & REFUELING PUR. SYSTEM
- 40. 11715-CBM-088A-2 : 4 0F 4 : FUEL PIT CLNG & REFUELING-PUR. SYSTEM-
- 41. 11715-CBM-089B-2 : 3 OF 4 : SAMPLING SYSTEM
- 42. 11715-CBM-089D-2 : 1 OF 1 : SAMPLING SYSTEM
- 43. 11715-CBM-090A-2-: 1 OF 2-1 VENT & DRAIN SYSTEM
- 44. 11715-CBM-090C-2 : 1 OF 3 : VENT & DRAIN-SYSTEM
- 45. 11715-CBM-090C-2 1 3 OF 3 : 7ENT & DRAIN SYSTEM-
- 46. 11715-CBM-091A-2 : 1 OF 4 : CONT QUENCH-&.RECIR SPRAY SUB' SYSTEM
- 47. 11715-CBM-091A-2 : 2 OF 4 :. CONT QUENCH & RECIR SPRAY SUB' SYSTEM 48, 11715-CBM-091A-2 : 3 OF 4 : CONT-QUENCH &-RECIR' SPRAY SUB SYSTEM
- 49. 11715-CBM-091A-2 : 4 OF 4 : CONT QUENCH & RECIR SPRAY-SUB SYSTEM
- 50. 11715-CBM-091B-2 : 1 OF 1 : CONT QUENCH & RECIR SPRAY SUB SYSTEM
- 51. 11715-CBM-092A-2 : 1 OF 2 : LEAKAGE MONITOR SYSTEM-
- 52. 11715-CBM-092A-2 : 2 OF 2 : CONTAINMENT VACUUM < SYSTEM
- 53. 11715-CBM-093A-2 : 1 OF 3 : REACTOR COOLANT SYSTEM' h
54.
11715-CBM-093A-2 : 2 OF 3 : REACTOR' COOLANT SYSTEM v-55, 11715-CBM-093A-2 : 3 OF 3 : REACTOR COOLANT SYSTEM
- 56. 11715-CBM-093B-2 : 1 OF 3 : REACTOR COOLANT SYSTEM
- 57. 11715-CBM-093B-2 : 2 OF. 3 : REACTOR COOLANT SYSTEM'
- 58. 11715-CBM-094A-2 : 1 OF 2 : RESIDUAL HEAT REMOVAL SYSTEM
- 59. 11715-CBM-094A-2 : 2 OF 2 : RESIDUAL HEAT REMOVAL SYSTEM-
- 60. 11715-CBM-095A-2 : 1 OF 4 : CHEMICAL-AND VOLUME CONTROL SYSTEM
- 61. 11715-CBM-095A-2 :'2 OF 4 : CHEMICAL AND VOLUME. CONTROL SYSTEM
- 62. 11715-CBM-095A-2 : 3 OF 4 : CHEMICAL AND VOLUME CONTROL SYSTEM
- 63. 11715-CBM-095A-2 : 4 OF 4 :-CHEMICAL AND VOLUME CONTROL-SYSTEM
- 64. 11715-CBM-095B-2 : 1 OF 2 :-CHEMICAL AND. VOLUME CONTROL SYSTEM
- 65. 11715-CBM-095B-2 : 2 OF 2 : CHEMICAL AND VOLUME' CONTROL SYSTEM
- 66. 11715-CBM-095C-2 :.1 OF 2 :. CHEMICAL AND. VOLUME CONTROL SYSTEM
- 67. 11715-CBM-095C-2 : 2-OF 2 :-CHEMICAL AND VOLUME CONTROL SYSTEM
- 68. 11715-CBM-096A-2 : 1 OF 3 : SAFETY INJECTION SYSTEM
- 69. 11715-CBM-096A-2 : 2 OF 3 : SAFETY INJECTION SYSTEM
- 70. 11715-CBM-096A-2 : 3 OF 3 : SAFETY INJECTION SYSTEM.
- 71. 11715-CBM-096B-2 : 1 OF 4 : SAFETY INJECTION SYSTEM
- 72. 11715-CBM-096B-2 : 2 OF 4 : -SAFETY INJECTION. SYSTEM 73, 11715-CBM-0968-2 : 3 OF 4 : SAFETY INJECTION SYSTEM
- 74. 11715-CBM-096B-2 : 4 OF14 :l SAFETY INJECTION SYSTEM
- 75. 11715-CBM-098A-2 : 2 OF 5 :'.STEMI GENERATOR-BLOWDOWN SYSTEM i
- 76. 11715-CBM-098A-2 : 3 OF 5 : STEAM GENERATOR BLOWDOWN SYSTEMt
- 77. 11715-CBM-098A-2 : 4 OF 5 : STEAM GENERATOR BLOWDOWN SYSTEM-OV 13 l-r
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. NORTH ANNA UNIT 1 INTERVAL 2 ISI CLASSIFICATION-BOUNDARY DRAWINGS
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SORTED BY SERIES-CONTINUED O
11715-CBM SERIES
- : DRAWING NUMBER
- SHEET TITLE
- 78. 11715-CBM-102A-2 : 2 OF 2 : Cl!EMICAL FEED SYSTEMS
- 89. 11715-CBM-105B-2 : 1 OF 2 - : SECONDARY PLANT GAS SUPPLY SYSTEM S0. 11715-CBM-106A-2 : 1 OF 4 : COFTAINMENT ATMOSPHERE CLEANUP SYSTEM
- 81. 11715-CBM-106A-2 : 2 OF 4 : CO!'TAINMENT ATMOSPHERE CLEANUP SYSTEM
- 82. 11715-CBM-106A-2': 3 OF 4-: CONTAINMENT ATMOSPHERE CLEANUP SYSTEM
- 83. 11715-CBM-106A-2 : 4 OF 4 : CONTAINMENT ATMOSPHET.E CLEANUP SYSTEM 13075-CBM SEWIES
- : DRAWING NUMBER
- SHEET TITLE 1.
13075-CBM-093C-2 : 1 OF 2 : REACTOR COOLANT SYSTEM 2.
13075-CBM-093C-2 : 2 OF 2 : REACTOR COOLANT SYSTEM 3.
13075-CBM-102C-2 : 1 OF 1 : CHEMICAL' FEED SYSTEM O
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O VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM FOR COMPONENTS SECOND INSPECTION INTERVAL i
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N1-002 2-1 Rev. 1 1990
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SECTION 2 TABLE OF CONTENTS SECTION PAGE 2.0 INSERVICE INSPECTION PROGRAM FOR COMPONENTS 2-3 2.1 PROGRAM DESCRIPTION 2-3 2.1.1 Section XI Requirements.
2-3 2.1.2 Weld Selection for Class 1. Piping 2-3 2,1.3 Weld Selection for Class'2 Piping.
2 '
2.2 PROGRAM
SUMMARY
2-4 2.2.1 Inservice Inspection-Program Summary Description 2-4 2.3 ISI CLASS 1. COMPONENTS - PROGRAM
SUMMARY
TABLE 2-6 2.4 ISI CLASS 2 COMPONENTS - PROGRAM-
SUMMARY
TABLE 2-32 2.5 ISI CLASS 3 COMPONENTS - PROGRAM
SUMMARY
TABLE-2-43 2.6 AUGMENTED INSPECTION REQUIREMENTS'ON ISI CLASS 1, 2,
2-46 OR 3 SYSTEMS.- PROGRAM
SUMMARY
TABLE 2.7 COMPONENT RELIEF REQUESTS 2 2.7.1 NDE. Series Relief Requests 2-48
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2.7.2 SPT-Series Relief Requests 2.
l N1-002 2-2 Rev. 1 1990
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2.0 INSERVICE INSPECTION PROGRAM FOR COMPONENTS 2.1 PROGRAM DESCRIPTION 2.1.1 The Inservice Inspection Program-for ISI Class 1,
2 and 3 components meets the requirements of Section XI of the ASME Boiler and Pressure Vessel Code,-1983 Edition through the Summer 1983 Addendum except_where these requirements have been determined to be impractical.
Detaile' relief requests for these impractical requirements are included ir r'ction 2.7.
Programmatic modifications cv Section XI requirements are outlined in Sections 2.1.2_and 2.1.3.
2.1.2 JSI 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 will be comprised as follows:
one' half of the sampling (12.5%:of the total number of piping welds) will be welds-which were examined during the first. interval, and one-half of the sampling (12.5% of the. total-number of piping welds)
- Pi be welds which were not examined-T during the first interval.
The welds selected 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 ir lieu of~ Notes 1(b) and 2 of Category B-J, Table IWB-2500-1.
See Relief Request NDE-4 for details.
2.1.3 ISI Class 2 Carbon Steel piping: welds will be selected for' examination per ASME Section XI, 1974 Edition with Addenda through Summer 1975, IWC-2411 as allowed by 10 CFR
- 50. 55a (b) (2) (iv) (B).
The Section XI Category (C-F) Item Number, Exam. Method,JExam Figure, and Acceptance Criteria will be per the 1983 Edition with Summer 1983 Addenda, Table IWC-2500-1 as summarized on page 2-39.
ISI Class 2 Stainless-Steel piping welds will be selected in accordance with Code Case N-408.
The SectionLXI Category (C-F-1), Item Number, Exam Method, Exam Figure, and Acceptance Criteria will be per~ Code Case N-408 as summarized on pages 2-37 and 2-38.
Use of Code-Case-N-408'is an optional upgrade, but it does provide inspection requirements in-fS line with later code editions, allowing an b
N1-002 2-3 Rev. 1 1990
,CN,
()
orderly transition to later interval requi sments.
To fully use Code Case N-408 inspection isometrics are required to be developed identifying less than or equal to NPS 4 high pressure safety injection piping.
This will be accomplished by the third period.
At that time item numbers C5.20 through C5.42 (Cat.
C-F-1) will be complied with, assuming that only a third of the interval requirements remain.
Additionally the inspection plan will be updated at that time.
2.2 PROGRAM
SUMMARY
2.2.1 The Inservice Inspection Program Summary for Components is presented in Sections 2.3, 2.4 and 2.5 in a tabular format.
The applicable NAPS-1 components and associated requirements are listed alphabetically according to Code Category.
Those Categories and Item Numbers listed with "N/A" are for components not found at North Anna Unit 1 and are included for reference only.
The following information is included in the tables:
?
\\~-
A.
Code Cateaorv - 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
[')
VIS - Visual per IWA-2211, 12 and 13 q)
N1-002 2-4 Rev. 1 1990
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 F.
Examination Recuirements'or Test Recuired
/Ficure 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 Recuest Number - References a specific relier. request contained-in Section 2.7; : Relief requests are presented.in two series:
an NDE-Ser.les for componentsEand-nondestructive examination areas; and a' SPT-Series.for. system pressure testing areas.
O i
l O
a N1-002 2-5 Rev. 1 1990 l
l
O O
O i
.t I
2.3 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.
REQU1 RED /
ACCEPTANCE ' RELIEF-NO.
PARTS TO-BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REOUEST:
L Bl.11 Reactor Vessel Circumferential Shell VOL IWB-2500-1 IWB-3510-Welds Bl.12 Reactor: Vessel l Longitudinal Shell VOL IWB-2500-2 IWB-3510' Welds 1
Bl.21
-Reactor. Vessel Circumferential-VOL IWB-2500-3 IWB-3510.
Head Weld L
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
~Bl.40 Reactor Vessel Head-to-Flange Weld VOL &
,IWB-3 510 '.
SUR Bl.51 Reactor Vessel. Beltline Region' Repair-
'VOL IWB-2500-1, IWB-3510 Welds and:-2 l
-)
~
r N1CLS1 2-6 Rev. 1 1990-
~ _..
O-O O
2.3.2 Examination Category B-B, Pressure Retaining Welds in Vessels Other Than Reactor Vessels ALT.
EXAM ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF-NO.
PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA
'FIOUEST-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 B2.21 Pressurizer Circumferential Head N/A N/A N/A Welds B2.22 Pressurizer Meridonial Head. Welds N/A N/A N/A B2.31 Steam Generator Circumferential
'N/A
'N/A N/A Head Welds-B2.32 Steam Generator Merid0nial Head-N/A N/A N/A Welds B2.40 Steam Generator Tubesheet-to-Head VOL IWB-es00-6 IWB-3511-Weld NOTE:
"N/A" -in the EXAM._ METHOD column indicates that no applicable components are included in North Anna Unit 1.
N1CLS1 2-7 Rev. 1'1990
.-w.,,
n.,
O O
O
'2.3.2 Examination Category B-B, Pressure Retaining Welds in Vessels Other Than Reactor Vessels (continued)
ALT.
EXAM ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF NO.
PARTS TO BF EXAMINED METHOD METHOD FIG NO.
CRITERIA REQUEST B2.51 Heat Exchanger Circumferential N/A N/A N/A Head Welds B2.52 Heat Exchanger Meridonial N/A N/A N/A Head Welds B2.60 Heat Exchanger N/A N/A.
N/A Tubesheet-to-Head Welds B2.70 Heat Exchanger Longitudinal, N/A N/A N/A-Welds B2.80 Heat Exchanger N/A N/A N/A Tubesheet-to-Shell. Welds
~
NOTE:
"N/A" in the EXAM. METHOD column indicates that no applicable components'are included.
in North Anna' Unit 1.
N1CLS1 2-8 Rev. 1 1990
. i --
E-
^
O O
O 2.3.3 Examination Category B-D, Full Penetration Welds of Nozzles in Vessels Inspection Program B ALT.
EXAM ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF NO-PARTS 'IV BE EXAMINED MET 580D METHOD FIG NO.
CRITERIA REuuril B3.90 Reactor Vessel Nozzle-to-Vessel VOL IWB 'c500-7 IWB-3512 Welds B3.100 Reactor Vessel Nozzle Inside VOL IWB-250'J-7 IWB-3512 Radius Section B3.110 Pressurizer Nozzle-to-Vessel VOL IWB-2500 IWB-3512 NDE-1 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-B3.140 Steam Generator Nozzle Inside VOL
- VIS, IWB-2500-7 IWB-3512 NDE-2 Radius'Section VT-1 B3.150 Heat Exchanger Nozzle-to-Vessel N/A N/A N/A Welds B3.160 Heat Exchanger Nozzle Inside N/A N/A
,N/A Radius Section
' NOTE:
"N/A" in the EXAM. METHOD column indicates that no applicable ccaponents are included in North Anna Unit 1.
N1CLS1 2-9
'Rev. 1 1990
O O
O 2.3.4 Examination Category B-E, Pressure Retaining Partial Penetration Welds In Vessels ALT.
EXAM ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF NO.
PARTS TO BE EXAMINED METHOD METHOD FIG MO.
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 Drive Nozzles VT-2 SURFACE 34.13 Partial Penetration Instrumentation
Nozz1es B4.20 Pressurizer Heater Penetration
NICLSI 2-10 Rev. I 1990
= -
r O
O O
i 6:.
r 2.3.5 Examination Category B-F, Pressure Retaining Dissimilar Metal Welds l
ALT.
EXAM f
ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF NO--
PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REuvr.5T i
B5.10 Reactor Vessel Nominal Pipe Size VOL &
VOL IWB-2500-8 IWB-3514 i
?4 in. Nozzle-to-Safe SUR k
End Butt Welds-f
.B5.20 Reactor Vessel Nominal Pipe Size.
N/A N/A id/A
.$4 in. Nozzle-to-Safe End Butt Welds-1 I
B5.30 Reactor-Vessel Nozzle-to-Safe N/A N/A N/A-End Socket Welds
(
B5.4O Pressurizer Nominal Pipe Size VOL &
N/A N/A
,,_ 4 in. Nozzle-to-Safe SUR End Butt Welds I
B5.50 Pressurizer Nominal' Pipe Size N/A N/A' N/A
$4 in. Nozzle-to-Safe End Butt Welds l
B5.60
' Pressurizer' Nozzle-to-Safe
'N/A N/A N/A l
End Socket Welds i
i i
I i
NOTE:
"N/A" in the EXAM. METHOD column indicates that no applicable components are included
[
in North Anna. Unit 1.
[
t N1CLS1 2-11 RMr. 1 1990 k
-r
,v,
____m_, _ _ _
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2.3.5 Examination Category B-F, Pressure Retaining Dissimilar Metal Welds (continued) 1.
).,
ALT.
EXAM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF ITEM.
s NO.
PARTS TO'BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REOUEST 1
4
]
B5.70 Steam Generator Nominal Pipe.
VOL &
IWB-2500-8 IWB-3514 i
Size 2 4 in. Nozzle-to-Safe SUt1 4
End Butt Welds "B5.80
. Steam Generator Nominal Pipe N/A N/A N/A i
Size.$ 4 in. Nozzle-to-Safe End. Butt Welds i
B5.90 Steam Generator Nozzle-to-Safe N/A N/A N/A
-l End Socket Welds B5.100 Heat Exchanger Nominal' Pipe N/A N/A N/A j
Size 1 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.
j i
i
+
NOTE:
"N/A".in the EXAM. METHOD column. indicates that no applicable components are included-in North Anna Unit 1.
1 i-N1CLS1 2-12 Rev. 1 1990 f
-_ -. = _
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O i
t 2.3.5 Examination Category B-F, Pressure Retaining Dissimilar Metal Welds (con.t) 4 ALT.
EXAM ITEM 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
'{
i t
B5.130 Piping Nominal Pipe Size VOL &
IWB-2500-8 IWB-3514 l
24 in. Dissimilar Metal SUR Butt Welds B5.140 Piping Nominal Pipe Size N/A N/A N/A i
<4 in. Dissimilar Metal
}
Butt Welds J.-
B5.150 Piping Dissimilar Metal N/A N/A N/A l
Socket Welds 1
]
j NOTE:
"N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 1.
f i
t I
1 1
NICLS1
'2-13 Rev. I 1990 i
1
O 9
d 2.3.6 Examination Category B-G-1, Pressure Retaining Bolting, Greater Than 2 in. In Diana
- ALT.
EXAM ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE REIM F NO.
PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA RECO ?]
1 B6.10 Reactor Vessel Closure Head Nuts SUR t
B6.20 Reactor Vessel Closure Studs, VOL IWB-2500-12 IWB-3515 in Place f
i t
-B6.30 Reactor Vessel Closure Studs SUR &
IWB-2500-12 IWB-3515
~
when removed VOL i
B6.40 Reactor Vessel Threads in Flange VOL IWB-2500-12 IWB-3515 NDE-3
{
B6.50 Reactor Vessel Closure Washers,
- VIS, Surfaces Bushings VT-1 B6.60 Pressurizer Bolts and Studs N/A N/A N/A 4
B6.70 Pressurizer Flange Surface, N/A N/A N/A when connection disassembled i
B6.80 Pressurizer Wuts, Bushings, N/A N/A N/A and Washers i '
)
B6.90 Steam Generator Bolts and Studs
'N/A N/A N/A i
j-
- In course of preparation.
i NOTE:
"N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna. Unit 1.
N1CLS1 2-14 Rev. 1 1990 t
- r l'
- ma a +.
.. _. - ~
i
'N l
i I
i 1
.L 2.3.6 Examination Category B-G-1, Pressure Retaining Bolting, Greater Than 2 in.
In Diameter (continued) i ALT.
EXAM ITEM EXAM.
EXAM
' REQUIRED /
ACCEPTANCE RELIEF
}
i NO.
PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REOUFST l j'
B6.100 Steam Generator Flange Surface, N/A N/A N/A when connection disassembled L
B6.110 Steam Generator Nuts, Bushings, N/A N/A N/A
}
and Washers j
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 i
L 'B6.150 Piping Bolts and Studs.
N/A N/A N/A B6.160 Piping Flange Surface, N/A N/A N/A when connection disassembled B6.170 Piping Nuts,. Bushings, and Washers N/A N/A N/A i
i I
i t
g
' NOTE:
"N/A" in the. EXAM. METHOD column indicates that no applicable components are includ?d i-in North Anna Unit 1.
N1CLS1 2-15 Rev. 1 1990
(
1 f
~
L O
O O
1 e
I i
2.3.6 Examination Category B-G-1, Pressure Retaining Bolting, Greater Than 2 in. In Diameter
[
(continued)
[
4 i
ALT.
EXAM i
ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF NO.
PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REuur.5T B6.180 Pumps Bolts and Studs VOL IWB-2500-12 IWB-3515
[
B6.190 Pumps Flange Surface,
- VIS, Surfaces i
when connection disassembled VT
-i
)
B6.200 Pumps Nuts, Bushings, and Washers
- VIS, Surfaces VT B6.210 Valves Bolts and Studs VOL IWB-2500-12 IWB-3515 f
i
.B6.220 Valves Flange Surface,
- VIS, Surfaces i
when connection disassembled VT-1 l
B6.230 Valves Nuts, Bushings, and Washers
- VIS, Surfaces l
VT-1 I
i l
)
^ n. course of preparation I
NOTE:
"N/A" in the EXAM.. METHOD column indicates that no applicable components are included h
j.
in North Anna Unit 1.
t I
I 5
[
N1CLS1 2-16 Rev. 1 1990 l
O O
O d
4 2.3.7 Examination Category B-G-2, Pressure Retaining Bolting, 2 in.
.d Less In Diameter i
I ALT.
EXAM
- ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF
-NO-PARTS TO BE EXAMINED METHOD HETHOD FIG NO.
CRITERIA REOUEST B7.10 Reactor Vessel Bolts, Studs and Nuts
- VIS, Surface VT-1 1
B7.20 Pressurizer Bolts, Studs, and Nuts
- VIS,
' Surface VT-1 B7.30 Steam Generator Bolts, Studs,
- VIS,
. Surface and Nuts VT-1 B7.40 Heat Exchanger Bolts, Studs and Nuts N/A N/A N/A B7.50 Piping Bolts, Studs, and Nuts
- VIS, Surface j-VT-1
' B7.60 Pumps Bolts, Studs, and Nuts
- VIS,
. Surface VT-1 i
i
- B7.70 Valves Bolts, Studs, and Nuts
- VIS, Surface VT-1 i
i B7.80 CRD Housings Bolts, Studs and Nuts
- VIS, Surface 4
i VT-1
{
- In course of' preparation.
- NOTE:
"N/A" in the EXAM. METHOD column indicates that no applicable components are included I
in North Anna Unit 1.
N1CLS1 2-17 Rev. 1 1990 l
O O
O i.
4 r
4 l
2.3.8 Examination Category B-H, Integral Attachments for Vessels ALT.
EXAM
,. ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF NO-PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REQUrST t
B8.10 Reactor Vessel Integrally Welded N/A N/A N/A j.
Attachments B8.20 Pressurizer Integrally Welded VCL 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 i
~B8.40 Heat Exchanger Integrally Welded N/A N/A N/A-Attachments 3
I L
l h
NOTE:
"N/A" in the EXAM. METHOD column indicates that no applicable components are included i
in North Anna Unit 1.
r i
i i
NICLS1 2-18 Rev. 1 1990
)
s t.
d
O O
O i
4 1
2.3.9 Examination Category B-J, Pressure Retaining Welds in Piping ALT.
EXAM
[
ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF l
NO PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REOUEST l B9.11 Nominal' Pipe Size > 4 in.
VOL &
IWB-2500-8 IWB-3514 NDE-4 Circumferential Welds SUR l
B9.12 Nominal Pipe Size 1 4 in.
VOL & SUR IWB-2500-8 IWB-3514 NDE-4 Longitudinal Welds B9.21 Nominal Pipe Size $ 4 in.
SUR IWB-2500-8 IWB-3514 NDE-4 Circumferential' Welds 4
j t
B9.22 Nominal Pipe Size S 4 in.
SUR IWB-2500-8 IWB-3514 NDE-4 Longitudinal Welds i
B9.31 Nominal Pipe Size 2 4 in.
VOL & SUR IWB-2500-9, IWB-3514 NDE-4 Branch Pipe Connection Welds
-10, and -11 t
B9.32 Nominal Pipe Size 5 4 in.
SUR IWB-2500-9, IWB-3514 NDE-4 Branch Pipe Connection Welds
-10, and -11
.B9.40 Socket Welds
.SUR IWB-2500-8 IWB-3514 NDE-4 1
l s
N1CLS1 2-19 Rev. 1 1990 I
e
--g
-,_____._,mu______.____
L
~
O l
I I
2.3.10 Examination Category B-K-1, Integral Attachments for Piping, Pumps, and Va'ves I
ALT.
EXAM ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF NO.
PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REuvr51 i
t I
B10.10 Piping Integrally Welded VOL or IWB-2500-13, IWB-3516 E
Attachments ~
SUR
-14, and -15 1
B10.20 Pumps Integrally Welded N/A N/A N/A l
Attachments t
-f B10.30 Valves Integrally Welded N/A N/A N/A f
Attachments j
i 1
i I
I L
NOTE:
- "M/A" in the EXAM. METHOD column indicates that no applicable components are included
{
in North Anna Unit 1.
i
)
[
I
~
N1CLS1 2-20 Rev. I 1990 r
~.... -. _.,,, _
,-0 O
O t
2.3.11 Examination Category B-L-1, Pressure Retaining Welds in Pump Casings ALT.
EXAM ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF NO.
PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REOUEST i
B12.10 Pump Casing Welds VOL SUR IWB-2500-16 IWB-3518 NDE-5 4
4 l
N1CLS1 2-21 Rev. 1 1990
t C
O i
5 i
)
i e
t r
i:
4
+
)
2.3.12 Examination Category B-L-2, Pump Casings.
[
3-1 4
t ALT.
EXAM ITEM EXAM.
EXAM REQUIRED /
' ACCEPTANCE RELIEF 3 -
NO.
PART" TOBE EXAMINED METHOD METHOD FIG NO.
CRITERIA REOUEST i'
I t
a.
l B?3.20 Pump Casing'
- VTS, VIS, Internal NDE-5 i
VT-3 VT-1 Surfaces i
j.
t J
- r l
k
,3.
i I
?
i t
i I
I E
f I
i i
i e
i l
{
o In course of preparation
{
i t
i k
l
,1 I
t N1CLS1 2-22 Rev. 1 1990 l
1 i
.l t
s.,.. _.
z
--4
t i
t t
i
~
I 2.3.13 -Examination Category B-M-1, Pressure Retaining Welds in Valve Bodies f
f ALT.
EXAM ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF NO. '
PARTS:TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REOUUT
~B12.30 Valves, Nominal Pipe Size N/A N/A N/A f
5 4~in. Valve Body Welds l
-B12.40 Valves, Nominal Pipe Size N/A N/A N/A
>4 in. Valve Body Welds i
l t
L..
i i,
}
l l
i i
t
?
NOTE:
"N/A" in the EXAM. METHOD' column indicates that no applicable components are included l
in-North. Anna Unit 1.
l 5
E t
l-N1CLS1-2-23 Rev. 1 1990
{
i i
-u e#
t-
, Nw-a mm--.
- -*E-
. - _. - _. - - = -.
O 1
i i
I a-t
?
f i
4 t
j 2.3.14 Examination Category B-M-2, Valve Bodies l
?
t ALT.
EXAM f
^ ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF j
NO, PARTS TO BE EXAMINED METHOD METHOD FIG NO, CRITERIA REOUEST l l
l B12.50 Valve Body, Exceeding 4 in
- VIS, VIS, Internal NDE-6 i
Nominal Pipe Size VT VT-3 Surfaces i
?
,i.
i 3
t f
t L
i i.;'
4
!.
- In course of preparation i
l' i
t h
i 3
i:
j' N1CLS1 2-24 Rev. 1 1990 t-I.
?
1 p.__
c_ _.,.
F s-+1 r-r
.a %
6 o
i fi i
i 2.3.15 Examination Category B-N-1, Interior of Reactor Vessel 4
a
[
ALT.
EXAM
)
!) ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RC 'EF -
l 3: NO.
PAR'S TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REJEM l j:
i l'
l I l B13.10'-
Reactor Vessel
- VIS, Accessible 1
f
' Vessel. Interior.
VT-3 areas i
t i.
t l-i i;
p 1-
.[
i i
i' l
I l
i t
i l
t I
i-l
- l.
- In course of preparation.
l i:
I i
1 l
N1CLS1 2 Rev.'1 1990 l
3 1
i I'
l
,L
_ _ _ _.., -.....,.... -. _. +. -...
,..,, ~
=__.
m m
r b
i, i
T 2.3.16 Examination Category B-N-2, Integrally Welded Core Support Structures and j
Interior Attachments to Reactor Vessels i
4 i
ALT.
EXAM ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF NO.
PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REQUEST 3
k l
B13.20 BWRs Only N/A N/A N/A I
l l
l B13.30 BWRs Only N/A N/A N/A i
i B13.SO Reactor Vessel Interior. Attachments
- VIS, Accessible Within Beltline Region VT-1 welds 1
B13.60
. Reactor V nsel Interior Attachments:
- VIS, Accessible l
..Beyond Beltline Region VT-3 welds i
t l
- In course or. preparation i
NOTE:
"N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 2.
i i
?
i N1CLS1 2-26
'Rev. 1 1990 I
i b
I
f i
7 I
i i
I 2.3.17 Examination Category B-N-3, Removable Core Support Structures
{
ALT.
EXAM I
ITEM.
EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF
.No.
PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REQUEST l t
[
B13.40 BWRs Only N/A N/A N/7.
j i
'B13.70 Reactor Vessel Core Support
- VIS, Accessible
. Structure VT-3 Surfaces j
t f
i 4
F i
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t i
j '
i f
i i
I
- In course of preparation 9
. NOTE:-
"N/A".in the EXAM. METHOD column indicates that no~ applicable components are included l
in North Anna Unit 1.
j l
r NICLS1-2-27 Rev. 1 1990 F
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I i
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2.3.18 Examination Category B-0, Pressure Retaining Welds in Control Rod Housings 2
i i
I i
ALT..
EXAM ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF i
NO.
PARTS W BE EXAMINED' METHOD METHOD FIG NO.
CRITERIA REuusi i
i i
Reactor Vessel Welds in CRD Housing VOL or 1WB-2500-18 IWB-3523 i
B14.10 SUR 4,
I t
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?
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4 4
4
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2 L
1 i
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N1CLS1 2-28 Rev. 1 1990 1
y i
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i 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, HYDROSTATIC SPT-11 Boundary VT-2 PER IWB-5222 B15.20 Pressurizer Pressure Retaining
- VIS, HYDROSTATIC
)
Boundary VT-2 PER IWB-5222 B15.30 Steam Generator Pressure Retaining
B15.31 Steam Generator Pressure Retaining
- VIS, HYDROSTATIC Boundag VT-2 PER IWB-5222 B15.40 Heat Exchanger Pressure Retaining N/A N/A N/A 4
Boundary B15.41 Heat Exchanger Pressure Retaining N/A N/A N/A Boundary o
In Course of Preparation NOTE:
"N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 1.
N1CLS1 2-29 Rev. 1 1990
~
O O
O r
4 i
i i
2.3.19 Examination Category 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 i
B15.50 Piping Pressure Retaining Boundary
B15.51 Piping Pressure Retaining Boundary
- VIS, HYDROSTATIC i
i B15.60 Pumps Pressure Retalning Boundary
- VIS, LEAKAGE i
B15.61 Pumps Pressure Retaining Boundary
- VIS, HYDROSTATIC SPT-1.
{
B15.70 Valves Pressure Retaining Boundary
I j
In Course of Preparation i
i f
NICLS1 2-30 Rev. 1 1990 t
.I
_ _ _. _ _ _. _ _. _. - - _. ~ _.
4 7
I i
' h 3
1
?
l 2.3.20 Examination Category B-Q, Steam Generator Tubing i
s ALT.
EXAM ITEM EXAM.
EXAM REQUIRED /
ACCEPTANCE RELIEF i
NO.
' PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REQUEST j
-B16.10 Steam Generator Tubing in Straight N/A N/A N/A F
Tube Design B16.20 4
Steam Generator Tubing in U-Tube VOL Hot Leg IWB-3521 i
Design and U-Bend j.
i d
i 4
4.
~
i NOTE:
"N/A" in the EXAM. METHOD column indicates that no applicable components are included in North Anna Unit 1.
i
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l:r s
i N1CLS1 2-31 Rev. l'1990
'\\
j.
1
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i 5
l 2.4 ISI Class 2 Components - Program Summary Table j
t 2.4.1 Examination Category C-A, Pressure Retaining Welds in Pressure Vessels I
i ALT.
EXAM f
ITEM EXAM EXAM REQUIRED /
ACCEPTANCE RELIEF
[
l..
NO.
PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REOUEST l 4
i C1.10 Pressure vessel VOL IWC-2500-1 IWC-3000 Circumferential l
Shell Welds I
I C1.20 Pressure Vessel VOL IWC-2500-1 IWC-3000 Circumferential
+
l Head Welds
..C1.30-Pressure Vessel VOL IWC-2500-2 IWC-3000 Tubesheet-to-Shell i
Weld i-i 1
j f
i i
J I
I r
j i-i NICLS2 2-32 Rev. 1 1990 I
i l-1
O O
O l
F 2.4.2 Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels ALT.
EXAM ITEM EXAM EXAM REQUIRED /
ACCEPTANCE RELIEF l
NO.
PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REOUEST !
C2.11 Pressure Vessel SUR IWC-2500-3 IWC-3000 5 1/2 in.
Nominal Thickness Nozzle-to-Shell.
I (or Head) Weld C2.21 Pressure Vessel SUR &
IWC-2500-4(a)
IWC-3000 f
> 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) i Thickness Nozzle Inside Radius Section l
without Reinforcing f
Plate i
C2.31 Pressure Vessel SUR IWC-2500-4(c)
> 1/2 in.
l Nominal Thicknees t
l Reinforcing Plate Welds to Nozzle and Vessel l
N1CES2 2-33 Rev. 1 1990 u _.. _ _ _ _ _ _ _ _ _ _ _ _ _. - -. _,
t i
i-I 2.4.2 Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels (continued) l t
4 a
ALT.
EXAM ITEM EXAM EXAM REQUIRED /
ACCEPTANCE RELIEF NO,.
' PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REOUEST.[
I C2.32 Pressure Vessel VOL IWC-2500-4(c)
IWC-30GO l
> 1/2 in.
l Nominal Thickness Nozzle-to-Shell (or Head) Welds When inside of Vessel.'is Accessible C2.33 Pressure Vessel-
- VIS, N/A No leakage
[
> 1/2 in.
VT-2 i
Nominal Thickness i
4-Nozzle-to-Shell
(
(or Head) When Inside of Vessel Is Inaccessible' 4
t 4
e I
i 2
1 t
N1CLS2 2-34 Rev. I 1990 s
i v
m.
L t
2.4.3 Examination Category C-C, Integral Attachments For Vessels, Piping, Pumps, and Valves l
i ALT.
EXAM ITEM EXAM EXAM REQUIRED /
ACCEPTANCE RELIEF l
NO, PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REQUEST i i
C3'.10 Pressure Vessel SUR IWC-2500-5 IWC-3000 j-Integrally Welded i
j Attachments
't l
C3.20 Piping SUR
' IWC-2500-5 IWC-3OOO
. Integrally Welded i
Attachments i
k C3.30 Pump SUR IWC-2500-5 IWC-3000 Integrally Welded Attachments j
f C3.40 Valve SUR IWC-2500-5 IWC-3000 Integrally-Welded i
Attachments I
i 4
i 4
i -
f 1
l l
N1CLS2 2-35 Rev. 1 1990 i
3>
i j
e
.,,.c
O O
O 2.4.4 Examination Category C-D, Pressure Retaining Bolting Greater Than 2 in. In Diameter ALT.
EXAM
' ITEM EXAM EXAM REQUIRED /
ACCEPTANCE RELIEF NO-PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REOUEST C4.10 Pressure Vessel VOL IWC-2500-6 IWC-3000 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 N1CLS2 2-36 Rev. 1 1990
O O
O 2.4.5 Examination Category C-F-1, Pressure Retaining Welds In Austenitic Stainless Steel or High Alloy Piping (Per Code Case N-408)
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 &'
> NPS 4 And 2 3/8 in. Nominal VOL i
Wall Thickness C5.12 Longitudinal Welds In Piping >
SUR &
IWC-2500-7 IWC-3000 NPS 4-And 1 3/8 in. Nominal Wall VOL Thickness C5.21 Circumferential SUR.&
IWC-2500-7 IWC-3000--
VOL C5.22 Longitudinal SUR &
IWC-2500-7 IWC-3000 VOL C5.30 Socket Welds-SUR IWC-2500-2 IWC-3000 N1CIS2 2-37 Rev. 1 1990
.m h
- 2. 4. 5_
Examination Category C-F-1, Pressure Retaining Welds In Austenitic St&inless Steel or High Alloy Piping (Per Code Case N-408) (Continued)
. ALT.
EXAM ITEM EXAM EXAM REQUIRED /
ACCEPTANCE RELIEF.
NO.
PARTS TO BE' EXAMINED
-METHOD METHOD-FIG NO.
CRITERIA PIOUEST C5.41~
Circumferential Branch Connection SUR IWC-2500-9, IWC-3000 Welds of Branch. Piping 2 NPS 2 to.'-13 C5.42 Longitudinal Branch Connection SUR IWC-2SOO-12 IWC-3000 Welds of-Branch Piping.2 NPS 2 and:-13 1
f N1CLS2 2-38 Rev. 1 1990
..... -... ~ - -
. - - -... - ~. -.. -
O O
O 2.4.6 Examination Category C-F, Pressure Retaining Welds In Piping-(Carbon or Low Alloy Steel)
ALT.-
EXAM ITEM EXAM EXAM
. REQUIRED /
ACCEPTANCE RELIEF' MO.
PMTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REOUEST C5.11 Nominal Wall Thickness 5 1/2 in.
SUR IWC-2500-7 IWC-3000 i
circumferential Piping Welds C5.12
. Nominal. Wall Thickness $.1/2 in.
SUR IWC-2500-7
'IWC-3000 Longitudinal Piping Welds
-C5.21
. Nominal' Wall Thickness 2 1/2 in.
SUR IWC-2500-7 IWC-3000 circumferential Piping Welds C5.22 Nominal Wall Thickness 2 1/2 in/
SUR IWC-2500-7
.IWC-3000 Longitudinal Piping Welds.
C5.31 Nominal. Branch Pipe Size'> 4'in.
SUR IWC-2500-9 IWC-3000 Circumferential Pipe Weld' to 13, inclusive C5.32 Nominal Branch Pipe Size > 4 in.
SUR IWC-2500-12, IWC-3000 NDE-7 I/r.gitudinal Pipe Weld and'-13 (1) NOTE:
Category C-F utilizes item numbers'which are the same as those found in Category.C-F-1.
Category C-F will be limited to welds found on the Main" Steam System ("SHP" line numbers) and Feedwater Systems ("WFPD" line numbers) only.
N1CES2 2-39 Rev. 1 1990
4 i
f 2.4.7: Examination Category C-G, Pressure Retaining Wolds In Pumps And Valves ALT.
EXAM i
ITEM EXAM EXAM REQUIRED /
ACCEPTANCE RELIEF-NO-PARTS TO BE' EXAMINED METHOD' METHOD FIG NO.
CRITERIA REOUEST
..C6.10
. Pump Casing Welds SUR IWC-2500-8 IWC-30CO.
NDE-C NDE-9
)
C6.20 Valve Body Welds' N/A.
N/A2
'N/A l
j 2
+
4
' ' NOTE:
- "N/A"~in the EXAM. METHOD. Column. indicates that no applicable components are included'
)
at North Anna Unit:1.:-
4 I
4 i
l l
i N1CLS2 2-40 Rev. 1 1990'
.=-.
= - -
l 4
~ rs 2.4.8 Examination Category C-H, All Pressure Retaining Components ALT.
ITEM EXAM EXAM TEST ACCEPTANCE ' RELIEF NO.
PARTS TO'BE EXAMINED METHOD METHOD REOUIRED CRITERIA REOUEST
- Ci.10 Pressure Vessel
' Pressure Vessel
- VIS, HYDROSTATIC IWC-3000 SPT,
Pressure Retaining' VT-2 PER IWC-5222 Components
' C7.30 Piping
- VIS, FUNCTIONAL IWC-3000
' Pressure Retaining VT-2 PER IWC-5221.
Components C7.40_
Piping
- VIS, HYDROSTATIC.
IWC-3000 SPT-5,-6 4
Pressure Retaining VT-2 PER IWC-5222 SPT-7,-8' Components SPT-11 C7.50 Pump
- VIS, HYDROSTATIC IWC-3000 Pressure Retaining VT-2 PER IWC-5222 Components C7.70 Valve
- VIS, FUNCTIONAL
'IWC-3000 Pressure Retaining VT-2 PER IWC-5221 Components-N1CLS2 2-41 Rev. 1 1990
=
i-t b
4 2.4.8 Examination Category C-H, All Pressure Retaining Components
.i; 4
ALT.
ITEM EXAM EXAM
~ TEST ACCEPTANCE.
' RELIEF R NO.
-PARTS TO BE EXAMINED-METHOD ~
METHOD REOUIRED CRITERIA REOUEST- !
t
.C7.80 Valve'
- VIS, HYDROSTATIC IWC-3 OO O'.
SPT-5,-6
'. Pressure' Retaining VT-2 PER IWC-5222.
SPT-7,-8 i Components
'[
4 F
4
)
l.
i I
4 l
l.
1 1
0' i
1 1
i N1CLS2 2-42
.Rev.'1 1990-
+
k
. c.,....,.
O O
O i
2.5 ISI Class 3 Components - Program Summary 2.5.1 Examination Category D-A, Systems In Support of Reactor Shutdown Function 1
ALT.
TEST i
ITEM EXAM EXAM AND EXAM ACCEPTANCE RELIEF
'NO.
PARTS TO BE EXAMINED 7ETHOD METHOD REOUIREMENTS CRITERIA
'REOUEST-D1.10 Pressure Retaining Components
- VIS, INSERVICE IWD-3000 VT-2 PER IWD-5221 D1.10 Pressure Retaining Components
- VIS, HYDROSTATIC IWD-3000
- VT-2.
PER IWD-5223 D1.20 Integral. Attachment-.
- VIS, IWD-2500-1 IND-3000 Component Supports and VT-3' Restraints-D1.30 Integral, Attachment-~
- VIS, IWD-2500-1 IWD-3000 t
Mechanical.and Hydraulic VT-3 Snubbers' D1.40 Integral-Attachment-VIS,:
IWD-2500-l' IWD-3000
]
, Spring Type Supports VT-3 l
D1.50 Integral Attachment-
- VIS, IWD-2500-1 IWD-3000' 1
1 Constant Load Type Supports VT-3 D1.'60 Integral Attachment-
- VIS, IWD-2500-1 IWD-3000 Shock Absorbers' VT-3 i
-N1CLS3 2-43 Rev. O 1990
O O
O 2.5.2 Examination Category D-B, Systems In Support of Emergency Core Cooling, Containment.
Heat Removal, Atmosphere Cleanup, and Reactor Residual Heat Removal ALT.
TEST ITEM EXAM EXAM AND EXAM ACCEPTANCE' RELIEF NO.
PARTS TO BE EXAMINED METHOD
-METHOD REOUIREMENTS CRITERIA REOUEST D2.10 Pressure Retaining Components
- VIS, INSERVICE'.
IWD-3000 VT-2 PER IWD-5221 D2.10 Pressure Retaining Components
- VIS, HYDROSTATIC IWD-3000 SPT-9 VT-2 PER.IWD-5222 D2.20 Integral Attachment-
- VIS, IWD-2500-1 IWD-3000 NDE-10 Component Supports.and VT-3 Restraints D2.30 Integral Attachment-
- VIS, IWC-2500-1 IWD-3000 NDE-10 Mechanical and Hydraulic VT-3 Snubbers D2.40 Integral; Attachment-
- VIS,
IWD-2500-1--
IWC-3000 NDE-10 Spring Type Supports.
VT-3 D2.50 Integral Attachment-
~ VIS,.
LWD-2500 IWD-3000 NDE-10 Constant Load-Type Supports VT-3.
D2.60 Integral Attachment-
- VIS, IWD-2506-1-'
.NDE-10 Shock Absorbers
.VT-3 N1CLS3 2-44 Rev.'O-1990"
O O
O 2.5.3 Examination Category D-C, Systems In Support of Residual Heat Removal From Spent Fuel Storage Pool ALT.
TEST ITEM EXAM EXAM AND EXAM ACCEPTANCE RELIEF NO-PARTS TO BE EXAMINED METHOD METHOD REOUIREMENTS CRITERIA PECUER D3.10 Pressure Retaining Components
- VIS, INSERVICE IWD-3000 i.
VT-2 PER IWD-5221 D3.10 Pressure Retaining Components
- VIS, HYDROSTATIC.
IWD-3000 VT-2 PER IWD-5223
~
D3.20 Integral Attachment-
- VIS, IWD-2500-1 IWD-3000 Component Supports VT-3 and: Restraints ~
D3.30 Integral Attachment-
-VIS, IWD-2500-1 IWD-3000 Mechanical-and Hydraulic VT-3 Snubbers D3.40 Integral Attachment-
- VIS, IWD-2500-1
'IWD-3000-Spring Type' Supports
.VT-3 D3.50 Integral Attachment-
- VIS, IWD-2500-1 IWD-3OOO Constant Load Type VT-3 Supports D3.60 Integral Attachment-
- VIS,
.IWD-2500-1 IWD-3000 Shock Absorbers
'VT-3 N1CLS3 2-45 Rev. 0 1990
f O
O 0
- ! 2. 6.-
Augmented Inspection Requirements on..ISI Class 1, 2, or 3 Systems. -- Program Summary Table'
' ITEM NO.
COMPONENT DESCRIPTION
'REFERENCEiS)
EXAM AND FREOUENCY!
1 REACTOR COOLANT PUMPS-- FLYWHEEL TECH. SPECS. 4.4.10.1'.1I UT-IN PLACE'AT' APPROX.
~
REG. GUIDE 1.14,-REV. 1 3 YEAR INTERVALS.
UT/PT (FLYWHEEL REMOVED)7 10 YEAR. INTERVALS.
-2 REACTOR COOLANT IDOP. BYPASS LINES
' UFSAR 3. 6. 2. 3.1 UT/PT EXAM EVERY WELD EVERY-40 MONTHS.
3 PRESSURIZER SPRAY PIPING :IN THE IDWER -
UFSAR 3.6.2.3.2 UT/PT EXAM SELECTED.WELDSI
. CUBICLE; BETWEEN FIDOR ELEVATIONS EVERY-40 : MONTHS.-
I 262 FT. 10~IN."AND 272 FT. 6 IN..'
4.
MAIN STEAM POSTULATED BREAK LOCATIONS-UFSAR 3C.2.7.
UT/PT EXAM OF 1/3'OF; SELECTED WELDS EVERY 40" MONTHS, WITH 100% OF ALL:.
WELDS COMPLETED BY THE END OF THE. INTERVAL.
1 5.
FEEDWATER POSTULATED BREAK-IOCATIONS
-UFSAR 3C.2.7 UT/PT EXAM OF 1/3 OF SELECTED WELDS EVERY AO
.i MONTHS,.WITH 100% OF.'ALL i WELDS. COMPLETED.'BY THE
~
~
'END OF THE INTERVAL.
i l
6.
STEAM GENERATORS - SUPPORTS
. TECH. SPECS.'4.4.10.1.2
'VT-1" EVERY : 40 MONTHS '1/3 '
OF THE MAIN MEMBER WELDS: !
1 JOINING A572' MATERIAL.-!
i i
i l
NIAUGTBL 2-46'
'Rev. 1.1990 4
..._,.3
- ..._,.v.
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.s
..Q,
.~;
~ - -
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O O
O
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[
2.6-Augmented l Inspection' Requirements on ISI ClassL1, 2,
or 3 Systems
. i 1
. t ITEM NO.
COMPONENT DESCRIPTION
' REFERENCE (S)
EXAM AND FREOUENCY.
i t
T ROCKWELL EDWARDS T-58 ANGLE IEIN84-48 RT'A SELECTED GROUP.OF 7.-
UNIVALVES-
- VALVES-EVERY 18: MONTHS g
8.
SERVICE WATER' PIPE WALL THICKNESS STATION PT-SEMI-ANNUAL UT THICKNESS.-
MEASUREMENTS 1-PT-75.14 AND DRY FIIM PAINT.
I THICKNESS.
2 9.
REACTOR' VESSEL INCORE DETECTOR-NRCB'88-09
~-100% EDDY CURRENT' j
THIMBLE. TUBES EXAMINATION ON'ALL INCORE!
DETECTOR THIMBLE TUBES l
IN SERVICE EACH REFUELING!
~
' 10.
REACTOR COOLANT' PIPING LER 82-043
'RT EVERY THIRD REFUELINGE[
THERMAL : SLEEVES DATED-8/26/82'
' OUTAGE.
- i ABBREVIATIONS USED
'NRC'IE'INFORMATION. NOTICE-q IEIN'
=-
LICENSEE. EVENT REPORT-LER-
=
'NRCB-
' ~NRC IE' BULLETIN-
=
4j'
'PT-2 =.l PENETRANT TEST / EXAMINATION l
PT-
= - - PERIODICi TEST J-(REFERENCE)
=
NRC~REGULATORYiGUIDE
' RADIOGRAPHY TEST / EXAMINATION-
'RT
=
UFSAR. = - UPDATED : FINAL' SAFETY ANALYSIS. REPORT L -
1 VT
.-=
VISUAL TEST / EXAMINATION L
+
i i
)
2
[
N1AUGTBL 2-47 Rev.El 1990-i
. ~ ~ - - -
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n--
. _ _ _ _ _ _,.. ~.'
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O 2.7.1 NDE SERIES RELIEF REQUESTS O
O N1-NDERR 2-48 Rev. 1 1990
(_s RELIEF REOUEST NDE-1 I.
IDENTIFICATION OF COMPONENTS Nozzle-to-Vessel Welds Pressurizer:
(1-RC-E-2)
Drawino No.
Weld No.
11715-WMKS-RC-E-2 9
II.
IMPRACTICABLE CODE REQUIREMENTS Section XI of-the ASME Boiler and Pressure Vessel-Code 1983' Edition through Summer 1983' Addenda, Category B-D, Item No.
B3.110, requires a volumetric examination of Pressurizer-nozzle-to-vessel welds.
Relief is requested from the volumetric examination requirements for the pressurizer nozzle-to-vessel-weld.
III.
BASIS FOR RELIEF-()
During the performance of the first interval examination, it was discovered that the pressurizer heater cables and the heater cable penetrations attached to the pressurizer bottom head limit access and prevent meaningful examination of the nozzle-to-vessel weld.
Measurements: conducted-of the examination area indicate that approximately 3 to 8 percent of the weld volume could be ultrasonically examined.
This would be accomplished at an. estimated cost-of 10' man-rem to complete the partial examination.
Other examination methods would:also be restricted:by the same J
obstructions.
It.is felt that-the gain in system integrity is not commensurate with the exposure associatedEwith this partial examination.
IV.
ALTERNATE PROVISIONS 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.
fR.)
N1-NDERR 2-49 Rev. 1 1990
1
(\\
\\s,)
RELIEF REOUEST NDE-2 j
I.
IDENTIFICATION OF COMPONENTS Nozzle Inner? Radius Sections Steam' Generators:
(1-RC-E-1A, 1-RC-E-1B, 1-RC-E-1C)
Pressurizers (1-RC-E-2)
Drawina No.-
Inner Radius Identification No.
11715-WMKS-RC-E-21 9NIR, 10NIR,-11NIR, 12NIR, 13NIR, (Pressurizer) and-14NIR 11715-WMKS-RC-E-1A.2-
.11NIRLand 12NIR (ISI Class 1)-
(Steam Generator A) 09NIR and 10NIR (ISI' Class 2)-
11715-WMKS-RC-E-1B.2 11NIR and 12NIR (ISI Class 1)
(Steam Generator B) 09NIR and 10NIR-(ISI Class 2) 11715-WMKS-RC-E-1C.2 11NIR'and 12NIR (ISI Class 1)--
l (Steam Generator C) 09NIR and 10NIR.(ISI_ Class 2)-
[
t rg II.
IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler.and Pressure Vessel Code, 1983 Edition through Summer 1983 Addenda, Category B-D, Item Nos. B3.120,.B3.140, and Category C-B,1 Item No..C2.22 4
require the nozzle inside-radius sections-of the pressurizer and steam generators to be volumetrically examined.
Relief is requested from the volumetric. examination L
requirements of the nozzle inner radii for the steam l
generator and pressurizer nozzles.
>: ts_/
l l
N1-NDERR 2-50 Rev. 1 1990 1
RELIEF REOUEST NDE-2 CONTINUED III.
BASIS FOR RELIEF Relief from examining the Section XI Code required volume is requested based-upon the following criteria:
1)
Nozzles in_the pressurizer and steam generators'contain inherent geometric constraints and clad inner surfaces which limit the ability to perform meaningful l
volumetric (ultrasonic) examinations:of the inner radii areas.
The pressurizer surge line nozzle I.D.
is physically restricted by the sparger, the-thermal sleeve, and heator bank interferences.
The steam generator main steam nozzles are physically restricted-by the flow limiting-devices.
t 2)
Presently, there is no comprehensive examination technique, nor guidance-for such in the ASME. code, which.would provide a conclusive assessment for.the Section XI-Code: required volumetric examinations of 4
these inner radii, particularly since no preservice
-)
results are available for. review.
3)
Radiography (RT) is not a_ viable examination technique due to the same inherent geometric constraints and accessibility limitations that restrict the effectiveness of the ultrasonic examination method._ In addition, high radiation levels'on primary system nozzles could potentially expose radiographic film, causing'it to " fog" beyond acceptable standards.
IV.
ALTERNATE EXAMINATION 1.
-As an alternate to the Section XI required' volumetric examination of the five Category B-D Pressurizer upper head nozzle inside radius sections-(10NIR, 11NIR, 12NIR, 13NIR, and 14NIR) the areas will be visually examined (VT-1) from the nozzle I.D. using direct or remote techniques when accessible by the end of the inspection interval.
L 2.
As an alternative to the Section XI Category B-D-required volumetric examination of1the Pressurizer lower head nozzle'inside radius-section (09NIR), this area on the o.D. of the nozzle will be visually examined.(VT-2) after the pressurizer has reached operating pressure and temperature.
N1-NDERR 2-51 Rev. 1 1990
-. - ~ - -..
1 RELIEF REOUEST NDE CONTINUED-As.an alternative-to the section XI: reduised volumetric 7
3.
examination of-the steam) Generators six Category _B-D nozzle-inside radius' sections (11NIR and'12NIR on=1-RC--
E-1A,_~1B, and. -lC),. the. areas _ will: be visually- -
examined (VT-1)efrom the nozzle.I.D.'using; direct ori remote techniques per the schedule;shown11n_ Table IWB-2412-1, Inspection-Program"B.J 4.
As an.alternativetto,the'Section XI required volumetric examination of the: Steam Generator Feedwater' nozzle'
- r inner-radius-sections (09NIR on-1-RC-E-1A,--1B,;and -L 1C),- the accessible: portions?of theseisections will bei visuallyc(VT-1) examinedioutage per.the schedule-shown1 inLTable IWB-2412-1,1 Inspection Program B..
5.
As an alternat'ive to the Section XI required volumetric L
examination of the Steam Generators' three_ Category'C-B:
1 Main Steam nozzlelinner. radius sections,f(10NIR-on-
.1-RC-E-1A, -1B, anu!-1C),Lthe area on the.O.D.7of the:
nozzles will Pr visually' examined (VT-2)Lwhen_the Steam
-r Generator has reachedinormal operating pressure _and il O
temperature per=the schedule'shownLin-Table.LIWB-2412-1, Inspection Program B.
NOTE: -Similar rel~ief was; submitted-by-_ letter datedu April 24,J1986ato Mr.LHarold1Denton,1 Serial No.
86-670-for,Surry Power: Station'UnitL1 and approved by4HRC, letter dated June'27,fl986.
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t N1-NDERR.
2-52
- Rev. l'1990' g.@ -Wn eet-fW y37
RELIEF-REQUEST NDE-3 I.
IDENTIFICATION OF COMPONENTS Threads in Flange Reactor Vessel (1-RC-R-1)
Drawino No.
Thread In Flance Mark No.
11715-WMKS-RC-R-1.3 TIF-01 through TIF-58 II.
IMPRACTICABLE CODE REQUIREMENTS Section XI of'the ASME Boiler and Pressure VesselLCode,.
1983 Edition through Summer 1983 Addenda,. Category B-G-1, Item No. B6.40 requires--a volumetric examination of the Reactor Vessel Threads In Flange. -Virginia Electric and Power Company is employing Table IWB-2412-1, Inspection Program B to schedule examinations.
Relief is requested from the examination _ frequency requirementsrspecified in Table.IWB-2412-1 for the reactor vessel threads in_ flange examination.
III.
BASIS FOR RELIEF Relief from the examination frequancy requirements is requested based upon the following criteria:-
1)
. Virginia Electric and Power Company currently schedules the reactor vessel flange threads examination to be performed in concurrence with the automated examination performed on the reactor vessel welds.
This permits the examinations to be conducted with more sophisticated (1.e., digital, -automated) tiltrasonic techniques--in lieu of manual techniques.
2)
In order to accommodate.the-automated ultrasonic calibrations, the calibration block is currently being maintained by cur Reactor Vossel-ISI contractor at their facility.
To examine-the percentage of threads in the flange specified in~the second period by Table IWB-2413-1, it would be necessary to either schedule an automated ultrasonic examination solely to examine these threads or to fabricate a calibration block'to N1-NDERR 2-53 Rev. 1 1990 4
---g
_m
t 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 i
justified or that a manual examination would be as l
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 of interval reactor vessel examination.
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N1-NDERR 2-54 Rev. 1 1990 1
1 l
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RELIEF REOUEST NDE-4 i
I.
IDENTIFICATION OF COMPONENTS ISI Class l' Pressure retaining welds in piping II.
IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through Summer.1983 Addenda requires that notes 1(b) and 2 of Category B-J, table IWB-2500-1 be-used in the selection of welds for examination.
III.
BASIS FOR RELIEF 1
The first interval selection was based upon the 1974-Edition with Summer 1975 Addenda (74/S75) of ASME Section XI.
As a result notes 1(b) and 2 cannot be applied without j
some programmatic additions and modifications.- In-addition, although stress'and utilization calculations exist for North Anna Unit 1, no correlation exists with actual weld-locations.
Total reuse'of the first interval plan is not desirable, since even.though the 74/S75 I'h requirements were met, distribution of welds selected did k-not equitably cover certain line functions and designs.
l IV.
ALTERNATE EXAMINATION ISI Class 1 piping welds will~be selected for examination such that 25% of the. total number of welds are examined during the interval.
The-25% sampling-will be_ comprised.as follows:. one half of the sampling (approximately 12.5%_of the total number of piping welds) will be welds which were examined in the first interval and one-half of:the sampling (approximately 12.5%'of the-total number of piping welds) will be welds which were not. examined in the-first interval.
Welds which-were examined in the first interval will be identified in the second interval plan by the designation "old" in the remarks column... Welds-which were-not examined in the first interval'will be identified in-the second interval plan by_the designation "new" in the remarks' column.. The welds: selected will 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 l
intervals to the extent' allowed by-code editions approved-at that time.-
ss N1-NDERR 2-55 Rev. 1 1990 l
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RELIEF REOUEST NDE-5 V
I.
IDENTIFICATION OF COMPONENTS
(
Pressure retaining welds in pump casings Pump casings Reactor Coolant Pumps:
(1-RC-P-1A,
-1B,
-1C)
Casing Exam Drawino No.
Weld No.
Identifier 4
11715-WMKS-RC-P-1A.1 1
Case 11715-WMKS-RC-P-1B.1 1
Case 11715-WMKS-RC-P-1C.1 1
Case II.
IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and. Pressure Vessel Code, 1983 Edition through Summer 1983 Addenda, Category B-L-1, Item No. B12.10 requires a volumetric examination to be performed on 100% of the pressure retaining welds in at s
t 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 i 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 1
accordance with Category-B-L-1.
Since the installation of these pumps, it has been i
recognized that a volumetric examination of the casing welds is not practical when employing current ultrasonic techniques.
O N1-NDERR 2-56 Rev. 1 1990 o
(m/
RELIEF REOUEST NDE-5 CONTINUED The physical properties of-the stainless steel casting and weld material preclude a meaningful ultrasonic examination.
The capability to examine these pump casing welds in the field did not exist until recently.
In the spring of 1981, an examination was performed on one of the reactor coolant pumps at the R.E. Ginna plant using the miniature linear accelerator-(MINAC),
which-was built under an EPRI sponsored program.
This equipment has been made available to other utilities, and currently constitutes the only viable examination method for the volumetric examination of reactor coolant pump welds.
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 perform the examination, the pump must be completely disassembled, including removal of the diffuser adapter.
This amount of disassembly is far beyond the amount of disassembly performed for normal maintenance.
Insulation must also be removed from the exterior of g-the pump casing.
~#
The examination has been' performed at four different sites, all of which have the 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 the l
welds were found at any of the sites.
A-review of-the-original radiographs of the Point Beach Unit 1 pump was performed prior to the MINAC examination, and all the landmarks found were identified during field examination with no apparent change.
l The successful-performance of this volumetric examination using the MINAC at four different sites i
demonstrates that the method is capable of satisfying ASME Section XI examination requirements.-However,'the performance of the examination has shown there'is a relatively high radiation exposure associated with it.
The total exposure associated with insulation removal, disassembly, examination and reassemblyLof the pump has averaged about 40 man-rem per pump.
i N1-NDERR 2-57 Rev. 1 1990
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 not justified from a cost / benefit perspective. 1The 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 practicable of the external casing weld of one pump will be performed to the extent and frequency of Category B-L-2 in lieu of the required Section XI examinations.
NOTE:
Similar relief-was submitted by letter dated-March 3 0 ~, 1988 (corrected), serial-no. 86-796B, for North Anna Unit 1, interval 1 and approved by'NRC letter j
dated July 17, 1987, serial no.87-443.
i I
OV N1-NDERR 2-58 Rev. 1 1990
- L i
RELIEF REOUEST NDE I.
IDENTIFICATION OF-COMPONENTS:
ISI Class 1 Valve' Bodies Exceeding:4'in.' Nominal Pipe 1 Size--
II.
IMPRACTICABLE CODE REQUIREMENTS Section-XI of the ASMELBoiler and Pressure Vessel Code, 1983: Edition through Summer-1983 Addenda,_CategoryLB-M-2,_
Item No. B12.50,-requires a-visual examination:(VT-3) be j
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.
i Because these examinations must be~ met whether'or notithe valves have to:be disassembled for: maintenance, this requirement is considered impractical'.
III.
BASIS FOR RELIEF i
The requirement to disassemble _ primary system valves for 1
()s internal pressure boundary surfaces has a-very small the sole purpose of performing a-visual examination of the
(_
potential.of: increasing plant safety margins'and a very disproportionate impact'on expenditures of plant: manpower j
and radiation exposure.-
i The_ISI Class 11 systems at North: Anna Unit l' include valves which-vary.in-size, design and manufacturer,-but allfareL a
produced.from either cast stainless'steslLor: cast carbon steel.
None of the' valve-bodiesEare welded.
The performance ~of both carbon and stainless cast valve bodies has been excellentt in-Pressurized-Water 1 Reactor:
(PWR) applications.: Based on this experience and;both-
-industry and regulatory. acceptance ofcthese alloys, continued excellent service'performancenis; anticipated.
I'
-A more practical.approachLisntolexamineLthe-internal pressure' boundary of only those valvesnthat require-disassembly:for maintenance purposes.;:This1 methodology: _
i would provide aumodified sampling program-to'thatfrequired>
by section XI while significantly. reducing; radiation l
exposure to plantipersonnel.
N1-NDERR 2 -Rev. 1 1990 l
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O RELIEF REOUEST NDE-6 l
CONTINUED Virginia Electric and Power Company. feels this approach-would provide a reasonable level of assurance that-the integrity of the primary system valves is-being maintained.
IV.
ALTERNATE EXAMINATION The visual examination of t'ae _ internal. pressure boundary i
surfaces will be performed, to the extent practical,-when a valve is disassembled for maintenance purposes.
l NOTE: 'Similar relief.was submitted-by letter' dated March 13 0, 1988 (corrected), serial no. 86-796B, for North Anna Unit 1, interval 1 and. approved by NRC letter dated July' 17,11987.
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O N1-NDERR 2-60 Rev. 1 1990
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RELIEP REOUEST NDE-7 O
~
I.-
IDENTIFICATION OF COMPONENTS Branch connection welds-- Main. steam relief headers Drawina No.
Weld Nos.
i 11715-WMKS-101A-1 SW-52 to SW-56 11715-WMKS-101A-2 SW-15 to SW-17 and SW-40W to SW-41W 11715-WMKS-101A-3 SW-32W to SW-35W and SW-18W See Detail A and Section B-B'of each drawing.
II.
IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel-Code, 1983 Edition through Summer 1983 Addenda, Category C-F-2, Item No. C5.31 requires circumferential pipe branch
-connection welds be surface examined.
III.
BASIS FOR RELIEF The design of the main steam relief header branch
("'
connection welds calls for the use-of a reinforcement pad.
(
These pads are fillet welded and completely encase-the branch connection' welds.
IV.
ALTERNATE PROVISIONS A surface examination of the reinforcement pad's-fillet welds associated with-one branch connection weld will be performed during the interval.
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N1-NDERR 2 Rev. 1 1990 l
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R RELIEF REOUEST NDE-8 I..
IDENTIFICATION OF COMPONENTS' l
Pump Casing Welds outside Recirculation Spray Pumps-(1-RS-P-2A and 1-RS-P-2 B) L I
Drawina No.-
Weld Nos.'
-11715-UMKS-RS-P-2A SW-1, : SW-2, SW-3 LS-6,:LS-7, LS-8 LS (Partial Access)
LS-10L(Partial Access).
11715-WMKS-RS-P-2B SW-1, SW-2, SW-3 LS - 6, _ ' LS -7,. = LS _ (Partial Access)
LS LS-101(Partial Access) 1 II.
IMPRACTICABLE-CODE REQUIREMENTS.
()
Section XI of the ASMEJBoiler and Pressure Vessel. code,-
1983 Edition-through Summer-1983. Addenda,. Category C-G, Item Number C6.10, requires pump casing-welds to:have a surface examination each inspectionkinterval. -A-surface examination of all of>the pumps casing-welds-is not practicable.
III.
BASIS-FOR RELIEF Each of the two outside recirculation' spray;pumpLcasings, have a. total of five.circumferential; welds.and,five longitudinal welds.1 Three-of'the:circumferential welds (SW-1, SW-2 and.'SW-3),-and three of!theclongitudinal-welds (LS-6, LS-7 and: LS-8) _ are completely encased in-concrete and are not accessible for examination from-the'outside-diamete c E (0. D. ). :Of the-remaining _two-longitudinal welds, one weid-is -partially encased 11n: concretef (LS-9).and one-
. weld is: partially. covered by a vibration'. plate: (LS-10)..
0.Ds examinations can beLperformed on both of these langitudinal 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 shaf t, and the pumpfshaft-(}
support obstructions.
-(
N1-NDERR 2-62 Rev. 1 1990
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O RELIEF REOUEST NDE_8'
]
CONTINUED l
IV.
ALTERNATE PROVISIONS j
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.
4.
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O N1-NDERR 2-63
-Rev. 1 1990-l
RELIEF OUEST NDE-9 E
-I.
IDENTIFICATION OF COMPONENTS-Pump Casing Welds:
Low-Head Safety Injection Pumps ((1-SI-P-1A=and 1-SI-P-1B)_
1 Drawina No.
Weld Noc.
1
-11715-WMKS-SI-P-1AL
- 1,- 2, 3
LS-l',: LS-2,1-LS-3 ELS-4_- (Partial: Access)
-j
- LS-5-'(Partial Access)c 11715-WMKS-SI-P-15 1, L 2, - 3
- LS-1,.LS-2, LS-3:
L LS-4 :(Partial Access):
LS-5-(Partial 1 Access)'
II.
IMPRACTICABLE' CODE REQUIREMENTS 1 Section-XI of the ASME Boiler ~and Pressure Vessel'_ Code,-
1983 Edition through Summer 1983:: Addenda,LCategory C-G,;
Item Number-C6.10,_ requires: pump casing weldssto=have a-surface examination _each inspection-: interval.
-A surface examination of all1 of the: pumps casing ; welds!is not
-practicable.,
III.
BASIS FOR RELIEF:
'Each'of the two low-head safety inject' ion' pump cas'ings have
= a tot'al of ' five circumfe:cential _ welds and five 1ongitudinal 1
Three of the circumferential welds:(1,2 and'3)_and-three of the longitudinal' welds:(LS-1,-LS-2:and LS-3)'are:
j L
completely encased in concrete-and are'not: accessible for~
~
examination.: Of the. remaining two longitudinal: welds,uone weld is ipartially' encased"in concretef (IE-4) 'and one1 weld is partially covered'by;a vibration plat &.(LS-5)".-
Partial outside Diameter (O.D.)7 examinations-can-be performed'on both ofLthese-longitudinal-welds.- The; remaining =two-circumferential_ welds-are completely accessible for-examinations from'the O.D.
Surfaceiexaminations from the-Inside-Diameter (I.D.')- are not a - practicable alternative..
Access 1to the-insideLoflthe pump casings ~is limited by-physical size (24 ' inch outside' diameter),Lthe pump. shaft,
-and_the pump shaft supports.
N1-NDERR 2 'Rev. 1 1990
O RELIEP REQUEST NDE-9 CONTINUED IV.
ALTERNATE PROVISIONS A surface examination of the accessible portions of circumferential and accessible longitudinal welds will be performed to the extent and frequency described in IWC-2500.
A remote visual examination (VT-1) of the I.D. of the pump casing velds will be performed only if the pump is disassembled for maintenance.
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N1-NDERR 2-65 Rev. 1 1990 0
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RELIEF REQUEST NDE-10 1.
IDENTIFICATION OF COMPONENTS ISI Class 3 Components in the Auxiliary Feedwater System II.
IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressute Vessel Code, 1983 Edition through Summer 1983 Addenda, IWD-1220.1-exempts integral attachments of support s and restraints to components that are NPS 4 and smaller except for PWR Auxiliary Feedwater Systems.
i This exemption does not provide a minimum (lower) size exemption for examinations of integral attachments on ISI Class 3 components within the Auxiliary Feedwater System.
III.
BASIS FOR RELIEF To examine all integral attachments in this system regardless of size is impractical considering that ASME Section XI allows the exemption of ISI class 1 components less than one inch NPS, which are more critical.
In O.
addition, IWA-7400 provides an exemption for replacements i
i at NPS 1 creating a situation, where no preaervice inspection would be required in a replaceme.it, although normal inservice inspection is required.-
IV.
ALTERNATE PROVISIONS A 1 NPS exemption will be applied on Auxiliary Feedwater Systems for examinations on integral attachments as required by IWD-2000.
I i
.N1-NDERR 2-66 Rev. 1 1990 i
d
i RELIEP REOUEST NDE-11 1
I.
IDENTIFICATION OF COMPONENTS Ultraconic calibration blocks i
IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through Summer 1983 Addenda, gives specific requirements for the fabrication of ultrasonic calibration blocks.
Specifically, paragraph IWA-223:(a) and IWA-2232 (c) (4 )
III.
BASIS FOR RELIEF North Anna power station was constructed prior to the issuance and adoption of ASME Section XI.
Therefore, ultrasonic calibration blocks were fabricated before the guidnlines of ASME Section XI were developed and approved.
Meeting the requirements of IWA-2232(a) and IWA-2232 (c) (4) of the 1986 Code would require us to manufacture new calibration blocks.
Using the existing calibration blocks allows us to correlate ultrasonic data from the first
()
interval inspections as required by IWA-1400(h).
IV.
ALTERNATE PROVISIONS The existing ultrasonic calibration blocks will be used for the second inspection interval examinations in lieu of current code requirements.
In addition, Code Case N-461, Alternative Rules for Piping Calibration Block Thickness, will be used as necessary.
Note:
It is our understanding that Code Case N-461 is scheduled for approval in Regulatory Guide 1.147 Revision 8.
Any limitations or modifications to this Code Case as indicated in the Regulatory Guide shall be adhered to.
I l
N1-NDERR 2-67 Rev. 1 1990
RELIEF REOUEST NDE-12 I.
IDENTIFICATION OF COMPONENTS ISI Class 1 and Class 2 Welds II.
IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through Summer 1983 Addenda, requires that the entire volume or area of a weld be examined before credit of examination can be given.
III.
BASIS FOR RELIEF Throughout the ISI Class 1 and ISI Class 2 systems situations exist where the entire examination volume or area cannot be examined due to interference by another component or part geometry.
IV.
ALTERNATE PROVISIONS Code Case N-460 alternative examination coverage for Class 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 Regulatory Guide 1.147 Revision 8.
Any limitations or modifications to this code case as indicated in the Regulatory Guide shall be adhered to.
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l N1-NDERR 2-68 Rev. 1 1990 L
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i 4
i RELIEP REQUEST NDE-13 1
I.
IDENTIFICATION OF COMPONENTS ISI Class 1 and 2 Piping, Vessel and Component Welds 4
II.
IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through Summer 1983 Addenda, IWA-2600, weld reference system.
III.
BASIS FOR RELIEF 1
The original construction code used at. North Anna Power Station, ANSI B31.7, 1969 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 1 has recently updated its weld isometrics, providing a detailed identification of location.
It is our O,
intention to use these drawings for tracking and locating i
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.
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N1-NDERR 2-69 Rev. 1 1990
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RELIEF REOUEST NDE-14 4
I.
IDENTIFICATION OF COMPONENTS.
Pressure Retaining Welds in the Reactor Vessel and Vessel Notzle area examined by the automated vessel tool inspection device.
II.
IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through Summer 1983 Addenda, IWA-2600, weld reference system.
III.
BASIS FOR RELIEF The automated tool establishes its reference point using an existing zero reference in the reactor vessel.
This point allows the device.to repeat examination locations without J
the necessity of any other reference systems.
It accomplishes this by the use of an electronic encoder system which provides for sufficient repeatability.
O IV.
ALTERNATE PROVISIONS I
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.
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N1-NDERR 2 Rev. 1 1990 i
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4 2.7.2 SPT SERIES i
RELIEF REQUESTS 1
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1 N1 004d 2-71 Rev. 1 1990 I
4
. - =
r,v--.m-weew,-.
--er
.ce-r.-.
-rer,w,.4 x.,.r,.we....,,+_w,-n.,.-y..-y,-
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+..w.ww...,_.
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RELIEF REQUEST SPT-1 I.
IDENTIFICATION OF COMPONENTS f
System Chemical'and Volume Control-(CH)
Components:
Piping on drawing 11715-CBM-095C-2, Sheet 2 of 2, 3
between the pumps, and the boundaries listed below.
j PUMP LlHE BOUNDARY ISI CLASS 1-RC-P-1A 2"-CH-214-1502-Q1 let-Flange 2
1 1/2"-CH-398-1502-Q1 1st Flange 1-3/4"-CH-372-1502-Q1 lat-Flange-2 1" & 3/4" line 1-CH-342 1
i 1" & 3/4" line 1-CH-341 1
1-RC-P-1B.
2"-CH-215-1502-Q1 ist Flange 2
i 1 1/2"-CH-397-1502-Q1 let Flange 1
3/4"-CH-373-1502-Q1 1st Flange 2
1" & 3/4" line 1-CH-364 1
1" & 3/4" line 1-CH-363 1
i()
1-RC-P-1C 2"-CH-216-1502-Q1 1st Flange 2
1 1/2"-CH-396-1502-Q1 1st Flange 1
3/4"-CH-374-3502-Q1 1st Flanne 2
1" & 3/4" line 1-CH-386
-1 1" & 3/4" line 1-CH-385 1
II.
IMPRACTICAL CODE. REQUIREMENTS
-ISI Class 1 System Hydrostatic Test per IWB-5222 Po u 2500 psig-
-To a 496F Test Pressure = 2550 psig ISI class 2 System Hydrostatic Test per'IWC-5222 Pd a 2735 psig Td = 250F 6
Test Pressure = 3419 psig III.
BASIS FOR RELIEF-Pressurizing the piping-listed above to the pressures required by Section XI will also pressurize the-number one seal:of the reactor coolant-pumps.
This could potentially damage the-
[
number-one seal.
O N1-004d 2-72
-Rev. 1 1990 a_._..,_
l t
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i 3
1 i
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j RELIEF REQUEST SPT-1 i
CONTINUED IV.
ALTERNATE TESTING The normal system leakage test-per IWB-5221 with visual (VT-2) examination after each refueling is an adequate alternative to s
I verify the integrity of these components.
4 NOTE:
Similar relief was submitted by letter dated May 22, 1987, Serial No. 86-796A for North Anna Unit.1, and-approved by NRC letter dated July 17, 1987.
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- V N1-004d-2-73' Rev.'l 1990.
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RELIEF REQUEST SPT-2 I.
IDENTIFICATION OF COMPONENTS System Chemical and Volume control (CH)
Components:
Piping located on drawing 11715-CBM-095C-2, Sheet 1 of 2, between the valves listed below.
VALVES LINE 1-CH-328 and 1-CH-HCV-1311 2H-CH-68-1502-Q1 2-CH-325 and 2-CH-496 3"-CH-1-1502-Q1 ISI Class 1
II.
IMPRACTICAL CODE REQUIREMENTS System Hydrostatic Test per IWD-5222.
Po=2500.psig, To=496 F, Test Pressure is 2550 psig per.IWB-5222.
III.
BASIS FOR RELIEF Check valves 1-CH-328 and 1-CH-325 prevent the components listed above from being pressurized to Section XI requirements without pressurizing the reactor coolant system.
The code required test pressure of 2550 psig will overpressurite the reactor coolant system.
Also, the power operated relief valves (1-RC-PCV-1456 and 1-RC-PCV-1455C) of the reactor coolant system are designed to i
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 while the reactor iscin a shutdown condition in order to seat check valves 1-CH-325 and 1-CH-328, thus creating a pressure. boundary.
The components listed above will then be tested at a pressure between 2300 psig and 2335 psig using a charging pump.
N1-004d 2-74 Rev. 1 1990
j t
i RELIEF REQUEST SPT-2 CONTINUED NOTE:
Similar relief was submitted by letter dated May 22, 1987, Serial No. 86-796A for North Anna Unit 1, and approved by NRC letter dated July 17, 1987.
I J
c p
O i
l N1-004d 2-75 Rev. 1 1990
I l
u RELIEF REQUEST SPT-3 I.
IDENTIFICATION OF COMPONENTS 1
System t
Residual Heat Removal (RH) i Components:
Piping located on drawing 11715-CBM-094A-2, Sheet-1 of 2, between the valves listed below.
I VALVES LINE i RH-MOV-1701 &
14"-RH-1-1502 1-RH-MOV-1700 ISI Class :
1 II.
IMPRACTICAL CODE REQUIREMENTS Class 1 System Hydrostatic Test IWB-5222.
Po=2235 psig, To=650 F, Test. pressure per IWB-5222 is 2280 psig.
l III.
BASIS FOR RELIEF i
1-l l
During the system hydrostatic test,of-the primary system, 1
RH-MOV-1700 and-1-RH-MOV-1701 are closed in order to prevent possible overpressurization of the residual heat. removal r
system.
Thus, the portion of the RHR system identified above l
cannot be pressurized with the primary system and due to system design, it cannot be pressurized without opening one-of the MOVs.
l IV.
ALTERNATE TESTING As an alternative, the components listed above'will be tested L
in accordance with IWC-5222:during the hydrostatic test administered to line 14"-RH-2-602.-
The test pressure will be 584 psig as determined by the setpoint of relief valves 1-RH-RV-1721A and 1-RH-RV-1721B.
This alternative is considered sufficient since the relief valves are set at 467 psig.
As a result,'line 14"-RH-1-1502 should not see a pressure significantly higher than 467 psig.
In addition, 1-RH-MOV-1700 and 1-RH-MOV-1701 will not open if the reactor coolant pressure is 660 psig.
Relief was granted to North Anna Power Station Unit 1 per Safety Evaluation Report dated July 13, 1987 (TAC No. 64718) for the same situation described above.
O
-N1-004d 2-76 Rev. 1 1990
.- _=.. -..
1
)
l RELIEF REQUEST SPT-4 1
I.
IDENTIFICATION OF COMPONENTS System Safety Injection (SI)
Components:
Piping located on drawing 11715-CBM-096B-2, Sheet 4 of 4, between the valves listed below.
VALVES LINES 1-SI-83, 1-SI-190 and 1-SI-195 6"-SI-131-1502 1-SI-86, 1-SI-192 and 1-SI-197 6"-SI-133-1502 1-SI-89, 1-SI-194 and 1-SI-199 6"-SI-132-1502 1-SI-95, 1-SI-211 and 1-SI-204 6"-SI-19-1502 2"-SI-59-1502 1-SI-99, 1-SI-209 and 1-SI-203 6"-SI-21-1502 2"-SI-61-1502 0\\
1-SI-103, 1-SI-213 and 1-SI-205 6"-SI-16-1502 2"-SI-63-1502 t
ISI Class :
1 II.
IMPRACTICAL CODE REQUIREMENTS Class 1 System Hydrostatic Test per IWB-5222.
Po=2235 psig, To=160 F, Test pressure per IWB-5222 is 2432 psig.
III.
BASIS FOR RELIEF The first valve in each' set of valves listed above prevent the components listed above from being pressurized without pressurizing the reactor coolant system.
The power operated relief valves (1-RC-PCV-1456 and 1-RC-PCV-1455C) of the reactor coolant system are designed to limit the pressurizer pressure to a value below.the fixed high-pressure reactor trip setpoint (2385 psig).
The relief valve setpoints are 2335 1
psig which is below the test 1 pressure of 2432 psig.
'It is'not desirable to take the reactor coolant system above the power operated relief valve setpoint.
(~U N1-004d 2-77 Rev. 1 1990 4
l l
RELIEF REQUEST SPT-4 CONTINUED IV.
ALTERNATE TESTING As an alternative, the reactor coolant system will be pressurized to a pressure as close as practical to 2335 psig l
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 beween 2300 psig and 2335.psig using a charging pump.
The reactor coolant system will be borated to a concentration equal to or greater than cold shutdown boron concentration.
NOTE:
Similar relief was submitted by letter dated May 22, 1987, Serial No. 86-796A for North Anna Unit 1, and approved by NRC letter dated July 17, 1987.
O 4
N1-004d 2-78 Rev. 1 1990 r-w-e w,en-
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[
REL!EF REQUEST SPT-5 I.
IDENTIFICATION OF COMPONENTS System Chemical and Volume Control (CH)
Components:
Piping located on drawing 11715-CBM-095C-2, Sheet 1 of 2, between the valves listed below.
VALVES LINES 1-CH-496, 1-CH-HCV-1311, 3/4"-CH-240-1502 and 2-CH-MOV-2289A 2"-CH-68-1502 3"-CH-1-1502 3"-CH-79-1S02 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.
b x_/
III.
BASIS FOR RELIEF Check Valves 1-CH-328, 1-CH-325 and 1-CH-496 prevent the components listed above from being pressurized without pressurizing the reactor coolant system.
The Code required test pressure of 3419 psig will overpressurize the reactor coolant system.
Also, the power operated relief valves (1-RC-PCV-1456 and 1-RC-PCV-1445C) of the reactor coolant system are designed to limit the pressurizer pressure to a value 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 1-CH-328 and 1-CH-496.
The components listed above will then be tested to a pressure i
l
,S between 2300 psig and 2335 psig using a charging pump.
gv; RELIEF REQUEST SPT-5 N1-004d 2-79 Rev. 1 1990
1 4
1 i
I CONTINUED 1
i NOTE:
Similar relief was submitted by letter dated May 22, 1987, Serial No. 86-796A for North Anna Unit 1, and 1
approved by NRC letter dated July 17, 1987.
i i
1 4
1 k
b 1
t t
i s
1 2
i e
I t
i i
i I
I I
l t
N1-004d 2-80 Rev.'l 1990'
4
)
RELIEF REQUEST SPT-6 I.
IDENTIFICATION OF COMPONENTS System Safety Injection Components:
Piping and valves located on drawings 11715-CBM-096A, Sheet 2 of 3, and 11715-CBM-096B, Sheet 4 of 4, listed below.
VALVE CONNECTING Lit {E VALVE 1-SI-MOV-1890C and 10"-SI-18-1502 1-SI-MOV-1890D 10"-SI-238-1502 to 6"-SI-133-1502 1-SI-197 to 6"-SI-132-1502 1-SI-199 to 6"-SI-131-1502 1-SI-195 1-SI-MOV-2890A 10"-SI-15-1502 to 6"-SI-16-1502 1-SI-213 to 6"-SI-130-1502 1-SI-211 to 6"-SI-19-1502 1-SI-MOV-2890B 10"-SI-140-1502
()
to 6"-SI-21-1502-1-SI-209 1-SI-193 2"-SI-55-1502 1-SI-194 1-SI-191 2"-SI-53-1502 1-SI-192 1-SI-188 2"-SI-51-1502 1-SI-190 ISI Class :
2 II.
IMPRACTICAL CODE REQUIREMENTS Class 2 System Hydrostatic Test,per IWC-5222.
Pd = 2485 psig, Design Temperature :bs less than 200 F, Test pressure'is 2733.5 psig.
III.
BASIS FOR RELIEF Check valves 1-SI-83, 1-SI-86, 1-SI-89,--l-SI-95, 1-SI-99 and 1-SI-103 prevent the components listed above from being pressurized without pressurizing the reactor coolant. system.
The Code required test pressure of 2733.5 psig will overpressurize the reactor coolant system.
O U
l N1-004d-2-81 Rev.-1 1990
~
I l
O RELIEF REQUEST SPT-6 CONTINUED The power operated relief valves (1-RC-PCV-1456 and 1-RC-PCV-1455C) of the reactor coolant system are designed to limit the pressurizer pressure to a value below the fixed high-pressure reactor trip setpoint (2385 psig).
The relief valve setpoints are 2335 psig which is below the test pressure of 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 1-SI-83, 1-SI-86, 1-SI-89, 1-SI-95, 1-SI-99 and 1-SI-103.
These components will then be tested to a pressure between 2300 psig and 2335 psig using a test pump.
O Similar relief was submitted by letter dated May 22, NOTE:
1987, Serial No. 86-796A for North Anna Unit 1, and approved by HRC letter dated July 17, 1987.
O N1-004d 2-82 Rev. 1 1990
.-~
r~T-)
RELIEF REQUEST SPT-7 I.
IDENTIFICATION OF COMPONENTS System Safety Injection (SI)
Components:
Piping located on drawings 11715-CBM-0968-2, Sheets 1 of 4, 2 of 4 and 3 of 4, between the sets of valves listed below.
VALVES LINE NUMBERS 1-SI-MOV-1865A, 1-SI-125 12"-SI-123-1502 and 1-SI-123 3/4"-SI-78-1502 1-SI-MOV-1865B, 1-SI-142 12"-SI-124-1502 and 1-SI-140 3/4"-SI-84-1502 1-SI-MOV-1865C, 1-SI-159 12"-SI-125-1502 and 1-SI-157 3/4"-SI-80-1502 ISI Class :
2 II.
IMPRACTICAL CODE REQUIREMENTS
/^T
(')
Class 2 System Hydrostatic Test per IWC-5222.
P =2485 psig, d
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 1-SI-125, 1-SI-142, and 1-SI-159 at the class 1 and 2 system boundaries prevent the pressurization of the above components without pressurizing the primary system.
The required test pressure is 2733.5 psig as stated above, which would overpressurize the primary system.
IV.
ALTERNATE TESTING As an alternative, it is requested that the class 2 components listed above be tested to the conditions of IWB-5222 which is required for the adjacent class 1 piping.
The 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.
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.
l 7_s
(
)
v N1-004d 2-83 Rev. 1 1990
RELIEF REQUEST SPT-8 I.
IDENTIFICATION OF COMPONENTS Systems Main Steam (SHP)
Decay heat Release (SPHV)
Feedwater (WFPD)
Chemical Feed (CFPD & SGD)
Blowdown (WGCB) l Sampling (SS) l Components:
Secondary side of the Steam Generators and attached piping located on drawings 11713-CBM-070B-2, Sheet 1 of 3, 2 of 3, and 3 of 3; 11715-L CBM-074A-2, Sheet 1 of 3; 11715-CBM-089B, Sheet 3 d 1 of 4; 11715-CBM-098A, Sheet 2 of 5; 11715-CBM-h
[o 102A-2, Sheet 2 of 2; and 13075-CBM-102C, Sheet 1 k
of 1 between the components listed in Table SPT-8.
9 ISI class :
2
,I II.
IMPRACTICAL CODE REQU7REMENTS
)
Class 2 Hydrostatic Test per IWC-5222 and IWA-5213(d).
For Feedwater components, P =1100 psig, T >200 F, test pressure d
d I
per IWC-5222 would be 1375 psig.
For the Chemical Feed
{
components, P =1775 psig, T <200 F, test pressure per IWC-5222 d
d would be 1952.5 psig.
The remaining components have P =1085 d
psig, T >200 F, test pressure per IWC-5222 would be 1356 psig.
d 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 abovo because these components cannot be isolated from the steam generators.
IV.
ALTERNATE TESTING The Westinghouse Technical Manual for the Steam Generators requires the secondary side to be pressurized to 1356 psig, held for 30 minutes and then reduced to design pressure (1085 psig) for a sufficient time to permit proper examination of welds, closures and surfaces for leakage or weeping.
. (-))
N1-004d 2-84 Rev. 1 1990
1
- i l
RELIEF REQUEST SPT-8 1
CONTINUED i
I l
The secondary side will be held at 1356 psig for 30 minutes and then reduced to 1085 psig for a minimum.of 3 1/2 hours in j
accordance'with Section XI.
A VT-2 examination will then be-performed on the components described in Table SPT-8.
- l 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.
4 W
O O
N1-004d 2-85 Rev. 1 1990 t
=...............a.,..--.
I Table SPT-8 Components i
FROM TO i
COMPONENT CONNECTED PIPING.
COMPONENT 1-RC-E-1A 32"-SHP-1-601 1-MS-SV-101A to 32"-SHP-22-601 1-MS-SV-102A 1-MS-SV-103A 1-MS-SV-104A 1-MS-SV-105A to 6"-SHP-37-601 &
1"-SHP-84-601 1-MS-PCV-101A to 3"-SHP-64-601 &
1-MS-18 1"-SHP-78-601 1-MS-327 to 1 1/2"-SHPD-6-601 1-MS-22 to 1/2"-SHPD-71-601 1-MS-26 1-RC-E-1A 32"-SHP-1-601 1-MS-35 1-NRV-MS-101A 3"-SHP-60-601 1-MS-344 1
1-RC-E-1A 32"-SHP-1-601f to 32"-SHP-22-601 Oi to 3"-SHP-45-601 1-MS-344 to 3"-SHP-531-601 1-MS-NRV-103A to 1"-SHP-518-601 1-MS-346 1-MS-348 1-RC-E-1A 2"-SS-302-601 SS-576 1-RC-E-1A 32"-SHP-1-601 to 32"-SHP-22-601-to'3"-SDHV-1-601 to 4"-SDEV-4-601 1-MS-20 1-RC-E-1A 16"-WFPD-24-601 1-FW-47 to 3"-WAPD-427-601 1-PW-68 to 3/4"-CFPD-1-601 1-WT-39 1-RC-E-1A 2"-WGCB-4-601 1-BD-1 2"-WGCB-5-601-1-BD-4 1"-WGCB-6-601 1-BD-2 1-RC-E-1A 2"-SGD-4-601 1-WT-459 l
N1-004d 2-86 Rev. 1 1990 l
~
l i.
RELIEF REQUEST SPT-8 Table SPT-8 Components CONTINUED 3
I l
FROM TO COMPONENT CONNECTED PIPING COMPONENT 1-RC-E-18.
32"-SHP-2-601 to 32"-SHP-23-601 1-MS-SV-101B 1-MS-SV-102B 1-MS-SV-103B I
1-MS-SV-104B 1-MS-SV-105B to 6"-SHP-38-601 &
1"-SHP-85-601 1-MS-PCV-101B to 3"-SHP-65-601 1-MS-325 1"-SHP-80-601 1-MS-57 to 1 1/2"-SHPD-8-601 1-MS-60 to 1/2"-SHPD-73-601 1-MS-64 i
1-RC-E-1B 32"-SHP-2-601 1-MS-74 1-MS-NRV-101B 3"-SHP-61-601 1-MS-353 t
1-RC-E-1B 32"-SHP-2-601 to 32"-SHP-23-601.
j.
to 3"-SHP-46-601 1-MS-352 to 3"-SHP-61-601 1-MS-353 to 3"-SHP-533-601 1-MS-NRV-103B to 1"-SHP-520-601 1-MS-356 1-MS-357 1-RC-E-1B
- 2 -SS-2 2 5-601 &
'1"-SS-303-601, 1-SS-218 1-RC-E-1B 32"-SHP-2-601 to 32"-SHP-23-601 to 3"-SDHV-2-601 to 4"-SDHV-4-601 1-MS-20
.1-RC-E-1B 16"-WFPD-23-601 1-FW-79 to 3"-WAPD-28-601 1-FW-100 to 3/4"-CFPD-2-601 1-WT-51 1-RC-E-1B 2"-WGCB-7-601 BD-10 2"-WGCB-8-601 1-BD-13.
2"-WGCB-9-601 1-BD-11 0
1-RC-E-1B 2"-SGD-5-601 1-WT-482 1
w N1-004d 2 Rev. 1 1990
i l
l k
l l
4 I
l RELIEF REQUEST SPT-8 l
Table SPT-8 Components CONTINUED.
1 l
FROM TO COMPONENT CONNECTED PIPING COMPONENT l
1-RC-E-1C 32"-SHP-3-601 1
to 32"-SHP-24-601
'l-MS-SV-101C 1-MS-SV-102C 1-MS-SV-103C 1-MS-SV-104C-4 1-MS-SV-105C i
to 6"-SHP-39-601 &-
1 1"-SHP-86-601 1-MS-PCV-101C to 3"-SHP-66-601 &
1-MS-95 1"-SHP-82-601 1-MS-23
)
to 1 1/2"-SHPD-7-601 1-MS-98 to 1/2"-SHPD-75-601 1-MS-412 I
1-RC
-1C 32"-SHP-3-601 1-MS-112 j
1-MS-NRV-1C' 4
3"-SHP-62-601 1-MS-362 1-RC-E-1C 32"-SHP-3-601 l
to 32"-SHP-24-601 l
to 3"-SHP-47-601 to 3"-SHP-62-601.
1-MS-362 to 3"-SHP-532-601 1-MS-NRV-103C
'to 1"-SHP-519-601 &'
1-MS-365 1-MS-1048 1-RC-E-1C' 2"-SS-227-601 1"-SS-304-601 1-SS-217 1-RC-E-1C
.32"-SHP-3-601 to 32"-SHP-24-601 to 3"-SDHV-3-601 to 4"-SDHV-4-601 1-MS-20 1-RC-E-1C 16"-WFPD-22-601 1-FW-111 to 3"-WAPD-29-601 1-FW-132 to 3/4"-CFPD-3-601 1-WT-67 4
1-RC-E-1C 2"-WGCB-10-601 1-BD-19 2"-WGCB-11-601 1-BD-22 1"-WGCB-12-601 1-BD-20
()
1-RC-E-1C-2"-SGD-5-601 1-WT-505 i
/
l N1-004d 2 Rev. 1 1990 E
. D
I 1
- l RELIEF REQUEST SPT-9 i.
I.
IDENTIFICATION OF COMPONENTS i
i l
System Feedwater (WAPD)
Components:
Piping located on drawing 11715-CBM-074A-2, 4
Sheets 1 of 3 and 3 Of 3, between the valves listed below.
VALVE CONNECTING LIRES VALVE 1-FW-62 3"-WAPD-10-601
- l to 3"-WAPD-9-601-1-FW-66 i
1-FW-64 3"-WAPD-9-601 1-FW s FW-93 3"-WAPD-12-601 to 3"-WAPD-11-601 1-FW-98 1-FW-96 3"-WAPD-11-601 1-FW-102 1-FW-126 3"-WAPD-14-601
'0 to 3"-WAPD-13-601 1-FW-130 1-FW-128 3"-WAPD-13-601 1-FW-134 1-FW-278 4"-WAPD-39-601 to 3"-WAPD-10-601 1-FW-66 ISI Class :
3 II.
IMPRACTICAL CODE REQUIREMENTS Class 3 System Hydrostatic Test per IWD-5223 and IWA-5213(d).
P =1400 psig, Td < 200 F, Test: Pressure is 1540"psig per IWD-d 1
.5223.
III.
BASIS FOR RELIEF Due to check valves 1-FW-132, 1-FW-100, and 1-FW-68, the piping listed above cannot be pressurized without pressurizing the steam generators.
The code required test pressure of 1540 psig would overpressurize the steam generators.-
N1-004d-2-89
- Rev. 1 1990 w
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y g
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l ()
RELIEF REQUEST SPT-9 CONTINUED IV.
ALTERNATE TESTING l
Since the components listed above cannot be pressurized without pressurizing the steam generators, they must be tested per the required manufacturer's hydrostatio 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 3 1/2 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 l,'
and approved by NRC letter dated July 17, 1987.
O i
i l
N1-004d 2-90~
Rev. 1 1990 2
.. ~..
RELIEF REQUEST SPT-10 I.
IDENTIFICATION OF COMPONENTS System Component Cooling (CC), Chemical and Volume Control (CH), Puel Pit Cooling (FC), Safety Injection (SI), Quench Spray (QS), Recirculation i
Spray (RS), Service Water (WS) and Sampling (SS).
Components:
All pipin and components included in the system hydrostat c test boundaries 1
k ISI Class t 1,
2 and 3 II.
IMPRACTICAL CODE REQUIREMENTS Per IWA-5265(b)..."the imposed pressure on any component, including static head, will not exceed 106% of the specified test pressure for the system."
III.
BASIS FOR RELIEF Portions of the above systems not capable of being isolated O
within the system hydrostatic test boundary are located throughout the plant.
Certain non-isolatable portions of the above systems have variations in elevation within the boundaries that would result in imposed pressures in excess of six percent of the specified test pressure.
It is Virginia l
Electric-and Power Company's desire to limit the test pressure imposed on system components to 106% of the specified test pressure (as required by paragraph IWA-5265(b)).
Thus, due to the effects of static head, portions of the piping at higher elevations will be subjected to & test pressure lower than that specified.
There is no practical method for isolating the piping segments to achieve the required test pressure at all elevations.
IV.
ALTERNATE TESTING Hydrostatic testing of systems that cannot be isolated to meet the system test pressure at-the test boundary high point and the 106% system test pressure maximum at the test boundary low point shall be conducted by pressurizing: to the system test pressure at the low point in the test boundary.
NOTE:
Sim41ar relief was submitted by letter dated May 22, 1987, Serial No. 86-796A for North Anna Unit:1, aind approved by NRC letter dated July 17, 1987.
N1-004d 2-91 Rev. 1 1990
l O)
(_
RELIEF REQUEST SPT-11 I.
IDENTIFICtTION OF COMPONENTS System Reactor coolant (RC)
Componentrl Partial Penetration Welds @ Bottom of Reactor l
Vessel Bottom of Reactor Vessel ISI Class :
1 II.
IMPRACTICAL CODE REQUIRtnEhTS l
l Section XI of the ASME Boiler and Pressure Vessel Code, 1986 Edition, Category B-E, Item No. 4.13, requireo reactor vessel partial penetration welds to have a visual (VC 2) examination during the system hydrostatic test of IWB-5221s in addition, l
Category B-P, Item Nos. B15.10, and B15.11 requide a visual l
(VT-2) examination of the bottom of the reactor \\essel during the system leakage test of IWB-5221 and during the system hydrostatic test of IWB-5222, respectively.
,r -
III.
BASIS FOR RELIEF
('
In order to meet the section XI pressure and temperature requirements for the system leakage and system hydrostatic tests of the reactor vessel, reactor containment at North Anna Unit 2 is required to be at a subatmospheric pressure.
Station administrative procedures require that self contained breathing apparatus be worn for containment entries under these conditions.
This requirement signif1F 7tly complicates the visual (VT-2) examination of the bottoi the reactor vessel during testing.
Access to the botto vf 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 air temperatures due to reactor coolant at temperatures above 500 degrees F and limited. air circulation in the vessel cubicle.
In addition, the eriminer is limited to the approximate-30 minute capacity of the breathing apparatus for containment entry, the VT-2 examination, and containment exit.
O
(_.)
N1-004d 2-92 Rev. 1 1990
LI I
-l
("Y)
\\
g,j RELIEF REQUEST SPT-11 CONTINUED IV.
A TERNATE TESTING Technical Specificutions require-that the Reactor Coolant System Leak Rate be limited to 1 gallon-per minute
.]
unidentified leakage..This value is calculated at least'once
'i 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 />.- The' i
incore sump room has an level alarm-in the contro1Eroom requiring operator action.
These actions would identifj any integrity concerns associated with this area.
A'VT-2' examination will be conducted when containment is at.
atmospheric conditions each refueling for evider.:e of boric acid corrosion.
O C
N1-004d 93 Rev. 1 1990
=
a
)
~
VIRGINIA' ELECTRIC AND: POWER.-COMPANY:
NORTH ANNA POWER STATION-UNIT-1 INSERVICE INSPECTION PROGRAM FOR COMPONENT-SUPPORTS SECOND INSPECTION INTERVAL--
llO LN19003-
-. 1 Rev. 1 -1990
O SECTION 3 TABLE OF CONTENTS l
l EECTION PAGE 3.0 INSERVICE INSPECTION PROGRAM FOR COMPONENT SUPPORTS 3-3 3.1 PROGRAM DESCRIPTION 3-3 3.1.1 Snubber Testing 3-3 3.1.2 Supports Exempt From Examination 3-3 3.1.3
. Supports Selected For. Examination-3-3 3.1.4 Sampling Plan 3 3.2 PROGRAM
SUMMARY
3-5 3.2.1 Inservice Inspection Program Summary 3-5 3.3 INSERVICE INSPECTION PROGRAM
SUMMARY
TABLE -
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ISI Class 1, 2,
and 3 Component Supports 3.4 COMPONENT SUPPORT RELIEF REQUESTS-3 O o-U N1-003 3-2 Rev. 1 1990
l qU 3.0 INSERVICE INSPECTION PROGRAM FOR COMPONENT SUPPORTS 3.1 PROGRAM DESCRIPTION The Inservice Inspection Program for ISI Class 1, 2 and 3 component supports meets the requirements of Section l
XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through Summer 1983 Addendum 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 Specificationa.
3.1.2 Component supports exempt from the
- amination requirements of IWF-2000 are those annected to components and items exempted from.xamination under IWB-1220, IWC-1220, and IWD-2000.
In addition, portions of supports that are inaccessible by being encased in concrete, gs) buried underground, or encapsulated by guard s
pipe are also exempt from the examination requirements of IWF-2000.
These exemptions are excerpted from proposed Code Case WGCS 89-1(b).
See Relief Request CS-1 for details.
3.1.3 Component supports to be examined shall be the supports of 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.
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N1-003 3-3 Rev. 1 1990
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.
ISI Class-3 Piping - Supports Examine-10%'of supports per interval.
Notes 1, 2 and 4.
Supports other Than Piping Supports - Examine 100% of supports per interval.
Notes 3 and 4.
NOTES:
(1)
Supports shall,be categorized to identify support types by component support fonction
.(e.g.,
A = supports such as one directional rod hangers; B = supports such as multi-directional restraints; and C = supports-1 that allow thermal movement, such as springs).
7 (2).
The total percentage sample shall be s
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.
This sampling plan is excerpted from proposed Code Case WGCS 89-1(b)=.
N1-003 3-4 Rev. 1 1990 l
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3.2 PROGRAM
SUMMARY
3.2.1 The Inservice Inspection Program Plan Summary for Component Supports is presented in Section H
3.3 in a tabular format..The component supports and. associated requirements are. listed in J
descending order according to Code category and Item Numbers.
TheLfollowing information.is included in'the tables:
A.-
Code Cateaory - The Section'XI Examination Category as defined in Table IWF-2500-1 for Class 1, 2 and 3 component supports.
B.
Item Number - The Section XI Item Number as listed in Table IWF-2500-1.
All Item Numbers are listed-for-each-Code category.
C.
Egrt Examined - The Section XI description of the. area to be examined.
D.
Examination Method - Lists the 1xamination method required by Section XI.-
The abbreviation used-is as follows:
O(_)
VIS - Visual examination per IWA-2213 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.
F.
Examination Recuirements/Ficure Number -
Lists thefapplicable Section XI-figure-for.
determining the volume of the component to i
be examined.
G.
Accentance Criterid - Lists the applicable portion of Section XI for determining the acceptance criteria.
H.
Relief Recuest - References a specific l
relief request contained in Section 3.4..
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U N1-003 3-5 Rev. 1 1990
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O 3.3 ISI Class 1, 2 & 3 Component Suppo--ts 3.3.1 Examination Category F-A, Plate And Shell Type Supports - Program Summary Table ALT.
EXAM ITEM EXAM EXAM REQUIRED /
ACCEPTANCE RELIEF NO-PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITEffEA REQUEST F1.10 Mechanical connections to
- VIS, IWF-1300-1 IWF-3410 CS-1 pressure' retaining components VT-3 and building structure F1.20 Weld' connections to building
- VIS, IWF-1300-1 IWF-3410 CS-1 structure
.VT-3 F1.30 Weld and mechanical connections
- VIS, IWF-1300-1 IWF-3410 CS-1 at. intermediate joints in VT-3 multiconnected integral and nonintegral supports F1.40 Component. displacement settings
- VIS, IWF-1300-1 IWF-3410 CS-1 of guides and stops, misalignment' VT-3 of supports,. assembly of support
' items h.
N1IWF 3-6 Rev. 1 1990
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O 3.3.2 Examination Category F-B, Linear Type Supports l
ALT.
EXAM ITEM EXAM EXAM REQUIRE /
ACCEPTANCE RELIEF NO.
PARTS TO BE EXAMINED METHOD METHOD FIG NO.
CRITERIA REOUEST F2.10 Mechanical connections to
- VIS, IWF-1300-1 IWF-3410 CS-l'-
pressure retaining components VT-3 and building structure F2.20 Weld connections to building.
- VIS, IWF-1300 IWF-3410 CS-1 structure VT-3 F2.30 Weld and mechanical connections
- VIS, IWF-1300-1 IWF-3410 CS-1 i
at intermediate' joints in VT-3 multiconnected.-integral and nonintegral supports F2.40 Component-displacement settings
.VIS, IWF-1300-1 IWF-3410 CS-1 of. guides and stops, misalignment VT-3 of supports, assembly of support items i
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N1IWF 3-7 Rev. 1 1990 1
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O 3.3.3 Examination Category F-C, Component Standard Supports ALT.
EXAM EXAM EXAM REQUIRE /
ACCEPTANCE RELIEF NO.
PARTS TO BE EXAMINED METHOD METHOD __
FIG NO.
CRITERIA FIOUEST F3.10 Mechanical connections to'
- VIS, IWF-1300-1 IWF-3410 CS-1 pressure retaining components VT-3 and building structure F3.20 Weld. connections to
- VIS, IWF-1300-1 IWF-3410 CS-1 building structure VT-3 F3.30 Weld and mechancial connectjons
- VIS, IWF-1300-1 IWF-3410 CS-1 at intermediate joints in VT-3.
multiconnected-. integral.and.
nonintegral supports F3.40
' Component displacement' settings
- VIS, IWF-1300-1 IWF-3410 CS-1
.of guides and stops,' misalignment VT-3 of 'sur ports, assembly of support
-items F3.50 Spring type supports, constant
- VIS, IWF-1300-1 IWF-3410 CS-1,.
load type supports, shock VT-3 CS-2 absorbers, hydraulic and mechanical. type snubbers 4
i N1IWF 3-8 Rev. 1-1990
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O 3.4 COMPONENT SUPPORT i
RELIEF REQUESTG 1
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N1-CSRR 3_9 Rev. 1 1990
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RELIEF REQUEST-NO. CS-1 I.
IDENTIFICATION OF COMPONENTS ISI Clcss-1, 2 and 3 Component-Supports II.
IMPRACTICAL CODE REQUIREMENTS The' nonexistent or unclear portions of Subsection IWF,Section XI 1983-Edition through Summer 1983 Addendum detailed in the BASIS FOR RELIEF section of this' relief request.
III.
BASIS FOR RELIEF Subsection IWF of the 1983 Edition through Summer.1983 Addendum of Section 7I lacks a_ complete concise' set of rules for the inservice. inspection of. component. supports.
The following areas in particular have--been--identified as needing clarification:
SUPPORTS EXEMPT FROM EXAMINATION AND TEST IWF-1230 in.the 1983 Edition through Summer.1983 Addendum of Section_XI-is "in the course of preparation".
The Section XI Working Group on Component Supports.(WGCS) has developed _ proposed Code Case WGCS 89-1(b) which-includes a complete set of exemptions in_Section 1230.
SUPPORTS SELECTED EQR EXAMINATION:
IWF-2510(a) in the 1983 Edition through SummerJ1983 l-Addendum of Section XI states:
" Component supports selected for examination shall'be the supports of those i
components that>are required'to be_ examined under IWB, IWC, IWD and IWF during the-first inspection interval."
These selection "equirements.areLconfusing in that the exemptions-q for these subsections have been_ modified significantly since'the application of ASME Section XI, 1974 Edition with
. Addenda through Summer 1975'for North Anna Unit 2, Interval 1.
WGCS 89-1(b) includes in_section 2510 a clear, detailed a
set of_ guidelines for' examination.
H SAMPLING PROGRAM' i
The-general-philosophy of Section XI has. evolved into a sampling. program approach where a percentage of like components are examined to determine their suitability for continued service.
WGCS-89-1(b) includes in Table 2500-1 a i
.N1-CSRR-3-10 Rev.'l
.1990-
O specific sampling program for supports.
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O N1-CSRR 3-11 Rey, 1 1990
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RELIEF REQUEST NO. CS-1.
CONTIKUED:
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 1983 Edition through Summer:1983-Addendum of-Section XI provide a complete, coherent and sound set of rules for the inservice inspection of-component supports.
IV.
ALTERNATE PROVISIONS In place of IWF-1230, which is under development, the following will be.used:
Component supports-exempt from the examination requirements of IWF-2000 are those connected to components and items exempted from examination under IWB-1220, IWC-1220, and-4 IWD-1200.
In addition, portions of supports that are inaccessible-by being encasedrin concrete, buried underground, or encapsulated by guard pipe are also exempt-from the examination requirements of IWF-2000.
7 A
SUPPORTS EXEMPT FROM EXAMINATION (m /
4 In Jieu or IWP-2510(a), the following will;be used:
Component supports to be examined shall be.the supports of those components that are required.to be examined =under-IWB-2500,-IWC-2500, and'IWD-2500 by volumetric, surface or 4
visual (VT-1 or VT-3) examination: methods..-
Piping supports to be examined shall be the supports of-;.iping not exenpted under IWB-1220, IWC-1220, and IWD-1220.
In conjunction with Table IWF"2500-1, Categories F-A, F-B and F-C the following sampling _ plan will be used:
l ISI Class 1 Piping Supports - Examine 25% ofLsupports 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 L
interval.
Notes 1, 21and 4.
Supports Other Than Piping Supports - ExamineL100% of' supports per_ interval..
Notes 3 and 4.
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N1-CSRR 3-12 Rev. 1 1990-
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RELIEF REQUEST No. CS-1 CONTINUED NOTES:
(1)
Supports shall be categorized to identify support types by component support function (e.g., A = supports such-as one directional rod hangers; 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 r~}
the multiple components are required to be ls_/
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.
(Q_/
l N1-CSRR 3-13 Rev. 1 1990 l
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O RELIEF REQUEST NO. CS-2 I.
IDENTIFICATION OF COMPONENTS ISI Class 1, 2 and 3 Component Supports II.
IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME. Boiler and Pressure Vessel Code, 1983 2dition with Addenda through the Summer 1983, describes visual' examination is IWA-2210 of the code.
Examination VT-3 (IWA-2213) and examination VT-4 (IWA-2214) are utilized for inspection as' described in subsection IWF Table 2500-2 for Category F-C supports.
Relief is requested from the requirement of a VT-4 examination per IWA-2214 due to unnecessary _and impractical duplication.
III.
BASIS'FOR RELIEF The VT-4 examination is only required for. support
'O examinations on Category F-C components (spring hanger, snubber, etc.), where operability and-functional adequacy need to be determined.
It was recognized by the Code that these examinations (VT-3, VT-4) were closely-related, and generally performed by the same individual qualified to each' discipline.
Although not endorsed inE10 CFR 50.55a, the Winter 1984 Addendum of the Code combined the VT-3 and VT-4 examinations to a singular VT-3 examination.
Applying this reduction administratively would-reduce qualification documents, examination records, review requirements, and reporting without eliminating the-intent of.the examination.
IV.
ALTERNATE PROVISIONS It is-proposed that the definition of a.VT-3 examination as written in the Winter 1984 Addendum be substituted for the current VT-3 and VT-4 requirement:
a)
The VT-3 visualiexamination-shall be conducted to determine the general mechanical.and. structural condition of components and their supports, such'as the verification of clearances, settings, physical-displacements, loose or missing parts, debris, corrosion, wear, erosion or the loss--of integrity at bolted or welded connections.
N1-CSRR 3-14 Rev. 1 -1990
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RELIEF. REQUEST NO. CS-2 CONTINUED.
b)
The VT-3 examination shall include. examinations for.
conditions that could affect operability or functional-adequacy of snubbers, and constant load and spring type supports.
c)
For component supports and component _ interiors, the visual examination may be performed remotely with or without-optical aids to verify the structural-integrity-of the_ components.
1 N1-CSRR 3-15 Rev.
1-1990 I
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