ML20058G055
| ML20058G055 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/31/1990 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20058G052 | List: |
| References | |
| PROC-900831, NUDOCS 9011090319 | |
| Download: ML20058G055 (126) | |
Text
{{#Wiki_filter:_ _ . _ . _ . . . . . . . O l VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM FOR THE SECOND INSPECTION INTERVAL VOLUME 1 INSERVICE INSPECTION PROGRAM FOR COMPONENTS AND COMPONENT SUPPORTS
, REVISION O AUGUST 1990 INTERVAL 2 DECEMBER 14, 1990 - DECEMBER 14, 2000 O
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i VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM SECOND INSPECTION INTERVAL
- (~';) DECEMBER 14, 1990 - DECEMBER 14, 2000 s
'~' REVISION O DISTRIBUTION RECORD DISTRIBUTION DATE DISTRIBUTION DATE NO. ENTERED INITIAL _ NO. ENTERED INITIAL 1 21
, 2 22 3 23 c
4 24 i 5 25 6' 26 ~ i, 7 27 8 28 9 29 10 30 (/ 11- 31 , 12 32
'13 33 14 34 -
15 35 16 36 ' 17 37 18 38 je 19 39 1. l- '20 40-Future. distributions to this program plan will be accompanied by two copies of the distribution memo, one of which is to be ' returned per instructions thereon, and the other one is to be. l filed sequentially behind this page giving you a record of the , contents of each distribution. *
-f 11 N2000 Rev. 0 1990 4
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r ~, ! k' . TABLE OF CONTENTS 4 SECTION TITLE PAGE i Assignment 11 Distribution Record lii Table of Contents iv Abstract 1- Inservice Inspection Program - General. '~ 2 Inservice Inspection Program for Components 3 Inservice Inspection Program for Component Supports e- . kJ l 111 X N2000 Rev. 0 1990
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n ABSTRACT VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM SECOND INSPECTION INTERVAL DECEMBER 14, 1990 TO DECEMBER 14, 2000 In accordance with 10CFR50.55a dated January 1, 1990, the North Anna Unit 2 (NAPS-2) Inservice Inspection (ISI) Program was updated to meet the requirements of ASME Section XI, 1986 Edition. This updated program is for the NAPS-2 second ten year inspection interval scheduled to commence December 14, 1990 and be completed December 14, 2000. In cases where the requirements of Section XI have been determined to be impractical, requests for relief have been developed per 10CFR50.55a(g) (5) (iii) . 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
-s . rules to be included in ISI programs.
x- .This document provides an overview and summary of the NAPS-2 ISI Program for Subsections IWA, IWB, IWC, IWD, and IWF. The boundaries of the ISI Program, component classifications, and the employment of exemptions in IWB-1220, IWC-1220, IWD-1220, and IWF-3230 are shown on the ISI classification Boundary Drawings (CBDs) listed on pages 1-11 to 1-12. The codings, symbols and text used on the CBDs are detailed on 12050-CBM-L&S-2, Legends and Symbols Drawing. Section 1 of this document provides the 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-2 is provided as well as relief requests for components. Section 3 of this document provides a program implementation overview for ISI Class 1, 2, and 3 component supports. A summary table of Section XI requirements applicable to NAPS-2 component supports is provided as well as relief requests for component supports. ,D' ,' iv N2000 Rev. 0 1990
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SECTION 1 l TABLE OF CONTENTS . i SECTION BGE 1.0' ' INSERVICE INSPECTION PROGRAM - GENERAL 1-2 l 1.1 G"NERAL INFORMATION 1-2 1.1.1 Preservice Examinations 1-2 ; i1 1.1.2 Initial Inservice Inspection Interval- 1 1.1.3 second Inservice Insp'ction Interval 1-2 ; l'.1.4 Inservice. Inspection Program 1-2. Description ; E 1.2 DRAWING LIST ~ ISI CLASSIFICATION. BOUNDARY 1-10 .; DRAWINGS ,
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1.1 GENERAL INFORMATION-North Anna Power Station Unit 2-(NAPS-2) is located on ' Lake Anna in Louisa County, Virginia. The plant
- employs a Pressurized Water Reactor (PWR) and j associated Nuclear Steam Supply System components '
i provided by Westinghouse Electric Corporation. 1.1.1 Preservice' Examinations Preservice examinations at NAPS-2 were performed
n
-l utilizing the requirements of ASME Section.XI, .,
- 1974 Edition with Addenda through Summer-1975. ,
1.1.2 Initial Inservice Inspection Interval !
" NAPS-2 commercial' operation commenced on O l' December 14', 1980. Accordingly,.the. initial ten l j::
year inspection interval was conducted from: ! i ' 12/14/80 to 12/14/90~; Examinations during'the . i first inspection interval were also performed
..per ASME Section~XI, 1974. Edition with Addenda i i: [. - # , through Sumner 1975.- Certain' system. pressure i pN ,
' testing requirements were completed per ASME-
*.- Section XI,.1977-Edition with Addenda-through :
f . } m ,E _ Summer 1979.= } 1
$ 1.1.3 Second Inservice. Inspection. Interval-l 4 '
'As mandated by the code of Federal Regulations, i
U 4 7 Title 10, Part 50, Article;50.55a (10CFR50.55a)', i p * =the-NAPS-2 Inservice Inspection ~(IST). Program. i kN .has been updated to the 19061 Edition:of ASME p, > Section.XI. This is'the latest edition and- : l; E addenda of Section'XI incorporated into . ! l" #~ 10CFR50.55a as of December 14,-1989. The second inservice inspection' interval.is' scheduled to- :' m ,
1 commence on December 14, 1990 and be completed ;
.'" 'onLDecember 14, 2000.
L l'.1.' 4 ; Inservice-Inspection: Program Description'~
~{
y. ' The ISI: Program contained herein' addresses ~ the . i inservice inspection and testing of ISI clast l' , 'W ' 2 ', and'3' components and the associated component ~
~
supports. . Applicable requirements-in- . 3 Subsections IWA, IWB, IWC,-IWD,,IWF and'the- - 5 w Mandatory Appendices of the 1986 Edition of ASME V,D ' Section XI have been incorporated into our- p
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(Continued) y, .
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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 l the ISI Program. The intent of this document.is to provide specific-information on the scope of l E the NAPS-2 ISI program (i.e., its boundary and. 1; u compliance with Section XI)fand-identify those ;
, Section XI requirements which are deemed ,
impractical.- Repests for relief for these ; impractical requirements have been developed per l 4 10CFR50. 55a (g) (5) (iii) . - s 1.1.4.1 . Exclusion of Subsection: IWE ; ,; ;" Subsection.IWE, Requirements For Class p ,' MC Components of Light-Water Cooled ' Power Plants,1 -is'not. included in this- 1 R program per the Final. Rules in the lD~). l -4[/NJ Federal Register, Volume 53,ipage: 16053,:which;specifically excludes the l p!, , requirements-of Subsection IWE from 10 , CFR'50.55a.. >y ' l'.1.4.2 'ExclusionLof Cubsections IWP and IWV. .; t
~l . Subsections IWP.and IWV, Inservice 'l L 4' Testing of. Pumps:and-Inservice Testing .,
-of Valves in Nuclear Power Plants are
~
not: included in this program. 'The IWP !! program wasEsubmitted-
, ;,. and IWV separately.5 -
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. , 1.1.4.3 Inservice-Inspection Plan o
The=insNrvica. inspection plan required. O s o by IWA-2420, detailing the components ' l m , and t component ' supports selected: for' y examinationLduring the-interval will-be ~ ]
.provided as a separate document. This ~i
(}. , document willibe provided by 12/14/90. -i h\ p L IN2001 1-4 Rev. 0 1990 ; m , i !
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A,_) O- m ' i o 1.1.4.4 Inspection Program Employed [ a- , : The ISI Program for North Anna Unit 2 i will utilize the interval format of )' Inspection Program B, as shown in IWA- i 2432. ) t 1.1.4.5 Wald Reference System i
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a, The weld reference system required by i 1 IWA-2600 is a recent addition to the i rules of ASME Section XI. The 2 implementation. plan for_this I requirement is detailed in relief ; requests NDE-13 and NDE-14,ishown on- ; 4 pages:2-69 and 2-70 respectively. h L
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T 1.1.4.6- Classification of. Components : N f,' L
'A. Classification of Components-Design i !
11: ;i V m , North' Anna' Unit.2 was issued I
. Wo construction permit No. CPPR-78 in-9 , a February 1971. The station" design; -
j' _ incorporates the codes ando a
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standards that were in'effect whenz i the: equipment ~_was' purchased.--The. J codes andtstandards used-for the .
-designiifabrication,:: erection, and
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60 m T V testing ofl safety related.- 4*. m .s Df"
- components are commensurate with l
- E JF ." the<importance of the safety' .{
w ., aw . functions'to be performed.; i
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The group classifications tabulated- '
,' 1 ; in the'"StandardLFormat and Content- i U
l f? ^ , e of; Safety: Analysis Reports;for. . j
,S Nuclear, Power Reactors",iissued;in
. 1 -j
, February ~'71', and in Safety Guide. ';
No. 26, > alished in March 1972, .
'l g/ incorpor.ced,.in most cases, later f :
h;g > editions of codes than those in' , j l effect when'the majority of safety-L ic
- relatodiaquipment was designed'.
! E ' " Some of'the equipment that would -
J' E fall under a~" group" as_ defined in t ' ;. Safety Guide No. 26 was. designed to= 'l; l T different codes or different Eli?
. editions of'the same code. For ,
qQ example, for different components
'qs_)p 1 that would be in the same group, !
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y j$ -one may be designed"tc ASME III- I 1969, one u ASME.III-1971,'and one ! to ASME VIII-1968.
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gg components of_ safety-related systems do not necessarily fall. j f".
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B. Classification of Componen'ts- 1
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_4 The classification of components _ 1 x4 _ , for_ Inservice.InspectionLwas'. ] W, performed by employing the
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( Regulatory Guide.l.26: Revision 1 3,:
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' ANSI N18.2-1973,1 ANSI N18.2a-1975,2 Mid,#, '
~y .. n . : and~NUREG-00800,: Standard Plani 3'.2.2-Revision 11, sin;ReviewL~
d 0 EW . ,L R Q) g, g "v - . conjunction:with the,Sy' stem Quality - 1 4 p: 1 ; ,
. Group: Classification;section,of'.thei 9 North-Anna" Power Station-UFSAR, d h:,;f[:fy J/
qlS SectionL3.2.2.', Quality Groups A,. , f Dp;M".f #, . B~,7and..C,fas: discussed'in? , g
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*3[ 'h Regulatory; Guide,1;26 and'are" . 4 g! nis s , considered;the same-asJISI Classes-jg@ j 1
, , . 1,72,fand[3_ for,tne1 purposes of -
M m N The!ISI[Classif$cationiofLeach: M(C $.Mff# y = u"' (component? included 91n: NAPSL2/ programFistshownJon'theiISI{
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. : Classification? Boundary Drawings. <n i
$ # %'a. V L(CBDs)g1'isted"onlpages 1-11-tos y % %] m. 1-12s.?The Legends and Symbols ISIi .._4
% -Classification' Boundary Drawing' .
PW , $@ g W W' C-(12050-CBM-L&S-2). ndatailsE the111ne.; [4y;
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codings}and' component 0 markings; 1 ' lm s which: provide the ;ISI- 3 %n h%' i classification;;ofLall!' items , k
' included-within?the?ISI1 Program? d i . boundaries. .In; general, the ISI- 3 glj's? ..%'
? >\, , classification ofepipingjis . f N@ o W " accomplished'byJ11ne " codings" or symbols shownon-12050-CBM-L&S-2. 4 ISI classification of components. e
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Inservice Inspection:(Continued)- which graphically cannot be-coded, ! (* such as pressure vessels, pumps,- 'j
, strainers,'and tanks, etc. is'shown. ,
as text-(e.g., ISI Claws 1A,-3E, i etc.) either'inside the component' l '~ graphics:or~ adjacent to the ;j component mark number. a ,f q v Classification changes are ,o
,4 typically-shown-at the seat of'a a j
, valve, with the ISI' Class:shown on F
either= side of the classification 4
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;u l'.1. 4;7 : . Components andJ Component Supports Exempt from. Examination h
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' :The application'o'f the1 exemptions;
! allowed'per IWB-1220, IWC-1220~,7IWD-l c A i.
1220,1andnIWF-1230?isLalso detail'ed by~' B l' 64, O . ~the codings andocorponent;markingsLof ' 3
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?l.1.4.5.2.;LBecauso(the exemptions of 1l 4 - V * ,'
, -IWF-1230-areL"in'the' course;ofE q I',, '
y preparation",Ja settof exemptions:for' u, componentLsupports'developediin<a j) proposed code: case, WGCS.89-1(b)Lis- q Rg" 'M" @ q$ being employed.< Relief' request CS-1. r .
- 4detailsLthe: reasoning for this' program j.1
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, x g; -1.'1.4'8.; .' Requests" For R'elief -Components andi y 4(
M y 1 Component. Supports m , i qr m , m 4
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(WhereftheLrequirements:of ASME SectionJ ; XI havelbeen determined.to be~- . d if 44,j ,* -impractical, requests.for relief have? '
- been' developed;in accordance with' 9 .. , 10CFR50. 55a (g) (5) (iii) . - The' . -
'I
. impractical requirements are'detailedf Jin three:setsjofCrelief requests:l jan- u y'/
h , NDE:serieslfor components and.
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nondestructive-examination areas, an; 5[
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, 1.1.4.8 Requests For Relief-Componentscand ,
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,7 ' Component Supports (Continued) 4
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; testing areas,-and'a-CS series for j "f
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request is formatted.as follows: Each relief j s W- ; ' IDENTIFICATION OF, COMPONENTS s I. i w t . . -
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, II. IMPRACTICAL CODE REQUIREMENTS
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, III. BASIS FOR RELIEF. d b'N #
.IV. ALTERNATIVE: EXAMINATION 1 21' , (OR TESTING) 9 s~ ..,
d h , M :/ . Relief requests;which pertain to.a j gf l' specific ASME Section XIqCategory and; j M, ItemJNumber:arelreferenc'*4,in the 9 % ' >'-6( , Inservice l Inspection Progr.m Summary llf 4
~ Tables in' Sections:2L:and 31of this. ;'
document; . Relief.. requests which are, 4 , programmatic in econtentowill;;be.; 1
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if7 *. /- -discussed.in the'textTof; sections;1,;2, ' i g%Ms or'3,Ebut:not? listed in.-the; Inservice = g + lp ' , M . . Inspection? Program:SummaryETables. ]j V.. . , v . . 1.1.4.9- ASME.Section XIECode-Cases'IncorporatedJ
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- USNRCiRegulatory: Guide.1.147, Revisi,on.:
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J 7,c-the(followingLCodeLCases;are(being- t Q[lN [ $ LincorporatedtintoTthe? NAPS-2.ISI y w<s' h m';< 7~
' Program:. J r -
y4 , . - . W' <t i l; w yy? ,D ' ' Case--N-401a- EddyicurrentiEsamination,- A
'.f, SectioniXI,7 Division 1.' , t[
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Standard" Material, Section ; hiR , , 4 ,
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V LReplacement, Section/XI,1 ' h)yM e . Division 1. g 3 4 ( t'- t i M [ ;l
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1 a- , Class 2 Piping,'~Section. , d XI',. Division 1. }>g'> ]., ,
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XI,-Divisioni1. j, c.:. 5 1,1.4.10 AugmentedTInservicel Inspection Program; d
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for ISI Class'1,c2, andn3: Components.- Jl.' , y
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M ..XI programlare summarizediiniSection' x m j j J
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- 2,;TableL2!6'ELA: listing'ofLspecifici l
f' componentsischeduledStotbe examined-
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@e g>A 4 n : included'as;-part.of4the Inservice
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ka4 m ha '." Inspection Planadiscussed'inSectionc 7% , 1.1.423.. This plan 7will.be;providedL .- g.
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'1. 112050-CBM-L&S-2 : ~1 OF 1 : LEGEND-AND SYMBOLS j l
a . 11715-CBB SERIES .: i
'## : DRAWING NUMBER' . : SHEET : TITLE l.,111715-CBB-006A-2': 2 OF '3 : AIR COOLING AND PURGING SYSTEM i
'j
- 2. <11715-CBB-04OD-2 : 2 OF?3 : AIR CONDITIONING CONDENSER WATER SYSTEM' ;
p+. j Y ' 11715-CBM' SERIES'
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- ESHEET;,: TITLE-
'{ 1 l##:L: DRAWING NUMBER 'I'
! 1.2 =11715-CBM-078B-2 : ! 3. 0F: 4 - : SERVICE WATER SYSTEM 4# i2. ;11715-CBM-078B-2 -:.4 OF 4-: . SERVICE WATER; SYSTEM- ['
13 . 111715-CBM-088A-2.':,3'0F.4h: . FUEL PIT CLNG &. REFUELING PUR. SYSTEM, 9i 6 4 7'11715-CBM-105B-2 : '2 0F 2 :' SECONDARY' PLANT GAS SUPPLYiSYSTEM. 1 5 7 ,
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.'12050-CBB SERIES' "L
2.
,; 4
#h: :: DRAWING ' 'k'
- u. Wt 3 NUMBER : iSHEET : . TITLE- !
- d by , J} E1 ,050-CB'B-104'A-21:i1 12 OF'1 : ' INTERIOR FIRE PROTECTION & HOSE R'sCK : SYS:
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H TITLE y +M 'i##:s: DRAWING (NUMBER!.~: 1 SHEET: :' q [.1.1 L12050 1CBM-070A-2 t i 310F. ' 31: 4 MAINI STEAMISYSTEM; 4 N <4 , 2 . , .112050.CBM-070B-2L:41 TOFF 3 :LMAIN0 STEAM. SYSTEM: .7 (J r ,' % 13.9 1'2050-CBM-070B-2;:62LOFJ3.:EMAINJSTEAM:. SYSTEM - [
/ !OlM4'.i 912050-CBM-070B 2f:E3. k 0F ' 3 J :.; MAINiSTEAML SYSTEMJ '
l 75/ 12050-CBM 1 072A-20:12LOF,3c':I-AUXILIARYJSTEAM?&1 AIR' REMOVAL SYSTEM: Ni J6h h12050-CBM-074A-2E:D1;OF 3E:lFEEDWATERLSYSTEMi O $m$Mi 2
, , ?'17.'12050-CBM-074A 2M:c3:OF.36:-FEEDWATER SYSTEM f',"4 ?8)sy12050-CBM9079A-2f:;if0FL5 :yCOMPONENT COOLING 7 WATER SYSTEM:
~
9L 212050-CBM-079A-2i:02:OFc5L: ..COMPONENTJCOOLING' WATER: SYSTEMS d.N10 C12 050-CBM-079A-2 q:0 3.' OF " 5: L:B COMPONENT: COOLING WATER hSYSTEM; ' j h A 7 $ $11',..%12050 CBM-079A'2:;;f4 - OF:i51 :ECOMPONENT-COOLING. WATER SYSTEMJ [,/'Ojl2%012050-CBM-079A-2[: 5LOF-5u: 9 COMPONENT > COOLINGATER SYSTEM- , 1 j f# L13 3 J12050-CBM-079B-2D: 3310Fi3E: ' COMPONENT COOLING \TER SYSTEM- j s ;14. ; 112050-CDM-082A-2 :.::' 1' OF D31:t COMPRESSED AIR 1SYSTLM ' ~ H j $15'.I;12050-CBM-082B-2n: 1iOF-3f:? COMPRESSED.' AIR. SYSTEM' .
!12050-CBM-082B-2.:02iOFH31:oCOMPRESSEDTAIR'SYSTEMi
' , 9 " 116 '
;17.: ~.? '12050 1CBM 2082C-2':~'2 OF 2!:HCOMrM SSED: AIR' SYSTEM -
J 0 112050-CBM-082F-2 : 2'OF12 : 1 COMPRESSED AIR: SYSTEM! > d 1, L 19.t112050-CBM-089A-2
.18 3 : :-3'OFJ4: -SAMPLING 1 SYSTEM l
? .
- O20..W12050,CBM-089B-21: ' 1 2 0 F .1 :: SAMPLING SYSTEM i
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' NORTH: ANNA' UNIT'2 INTERVAL 2 ISI CLASSIFICATION BOUNDARY DRAWINGS
~ ~
.. .? SORTED BY SERIES-CONTINUED
~~~
OM[, TQ , j m.f 12050-CBM SERIES- I 4 I
- , ## 1: DRAWING NUMBER -: SHEET
- ' TITLE )
bL21./12050-CBM-090A-2 : 1 OF 3': VENT &-DRAIN SYSTEM 22.:12050-CBM-090A-2 : 3 OF 3 : VENT &. DRAIN SYSTEM .i
- 23' 12050-CBM-090B-2 : 1 OF 1.: VENT & DRAIN SYSTEM
'24. 12050-CBM-091A-2 - l' OF 4 : CONT-QUENCH & RECIR SPRAY SUB SYSTEM
, 25. 12050-CBM-091A-2 : 2 OF.4 :. CONT QUENCH.& RECIR SPRAY SUB SYSTEM 1
'26. 12050-CBM-091A-2 : 3 OF 4 : CONT QUENCH & RECIR SPRAY;SUB SYSTEM .
- 27.^12050-CBM-091A-2 : 4'OF 4 : CONT QUENCH & RECIR SPRAY'SUB SYSTEM
- 28.512050-CBM-091B-2': 1 OF.l: CONT-QUENCH'&-RECIR SPRAY-SUB SYSTEM
- 29. 12050-CBM-092A-2.: 1 OFL2 : LEAKAGE MONITOR SYSTEM .
M '
-30'. 12050-CBM-092A-21: 2 OF 2 : CONTAINMENT VACUUM SYSTEM !
!31.712050-CBM-093A-2': 1-OF 3 : REACTOR COOLANT SYSTEM-LOOP'1: [
y # 32.y12050-CBM-093A-2 : 2 OF=3 :.' REACTOR COOLANT SYSTEM-LOOP 2. 1
, J3. 12050-CBM-093A-2': 3JOF 3 :-REACTOR COOLANT SYSTEM-LOOP 3
< ? 3.%H-12050-CBM-093B-2 :-1 OF 3,: REACTOR'COOLANTESYSTEM-
,m 1 35. 12050-CBM-093B-2x: 2 OF 3: : REACTOR COOLANT SYSTEM:
'36'.K-12050-CBM-094A-2i:-11OF 2 :' RESIDUAL HEAT! REMOVAL' SYSTEM' F37 '.w 12 050-CBM-094 A-2 : 2~OF'2:: RESIDUAL HEAT REMOVAL = SYSTEM ,
+
13 8 *.S 12 050-CBM-09 5 A-2 : -1 OF. 2 ' : CHEMICAL AND VOLUME CONTROL: SYSTEM- 4
- , c39.112050-CBM-095A-2:V: :2O F !2' : CHEMICALAND VOLUME: CONTROL 1 SYSTEM'
?j H $4 0.::12050-CBM-095B-2 ' : 1 OF12 . : DCHEMICAL AND: VOLUME CONTROL SYSTEM ' :1 L;4 ' ?441'.i12050-CBM-095B 21: Ji2 L OFD 2 :n CHEMICAL .~AND VOLUME ! CONTROL SYSTEM - l
~
'NJ 4 2. r 12 050-CBM-095C-2 D : 1.0FL2 ': CHEMICAL AND VOLUME CONTROL SYSTEM-h 543.'12050?CBMf095C-2I:J2cOF 2 :c CHEMICAI) AND VOLUMElCONTROL' SYSTEM' . f[f
, ; 4 4 '. 912050-CBM-096A-2: :;-1-OFL3j:0 SAFETY INJECTTON SYSTEM J g' ,
145.f12050-CBM-096A-2J: 2fOFc33:7 SAFETY! INJECTION; SYSTEM ., i 46.'E12050-CBM-096A-2L:.3JOF 3'~-:LSAFETYfINJECTION SYSTEM < ! 4 'T47,712050-CBM-096B 23:!1 OFJ4':1 SAFETY L INJECTION : SYSTEM : g ,48.a12050 CBM-096B-2 L i t 2 - OF( 4" : SAFETY l INJECTION) SYSTEM '
+
y !4 9. D12050'-CBM-096B- 2 :L3 OFL4 : SAFETY / INJECTION / SYSTEM N y'50.J12050-CBM-096B-2f: 34 :OF L4 L:- SAFETY INJECTION-SYSTEML p 151. ?l2050-CBM-098A-21:12SOF 5 :i ' STEAM cGENERATOR' BLOWDOWN! SYSTEM" , f , 452jU12050 CBM-098A-2i: 13 EOF:51:1 STEAMLGENERATORbBLOWDOWNLSYSTEM: ') 1
- 53. f)12 050-CBM-098A -2 7:; 4 ? OF c 5 E.:n STEAMLGENERATOR- BLOWDOWN; SYSTEM:
Y54 112050-CBM-102A-23:!2?OF 2 : CHEMICALDFEED SYSTEMS ' 55 '.' ~ 12 05 0-CBM-102 B-2 L: 1 OFL1: :1 CHEMICAL FEED SYSTEM' l
, , 'li g '
1 13075-CBM SERIES-m t##:j:DRAWINGENUMBER i : -- SHEET :- s TITLE 4 a ' 1
.11h 13075-CBM-093D-2^: 1EOFf2!: REACTOR COOLANT SYSTEM' 4 '
M ,x
- 2. . 13 075 -CBM-09 3D-2 E : 2 ' OF 21:' REACTOR' COOLANT SYSTEMJ
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kV SECTION-2 'l
~;< TABLE OF CONTENTS l y
"l ' . SECTION EbfnE
=2. 0 ; INSERVICE INSPECTION PROGRAM FOR COMPONENTS 2-3 l a
F, J.. 2.1 -PROGRAM DESCRIPTION 2 . iv 2.1.1 Section XI Requirements 2 i W'
, -241.2c Weld; Selection for Class 1 Piping- 2-3 ~;
o 2.1.3. Wald Selection for Class:2 Piping: ' 2 -3 ' 3 J
- p. .!s 2.2'iPROGRAM'
SUMMARY
3 .} j s 2.2'.1 < Inservice Inspection' Program Summary' Description.2-3 1 ?m , . j;<,t 4 2.3 .ISI CLASS 1 COMPONENTS'--PROGRAML
SUMMARY
TABLE.
- 2-5 3, g- --
I r . . .
'[
, 2.4i ISI CLASS 2? COMPONENTS ~~. PROGRAM
SUMMARY
~ TABLE 2-31 i
$NLM, . it O'
' !2.5i:ISI CLASS 3LCOMPONENTS<- PROGRAM
SUMMARY
TABLE < 2-43 ?! wit .. ~
;r AUGMENTED.INSPECTIONREhUIREMENTSONISICLASS1, 2, [X
? f{- ML2 [6 2 La (Q ' '
LOR-'3 SYSTEMS;--PROGRAM-
SUMMARY
TABLE < q
,a IfG ;"
v
-{
- 2 7.L' COMPONENT RELIEFcREQUESTS<
2-48
- c-
.. l2.7' 11 '~NDEiSeries Relief: Requests -
. 2-48j Gi
.2.7:.2 .SPT Serie's Relief.? Requests' 2-71~ H
- 4 3e. n. n ' g, Ch[ U. ., j(' N' -il p' l l 'j M
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+6 N2002: 2-2 Rev. 0 1990 g ;1 y 3 100 .
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A 1 (f
- f. 2.0 INSERVICE INSPECTION PROGRAM FOR COMPONENTS 2.1 PROGRAM DESCRIPTION l
'2.1.1 The Inservice Inspection Program for Class 1, 2 l
' and 3 components meets the= requirements of 1 Section XI of the ASME Boiler and Pressure sw Vessel Code, 1986 Edition-except where these
, requirements have been< determined to be impractical. Detailed = relief requests for these (
impractical requirements-are-included in Section , 2.7. Programmatic modifications to Section XI q requirements are outlined in Sections 2.1.2 and (t 3 241.3.. b 2.1.2 ISILClass 1 piping welds will be selected'for UC examination such that 25% of the total number of (' qE 4 welds-are examined during'the int 9rval. ' r .:n The-25% sampling will be comprised as followsr one half y% y of the~ sampling (12.5% of'the tohal: number-of' piping welds) will be weldo whic'a were examined ]l 1 a g; ,, during the first interval,nand one-half of the R Oif y t sampling (12.5%.of theitotal number <of piping. ; J Ggy, ,
< welds)lwill'-be welds'which wsre not examined L Hbl~ .
- duringthe first intervtl. . ?The welds.: selected i H;~'; ,
will=betevenly distributed ~across theilSILClass.
' 1
)) ( 4 fA 1 piping weld.populicion based:on line. size,. o u ; ci 9 3 line function, and'line' design'to the extent 1 (:g afS practicable. ;This criteria will be. employed in-(gi*- , /g '. -
-lieuyot Notes'1(b)?and:2,of. Category:B-J, Table.
l{ g M :IWB-2 5 00-1.= See Relief Request:NDE-4-for-2 gi . ' ' DN details. ; 4 ,m, ,g , 1 jm ! e
~
2.1.3 ISI(Class.2 Carbon'Steelspipingivelds-willMbi i @Wf N Wfi, selectedLfor: examination perfASME Section.XI, j 19747 Edition;with! Addenda:through!Summaci1975,- ' i K gnNy
- h, 1 ,
- IWC-2411 as- allowed by"10CFR50.55a(b) (2) (iv)-(B)~.
ISI Class' 2~ Stainless: Steel piping welds: will-.be 4? ~ 1 J ' t < selected infaccordanceLwith/ Table.IWC-2500 1,' i d s Category.C-F-1.- ' H"f4 ' y 1 '74 .
'2 ; 2 ' PROGRAM::
SUMMARY
> ' N l
i p $ =2.2.1 .The(Inservice Inspection Program: Summary forithe. [
' Components:is presentedLin'Sectionso2'.3',9244 and; 3' L gj , -2.5'inLa.tabulariformat.-;Theiapplicable: NAPS-2 pt w- components and associated; requirements;are.
p Of Llisted alphabetically!according to Code- ' L, " category. Those Categories:and Item: Numbers H am
- 3' t ." -listed ~with "N/A" are for components.not found- -j L._)? .
- I e
, l lN2002 2-3 Rev. 0.1990 "l' , ,
s> 1.
. . . - .. - - . . . . . . . . ~ . - . _ - ._.- - - - - _
T l llC
~
2 4
. I
, at North Anna Unit 2 and are included for '
reference only. The following information is q included in'the tables. 1 4
- [ -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 1 3 components,.respectively. ,
r B. Item Number - The Section XI Item Number.as. i listed in Tables'IWB-2500-1, IWC-2500-1 and- j. IWD-2500-1.- All' Item Numbers are listed for ; i each Code category with- the exception of '!
, those associated with Program A of Category. i B-D. t f' C.- Part Examined'- The ASME Section XI [
description of the area to be examined. j D.. Examination Method - Lists the: examination i M method or methods required by the provisions i b =of Section XI. The abbreviations'used are
. Dasifollows:1 .
j j
) , VOL - Volumetric per: IWA-2230
-SUR.- Surface per IWA-2220 .
L D.' i"' !j
'VIS - -i VisualL per. IWA-2211, 12 ' and 13 L) .
4 bYA' ' i' '
- E. Alternate' Examination Method ~- Lists thef
~
d examination' method that will:be' performed;as i ,' an? alternative to the;Section XILrequired., ; p 4
-examinationLas stated 11ncaireliefDrequest. >
l h
! F .' . Examination Requirements'or' Test-Reauiredt ,
j pm ' /Fiaura Number - Lists the= applicable J Section XI~ figure for:determiningjthe'volumec
.of'the componentLto be; examined. ,jJ 4"
n < a G. Accentance Criteria--iLists{the applicablei 'l '
, portion _of Section XI?for determining the' 4- < acceptance' criteria.
lH. 4 Relief Recuest Number;- References a. 1 specific'reliefgrequest contained in Section. 2.7. : Relief requests'are presented in'two .W
'j
~
series: 'anLNDE-Series'for components and-nondestructive examination-areas'andLa SPT- ' , {( ~ Series for-system pressure testing areas,
)
i
. nc N2002 2-4 Rev. 0 1990
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' s 2-2.3 . ISI5 Class -1 Components: J - -Program 1 Summary Table 2.3.1 Examination 1 Category B-A,. Pressure Retaining Welds In Reactor Vessel ALT. EXAM i
' ITEM EXAM.- . EXAM. REQUIRED / ACCEPTANCE - RELIEF.
. NO. PARTS TO BE' EXAMINED METHOD METHOD FIG NO. CRITERIA REQUEST Bl.11 .ReactoriVessel~Circumferential Shell- ~
- VOL ' IWB-2500-1 IWB-3510 Welds ~
Bl.12 Reactor VesselSLongitudinal'Shell VOL IWB-2500-2 IWB-3510 Welds .' - Bl.21 Reactor Vessel Circumferential VOL IWB-2500-3 IWB-3510
- Head Weld Bl.22 Reactor. Vessel ~ Meridional Head. Weld ; V O L '- -IWB-2500-3 IWB-3510 Bl.30 -Reactor Vessel'Shell-to-Flange: VOL IWB-2500-4 IWB-3510 NDE-15 Weld t
G1.40 Reactor Vessel ~ Head-to-Flange: Weld .VOL & IWB-2500-5 IWB-3510 , SUR-l l Bl.51 Reactor' Vessel' Beltline:-Region-Repair; "' ' ' '
.VOL- IWB-2500-1, IWB-3510 i Welds and -2 ';
i l- . l N2CLS1 5 Rev. O 1990 3 i
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p - l2.3.2--Examination!CategoryjB-B,-0 Pressure. Retaining Welds inLVessels Other Than Reactor Vessels-cu l _ ALT. EXAM
" ITEMI ._ _ ... _.. .
~ EXAM.; ~~ EXAM REQUIRED / ACCEPTANCE: RELIEF ~
l 2NO. . . . PARTS : TO ' BE '- EXAMint;D ~ METHOD' METHOD ' FIG NO.- ~ CRITERIA REOUEST' l- - - _ 7 i
- 'B2.11- Pressurizer Circumferential "VOL IWB-2500 IWB-3511 Shell-to-Head Welds
- -
l - i - l B2.12: Pressurizer'Longitudina1T 'VOL- IWB-2500-2 IWB-3511 : l Shell-to-Head Welds- .
~~'
'B2.21 Pressurizer Circumferential ' Head ; ~ .N/A N/A N/A Welds h~B2.22 Pressurizer'Meridonial Head Welds- N/A? N/A _N/A i
- B2. 31- Steam-Generator Circumferential ;N/A N/A Head Welds N/A i s
i
'B2.32 4
- l. Steam' Generator _Meridonial' Head 1 N/A N/A- N/A l Welds: - -
i B2 . 40 Steam Generatoic Tubesheet-to-Head - VOL, IWB-2500-6 IWB-3511 l Weld NOTE: "N/A""in the' EXAM." METHOD column indicates.that'no applicable components are-included
.iniNorth: Anna Unit 2.-
j~ N2 CLS1.. 2 Rev. 0 1990
~
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+
(continued)C~~~ ~
-ALT. EXAM JITEM -
4: . EXAM.. EXAML REQUIRED / ACCEPTANCE RELIEF _ NO .- PARTS TO~BE" EXAMINED 1 - METHOD- MCPHOD FIG NO. CRITERIA REOUESI-B2.51 Heat Exchanger.Circumferentialk ;N/A N/A N/A
-Head Welds c:
B2.52. Heat ExchangsrcMeridonisl- -
.N/A- N/A N/A - 4 Head'Weldsi -
B2.60 ' Heat Exchanger- , . N/A N/A N/A .! Tubesheet-to--Head : Welds ' '
'B2.70 Heat Exchanger)Longitudinkl1
~ '
N/A N/A N/A. Welds- i B2.80 Heat Exchanger-' . N/A; N/A N/A Tubesheet-to-Shell Welds l
.t NOTE: "N/A" inLthe; EXAM.' METHOD: column' indicates that'no. applicable components are included in North Anna: Unit 2.:
l
~
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2 . 12.323 ;Examinat' ion Category;B-D,: Full Penetration Welds Lof Nozzles- in ~ Vessels -
-Inspection'ProgramlB .
e 4 EXAM-
~
~
' ALT.
.. ITEM -
EXAM.' EXAM REQUIRED / ACCEPTANCE RELIEF- .
~
NO. ~ PARTS TO BE EXAMINED METHOD ~ METHOD FIG NO. CRITERIA REOUEST B3.90- : Reactor Vessel Nozz1'e-to-Vessel~
-VOL 'IWB-2500-7 IWB-3512 NDE-15 Welds) .
. B3.100 'ReactoriVesselENozzle Inside> VON IWB-2500 IWB-3512' NDE-15 , Radius Section ; B3.110 Pressurizer Nozzle-to-Vessel.' .,VOL IWB-2500-7 IWB-3512 NDE-1 ,
. Welds.
B3.120 Pressurizer NozzleLInside! V O L VIS, IWB-2500-7 IWB-3512 NDE-2
' Radius-Section- -
VT-2 r
. Steam Generator Nozzie-to-VesselX B3.130 . N/A- 'N/A N/A
~ Welds - -]
i B3.140 Steam Generator-Nozzle'Inside ..VOL -VIS, IWB-2500-7 IWB-3512 NDE-2 Radius Section VT-1 ] i B3.150 Heat; Exchanger:Hozzle-to-Vessel
.N/A. N/A: N/A .!
Welds
- B3.160 Heat ~ Exchanger Nozzles Inside- ' N/A . - N/A N/A- -7 Radius Section .
N/A" in-the4 EXAM ( METHOD column ~ indicates:that-no applicable components are included
- NOTE:
in-North-Anna. Unit 22. _ N2CLS1- ~2-8 Rev. O 1990 ,
, f
_.- - _.__ _ :. . _.; _ . . . _ , um . __2.~ . _ . . . . - .
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b . O'I "y,. e _ 2.3.4 Examination CatMgory BAE, Pressure Retaining Partial:. Penetration Welds:In. Vessels. .
+
~
-+ ALT.- EXAM EXAM. EXAM ~ REQUIRED / ACCEPTANCE -RELIEF ITEM ~ -
CRITERIA REOUEST-
~NO. 'PAicTS TO'BE EXAMIurD METHOD METHOD FIG NO.
EXTERNAL _IWB-3522 3B4.11 ' Partial: Penetration VesselcNozzles VIS,
. SURFACE
- VT-2^
w-Partial Penetration Contror Rod VIS,n . EXTERNAL IWB-3522
-B4.12-Drive Nozzlesi .
~
VT-2' SURFACE EXTERNAL IWB-3522 SPT-11 B4.13 Partial Penetration Instrumentation- VIS, SURFACE Nozzles VT-2 EXTERNAL IWB-3522 B4.20 Pressurizer' Heater. Penetration: VIS,- SURFACE
-Welds . -VT-2 e
w N2CLS1- 2-91 A Rev. 0 1990'
.m'- Ws
'~'
e j_ .
. I
1- .
.,. . ;w. - , ;_. 3 - m .
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=
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nq - 2.3.5- ' Examination Category!B-F, Pressure Retaining Dissimilar' Metal Welds ALT. EXAM ITEM _
-EXAM. - EXAM -: REQUIRED / ACCEPTANCE - . RELIEF- ;
; NO- -PARTS TO BE EXAninr.u METHOD- METHOD FIG NO.
~
' CRITERIA REOUEST ;
i B5.10 Reactor. Vessel Nominal' Pipe. Size :VOL &- VOL IWB-2500-8 IWB-3514' NDE , ~2'4 in rNozzie-to-Safe 'SUR-l End Butt'. Welds?
~
B5.20 ' Reactor Vessel Nominal Pipe: Size. N/A N/A N/A s 4:in.~ Nozzle-to-Safe' t
- End Butt Welds i
~ B5.30 . Reactor? Vessel Nozzle-to-Safe. N/A: 'N/A N/A-1 1 End Socket Welds .
B5.40 Pressurizer Nominal PILpe Size' '
~
.VOL & N/A N/A
>.4:in. Nozzle-to-Safe ,SUR End:ButtiWelds q
I
' B5.50 Pressurizer Nominal Pipe -Size - .N/A. N/A N/A i S 4'in. Nozzle-to-Safe' -
EndiButt Welds-4 B5.60 -Pressurizer' Nozzle-to-Safe N/A. N/A N/A , End Socket' Welds; '
~
i
'l , NOTE: "N/A" in the EXAM.' METHOD column indicates that no applicable components are included I in North-Anna Unit 2. '
j N2CLS1: ~ 2-10 Rev. 0.1990
, y e ., .., ,,..,...w, ..,,+..%.~[,. ,,h-2.,.,.% ,..-,y[.,e,
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'2.3.5 LExam nation Category B-Fr Predsure Retaining Dissimilar:-MetalLWelds (continued)-
ALT.: EXAM , iITEM : EXAM.. . EXAM'- REQUIRED / ACCEPTANCE' RELIEF NO- PARTS TO'BE' EXAMINED-- METHOD- METHOD FIG NO. CRITERIA REOUEST
.'B5.70 Steam Generator Nominal Pipe .VOL &: 'IWB-2500-8 IWB-3514
-Size T 4 in'. Nozzle-to-Safe: '
>SURl
-End; Butt: Welds:
B5.80 Steam Generator' Nominal: Pipe N/A .N/A N/A
; Size S 4-in.-Nozzle-to-Safe' ,
End Butt: Welds' ' i
-B5.90 Steam' Generator- Nozzle -to-Safe- .N/A N/A N/A
-EndLSocket' Welds Heat' Exchanger ~ Nominal Pipe.
B5.100- N/A N/A N/A Size _>'4'in.1 Nozzle-to-Safe End .. Butt-' Welds B5.110 Heat'ExchangerLNominal Pipe N/A- N/A N/A '
' Size $'4.in. Nozzle-to-Safe End Butt' Welds-NOTE: "N/A"~in the EXAM.-METHOD column indicates;that no.' applicable components are included in North Anna'Uniti2.-
^
- fi2CLS1 ~
~
2-11 Rev. O'1990 j
-a;., ".' ~ . ;;
.~_ -;-... c.~, :. . , , , , - : J,- .. - . ..;~ . , 4 - n.- . e.., .J--..- , - , , -.-,-, . , . . . . , . , ,, +
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o . 2.3.5. Examination CategoryiB-F,-iPressure: Retaining Dissimilar Metal-Welds-(con.t)
. ALT. EXAM-
. EXAM. EXAM REQUIRED /. ACCEPTANCE -RELIEF
~ ITEM- CRITERIA REQUEST-PARTS TO BE EXAMINED
^
METHOD METHOD' FIG'NO.
- -NO.
B5.120 : Heat-Exchanger Nozzle-to-Safe:
~
N/A N/A N/A-End Socket 1.Nelds .
' Piping NominaliPipe Size VOI!: & -IWB-2500-8 IWB-3514 iB5.130 SUR
> 4 in.-; Dissimilar Metal ~
Butt Welds B5.140 Piping 1 Nominal. Pipe Size- N/A N/A N/A
$4 in.? Dissimilar Metal-
~ Butt Welds B5.150 -Piping' Dissimilar Metal N/A .N/A N/A Socket. Welds-NOTE: "N/A" in the-EXAM. METHOD column-indicates'that'no applicable components are included
~
.in-North Anna Unit:2.
N2CLS1. 2-12 Rev. 0 1990
- a. -
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id:- 7 f .
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2.3.6- Examination-Category.;B-G-lh Pressure Retaining Bolting, Greater Than 2~in. In' Diameter:- 1 ALT. EXAM
~ EXAM. : EXAM' REQUIRED / ACCEPTANCE . RELIEF-LITEM CRITERIA REQUEST:-
PARTS TO'BE'-EXAMINED- METHOD METHOD' FIG NO.
~NO.
B6.10- Reactor Vessel Closure Head-Nuts :SUR Reactor Vessel Closure Studs,- VOL~ INB-2500-12 IWB-3515 B6.20 _ in Place SUR & IWB-2500-12 IWB-3515 B6.30 ReactorLVessel' Closure Studs ~ when removed VOL
'VOL IWB-2500-12 IWB-3515 NDE-3, B6.40 Reactor Vessel Threads in Flange 1 NDE-15
. Reactor Vessel Closure Washers,-~ .VIS,- Surfaces IWB-3517 B6.50 Bushings-. 'VT-1' B6.60 Pressurizer! Bolts-and: Studs' N/A. N/A N/A
~B6.70 Pressurizer-Flange' Surface, _ N/A N/A N/A when connection disassembled B6.80 Pressurizer Nutsj; Bushings, N/A" N/A N/A and Washers B6.90 Steam Generator'! Bolts'and Studs. -
.N/A' N/A. -N/A
-* In course-of preparation.- ' NOTE:. "N/A" in the. EXAM.~. METHOD-column indicates that no applicable components are included
-in North?AnnalUnitL2.
N2CLSI 2-13l Rev. 0 1990 w-b
3-
.. x; g 'yItq.*
^ '
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2.3.6 TExamination
Category.;B-G-1,? Pressure Retaining Bolting, Greater Tht.n .2 'in. -
~
~
i-In .. Diameter E(continued) - _ 1
.-.s JALT. EXAM
~ ITEM EXAM.- EXAM' . REQUIRED / RELIEF No. -PARTS:TO BE EXAMINED METHOD METHOD FIG NO. . ACCEPTANCE:
CRITERIA ' REO '
- B6.100 ~ Steam l Generator Flange-Surface,
- N/A '
- N/A N/A' E
when' connection disassembled
- B6.110 ~ Steam Generator [ Nuts,.' Bushings,1 'N/A N,'A N/A.
and Washers' ,
- B6.120 -Heat Exchanger. Bolts and'Studsi N/A' - N/A N/A
~
j B6.130 Heat Exchanger Flange Surface, N/A N/A N/A: b6.140 Heat Exchanger-Nuts,-' Bushings, N/A .. N/A :N/A ' B6.150 Piping Boltsrand Studs N/A . N/A N/A < l B6.160 Piping Flange Surface, .. N/A. N/A N/A i when connection' disassembled ' B6.170 PipingiNuts, Bushings,;.and Washers- N/A- - N/A N/A -.
. i "N/A"'i~n the. EXAM.tMETHOD column indicates that no applicable components are included NOTE: ; ' i
~in North' Anna Unit 2.: i I
'N2CLS1 .
'2-14 Rev. O 1990 ;
* ,p
- T W .__ _- ' -, <~vA+ Am-
-____=_________:_=____.___-- -
- -:_=--__-_-__u_-___-_-_--~m
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2.3. 6 ' Examination Category : B-G--l', c Pressure Retaining Bolting, l Greater Than 2 in.
' ' ~
. In Diameter ~
-(continued)
~~
~
-ALT. EXAM-ITEM- . . _
jEXAM. -EXAM REQUIRED / . ACCEPTANCE . RELIEF :-
~ NO- ' PARTS'TO BE EXAMINED- -
METHOD METHOD' FIG NO. CRITERIA REODEST PumpsLBolts and Studs
~
- B6.180 VOL IWB-2500-12 IWB-3515-
-- B6.190' Pumps Plange' Surface,: . . .
.VIS, Surfaces 'IWB-3517-when. connection disassembled ~ VT
- B6.200 Pumpr, Nuts,' Bushings,'and Washers- :VIS,- Surfaces IWB-3517- ,
VT_ B6.210 Valves Bolts and! Studs -VOL IWB-2500-12 IWB-3515 i
' Valves! Flange: Surface,.
~
B6.220 VIS, Surfaces IWB-3517 when connection' disassembled: VT--1 j B6.230 Valves. Nuts'~ , Bushings,1and! Washers VIS, Surfaces IWB-3517 VT-1: 4 NOTE: "N/A" in;the EXAM. METHO'D column indicates that no applicable components are included I , in NorthJAnna Unit 2. t N2CLS1- 12-15.. Rev. O 1990 I
'mg-A br-~>< ., Aw.' +.
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- W~ - - + -9 -
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2.3.7 Examination Category B-G-2, _ Pressure Retaining Bolting, 2.in. and Less.In-Diameter. n ALT. EXAM + ITEM' EXAM.. 1 EXAM- ' REQUIRED / ACCEPTANCE 1 RELIEF.
.NO. PARTS TO BE' EXAMINED' METHOD METHOD FIG NO. CRITERIA REOUEST.
n LB7.10 Reactor ^ Vessel: Bolts,; Studs and. Nuts ~ -
-VIS, Surface IWB-3517.
VT--1 B7.20 Pressurizer Bolts,LStuds,fand Nuts l VIS, Surface IWB-3517 VT-1 B7.30 Steam Generator [ Bolts,) Studs, -VIS, Surface IWB-35:l?
-and Nuts -
VT-1 B7.40 ' Heat' Exchanger Bolts,. Studs.and: Nuts- N/AJ N/A N/A. N/A o z. B7.50 Piping Bolts, Studs, and" Nuts. -VIS, Surface IWB-3517 .i VT-1 B7.60 Pumps Bolts,' Studs,-and NV.ts 'VIS,. Surface' IWB-3517 VT : B7.70 Valves. Bolts,' Studs,.and) Nuts VIS,' Surface -IWB-3517 VT-1 B7.80 CRD Housings Bolts, Studs and' Nuts 'VIS, Surface IWB-3517-
-VT-1 l NOTE: "N/A"JinjthejEXAM. METHOD'columniindicates.that no applicable components are included.
' in' North: Anna'-Unit'2.. - .
i N2CLS1 '2 Rev.-O.1990
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IntegralAbtaNhments'for. Vessels m. ~
.' ALT. . EXAM.
ITEM = EXAM. EXAM REQUIRED / ; ACCEPTANCE ': . RELIEF -
^ PARTS TO-BE'EXAnizzu:
NO. - METHOD" METHOD FIG NO.- . CRITERIA REQUEST +
-'B5.10. . Reactor: Vessel Integrally.. Welded ' N/A. N/A - N/A-Attachments .
2 B8.20- Pressurizer Integrally. Welded: ' ~ _ JVOL OR_ ~ IWB-2500-13, IWB-3516 I Attachments' 'SUR -14, and -15 i I B8.30 Steam Generator Integrally Welded VOL OR IWB-2500-13, ' IWB-3516-3- Attachments- ~
-SUR -14, and -15 1
- 2 B8.40 Heat' Exchanger Integrally Welded .. N/A l N/A ~ N/A-Attachments:
A NOTE: "N/A".in the[ EXAM.IMETHOD!co1Omn indicates that.'no applicable components are included
~ '
- in' North Anna' Unit
- 2.- -
i i . k s N2CLS1'- .
;- .L2--17 _
Rev. O 1990 1
?
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?
. - . ~ ~
- ALT. EXAM
~ ' ITEM _ EXAM.; .
EXAMi REQUIRED / --ACCEPTANCE RELIEF i NN PARTS TO BE:EXAnin w- METHOD- METHOD /IG NO. CRITERIA REQUFEI , . .B9.11- Nominal PipesSize >:4 in.- -VOL.& IWB-2500-8~ IWB-3514 NDE-4
'Circumferential: Welds' TSUR B9.12 Nominal Pipe Size > 4jin._ VOL1& SUR- IWB-2500 IWB-3514 NDE-4 Longitudinal Welds-( B9.21 ~ Nominal' Pipe. Size.f 4i~in. SUR- .IWB-2500-8 IWB-3514. NDE-4:
CircumferentialiWelds B9 22 Nominal Pipe: Size-< 411n. 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 1 Connection Welds? -10, and -11 l .- i l B9.32 Nominal ~ Pipe Size <^4'in.= SUR-
~
-IWB-2500-9,. IWB-3514 NDE-4 :
.[
Branch Pipe Connection Welds-- -10, and -11 B9.40 Socket Welds. SURJ ' IWB-2500-8 IWB-3514 NDE-4
^
t l
.p - .I N2CLS1 ,
2 ,
- c. Rev. O'1990
. 27 .~ _ ,
, 2_ ' ~. , _ :.l. 2
.,__ _.-Lw.,,~ _
y., :ce lu.i. i:'lll:L ~ -:m,- : les r, -- n ; b.,4 < n : e m :-~'- , w hi -4' W,, .N~~% c~"i 5 r ~ ww=,'~ < rr = = = ' ~ ~ ' = ~ - = - = - - " = ' - ~ ' - - -
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Examination CategoryrB-K-1bIntegral-Attachments forJPiping, Pumps,.and'. Valves 12.3.10 _..
- 1 ALT. . EXAM ..
. ITEM ! EXAM. FEXAM REQUIRED / ACCEPTANCE . RELIEF.- :
NO. PARTS TO~BE' EXAMINED' METHOD METHOD FIG NO. CRITERIA REuUEST-B10.10 Piping: Integrally (Welded- VOL'or IWB-2500-13,. .IWB-3516 Attactunents 'SURi -14, and -15
-B10.20 Pumps l Integrally -Welded ~.. '
N/A' - N/A' N/A-Attachments i B10.30- ' Valves' Integrally Welded. JN/A N/A' ' N/A-
' Attachments -
Lr -
-i NOTE: "N/A"rin'the EXAM.r METHOD column indicates;that'no'. applicable-components are. included '
'in North--AnnalUnit}2.-
t
,, t
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~
N2CLS1' 2--19 ' IRev. O 1990'
- ~
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l ~ - 2.3.11 ' Examination: Category B-L-1,-Pressure Retaining Welds.in Pmap' Casings . [ _ o l ALT. - EXAM. -, i ITEM' EXAM.$ : EXAM' ACCEPTANCE'- RELIEF -- .i i
. REQUIRED /-
, : NO '. PARTS.TO--BE EXAMINED ' METHOD' METHOD . FIG NO. ' CRITERIA REQUEST ' l l i B12.10 Pump Casing Welds- : VOL- ' SUR-' IWB-2500-16 IWB-3518 NDE-5) '
. ~
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= .-
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~
ALT. EXAM ITEM . EXAM.- -EXAM' ; REQUIRED / -ACCEPTANCE RELIEFJ NO .~ _ PARTS TO'BE EXAMINED METHOD METHOD- ' FIG NO. CRITERIA' REOUEST-
-~- ,-
B12.~20 Pump Casing. VTs, 'VIS,. - Internal 'IWB-3518 i NDE I
- VT-3 VT-l' ' Surfaces 4
4-k , i i i i t u i l
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2 , Rev. 0 1990 2
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; u t s a 2
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- m
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= iy iy .t n 1 Pd Pd Ni o s s o o An i a lB lB XU -
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e, O s . C+ ; O . 2.3.15 Examination Category B-N-1, Interior of Reactor vessel ALT. EXAM EXAN. EXAM REQUIRED / ACCEPTANCE RELIEF . ITEN METHOD METHOD FIG NO. rwrTSNTA RFuussi NO. PARTS TO BE WW4MIsr.u
-VIS,. Accessible IWB-3520.2 B13.10 Reactor. Vessel'- areas Vessel Interior- VT-3 2-24 Rev. O 1990 N2CIS1
=
0 .
"O 1
2.3.16 . Examination Category B-N-2, Integrally. Welded Core Support Structures and Interior Attachments to Reactor Vessels ALT. EXAM ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA RF.udr.5T l D13.20 BWRs Only N/A N/A N/A D13.30 BWRs Only N/A N/A N/A B13.50 Reactor Vessel Interior Attachments VIS, Accessible IWB-3520.1 Within Beltline Region VT-1 welds t ! B13.60 Reactor Vessel Interior Attachments VIS, Accessible IWB-3520.2 ! Beyond Beltline Region VT-3 welds l NOTE: "N/A" in the EXAM. METHOD column indicates that no applicable components are included 4 in North Anna Unit 2. - I i N2CLS1 2-25 Rev. O 1990 '
-, .- <, ,, , . - - ~
. . . - . -,- , . - , - - - - - . - , . . . . . . - , , . . , - .<,~..~.,,L--
. + , - - - ~ ~ . . - - , , , . - ~---.,-....s~--
' ], i (. _ q- ._ l' i , l 2.3.17 Examination Category B-N-3, Removable Core Support' Structures ALT. EXAM ITEM EXAM. EXAM NO. REQUIRED /- ACCEPTANCE RELIEF
-PARTS TO BE EXAMINED METHOD METHOD FIG NO. cnITERIA L ;- _ 1.s i ,
D13.40 BWRs Only N/A t N/A N/A . B13.70 Reactor Vessel Core Support. VIS, Accessible IWB-3520.2' ! Structure VT-3 Surfaces ; i l i , t t I
- i l
4
~
. NOTE: "N/A" in the EXAM. MET)IOD column indicates that no applicable components are included in North Anna Unit'2. ' i 4 i ; 4
- N2CLS1 2-26 Rev. 0 1990 4
7
. , . . . , . , , , , . . . . , , , , . , . , , , ,. ~,. ,,,c.c, .,,,.,,n.~ n., - ,, , , - , , . . , . . . , .
. ,, + . . - . , , , - - _ - - . - . . .
... i; . I .
2 f 2.3.18 Examination Category B-0,. Pressure Retaining Welds'in Control Rod Housings i ALT. EXAN ITEM EXAM. ' EXAN REQUIRED / ACCEPTANCE RELIEF-
~ NO. PARTS 1D BE EXAMINED METHOD nr inOD FIG NO. CRITERIA REuudi.
D14.10 Reactor Vessel Welds in CRD Housing VOL or IWB-2SOO-18 IWB-3523 SUR
- I 2 .
4 4 i ; k 4 i i i i I ( t
- N2CLS1 2 - 2 7 -- Rev. O 1990 4
- . :- . - , --;;. . - - . . ~ -- . - - . . - - ..... - --. : ---._-. ... ....- . ,
O V C" b 2.3.19 Examination Category B-P, All Pressure Retaining Components ALT. TEST ITER EXAM. EXAN REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXANTWED METHOD METHOD FIG NO. . CRITERIA B h m z.s i i B15.10 Reactor Vessel Pressure Retaining VIS, LEAKAGE IWB-3522 SPT-11, i Boundary 'VT-2 PER IWB-5221 SPT-12
'B15.11 Reactor Vessel Pressure. Retaining .VIS, HYDROSTATIC IWB-3522 SPT-11,
- j. Boundary- VT-2 PER IWB-5222 SPT-12 i B15.2O Pressurizer Pressure Retaining VIS, LEAKAGE IWB-3522 SPT-12
' Boundary VT-2 PER IWB-5221 B15.21 Pressurizer Prbssure Retaining- VIS, HYDROSTATIC IWB-3522 SPT-12 Boundary l'
-VT-2 PER IWB-5222 D15.30 Steam Generator Pressure Retaining VIS, LEAKAGE IWB-3522 SPT-12 , Boundary VT-2 PER IWB-5221 t
B15.31 Steam Generator Pressure Retaining VIS, HYDROSTATIC IWB-3522 SPT-12 I I Boundary VT-2 PER IWB-5222 i D15.40 Heat Exchanger Pressure Retaining N/A N/A Boundary N/A B15.41 Heat Exchanger Pressure Retaining N/A N/A N/A ;
; Boundary ;
N2CLS1 2-28 Rev. O 1990
O
^
C'_- O l
' Examination Category B-P, All Pressure Retaining Components (continued) 2.3.19 ALT.- TEST
.' ITEM . EXAM. EXAM REQUIRED / ACCEPTANCE -RELIEF NO. PARTS TO BE EXArunr.u METHOD METBOD FIG NO. CRITERIA REuuhi-
^
015.50 Piping Pressure Retaining Boundary VIS, LEAKAGE IWB-3522 SPT-12 7 VT-2 PER IWB-5221 D15.51 Piping Pressure Retaining Boundary VIS, HYDROSTATIC IWB-3522 SPT-1,-2 VT-2 PER IWB-5222 SPT-0,-4 + SPT-12 B15.60 Pumps Pressure Retaining Boundary VIS, LEAKAGE IWB-3522 SPT-12 l i VT-2 PER IWB-5221 ! i B15.61 Pumps Pressure Retaining Boundary VIS, HYDROSTATIC IWB-3522 SPT-1, , VT PER IWB-5222 SPT-12 i B15.70 Valves Pressure Retaining Boundary VIS, LEAKAGE IWB-3522 SPT-12' I VT-2 PER IWB-5221 B15.71 Valves Pressure Retaining-Boundary VIS, HYDROSTATIC IWB-3522 SPT-1,-2 ' VT-2 PER IWB-5222 SPT-3,-4 ' SPT-12 i i l t l N2CLS1 2-29 Rev. 0 1990 I l
- . , , . ._- . .a . .. . .. .. ,. . . . , . . . ,. _ _ _ - _ _ . _ _ _ _ _ _ . _ _ _ _ -
. _ _ , ~ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _
' ~
l (
- ~;
f: , 2.3.20 Examination Category B-Q, Steam Generator Tubing.. l
. ALT. EXAM ,
ITEM EXAM. EXAM REQUIRED / ACCEPTANCE RELIEF NO- PARTS M BE EXAM 2NED METHOD nr.inOD FIG NO. CRITERIA REQUEST , l ( D16.10 Steam Generator Tubing in Straight- N/A N/A N/A , Tube' Design B16.20 Steam Generator Tubing in U-Tube VOL Hot Leg IWB-3521 .
- Design and U-Bend t
t i i !
' NOTE: "N/A" in the EXAM. METHOD column indicates that no-applicable components are included in North Anna Unit 2.
4 i i N2CLS1 2-30 Rev. 0 1990 I I '.._. , . _ _ . ..;.,... _..._-4
. . ~ . . - . . , _ , _ _ _ - . . - _ _ _ . . _ . _ _ _ _ , _ _ _ _ _ _ _
~
m' 2.4 ISI Class'2 Components - Program Summary Table 2.4.1 Examination Category C-A, Pressure Retaining Welds in Pressure Vessels ALT. EXAM ITEM EXAM EXAM REQUIRED / ACCEPTANCE RELIEF PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOJEST NO. C1.10 Pressure Vessel VOL IWC-2500-1 IWC-3000 Circumferential Shell Welds C1.20 Pressure Vessel VOL IWC-2500-1 IWC-3000 Circumferential~ Head Welds C1.30 Pressure Vessel VOL IWC-2500-2 IWC-3000 Tubesheet-to-Shell' Weld
'N2CLS2" 2-31 Rev. 0 1990
-- ~
. wi . _
Lj . a 2.4.2 1 Examination Category C-B, Pressure Retaining Nozzle Welds.in Vessels ALT. EXAM ITEM EXAM EXAM- REQUIRED / ACCEPTANCE REL EF 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 (or IIcad) Weld C2.21 Pressure vessel SUR-& IWC-2500-4(a) IWC-3000
> 1/2 in. VOL or (b)
Nominal Thickness Nozzle-to-Shell (or Head) Weld without Reinforcing. Plate. C2.22 Pressure Vessel VOL IWC-2500-4(a) IWC-3000 3
> 1/2 in.' Nominal or (b)
Thickness i Nozzle Inside l Radius Section. without Reinforcing Plate C2.31 Pressure Vessel SUR IWC-2500-4(c) IWC-3000
> 1/2 ~in. ~
Nominal Thickness ! Reinforcing. Plate Welds i to Nozzle and Vessel N2CLS2 2-32 Rev. 0 1990
,, .,~._
,~
(%J;) ( )= (u./l
'u J 2.4.2 ' Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels (continued)
ALT. EXAM
. ITEM EXAM EXAM . REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD . METHOD FIG NO. CRITERIA REOUEST C2.32 Pressure Vessel VOL IWC-2500-4(c) IWC-3000
> 1/2'in..
Nominal Thickness Nozzle-to-Shell- - (or Head) Welds When inside of' Vessel is~ Accessible C2.33 Pressure Vessel'. VIS, N/A No leakage
> 1/2-in. VT-2 Nominal-Thickness Nozzle-to-Shell (or Head):When Inside of Vessel Is Inaccessible 4
i i d N2CLS2 2-33 Rev. 0 1990
.-,_-. . _ . . _ . __..~,_ .._ __ . . _ . - = _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ , _ _ _ _ _ _ -
O -
-Examination Category C-C,-Integral Attachments For Vessels, Piping,-Pumps, and Valves-
~
2.4.3 ALT. EXAM EXAM EXAli REQUIRED /. ACCEPTANCE RELIEF
' ITEM- CRITERIA REOUEST NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO.
Pressure ~ Vessel- SUR IWC-2500-5 IWC-3512 C3.10 Integrally Welded Attachments SUR' IWC-2500-5 IWC-3512 C3.20 ' Piping Integrally Welded . Attachments Pump SUR IWC-2500-5 IWC-3512 C3.30 Integrally Welded Attacnments VaIve- SUR IWC-2500-5 IWC-3512 C3.40 Integrally. Welded Attachments N2CLS2 2-34 Rev. 0 1990
. . , . . - . - . - . - = - - - - - --
_ _ _ _ . . . ~ . . . . . . .
~, --
,~
<j ' G .
wj 2.4.4 Examination-Category C-D,; Pressure Retaining Bolting Greater Than 2 in. In Diameter ALT. EXAM ITEM EXAM- EXAM REQUIRED / ACCEPTANCE -RELIEF i ((Q. PARTS TO BE EXAMINED METHOD METHOD FIG NO. ' CRITERIA REOUEST
'C4.10 Pressure Vessel VOL IWC-2500-6 IWC-3512 Bolts and Studs C4.20 Piping N/A N/A N/A Bolts and Studs C4.30 Pump N/A N/A N/A Bolts and Studs C4.40 Valve N/A N/A N/A Bolts and Studs N2CLS2 2-35 Rev. 0 1990 4
- m... , , . r .. s. e , . , - - , , .c. ..rE.- .
,. _ [' . _ . , , _ , __________________.___.___._____________._m.. .m.___._
s- _ ._-s ./ .
\ \
2.4.5 -Examination Category.C-F-l', Pressure Retaining Welds In Austenitic Stainless Steel..or High Alloy Piping
~
ALT. EXAM ITEM EXAM EXAM REQUIRED / ACCEPTANCE RELIEF ; NO. ' PARTS TO BE EXAMINED METIIOD METHOD FIG NO. CRITERIA . ' REQUEST 9 C5.11 .Circumferential Welds In Piping SUR & IWC-2500-7 IWC-3514
> NPS 4 And l'3/8'in. Nominal VOL Wall Thickness
' C5.12 Longitudinal Welds'In Piping > SUR & IWC-2500-7 IWC-3514 NPS 4 And 2 3/8 in. Nominal Wall VOL Thickness C5.21 Circumferential SUR'& IWC-2500-7 IWC-3514 VOL C5.22 Longitudinal SUR & IWC-2500-7 IWC-3514 VOL C5.30 Socket Welds SUR IWC-2500-7 IWC-3514 j
4 I N2CLS2 2-36 Rev. 0 1990
...- . . . --. . - - . . ~ . . - . . . . .- , , . , . - - . - - . _ . . ~ _ _ - . _ _ _ _ _ _ _ _ . - _ .. .- - . _
O ~ 2.4.5 Examination Category C-F-lj Pressure Retaining Welds In
~
Austenitic Stainless Steel _or High Alloy Piping (Continued) ALT. EXAM ITEM EXAM IDUWI REQUIRED / ACCEPTANCE RELIEF METHOD METHOD FIG NO. CRITERIA REQUEST NO. PARTS TO BE EXAMINED C5.41 Circumferential Branch Connection SUR IWC-2500-9, IWC-3514 Welds of Branch Piping.1 NPS 2 to -13 C5.42 Longitudinal Branch Connection SUR IWC-2500-12 IWC-3514 Welds of Branch Piping 1> NPS 2 and -13 N2CLS2 2-37 Rev. 0 1990
~
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l I L x ,/ _ (/
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i
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~
2.4.6 Examination Category C-F-2, Pressure Retaining Welds In Carbon-Steel or Low Alloy Steel Piping
. ALT. EXAM ITEM EXAM EXAM REQUIRED / ACCEPTANCE RELIEF-
. NO. PARTS'TO BE' EXAMINED METHOD METHOD FIG NO. CRITERIA REOUEST C5.51 Circumfere6tial Welds In' Piping SUR & IWC-2500-7 IWC-3514
> NPS 4 And 2 3/8 in. Nomi.nal VOL Wall Thickness 05.52 Longitudina1-Welds In Piping > SUR'& IWC-2500-7 IWC-3514 NPS.4 And >'3/8 in . Nominal Wall
_ VOL Thickness C5.61 Circumferential SUR & IWC-2500-7 IWC-3514 VOL C5.62 Longitudinal. SUR & IWC-2500-7 IWC-3514 VOL C5.30 Socket Welds SUR IWC-2500-7 IWC-3514
- N2CLS2 2-38 Rev. O 1990 y +n , - w1 w. ,-.-% *4 <a+sy ,- s., .y.-..',- --y. ~ , . - *,-,4# - ,*e + %, ,.ee. . -e .- we m.- ., #. < , - - - - v , -- .__m_ _ . . _ -.--mm-r----mm:-* - - - - - - - - - - ~
,m, _.
,= .
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2.4.5 Examination' Category C-F-2, Pressure _ Retaining Welds In Carbc,n Steel or Iow Alloy Steel Piping (Continued) 4 ALT. EXAM ITEM EXAM EXAM. REQUIRED / ACCEPTANCE RELIEF-NO. PARTS TO'BE EXAMINED METHOD METHOD FIG NO. CRITERIA REQUEST C5.81 Circumferential Branch Connection SUR IWC-2500-9, IWC-3514 NDE-7
- Welds of Branch Piping 2 NPS 2 to -13 i
i C5.82 Longitudinal Branch Connection SUR IWC-2500-12 IWC-3514 Welds of Branch Piping > NPS 2 and -13 r l t N2CLS2 2-39 Rev. 0 1990
. - :- + . . .
t
\ >
1 . ( kg/ (/ 2.4.7 Examination Category C-G, Pressure-Retaining Welds In Pumps And Valves ALT. EXAM ITEM EXAM EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REQUEST C6.10 Pump Casing Welds-- SUR IWC-2500-8 IWC-3515 NDE-8 NDE-9 C6.20 Valve Body Welds N/A N/A N/A L NOTE: "N/A" in the EXAM. METHOD Column indicates that no applicable components are included at North Anna Unit 2. N2CLS2 2-40 Rev. 0 1990
~
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 REOUIprn CRITERIA REOUEST C7'.10 Pressure Vessel VIS, FTJNCTIONAL IWC-3516 SPT-12, Pressure Retaining VT-2 PER IWC-5221 SPT-13 Components Pressure Vessel VIS, HYDROSTATIC IWC-3516 SPT-8, C7.20 Pressure Retaining VT-2 PER IWC-5222 SPT-12, Components SPT-13 VIS, FUNCTIONAL IWC-3516 SPT-12, C7.30 Piping.-
Pressure Retaining VT-2 PER IWC-5221 SPT-13 Components - Piping VIS, HYDROSTATIC IWC-3516 SPT-5,-6 C7.40 Pressure Retaining VT-2 PER IWC-5222 SPT-7,-8 SPT-11, Components
-12,-13 C7.50 Pump VIS, FUNCTIONAL IWC-3516 SPT-12, Pressure Retaining VT-2 PER IWC-5221 SPT-13 Components Pump VIS, HYDROSTATIC IWC-3516 SPT-12, C7.60 Pressure Retaining VT-2 PER IWC-5222 SPT-13 Components-C7.70' Valve VIS, FUNCTIONAL IWC-3516 SPT-12, Pressure ' Retaining VT-2 PER IWC-5221 SPT-13 Components N2CLS2 2-41 Rev. G 1990
/
..i ,,...i
~
O~ 0-O~ 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 revue.5T C7.80 Valve VIS, HYDROSTATIC IWC-3516 S PT-5, -6 Pressure Retaining VT-2 PER IWC-5222 SPT-7,-8 Components SPT-12, SPT-13 N2CLS2 2-42 Rev. 0 1990
.. ~ .
~-
L) . p
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2.5 ISI Class 3 Components Program Summary 2.5.1 Examination Category D-A, Systems In Support of Reactor. Shutdown Function ALT. TEST ITEM EXAM. EXAM AND EXAM ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD REOUIREMENTS CRITERIA REQUEST-D1.10 Pressure Retaining Components .VIS, INSERVICE- IWD-3000 VT-2 PER IWD-5221 D1.10 Pressure Retaining Components VIS, HYDROSTATIC IWD-3000 VT-2 PER IWD-5223 D1.20 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Component Supports and VT-3 Restraints I r i D1.30 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Mechanical and Hydraulic. VT-3 Snubbers D1.40 Integral. Attachment- VIS, IWD-2500-1 IWD-3000 Spring Type Supports VT-3 D1.50 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Constant Load. Type Supports VT-3 -
- D1.60 Integral Attachment- -
VIS, IWD-2500-1 IWD-3000 4 Shock-Absorbers VT-3 4 N2CLS3 2-43 Rev. 0 1990
'(m.
yy} . :(.x <
) --- (
v i. 2.5.2 -Examination Category D-B,. Systems In Support of Emergency Core Cooling, Containment Heat-Removal,- Atmosphere. Cleanup, and Reactor Residual Heat Removal l ALT. TEST ITEM EXAM ~ EXAM AND EXAM ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD REOUIREMENTS CRITERIA' REQUEST D2.10 Pressure Rstaining 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 Component Supports and VT-3 Restraints D2.30 Integral Attachment- VIS, IWC-2500- 1 IWD-3000 NDE-10 Mechanical'and Hydraulic VT-3 Snubbers 1
D2.40 , Integral Attachment- VIS, IWD-2500-1 IWC-3000 NDE-10 Spring Type Supports VT-3 D2.50 Integral Attachment- VIS, IWD-2500-1 IWD-3000 NDE-10 Constant Load Type Supports VT-3 D2.60 Integral Attachment- VIS, IWD-2500-1 IWD-3000 NDE-IO Shock Absorbers VT-3
~
H2CLS3 2-44 Rev. 0 1990
,,~ -
_. e-
/
Q) Q ,1 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 RELTEF NO. ' PARTS TO BE EXAMINED METHOD METIIOD REOUIREMENTS CRITERIA REOU M
-D3.10 Pressure' Retaining Components VIS, INSERVICE IWD-3000 VT-2 PER IWD-5221 D3.10 Pressure Retaining Components VIS, HYDROSTATIC IWD-3000 VT-2 PER IWD-5223 p, on Integral Attachment- VIS, IWD-2500-1 IWD-3000 C,mponent Supports VT-3 and R?straints 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 l Spring Type rupports VT-3 l
D3.50 Integral Attachment- VIS, IWD-2500-1 IWD-3000 Constant Load Type VT-3 Supports D3.60 Integral Attachment-' VIS, IWD-2500-1 IWD-3000 Shock-Absorbers VT-3 i N2CLS3 2-45 Rev. 0 1990
. - . _ ~ -- . , - -, ,. . . . _ _ _ - - , _ _ _ _ _ _ _ _ _ ._ __ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _
,, e~ - ,~ 3
?( -
-ds '
2.6. Augmented Inspection Requirements on1ISI Class 1, 2, or 3 Systems - Program Summary Table ITEM NO. COMPONENT DESCRIPTION REFERENCEfS) EXAM AND FREOUENCY 1 REACTOR COOLANT PUMPS - FLYWHEEL TECH. SPECS. 4.4.10.1.1 UT IN PLACE AT APPROX. REG. GUIDE.1.14, REV. 1 3 YEAR INTERVALS. UT/PT (FLYWHEEL REMOVED) 10 YEAR 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 LOWER UFSAR 3.6.2.3.2 UT/PP EXAM SELECTED WELD: CUBICLE BETWEEN FIDOR ELEVATIONS EVERY 40 MONTHS 262 FT. 10 IN. AND 272 FT. 6-IN.
- 4. PRESSURIZER SAFETY VALVE INLET PIPING UFSAR 3.6.2.3.3 UT/PT EXAM SELECTED PELDS LINES- EVERY 40 MONTHS
- 5. MAIN FTEAM POSTULATED BREAK IDCATIONF- UFSAR 3C.2.7 UT/PT EXAM OF 1/3 OF SELECTED WELDS EVERY M MONTHS, WITH 100% OF ALL WELDS COMPLETED BY THE END OF THE INTERVAL.
6 FEEDWATER POSTULATED BREAK IDCATIONS UFSAR 3C.2.7 UT/Pr EXAM OF 1/3 OF SELECTED WELDS EVERY 40 MONTHS, WITH 100% OF ALL WELDS COMPLETED BY THE END OF THE INTERVAL.
- 7. _ STEAM GENERATORS - SUPPORTS TECH. SPECS. 4.4.10.1.2 VT-1 EVERY 40 MONTHS I/3 OF THE MAIN MEMBER WELDS JOINING A572 MATERIAL.
N2AUGTBLL 2-46 Rev. 0 1990
m - p Q. g_. g
- 2.6 Augmented Inspection Requirements on ISI Class 1, 2, or 3. Systems !
. - i ITEM NO, wrtrurstar DESCRIPTION REFERENCEfS) EXAM AND FREOUENCY l i
- 8. ROCKWELL EDWARDS T-58 ANGLE - IEIN84-48 RT A SELECTED GROUP OF i UNIVALVES VALVES EVERY 18 MONTHS !
~
.9. SERVICE ~ WATER PIPE WALL THICKNESS STATION PT SEMI-ANNUAL UT THICKNESS ' >
MEASUREMENTS 1-PT-75.14 AND DRY FILM PAINT
- l THICKNESS.
{ 10. REACTOR VESSEL INCORE DETECTOR NRCB 88-09 100% EDDY CURRENT j THIMBLE TUBES EXAMINATION ON ALL INCORE' DETECTOR THIMBLE TUBES IN SERVICE EACI REFUETING : t
- 11. REACTOR COOLANT PIPING - LER 82-043 RT EVERY THIRD REFUELING
, THERMAL SLEEVES DATED 8/26/82 OUTAGE. > i l ABBREVIATIONS USED IEIN =- NRC IE INFORMATION NOTICE i j LER .= LICENSEE EVENT' REPORT ! NRCB = NRC-IE. BULLETIN I PT = PENETRANT TEST / EXAMINATION ! PT =- PERIODIC' TEST (REFERENCE)
.RG = NRC REGUIATORY GUIDE ,
RT- = RADIOGRAPHY TEST / EXAMINATION ! UFh R = -UPDATED FINAL SAFETY. ANALYSIS._-REPORT ! , VT =
. VISUAL TEST / EXAMINATION- :
s N2AUGTBL 2-47 Rev. O 1990 , f I
. . . - _ -- . - .. - - . - . . - - . - . ~ - _ - . . _ . . . . - . . . . - . - . . . .. . - . .
I
' s t
4 : i i h 2.7.1 ' NDE SERIES RELIEF REQUESTS b i 1 t i k
~
f
% 4
.N2-NDERR 2-48 Rev. 0 1990 '
k
' ' "~~~* ~ ""' ' ' ~ ~ ~ '
1 RELIEF REOUEST NDE-1 l I. IDENTIFICATION OF COMPONENTS I Nozzle-to-Vessel Welds l Pressurtizer: (2-RC-E-2) ] 1 Drawina No. Wald No. ) l 12050-WMKS-RC-E-2 9 1 II. IMPRACTICABLI CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code 1986 Edition, Category B-D, Item No. B3.110, requires a j
, volumetric examination of Pressurizer nozzle-to-vessel 1 welds. I Relief is requested from the volumetric examination requirements for the pressurizar nozzle-to-vessel weld.
III. BASIS FOR RELIEF l [\- 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 y bottom head limit access and prevent meaningful examination I of the nozzle-to-vessel weld. Measurements conducted of l- the examination area indicate that approximately 3 to 8 i t 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 f Ll obstructions. It is felt that the gain in system integrity [ , is not commensurate with the exposure associated with this partial examination. y H
.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.
i N2-NDERR 2-49 Rev. 0 1990 i
RELIEF REOUEST NDE-2 { I. IDENTIFICATION OF COMPONENTS ! Nozzle Inner Radius Sections Steam Generators: (2-RC-E-1A, 2-RC-E-1B, 2-RC-E-1C) Pressurizer: . (2-RC-E-2) Drawina No. Inner Radius Identificatipn No. 12050-WMKS-RC-E-2 9NIR, 10NIR, 11NIR, 12NIR, 13NIR, (Pressurizer) and 14NIR 120$0-WMKS-RC-E-1A.2 11NIR and 12NIR (ISI Class 1) (Steam Generator A) 09NIR and 10NIR (ISI Class 2) 12050-WMKS-RC-E-1B.2 11NIR and 12NIR (ISI Class 1) (Steam Generator B) 09NIR and 10NIR (ISI Class 2) 12050aWMKS-RC-E-1C.2 11NIR and 12NIR.(ISI Class 1) (Steam-Generator C) 09NIR and 10NIR (ISI Class 2) II. , IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1986LEdition, Category B-D, Item Nos. B3.120, B3.140, and Category C-B, Item No. C2.22 require the nozzle inside radius sections of the pressurizer and steam generators to be volumetrically examined. Relief is requested from the volumetric examination
. requirements of the nozzle inner radii for theEsteam
-generator and pressurizer nozzles.
O N2-NDERR 2-50 Res . 0 1990 l _m_m ______._m_____-..- . _ _ _ _ ._ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ . _ . _ _ ______________m__- _____m . - - -_-__--- -
) RELIEF REQUEST 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 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 heater bank interferences. The steam generator main steam nozzles-are physically restricted by the flow limiting devices.
- 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 these inner radii, particularly since no preservice
.results are available for review.
1
- 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.
- 2. As an alternative to'the Section~XI Category B-D
< required volumetric examination of the Pressurizer lower head' nozzle inside radius section (09NIR), this area on the O.D. of the nozzl'e~will be visually.
examined (VT-2) after the pressurizer has reached = operating pressure and temperature. O N2-NDERR 2-51 Rev. 0 1990 I
O RELIEF REOUEST NDE-2 CONTINUED
- 3. As an alternative to the section XI required volumetric examination of the Steam Generators six Category B-D nozzle inside radius sections (11NIR and 12NIR on 2-RC-E-1A, -1B, and -1C), the areas will be visually examined (VT-1) from the nozzle I.D. using direct or remote techniques per the schedule shown in Table-IWB-2412-1, Inspection Program B.
- 4. As an alternative to the Section XI required volumetric examination of the Steam Generator Feedwater nozzle inner radius sections'(09NIR on 2-RC-E-1A, -1B, and -
IC), the accessible portions of these sections will be visually _(VT-1) examined outage per the schedule shown in Table IWB-2412-1, Inspection Program B.
- 5. As an alternative to the Section XI required volumetric examination of the Steam Generators' three. Category C-B Main Steam nozzle inner radius sections, (10NIR on
. 2-RC-E-1A,: -1B, and -1C), the area on_the O.D. of the nozzles:will be visually examined-(VT-2) when the Steam Generator has reached normal operating pressure and 4i. _ temperature per the schedule shown in Table IWB-2412-1, Inspection Program B.
NOTE: Similar relief was submitted by-letter dated April 24, 1986 to Mr. Harold Denton, Serial No. 86-670 for Surry Power Station Unit 1 and approved-by NRC letter dated June 27, 1986, 1 e; N2-NDERR 2-52 Rev. 0 1990
%. RELIEF REOUEST NDE-3 L's-[ c I.. IDENTIFICATION OF COMPONENTS Threads in Flange
-Reactor Vessel (2-RC-R-1)
Drawina No. Thread In Flance Mark Nq2
, 12050-WMKS-RC-R-1.3 TIF-01 through TIF-58 II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1986 Ed' tion, Category B-G-1, Item No. B6.40 requires a volumetric examination of the Reactor Vessel Threads In Flange. In addition, deferral of the examination is not permissible. Virginia Electric and Power Company is employing Table IWB-2412-1, Inspection Program B to schedule examinations.
Relief i;s requested from the examination frequency requirements specified in Table IWB-2412-1 for the reactor r vessel threads in flange examination. A. i ,/ .III. BASIS FOR' RELIEF Relief from the examination frequency requirements is ; requested based upon.the following. criteria:
- 1) Virginia' Electric and Power Company currently schedules the reactor vesselcflange threads examination to be performed in concurrence with the automated examination j
performed.on the reactor vessel welds.: 'This permits the examinations to be conducted with more sophisticated (i.e., digital,' automated) ultrasonic y . techniques in: lieu of manual techniques. 2)J In' order.to accommodate:the automated ultrasonic calibrations, the calibration block is currently-being maintained by our. Reactor Vessel-ISI. contractor at. l -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 E 2 g N2-NDERR 2-53 Rev. 0 1990 l
i L RELIEF REOUEST NDE-3 CONTINUED perform manual ultrasonic examinations. Virginia Electric and Power Company does not believe that the cost of an additional automated examination is justified or that a manual examination would be as reliable as an automated examination for these threads. IV. ALTERNATE PROVISIONS h 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. 'i V
^N2-NDERR 2-54 Rev. 0 1990 r -
4 RELIEF REOUEST NDE-4 I. IDENTIFICATION OF COMPONENTS ISI class 1 Pressure retaining welds in piping II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, ! 1986 Edition requires that notes 1(b) and 2 of Category B-J, table IWB-2500-1 be used in the selection of welds for examination. ; III. BASIS'FOR RELIEF
, The first interval selection was based upon the 1974 Edition with= Summer 1975 Addenda (74/S75) of ASME Section XI. As a result notes 1(b) and 2 cannot be applied without !
some programmatic additions and modifications. In addition, although stress and utilization calculations exist:for North Anna-Unit 2, no correlation exists with actual weld. locations. Total reuse of the first interval e- plan is not~ desirable, since even though the 74/S75 ( ,4) requirements were met, distribution of welds selected did not equitably cover certain line functions and designs. IV. ALTERNATE EXAMINATION ISI Class.1 piping welds will.be selected for examination such that.25% of the total number of welds are examined during the interval. The 25% sampling will be comprised as follows: one half of the sampling-(approximately 12.5% of thettotal number of piping welds) will-be welds which were. 1 examined in the first. interval andtone-half of the sampling 1 (approximately'12.5% of the total number of piping welds)' willLbe 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-intervals to the extent allowed by code editions approved-at that time.
1 O l N2-NDERR 2-55 Rev. 0 1990-L l
r
-['} RELIEF REOUEST NDE-5 3 . ,' 'w/ .
I. IDENTIFICATION OF COMPOFENTS I Pressure retaining welds in pump casings Pump casings Reactor Coolant Pumps: (2-RC-P-1A, -1B, -1C) ; Casing Exam Drawina No. Weld No. Identifier > 12050-WMKS-RC-P-1A.1 1 Case 12050-WMKS-RC-P-1B.1 1 Case ! 12050-WMKS-RC-P-1C.1 N/A Case . II. IMPRACTICABLE CODE REQUIREMENTS Section XIlof the ASME Boiler and Pressure Vessel Code, 1986 Edition, Category B-L-1, Item No.-B12.10: requires a ;
. volumetric. examination to be performed on 100% of the .
pressure' retaining welds in-atLleast one pump in each group
'/y of pumps' performing similar-functions in the system (e.g.,
'(_f reactor < coolant-pumps). In addition, category B-L-2,1 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. .Pumpfcasing Weld [ t Two:of the North Anna Power. Station Unit.2 reactor. coolant pum*s p 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 a boundaryrweld in the. casing that is to be examined in ' L accordance with category B-L-1. H Since the installation'of these. pumps,- it.has been p < recognized that a volumetric examination of the casing-I . welds isinot= practical-when employing current L , ultrasonic techniques. 1 1 D l A, / N2-NDERR 2-56 Rev. 0 1990 L L l i r
?
P
/' 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 4
, casing welds in the field did not exist until recent1,. <
LIn 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 _ i , 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 the pump casing.-
f ') The examination has been performed at four different sites, all of which have the Westinghouse Model 93 1
\_f.
pump. The MINAC examination-was performed at Ginna.in the spring of 1981,:at Point Beach Unit 1 in'the fallT of 1981,.at Turkey Point Unit'3 early in 1982 and at H. B. Robinson Unit 2 later in 1982. No problems with the
,i
_w elds were found at any ofsthe. 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 noparent change.. The successful performance of this_ volumetric l examination using the.MINAC at four different sites demonstrates that,the' method is capable of satisfying ASME Section XI, examination requirements. However, the performance of the' examination has shown-there_is a > relatively.high radiation exposure associated with it. The. total-exposure associated with-insulation. removal, disassembly, examination and reassembly of,the pump has averaged about 40 man-rem'per_ pump._ ! y-s + N2-NDERR 2-57 Rev. 0 1990
r
.. I
.f
./ RELIEF REOUEST NDE-5 CONTINUED y 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 1 Surry. Both examinations yielded similar results. : i B. Pump Casing The pump casing examinations are also not justified ( from a. cost / benefit perspective. The pump disassembly,- ' examination and reassembly is estimated to cost'
-$750,000.
'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 ; (y extent practicable of-the external casing' weld of one pump s_) j' will be performed to the extent and frequency of Category B-L-2 in lieu of the required Section XI examinations. C-NOTE: Similar' relief was submitted by letter dated March
~
30, 1988 (corrected), serial no. 86-796B, for North 3 i Anna Unit 1, interval 1.and approved by NRC letter , dated July 17, 1987, serial no. 87-443. t I { l; l(- A L l i l l ' l' N2-NDERR 2-58 Rev. 0 1990 . l
I f 4 RELIEF REOUEST NDE-6 I.. IDENTIFICATION.OF COMPONENTS ISI Class 1 valve Bodies Exceeding 4 in. Nominal Pipe Size
, II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the'ASME Boiler and Pressure Vessel Code, 1986-Edition, Category B-M-2, Item No. B12.50, requires a
' visual examination (VT-3) be performed on the internal pressure boundary surfaces of one valve in each group of
'~
valves that are the same construction design and manufacturing method, and that perform similar functions in the system.- Because these examinations must be met whether or not the s valves have to_be disassembled for maintenance, this requirement-is considered impractical. III. BASIS FOR RELIEF The requirement to disassemble primary' system valves for the. sole purpose of performing a visual examination of the internal pressure boundary surfaces has a very small-e potential of. increasing plant safety. margins-and;a very, disproportionate impact on expenditures,of plant manpower-and radiation exposure. '
-The'ISI Class 1 systems at North Anna Unit-2 include valves which vary _in size,_ design and manufacturer, but all are-
. produced.from either cast stainless _ steel or. cast carbon steel. _None of the valveDbodies are welded.
The performance of both carbon andLstainless cast valve bodies has been excellent in Pressurized' Water; Reactor
-(PWR)napplications. Based on this; experience and both-industry and< regulatory acceptanceiof these alloys, continued excellent service performance is anticipated.;
A1more practical approach is to examine the internal pressure boundary.of only those valves that require disassembly-for maintenance purposes. 'Thiscmethodology would provide'a modified' sampling program to that required by Section XI while significantlyLreducing radiation exposure to plant-personnel.
'N2-NDERR 2-59 Rev. 0 1990 k
__ ______m__________ __ _ _ _ _ _ _ _ - - - ----- -- ---- '
- - - ~ '
~1 .j-; . ' k, [ RELIEF REOUEST NDE-6 I CONTINUED u
Virginia Electric and Power Company feels this approach would provide a reasonable level of assurance that the. integrity of the primary system valves is being maintained. IV. ALTERNATE EXAMINATION- ;
-The visual examination of the internal pressure boundary- ,
surfaces will be performed, to the extent practical, when a ; valve is-disassembled for maintenance purposes. NOTE: Similar relief was submitted by letter dated March 30,.1988 (corrected), serial no. 86-796B, for North i Anna Unit.1, interval 1 and approved by NRC letter dated' July 17, 1987. l t E i L c l-
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\
i
- l. j
() N2-NDERR 2-60 Rev. 0 1990 L
. j
i i 1 - ,l L(_j RELIEF REOUEST NDE-7 I. IDENTIFICATION OF COMPONENTS Branch connection welds - Main steam relief headers Drawina No. Weld Nos. 12050-WMKS-101A-1 SW-77 to SW-88 lp 12050-WMKS-101A-2 SW-83 to SW-87 - 12050-WMKS-101A-3 SW-7W to SW-11W , See Detail ' A and Section B-B of each drawing. J
, II. IMPRACTICABLE. CODE REQUIREMENTS
. i
-Section.XIlof the ASME. Boiler a.d Pressure Vessel Code, -
1986 Edition,. Category-C-F-2, Item No. C5.81 requires circumferential pipe branch connection welds be surface ,
- y. examined. ,
4 i III.. BASIS FOR: RELIEF i i Theidesign of the main steam relief header branch ; connection welds' calls-for'the-use of a reinforcement pad. t L .These pads are fillet welded and: completely encase:the ' L
' branch connection welds.
IV. ALTERNATE PROVISIONS A. surface examinationiof the reinforcement pad's fillet L' wel.ds associated with-one branch. connection weld will be x performed during'the interval.
. t I ~'
l l-q i t l { ' N2-NDERR 2-61 Rev. 0 1990
l
, 1 RELIEF REOUEST NDE-8 I. IDENTIFICATION OF COMPONENTS Pump Casing Welds outside Recirculation Spray Pumps (2-RS-P-2A and 2-RS-P-2B)
. ,. lDrawina No. Weld Nos.
12050-WMKS-RS-P-2A SW-1, SW-2, SW-3 LS-6, LS-7, LS-8 m LS-9 (Partial Access) LS-10 (Partial Access) 12050-WMKS-RS-P-2B -SW-1, SW-2, SW-3 LS-6, LS -7 , ' LS - 8 , LS-9 _(Partial Access) r , LS-10L(Partial Access) e c. II.- IMPRACTICABLE CODE REQUIREMENTS SectionLXI ofithe ASME Boiler and Pressure Vessel Code, I n r[^)! 1986 Edition,. Category C-G, Item Number C6.10, requires
\s / pump casing welds to.have a surface examination each m inspection interval. A surface-examination of all of the "i pumps casing welds is notJpracticable. i
~ III.! BASIS-FOR RELIEF Each of the~two outside recirculation' spray pump casings have a total of five'circumferential welds and five
! longitudinallwelds. Three of: the circumferential welds l
^@?(> > (SW-1~, SW-2'and' SW-3)., and threeLof the longitudinal welds j (IS-6,- LS-7 and LS-8) are completely encased in concrete 7
" ' andiare nottaccessible'for examination.from the outside diameter'(0.D.).. Of,the remaining,two longitudinal welds, T
~
one weld is partially encased in concrete:(LS-9) and one. weld'is: partially ~ covered by.a vibration. plate (LS-10). . L 's O.D.1 examinations can be-performed on~both'of;these ; l . longitudinal welds. -The remaining two circumferential' L ' gm ' welds.are" completely accessible for-examinations from'the' p O.D. Surface examinations from the=Inside Diameter (I.D.)- L are not a_ practicable alternative._ Access to the inside of 4' ~ the pump. casings is limited.by physical' size (24 inch; H a' outside-diameter),3 the' pump' shaft, and the pump shaft-
~
, support obstructions.
9 ~R. . N2-NDERR 2-62 Rev. 0 1990 f
i P
'l RELIEF REOUEST NDE-8 CONTINUED i-IV. ALTERNATE PROVISIONS A surface examination of the accessible portions of the circumferential and longitudinal welds will be performed to the extent and frequency described in IWC-2500. A. remote
. visual examination (VT-1) of the I.D. of the pump casing a' welds will be performed only if'the pump is' disassembled i .for maintenance. i S
i 1
' [% .' '
' y/ :
t L , . i l l 4
'I
-N2-NDERR, 2-63 Rev. 0 1990 1
(,- % M} lt RELIEF REOUEST NDE-9
, I. IDENTIFICATION OF COMPONENTS 4
Pump Casing Welds Low Head Safety Injection Pumps (2-SI-P-1A and l 2-SI-P-1B) Drawina No. Weld Nos. 12050-WMKS-SI-P-1A 1, 2, 3 LS-1, LS-2, LS-3 LS-4 (Partial Access) LS-5 (Partial Access)
.12050-WMKS-SI-P-1B 1, 2, 3 LS-1, LS-2, LS-3 i
(; LS-4 (Partial Access)- LS-5 (Partial Access) f II. IMPRACTICABL2 CODE REQUIREMENTS' 4 Ki J Section XI of the ASME: Boiler and' Pressure Vessel Code, I L Ns/ ' 1986 Edition, Category C-G, Item Number C6.10, requires l . pump casing welds to have a surface examination each-0 . inspection interval. A surface examination of all of the b pumps _ casing welds 11sLnot practicable. l BASIS'FOR RELIEF L III. l Each of the two low head safety ~ injection pump' casings have a total of five circumferential' welds.and five longitudinal-
; welds. Three of the circumferential welds (1,2 and 3) and three_of'the longitudinal welds (LS-1, LIE-2 and LS-3)_are completely encased in concrete and:are rg>i?._ accessible for examination.- Of the remaining _two longitudinal welds,-.one t
weld is partially encased in concrete (LS-4) and one weld' : is partially _ covered by a vibration' plate (LS-5). Partial g Outside Diameter (O.D.) examinations can be: performed on l l both of these longitudinal welds. 'The remaining two-I. l circumferential' welds are completely accessible for _ examinations from thef0.D. -Surface examinations from the-
-Inside Diameter (I.D. ) are notia practicable- alternative.
Access to the inside of the pump' casings is limited by. physical. size (24 inch.outside diameter), the pump shaft, and the pump shaft supports. V N2-NDERR- 2-64 Rev. 0 1990
RELIEP REOUEST NDE-9 O 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 welds will be performed only if the pump is disassembled for maintenance. O ti2-NDERR 2-65 Rev. 0 1990 5
RELIEF REOUEST NDE-10 I. IDENTIFICATION OF COMPONENTS ISI Class 3 Components in the Auxiliary Feedwater System II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, c 1986 Edition, IWD-1220.1 exempts integral attachments of
-supports and restraints to components that are NPS 4 and -l smaller except for PWR Auxiliary Feedwater Systems. - l 5
This exemption does not provide a minimum (lower) size exemption for-examinations of integral attachments on ISI l 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
,;~q . addition, IWA-7400'provides an exemption for, replacements
( , at NPS l'. creating a situation,'where no preservice
,n'-4 inspection would be required in a replacement, although-normal inservice inspection is required.
IV. ALTERNATE PROVISIONS A 1 NPS' exemption:will be: applied on Auxiliary Feedwater ! L ' Systems for examinations on' integral attachments as required by IWD-2000.
- a o f I
L v ,
+
N2-NDERR 2-66 Rev. u 1990
i/i BELIEF REOUEST NDE-11
?%_JU
.I. IDENTIFICATION OF COMPONENTS '
Ultrasonic calibration blocks II. . IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, t 1986 Edition, gives specific requirements for the fabrication of ultrasonic calibration blocks. Specifically, paragraph IWA-2232(a), IWA-2232(b)'and IWA-l 22 32 (d) (4 ) III. BASIS FOR RELIEF North Anna power station was constructed prior to the i L issuance and adoption of ASME Section XI. Therefore, l- " ultrasonic calibration blocks were fabricated before the L guidelines of ASME Section XI were. developed and approved. . Meeting the requirements of IWA-2232(a), IWA-2232(b) and IWA-22 3 2 (d) (4 ) of the 1986 Code would-require us to , E manufacture new calibration' blocks. Using the existing calibration blocks allows us to correlate ultrasonic data (~T from the first interval ~ inspections as required-by IWA-14 00 (h)l, , ' d. L IV. ALTERNATE PROVISIONS i 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, L i L
- Alternative Rules for. Piping. Calibration Block Thickness, will be used as necessary.
Note: ItLis'our understanding th'at Code: Case'N-461?is= y scheduled for? approval in RegulatoryLGuide 1.147 R Revision 8. Any limitatiens or modifications-to this Code Case as. indicated 11n the Regulatory Guide shall be adhered'to.: i i e A. h N2-NDERR 2-67 Rev. 0'1990
RELIEF REOUEST NDE-12 I. IDENTIFICATION OF COMPONENTS , l ISI-Class 1 and Class 2 Welds II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the'ASME Boiler and Pressure Vessel Code, 1986 Edition, requires that the entire volume or area of a weld be examined before credit of examination can be given. III. BASIS FOR RELIEF Throughout the ISI Class 1 and ISI Class 2 systems situations exist where the entire examination volume or
-area cannot be examined due to interference by another component or part geometry. .
IV. ALTERNATE PROVISIONS Code Case N-460 alternative examination coverage for Class 1 and Class-2 welds, will be utilized in its entirety for
. determination of examination credit.
7.
/~N ! Note: It is our understanding that Code Case N-460 is-i _).- 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 N2-NDERR 2-68 Rev. 0 1990 >
i
1 O RELIEF REOUEST NDE-13 I. IDENTIFICATION OF COMPONENTS ISI Class 1 and 2 Piping, Vessel and Component Welds II. IMPRACTICABLE CODE REQUIREMENTS Section XI of.the ASME Boiler and Pressure Vessel Code, 1986 Edition, IWA-2600, weld reference system. III. BASIS FOR RELIEF The original construction code used at North Anna Power Station, ANSILB31.7, 1969 Edition, did not establish a weld reference system. Immediate establishment of a weld reference system cannot be practically attained within the g scope and-schedule of existing outages. IV. ALTERNATE PROVISIONS North Anna Unit 2 has recently updated its weld isometrics, providing a, detailed identification of location. It is our
;' intention to use these drawings'for tracking and locating.
welds.
<In addition, as welds requiring volumetric examinations are examined a-reference will be'establishedLfor 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.-
+
0
. N2-NDERR 2-69 Rev. 0 1990
() RELIEF REOUEST NQq-li I. IDENTIFICATION OF COMPONENTS Pressure Retaining Welds in the Reactor Vessel and Vessel Nozzle area examined by the automated vessel tool inspection device. II. IMPRACTICABLE CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1986 Edition, IWA-2600, weld reference system. III. BASIS FOR RELIEF The automated tool establishes its reference point using an existing zero reference in the reactor vessel. This point allows the device to repeat examination locations without the necessity of any other reference systems - It-accomplishes this by the use of an electronic encoder system which provides for sufficient repeatability. IV. ALTERNATE PROVISIONS The automated vessel tool examinations will continue to e- establish.its reference system based upon the existing zero reference. No other system is planned or deemed-necessary. s O N2-NDERR 2-70 Rev'. 0 1990
l i 1
,H RELIEF REOUEST NDE-15 I. IDENTIFICATION OF COMPONENTS Reactor vessel shell-to-flange weld Reactor vessel nozzle-to-vessel. welds !
Reactor vessel nozzle inside radius sections , Reactor vessel nozzle-to-safe-end welds Reactor vessel threads in flange ,
~!
Drawina No. Mark No. l l 12050-WMKS-RC-R-1.1 Wald 1 Welds 10, 12, 14 NIRs-10, 12, 14 12050-WMKS-RC-R-1.3 (50%) TIF-01 through TIF-58
~12050-WMKS-109E-1 Weld 1 12050-WMKS-109F-1 Weld 13 '
12050-WMKS-109G-1: Weld 25
'II. ' IMPRACTICABLE CODE REQUIREMENTS l
.SectionLXI of.th'e ASME~ Boiler and. Pressure Vessel Code,
-- i( -1986 Edition, Category'B-A, Item Bl.30, Category B-D, Item.
'l '
13.90,' Category B-D,. Item:B3.100, Category B-F, Item-B5.10, > and' Category B-G-1, Item B6.40-requires examinations, which a ' L -utilize the automated vessel tool. r -
' Relief is. requested from interval'. requirements described' in. -
- IWA-24321concerning the examination of the reactor vessel.
III. LBASIS FOR RELIEF North Anna Unit'2, first' interval, began December 14, 1980. M and concludes December 14, 1990.. As part of the:first interval inspection, North Anna' Unit 2 conducted examinations.on the reactor vessel,using the automated vessel tool. These examinations were conducted approximately two months: prior to the start,of the second-
~
interval. As only two months-remain'before.the' start of g the'second interval, requiring the automated vessel' tool to be brought.back to conduct examinations-for the first.
. period,.second interval 11s, impractical economically, and- i would unnecessarily impact a subsequent outage. .i m.
b
'V N2-NDERR 2-71 Rev. 0 1990
I RELIEF REOUEST NDE-15 > CONTINUED P IV. ALTERNATE PROVISIONS Alternatively the required second interval, first period ; examinations have been combined with the requirements of the first interval. This will not eliminate any required examination, as different areas will be examined. This application is implied as acceptable in IWA-2430(d) of the 1986 Edition of ASME Section XI, however this relief request is being submitted as only the reactor vessel examinations are affected. l l t ! I: ; l'%/ t
~
i .I',
'N2-NDERR 2-72 Rev. 0 1990
_.____.1_______________ I____________.____ - - ,
_ _ . . . . - _ . _ . . _ . . . . . _ . _ _ . _ __. . . _ . . _ _ . _ . . . _ _ _ _ _ _ _ _ _ . . . _ . _ _ _ _ _ _ . - . . . . _ . - . _ _ - . . . . . ~ _ . _ _ _ _ - 1 T
/
l
, 1 i'
l' 2.7.2 SPT SERIES L RELIEF REQUESTS i i I i f i
- ).
i.
'- (
N2-004d 2-73 Rev. 0 1990
A RELIEF REQUEST SPT-1 I. IDENTIFICATION OF COMPONENTS System : Chemical and Volume Control (CH) 1 Components: Piping _on drawing 12050-CBM-095C-2, Sheet 2 of 2, between the pumps, and the boundaries listed below. PUMP LIEZ BOUNDARY ISI CLASS 2-RC-P-1A 2"-CH-414-1502-Q1 1st F1ange' 2 1 1/2"-CH-798-1502-Q1 1st Flange 1 3/4"-CH-772-1502-Q1 1st Flange 2 != 1"-& 3/4" line 2-CH-274 1 1" & 3/4" line 2-CH-275 , 1 , 2-RC-P-1B 2"-CH-415-1502-Q1 1st Flange 2 1 1/2"-CH-797-1502-Q1 1st Flange 1 3/4"-CH-773-1502-Q1 1st Flange 2 1" & 3/4" line 2-CH-298. 1 1" & 3/4" line 2-CH-299 1 2-RC-P-1C 2"-CH-416-1502-Q1 1st Flange' _2 l: 1 1/2"-CH-796-1502-Q1 1st Flange 1 L 3/4"-CH-774-1502-Q1 lat. Flange 2
- l 1" & 3/4" line 2-CH-321 1 1"-& 3/4".line 2-CH-322- 1 II. IMPRACTICAL CODE-REQUIREMENTS ISI. Class:1 System Hydrostatic-Test per IWB-5222
- Po~= 2500,psig .To =s 496F Test Pressure _= 2550 psig ISI Class 2 System Hydrostatic Test per IWC-5222 Pd = 2735 psig: Td' = 250F -
-Test Pressure.= 3419 psig III. BASIS-FOR RELIEF Pressurizing -t.he ~ piping listed above to the: pressures req'uire'd i by-Section_XI.will also pressurize the number one seal-of the '
l- reactor coolant pumps. ;This'could potentially damage the number.one seal. l'
^t N2-004d 2-74 Rev. 0 1990 o ,
. %/ . RELIEF REQUEST SPT-1 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 verify the integrity of these enmponeats.
NOTE: Similar relief was submitted by letter dated May 22, 1987, Serial No. 86-796A for Ncrth Anna Unit 1, and approved by NRC letter dated Jtly 17, 1987. If J(/~3 ,/
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1 O N2-004d 2-75 Rev. 0 1990
1 1 RELIEF REQUEST SPT-2 I.- IDENTIFICATION OF COMPONENTS 1 System. : Chemical and Volume Control (CH) I Components: Piping located on drawing 12050-CBM-095C-2, Sheet i 1 of 2, between the valves listed below. j i VALVES LINE 2-CH-341 and 2-CH-HCV-2311 2"-CH-468-1502-Q1 1 2-CH-358 and 2-CH-340 3"-CH-401-1502-Q1 ISI Class : 1 II. IMPRACTICAL CODE REQUIREMENTS System Hydrostatic Test per-IWB-5222. Po=2500 psig, To=496 F,- Test Pressure is 2550 psig per IWB-5222. III. BASIS FOR RELIEF : [ - Check' valves 2-CH-343 and 2-CH-358 prevent the components l'3 listed above from b;;4 7 pressurized to Section XI requirements
~
L without pressurizin, t.ra. reactor coolant system. The code required test pressure of-2550.psig will overpressurize the reactor coolant' system. Also, the power operated relief valves (2-RC-PCV-2456 and 2- ;
.RC-PCV-2455C). of the reactor coolant system are designed to. '
limit the pressurizar pressure to a value below the fixed high-pressure reactor trip setpoint (2385 psig). The relief: Jvalve setpoints are 2335;psig. It is not desirable.to1take the reactor coolant system above the power operated relief valve =setpoint. IV. ALTERNATE TESTING , t 5As anLalternative, the reactor coolant system will'be' pressurized to a' pressure as'close as practical to 2335 psig. but not less than 2300 psig while the reactor is.in a shutdown condition in order to' seat check valves 2-CH-358 and 2-CH-341', 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. l O lN2-004d- 2-76 Rev. 0 1990 L.
e i f 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. !
't i
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.i N2-004d 2-77 Rev. 0 1990
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f y ls-) RELIEF REQUEST SPT-3 I. IDENTIFICATION OF COMPONENTS System : Residual Heat Removal (RH) Components: Piping located on drawing 12050-chm-094A-2, Sheet . 1 of 2, between the valves listed below. VALVES LIHE 2-RH-MOV-2701 & 14"-RH-401-1502 2-RH-MOV-2700 ISI Class : 1 II. IMPRACTICAL CODE REQUIREMENTS Class 1 System Hydrostatic Test IFB-5222. Po=2235 psig, To=650 F, Test pressure per IWB-5222 is 2280 psig. III. BASIS FOR RELIEF During the system hydrostatic test of the primary system, 2- ! RH-MOV-2700 and 2-RH-MOV-2701 are closed in order to prevent possible overpressurization of the residual heat removal system. Thus, the portion of the RHR system identified above cannot be pressurized with the primary system and due to system design, it cannot be pressurized without opening one of the MOVs.
- IV. ALTERNATE TESTING l As an alternative, the components listed above will be tested in accordance with IWC-5222 during the t.ydrostatic test l administered to line 14"-RH-402-602. The test pressure will be 584 psig as determined by the setpoint of relief valves 2-RH-RV-2721A and 2-RH-RV-2721B. This alternative is
( -considered sufficient since the relief valves are set at 467 ! psig. As a result, line 14"-RH-401-1502 should net see a l pressure.significantly higher than 467 psig. In addition, ! RH-MOV-2700.and 2-AH-MOV-2701 will not open if the reactor L coolant pressure-is 660 psig. I Relief was granted to North Anna Power Station Unit 1 per Safety Evaluation Report dated July 13, 1987 (TAC No. 64718) for the same Lituation described above. O b N2-004d 2-78 Rev. 0 1990
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, ( RELIEF REQUEST SPT-4 j
I. IDENTIFICATION OF COMPONENTS System : Safety Injection (SI) Components: Piping located on drawing 120$0-CBM-0968-2, Eheet 4 of 4, between the valves listed below. VALVES LINES
- 2-SI-92, 2-SI-90 and 2-SI-91 6"-SI-531-1502 2-SI-100, 2-SI-98 and 2-SI-99 6"-SI-533-1502 '
2-SI-106, 2-SI-104 and 2-SI-105 6"-SI-532-1502 2-SI-125, 2-SI-112 and 2-SI-123 6"-SI-416-1502 2"-SI-463-1502 2-SI-113, 2-SI-117 and 2-SI-111 6"-SI-419-1502 2"-SI-459-1502 , 2-SI-118, 2-SI-124 and 2-SI-116 6"-SI-421-1502 2"-SI-461-1502 3 ISI Class : 1 II. IMPRACTICAL CODE REQUIREMENTS Class 1 System Hydrostatic Test per IWB-5222. Po=2235 psig, , To=160 F, Test Pressure por 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'(2-RC-PCV-2456 and 2-RC-PCV-2455C) of the reactor coolant system are designed to limit the pressurizer pressure to a value below the fixed high-pressure reactor trip setpoint (2385 psig). The relief valve setpoints are 2335 psig which is below the test pressure of 2432 psig. It is not desirable to take the reactor coolant system above the power. operated relief valve setpoint. I N2-004d 2-79 Rev. 0 1990
l l h C RELIEF REQUEST SPT-4 CONTINUED IV. ALTERNATE TESTING I As an alternative, the reactor coolant system will be pressurized to a pressure as close as practical to 2335 psig ! but not less than 2300 psig while the reactor is in a shutdown condition 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. i I l l O l N2-004d 2-80 Rev. 0 1990 l _. . _ _ - _ . . . ~ - -
L l
' RELIEF REQUEST SPT-5 ; I. IDENTIFICATION OF COMPONENTS System : Chemical and Volume Control (CH) -i Components: Piping located on drawing 12050-CBM-095C-2, Sheet i 1 of 2, between the valves listed below.
VALVES LINES 2-CH-358, 2-CH-HCV-2311, 3/4"-CH-640-1502 and 2-CH-MOV-2289A 2"-CH-468-1502
. 3"-CH-401-1502 L
3"-CH-479-1502 3"-CH-819-1502 ) ISI' Class : 2 l j l II. . IMPRACTICAL CODE REQUIREMENTS Class 2 System Hydrostatic Test per IWC-5222. Since'there are ; no relief. valves for the above components, test pressure per ,
. IWC-5222 is 3419 psig.
III.- RASIS FOR RELIEF i Check Valves 2-CH-341, 2-CH-340 and 2-CH-358 prevent the components. listed above from being pressurized without pressurizing the reactor coolant system. The code required 4 test pressure of.3419 psig will overpressurize the reactor ..,
. coolant system. S l
Also, the power operated relief valves.(2-RC-PCV-2456 and i 2-RC-PCV-2445C) of the reactor coolant system are designed to-limit the pressuriser pressure to a value below the fixed high-pressure reactor trip setpoint (2385 psig). The relief l
. 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 presmirized to'a pressure as close as practical to 2335 psig but ..ot less than 2300 psig using a charging pump while the reactor is:in a shutdown condition to create a pressure.
boundary at check valves 2-CH-341 and 2-CH-358. The components listed above will then be tested to a pressure -!
) between 2300 psig and 2335 psig using a charging pump.
^
N2-004d 2-81 Rev. 0 1990
i i RELIEF REQUEST SPT-5 . CONTINUED I 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. t i T L t
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N2-004d 2-82 Rev. 0 1990 ~i
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I i RELIEF REQUEST SPT-6 I. IDENTIFICATION OF COMPONENTS System : Safety Injection Components: Piping and valves located on drawings 12050-CBM-096A, Sheet 2 of 3, and 12050-CBM-096B, Sheet 4 of 4, listed below. : I VALVE CONNECTING LINE VALVE < 2-SI-MOV-2890C and 10"-SI-418-1502 l
.2-SI-MOV-2890D 10"-SI-624-1502 to 6"-SI-533-1502 2-SI-91 1 to 6"-SI-532-1502 2-SI-105 '
to 6"-SI-531-1502 2-SI-99 2-SI-MOV-2890A 10"-SI-415-1502 + to 6"-SI-416-1502 2-SI-112 ' to G"-SI-419-1502 2-SI-117 to 6"-SI-530-1502 2-SI-214 to 6"-SI-421-1502 L[ 1, 2-SI-MOV-2890B 10"-SI-540-1502 t to 6"-SI-421-1502 2-SI-124 2-SI-89 2"-SI-451-1502 2-SI-90 > 2-SI-97 2"-SI-453-1502 2-SI-98 2-SI-103 2"-SI-455-1502 2-SI-104 , ISI Class : 2 L' II. IMPRACTICAL CODE REQUIREMENTS '.1 L Class 2 System Hydrostatic Test per IWC-5222. Pd = 2485 psig, ' Design Temperature.is less than'200 F, Test pressure is 2733.5 psig. i III. BASIS FOR RELIEF i Check valves 2-SI-92, 2-SI-100, 2-SI-106, 2-SI-125, 2-SI-113 i
'and-2-SI-118' 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. L l N2,004d 2-83 Rev. 0 1990 1
RELIEF REQUEST SPT-6 CONTINUED The power operated relief valves (2-RC-PCV-2456 and 2-RC-PCV- , 2455C) of the reactor coolant system are designed to limit the ! pressuriser pressure to a value below the fixed high-pressure ' reactor trip setpoint (2385 psig). The relief valve setpoints , are 2335 psig which is below the test pressure of 2733.5 psig. It is not desirable to take the reactor coolant system above . , the power operated relief valve setpoint. - IV. ALTERNATE TESTING As an alternative, the reactor coolant system will be pressurized to a. pressure as close as practical to 2335 psig . but not'less than 2300 psig while the reactor is in a shutdown condition to create a pressure boundary at check valves 2-SI- ; 92, 2-SI-100,.2-SI-106, 2-SI-125, 2-SI-113 and 2-SI-118. i These components will then be tested to a pressure between 2300 psig and 2335 psig using a test pump. i NOTES- 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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' N2-004d 2-84 Rev. 0 1990 m .n w w, .- -
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RELIEF REQUEST SPT-7 I. IDENTIFICATION OF COMPONENTS System : Safety Injection (SI) l Componentst Piping located on drawings 12050-CBM-0968-2, J Sheets 1 of 4, 2 of 4 and 3 of 4, between the sets of valves listed below. VALVES LINE NUMBERS 2-SI-MOV-2865A, 2-SI-151 12"-81-523-1502 ; and 2-SI-149 3/4"-SI-478-1502 2-SI-MOV-28658, 2-SI-168 12"-SI-524-1502 ! and 2-SI-166 3/4"-SI-484-1502 , 2-SI-MOV-2865C, 2-SI-185 12"-SI-525-1502. , and 2-SI-183 3/4"-SI-480-1502 ISI Class : 2 II. IMPRACTICAL CODE REQUIREMENTS , i class 2 System Hydrostatic Test per IWC-5222. Pa=2485 psig, T=200_F, Test pressure per the code is 2733.5 psIg since there is no overpressure protection.for the above components. III. BASIS FOR REQUEST ,, 1 Check valves 2-SI-151, 2-SI-1CS, and 2-SI-185 at the Class 1 and 2 system boundaries prevent the pressurization of the above components without pressurizing the primary system. The , required test pressure is 2733.5 psig as stated above, which would overpressurize the primary system. l 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. l Thus, testing per IWB-5222 would require a test pressure of ' L 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. , i N2-004d 2-85 Rev. 0 1990
) RELIEF REQUEST SPT-8 i
I. IDENTIFICATION OF COMPONENTS l Systems : Main Steam (SHP) Decay Heat Release (SPNV) l Feedwater (WFPD)
- Chemical Feed (CFPD & SGD) '
Blowdown (WGCB) Sampling (SS) i components: Secondary side of the Steam Generators and , attached piping located on drawings 12050-CBM- t 070B-2, Sheet 1 of 3, 2 of 3, and 3 of 3; 12050- , CBM-074A-2, Sheet 1 of 3; 12050-CBM-089B, Sheet 3 of 4; 12050-CBM-098A, Sheet 2 of 5; 12050-CBM-102A-2, Sheet 2 of 2; and 12050-CBM-1028-2, Sheet 1 of 1 between the components listed in Table SPT-8. l ISI class 2 II. IMPRACTICAL CODE REQUIREMENTS : [ Class 2 Hydrostati'c Test per IWC-5222 and IWA-5213(d). For Feedwater components, dP =1100 psig, T d >200 F, test pressure For the Chemical Feed per IWC-5222 would be 1375 psig. components, Pd =1775 psig, Td<200 F, test pressure per IWC-5222 > would be 1952.5 psig. The remaining components have P d=1085
'psig, T >200 F, test pressure per IWC-5222 would be 1356 psig.
d i III. BASIS FOR REQUEST Westinghouse,.the manufacturer of the steam generators, gives specific testing requirements for the steam generator which must also be applied tc the components listed above because
- these components cannot be isolated from the steam generators..
- IV.- ALTERNATE TESTING l
The Westinghouse Technical Manual for the steam Generators ! l, requires the secondary side to be pressurized to 1356 psi
. held for 30. minutes and then reduced to design pressure (g, 1085: ;
psig) for a sufficient time to permit proper examination of walds, closures and surfaces for leakage or weeping.
.N2-034d 2-86 Rev. 0 1990 .
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- l. RELIEF REQUEST SPT-8 CONTINUED The secondary side will be held at 1356 psig for 30 minutes and then reduced to 1085 psig for a minimum of 3 1/2 hours in accordance with section XI. A VT-2 examination will then be performed on the components described in Table SPT-8.
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 l I l-
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l' l~ b i N2-004d 2-87 Rev. 0 1990 t
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Table SPT-8 - Components FROM TO COMPONENT CONNECTED PIPING COMPONENT l 4 2-RC-E-1A 32"-SHP-401-601 2-MS-SV-201A 1 to 32"-SHP-422-601 2-MS-SV-202A I 2-MS-SV-203A l 2-MS-SV-204A 2-MS-SV-205A 3 to 6"-SHP-437-601 & 1"-SHP-484-601 2-MS-PCV-201A I to 3"-SHP-464-601 & 2-MS-18 l
'1"-SHP-478-601 2-MS<335 I to 1 1/2"-SHPD-406-601 2-MS-?2 ]
to 1/2"-SHPD-471-601 2-MS-26 . 2-RC-E-17. 32"-SHP-401-601 2-MS-502 ] 2-NRV-MS-201A 3"-SHP-460-601 2-MS-344 1 2-RC-E-1A 32"-SHP-401-601 to 32"-SHP-422-601 to 3"-SHP-445-601 2-MS-344 to 3"-SHP-562-601 2-MS-NRV-203A to 1"-SHP-555-601 2-MS-346 t 2-MS-348 ', 2-RC-E-1A 2"-SS-620-601 & 1"-SS-753-601 2-SS-83 2-RC-E-1A' 32"-SHP-401-601 E to 32"-SHP-422-601 l to 3"-SDNV-401-601 to 4"-SDNV-404-601 2-MS-20. 2-RC-E-1A 16"-WFPD-424-601 2-FW-62 to 3"-WAPD-427-601 2-FW-70 i to 3/4"-CFPD-401-601 .2-WT-42 2-RC-E-1A 2"-WGCB-404-601 2-BD-4 2"-WGCB-405-601 2-BD-1 ] 1"-WGCB-406-601 2-BD-2 1 2-RC-E-1A 2"-SGD-404-601 2-WT-426 1^ N2-004d 2-88 Rev. 0 1990
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). RELIEF REQUEST SPT-8 Table SPT-8 Components CONTINUED i 1
i FROM TO COMPONENT CONNECTED PIPING COMPONENT 2-RC-E-1B 32"-SHP-402-601 to 32"-SHP-423-601 P-M3-SV-201B I + 2-MS-SV-202B 2-MS-SV-203B 2-MS-SV-204B 2-MS-SV-205B to 6"-SHP-438-601 & l 1"-SHP-485-601 2-MS-PCV-201B ! to 3"-SHP-465-601 2-MS-333 l 1"-SHP-480-601 2-MS-57 to 1 1/2"-SHPD-408-601 2-MS-60 to 1/2"-SHPD-473-601 2-MS-64 2-RC-E-1B 32"-SHP-402-601 2-MS-73 2-MS-NRV-201B l' 3"-SHP-461-601 2-MS-353 u .[
'v 2-RC-E-1B 32"-SHP-402-601 to 32"-SHP-423-601 l to 3"-SHP-446-601 2-MS-352 to 3"-SHP-461-601 2-MS-353 to 3"-SHP-563-601 2-MS-NRV-203B to 1"-SHP-503-601 2-MS-356 2-MS-357'
, ?-RC-E-1B- 2"-SS-625-601 & 1"-SS-754-601 2-SS-84. 2-RC-E-1B 32"-SHP-402-601 to 32"-SHP-423-601 to 3"-SDRV-402-601 to 4"-SDRV-404-601' 2-MS-20 1 2-RC-E-1B 16"-WFPD-423-601 2-FW-34 ' to-3"-WAPD-428-601 2-FW-192 to 3/4"-CFPD-402-601 2-WT-54
'2-RC-E-1B 2"-WGCB-407-601 2-BD-13 2"-WGCB-408-601 2-BD-10 2"-WGCB-409-601' 2-BD-11 2-RC-E-1B 2"-SGD-405 o01 2-WT-427 N2-004d' 2-89 Rev. 0 1990
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i RELIEF REQUEST SPT+8 Table SPT-8 Components CONTINUED FROM TO COMPONENT CONNECTED PIPING COMPONENT 2-RC-E-1C 32"-SHP-403-601 to 32"-SHP-424-601 2-MS-SV-201C 2-MS-SV-202C 2-MS-SV-203C 2-MS-SV-204C
, 2-MS-SV-205C to 6"-SHP-439-601 &
1"-SHP-486-601 2-MS-PCV-201C to 3"-SHP-466-601 & 2-MS-95 1"-SHP-482-601 2-MS-331 to 1 1/2"-SHPD-407-601 2-MS-98 to 1/2"-SHPD-475-601 2-MS-102 2-RC-E-1C 32"-SHP-403-601 2-MS-111 2-MS-NRV-201C 3"-SHP-462-601 2-MS-362 2-RC-E-1C 32"-SHP-403-601
.to 32"-SHP-424-601 to 3"-SHP-447-601 2-MS-TV-213C to 3"-SHP-462-601 2-MS-362 to 3"-SHP-564-601 2-MS-NRV-203C to=1"-SHP-504-601 & 2-MS-366 1"-SHP-557-601 2-MS-365 2-RC-E-1C 2"-SS-627-601 1"-SS-755-601 2-SS-85 2-RC-E-1C 32"-SHP-403-601 to 32"-SHP-424-601 to 3"-SDNV-403-601 to 4"-SDNV-404-601 P-MS-20 2-RC-E-1C 16"-WFPD-422-601 .
2-FW-126 to 3"-WAPD-429-601 2-FW-134 to 3/4"-CFPD-403-601 2-WT-70 2-RC-E-1C 2"-WGCB-410-601 2-BD-22 2"-WGCB-411-601 2-BD-19 1"-WGCB-412-601 2-BD-20 2-RC-E-1C 2"-SGD-405-601 2-WT-428 N2-004d- 2-90 Rev. 0 1990
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( ) RELIEF REQUEST SPT-9 l I. IDENTIFICATION OF COMPONENTS I System Feedwater (WAPD) ; Components: Piping located on drawing 12050-CBM-074A-2, Sheets 1 of 3 and 3 Of 3, between the valves listed below. VALVE CONNECTING LINES YALEE 2-FW-64 3"-WAPD-410-601 to 3"-WAPD-409-601 2-FW-66 2-FW-66 3"-WAPD-409-601 2-FW-70 2-FW-93 3"-WAPD-412-601 ) to 3"-WAPD-411-601- 2-FW-98 ' 2-FW-98 3"-WAPD-411-601 2-FW-102 I 2-FW-128 3"-WAPD-414-601 r N- te-3"-WAPD-413-601 2-FW-130 a,j ' 2-FW-130 3"-WAPD-413-601 2-FW-134 2-FW-278 4"-WAPD-439-601 to 3"-WAPD-409-601 2-FW-66 ; ISI Class : 3 II. IMPRACTICAL CODE REQUIREMENTS Class 3-System-Hydrostatic Test per IWD-5223 and IWA-5213(d). Pd =1400 psig, Td < 200 F, Test Pressure is 1540 psig per-IWD-5223.
-i III.- BASIS FOR RELIEF Due to check valves 2-FW-134, 2-FW-102, and 2-FW-70, the piping listed above cannot be' pressurized without pressurizing -!
the steam generators. The code required test pressure-of 1540 , psig would overpressurize the steam generators.
-N2-004d 2-91 Rev. 0 1990 e e- i . - - - . ,. ...m.. --.--m..-~-.... .-,~---..-,f. w v.. . - , - - - ---*'- - - e
_ . - . . . . . _ _ . . ~ _ _ _ _ . _ _._. _ -_ - - _ _.__. _ __... _ _ _ _ _ _ _ I RELIEF REQUEST SPT-9 ! CONTINUED IV. ALTERNATE TESTING Since the components listed above cannot be pressurized
- without pressurizing the steam generators, they must be testr.d per the required manufacturer's hydrostatic test method.
Therefore,.the proposed alternative examination is the ' examination described in the Westinghouse Technical Manual for the secondary side of the steam generators. The examination is to pressurize the secondary side of the steam generators to ; 1356 psig,. hold for 30 minutes, and then reduce to the design r pressure (1085 psig) for 3 1/2 hours. A VT-2 examination will : then be performed. 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. l l^ ., 2 [
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N2-004d- 2-92 Rev. 0 1990
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1 l ll RELIEF REQUEST SPT-10 I. IDENTIFICATION OF COMPONENTS System : Component Cooling (CC), Chemical and Volume Control (CH), Fuel Pit Cooling (FC), Safety ; Injection (SI), Quench Spray (QS), Recirculation Spray (RS), Service Water (WS) and Sampling (SS). Components: All piping and components included in the system hydrostatic test boundaries ' ISI class : 1,.2 and 3 II. IMPRACTICAL CODE REQUIREMENTS i Per IWA-5265(b)..."the imposed pressure on any component, l including static head, will not exceed 106% of the specified test pressure for the system." . III. BASIS FOR RELIEF i Portions of the above systems not capable of beiwg isolated E within.the system hydrostatic test boundary are located , throughout the plant. Certain:non-isolatable portions of the , o above systems have variations in elevation within the t boundaries that would result in imposed pressures in excess of six percent of the specified test pressure. It is Virginia Electric and Power Company's desire to limit the test pressure imposed on system components to 106% of the specified test pressure l(as required by paragraph IWA-5265(b)). Thus, due to- 1 the effects of static head, portions of the piping at higher ; elevations!will be subjected to a test pressure lower than h that specified.- There is no practical method for isolating
.the piping segments to achieve the required. test pressure at >
all elevations. LIV. -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: Sibilar' 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. N2-004d 2 Rev. 0 1990
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I RELIEF REQUEST SPT-11 I. IDENTIFICATION OF COMPONENTS System : Reactor Coolant (RC) ; components: Partial Penetration Welds 9 Bottom of Reactor Vessel Bottom of Reactor Vessel ISI Class : 1 II. IMPRACTICAL CODE REQUIREMENTS Section.XI of'the ASME Boiler and Pressure Vessel Code, 1986 Edition, Category B-E, Item No. 4.13, requires reactor vessel partial penetration welds to have a visual (VT-2) examination i during the system hydrostatic test of IWB-5222; in addition, Category B-P, Item Nos. B15.10, and 815.11 require a visual (VT-2) examination of the bottom of the reactor vessel during the system leakage test of IWB-5221 and during the system u hydrostatic test of IWB-5222, respectively. III. BASIS FOR RELIEF L In order to meet the Section XI pressure and temperature ; requirements for the system leakage and system hydrostatic r 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 i o breathing apparatus be worn for containment entries under these conditions. This requirement significantly complicates the visual (VT-2) examination of the bottom of the reactor vessel during testing. Access to the bottom of the reactor- 4 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 examiner is: limited R L to the approximate 30 minute capacity of the breathing
!. apparatus for containment entry, the VT-2 examination, and I. containment exit. 1 5 O j N2-004d 2-94 Rev. 0 1990 T w % w w .w..-..,,. , - . ,, , - . . - - - - , -.-w....-- ..---,--..,7- - - , , - - - , . - .-- m.
l O- RELIEF REQUEST SPT-11 CONTINUED IV. ALTERNATE TESTING Technical Specifications require that the Reactor Coolant System Leak Rate be limited to 1 gallon per minute unidentified leakage. This value is calculated at least once per 72 hours. Additionally the containment atmosphere particulate radioactivity is monitored every 12 hours. The incore sump room has an level alarm in the control room requiring operator action. These actions would identify any integrity concerns associated with this area. A VT-2 examination will be conducted when containment is at atmospheric conditions each refueling for evidence of boric acid corrosion. 4 O H2-004d 2-95 Rev. 0 1990 m- . . . . . . . , . . . , . . . , , . . , . . . . . . , , , , . . . . , . , , . . , . . . , . . . . . . , , . . . . . . . . . , , . , . . . , , . , , , , . . , . . . . .
i i
) RELIEF REQUEST SPT-12
- 1. IDENTIFICATION OF COMPONENTS i
System : Reactor Coolant (RC) Charging (CH) Safety Injection Components: Pressure Retaining Bolting ISI Class : 1 and 2 II. IMPRACTICAL CODE REQUIREMENTS Subparagraph IWA-5242(a) requires, for systems borated for the purposes of controlling reactivity, insulation shall be removed from pressure retaining bolted cos.5ections for visual examination VT-2. III. -BASIS FOR-RELIEF A majority of these systems are located in containment. In cases where there is no intermediate isolation from the !
'I reactor coolant system the system pressure test is performed o when the reactor coolant is greater than 500 degrees F and the !
!( containment is subatmospheric. Removing and reinstalling insulation under these conditions is difficult to perform and deemed impractical when compared to the existing VT-2 program. , IV. = ALTERNATIVE TESTING It is proposed that bolted connections on lines 3. inch NPS and larger on systems containing boric acid be examined each refueling outage. The examination would be performed with the # E insulation removed. This alternative only applies to systems that can only be pressur' tested under subatmospheric conditions. This alternative is already in place and goes beyond our. response to IE Bulletin 82-02, Degradation of Threaded *
- h. Fasteners in the Reactor Coolant Pressure Boundary of PWR- j Plants. In our response to IE Bulletin 82-02 we agreed to '
examine pressute retaining bolting on lines 4 inch NPS and <
. larger each refueling outage.. In addition our response to NRC. '
L . Generic. Letter 88-05,-Boric Acid Corrosion of Carbon Steel p Reactor Pressure Boundary Components in PWR Plants, we t committed to performing a visual-examination of all accessible ' portions of systems contain boric acid anytime the O N2-004d1 2-96 Rev. 0 1990 l-
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5 RELIEF REQUEST SPT412 CONTINUED unidentified leak rate exceeds a predetermined value, at every cold shutdown prior to decontaminating the containment, and during every reactor startup from Mode 5. In addition the Code required testing will still be conducted with a VT-2 < Examination without removing the insulation. { l l l 1 4
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a l RELIEF REQUEST SPT-13 I. IDENTIFICATION OF COMPONENTS System : Charging (CH) Safety Injection (SI) Quench Spray (QS) E Components: Pressure Retaining Bolting ISI Class : 2 II. IMPRACTICAL CODE REQUIREMENTS subparagraph IWA-5242(a) requires, for systems borated for the purposes of controlling reactivity, insulation shall' be removed:from pressure retaining bolted connections for visual examination VT-2.' III. BASIS FOR RELIEF Removing insulation and heat tracing can be detrimental to I. 'these components. In some areas the insulation covering
-bolted connections on these-systems is calcium silicate with.a solid ~ plaster exterior. This insulation cannot be removed without' damaging it.
The inventory of charging and safety injection is monitored as part of the Tech. Spec. requirements. When the reactor coolant leak rate exceeds a predeterrined level the system is walked down to identify the source ar.: a work request is' submitted to correct the-problem. Ar.. gross leakage:in inaccessible areas.would be detected by local radiation monitors.- A majority of thesw systems are located in accessible areas of the auxiliary building and yard, and are walked down each day by operators. A work request is submitted for any leakage noted by.the-operators. IV . - ALTERNATXVE TESTING It is proposed that current program of performing system ' pressure tests'each. period and system hydrostatic tests each interval be maintained. These tests will be performed with the insulation in place. If evidence of leakage is detected the insulation will be removed until the source is located and corrected. o O N2-004d 2-98 Rev. 0 1990 f
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4 i b SECTION 3 TABLE OF CONTENTS SECTION 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 3-4 r 3.2 PROGRAM
SUMMARY
3-5 3.2.1 Inservice Inspection Program Summary 3-5 ' 3.3 INSERVICE INSPECTION PROGRAM
SUMMARY
TABLE - 3-6 ' r ISI Class 1, 2, and 3 Component Supports 3.4- COMPONENT SUPPORT RELIEF REQUESTS 3-10 I l l i i k, N2003 3-2 Rev. 0 1990 4
I i 1 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
.)
i XI of the ASME Boiler and Pressure Vessel Code, 1986 Edition except where these requirements have been determined to be impractical. Detailed relief requests for these impractical requirements are included.in Section 3.4. Programmatic modifications to Section XI l requirements are outlined in Sections 3.1.1 through 3.1.4. 3.1.1 This program does not cover inservice testing of. ) snubbers. Snubbers will be tested in accordance with Technical Specifications. 3.1.2 Component supports exempt from the examination requirements of IWF-2000 are those connected to components and items exempted from examination j under IWB-1220, IWC-1220, and IWD-2000. In addition, portions of supports that are ' incccessible by being encased in concrete, ; buried underground,.or encapsulated by guard pipe are also exempt from the examination
-requirements of IWF-2000. These exemptions are i 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 i 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. I N2003 3-3 Rev. 0 1990
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t v j 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 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
. f-f comprised of supports from each system-
\- (such as Main Steam,-Feedwater or RHR),
L where the individual sample sites 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 r within a system of similar design, function ' and service, the supports of only one of the multiple components are required to be examined. 1 (4) To the extent practical, the same supports selected for examination during the first ; p inspection interval shall be examined ; during each successive inspection intervel. ' L This sampling plan is excerpted from proposed Code _ Case WGCS 89-1(b). 1. 1 N2003 3-4 Rev. 0 1990 l l.
j j l l I l i [ 3.2 PROGRAM
SUMMARY
3.2.1 The Inservice Inspection Program Plan Summary for Component Supports is presented in Section 3.3 in a tabular format. The component supports I and associated requirements are listed in descending order according to Code Category and Item Numbers. The following information is included in the tables: A. Code Cateaory - The Section XI Examination Category as defined in Table IWF-2500-1 for l Class 1, 2 and 3 compe:ent 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. Part Examined - The Section XI description of the area to be examined. D. Examination Method - Lists the examination method required by Section XI. The abbreviation used is as follows: VIS'- Visual examination per IWA-2213
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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 the applicable Secticn XI figure for determining the volume of the compc.nent to ' be examined. G. Accentance Criteria - Lists the applicablo
. portion of Section XI for determining the .
acceptance criteria. i H. Relief--Recuest - References a specific-relief request: contained in Section-3.4. 2 l (G V N2003 3-5 Rev. 0 1990 ll
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3.3.1 Examination Category F-A, Platc And Shell Type Supports - Program Summary Table ALT. EXAM ITEM EXAM EXAM REQUIRED / ACCEPTANCE RELIEF NO. PARTS TO BE' EXAMINED METHOD METHOD FIG NO. CRITERIA REQUEST' F1.10 Mechanical connections to VIS, IWF-130'J-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 I
N2IWF 3-6 Rev. 0 1990
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W 3.3.2- Examination Category F-B,. Linear Type Supports AUT. EXAM ITEM EXAM . EXAM REQUIRE / ACCEPTANCE RELIEF NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REQUEST F2.10 Mechcnical connections to VIS, IWF-1300-1 IWF-3410 CS-1 pressure retaining components VT-3 and building structure F2.20 Weld connections to building VIS, IWF-1300-1 IWF-3410 CS-1 . structure VT-3 F2.30 Weld and mechanical connections VIS, IWF-1300-1 IWF-3410 CS-1 ; at intermediate joints in VT-3 multiconnected integral and nonintegral supports , i 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
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3.3.3 Examination' Category:F-C, ConFonent' Standard' Supports ALT. EXAM EXAM > EXAM REQUIRE / ACCEPTANCE RELIEF ' NO. PARTS TO BE EXAMINED METHOD METHOD FIG NO. CRITERIA REOUEST F3.10 Mechanical connections to- VIS, IWF-1300-1 IWF-3410 CS-l' pressureEretaining components'. - VT and building structure
-F3.20. Weld connections-to; VIS, IWF-1300-1 IWF-3410 CS-1 building structure VT-3 l F3.30 Weld and mechancial connections VIS, IWF-1300-1 IWF-3410 CS-1 '
.at-intermediate' joints i. 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-supports, assembly of support l
' items-F3.50 -Spring: type' supports, constant' VIS, IWF-1300-1 IWF-3410 CS-1 load type supports, shock 4 VT-3 absorbers,-hydraulic and-mechanica1-: type snubbers 4
N2IWF 8 Rev. O 1990
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r 3.4 COMPONENT SUPPORT , RELIEF REQUESTS i
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/~' l RELIEF REQUEST NO. CS-1
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I. IDENTIFICATION OF COMPONENTS ISI Class 1, 2 and 3 Component Supports TI. IMPRACTICAL CODE REQUIREMENTS 4 The nonexistent or unclear portions of Subsection IWF, ' Section XI 1986 Edition detailed in the BASIS FOR RELIEF section of this relief request. III.- BASIS FOR RELIEF Subsection IWF of the 19L6 Edition of Section Xi lacks a complete concise set of rules for-the incervice inspection of. component supports. The following areas in particular have been identified as needing clarification: SUPPORTS EXEMPT FROM EXAMINATION AND TEST a; 1 1IWP-1230'in.the 1986' Edition of Section'XI is "in-the courseiof preparation". The Section-XI Working Group on Component' Supports 1(WGCS) has developed proposed. Code Case i _ " '.('T WGCS 89-1(b)cwhich-includes a complete set of' exemptions in j
, f(,); Section 1230 (
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SUPPORTS SELECTED FOR EXAMINATION. ' IWF-2510(a)oin the'1986. Edition:of Section.XI. states:
" Component supports selected forJexamination shall;be the 1 supports of those components'that are. required to be' c "
examined'under?IWB, IWC, IWD and IWF during the first o'
" inspection 11nterval." LThese selectionerequirements aru
<Leonfusing in'that the;exemptionszfor these subsections have'
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.r . '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)nincludes lint section- 2510 a clear, detailed set' of' guidelines for.
examination.
; SAMPLING PROGRAM' LThe general' philosophy.of Section XI,has evolved'into a "r Jsampling;programlapproach where a percentage of l'ike-
@I' components are examined'to determine their suitability for-jj' . continued service.=LWGCS:89-1(b)-includes in Table 2500-l'a-specific sampling program-for supports. ' jr sf ,
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.N2-CSRR 3-10 Rev. 0 1990
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RELIEF REQUEST NO. CS-1 CONTINUED It is Virginia Electric and Power Company's position that ! the portions of WGCS-89-l'b) presented in the Alternate , Provisions section of this relief request in conjunction with Subsection IWF of the 1986 Edition of Section XI provide a complete, coherent and sound set of rules for the inservice' inspection of component supports. l IV.': ALTERNATE PROVISIONS q
- 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.fromEexamination under IWB-1220, IWC-1220, and u IWD-1200.. In= addition, portions of. supports-that are. "
-inaccessible by being encased in concrete, buried *]
underground, or encapsulated by guard pipe are also exempt
, from the examination. requirements of IWF-2000.
. SUPPORTS EXEMPT FROM EXAMINATION' l
L, In lieu or IWF-2510(a), the following will be used:- j I, Component supports to be. examined-shall'be the supports-of y' those components that'are required to be: examined under' j IWB-2500, IWC-2500,=and IWD-2500 by volumetric, surface;or3 0
? visual (VT-1 orL VT-3): examination' methods. Piping-supports-
-to be examined shall;be the. supports:of piping not exempted i under IWB-1220,.IWC-1220, and IWD-1220. ] ;
JIn conjunction withiTableLIWF-2500-1, Categories'F-A, F-B U and F-C the'following? sampling p1'an will.be used: ISI. Class-l' Piping Supports - Examine 25%fof. supports per'
-interval.'~ Notes,1, 2 and:4.'
1
'ISI? Classt 2 Piping Supports; ' Examine 15% of supports per-
= interval. Notes (1,12-and 4.
Si
'ISI?ClassL.3 Piping:- Supports Examine,10% of supports per' ~
9 interval.; . Notes l',;2:and 4.. ,
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' Supports Other!Than-Piping Supports . Examine 100% of' J supports;periinterval. Notes;3 and 4.- J
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RELIEF REQUEST NO. CS-1
,k CONTINUED NOTES:
c (1) Supports shall be categorized to identify support types by component support function (e.g., A = supports such as one directional r 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),
t 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 t andiservice, the supports of only one of: tha'anitiple components are required to be
. sy 3 examined.'
, )
c's;) . To the. extent practical,'the same supports A ! "= '(4 ) 'j selected'for-examination during the first " inspection!intervalishall'be examined l d .during'ench successive: inspection interval, t O' 1: 1; p,'I , l ' TW - 4 J , i l 5~ , J s . H . 4 i I / - h ? i . i ,- , i 3" O
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