ML18153B338

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Forwards ISI Program Relief Request SR-021 for Partial Exams Conducted During 1993 Surry Unit 2 Refueling Outage.W/One Oversize Drawing
ML18153B338
Person / Time
Site: Surry Dominion icon.png
Issue date: 10/08/1993
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18151A518 List:
References
93-608, NUDOCS 9310150178
Download: ML18153B338 (23)
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Text

{{#Wiki_filter:ACCELERATED DOCUMENT DISTRIBla(ION SYSTEM _, 1 REGULATC.- INFORMATION DISTRIBUTION.STEM (RIDS) ACCESSIO~ NBR:9310150178 DOC.DATE: 93/10/08 NOTARIZED: NO FACIL~50~2a1 Surry Power Station, Unit 2, Virginia Electric & Powe AUTH.NAME AUTHOR AFFILIATION STEWART,W.L. Virginia Power (Virginia Electric & Power Co.) RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) DOCKET# 05000281

SUBJECT:

Forwards ISI program Relief Request SR-021 for partial exams conducted during 1993 Surry Unit 2 refueling outage. R I D s I DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR _JENCL _j_ SIZE:-~~------1/....._~~ TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code 1 NOTES:lcy NMSS/SCDB/PM. RECIPIENT ID CODE/NAME PD2-2 LA BUCKLEY,B INTERNAL: ACRS NRR/DE/EMEB NUDOCS-ABSTRACT OGC/HDS2 RES/DSIR/EIB EXTERNAL: EG&G BROWN,B NRC PDR NOTES: NOTE TO ALL "RIDS" RECIPIENTS: COPIES LTTR ENCL 1 0 2 2 6 6 1 1 1 1 1 0 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD2-2 PD AEOD/DSP/ROAB NRR/EMCB ~~~CB iG(IL]} 01 EG&G RANSOME,C NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 0 1 1 1 PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 20 05000281 A D D s R' I D s I A D D s

L l e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 8, 1993 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen: VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM RELIEF REQUEST Serial No. NO/ETS Docket Nos. License Nos. 93-608 RO 50-281 DPR-37 Surry Power Station Unit 2 is presently in the third period of its second ten-year interval for inservice inspections. Examinations during this interval have been conducted to the requirements of the 1980 Edition and Winter 1980 Addenda of ASME Section XI. Pursuant to 1 O CFR 50.55a (g) 5, relief is requested from certain requirements of ASME Sec.1ion XI associated with partial examinations conducted during the 1993 Surry Unit 2 refueling outage. Relief request, RR-021, is provided detailing the basis of these requests. These relief requests have been reviewed and approved by the Station Nuclear Safety and Operating Committee. Should you have any additional questions or require additional information, please contact us. Very truly yours, Jt~c9 _(..--... -7* / ~'"' /~- 3::::.~,-----------. / '-..J W. L. Stewart Senior Vice President - Nuclear Attachments cc: U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station 1/0'f J

. r i. Surry Power Station Unit 2 ISi Examination Relief I

.l I.

11.

111. I Relief Request SR-021 Identification of Components Weld No. Line/Mark No. System Drawing Number Class 1-01 02-RC-R-1 RC 11548-WMKS-RC-R-1.2 1 1-10 31 "-RC-308-2501 R RC 11548-WMKS-RC-10-1 1 1-12 27.5"-RC-309-2501 R RC 11548-WMKS-RC-10-1 1 1-13 27.5"-RC-309-2501 R RC. 11548-WMKS-RC-10-1 1 1-14 27.5"-RC-309-2501 R RC 11548-WMKS-RC-10-1 1 1-22 29"-RC-307-2501 R RC 11548-WMKS-RC-10-1 1 2-02 02-RC-E-1A RC 11548-WMKS-RC-E-1 A.1 2 02-RC-E-18 11548-WMKS-RC-E-1 8.1 2 02-RC-E-1C 11548-WMKS-RC-E-1C.1 2 2-06 02-RC-E-1A RC 11548-WMKS-RC-E-1A.1 2 02-RC-E-1C 11548-WMKS-RC-E-1 C.1 2 1-A01 02-RH-E-1A RH 11548-WMKS-RH-E-1 A 2 1-801 02-RH-E-18 RH 11548-WMKS-RH-E-18 2 System Abbreviations RC - Reactor Coolant System RH - Residual Heat Removal System Impracticable Code Requirements The 1980 Edition, Winter 1980 Addenda (inclusive) of ASME Section XI in Tables IW8-2500-1 and IWC-2500-1 does not allow any limitations to the required volumetric and surface examinations. Code Case N-460 (Alternative Examination Coverage For Class 1 and Class 2 Welds) allows a reduction in coverage, if the reduction is less than 10%. Basis For relief The components listed above have been examined to the extent practicable as required by the Code. Due to interferences of other components or weld joint geometry the reduction in coverage for the listed components was greater than 10%. Tables SR-021-1, 2, 3, 4 and 5 are provided detailing the limitations experienced. Amplifying sketches or drawings are also provided. Alternative components could not be substituted for examination due to the mandatory

I selection requirements of the Code, or because the examination coverage attained was representative of what., could be expected for that type configuration. IV. Alternate provisions It is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements.

Weld No. 1-01 (0°-360°) Beam Angle 0 45 45 45 45 60 60 60 60 45 & 60 45 & 60 45 & 60 45 & 60 0 Exam Area Weld Weld Weld Weld Weld Weld Weld Weld Weld Base Base Base Base Base Table SR-021-1 SUrry ~ft 2 9£.l!l!!!!in!!t!m ~ E:tf=t= (lle=:to;- Veasel) category B-A. ltm B1.40 Scan Direction XExam Reason For Partial 2 5 7 8 2 5 7 8 2 5 7 8 97 28 97 97 97 14 97 97 97 36 96 84 84 84 Proximity to Flange and lifting Lug Interference. Lifting lugs are approximately 511 in width. Sketch/Drawing No. 1 11548-WMKS-RC-R-1.2

  • Estimates are based on 1991 and 1993 examination results. Earlier examination results (Period 1) occurred prior to our procedures requiring specific scan coverage percentages. The examination reports indicated what caused limitations, but not the degree of limitation by scan.

UT Scan D1rect1on Det1n1t1ons. 2 - Axial scan flange side of weld 5 - Axial scan head side of weld 7 - Circunferential scan, clockwise (looking down on head) 8 - Circunferential scan. couiterclockwise (looking down on head) e

Table sa-021-2 Slrry U,ft 2 EJuainatfan Coverage Estf*tes (Pfpins> UT Scan Coverage X Weld No. Category Item No. 2 5 7 8 Reason For Partial Sketch/Drawing No. 1*10 B*J B9.11 100 60 100 100 Pipe to elbow Jofnt 2 configuration. 11548*WMKS*RC*10*1 1*12 B*J B9.11 56 86 100 100 Pipe to Reactor 3 Coolant~ config* 11548-WMKS*RC-10*1 uretion. 2t Calibre* tion 1chlved IIIDXflllll coverage practicable. e 1*13 B*J B9.11 86 56 100 100 Pipe to valve conflg* 3 uretlon. 2t callbr1* 11548-WMKS*RC-10*1 tlon achieved 1111xt111111 coverage practicable. 1*14 B*J B9.11 56 86 100 100 Pipe to valve conflg* 3 uretfon. 2t calibre* 11548*WMKS*RC*10*1 tion tchfeved 11axi111111 coverage practicable. 1-22 B*J B9.11 98.6 61 100 100 Valve to elbow conflg* 4A/4B uretlon. 11548*WMKS*RC*10*1

lleld No. 2-02 (0°-360°) Beam Angle 0 45 45 45 45 60 60 60 60 Table SR-021-3 SUrry lhit 2

  • Ex*ination ~

Estil!:stes (Sts-Gei1ea~aturi category C-A, ltea C1.30 Exam Area Seen Direction XExam lleld & Base 96 lleld & Base 2 96 lleld & Base 5 80 lleld & Base 7 96 lleld & Base 8 96 lleld & Base 2 96 lleld & Base 5 80 lleld & Base 7 96 lleld & Base 8 96 Reason For Partial Sketch/Drawing No. Handholes, 1154S*"'4KS*RC-E*1A.1 blowdown piping, 11548*"'4KS*RC-E*1B.1 end nozzles 1154S*11MKS*RC-E*1C.1

  • Estimates ere based on 1988 end 1993 examination results. Earlier examination results (Period 1) occurred prior to our procedures requiring specific scan coverage percentages. The examination reports indicated what caused limitations, but not the degree of limitation by scan.

UT Scan Direction Definitions. 2 - Axial scan tube sheet side of weld 5 - Axial scan shell side of weld 7 - Circumferential scan, clockwise 8 - Circumferential scan, counterclockwise Steam Generator 11A11 1983 Examined 21 11 - 14411 Steam Generator 11811 1988 Examined 14411

  • 28411 Steam generator 11c11 1993 Examined 28411

- 21 11 e

Weld No. Beam Angle 0 45 & 60 45 & 60 45 & 60 45 & 60 Table SR-021-4 Slrry lklit 2

  • Exaination Coverage Esti*tes (Stea Gener!!tor) category C-A. ltea C1.10 Exam Area Scan Direction XExam Weld & Base 96.4 Weld & Base 2

96 Weld & Base 5 82.8 Weld, Base 1 96.4 Weld & Base 8 96.4 Reason For Partial Sketch/Drawing No. Insulation supports. 11548*WMKS*RC*E*1A.1 welded pads, 11548-MMKS*RC*E*1C.1 and nozzles

  • Estimates are based on 1991 ind 1993 examination.results. Earlier ex11111ination results (Period 1) occurred prior to our procedures requiring specific scan coverage percentages. The examination reports indicated what caused limitations, but not the degree of limitation by scan.

UT Scan Direction Definitions. 2

  • Axial scan transition side of weld 5 - Axial scan shell side of weld 7
  • Circllllferential scan, clockwise 8 - Circllllferential scan, counterclockwise Steam Generator 11A11 1983 Examined 011 - 18411 Steam Generator 11c11 1991 Examined 18411

- 36911 Stearn generator 11c11 1993 Examined 36811 - 55211 e

Weld No. 1 *A01/ 1-801 (0°-360°) Beam Angle 45 45 45 45 Table SR-021-5 Slrry ltli t 2 '*Exaaination Coverage Estimtes (RH heat Exchareer> category C-A. I tea C1.20 Exam Area Scan Direction XExam Reason For Partial Weld & Base 2 62 welded supports, Weld & Base 5 54.5 and nozzles. Weld & Base 7 62 Weld & Base B 62 Sketch/Drawing No. 11548*WMKS*RH*E*1A 11548*WMKS*RH*E*1B

  • Earlier examination results (Period 1) occurred prior to our procedures requiring specific scan coverage percentages. The examination reports indicated what caused limitations, but not the degree of limitation by seen. An extended beam bath was used to increase coverage.

UT Scan Direction Definitions. 2

  • Axial seen bottom side of weld 5
  • Axial seen top side of weld 7 - Circ1.111ferentlel seen, clockwise B
  • Circ1.111ferentiel seen, counterclockwise 02*RH-E-1A "Yeld 1*/\\01 11 1988 Examined 44n - 8811 02*RH*E*1B "Weld 1*B01" 1986 Examined 011
  • 44 11 02*RH*E*1B "Weld 1*901 11 1993 Examined 8811
  • 011 e

I F E D C B A 8 7 6 5 8 Ar JA SHRO!JD SUPPOq; T 05SEM8L Y 1HEAO TO FLANGE __ -CLO~t':~~~t-10 1~5~,E :;A-508 CLr>SS 21 -VESSEL VENT SEE NOTE I ELEVATION VIEW - REACTOr? VESSEL HEAD I 4.06" I _J_ CONlROL ROD TUBE IASME 58-1671 SECTION 8-B TYPICAL CONTROL ROD DRIVE HOUSING '- TYPICAL CONTROL ROO DRIVE HOUSING WELD .655" TrlJCK WELD 14TFl RE<CTOR VESSEL HEAD*,. f 314' - I~ NUTS SA-lq4 GRADE 2H IJ PER CLAMP> I P~RTIAL CLADDll,G,- SECTION C-C TYPICALCROMHDUSING HCflD PENETRATION ' fF.tlE TRA 1 ION WELD DETAIL I TYPICAL MARMON CLAMP !HOUSINGS 51,53,55,571 J"*Ml.fl~ 10:.1.:, IJ1.t17 n~n1:(,r-r;,r;a;,1r,rr.r.*i,~;,.(1r;*1 4 REACTOII VESSEL STUD LOCATION T YPJCAL 58 PLACES 3 2 F E -*210*- SECTION A-A TOP VIEW-REACTOrl VESSEL HEAD CONTROL ROD ORIVE HOUSING WELD LOCATIONS 314' - 10 CAP SCREWS SA-1q3 GRADE 8-7 13 PER CLAMPI ~ VIRGINIA POWER 'f{JI/I NORTH CAROLINA POW_~E~R::::-;-,:;:;,--~~~~~---1 POW[R E~INEER!l<G Sc'.RVICES RIC>MHl,VIRCINIA INSERV!CE INSPECTION DETAIL DRAWING REACTOR VESSEL HEAD & CROM WELDS D C. B SURRY POWER STATION UNIT 2 A VIRGINIA POW~E_R _____ 1 DSQI SI.PY.~V-CAD "'1:J. R(R0"0102 SCAC.C NONE lH..ESs OIH(RWISE JriiCJTED 2

F E D C B 8 TO 11548 -wms-010001 J0"-5HP*J01*601* 16" FEEDWATE NOZZLE 2*07 LOWER SHELL-----<- 8ARRELS ASHE SA*533 QR. A CL. I STUB BARREL ASHE SA*SJJ GR. A CL. I TUBE SHEET---- ASHE SA*508 CLASS 2 INTEQRALL Y CAST - SuPPORT PAD ITYPICAL Of 41 7 CH J.62"T cs 113.5' J.62"T cs I cs J.68"T 76.75° cs 1Ja* "' 2.e~*r cs 2.a2*T 138" INTEGRALLY CAST NOZZLE ITYPICAL OF 21 GENERAL ELEVATION A 0J*SEP* lqq2 14107 ZCi51 [ 3~5. 002]RCEBB0 IA I. OGN 6 /""/.:;z1/I"" A5fi4E SA*508 CLASS Z / LIFT11~PI~~~ 3:* ;~ICK 5 16' 10 SECONDARY HANWAY 20 80LTS 1.25' OIA. 8' LENGTH !TYPICAL OF' 2J IPPER SHELL BARRELS ASHE 5A-5JJ GR. A CL, I STEAM GENERATOR 2-RC- _k!L 16' MANW'Ai 1& e111s,.es* "~A. fTYPICAL OF 21 SEE BC"TOM VIEW 4 BOBC I CL *""NWAY I 16 SOL TS 1.aa*o1A. REVISED PEA ISi REVIEW 3 E P60-J !E I i I 2 J1*-At *3~2-2501A* <CROSSOVER LEQI TO 11548

  • W,..k'S*P'.:-12-1 lOE*JI PAD*4
  • -*-*-*--------4------------*

INITIAL ISSUE I I I I 0 zq*-RC-301*2':BIR* ........... PAO-I.. IHOTLEGI BOTTOM VIEW e SEE 11548-WMKS-RC-E-IA,2 FOR DETAILS ANO SECTIONS. VIRGINIA POWER NORTH CAROLINA POWER II.Cl.EM EICllOEERIICl SERVICES RICHOCJ,YIRGl~IA INSERVICE INSPECTION DETAIL DRAWING STEAM GENERATOR: 2-RC-E-IA SURRY POWER STATION UNIT 2 VIRGINIA POWER RCE0001AI !,N.(SS 01.<<.. ISE ICJ1[0 SH I DJ 2 2 F E D C B A

F E D C B A 8 7 ro 11~..cf C -'d,..i<~--Cl~!C'I -. r ICF'*71 I :e*-,"'*<C:-ec,-,... *~- 32*1~,:iz.:LE **-- UPPER HEAD n ~ n A~.:~ A =~~~f: _)-,.._-- ~ !=~.: ~ C.l.~PON STEEL

    • ,I' 3.62'T

,--,----CH-----.. 6 t-'AfH l£TEAH !IO;'.'.:LE n*:.l"E St.-50~ CLASS Z L:FTl~,(j :..*.*(j J.11;' T1-HO'

T tPl::::"iL OF 21 5

113.'5'

e:.* la !:ECO'l:ARY MO*IWAY 20 ROL TS I.ZS' C'!A. '3' L~ro:.:H IT'l'P!Ct>L !jF' LI J.E2'T 2 ----uPP[A 51-l[LL el.PS.EL$

---.1----'L--,-- CS ------j ASHE S..-533 GR. A CL, I FROH 11540

  • WM1(S*01"1GI ICF-31 16' F'EEOWA T[R -

NCZZcE llJ-5' 3.62"T _., 2 WELOEO Tflut11m~s IBD' i.PtloQT 112' OIA,I {B )TIO ~---t--cs J *//~

cs i 1~TION CO"-£ Ll::.Ga*r c9 I

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/ cs b I ~-c, ( ~ 1J0*

  • ---- Z WELOEO TRUNIOftS I -

1 ( 1e0* A~..:.Ar A....,. ,A Ill' CIA.I LCWER !t-ELL------- Bt.r.~ELS 2-04 ASME SA*533 C.R. A CL. l [EI] STUB BARPEL -------- ASME SA*533 GR. A CL. I INTEC,RALI.Y CAST -- SUPPORT P'-CJ <TYPICAL OF 41 INTEC,PALL f CAST ** NOZZLE IT YP!(AL GF 21 2.82'T cs 2.e2*r 138' cs J.2S'T 76' GENERAL ELEVATION STEAM ___ GENERATOR 2-RC- ..k!L / 6° SECONOAAY HANOHOLE / 8 BCL TS :.e0* CIA. (TYPICAL 0~ 21 / I,*C, I

  • ('4Cil-.tlfL H: AO 5.Z'T, St.~CrJ C!.i.;S.?

c.-.FiB')rJ SltL 16'Ml.",;WM 16 BCL TS 1.80' [JIA. n... '-':,.t.L or 21 SEE 90' TCI*' l!C.W' 4 3 ,:.J-3 E !E I I 2 I ~:*-:. :-::~:.-.F,:-;::i. ,cr.,;s;::,E~ LEG* "; ?1~4d .,...*,5.::.,:-1;-:

  • -*-*-*-*-*-*--~----*-*-*-*-*

eoec 1 CL**,~*-***, - - 0 16 e<JL rs 1.ee* oi.:.. PA0*2 ecec I.. _.....:.*,.:., I 16 B':L TS 1.88' DIA, I I BOTTOM VIEW I. 0 SEE 11548-'tl:-lKS-RC-E-IB.2 FDR DETAILS AND SECTIONS. VIRGINIA POWER NORTH CAROLINA POWER '"EVl~EO FE~ ISi '-EVIE" 2 F i l e I I D C B L...L...L...------------------------------------------------------'--*-------------------------------* 03-SEP-lqqz 14105 ZG5: C 3':,'3,e'02JRCE00018 I. [IGN

B F TO 11548

  • WMKS-010~D1 IOF-6, 7

J.62'f 6 /. HA:zir~AH ASH£ 5A*509 CLASS 2 LIFTING LUG 3.'5' THICK ITYPICtliL OF 2> 5 1------CH-----~ E D C B A 16' FEED WATER NOZZLE STUB BARREL ASME SA*5JJ GR. A CL. I 2-97 TUBE SHEET -------< ASHE SA*59B CLASS 2 INTEGRALLY CAST -- SUPPORT PAO ITYPICAL OF 4J INTEGRALL Y CAST NOZZLE CTYPICAL OF 2J 0J*SEP* lqqz 14132 ZG51 [ :?55.002JRCE0001C I.DUN 113.5' J.6Z'T UJ.5' J.62'T cs cs J.6B'T 76.75' cs 138' 2.82'T cs 2.B2'T 138' cs J.zs*r 76' F /2 J6* 10 SECO~ARY HANWAY 20 BOI. TS 1,25' DIA. 8' LENGTH lfYPJCAL OF 21 UPPER SHELL BARqELS ASME SA*SJJ GR. A CL. I /2 WELCEO TRUNIONS 189" APART IIG!t'OJA,1 2 WELDED TRUNIOUS 1Bir AFART urOIA.J STEAM GENERATOR 2-RC- __.£!£._ 6' SECONDARY HAIOO.E 8 BDL TS 1.011' DIA. !TYPICAL OF 21 ~HANNEL HEAD ~ SA508 CUI,$$ 2 ARBON sr!='EL 16' MAN\\ilAf GENERAL ELEVATION 1~T~~l!L *-ge* i,IA. SEE BOTTOM VIEW B08C CL-HANWAY 16 BDLTS 1.88' DIA. 4 REVISED PER ISi REVIEW I 3 !E I I 2 31'-RC*3C8-tSDIA-ICAOS50VER LEGI TO 115*9 -WHKS*RC*l0*1

  • --------------~-------------

INITIAL ISSUE n JH"5481

  • ""sfa:ie:1 I IDE-21 zq**RC-:!07-2501R*

OiOTLEGJ BOTTOM VIEW 8 SEE 11548-WMKS-RC-E-IC.2 FOR DETAILS AND SECTIONS. VIRGINIA POWER NORTH CAROLINA POWER II.a.EM [O,OfNEERIIC. SERVICES RICtMHJeYIROl"'IIA INSERVICE INSPECTION DETAIL DRAWING STEAM GENERATOR: 2-RC-E-lC SURRY POWER STATION UNIT 2 VIRGINIA POWER IPL [IOI 8Ak: 2 RCE9091CI DAA*UG trilO. Jl[Y, 11548-WMKS-RC-E-IC.I I IH.lSS GYHERWl5[ IGl[D 5M I DJ 2 F E e D C B A

8 $!£LL~~ 42' OD,62!1' THICIC ASTP1 A-240 GR 304 1e*-cc-q-121-SHEI L SIDE Ill.ET 151 CLASS 3A FROH 11!148

  • IIH1CS*BJ12ABI CeF*21 S1£LL ASTH A*24B GR 31!4 18'*CC*l!l*l21*

Sl£LL SIDE OUTLET ISi CLASS 3/1 TD 11!1411

  • IIHICS*B112AAI 19£*31 SHELL FLANGE ASTH A*IB2 FJB4 lll"*RH-188*602*

TUBE SIDE Ill.ET ISi CLASS 2A FRDl1 11548 I

  • 11KKS*B117Al*3 I

CaE*21 TLBE SIDE S1£LL ASTH A*24S TP 304 / .875 THICKNESS'.:......./ ELLIPTICAL HEAD 42'00 ASTH A*24B TP 3114 .875' THICKNESS ----' e 7 7 6 5 141

  • I !118' DIA. Hll.ES TYP, JH EACH SUPPORT Pt.ATE

{ TUBE SIDE l:AJTLETJ_. --- NDZnE REJNFORCl"G SADDlE ASTH A*241l TP JB4 CTYPICALI RESIDUAL HEAT REMOVAL EXCHANGER 2-RH-E-IA 11r-RH-1eq-6Bz-TUBE SIDE OUTLET ISi CLASS 2A SECTION A-A LOWER SUPPORT 4 3 SECTION C-C GUSSET DETAIL L, __ l~T .'l'REFERENC£ {TUBE SIDE / JIUT V 1rS01 41 !'--{ TUBE SIDE OUTLET ISi CLASS 2A DETAIL I ir SCH *1 TUBE SIDE NOZZLE WELD~ INIT JAL 1551£ 2 WENT COIH:CTIDN F. ISi SECTION B-8 lPPER SUPPORT ..... VIRGINIA POWER t<<lRTH CMll..lNA POWER l'OIIEII [ICJJl£MIIG SEAY la& IIIIMOCJ,YIAOIIIIII 13.14' 31191!" Tt*IEADED FIA.L CPI.GI JNSERVICE INSPECTION DETAIL DRAWING RESIDUAL HEAT REMOVAL HX:2-RH-E-lA SURRY POWER STATION UNIT 2 VIRGINIA POWER V-._........ 11548-VMICS-RH-E *IA 8 2 E D C B A e

C B B S1£LL !£AO 42' OD.625' TtllCIC ASTH A-248 GR 384 18'*CC*7*121* SHELL SIDE Ill.ET 1$1 CLASS 3A FROM 11549

  • WHICS*lll2SI laf-31 SHELL ASTH A-2411 GR 384 7

6 5 141

  • I 518' DIA. HOLES TTP. IN EAC>: 51.f'PORT Pt.ATE t TUBE SIDE OOTLETJ_.

NOZZLE REINFORCING SA011E ASTH A-248 JP 304 ITYPICALI RESIDUAL HEAT REMOVAL EXCHANGER 2-RH-E-18 _/_ SEE DETAIL I 'CE::::::::::::::::=:::::::::::=:::::::=::::=!.::.-- ---1 __ T_D_l_l5_49--, I

  • IIMCS*l!ll7Al*3 I

caE-61 I l!l"*Rll-llli!-682* I TIIIE SIDE OOTLET I ISi a.ASS 2A SECTION A-A LOWER SUPPORT 4 -~, 13" ll IIZ' g Sll'l'ORT I IIZ' Pl.ATE SECTION C-C GUSSET DETAIL I... ~ 1,-.n TREFERENCE {TlllE Sl!E V i,-.n II' SOt 41 I I t j---{ TLIIE SIDE WTLET ISi a.ASS 2A DETAIL I tr SCH 41 TUBE SIDE NOZZLE WELDS ISi Q.ASS 3A ,e, SECTION B-B lJ>PER SUPPORT .. VIRGINIA POWER W, NOOTH CMCLINA POWER PIIIIEA ENIIIEEAIIII SERYICES IIIOIOCl,'flllCIIIIIA ELLIPTICAL HEAD 42'DD ASTH A-248 TP 31l4 .875' THICKNESS ---J INSERVICE INSPECTION D:.;,..E-.-T-AI_L_D_R_A_W_IN_G_, RESIDUAL HEAT REMOVAL HX: 2-RH-E-lB A n------rr------rr------rr-------,rr-------,r-r------1 SURRY POWER STATION UNIT 2 VIRGINIA POWER INITIAL ISS~ gDIC), D'lll!IIIIJ tia. 11548-lrlMKS*RH*E-18 8 ..Un onoo1* IIDIDI.. I IF 2 7 2 E e D C B A

Reactor vessel Bea4 Wel4 1-01 45 DEGREE AND 60 DEGREE SCAN DIRECTIONS e WELD 1 Sketch 1

Reactor Coolant p~ Elbow I<!- 5 scan 2" 1/4" Weld 1-10 OD Line 3111-RC-308-2501R -l>I 2 scan D C F 3" 3.5" Exam. Vol. C-D-E-F l)"awlng ~t To Sc11Je Sketch 2 2 scan e 0.968" (1/3t) . I 1/4"

2.320 Welds 1-12, 1-13 & 1-14 OD Line 27%-RC-309-2501R The longer sound path wl 11 be the 2 scan for weld 1-12/1-14 and the 5 scan for weld 1-13. The shorter sound path wl 11 be the 5 scan for welds 1-12/1-14 and the 2 scan for weld 1-13. Sketch 3 2.3" Exam. Vol. C-0-E-F D-awl ~t To Scale 0 E Valve or Purp As l,ppl !cable 0.773 1/4" e

Valve t.OV-2594 5 scan 1/4" Weld 1-22 OD Line 2911-RC-307-2501R 2 scan D F E 5 1/4" 5 3/4" Ex11111. Vol. C-D-E-F lrawlng ft>t To Scale Sketch 4A 2 scan e

1. 090" (1/ Jt) 1/4"

Valve Side of Weld Weld 1-22 on Line 29"-RC-307-2501R Weld -i> 5 1/4" 2" <!- 6 Oclock Position On Pipe 0-awlng Not To Scale Sketch 4B 1)-aln Line Limits 2 Scan for 1. 41 of Tota I We Id. e

e OVERSIZE DOCUMENT PAGE PULLED SEE APERTURE CARDS NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS _..__I __ APERTURE CARD/ HARD COPY AVAILABLE FROM RECORDS AND REPORTS MANAGEMENT BRANCH

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