ML20086S152

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Forwards Rev 1 to Relief Request B-6,Rev 1 to Relief Request B-7 & Relief RequestB-8 to ISI Program
ML20086S152
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 07/27/1995
From: Terry C, Woodlan D
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TXX-95192, NUDOCS 9508010119
Download: ML20086S152 (21)
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Text

{{#Wiki_filter:_ _ _ _ _ _ _ _ _ o ' -. Log # TXX-95192 _P9 File # 10010.1 905.4 (clo) = = Ref. # 10CFR50.55a(g)(5)(111) 7I1 ELECTRIC July 27, 1995 C. Iance Terry GroepVketrenMent Naclear U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 [

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) UNIT 1 L DOCKET NO. 50 445 RELIEF REQUESTS TO THE UNIT 1 INSERVICE INSPECTION PROGRAM (1986 EDITION OF ASME CODE. SECTION XI, NO ADDENDA, INTERVAL START DATE: AUGUST 13, 1990 FIRST INTERVAL) REF:

1) NUREG 1482, " Guidelines for Inservice Testing at Nuclear Power Plants," April 1995
2) TU Electric letter logged TXX-92138, from William J. Cahill, Jr-. to the NRC, dated March 12, 1992
3) TU Electric letter logged TXX-93107, from William J. Cahill, Jr. to the NRC, dated March 15, 1993
4) NRC Letter " Evaluation of the First Ten Year Interval Inspection Requests for Relief for Comanche Peak Steam Electric Station. Unit 1 (TAC NO. M83125)." from William D. Beckner to C. Lance Terry, dated November 29, 1994
5) TU Electric letter logged TXX-94050, from William J. Cahill, Jr. to the NRC, dated March 1, 1994
6) NRC Letter " Evaluation of the First Ten Year Interval Inspection Requests for Relief for Comanche Peak Steam Electric Station, Unit 1 (TAC NO. MB9599)," from William D. Beckner to C. Lance Terry, dated February 14, 1995 Gentlemen:

TU Electric has determined that certain inspection requirements of Section XI of the ASME Code are impractical and is requesting relief in accordance with the requirements of 10CFR50.55a(g)(5)(iii). This request is consistent with the guidelines of draft NUREG 1482 (Reference 1). This transmittal submits relief requests B 6 Revision 1. B 7 Revision 1 and B 8 (Attachments 1, 2, and - 3 respectively). These relief requests have been implemented pending your

approval, i-Relief Requests B 6 Revision 0 was submitted to the NRC by References 2 and 3 l-and accepted by the NRC via Reference 4.

Relief Request B 7 Revision 0 was submitted to the NRC by Reference 5 and accepted by the NRC via Reference 6. I 9508010119 950727 ~ PDR ADDCK 05000445 Q PDR \\ Energy Plaza 1601 Bryan Street Dallas. Texas 75201 3411

w 'i' TXX 95192 -Page 2 of 2 'If'you have any questions, please contact Mr. Carl B. Corbin at (214) 812-8859. Sincerely, L C. L. Terry i 1 6E By: D. R. Woodlan Docket Licensing Manager i CBC:cc i Attachments -l c Mr. L. J. Callan, Region IV Mr. D. D. Chamberlain,' Region IV Mr. T. J. Polich. NRR J Mr. G. Bynog, TDLS l Resident Inspector, CPSES

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-Attachment 1 to TXX 95192 r 4 ['] RELIEF REQUEST v B-6 REVISION 1 1 l 1 A. Item (s) for which relief is requested: i i TBX 1300- 1 I TBX 1300-2 ) Reactor Vessel Closure Head i Head to Flange and Ring to Disc Welds Bs Item (s) Code Class: 1 i 1 C. Examination requirement from which relief is requested: The requirement for volumetric examination of 100% of the weld lengths as described in Table IWB-2500-1. Examination Category B-A. Item No.'s Bl.40 and Bl.21. Note 'Ihe CPSES ISI Plan requires that 1/3 of each of these welds be examined each inspection period. A relief request revision is processed j -(u) to document the specific limitations encountered during each j examination. 1 D. Basis for relief: 1 Interferences from the reactor head flange, shroud and lifting lugs preclude the complete ultrasonic examination of the volume required by Fig.'s IWB-2500-3 and IWB-2500-5 as applicable. Approximately 13% of the examination volume of weld TBX-1-1300-1 and 17% of the examination volume of weld TBX-1 1300-2 did not receive the full code required coverage during the first period examinations. Approximatley 15% of the examination volume of weld TBX-1-1300-1 and 17% of the examination volume of weld TBX-1-1300-2 did not receive the full code required coverage during the second period examinations. Best effort examinations were performed during each period with the following results. Full circumferential scan coverage was obtained for both welds. Axial scan coverage was achieved in one beam path direction with two different beam angles for approximately 99% of the examination volume of TBX-1-1300-1 and for approximately 97% of the examination volume of TBX-1-1300-2. See pages 3 through 9 for weld locations and examination area. conflgurations. s. Page 1 of 9 -l

l G(s.-- B-6 RELIEF REQUEST REVISION 1 (cont.) There were no recordable indications identified by the best effort volumetric examinations performed or by the required surface examination performed on TBX-1-1300-1. - E. Alternate examinations: None F. Anticipated impact on the overall level of plant quality and safety: None O I 1 O Page 2 of 9

~ RELIEF REQUEST NO. B-6 rev.1 page 3 of 9 WELD LOCATION i \\ G e Ch s --. g O

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RELIEF REQUEST NO. B-6 rev.1 page 5 of 9 WELD CONFIGURATION tJELD *l I D Tutt l i i I _ _.1.T 8t-t- 13 e. o, Rr rl.1_.. lL$ tne ftanu _' __. i. ..__ canscuE Eti t Alo, i 4 l i __ _ _{ R.V. C t o' usq_ Eta p__ Tx,Tsi-to, gv.0 Ec.J __ gy, i lo-2'- l ! fV i g i i K /\\ \\ \\ i- \\ l / 1 / ' l ~~ l\\- '- T~ N j ~~ i i T s. i / +l h 'g.. i g ~ l s 1 s g I. I 's \\ l i l _ _ _ _ l \\__d. u i j i i l l N s 1 i l \\\\ l i l \\ i / I l l \\ i I I \\ /j / (I l l l = _L . j. l / / I i I ___.______.___L_. ._____J i i ,[______..I i. i l l

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RELIEF REQUEST NO. B-6 rev.1 page 6 of 9 WELD CONFIGURATION I me is_. p u it i no. I i Tr ax - I - i soc eau q mg #2 -h- .j _ ---. 9--M pf9 EW; %1 i g,y ctagcgg33' HpAruA-i i 1 l s o-28-91 n I-3 l gg i i /

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RELIEF REQUEST NO. B-6 rev.1 page 8 of 9 l'st PERIOD RESULTS /- V WESTINGHOUSE NUCLEAR SERVICE DIVISION R S 2, INSPECTION SERVICES LIMITATION TO EXAMINATION N0 l TBX-t-UC0 AEV. / PLANT CGMANC//E PEAf UNIT SKETCH SYSTICoup A. V CLOSuff MEAD PROCEOURE N-ZSZ-210. ANo R. / /0~ A ~ T/ E X AMINER OATE LEVEL d RELATED TO: U/T X P/T MIT V/T ITEMISh / 1*I PROVICE GENER AL INFORM ATION TO DESCRIBE APPROXIMATE SIZE, LOCATION ANO TYPE OF LIMITATION. EX AM/ SCAN SURF ACE AREA ? -> OIRECTION 7 gy. M sur smer SUR 2 FLAN 6-E I I O I. 5

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i i NOTE: 8% of weld #1 not examineo using 45* 13% of weld #2 not examines using 45, angle pass 125' of welo #1 not examinee using 60, angle beam 175 of welo #2 not examines using 60, angle naam angle seam

RELIEF REQUEST NO. B-6 rev.1 page 9 of 9 2'nd PERIOD RESULTS WESTINGHOUSE NUCLEAR SERVICE DIVISION G INSPECTION SERVICES LIMITATION TO EXAMINATION t PLANT COMANCHE PEAK UNIT NO.1 SKETCH Tex 1 1300 REV.1 SYST./ COMP, R. V. CLOSURE HEAD PROCEDURE TX ISL210 REV. 2 - A, I. EXAMINER DATE 31295 y Slostff RELATED TO .1T X PT MT VT CENT, NO. 1.2. W PROYCE GEaIEAAL eWORMAT10ed TO DESORE APPRONMATE SEE. LOCAfloat Ass TYPE OF LaSTAT10el.. LNITATIONS ARE DUE TO FLANGE, SHROUD AND LIF'TWO LUG. SEE WELD PROFILE OSTA8eED AT 1RFO1 FOR EXAh854AT10BICOVERAGE PtOT wfLD # 1 '5% OF REQtMRED EXAMMATION VOLUME NOT EXAasseED 99% EXAMMEO wfTH THE 45 DEGREE ANO 80 CEOREE N AT LEAST Oe8E DMECTION 45 DEGREE 8% 8807 EXAmeWED. % DEGREE 15% NOT EXAMMED WELD # 2 17% OF REQUIRED EXAMMATION VOLUME h0T EXAhleeED 97% EXAMMED wfTH THE 45 DEGREE AND 00 DEGREE N AT LEAST ONE DRECTION. 1 45 DEGREE 11% NOT EXAMMED. 60 DEGREE t 7% NOT EXAMMED. i y w&L.D M E s3 c/toFk w /' EHR o u c w.A l I-3 -+ I Lu3 f l I ma p i a m J 1 II.ANGd L'Lof $7uy C{L *$ 554= Meta # 18 HOLF " A 2 .f;

' Attachment'2 to TXX 95192 ( RELIEF REQUEST B-7 REVISION 1 l A. Item for which relief is requested: TBX-1-3100 1 TBX-1-3100 1 1 4 TBX-1-3100 1 i TBX-1-3100 1 Steam generator tubesheet-to-channel head welds j l B. Item Code Class: i g C. Examination requirement from which relief is requested: ASME Section XI 1986 edition, no addenda. 'Ihe requirement for volumetric examination of 100% of each of the steam generator tubesheet-to-channel head welds as described in Table IWB-2500-1. Examination Category B-B. Item No. B2.40. Note: A relief request revision is processed to document the specific limitations encountered during the examination of each of the steam generators. l 1 D. Basis for relief: j Interference from the steam generator tube sheet flange configuration, welded insulation support pads and a welded component name tag ~ preclude the complete ultrasonic examination of the volume required by Fig. IWB-2500-6. Approximately 31% of the examination volume of weld TBX-1-3100 1 and approximately 37_% of the examination volume of weld TBX-1-3100-2-1 did not receive the full code required coverage. See pages 2 thru 7 for weld location and examination area configurations. E. Substitute examinations: None - however manufacturers shop volumetric exam records are available in permanent plant files. F. Anticipated impact on the overall level of plant quality and safety: None Page 1 of 7

RELIEF REQUEST NO. B-7 rev.1 page 2 of 7 WELD LOCATION O a e.' i E ~ ile.M bf W h l H re d is reested l E g, -= u v J M 88 " 8 w w g M ac 8 D 1 gR g H U 1 aj ( e* = r Ul / 9 a e hI n p' i m O !g s h s, Es I N b 2 9 5 2 8 l- ! !! 8 3 2 2 3 8 s = l g bEk k.$ I d gi;il!II 15III = li I si mE sE si N .: 44 AA 44 3t' ll!!!Ill h Edidid id g 4, I. O Im x-no w I

RELIEF REQUEST NO. B-7 rev.1 page 3 of 7 TBX-1-3100-1-1 RESULTS /~'g ( WESTINGHOUSE NUCLEAR SERVICE DIVISION INSPECTION SERVICES LIMITATION TO EXAMINATION puur C.OM ANC H s ffAM 1 TB 1-100 Re_v.1 UNIT SKETCH behm CNCLA foes lbI" SID bO. 3 PROCEDURE sysT/ coup exaumenhAU $wkh! -WDL >rA,,,, s t - s.n i unaon g RE LATED TO: U/T P/T MIT V/T ITEMts)- Wd I~ PMOVIDE GENERAL 180PORMATIO88 TO DESCRSE AMTIOKm4 ATE SIZE. LOCATION AND TWE OF UWITATION. i Flan 3c b 7 un sku.:t 0 ~ E. h h i d.10.9 %un m m L -~ - i MI 2 0.i'/o non s.tainws.o 60'_ 3170 na E.htum s c 't ILLosTARTsyc Outy i P. i.

RELIEE REQUEST NO. B-7 rev.1 page 4 of 7 TBX-1-3100-1-1 RESULTS WESTINGHOUSE NUCLEAR SERVICE DIVISION INSPECTION SERVICES LIMITATION TO EXAMINATION puuy Co m Autt4 r PEAK i T'RX I 31oo ta v.1 unrr susTcw sysTiconer $$ E

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RELIEF REQ' EST NO. B-7 rev.1 p^ge 5 cf 7 TCX-1-3100-2-1 RESULTS U p y w d ; g x g, g,[ ty l i:11 .PrePilE _of the, ErmaM ion Vo. lu me,_ j. 1 _ _ e C_onundhe i'ed. Urst " rinjr-TW3100 Rea.1 l '56m l(,eneMc

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RELIEF REQUEST NO. B-7 rev.1 page 7 of 7 TBX-t-3100-2-1 RESULTS 7 e a -l WESTINGHOUSE NUC1. EAR SERVICE DIVISION INSPECTION SERVICES LIMITATION TO EXAMINATION PLANT COMANCHE PEAK UNIT NO.1 SKETCH ex-1 3100 REV.1 SYST./CCh.P. STEAM GENERATOR NO. 2 PROCEDURE TX ISl-210 AEV. 2 EXAMINER /d DATE 3-11-95 / RELATE 0 TO-UT X PT WT VT

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21 PROVsOE GDIERAL INPC8tMATIOde TO DESCRIE APPROKIMATE SEE. LOCATION AND TYPE OP UMrfAT10N. 5 set = l x l i 1 N n ?.$ \\ \\ N__ y e.td 4 _. __ y __ q i \\i ti NJ l COOO 00Qb Q C ~.3 0 C 3 \\ 'NJ' C O G G a N. N N l l n 2 5* x 2.5* seSULATION 2SDE 6 5* x 3.5* 1.D. TAS 25" j P A03,13" APART 3me FROM 0* RIFEfWICE AROUNO WELD O' REF. IS CINTUE.seE OF COU> LEO MANWAY ALA. 2' x 2' GENERATOR SUPP' ORTS 38.7% OF TOTAL v0LUME NOT NSPECTED B25* APART 380* 38 7% NOT M5PECTID BYSO* SCAN 22.e% NOT NSPECTID SYA6' SCAN } q / 22.6% NOT NSPECTED BYO* SCAN

' Attachment 3 to TXX 95192 RELIEF REQUEST. B-8 A. Item (s) for which relief is requested: TBX-4200-5 Dissimilar Metal Nozzle to Elbow Weld B. Item (s) Code Class: 1 l C. Examination requirement from which relief is requested: The requirement for volumetric examination of 100% of the weld length as described in Table IWB-2500-1. Examination Category B-F. Item No. B5.70. I D. Basis for relief: The difficulties associated with ultrasonic examination of spun cast stainless steel material and the specific examination area geometry of this j steam generator primary nozzle to elbow weld precludes the complete ultrasonic examination of the volume required by Fig. IWB-2500-8. Approximately 15% of the examination volume did not receive the full code required coverage. A best effort examination was performed utilizing a longitudinal wave. Full circumferential scan coverage was obtained in 2 beam path directions. Axial scan coverage was achieved in two beam path directions for 85% of the examination volume and in one beam path direction for 100% of the examination volume (see pages 2 & 3). Other transducers and attempts to utilize a full V technique proved inaffective on the basic calibration block. There were no recordable indicatJons identified by the best effort volumetric examination or by the required surface examination performed. E. Alternate examinations: 1 None F. Anticipated impact on the overall level of plant quality and safety: None Page 1 of 3

~. / 'u J P HP N j b STEAM O ^ GENERATOR 6 's -s nr.:-4 eor -s atr. :-4z0: 2 1 - 8' _ p'6 7 9 '7 I 28 -5 REr. :-4ros c2 4 4. 3 -ac- -ce4 nr. :-4ea ,,.,3,.,e RED. EL. 3 is 27.s-ac-i-cas m REF.1-4203 g 29 - NC - t - 023 e C*** i ta REACTUR VESSEL LLICTRAffW Otf Cr~'d CTRIC flDTESiTHICKNESSES ARE MIN. VALL VALUES DESCRIPTION'LDOP 2 REACTOR COOLANT 7tj MATERIAL IS SA-351-CF8A T/SCHi(27.5)2.21', (29)2.33' J, ' Z o, Ul1IT 1 c3i.32a8 BRPi RC-1-520-001 ItiSERVICE It4SPECTIDt: LDCATIDil ISDMETRIC APPROVAL: T M/74 7-a s -90 FLOViH1-0250 T BX 4200 {REV.1 l7-23-90 i

l I 1 ,) RELIEF REQUEST NO. B-8 page 3 of 3 WESTINGHGUSE NUCLEAR SERVICE DIVISION INSPECTION SERVICES LIMITATION TO EXAMINATION PLANT COMANCHE PEAK UNIT NO.1 SKETCH *ex14200 REV.1 SYST.. COMP. LOOP 2 REACTOR COOLANT PR'OCEDURE ~X-ISI-211 REV.2 EXAMINER M, .d _ ' ' OATE 3-11 95 MLAftO TO vi X 77 MT VT

OENT. NO.

5 PROVIDS QUEEA&L IMPOARAADON TO DE404E APretoXhAAft SEZr LOCATIOsl AMD TYPE OF LBETAftoeL 15% OF NE REQUmtD EXAMMATION VOLUME IS NOT COVEMED se TWO SEAM PATH Oe'tECDONS. 100% OF NE REQUIMD DAMM ATiON VOLUME IS COVERfD W ONE BEAM PATH OMECDON. \\ v a 1 t i i e E l -et 9 s, ~. N a-s i N I N 1 I .N F, / m I \\ V [. a -}}

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