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{{#Wiki_filter:,s ) a n.k c, .,s UNITED STATES 74E[i NUCLEAR REGULATORY COMMISSION i REGION IV II k,,%))!p; f' f 611 RY AN PLAZA drive. suite 1000 ARLINCToN. TEXAS 76012
- f October 11, 1979 Docket No. 50-445/Rpt. 79-26 50-446/Rpt. 79-25 I.
1 MEMOPM DUM FOR: File THRU: W. C. Seidle, Chief, RC&ES Branch FROM: R. E. Hall, Chief, Engineering Support Section
SUBJECT:
ALl.EGATIONS REGARDING CONSTRUCTION DEFICIENCIES COMANCHE PEAK STATION, UNITS 1 & 2, DN 50-445; 50-446 At approximately 4:00 p.m. October 9, 1979, a former Brown & Root employee "valk.1-in" to the RIV of fice indicating that he had allegations regarding deficiencies in safety-related construction at Comanche Peak. During the ensuing interview, the following specific allegations were obtained: 1. In the Unit 1 Auxiliary Building at elevation 807, rebar was o=itted in four columns in the EA wall. This construction was co=pleted in early 1978, probably in March or April. The omission of a portion of the prescribed rebar was reported to him by his rebar General Foreman. He also indicated that a G&H or B&R engineer also was aware of the omission; however, he could not recall his name. (He agreed to call it to me if he could recall it.) 2. Also, in the Unit 1 Upper Auxiliary Building, the concrete slab poured for the ceiling above the elevation 832 level, in the area just before entry into Safecuards Building 1, had had a 20' x 20' honeycomb area C" which was exposed upon removal of forms. He was not aware of corrective action taken; however, he felt that it had simply been dry-packed. This placement was made in August or September of 1978. 3. In Unit 1 Containment, there had been a mixup in anchor bolts. He in-dicated that 3000 anchor bolts had been interchanged, so=e having been furnished by " Boston Made" and others by Southern Made." 4. Two unsupported general allegations were also made regarding general cracking of floor slab concrete in the plant buildings and omitted h horizontal tie rebar in the Unit 1 Contain=ent wall. Without specifics, [ h the alleger was advised that these could not be pursued, and that they did not appear significant from a safety viewpoint in any respect. i CMl 8512O20096 B51106 PDR FOIA PDR GARDEBD-59
Docket No. 50-445/Rpt. 79-26 j 50-446/Rpt. 79-25 October 11, 1979 1 The alleger indicated that he was not only contacting the NRC, but had already contacted, and planned to continue contacting, other agencies including OSHA with allegations within other jurisdictions. He did not indicate an intent to contact the press; however, this would not.ppear i unlikely. i, / ( _- / R. E. Hall, Chief Engineering Support Section ec: W. A. Crossman j R. G. Taylor i I 'l i h i 4 t i j i. N d 5
AC-26 =%j BrownffRoot.Inc. QUAUTY ASSURANCE DEPARTMENT !.....h. y:n % ~ b ' I b #* *
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9A RECORD NONCONFORMANCE REPORT (NCR) l b.i D EX ED [_ _ c 5 o"D pro;ECT cPsES ac8 No. as li9s aAce a2 unit, STRUCTURE SYSTEM COMPONENT TAGilo NU@htgg LOCATION oR ELEVATicN Rim No {201-4812-007 { Containment 81dg., Concrete 2 819'-846' N/A teiTREND (3) NONCONFORMING CONDITION l CATEGORY I II b b-b \\ 2323-SS-9 REV PARA 131 DOCJMENT VioLATEo: Cited specification states, "All concrete shall be consolidated by suitable means, and thoroughly worked around the reinforcement and embedded fixtures and into corners of forms." This specification was violated in 5 locations on the reactor containment #2 core walls in compartment # 4, pour No.201-4812-007, 6-21-79. See attachment # 1 for location of defectiv goncrete. S *" I h I b ps REac=:Ec er . e cATe i9, aE7v.w AP= Rov At ',1 ci D ATE Buddy Lamb I 3 / 3 / 80 / M m # a 4 M,, I s /i-b l 67: PAEPARED BY: e 181 O ATE: 41 1 ' 'fD SY: a 121 OATE. l Buddy Lamb 3 / 3 / 80 ' w p(/_ / A Z.f I J /5 /[G l (131 Disposition ASSIGNED To. tidt DUE DATE: list CORRECTIVE ACTION REoutST CAR NO,116) ASME CODE CLASS! D. C. Frankum 3 /18 /80 C Recuired 3 Not Recuired ~ Yes p o j t17I DISPoSITicN X REWORK REPAIR Ust ASIS SCRAP. Area 1: Previously dispositioned on NCR C-1824, Rev. 1. Area 2: See construction operation traveler CE-80-001-5500.' Area 3: See construction operation traveler CE-80-002-5500,- Area 4: See construction operation traveler CE-80-004-5500.' gg% h. Area 5: See construction operation traveler CE-80-003-55 l L OLAJi0 l3h/eo 12$0)uAfM/bi !sh ho (18) CONSTRUCTicN PEVIEW/APPAoVAL i(19s OATE. C REVIEW APPaoVAL ' (211 O ATE. (246 AN[EVIEW APPMoVAL; 612 s1 O ATE (221 ENG mEVfWIAPPRoV AL 's 31 O ATE. l M A. A. d 4.,. - /10/ 8 0 k/// C M LW ISO I (1 i 261 V EFIC ATICN 1331 REVARKS. I l u-Satisfactory ZUr1 satisfactory C Not Reo'd QA RECORD ~ '7 7) CA Cf ENGR INSPR. VERIFICATicN. I281 O ATE. RTN. OA REVIEW /A ~ n? u b A u slake s e,. sa..w i29s ANs ' CONCURRENCE 130sDATE t FILE No. l [j j,?' l ,( }f ~~ N' ' l' s J
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m /../ Y /,.i O c _. A CONSTRUCTION OPER ATION TRAVELER 35-1195 @CE-80-OOi-5500 @ EQUIPMENT NO. huNIT NO. @ QUANTITY @PAGEIOF4 TRAVECER NO. N/A 2 1 ACTIVITY DESCRIPTION Pour Sack or Lore Wall (AREFERENCE DR AWINGS Void and Henevcombed Areas v NCR-IB24 6 2 Area 2 SPEC./ PROC./ENG. INSTR. LOCATION SYSTEM See Attachment Reactor Buildirie. Unit #2 N/A M E* NA IMIM DATE W4/M DEPT.CNF L-ENG'N G O4 PREPARED BY DATE A QA/QC ENG' ANI' REVIEWED BY -- 7 N/A DATE ANI REVIEW QA/QC ENG ANI OP. NO. DEPT.' OPERATION 1 QC Inspect chipping of honeyemi,ed' and/or voided area (areas) to insure all honeymi+i concrete has been removed and chipping is in accordance with approved procedures. 2 35R Replace any rebar removed for chipping access. Civil 3 QC Verify all rebar is replaced. 4 B5R Install any required enbedments removed during chipping. Civil 5 QC Verify all required embedments are installed. 6 B5R Clean chipped area and install any'fomwork required at Civil this time. 7 QC Verify cleanliness. 8 B5R Install any remaining fomwork necessar. f ljk'[ Civil 9 QC Verify stability, line and grade, tightness of joints and proper concrete cover is maintained. 10 QC Review attached pour plan to insure planned pourback procedure will provide acceptable results. 11 QC Verify pour card sign off is complete and existing con-crete surfaces are properly prepared in accordance with approved procedures and/or engineering instmctions. 12 B5R Proceed with pourback in accordance wi*h attached pour Civil plan. 13 QC Operations 4 through 12 shall be repeated if multiple concrete lifts are required. 14 QC Verify pourback cc=pleted in accordance with attached pour plan.
/.. ^ s s. = CONSTRUCTION OPERATION TRAVELER 35-1195 TRAVELER NO. EQUIPMENT NO.- hNIT NO. @ QUANTITY @PAGE/ OF4 CE-80-oo2.-55co N/A 7 i ACTIVITY DESCRIPTION Four BaCK of t. ore Wall REFEPENCE DRAWINGS Void and Heneveombed Areas NCR-t924 Et e 2.. Area 3 SPEC./ PROC./ENG. INSTR. LOCATION SYSTEM gSeeAttachment Reactor Building, Unit #2 N/A PREPARED BY 2N#m U UMM DATE W /C DEPT.C' vfl N r N EDN6 NMM QA/QC ENG' ANI DATE REVIEWED BY / 1 N/A DATE ANI REVIEW QAM2C ~ O P. NO. DEPT. ' OPERATION ENG ANI Inspect cSipl ng of honeyW and/or' voided area (areas) ii 1 QC . to insure all honeycombed concrete has been removed and chipping is in accordance with approved procedures. ~ .5 2 B5R Replace any rebar removed for chipping access. Civil 3 QC Verify all rebar is replaced. 4 B5R Install any required embedments ' removed during chipping. Civil 5 QC Verify all required embedments are. installed. 'l 6 B5R Clean chipped area and install an9'formwork required at Civil this time.' 7 QC Verify cleanliness. 8 B5 Install any remaining formwrk necessarf. kNk$pg 9 QC Verify stability, line and grade, tightness of joints. and proper concrete cover is maintained. 10 QC Review attached pour plan to insure planned pourback procedure will provide acceptable results. i 11 QC Verify pour card sign off is complet and existing. con- : crete surfaces are properly prepared in accordance with ' approved procedures and/or engineering instructions. 12 B5R Proceed with pourback in accordance with attached potir Civil plan. 13 QC Operations 4 through 12 shall be repeated if multiple concrete lifts are required. 14 QC Verify pourback completed in accordance with attached pour plan.
i l p m. ', ' i CONSTRUCTION OPERATION TRAVELER 35-1195 @CE-80-cos-55co @ EQUlPMENT NO- - huNLT NO. @ QUANTITY. PAGE / OF4 TRAVELER NO. N/A 2 1 (h ACTIVITY DESCRIPTION Pour Back or Lore Wall (~ REFERENCE DRAWINGS V./ Void and Honevcombed Areas NCR-I624 Psv 2 Area 5 LOCATION SYSTEM g SPEC./ PROC./ENG. INSTR. See Attachment Reactor Euilding, Unit #2 N/A PREPAREO SY be* N i lM/ w DATE W/M DEPTC N N #'*LD M h DATE Ad QA/QC ENG ANI REVIEWED BY / ANI REVIEW N/A DATE QA/QC .t.. OP. NO. DEPT. OPERATION ENG ANI 1 QC Inspect c' hipping of honeyW and/or' voided area (areas) to insure all honeycombed concrete has been removed and chipping is in accordance with approved procedures. 2 B6R Replace any rebar removed for' ch' pping access. i Civil 3 QC Verify all rebar is replaced. 4 B5R Install any required embednents removed during chipping. Civil F
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QC Verify all required embedments aie installed. 1 -} 6 B6R Clean chipped area and. install any formark required at Civil this time.. 7 QC Verify cleanliness. 8 B6R Install any remaining forwork necessary. M N 0fM DN Om Civil i 9 QC Verify stability, line and grade, tightness of joints and proper cbncrete cover is maintained. 10 QC Review attached pour plan to insure planned pourback procedure will provide acceptable results. I 11 QC i ' y-ify pour card sign off is complete and existing con-: cete surfaces are properly prepared in accordance with * ( approved procedures and/or engineering instrtx:tions. 12 B6R Proc'eed with pourback in accordance with attached podr Civil plan. 13 QC Operations 4 through 12 shall be repeated if multiple concrete lifts are required. d 14 .QC Verify pourback completed in accordance with attached pour plan.
/ f f* CONSTRUCTION OPERATION TR AVELER 35-1195 @CE-80-ccxf-5Sco @ EQUIPMENT NO. @UNITNO. @ QUANTITY @PAGElCPt TRAVEtER NO. N/A 2 1 ACllVITY DESCRIPTION Four BaCK 01 t. Ore hall QREFERENCE DRAWINGS _ Void and Henevcombed Areas v NCR-1824 E< 2 Area 4 SPEC./ PROC./ ENG. INSTR. LOCATION SYSTEM See Attachment Reactor Buildine, Unit #2 N/A b = M l8d DATE 3 MIN DEPTC/WL EDd PREPARED BY b 'e DATE M QA/QC ENG AN1' REVIEWED BY ANI REVIEW N/A DATE CA/QC OP. NO. D EPT. OPERATION ENG ANI 1 QC Inspect chipping of honeycombed' and/or voided area (areas) to insure air honeycombed concrete has been removed and chipping is in accordance with' approved procedures. 2 BSR Replace any rebar removed for chipping access. Civil 3 QC Verify all rebar is replaced. 4 B5R Install any required embedments removed during chipping. ~t Civil 5 QC Verify all required embedments are installed. 6 B6R Clean chipped area and install any formwork required at Civil this time. 7 QC Verify cleanliness. 8 B6R Install any remaining formwork necessary. '0"R WF.)mLOMDMB [. Civil 9 QC Verify stability, line and grade, tightness of joints and proper concrete cover is maintained. 10 QC Review attached pour plan to insure planned pourback procedure will provide acceptable results. 11 QC Verify pour card sign off is complete and existing con-crete surfaces are properly prepared in accordance with approved procedures and/or engineering instructions. 12 B6R proceed with pourback in accordance with attached pour Civil plan. 13 QC Operations 4 through 12 shall be repeated if multiple concrete lifts are required. 14 QC Verify pourback ccepleted in accordance with attached pour pla..
~ ~ ~. Fl /* l.. %,_. ? s U ~~ CONSTRUCTION OPERATION TRAVELER 35-1195 i TRAVELER NO. 2 UlPMENT NO. hNIT NO. hUANTITY @PAGEIOF4 ~~ ~' ._'!Wte noy l 2 I Ooo-5500 s REFERENCE ORAWINGS h ACTIVITY DESCRIPTION Pour BaCK ot Lore Wall NCR-1924 @ 2. Area 2 /W Void and Henevcerbed Areas SYs7EM SPEC./ PROC./ ENG. INSTR. LOCATION See Attachment Reactor Building. Unit #2 - N/A Nm M IM'M DATE D / <'iD DEPT.C N8t-ENGW Gf0^*5 .2 EPA ED sy / ^ DATE A A QA/QC ENG ANI.. d.~ gy [ ~
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., ai. ,~ -. +j-OP. NO. DEPT. OPERATION ENG ant e n ans y*,sa. g._m ,y.,44, e 4 ;'.. P-1 QC t chfpping of honeycu 2,+i and/or. voided area.lareas)m.; Vi yg y' . ure all hcssyW concrete has been removed anci' cfq to ~d ~.;W chipping is in accordance with approved procedures me .a. ..., ~~. m.,..- Replace any rebar removed fdr gppgto /Oaccess'.N W 4'"' M @M8o S.i~'.N 2 B4R Bee g pS. dfgja Civil M~-~ ' " = " + -r - d o 3 QC Verify all rebar is replaced.M r a w v- -/* E GW v-AM 4 B4R Installanyrequiredembed=entsre.:cvedduringchippin5. M N/b/h nen a A n /in in c1yt1 ( ~? 2 As lJe/vd S QC Verify all required embedments are installed. O. W % ;s u r-a, ..Sen hare-m.no g g yu ,- )T l;.- 6 B4R Clean chipped area and install any fornwork require'd. sat M~t OD Civil this time.+ o 2 a//. Na NE *as 4N/W -A -
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u 7 QC Verify cleanliness.re a zu % e '.he.# v-sed"'~~)- M TTr'6 i p" " ]g,ei B4R install any remaining formork necessary. !>./4 ~Q y p f,g 2iw h:--M,...2/@.kh 7 '*M ""~; -' 3. 8 mDs Civil l ' M-9 9 QC Verify [ stability, line and grade, tightness of joints.A, N d -#-** N.. and proper concrete cover is mainta m v-~ As E 5%r u..e.e.,..T 10 QC Review attached pour plan to insure planned pourback. ~ liY i A MM u r-* procedure will provide acceptable results. l e r m <m-s, 4 m v-s w _ a 11 QC Verify pour card sign off is complete and existing con-- 5 crete surfaces are properly pr pared in accettiance with
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approved procedures and/or e e v-w eo r;;;;u v.sy.a., ed with pourback in accorgepth agaped pourf g q.2.p, 12 P P x nw-u-e n 13 QC Operations 4 through 12 shall be repeated if multiple concrete lifts are required. s,er, A.r e a W f. jQ 1 QC Verify pourback cc picted in acecrdance with st:sched. ' ^ W.*--L L-.e e FOR_MORMALON THW".c' Ce ?.'. dW' V e 7 : ar p1:.. . - -. _ -... _ _.. -. ~. _. _ _ -, _____ _ ._-..____y__ -_.._r..__m--.,.-.w.,,
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CONSTRUCTION OPERATION TRAVELER 351195 / . ?',2v df/T 00)huNIT NO. @QUAN m f PAGE/ 06 $ N. IPMENT NO. TRAVELER No. 2 ~ 2 l i . ' * * '. ook-5500 ACTIVITY DEsCRIPrION Four 5ACK Ot t. ore nall REFERENCE DRAWINGS N. VCR-tF2.d R v 7. Area 3 t Void and Henevec-bed Ar-ss l.OCATION SYSTEM g SPEC./ PROC./ENG. INSTR. Reactor Building. Unit 82 N/A See Attachment N#m UU < =8 DATE W ID DEPTC.wm Er4dNrserrJG .-A" PREPARED BY Mud //),-/I
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~ C' & v-e-A 10 QC Review attached pour plan to insure planned pourbad procedure will provide acceptable results. Ar# pae em 11 QC Verify pour card sign off is complete and existing con-crete surfaces are properly prepared in accordance with. d h v'-#* approved procedures and/or engineering instructions AMDJy-x-fo Proceed with pourback in accordance with attached po O M
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s,. CONSTRUCTION OPERATION T* AVELEh REvis:C', REOCS 5 tri n TRAVELER NO. ACTIVITY DESCRIPTION PAGE o-80-oez-sseo Pourback Of Core Wan Void and Honeyccr.ted LOQ EQUIPMENT NO. l Areas N/A I C arv C C REVIEWED SY.O REVISION DESCRIPTION
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? I 4 -.-g ACTlvlTY DESCRIPTION Four daCK Of Lore WS1.1 REFERENCE DRAWINGS i-N'CR iP2d Etv 2. Area S N ki:': Void and Heneveembed Areas W SYSTEM SPEC./ PR OC./ ENG. INSTR. LOCATION ,,7,7 Reactor Building. Uni 82 N/A See Attac%nent h > ~ AII hll> d DATE Y4 /N _ DEPTC>vit M m Fe T-u EPARED BY ~' hhD BY h DAT.E.8 QA/QC ENG ANI f .W.c.r.;;.
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?-M 10 QC Review attached pour plan to insure planned pourback g g.g.g procedure will provide acceptable results. 11 QC Verify pour card sign off is complete and existing con-g 33 3 crete surfaces are properly prepared in accordance with approved procedures and/or engineering instructions. 12 B6R proceed with pourback in accordance with attached pour Jg7-Civil plan. 13 QC Operations 4 through 12 shall be repeated if multiple hp 5 E4-Se concrete lifts are required. 14 QC Verify pourback completed in accordance with attached pp 514-so pcur plan. _ _ menOMd b y w.u m -
r e i v-CONSTRUCTION OPERATION TR AVELER REVISION RECORD SHEET.,,..,.. TRAVELER NO. ACTIVITY DESCRIPTION PAGE G-80-oc6-5Ebo Pourback of Core Wall Void and Honeyccebed
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1 l s. .' 7.' CONSTRUCTION OPERATION TRAVELER 35 1195 ~ U 's . [-- nl TRAVELER NO. 2 glPMENT NO. hUNIT NO. pUANulY PAGElCP4 W-80-cod-SSOo .,n 'k>*s-V8st-ace 7 7 l ~ ~: ;,. REFERENCE DRAWINGS ACTIVITY DESCRIPTION Four Back or (., ore Wah y ,g ~ NCR-le24 lie < 2 Area 4 N Void and Henevcembed Areas N gSYSTEM SPEC./ PROC./ENG. INSTR. LOCATION gSeeAttac; sat Reactor Buildine, Unit #2 N/A Daw UR lMJ DATE 3/U N DEPT 6 'l hWM PnEPARED SY DATE QA/QC ENG ANI hh = D SY . - - ~,.-- 1 .J; .~ ./ ^ ' ' ' ~ ' """ A w2 - - N/A ~'- " ~ DATE _ w. i : ANi Review '-* ~ ~_-- WM 's L et q. ENG ? ANI-s.s .... '..OP. NO. DEPT. OPERATION ~ ~ Inspect chipping.of honeyA and/or voided area [ areas %- /.n * -Es 1 QC to insure all' honeycombed concrete has been removed and ; .;.I chipping is in accordance with appiuved procedures. T, f.. . Aia i '? 2 2 B4R Replace any rebar removed for chippingsaccess. JKW;M hu. .a.~ :. _. .7*/". r M- ~ b -7 M r.,= Civil 3 QC Verify all rebar is replaced.
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4 BSR Install any required embedments recoved during chippia.g. gg g/u/g. 8 Civil 1 ~ ###' 3' "* ,} '5 QC Verify all required embedments are installed. .a .m N$/o Cleanchippedareaandinsta11'anyformworkrequireda4 9,g.J.g. 6 B4R
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E . a=t..._-h Brown & Rooi..Inc. ~ QU AUTY ASSURA NCE CEDART'iE'.'T QA RECORD NONCONFORMANCE REPCRT (NCE: to.,ECT CPSES JC8 NO 351195 p4CE . Oc 4 21 UNITI STRUCTURE SYSTEM COMPONENT i TAGilo NUMBER LOCATION O A ELEVATION Rf A NC Containment l 2 Building l Concrete l201-4812-007 819' - 846' N/A (3) NONCONFORMING CONDITION [,'."gCav E 2 323-SS-9 5 8.2.6(a) C-11 + , i3 occuuENT victATEo. .Ev P,, Cited specification scates; "All concrete shall be consolidated by suitable means, and thoroughly worked around the reinforcement and er: bedded fixtures and into cor-ners of for::s". 'Ihis specification was violated in twenty-two locations on the reactor containment ntrber 2 core walls in ccrrpartment #4, ocur no. 201-4812-007 on 6-21-79. See attachment #1 for location and size of defective concrete. This revision is to delete area no.s 3 and 4 from attachment #1. j i l l + aE3C8'E: Sv Se OATE '9'2Evf.\\a3880,v.a-
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j.: ~- Defective concrete areas cited shall be chipped to sound concrete and repaired as stated below. All areas shall be coated with weld-crete prior to pouring. Area 1 - Form and pour back with area surrounding adjacent blockout using 3/8" aggregate concrete. Area 2,7,8,9,10,11, &,18 - Form and pour back with Master Builder's Masterflow 713 Non-Shrink Grout. Area 5,6,17,19,20,21, & 22 - Form and pour back with 3/8" aggregate concrete. Area 12 - Chipping has extended area 12 to join area 3, therefore area 12 shall be omitted from this disposition. Areas 13 & 14 - These areas are under engineering investigation and shall be o-mitted from this disposition. Area 13 &l4 will be addressed on later NCR, with areas 3,4, and 12. Areas 15 & 16 - Dry pack these areas in accordance with construction procedure CCP-12. EBR lEDRhlg;03 OM
i Gibbs 8 Hill. Inc. Interoffice Memorandum CPP-A-3592 TO: J. T. Merritt, Jr. DATE: December 5, 1979 FROM: R. E. Heim JOB NO: 2323
SUBJECT:
Concrete / Containment #2 REF. NO: NCR-C-1824-Rev.1 COMANCHE PEAK STEAM ELECTRIC STATION 1981-83 2300 Mif INSTALLATION NCR-C-1824-R1 ~ By copy of this letter we are advisin;: Brown F. Root that the " repair" disposition on the subject NCR is acceptable. /- ~ R. E. Heim Resident Engineer h REM:GDW:ss cc: ARMS OL D. Horne IL FOR lHFOREAT OM DE.'I f l l _-, ~... -.
.. M) Brownf5 Root.Inc. 2: CUALITY ASSURANCE DEPARTMENT QA RECORD NONCONFORMANCE REPORT (NCR; ~- '. ' ' ~ 40dCT CPSES JOB NO 351195 DAGE 05 (2' UNIT: STRUCTURE SYSTEM C OMPCNENT 6 TAG,10 NUMBER LOCATION CR ELEV ATION AIR NC l Containment i 2 Building l Concrete I201-4812-007 819'-846' N/A 7"E 0 8.2.6(a ) [-17g (3) NONCONFORMING CONDITION cy isi ooCwuENT victATEo: 2323-SS-9 5 C-11 REv ,A,A Cited specification states "All concrete shall be consolidated by suitable means, and thoroughly worked around the reinforcement and embedded fixtures and into corners of forms. This specification was violated in twenty two locations on the reactor containment 42 core walls in compartment #4 pour No. 201-4812-007, 6-21-79. See Attachment #1 for location and size of defective concrete. I i j.5 eE=ca E: av e,: :E .s a3 .v Anoa
- e. :2TE Suddy Lamb 11 / 10 / 79 fg.w,./ [',//v.,o
/,' er/;; n PaEPAato Sy: i 188 CATE: t i ll ISSUE)T SY: i 112) O ATE. I Buddy Lamb l 11 / 14 / 79 Mw M #41, l g M/1f i i f f 1131 OISPCSITION ASSIGNED TO: (14e CUE DATE. (ISI CCARECTIVE ACTION REQUEST: CAR NO.'(16) ASME CODE 1C' ASS: D. C. Frankum 11 / 2f}<79 C Recuired C Not Recuired l 2 V" X. No I r171 CiSPOSIT:CN R EWORK REPAIR USE AS fS SCRAP _ t i i i IDH H i > 'T10N DNLY (18: CONSTRUCTICN AEViEWIAPDAOVAL '119: C ATE: (201 CA/OC REvtEW APPaOVAL: l 4211 OATE. I
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! / / 122) ENG. Review / APPROVAL j1231 DATE: f24) ANI REVIEW APPROVAL: 112 5) DATE: l 'I / ll l 126) VERIFICAT;ON. 1 (331 REM ARK 3 l -- Satisfactory ZUnsatisfactory C Not Reg'd l 127: CA.'CC ENGRilNSPR. VERIFICATION: 1281 OATE. I' / / 29 ant ColiCURRENCE 130 CATE / / 4 i e 9 e= H
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y) ? TUSI SITE (T 'h ,h 910-8908-6k0 hi f' mar /,/tffd S ~ b GTT-2lcO 0 ATTENTION: J. T. MERRITT/R. E. HEIM/J. A. ALLEN G&H JOB NO. 2323
SUBJECT:
STAINLESS STEEL LINER REPAIR 3 FIFERENCE: CPPA-4 668 i FOLLOWING IS OUR RESPONSE TO CPPA-4668 RECEIVED AT G6H ON l APRIL 30, 1980. I I', f THE REPAIR PROCEDURE PROPOSED IN CPPA-4 668 IS ACCEPTABLE. AIJ., WEIDING INMING TESTI2C BBOULD BE IN ACCORDANCE WITH SPECIFICA 2323-SS-18. SPECIFICATION 2323-SS-14 IS NOT APPLICARLE. SEE MARKED UP ATTACHMENT. IN ADDITION NE WOULD SUGGEST THAT TRESE *PA%!:" PIA ~ES BT
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IDENTIFIED IN THE FIELD SUCH THAT NO OTHER FUTURE SUPPORTS GET INADVERTENTLY ATTACHED TO THEM. Wb hN j H. R. ROCK /E. L. BEZXOR/M. L. BERGMAN /A. M. KENKEE i i
- l JOB No.35 110s Telecopied to Site w/ attachments
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- 70 ' ,g- ./ Q.45. What was the nature of the allegation investigated and 'the investigation findings? A.45. (Stewart) NRC Inspection Report 77-13 discusses the nature of the allegation, wherein the Applicants informed the NRC Region IV office on November 23, 1977, by telephone, of a call on..- e November 22, 1977, from an unidentified Q was apparently concerned with the workmanship at the site regarding the use of-rotofoam as a' temporary spacer in construction to maintain the (, ' required air space between Category 1 seismic structures. During that inspection, the NRC inspector reviewed the allegation and found that contrary to thegbelief, all temporary rotofoam blocks had been removed from the subject areas. The B&R QA/QC inspection staff had initiated an inspection and documentation program to assure that the required 1" gap between Category 1 seismic structures was being inaintained in the as-built condition. This matter was treated as an.open item pending NRC review of the B&R QA/QC inspection results. .O Q.46. Did the NP.C staff conduct followup inspections to determine i whether the Applicants, in fact, implemented the corrective i actions they represented they would undertake? A.46. (Stewart and Taylor) Yes. '" As stated previously, it is standard staff practice to follow up on unresolved matters or findings to ensure that the Applicants have fulfilled their cemitments and 63 V'
o .g COMANCHE PEAK STEAM ELECTRIC STATION VEXAS UTILITIES GENEAATING CO. NONCONFORMANCE REPORT (NCR) C-82-01202 R. 1 Ac-fr uNir i STAuCTUAE/ SYSTEM ITEM / COMPONENT TAG /10 NUMBER LOCATION OA ELEVATION ; AIA NO I 2 Reactor Concrete 201-4834-001 834' N/A NONCONFORMING CONDITION During removal of expanded metal in core area of Reactor 2, voids were identified that cound not be detected at post-placement inspection. Caused by lack of con-ay solidation of concrete due to congested area. = 0 8 Location: 834', 8' South of 180 AZ centerline, 7' North of 180 AZ centerline E C. h ~ ~ G e k AEFEAENCE DOCUMENT-OI OP ll- 0 1/7171 554 AEV 1/S PAAA 3 2 2/S 2 b REPOATED BY: DATE: M. Tatarko 8 /12 /82 {..l OE REVIEW /APPAOVAL: tR/$ // ~ 3 i 2 iAs DATE: O ACTICN A00AESSEE / DEPARTMENT J.T. fierritt/Kissinger Engineering DISPOSITICN: AEWCAK REPAIR XXX USE AS IS SCRAP Repair in accordance with CCP-12 up to elevation 834'0" h". d Repair void above elevation 834'0" h" in accordance with DCA 6663 Rev. 6 (copy attached). Welding Engineering to issue Repair Progress Sheet for repair of JJtm7 t.u flMI } e 7 Z9 nr ODM,ni io. ATim 2 '/ r.m
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- III (WIII) (NKII.XNOT) BE INCCEPORATED IN ' ESIm DOCGENT DCA NO.
6663 Rev. 6 D 1. SAFEIT IEEATED DOCDENT: XX YES__NO I 2. CRIGINMOR: CPPE XX ORIGINAL DESICMER 3. DESCRIFFIN: 2323-S2-0559 3 A. APPLICABIJt IEEC/DCVB3mmart 2323-S2-0560 Istv. 2 9. THIS REVISION VOIDS AND SUPERSEDES DCA-6663 Rev. 5. To orovide inspection of underlying concrete, cut 2" x 2" square holes i in the Reactor Building Unit #2, stainless steel cavity liner in the locations described on the attached sheet 2. Cut a 6" x 6" square hole throuch the liner I at ooints 1 and 11 of the attached sheet. The recair orocedure outlined on attached sheet 3 of 3 shall be used for ret. air of these holes.
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1 r L includino testino, shall be in accordance with specification 2323-S5-18. NO FUTURE SUPPORTS SHOUT.0 SE ATTACHED TO THE.] REPAIR Pt.ATES. (Note: Do not cut across weld seams or embedded weld plates). Core drill 2" diameter holes 3" deep J into the concrete at ooints 1. 5. and 6 on the attached sheet 2. (Reference f locations 128. 125 and c71 Note-rnre bores shall ha <tnnned at enntzet with reinforcing bars. uev1=M en include void repair detat Is on 5heets 4 and 5. 2 4. SUPPGtFING DOCDENMTIN: i GTT-6013 ~ TVX-14,13& 5 SirbG5% hRC-82-01202: CPPA-26.218: UU 5. APPROVAL SIWMURES: TJL/sgf 1-24-83 -7[m JAN 271983 om / 74-BJ ~ 1 A. CRIGINECE: DESIm aEPnESd: Mkeek om l-15-g3 a. DOCUMENT ppNTROL 6. VE200R 1PANSMITmL m,pueus YES No l 7. STNEARD DISTRIBUFICN: .1 f.T ' ' DCA FQ M 11-00 {t)~~~~~~ ...-)[O f*b b'.' Adnun. Rev 7-62 AINI (Original) (f) ^' i ( !Ji.. Quality, Engineering 15 for Orig. Design. ( 14 L* West,Lngbouse-6ite ( t}._ Civil Engineering (1) l s%.. '. ~T *~.~ m... ...? ~g.,;LTIL.g,
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OCA-6663 Rev. 6 Page 5 of 5 '( Repair method shall, be as follows: a) Cut openings at locations shown on sheet 4 of 5, and remove liner plate section. b) Repair any damaged Nelson studs on removed liner section. c) Chip to sound concrete. d) Drill 1/4" air relief hole in liner plate at top of void and grout access hole, size as required, in the removed section. e) Replace liner and weld up as shown on Sheet 4 of S. f) Provide formwork to brace replaced liner plate section when grouting. g) Pump grout into access hole until grout escapes through air relief hole. h) Repair grout access hole as shown on sheet 3 of S.
- 1) Repair 1/4"9 air relief hole as shown below.
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^ TEXAS UTILITIES NCR No' GENERATING CO. NONCONFORMANCE REPORT (NCR) C-82-01202 (.: - ) 'T STRUCTURE / SYSTEM ITEM / COMPONENT TAG /tO NUM8ER LOCATION OR ELEVAfiONl AI A NO 2 Reactor Concrete 201-4834-001 _ 834' _[. N/A_ NONCONFORMING CONDITION During removal of expanded metal in core area of Reactor 2, voids were identified d that could not be detected at post-placement inspection. Caused by lack of con-i solidation of concrete due to conjested area. 8ey Located: 834' Elevation i n 8' South of 180 AZ centerline and ez 7' North of 180 AZ centerline E 2 E 01-0P-11.0-3/2323-559 3/5 3.2.2/8.2.6 REFERENCE DOCUMENT. ngy PARA REPORTED BY: DATE: Mark Tatarko 8 f12 i 82 t.$ r wg&h p, gg O ACTION ACORESSEE / DEPARTMENT J. T. Merri tt/"--[odo2ot edh Enaineerina DISPOSITION: REWORK AEPAIR YYY USE AS IS SCRAP Repair in accordance with CCP-12.up to elevation 834'O 1/2", E Request temporary waiver to cut liner plate and chip to determine extent of E void above elevation 834'O 1/2". l 0 e ze .c <.n n m ~-b u a., t u n u p:_ : wnu m s O f. Ud hi i 1 ENG.$ REM 1MGC5's - ~ /d in f 2L W/ APPROVAL CATE. f // I P W // OE A5dMVA54RO' ? DATE // / / ///,r 10ih,SV w_ . N6dTION VEF6 ON & ' CLOSURE: OATE COMMENTS:
( s TEXAS UTILITIES SERVICES INC. P O. BOX 1002 Gt.EN ROSE. TEXAS 79043 [. CPPA-26,218 Aggs Janua ry 12, 1983 lh'g4ED d
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.,EI-R.E. Ballard ll C L
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Gibbs & Hill Inc. ((. y,,,. 393 7th Ave. j? ! '] e a New York, NY 10001 b r... COMANCHE PEAK STEAM ELECTRIC STATION "u VOIDS BEHIND UNIT 2 REACTOR CAVITY LINER
Dear Mr. Ballard:
Voids have been detected behind the S.S. liner olate in the Unit 2 Reactor Cavity at the following locations: Elevation 835'-0"; 8-0 soutn and 7-0 north of the 180 Azimuth on the west side. I have re-viewed GTT-6013, however, the sizes of the openings are too small to facilitate the repair of this defective concrete. I am prooosing to cut liner plate, repair defective concrete and then repair liner plate as shown on the attached sheet. Please advise as to the acceptability of this proposal. I' further information is required contact T. Lutz at x421. Please respond by 1-20-82. Very truly yours, 's~ R hC c[6T- 'R.M. Kissinaer V Project Civil Engineer g&
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~ TUGC0(2) Ac-2s' PAGE 1 CF 8 C34ANGE PEAK SIEAM EI.ECTRIC STATICN I ( UESIG4 GANGE AUINCRI?.ATICN (WII.I.) @WE)tC:0 SE INCCRPCRATED IN DESIGi DCCDDT CG.'O. 6663 Rev. 10 1. SAFETY REI.ATED IXXDiEyr: XX YES NO ,,{ 2. CRIGINA*ICR: CPPE XX CRIGINAI. DESIGER Ib 2323-52-0559 L d 3. DESG.IFrICN: A. APPI.ICA31.E SPEC /1M/1XXI3ENr 2323-52-0560 REv. 2 3. DETAII.S THIS REVISION VOIDS AND SUPERSEDES CCA-6663 Rev. 9 To crevide insoection of underivino concrete, cut 2" x 2" scuare holes in the Peacter Buildine, Unit d2. stainless steel cavitv li-ar in *e inr1*icas dasc*i5ad 4a w st ached sneet 2. Cut 6" x 6" scuare hole thecuch the linea ceia s 1 and.. S' -e nt3c ed sneet The recair crecedure outlined on the attached sheet I sha" te.sec fcr recair of these coles. All weldina, includino testina, shal ce in ic creacce .iO FUTURE SUPPORTS SHOULD SE AT~ ACHED TO ~~-E55 ; epa:? sitm s ceci'i c a ri co ????-55 '_?. ' M E~. (Ncte: Do not cut acrcss '. veld seens or s'r::eccec weif Olnes). Ire 2- ' 2" diameter holes 3" deeo into the concrete at coints 1. 5, and 6 cn tne attacneu sheet 2. (Reference locations 128, 125 and 971 Note: Core bores shall be stcceed at contact with reinforcine bars. Revised to include void reoair details on sheets A and 5. Revised location as shewn on oace 4 of 5. 35-1190 Revision 3: Added alternate weldina detail (T ce II' -c.,.,,..s,
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i DCA-6663 Rev. 10 Page 2 of 9 B. DETAILS (Cont) ? Rev. 9: Page 7 added to indicate Nelson stud locations on replacement itner plate at openings shown on page 5. Re. 10: P$ge6revisedasshownandpage8addedtoindicateadditional locat. ions of grout access and air relief holes. i
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N OCA-6663 Rev. '. C P ce 5 of 3 i Repair method shall be as follows: a) Cut ocenings at locations shown on sheet 4 of 5, and remove liner a plate section. / f'].C ~ b) Repair any damaged Nelson studs on removed ifner section. / ~ c) Chip loose concrete wnere accesible at locnions snown on : age 5 af 'O. N d) Jrill 1/4" air relief hole in liner olite 1: too of voic inc grou; access hole, size as requirec, in :ne rer.cVec section. e) Replace liner and weld uo as shown on Sheet 4 of 5. 3revice formnork to Orsce reclacec liner clate taction wren : .:'ng.
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l CIVIL / STRUCTURAL ALLEGATION REVIEW CATEGORIES l Category Est. Mandays Allegation Package Assigned Schedule No. Subject to Complete Nos. Prepared to Open Close Remarks 1. Inadequate materials AC-16, AC-19, AC-20, used in concrete AC-21. AC-27 2. Concrete placements AC-22, AC-23 3. Poor weather conditions AC-24, AC-35 placement of concrete 1 4. Concrete voids / cracked / AC-25, AC-32, AC-34, crumbled AC-41, AC-28, AC-33 S. Hiscel. concrete AC-17, AC-18, AC-26, AC-29, AC-31, AC-36, AC-42, AC-43 6. Rebar improperly AC-30, AC-37, AC-38, installed / drilled or AC-39, AC-40 omitted i l l "=oI A -B6-Si C1l 'G
/ v. 4 I t Concrete P. 4 CONIR0lllD COPY CIW4ANClit PE AK NOClE AR POWE R Pi ANI Al t E CAI IONS AN070f lUEI5ilf.kildN5'5fet4ARY I CN055 REF./OR COHPIEll0N ALLEGER-DATE RECEIVED SOURCE IRACKING CAllGORY l-7 SCHilittl E SollRCE IA5K 'No. AttECA110N 04 CONCERM ACil0N/51ATUS ANON C0tifl0 SN/DAIE SYSIEH NO. IEAD OPIN COMPlEIE IwKUMtNI PAGE 5E-79 i,,., _ t ;__ =n-1 na-nos 1/r/nm a w ANI P. 16 1 - 06 3/7/84 A-27 _ ar-si rae -. - m ' - - - ! ; ;- ARI Iestimony, P. 31 JS 2' '--'-etr 7'r'-f :n L'n!i * " '" !:! d!: -- ; im. A5tB 1 Unknow Testimony, contalonent dose in the applicant respen Pr - ART dtd 5/24/82, 39 in ltr. dtd 6/12/ estimony
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9MANCHE PEAK STEAM ELECTRIC 9% TION TEXAS UTILITIES .- GENERATING CO. JO ORMAt CE REPORT (N(,nf C-82-01432 R.2 l UNIT STRUCTURE / SYSTEM ITEM / COMPONENT TAG /10 NUMBER LOCATION OR ELEVATION RIR NO 1&2 Auxiliary Concrete 002-7810-002 810' N/A I NONCONFORMING CONDITION Specification states: "All debris and foreign material be removed from area to a receive concrete." On pour 002-7810-002, embedded foreign material was located with flex drill. 5 E E Location: 6'-10" West of LA, 9' North of 6A, 810'. hh IC43 2323-SS-9 5 ,,,, 8.2.5 REFERENCE 00CUuENT. ngy REPORTED BY: CATE: 1 Mark Tatarko 9,13,82 ! l OE REVIEW / APPROVAL: DATE: Muk AY // / 2 /A?z O ACT ON ACORESSEE / DEPARTMENT l J. B. George /Kissinger Engineering OISPOSITION: REWORK REPAIR YYY USE AS IS SCRAP Replace installation (Ethafoam #220 Polyetylene foam) over exposed pipe. Seal mg Joints with R.T.V. or equal, u)y Chip area out and replace concrete with same mix design as per CCP-12. O Q QA RECORO I FOR INFORMATl0N ONIy^* "1"D-Q h 8 INDEXED G n uE ~ 0. /5. / SUDFILE NO D^M AlcA AlO ENG(A IEW/ APPROVAL DATE: vnk /> ll i 4 i 8e " "' W f.^' W A /f //if(v ^ ^ w DISPOSihCE YERIFICA' O L / / III I COMMENTS: p Rev. 2 issued to change disposition.
7,Mr.nCHE FEA< S T D.u ELECTR' $ 7 A T1CM 'j ner- -e INSPECTICN gEPCRT g:o. /it'-f: - 7e m,>.- ).ce, mic.u.a. ,c. oo 2 - 78/o-oo z. )c<ksr..,y/whiauc:. x t; ;m c:G,, l ib.,;ccmr;caA lejr e /, w,. c " a n, ,,,.,),, m UWQ. AL,: c.c. CC. A 4L's. A C.u.MGL 30 MLM i'i ;A : LhT' L; usa.cL:si. :aG. 2223-SS 9.lAtv.s', pq p ~ d. o-2 + 3 i?- z + 3 l .- p -e = s a g re s.,ir-u ne-a n=r=u =. c4 >m.- - =n =. o,can:n unsnenc:s u nevan
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~ y! )p/g4 Q;,2 f,,,.o., i i Mc :n c:w.ma :.:.: u u:au iras sansner ar G ameven c- , u.ssensuc ur iras usm in.:w im,o. oe INSFECTION ATTRl!UTE3 y garg 3;g y,,,,;3 g ,5 l l Pa n e emi,-d n a,J +4, hiAsn -, flu I i l l Ii-An /,, 'd m es det fio n 's/s/er C ?z-o ter] '-1~1 I ~ 2. l M % s p,s A. a , e ni A ,'n n o,. x,,. e I ;)* I Iui/d ec,o 17 ~,x ber &w < /L J#a t-n-p.)GI-A 2-I -? l* % inspee/n lr<s,..t C/nes x/ft c.nz o/a sk i f l I 4'- 7 I c. f' I I d l 4, N hra s~ e m are,/ l < Y1 I l I i l-I 1 1 II i I I II I i l l l l l 6 I I II l 1 I II I I I I I I i l I ! ! l 1 I ! ! I i l i I i I Cnn in. - l 1 i l '"n InmHMAllRAI nnou u I ; I i utn y j g, i i I l I 1 I i i i l I i i
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t 'h GENERATING CO.l TEXAS UTILITIES NCR reo 3 NONCONFORMANCE REPORT (NCH) A C-82-01432 R.1 N M UNIT STRUCTURE / SYSTEM ITEM / COMPONENT TAG /iG NUMBER LOCATION OR ELEVATION RIA NO 1&2 Auxiliary Concrete 002-7810-002 810' N/A NONCONFORMirIG CON 0lTION Specification states "all debris and foreign material be removed from area to ci receive concrete". On pour 002-7810-002, embedded foreign material was located j with flex drill. 8 5 Location: 6'10" West of LA, 9' North of 6A, 810' = b i i e l 2323-55-9 5 8.2.5 REFERENCE DOCUMENT. Agy MPORTED BY: DATE: 1 Mark Tatarko 9,13,82 l l.OE REVIEW / APPROVAL: OATE: ,pf/J kJ u_h // /M2 N O ACTION ADDRESSEE ~ ~/ DEPARTMENT l J. B. Georce/Kissinoer Engineering i DISPOSITION: [ REWORK REPAIR YYY U3g AS 33 ScpAp j i Replace installation (Ethafoam #220 Polyetylene foam) over exposed pipe. Seal uJy joints with R.T.V. or equal. u) E Chip area out and replace concrete with same mix design as per CCP-12. O O NOTE: J6r chipping to determine the embedded material.J@esud-6aTnline i 2 4 FO-X-037-lbou x. nnid. r & W a.h-/dl is wrapped and band 9 with 2" sheet Fth ' La rau (Polyety ene room; R 9 enntinuously h _ay.cune-ttT e6Ee~dded pipe. ggp/ FOR INF0 5 A g g go, ENG. view / APP n ~ DATE: ,/\\ /- - , Y,^ / / CE REVIEW APPROVAL: OATE. uf / / OISPOSITION VERIFICATION & CLOSURE: DATE. t / / COMMENTS: ReV. 1 issued to Change disposition. .M
i .... ~ ON ) fEXAS UTILITIES GENERATING CO. NONCONFORMANCE REPOFkT (NCH) l C. A7.n14 U ( UNIT STRUCTURE / SYSTEM ITEM / COMPONENT TAG /lO NUMBE9 LOCATION OR ELEVATION RIA NO. 1A7 Anvili arv Concrete 002-7810-002 810' N/A I NONCONFORMING CONDITION Specification states "all debris and foreign material be removed from area to receive concrete". On pour 002-7810-002, embedded foreign material was located with flex drill. g E 8 Location: 6' 10" West of LA 5 9' North of 6A 1 Elevation 810' o E Ec 2 E REFERENCE DOCUMENT
- REV PARA REPORTED BY:
9, 15,: DAT 82 Mark Tatarko I OE REVIEW / APPROVAL: DATE: Jhh Yh O ACTION ADDRESSEE / ~ 9 /s /az DEPARTMENT J. T. Merritt/Kissinger Engineering DISPOSITION: REWORK REPAIR USE AS IS SCRAP $g Engineering request waiver to determine the extent of the area where the embedded g material is 1 cag gNorEt a 0 v :- G. /*72iE C///P//dG b fe7acmiocr' W mMoonero snorwnAN ^ Z gypy$x JL,4a.) doJ Gt' f,#x;;?-y t 3 1 /S*d & C LU H C/*' l & M G' #d^'tu N G .ms-res s.s w m eeeesa a.o w en sw ern -wm *2ro &<pritm y Fdam) ,(.e de <fot.JTsJdsd2Ly A dovuo W e m newcao,+$,,og, FOR LNFORMAION ONL.Y ENG.A W/ APP VAL DATE: 'A /.5' & ~ /hlWS. 2 / f// / REVIEW APPROVAL: 0T P dlSPOSITION VERIFICATION & ' CLOSURE: '-' OATE: / / COMMENTS:
3 7 TUQ-1442 TEXAS UTILITIES GENERATING COMPANY OFFICE MEMOR ANDUM r. J. B. George Glen rto T.u. October 20, 1982 subj.cs Comanche Peak Steam Electr.ic Station M PA82
- The attached form documents a construction deficiency recently verbally reported to the NRC. Please assign an engineer to evaluate this deficiency working directly with C. T. Brandt to resolve this problem.
We need to jointly determine by November 10, 1982, if this deficiency is fonnally reportable under 10CFR50.55(e). Thank you for your cooperation. A R. G. Tolson TUGC0 Site QA Supervisor RGT/bil Attachment cc: D. N. Chapman G. R. Purdy
- 8. C. Scott C. T. Brandt M. R. McBay FoM-W-s j i
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E ON TE UTIUTIES fl "C" "** NONCONFORMANCE REPORT (NCR) GENERATING CO. c-A7_n 14 77 (', UNIT STRUCTURE / SYSTEM ITEM /CCMPONENT TAG /lO NUMBER LOCATION OR ELEVATICN RIR NO. 11? Anviliarf concrete 002-7810-002 810' N/A NCNCCNFORMING CCNDITION Specification states "all debris and foreign material be removed feri area to receive Concrete". On pour 002-7810-002, embedded foreign material was located with flex drill. mzz 8 Location: 6' 10" West of LA 9' North of'6A Q-Elevation 810.'.. a z .y c: g p..; n! a 9 REFERENCE DCCUM ~ ~ REV PARA REPORTED BY: 9,DAT{** l 32 ' Mark Tatarka CE AEVIEW/ APPROVAL....- CATE: l %I / A $ /Af, Ie92 i C ACTION ACORESSEE. v / DEPARTMENT l ' J. T. MerTitt/Kissincer Engineering DISPOSITION: REWCAK REPAIR USE AS IS SCRAP . ~,-.- us Engineering hauest waiver to determine the extent of the araa where the embedded U material is located. c: ?- g 1 9 l E< ENG.R W/APPA VAL oATE: th! [2__ n f '^ tf =, '// / j' >\\ A ti W t / / dlSPOSITION VERIFICATICN & CLCSURE: CATE: t' / / CCMMENTS: sI
.D//f t: 1 0 / 112 d8 tal 'ACILITY ll0TIFICU I..I ITEhdR EVElli RECI0llAL ACi _3_.1 .Y REPORTS 1RIST 111CLUDE SPEE:.li.3 (5LE l'OLICY CUIDE 10. h-26 REV.1), PA0 llEETINGS, OTilER IMPORTAllT
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DACK OF PAGE TOR ADDITIO!!AL :,PACEn. i C )NSTRUCT10N omanche Feak Verbal To SRIC this POTENTIAL 50.55(e): While drilling holes in a concreto Followup in accordance Date. floor for the purposes of installing anchor bolts, with MC-2512. omon P50-445:446 debris consisting of "Rotoform" and plywood was L. discovered in the interior of the floor concrete. Preliminary exploration via additional holes indicates the debris may b4 as much as 17 feet Inn 9 i by approximately 2 feet wide.-The void in the concrete created by the void is approximately 18 inches below the floor surface. Preliminary indications are that there is an additional void under the plywood which in turn is under the "Rotoform" material. The size or depth of this latter void has not been determined as yet. The floor in question is a ' lab approximatey s i 3.5 feet thick in the common facility Auxiliary Building and supports two waste evaporator storage tanks. The floor slab was placed on April 11, 1977 and was 450 cubic yards in size..The licensee ~ ~ ~ ~ ' ~ ~ - ~ will continue his evaluat{dn of this matter and will file a report within 30 d4ys. .SE IIOTE: STATUS OF UHUSUAL SPECIAL IllSPECTIONS _0R I_lNESTICATIONS ARE TO'BE,JllCI.UDEn Ill Tile DAILY REi ORTS EVERY TilURSDAY. ~' DRAllCII SICHATU,E A ClitCK llERE IF DACK OF PAGE C0!!TAllIS IliFORllATI0li l'N l L .,-,.m.
l O O TEXAS UTILITIES SERVICES INC. I CPPA-24,328 OFFICE MEMOR ANDUM R. G. Ibison Glen Ro. Texa.ctober 26, 1982 O 7, CDMANCHE PEAK STEAM ELECTRIC STATICN subject SDAR CP U CCNCREIE WID IN AUXILIARY BUIIDINC; Ref 1) TUQ--1442
- 2) Meno-RMK to MRM dated, Oct.25,1982 We have reviewed the subject deficiency to deter:nine reportability per the provisions of 10CFR50.55(e) as directed by Ref.1.
Our review of the area after exploratory chippirg ha:s indicated the " foreign material" asstand to be plyw:cd is an enbedded stainless steel floor drain pipe. 1he embedded pipe is line #4ED-X-037-150GR at approximately design elevation 808'-6". The floor drain pipe is wrapped with 2" sheet Ethafoan #220 (Dow Q1emical Co.). We attribute the apparent void to the interior of the pipe. Our evaluation has concluded the concern is not reportable. Please contact this office if additional information can be provided. y ~ M. R. McBay f Engineeirng Madger i MBM/RPB/and cc: ARMS J. B. George R. M. Kissinger R. A. Jones D. N. Chapnan CY e> I i
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'"ll"J. O*."*"" i i t October 29, 1982 TXX-3589 Mr. G. L. Madsen, Chief l Reactor Project Branch 1 U. S. Nuclear Regulatory Coninission i Office of Inspection and Enforcement 611 Ryan Plaza Drive, Suite 1000 Docket Nos. 50-445 Arlington, TX 76012 50-446 COMANCHE PEAK STEAM ELECTRIC STATION AUXILIARY BUILDING CONCRETE FLOOR SLABS FILE NO.: 10110
Dear Mr. Madsen:
On October 20, 1982, we verbally infomed yo.ur Mr. R. G. Taylor of a deficiency regarding embedded rotafoam and plywood in the Auxiliary Building concrete floor tlabs. We have cumpleted our investigation and concluded that the matter is not reportable under 10CFR50.55(e). Records supporting this determination are available for your Inspector's review at the CPSES site. Very truly yours, m I . J. Gary RJG:eaq cc: NRC Region IV - (0 + 1 copy) Director, Inspectio!n & Enforcement (15 copies) U. S. Nuclear Regulatory Commission Washington, DC 20555 ~ I cw ,Q 9u i le e n. \\ v-.: - t-j,4 j a_.y d (J J
l O i e cc: R'. J. '. G a ry ( 2 ) B. R. Clements D. N. Chapman R. L. Ramsey J. C. Kuykendall J. T. /4erritt D. Frankum H. C. Schmidt B. S. Dacko R. G.. Tolson R. G. Taylor F. B. Shants e e-O ,,.._e-_ ..n_-.,-
/ .h. y h I 'i .'>4 \\ j 1 \\ Docket No. 50-446 ~ O Texas Utilities Generating Company I l ATTN: Mr. R. J. Gary, Executive Vice President and General Manager 2001 Bryan Tower Dallas, Texas 75201' j. Gentlemen: This refers to the telephone conversations between-}fr. 'L. F., Fikar and me on i Septeder 17', 1979, and between Mr. Fikar and Mr. W. C. Seidle of my staff on ( Septenber 18, 1979, concerning your plans to resume the placement of concrete in the Reactor Containment Building exterior vall and dome on Septeder 18, j 1979. j l \\ Following the detection of the inadvertent o::lission of shear tie reinforcing ,j ( steel in the 32nd lif t of the Unit No. 2 Reactor Containment Building (RCB) exterior vall, placement of additional concrete.in the RCB was stopped by a j TUGC0 s top-vork order issued on Septeser 7,1979. This action uns confirmed I by a F.egion IV 1==:rediate Action Letter, dated Septed er 7, 1979. c On Septed er 18, 1979, our on-site Resiaent' Reactor Inspectior completed the i NRC review of the actions identified in the' RIV Immediate Action Letter to correct concrete placement problems which resulted in the omission'of shear l tie reinforcing steel. Based on the results of the NRC review, we hav,e.no I objection to your plan to resume concrete placement in the shield wall and l dome. We vill continue to monitor closely your work.a'etivi. ties, r.nnagement I controls and it:plementation of your Quality Assurance program during subsequent inspections. 1 If you have any questions regarding this matter, please contact this o'ff' ice. l Sincerely,. Onginal s?aned by - l . Karl V. Seyfnt l bec to DAC:ADM for dist. l (. V. Seyfrit Central Files { Director PDR dist. by RIV g bec to Reproduction Unit for dist. 9/18/79, LPDR. Tex. Dpt. of E.R. . Central IE Files. ELD ; NRR. MIPC. r' TTC a i AD/F O{Y..RG'faylorf Standards Develpment NSIC
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Q r ,g M.. W-1. Gf N 'N 1 9 NOV 1979 i i t In Reply Refer To: l RIV Docket No.. 50-445/Rpt. 79-18 I 50-446/Rpt. 79-18 y 1 Texas. Utilities Generating Company ATIN: Mr. R. J. Gary, Executive Vice } President and General Manager 2001 Bryan Tower D=11==, Texas 75201 t i Gentlemen: !i This refers to the-inspection activities performed by our Resident Inspector, Mr. R. G. Taylor, for the periods of August and September 1979, of activities ~ authorized by NRC Construction Permits No. CPPR-126 and 127 for the Comanche l Peak facility, Units No. I and 2, and to the discussion of our findings with j Mr. R. G. Tolson and other members of your staff during the inspection period., j r Areas av==4nad during the inspection and our findings are discussed in the enclosed inspection report. Within these areas, the inspection consisted of ~ selective eF2*ination of procedures and repreSantative records, interviews With personnal, and observations by the inspector.. l During the inspection, it was fou'nd~that certain. activities under your license appear to be in noncompliance with Appendix 3 to'10 CFR 50 of tha NRC Regula-i tions, " Quality Assurance Criteria for N= 1==r Power Plants." l The Notice of Violation for theiitems of noncompliance reported.in the enclosed inspection report were forwarded to you by our letter dated September 24, 1979; therefore, this letter does not require further response regarding this matter. s We have also examined actions you have taken with regard to previously identified l l inspection findings. The status of these items is identified in paragraph 2 of the enclosed report. AA j ~* j } ~ i t .E.> W \\ .......4...'....... i ,... g pr/4g" " ACrossman .WCSeid e WEV er "W'd7d7N"'""'"lUTjf/N" " " d7 /75" ,10/15/79 l / =* mcsoeu m o.m meuom y c.,.,.,,, y ; y,s. w w -t u - - -./Ad
J 9 NOV 1979 Tazas Utilities cenerating Company 2 i i report. li One new unresolved item is identified in paragraph 8 of the enclosed ll'l In accordance with Section 2.790 of the NRC's "Ru3as of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document Room. If the report contains any information that you believe to be proprietary, it is necessary that you submit a written application to this office, within 20 days of the date of this letter, requesting that such information be withheld from public disclosure. The application must include a full statement of the rea-sons why it is e1 4H that the information is proprietary. The application must ine1=de a full stae===ae of the reasons why it is claimed that tha infor-nation identified is cone =4n=d in an -1a-a to the application, since the app 14a=*4m without the ene1-- ee will also be placed in tha Public Document Room. If we do not hear from you in this regard within the specified period, i1 the report will be placed in the Public nae --ne geout. I !i Should you have any questions ww4 this inspection, we will be pleased !i to discuss them with you. Stacerely, Original siped by l! W C. Seidle - W. C. hidla, Chief Reactor Construction and l Engineering Support Branch i IE Inspection Esport No. 50-445/79-18 f
Enclosure:
~ i 50-446/79-18 cc: w/ enclosure Texas Utilities Generating C e 7 i t ATTN: Mr. H. C. Schmidt, Project Manager 2001 Bryan Tower l, n=11==, Texas 75201 bec to Reproduction Unit 1 bec to DAC:ADM for distribution 9 NOV 19,6 for distributicip(/- A /J 'lI AD/RCI (Reinmuth) Central Files ~ IE Files PDR Standards Development LPDR EL'D TIC NRR (9 Cys)2/ NSIC ~ ~ r bec distributed by RIV Q 77 l ' Texas Dpt. of Health Resources ...,m..-_-.y v.--._.- ,,,n.,- .__,,,_.,,-,~y, ,..,-..rm..,,,_,,.._y...,-
U. S. NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT i REGION IV Report No. 50-445/79-18; 50-446/79-18 i Docket No. 50-445; 50-446 Category A2 I Licensee: Texas.Utilties Generating Company 2001 Bryan Tower Dallas, Texas 75201 Facility Name: Comanche Peak, Units 1 & 2 Inspection at: Comanche Peak Steam Electric Station, Glen Rose, Texas Inspection conducted: August and September 1979 Inspector: M,MYM /w / / /o /> /p 9 R. G. Ta'ylor, ~ Resident Reactor Inspector, Projects Section Date Approved: [ /C[/7/7f W. A. Crossman, Chief, Projects Section Date Inspection Summary: Inspection for August and September 1979 (Report No. 50-445/79-18; 50-446/79-18) Areas Inspected: Routine inspection by the Resident Reactor Inspector (RRI) of safety related construction activities including installation and welding of reactor coolant and other. piping systems; electrical cable and component instal-lation and testing; placement of containment concrete; equipment maintenance and storage; Authorized Nuclear Inspector activities; calibration of tools and equipment; and follow up on previously identified inspection findings. The inspection involved one hundred forty-seven inspector-hours by the RRI. Results: Of the nine areas inspected, no items of noncompliance were identified in six. Four items of noncompliance were identified in three areas (infraction - failure to follow procedures for calibration of welding machines - para-graph 9.b.(2); infraction - failure to train and indoctrinate QC personnel - paragraph 6.a.; deficiency - failure to properly record inspections - para-graph 8.b.; and deficiency - failure to control QC inspection stamps para-graph 8.c.). W 4 .w. ~ s- - - - -,we, w , - ~, - y w -,,,,-~-- ~, - - - -, ,-v-pe-.-~p-y,,m----
j DETAILS 1. Persons Contacted Principal Licensee Employees
- R. G. Tolson, TUGCO, Site QA Supervisor
- D. N. Chapman, TUGCO, QA Manager
- J. B. George, TUSI, Project General Manager
- J. R. Merritt, TUSI, Construction & Engineering Manager Other Persons
- U. D. Douglas, Brown & Root Construction Project Manager
- J. P. Clark, Brown & Root Project QA Manager
- J. V. Hawkins,. Brown & Root QC Supervisor The RRI also interviewed other licensee and contractor employees during the inspection period. The RRI also interviewed one of the Authorized Nuclear Inspectors assigned to the site by Hartford Steam Boiler.
- Denotes those persons with whom the RRI held on-site management interviews.
2. Action on Previous Inspection Findings (0 pen) Infraction (50-445/79-11): Failure to Implement the Quality Assurance Program for Civil Construction. The licensee notified RIV by letter dated June 12, 1979, that action had been taken to instruct construction concrete supervisory personnel of their responsibilities for involvement in concrete activities in the future. The RRI. interviewed the appropriate supervisory personnel involved and ascertained that necessary specific instructions have been issued and emphasized. The item remains open pending completion of the investigation of the in place concrete by the licensee's consultant. (Closed) Infraction (50-445/79-04; 50-446/79-04): Failure to Follow Equipment Maintenance Instructions. -The licensee notified RIV by letters dated March 20 and April 12, 1979, of the immediate and long term preventive and cor-rective actions related to this infraction. The RRI verified that all meas-ures committed to in the letters have been implemented and, therefore had no further questions. 3. ASME Certification System The RRI verified that the licensee and his contractor have been authorized to accomplish piping system fabrication and installation by the American Society of Mechanical Engineers (ASME) as follows: The FSAR, in Section 3.2, indicates the applicable Code version a. in effect for piping systems to be ASME Section III,1974. The actual Code in effect is the 1974 version through the Summer 1974. 2
t The RRI interviewed the QC personnel of record for the most recent mainte-nance actions and found them to be knowledgeable of the requirements for the units. No items of noncompliance or deviations were identified. 12. Unit 2 Containment Concrete Placement Activities a. Placement 201-5805-026 Early in the inspection period, the RRI observed, over a span of several days, the activities involved in preparing for and the placing approxi-mately 460 cubic yards of concrete in the wall of the Unit 2 containment between elevations 955 to 961 feet. The placement is identified in the - construction documentation as 201-5805-026. The RRI selectively verified that reinforcing steel in accordance with the design drawings had been installed in the area of examination. Sev-eral "Cadwelds" were examined by the RRI and gave the visual appearance of having been satisfactorily made. The qualification data and the sequential test record's for the "Cadwelders" were inspected and found to meet requirements. The RRI examined the form work for clearance and cleanliness at the initiation of placement of the concrete and also found that requirements had been satisfied. The actual placement of concrete during the time of observation was accomplished in a workman-like manner. The RRI visited the concrete batch plant and aggregate storage areas during the placement span and found everything in order with the exception that a portion of the automatic electronic control of the batch plant had failed. The batching facilities were, however, being properly manually controlled to provide the ingredients required for the grout and normal concrete mixes. The RRI also verified that the licensee QC personnel assigned to the actual placement, to the concrete test stations and to the batch plant were present and attentive to the activities for which they were responsible. No items of noncompliance or deviations were identified. b. Placement 201-5805-032 On September 4, 1979, the licensee Site QA Supervisor notified the RRI that a quantity of shear tie reinforcing steel (cross-connecting the reinforcing steel on the inside face of the wall to the outside face steel) had been omitted from placement 201-5805-032. The omission d was reported by an ironworker foreman. The shear ties are additional D steel comparable to reinforcement utilized throughout the entire ele-e ' vation and were called for in the design to take localized stresses just below the springline of the wall to the building hemispherical dome. 13 4 -.,-a n .g, -.n,g-
The licensee stated that the engineer had directed the placement of the missing steel in the next placement (201-5805-033) and that the structural integrity of the containment was not affected. The RRI inquired as to why this matter had not been reported to the RRI as a " potential" significant construction deficiency in accordance with 10 CFR 50.55(e) at the time of initial identification of the problem on August 27 rather than after the fact on September 4, 1979. The licensee informed the RRI that he had applied the various judge-mental factors involved in 50.55(e) and had determined that the matter was not significant and therefore, not reportable. The RRI reviewed the documentation and reported the situation to Region IV management. Subsequent discussions between licensee and NRC manage-ment resulted in the licensee issuing a stop-vork order on further concrete placement in the Unit 2 wall and dome pending a thorough technical review of the matter. These discussions and confirmation of the stop-work order were documented in a Region IV letter to the licensee dated September 7, 1979. The licensee's Architect / Engineer developed an engineering analysis indicating that the additional steel placed into concrete placement zone 201-5805-033 adequately compensated for the added steel missing in 201-5805-032. The licensee and personnel representing the A/E met with NRC person-nel on September 14, 1979, to discuss the technical details of the engineer's analysis and to discuss the measures proposed by the licensee to prevent such occurrences in the future. The licensee proposed to augment his normal QC operation, which had missed the original reinforcing steel shear tie omission through human error, with a documented special inspection by the ironworker supervision and an additional ironworker steel detailer. The licensee released the stop-vork order on September 18, 1979, after the RRI verified that the committed additional actions had taken place. 13. Unresolved Items l Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of non-compliance, or deviations. One such unresolved item is discussed in paragraph 8 of this report. 14. Management Interviews The RRI had interviews with one or more of the-licensee and construction management persons designated in paragraph 1 on September 4, 6, 7, 11, 12-and 13, 1979. The RRI's inspection findings and certain licensee actions within the period were discussed. 14
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- p U. S. NUCLEAR REGULATORY CO)S:ISSION b(f 0FFICE OF INSPECTION AND ENFORCEMENT '/
REGION IV Ieport No. 50-445/79-26; 50-446/79-25 Docket No. 50-445; 50-446 Category A2 Licensee: Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 Facility Name: Comanche Peak, Units 1 & 2 Investigation at: Co=anche Peak Steam Electric Station, Glen Rose, Texas Investigation conducted: October 11-22, 1979 Inspector:4. f'. Mud-cMu //[?/27 p R. G. Taylor, Resident Reactor Inspector, Projects Date Section Approved: k //[8/79 fe W. A. Crossman, Chief, Projects Section Date Investigation Su=rnarv: Investigation on October 11-22, 1979 (Renort No. 50-445/79-26: 50-446/79-25) Areas Investigated: Special investigation of allegations by a former site construction worker of improprieties in the civil construction phase of this facility. The investigation involved ten inspector-hours by one NRC inspector. Results: Three of the allegations were determined to be factual, but without merit since they had been detected and corrected within the licensee's QA program. One allegation had no merit and one could be neither substantiated nor refuted. ng g q,q j j G' //f}'l l -er hw c
~ e 4 INTRODUCTION Co=anche Peak Steam Electric Station (CPSES), Units 1 and 2 are under con-struction in Somervell County, Texas, near the town of Glen Rose, Texas. Texas Utilities Generating Company is the Construction Permit holder with Brown and Root, Inc. as the Constructor and Gibbs and Hill, Inc. as the Architect / Engineer. REASON FOR INVESTIGATION A person who visited the Region IV office made allegations of construction improprieties at the Comanche Peak Stat' ion.
SUMMARY
OF FACTS A person who identified himself as a former Brown & Root employee visited the Region IV office at approximately 4:00 p.m. on October 9, 1979. The person stat,ed that he wished to discuss deficiencies in safety-related construction at the Comanche Peak Station. The person was then interviewed by personnel of the Region IV, Reactor Construction and Engineering Support Branch. The interview developed the following allegations: Allegation 1: ~ C [k,9b k In the. Unit 1 Auxiliary Building at elevation 807', rebar was omitted in four co'lu=ns in the EA wall.' The alleger stated that he had acquired the infor=ation from his general' foreman and that site engineering personnel (names unknown) were aware of the omission. Allegation 2: Intheinit1AuxiliaryBuilding,the-concreteslabactingastheceiling above elevation (floor) at 832', in the area just before entry into the Unit 1 Safeguards Building, had a 20' x 20' honeycocb area which was exposed upon concrete form removal. The alleger indicated that he was aware of the corrective action taken, but felt it had been si= ply dry-packed. Allegation 3: In Unit 1 Containment, there had been a mixup in anchor bolts. The alleger indicated that 3000 anchor bolts had been interchanged, some having been furnished by " Boston Made" and others by " Southern Made." Allegation 4.a: There is general cracking of floor slab concrete in the plant buildings. Allegation 4.b: $[g Horizontal tie rebar was omitted in Unit 1 Containment / Containment Wall. 1
CONCLUSIONS The following conclusions are based on review of various documents, technical literature, and observations by the NRC Resident Reactor inspector. Supporting documentation for these conclusions are referenced in the attached details. Allegations 1, 2 and 3: These allegations were found to be based on factual events that had been detected and documented within the context of the licensee's Quality pgCJ'q)\\ Assurance system as required by Appendix B to 10 CFR 50. Two of three alleged events were corrected in accordance with sound engineering practices, while the third was evaluated by the engineer and found to be adequate in the "as is" condition. Allegation 4.a: This allegation has no apparent merit. Hairline surface cracks in concrete are not considered to have any effect on structural integrity. Allegation 4.b: This allegation could neither be substantiated nor refuted based on avail-able evidence but is thought:to refer to an event involving the omission ri(,- of horizontal ties in the upper part of the Unit 2 Containment wall which g is discussed in Inspection Report No. 50-445/79-18; 50-446/79-18. 1.
DETAILS 1. Persons Contacted Alleger - A person, referred to as the alleger in the text of this report, who was previously employed by Brown & Root (B&R) at CPSES. Princinal Licensee Employees Site Quality Assurance Supervisor Site Resident Manager Principal Brown & Root Employees Site Chief of Security 2. Backcround Information At approximately 4:00 on October 9, 1979, a former Brown & Root employee " walked-in" to the RIV office indicating that he had allegations regarding deficiencies in safety-related construction at Comanche Peak. During the ensuing interview, the following specific allegations were obtained: In the Unit 1 Auxiliary Building at elevation 807', rebar was omitted a. in four columns in the EA wall. This construction was co=pleted in <[f) early 1978, probably in March or April. The omission of a portion of ')(,7 the prescribed rebar was reported to him by his rebar General Fore =an. He also indicated that a Gibbs & Hill (G&H) or B&R engineer also was aware of the omission; however, he could not recall his name. b. Also, in the Unit 1 Upper Auxiliary Building, the concrete slab poured for the ceiling above the elevation 832' level, in the area just before entry into Safeguards Building 1, had a 20' x 20' honeycomb area which was exposed upon removal of forms. He was not aware of corrective action taken; however, he felt that it had simply been dry-packed. This placement was made in August or September of 1978. c. In Unit 1 Containment, there had been a mixup in anchor bolts. He indicated that 3000 anchor bolts had been interchanged, some having been furnished by " Boston Made" and others by " Southern Made." l d. Two unsupported general allegations were also made regarding general cracking of floor slab concrete in the plant buildings and omitted horizontal tie rebar in the Unit 1 Containment wall. Without specifics, the alleger was advised that these could not be pursued. 3. Investigation The above allegations were forwarded to the NRC Resident Reactor Inspector (RRI) at CPSES for review and investigation. The RRI obtained and reviewed the Brown & Root personnel file on the alleger to establish that the alleger . i
.s could nasonably have some knowledge of the alleged improprieties. It ~ was establish,ed that he had been employed at the site during the occurrence of most or all of the alleged incidents. The RRI discussed the allegations with the site QA Supervisor who then informed the RRI that essentially the same allegations had been telephoned to the President of TUSI/TUGCO by the alleger on October 4, 1979. The allegations received by.the President of TUSI/TUGC0 were forwarded through licensee management channels to the Resident Manager for investigation. An interview of the Resident Manager indicated that allegations 1 and 2 made to the NRC were the same as two made to the licensee. The alleger apparently did not restate allegations 3 and 4 to the licensee but added i two others involving a scheme for pilferage of "consumables."; i.e., non-safety material such as lumber and ice chests. The licensee's site QA Supervisor was found to have initiated a search for data relating to allegations 1 and 2 based on the comparable allegations made to the President of TUSI/TUGCO. His search revealed two Brown and Root Nonconformance Reports (NCRs) bearing directly on allegations 1 and 2. These will be discussed later in this report. '[ The RRI' asked that a comparable' search be initiated relative to allegations -3 and 4 received by the NRC. A complete document package on allegation 3 was i= mediately offered to the RRI covering allegation 3. The search relative to allegation 4 was not possible due to the lack of specificity. 4. Analvsis of Alle_ations c Allegation 1: Omission of Reinforcing Steel from Colu=ns in the Unit 1 Auxiliary Building Reference to design drawings revealed that there are,only four colu=ns in the EA wall of the Auxiliary Building. (See Figure 1,2-33 of the FSAR) These columns, as well as the entire EA vall, extend virtually from the building foundation to the roof. Brown and Root NCR C-806, dated October 27, 1977, stated that it had been discovered, while erecting reinforcing steel for the EA wall above elevation 831', that reinforcing steel in four columns had been omitted in the preceding erection activity; i.e., between elevation 807' through 831'. The L[Q NCR stated that twelve bars, each one inch in diameter, were omitted from each column and that four separate earlier concrete placements h were involved during a period from May through October 1977. The NCR information was submitted to the Architect / Engineer for resolution 4 which was provided by Design Change / Design Deviation Authorization No. 486, dated November 1, 1977, authorizing not only the emission of the steel between 807' and 831' elevation, but further directing that it be omitted in the. balance of the columns through elevation 873'. The engineer stated that the omission of the steel would still allow the column to accept all design loads with adequate margins. The RRI -reviewed the involved design detail drawing in conjunction with this analysis and determined that the omitted steel constituted 50% of the vertical. steel on one of the four column faces and that the remaining steel is of the same spacing as the comparable steel in the wall face continuing from column to column. -S-
- s... '
The only unaccounted for disparity between the allegation and the referenced NCR is that of dates of occurrence, a difLerence of five to six months. The RRI has concluded that the the allegation and the NCR are related to the same event since the allegation, as stated, y,h\\ was hearsay information and the construction of the columns involved was a one time event. Therefore the alleged time frame is in error. The RRI had no further questions regarding this allegation. Allegation 2: Honeycomb in Concrete Slab in the Unit 1 Auxiliary Building The licensee research revealed that NCR C-1034, dated July 19, 1978, had been prepared to document the concrete honeycomb areas involved in this allegation. The Architect / Engineer's direction was to re=ove the honeycomb back to sound concrete. The void area was then to be filled with dry-pack concrete and/or small size coarse aggregate con-crete, all in accordance with a standard, engineer approved, repair procedure for such work. The RRI observed various phases of the repair work from August 1978 through January 1979 when the repair was finally completed. None of the ob'servations indicated a need for concern on -the part of the RRI since the work vas being done in a =anner typical of acceptable methods of repairing such concrete structures. A11ecation 3: Mixup in Anchor Bolts The licensee's site QA Supervisor indicated a matter similar to this allegation had been the subject of a "possible" Significant Con-struction Deficiency Report to the NRC, Region IV office in 1977. He offered a substantial file folder for the RRI's review. The file contained copies of Brown and Root Nonconformance Reyorts M-704 and M-722, dated July 18 and July 25, 1977, respectively. The reports describe a mixup in a group of about 2000 bolts and nuts used for embedded equipment anchorages which were supplied in part by Bostrom-Bergen Metal Products (Boston Made) and Southern Bolt Co. (Southern Made). It was not significant who supplied the nuts and bolts but rather that each supplier had been authorized to supply nuts and bolts of somewhat different steels in terms of chemicci composition. One composition was amenable to tack welding of the nut to-tne bolt prior to embedment in concrete while the other was not. The NCRs describe a combined engineering and construction management solution to properly identify the differing materials and to uti4tze thh materials which could not be readily welded in a different metdod of assembly. The above matter was reported to the NRC and was followed to conclusion as indicated in Inspection Report 50-445/77-09. The RRI had no further questions relative to this allegation. t-m y ---,,.r + y
.s, Allegation 4: As indic'ated under paragraph 2, this allegation includes two separate items which will so be treated in this analysis. Allegation 4.a: General Floor Cracking During the past fifteen months, the RRI has toured all of the safety-related plant areas several times each month. The RRI has not observed cracks in the floors of the buildings that he would consider significant in terms of possible structural failure; i.e., cracks which are open to such an extent that awl or pick can be inserted to a substantial depth in the crack. The RRI would expect fine hairline surface cracking to occur and normally not notice it. Such hairline cracks are an unavoidable occurrence in heavily reinforced concrete structures, particularly in walls or floors with a relatively thick cross-section. According to recognized technical literature such as the U. S. Department of the Interior's " Concrete Manual," the cracking is caused by differing amounts of thermal expansion between the interior of the member and its exterior created by the chemical reaction ~~ process referred to as hydration and commonly called curing. Such cracking is usually very tight and when investigated, extends only into the concrete to the most exterior layer of reinforcing steel, typically one to two inches below the surface. This type of cracking is not considered to have any effect on the integrity of the structure. Allegation 4.b: Omitted Horizontal Ties in Containment 1 Walls The RRI has not been able to either effectively substantiate or to refute this allegation. It is hypothesized that the alleger ab misconstrued an event which occurred in the Unit 2 Containment wall just before his final period of employment. This event Ah# involved the initial omission of horizontal ties (more commonly referred to as shear ties) in the upper part of the Unit 2 Con-tainment wall and is discussed in Inspection Report No. 50-446/ 79-18. This hypothesis is based on substantial indications that all of the allegations made were essentially based on hearsay information relative to events about which the alleger had little or no personal knowledge.. ww ey--- e-y --,,+-w-p.m--e-- w-- ,-r-, e -y--,-=ee-r +1er-*+ ewe-e w. =-~P-e-
OVERSIZE DOCUMENT PAGE PULLED SEE APERTURE CARDS NUMBER OF PAGES: ACCESSION NUMBER (S): 5'6IQ cGL o/ OQ l l l APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH,TIDC FTS 492-8989
U. S. NUCLEAR REGUI.ATORY ComISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION IV Report No. 50-445/79-26; 50-446/79-25 Docket No. 50-445; 50-446 Category A2 Licensee: Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 Facility Name: Comanche Peak, Units 1 & 2 Comanche Peak Steam Electric Station, Glen Rose, Texas Investigation at: Investigation conducted: October 11-22, 1979 hb79 4 f#Mvbdv Inspector: Date p R. G. Taylor, Resident Reactor Inspector, Projects Section e r - //[8/79 k Approved: Date W. A. Crossman, Chief, Projects Section Investigation Su::Imary: Investigation on October 11-22. 1979 (Report No. 50-445/79-26; 50-446/79-25) Special investigation of allegations by a former site Areas Investigated _: construction worker of improprieties in the civil construction phase of this The investigation involved ten inspector-hours by one NRC inspector. facility. Three of the allegations were determined to be factual, but without Results: merit since they had been detected and corrected within the licensee's QA One allegation had no merit and one could be neither substantiated program. nor refuted. / Csi i
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INTRODUCTION Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 are under con-struction in Somervell County, Texas, near the town of Glen Rose. Texas. Texas Utilities Generating Company is the Construction Permit holder with Brown and Root, Inc. as the Constructor and Gibbs and Hill, Inc. as the Architect / Engineer. l REASON FOR INVESTIGATION A person who visited the Region IV office made allegations of construction ~ improprieties at the Comanche Peak Station. t
SUMMARY
OF FACTS A person who identified himself as a former Brown & Root employee visited the Region IV office at approximately 4:00 p.m. on October 9, 1979. The person stated that he wished to discuss deficiencies in safety-related construction at the Comanche Peak Station. The person was then interviewed by personnel The of the Region IV Reactor Construction and Engineering Support Branch. interview developed the following allegations: Allecation 1: In the[ Unit 1 Auxiliary Building at elevation 807', rebar was omitted in four columns in the EA wall.' The alleger stated that he had acquired the information from his general' foreman and that site engineering personnel (namas unknown) were aware of the omission. Allegation 2: / In the' Unit 1 Auxiliary Building, the concrete slab acting as the ceiling above elevation (floor) at 832', in the area just before entry into the g/ 33 Unit 1 Safeguards Building, had a 20' x 20' honeycomb area which was exposed upon concrete form removal. The alleger indicated that he was aware of the corrective action taken, but felt it had been simply dry-packed. Allegation 3: In Unit 1 Containment, there had been a mixup in anchor bolts. The alleger indicated that 3000 anchor bolts had been interchanged, some having been I furnished by " Boston Made" and others by "Sou,thern Made." l e Allegation 4.a: I There is general cracking of floor slab concrete in the plant buildings. Allegation 4.b: Horizontal tie rebar was omitted in Unit 1 Contain=ent/ Containment Wall. -
f CONCLUSIONS The following conclusions are based on review of various documents, technical literature, and observations by the NRC Resident Reactor Inspector. Supporting documentation for these conclusions are refarenced in the attached details. Allegations 1, 2 and 3: I These allegations were found to be based on factual events that had been detected and documenteo within the context of the licensee's Quality Assurance system as required by Appendix B to 10 CFR 50. Two of three alleged events were corrected in accordance with sound engineering practices, while the third was evaluated by the engineer and found to be adequate in the "as is" condition. Allegation 4.a: This allegation has no apparent merit. Hairline surface cracks in concrete are not considered to have any effect on structural integrity. Allegation 4.b: I This allegation could neither be substantiated nor refuted based on avail-j able evidence but is thought to refer to an event involving the omission of horizontal ties in the upper part of the Unit 2 Containment wall which is discussed in Inspeccion Report No. 50-445/79-18; 50-446/79-18. ( f b i I f i I
DETAILS 1. Persons Contacted A11eger - A person, referred to as the alleger in the text of this report, who was previously employed by Brown & Root (B&R) at CPSES. Principal Licensee Emoloyees Site Quality Assurance Supervisor Site Resident Manager Prineinal Brown & Root Employees Site Chief of Security 2. Background Information At approximately 4:00 on October 9, 1979, a former Brown & Root employee " walked-in" to the RIV office indicating that he had allegations regarding deficiencies in safety-related construction at Comanche Peak. During the ensuing interview, the following specific allegations were obtained: In the Unit 1 Auxiliary Building at elevation 807', rebar was omitted o a. j7 in four columns in the EA wall. This construction was completed in early 1978, probably in March or April. The omission of a portion of the prescribed rebar was reported to him by his rebar General Foreman. f He also indicated that a Gibbs & Hill (G&H) or B&R engineer also was aware of the omission; however, he could not recall his name. b. Also, in the Unit 1 Upper Auxiliary Building, the concrete slab poured for the ceiling above the elev~ation 832' level, in the area just before entry into Safeguards Building 1, had a 20' x 20' honeyecmb area which was exposed upon removal of forms. He was not aware of corrective action taken; however, he felt that it had simply been dry-packed. This placement was made in August or September of 1978. c. In Unit 1 Containment, there had been a mixup in anchor bolts. He indicated that 3000 anchor bolts had been interchanged, some having been furnished by " Boston Made" and others by " Southern Made." og d. Two unsupported general allegations were also made regarding general 90 cracking of floor slab concrete in the plant buildings and omitted horizontal tie rebar in the Unit 1 Containment wall. Without j specifics, the alleger was advised that these could not be pursued. 3. Investigation The above allegations were forwarded to the NRC Resident Reactor Inspector (RRI) at CPSES for review and investigation. The RRI obtained and reviewed the Brown & Root personnel file on the alleger to establish that the alleger - - - -
~ - - 3 could reasonably have some knowledge of the alleged i= proprieties. It was established that he had been employed at the site during the occurrence of most or all of the alleged incidents. t l The RRI discussed the alle'gations with the site QA Supervisor who then informed the RRI that essentially the same allegations had been telephoned to the President of TUSI/TUGC0 by the alleger on October 4, 1979. The allegations received by the President of TUSI/TUGC0 were forwarded through licensee management channels to the Resident Manager for investigation. An interview of the Resident Manager indicated that allegations 1 and 2 made to the NRC were the same as two made to the licensee. The alleger apparently did not restate allegations 3 and 4 to the licensee but added two others involving a scheme for pilferage of "consumables"; i.e., non- } safety material such as lumber and ice chests. i The licensee's site QA Supervisor was found to have initiated a search for data relating to allegations 1 and 2 based on the comparable allegations made to the President of TUSI/TUGCO. His search revealed two Brown and Root Nonconformance Reports (NCRs) bearing directly on allegations 1 and 2. These will be discussed later in this report. t The RRI asked that a comparable search be initiated relative to allegations 3 and 4 received by the NRC. A complete document package on allegation 3 i was immediately offered to the RRI covering allegation 3. The search relative to allegation 4 was not possible due to the lack of specificity. l 4. Analvsis of Allegations 1 Allegation 1: Omission of Reinforcing Steel from Columns in the Unit 1 Auxiliary Building Reference to design drawings revealed that there are only four columns 1 in the EA wall of the Auxiliary Building. (See Figure 1.2-33 of the FSAR) These columns, as well as the entire EA wall, extend virtually from the building foundation to the roof. Brown and Root NCR C-806, 4 dated October 27, 1977, stated that it had been discovered, while 4 erecting reinforcing steel for the EA wall above elevation 831', that j reinforcing steel in four columns had been omitted in the preceding erection activity; i.e., between elevation 807' through 831'. The i NCR stated that twelve bars, each one inch in diameter, were omitted from each column and that four separate earlier concrete placements were involved during a period from May through October 1977. The NCR information was submitted to the Architect / Engineer for resolution which was provided by Design Change / Design Deviation Authorization No. 486, dated November 1, 1977, authorizing not only the omission of the steel between 807' and 831' elevation, but further directing that it i be omitted in the balance of the columns through elevation 873'. The engineer stated that the omission of the steel would still allow the column to accept all design loads with adequate margins. The RRI i reviewed the involved design detail drawing in conjunction with this onalysis and determined that the omitted steel constituted 50% of the vertical. steel on one of the four column faces and that the remaining steel is of the same spacing as the comparable steel in the wall face continuing from column to column. -S-l r-w-r-. ,.,,,sw-. .~,..-c,-.m-r--,-,.,,r-v,.,.,.,-e,- .-,ee,..,-*,,-w.,w, e,,_w-.
The only unaccounted for disparity between the allegation and the referenced NCR is that of dates of. occurrence, a difference of five i to six months. The RRI has concluded that the the allegation and the NCR are related to the same event since the allegation, as stated, was hearsay information and the construction of the columns involved was a one time event. Therefore the alleged time frame is in error. 4 The RRI had no further questions regarding this allegation. Allegation 2: Honeycomb in Concrete Slab in the Unit 1 Auxiliary Building The licensee research revealed that NCR C-1034, dated July 19, 1978, had been prepared to document the concrete honeycomb areas involved g'}- in this allegation. The Architect / Engineer's direction was to remove e.J the honeycomb back to sound concrete. The void area was then to be filled with dry-pack concrete and/or small size coarse aggregate con-1 crete, all in accordance with a standard, engineer approved, repair procedure for such work. The RRI observed various phases of the repair work from August 1978 through January 1979 when the repair was finally completed. None of the observations indicated a need for concern on the part of the RRI since the work was being done in a manner typical of acceptable methods of repairing such concrete structures. l Allegation 3: Mixup in Anchor Bolts l The licensee's site QA Supervisor indicated a matter similar to this j allegation had been the subject of a "possible" Significant Con-struction Deficiency Report to the NRC, Region IV office in 1977. He offered a substantial file folder for the RRI's review. The file contained copies of Brown and Root Nonconformance Reports M-704 and M-722, dated July 18 and July 25, 1977, respectively. The reports describe a mixup in a group of about 2000 bolts and nuts used for embedded equipment anchorages which were supplied in part by 4 Bostrom-Bergen Metal Products (Boston Made) and Southern Bolt Co. (Southern Made). It was not significant who supplied the nuts and bolts but rather that each supplier had been authorized to supply nuts and bolts of somewhat different steels in terms of chemical composition. One composition was amenable to tack welding of the nut to the bolt prior to embedment in concrete while the o:her was not. The NCRs describe a combined engineering and construction management solution to properly identify the differing materials and to utilize the materials which could not be readily welded in a different method of 1 assembly. The above matter was reported to the NRC and was followed to conclusion as indicated in Inspection Report 50-445/77-09. The RRI had no further questions relative to this allegation. i ' .-.m 4.m. - -, --ir
4 Allecation 4: As indicated under paragraph 2, this allegation includes two separate items which will so be treated in this analysis. Allegation 4.a: General Floor Cracking During the past fifteen months, the RRI has toured all of the safety-related plant areas several times each month. The RRI has not observed cracks in the floors of the buildings that he would consider significant in terms of possible structural failure; i.e., cracks which are open to such an extent that awl or pick can be inserted to a substantial depth in the crack. The RRI would ${s( ' I) expect fine hairline surface cracking to occur and normally not notice it. Such hairline cracks are an unavoidable occurrence in heavily reinforced concrete structures, particularly in valls or floors with a relatively thick cross-section. According to recognized technical literature such as the U. S. Department of the Interior's " Concrete Manual," the cracking is caused by differing amounts of thermal expansion between the interior of 1 the member and its exterior created by the chemical reaction process referred to as hydration and commonly called curing. Such cracking is usually very tight and when investigated, extends l only into the concrete to the most exterior layer of reinforcing steel, typically one to two inches below the surface. This type of cracking is not considered to have any effect on the integrity of the structure. Allegation 4.b: Omitted Horizontal Ties in Containment 1 Walls The RRI has not been able to either effectively substantiate or to refute this allegation. It is hypothesized that the alleger misconstrued an event which occurred in the Unit 2 Containment 4 wall just before his final period of employment. This event involved the initial omission of horizontal ties (more commonly referred to as shear ties) in the upper part of the Unit 2 Con-tainment wall and is discussed in Inspection Report No. 50-446/ 79-18. This hypothesis is based on substantial indications that all of the allegations made were essentially based on hearsay information relative to events about which the alleger had little or no personal knowledge. i __
OVERSIZE DOCUMENT PAGE PULLED SEE APERTURE CARDS i NUMBER OF PAGES:_ ACCESSION NUMBER (S): 25/2nLOJ/ / 95/G6 RA //(o i l 'l APERTURE CARD /HARD COPY AVAIL.ABLE FROM RECORD SERVICES BRANCH,TfD i FTS 492-3939 l
Figure 2.7-1 Pact i ;; C C '..t.'ui Cu.= ' =..Y_s' S '- =.' '.r =. = = C".' =,_' S T_.r. " 7 ^ ' '. r v. DESIG'? CHANGE /DESIG;; DEVIATI0l! AUTHORIZATIC:. ,.. - -. ) (,.. - -. mss *xe,) _7 s. 0 P.3,, u.,. - D w _: L o .:v t. nLr. 0 3,t c e.. w,.,. .s.. t.. ..u. 7.,,2. d i G. 7 ..,:, w,7,c.. -,1a. 1.2 v S.1.=. =~t.-**=.'..=D-. .( a' ~ ~. C z..,,.,,. / w- -...r.. - _tyi/ wm. - - - w.-. - - -.., ,t = S C,. e t 10,.,, O: e _c, v: .w u. m:- as A. APPLICA3LE SPEG/D57G/DCGi'5iiG 23n <:_n7:7 12 1 7 7-r Rev. Issu2 1--_ ~
- 3. DETAILS The wall reinforcement across the face of the columns sbet:n in Details 109 & 119 were cmit*elabove elevation 810'6" Solution: The columns reinforced without the wall bars within t he li-4 --
of the column are cacable of withstandinc the desien loads. The 7271 b' within the limits of the columns are to be omitted through elevatica 373'-5" ._..m., ,..n.. r"P!!. 9
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. sn. h .2. G v e. U.h,d s 7; - y SUPPORTING COCDEtiTATIO:I C,'k l_Fo~Ib BSW C1D 2. l GTT-1697 1, I } 3. SIGATURES R.B.W./akh 11-1-77 A. AFPROVED BY: [ f /. - /. ____ / //,/ ? [Cb d. M ')cive [ f.1.- 7p_1sen a Da:e 3. A??R0t/ED BY: vy // -' .7'~ Rese.}~ D C g.M A m //r: c ~' W.zineer C) C. A??20T.'.D 37 : - T-7 Projecc ~ingir:Mr or EngMeering Superv.s cr Oc. ; 2 i. S ~. 4'be N...iD D 7. O..S 7 ' "L 1' 7 ..4 ~ ~ ~ s s-3 ~ U e r o L w.u.r_ r. e... _ :., m-J. 6 TUSI Dallas (6) 3&R Field (1) FOR FJ: CORD C:7T 'TUSI Field (1) 3&R Houston (1) FOR CLARI=~ CATIC'.: C'.P Y TUGCC Site QA (1) 3&R Site 0.A (1) x NEED.TO KSC:7 GLH Mew York (1) 3&R Hous ton QA (1) X ALL (A-~~'C~~I:} ECv~.E.~' 'i LT.E.~ ' 6 /4/ 27,p u v f 6)' PER ATTACHED LIST
1="rc+ Brown &RootJnc. Q' NONCONFORMANCE REPORT (NCR) b b' EXED k(, 2 GUALITY ASSURANCE DEPARTMENT CPSX STR-AB REBAR X 2323-S5-10 Rt.k 0 0,,,,,, PLANT SYSTEM COMPONENT T AG/ SPIN /IDENT NO I DR AWING / SPECIFICATION NO l SERI AL NO. . CODE CODE CODE A i 8lCIOIE IF l G; lunes) l H, tuneel i J; (Unes* l 14 5-10 11 16 17 56 FOR INFORMATION ONI.Y PURCH ASE ORDER VEND NUMBER CODE % 49 7473 C-806 102777 e i t .t t t t t .B 9 t i I f f f I I I E I 9 I I E 1
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t I t ie MRR RIR VENDOR *S COUNT UN6 73 PURCH"5 RLS/H3LO NO.l CODE INPW NUMSER NUMSER HE ATILOT/SATCH NO, OUANTITY OR NO. ST AT US DATE 74 79 SS85 06 95 96 105 108 111 112 121 122 127 i (23 McMCose rosasamG COMotTloMe Cited specification states in 6.4.1, " Reinforcing shall be accurately placed in accordance with the drawings..." ggg In the Aux. Bldg. at elevation 831'-6" it was discovered #9-wall verticals (12) at 4 locations were omitted at EA & 3A-4A & 6A-7A along the east column faces. The 13#11 column dowels were correctly installed. See attached sketches. Pour # involved: 002-4810-049 (5/20/77) 002-4810-020 (6/3/77) 002-4810-050 (6/3/77) 002-5831-001 (10/18/77) (3) REPoRTEDSV: Igel D ATE. I D. Mercier g7 3 [m E ve Ews Appmo v a64 _ ! 10-27-77 .3 PesPAmEn ev '(s) DATE-i g,, ga r g ; Neill Britton !10i27i f f g),77,7f 77 tog ossroseTson Assat.NEO To: lo op out D ATE: It s 3CommECTe vt AC nsowssT: gjgg 1:33 P,?C ^N [ H.C. Dodd, Jr. Ils11i77 MRequired at Reovired M k,0....u. -.jg+,o ,,,, o..Po... o.. g REwoAM R E P AI R USE AS IS SCRAP
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5 INSilluCTIONS I Olt COMPLL ilNG IHL NONCONI OllMANCE 141 POlt I B&R OA COMPLETE ITEMS s1 THilOUGH m12 1 CATA FIELD: To ise filled nui en accordance with Proirci Quehty instructiom s 2 NONCONFORMING CONDITION: A concise occur. iter description of the deficiency The dehneated description of the nonconformmg condition shall provide sufficient detal establishang (as applicable)-
- a. the document violated j
- b. sequence of events pertammg to *be nonconformance,
}
- c. accurate phasecal description of the nonconformance Schetches. pictures, and/or additional back up data, if required, shall be provided as attachments and refererw:ird
.l. REPORTED BY: Nente of individual reporting nonconformance. (indude organization and department! 4. DATE. Month / Day / Year isonconformance is reported. 5. PREPARED BY: Name of 88 R OA person propenng nonconformance report. S. DATE: Month /Dey/ Year nonooaformance report is prepared. 7. REVIEW / APPROVAL: Signature of Protect GA Meneger. Houston Omardinator. ur darugnee 3. DATE: Date of appeoval. 3. DISPOslTION ASSIGNED TO: The name of the person who is responsible for the disposition. 10. DUE DATE: Month / Day / Year by which the disposition is due from the assigned individual as agreed upon by the assigned organuation and QA. 11. CORRECTIVE ACTION REQUEST: Corrective action is required /not required; check as appropnate (Enter CAR a if required). 12. REPORTABLE DEFICIENCY. If a nonconformance may be considered signifscant as defmed en 10 CFR 50 Secteon 50.55 (el. check possible, if not, check no. THE ASSIGNED ORGANIZAllON IS RESPONSIBLE FOR COMPLETING ITEM =13 13. DISPOSITION: Action to ise taken to resolve /close the nonconformance. THE INDICATED ORGANIZATION SHALL COMPLETE ITEMS =14 THROU'3M m23 ITHE PHOJECT OA MAN AGER. HOUSTON COOllDINATOR. OR DESIGNEE MA ( "N/A" SPECIFIC REVIEWS / APPROVALS WHICH ARE NOT REQUIRED.HL SHAL L IfJill Al AND DATE SUCH ACTIONI. 14. CONSTR. REVIEW /APPROV AL: Signature of B&R Construction individual responsible for the approval of the disposition.
- 15. DATE: Month / Day /Yeae sit sulunettail
- 18. QA REVIEW / APPROVAL: begnatuse of B&R UA/OC Engmeer/ Supervisor as concurrance tnat the specified dispose. m can be accomplished in accordance with delmeated design, construction, and quality program requirements.
17. DATE: Month / Day / Year of B&R QA concurrance 18. CLIENT REVIEW / APPROVAL: Signature of Chent's Representative as acknowledgement. 19. DATE Month / Day / Year of chant approvel. 20. ENG REVIEW / APPROVAL: Signature of Engmeer (of P.E.. if apphcableiresponsiblefor design esatuation / changes. 21 DATE: Month / Day / Year of approval.
- 22. ANI VERIFICATION: Signature of Authonied Nuclear inspector as authnritation to proceed with delmeated disposstion action (Required only for "ASME Cnde" items).
- 23. DATE: Month / Day / Year of ANI approval ITEMS =24 THROUGH m30 SHALL BE COMPLETED BY B&R, OA AND THE ANI (lF REQUIRED)
CONCURRENTLY AS VERIFICATION /Rl" INSPECTION OF COMPLETED DELINE ATED DISPOSITION ACTION FOR COMPLIANCE TO SPECIFl!D REQUIREMENTS 24 VERIFICATION: Results of venfic.ition of disposition action completed /re mspection.
- 25. QA/OC ENGR /INSP VERIFICATION: Signature of QA/OC Engineer / Inspector performmg verification /re mspection 26.
DATE: Month / Day /Yeer of OC Venfication. 27. ANI VERIFICATION: Signature of Authonzed Nuclear Inspector performmg venfication/re-mspection 28. 'J AT E: Month / Day / Year of ANI wenfication/re inspection. 29. OA REVIEW / CLOSURE: Segnature of cognizant OA/QC Engmeer# Supervisor authonzmg closure 3L DATE: Month / Day / Year of NCR Closure
- 31. REM ARKS: Statements and notes pertmate to the nonconformance.
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i c.. . u ;' .'7 >L COMANCHE PEAK STEAM ELECTRIC STATION / (' d 0 'g C L; ~ DESIGN CHANGE / DESIGN DEVIATION AUTHORIZATI fg ,,2 e 's 9-T C'l 1 .~ (UILL)(F4LL*NGlE) BE INCORPORATED AUTHORIZAfION NO. 486 IN DESIGN DOCUMENTS. SAFETY RELATED: X YES NO 1. DESCRIPTION OF CHANGE /DEFsATW/EliaIFIMICn A. APPLICABLE SPEO/DWG/DG4TMNTr pap 1_s.n747 12 1-7-77 Rev. Issue Date B. DETAILS The wall reinforcement across the face of the columns shown in Details 109 & 119 were omittedabove elevation 810'6". Solution: The columns reinforced without the wall bars within the limits of the column are cacable of withstandino the desian loads. The wall bars within the limits of the columns are to be omitted through elevation 873'-6". IIMrnDHATiflM PMW ' lHE U51BTIFE E BUEW wwW ' 13 mi m run uruniaiiUh Giii-envrwr nnne swans FOR Cl!RRENT 2. SUPPORTING DOCUMENTATION EEW GTT-1697 3. SIGNATURES R.B.W./akh 11-1-77 A. APPROVED BY: / //--%.29 E["dMenafive[.fp Date h, -J -- //- Z-77 B. APPROVED BY: C. APPROVED BY: / h "7 m ProjWct 'tngitreifr or EngMeering Supervisor Date 4. STANDARD DISTRIBUTION 5. DOCUMENT CONTROL TUSI Dallas (6) B&R Field (1) FOR RECORD ONLY TUSI Field (1) B&R Houston (1) FOR CLARIFICATION ONLY TUGC0 Site QA (1) B&R Site QA (1 X NEED TO KNOW G&H New York (1) B&R Houston yA (lP X ALL (A_5ECIED) COCL?DT HOLIERS ~ 6/// 47gwf 6) PER ATTACHED LIST l s
8-3-78 $nf.7 Root.fnc. ~~ INTEROFFICE MEM0 15084 IM T0: Distribution FROM: J. Jardine
SUBJECT:
Recall of WES-12 Revision 1 WES-12 Revision 1 " Radial Shear Bar Fabication" is being recalled at this time because it is no longer needed for production use at CPSES. All radial shear bar fabrication at CPSES has been completed. /21ekY& J.fardidV ... -JAJ/.ARJ/dba Pr6 ject /leidingEngineer L. A. Ashley (IL) QA Vault (IL) ARMS (1L) D N Cr[L,1 1
0, ? W Date / To: Document Control From: Welding Engineering Dept. Sub: Transmittal of WES /2 Rev. -- Please distribute this in accordance with Master List No. / 3 SEC AL L ALL $cP/ES m / h er b*d Weld Data Control Center A H roject Welding Eng. fDMe~ Date h k Received Doc. Contl. / J e >--on u ir :. A Date & / ~7 / 7.2 i e e 6i-ep-
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f b A ff77 Date To: Document Control From: Welding Engineering Dept. Sub: Transmittal of WES - /2 Rev. / Please distribute this in accordance with Master List No. /.3 M Weld Data Control Center Appd. Project Welding Eng. ht1! ' / 7 Received Doc. Cont 1. / 4 ,/
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