ML20136A956
Text
{{#Wiki_filter:_ _ mm- --m-..- ~ $0 l-C07 D A/u A s INSTRUCTION ISSUE REVISION PAGE ^ TEXAS UTILITIES GENERATING CO. CPSES i CP-QP-0.14 16 JUL 0 31984 1 of 1 l PROCUREMENT / RECEIVING INSPECTION MANUAL TABLE OF CONTENTS QUALITY DOCUMENT NUMBER TITLE REVISION ~CP-QP-2.0 IMPLEENTATION OF THE CPSES QA PROGRAM 1 CP-QP-2.1 TRAINING OF INSPECTION PERSONNEL 15 QI-QP-2.1-6 QUALIFICATION OF RECEIVING INSPECTION PERSONNEL 5 CP-Q P-5.0 QUALITY ASSURANCE REVIEW OF SITE GENERATED PROCUREMENT DOCUMENTS 1 -QI-QP-5.0-1 REVIEW AND APPROVAL OF CPSES NON-ASME FIELD PROCUREMENT DOCUMENTS 2 QP-QP-5.0-2 -INSPECTION AND RELEASE OF CPSES PROCURED NON-ASME MATERIALS 0 CP-QP-8.0 RECEIVING INSPECTIONS 3 CP-QP-8.1 SUPPLIER EVALUATION 1 QI-QP-8.1 RECEIVING INSPECTION FOR ASME SECTION XI O ITEMS CP'_QP-15.0 TAGGING SYSTEM 4 ~ CP-QP-16.0 NONCONFORMANCES 14 CP-Q P-18. 0 INSPECTION REPORT. 18 CONTROLLED COPY. CONTROL NO.M-C a f O l' 3 lho 8601020360 851113 f P PDR 59 DE TUGCO CA ,,,~--,,,-,,,--n---,,,,,.y v.,, r---,
... ~.. PROCEDURE ISSUE REVISION PAGE NUMBER DATE TEXAS UTILITIES GENERATING CO CPSES CP-QP-2.0 1 10-9-79 1 of 2 o /0/8/79 PREPARED BY: N DATE IMPLEMENTATION OF THE CPSES QA PROGRAM APPROVED BY: d. 44, EN /0!9!7f DATE ' OMTROLLED COPY .g1
1.0 REFERENCES
CONTROL MO + l-A TUCCO/TUSI CPSES QA Plan 1-B Brown & Root Quality Assurance Manual 1-C TUCCO Quality Procedure Manual 1-D Brown & Root Quality Assurance Procedures Manual 1-E Browa & Root Non Destructive Examination Procedure Manual 2.0 GENERAL This document describes procedures that have been prepared for implementation of the CPSES Quality Assurance Program as defined in Reference 1-A. e [- 3.0 PROCEDURE 3.1 B&R CONSTRUCTION PROCEDURES Construction procedures implement applicable Quality Assurance criteria defined in References 1-A and 1-B and establish construction methods and techniques to assure compliance wit'.i engineering requirements. Basic procedures also outli'e QA n or QC interfaces and construction operations necessary to assure satisfactory completion of the CPSES project in accordance with code and regulatory requirements. These procedures are prepared by construction personnel and are reviewed by appro-priate QA/QC personnel for compliance to project requirements prior to issue. l l TUGCO OA farm No 1
PROCEDURE ISSUE REVISION PAGE NUMBER DATE TEXAS UTILITIES GENERATING CO. CPSES 2 CP-QP-2.0 1 10-9-79 2 of 2 3.2 TUCCO AND B&R QUALITY PROCEDURES Reference 1-C contains procedures describing QA/QC functions that are the direct responsibility of TUCCO. Reference 1-D contains procedures implementing QA/QC functions that have been delegated to Brown & Root. Exceptions to this procedure development concept include areas such as receipt inspection and NDE functions which are described within References 1-D and 1-E. These procedures are prepared by QA/QC personnel and reviewed internally for compliance to project requirements prior'to issue. 3.3 TUSI TECHNICAL PROCEDURES These procedures implement basic requireme'nts in the area of Design Change Control, Engineering review of nonconforming conditions and other areas that have been delegated to TUSI. These procedures are prepared by personnel assigned to TUSI's staff and are re. viewed internally for compliance to project requirements prior to issue. QA Staff personnel participate in the procedure preparation phase as necessary to assure compliance with applicable Quality Assurance Criterion. 3.4 SUBCONTRACTED EFFORTS Project purchase orders / subcontracts define applicable QA/QC criteria for efforts subcontracted by TUSI or Brown & Root. , First level control of these activities is normally accomplished P by the selected subcontractor with QA Staff personnel involved in Audit or Surveillance functions. At the option of the TUGC0 Site QA Supervisor, first level control of subcontracted efforts at the CPSES Site, may also be accomplished by the Site QA/QC Staff. 6 TUGCO OA
M o~ }_.avdc.,Lael EG4G /SRO 33as 1.. - _ U ;13 l (,, l 9 7</ RewsL>ed " Teel,, h / Re s'a n ~i', Gv:da -ce l,a d-a t ddel Ju e h E,eL.J td..L '.shc/. /.s b do-.4cte /L.L. se R soy 4 <-c Cs_SE R)j v.,J.f J ~RevieLeJ .s<. v e c /,sa j./e_ ss 6 R 's o R ev s ewa l. Consb <h a. flppy,'s.( insjeeks' 50- Ws/Tc3 -t e' <-d so - 44c/?'3 - /.2 J f J.4p,.:I //, /973 Rea,a, aJ U Rc. Ih So-n.s-/ew-to el. IJ Ju-<.ti, ter<f Rec e 6'<ed coq.-f TRT e e 4.,/2.-l. 2 e.L--t %< sad .4 TO G-C ~ L4..~ < L A e. o C o--~ ~...~ c - J s.,v:, ~.f A Q E -1, AQ E. '/, # AQ E
- at eloc -,- + c o n-fr. 1 e ~, >e vieL a J MS -605 sp c., axJdae~ +
E.5-/do Redwel TUGCO C P-qP-K. O.. - Dor 4 .-en (MCR. ) c C P-Q P-l8'O 'h,yedi.~ Re pa, -l. _Thq 2. _ _ _ _ 'ivt, M, l'I r 1 Tue. A rs.a. n., _ J Lw ~_ s _ rgq e.- n. L. L w-~ LI,.._ cp c. p c.<,,..J..-Caws.~osel+.:d,,,,,,,.,_,,,s.. s 4 c .L b - ,,.._,4 J F C a ' h p i.. Pv t..,', 5-p.' r, a-J. ' AQ E-El Lt-< - vi <~<d L t.- Sv. d ll C&l. L 6 a.c.4J-. 5v F< 4,4) 4Q E. Tevie.ved NCR le b o o k seo.,c.L..'. .f. a g Iee-[. All<x.. s) R<s,e,g/, c ia A/c 4 ' a c G, 10, 4. I L..af d L ce - !, s,i t < < ~ N c R.i
- 6. E,.3 d % 4< i o.\\t<(aba.
"~ lo s 3 _ - _ _ TolsIsr,l'fs'V. wea 4 M evviched R,f 1 6 de ~ A q E-sc, R A E -kc e_ E l < <.b: <. ( E h.. -.- h AQE-3p ~ Mc - 45., 4 hq %,[cJ !d. A/C R s3 R a,E-E, Lh.,,,esa Tc m ha.,at " Ei. b.Jml he.~',..;.J., As.u. LSU o.k b-k.k. b .,c. h e,too (,vw{-Dk--D-6 54 Q '.h< % s b i I ,_ D /4 ,c
li, I 9 f 4 L. 'Da g 4 - - - - Ju lg RevilweJ Joc.v-.,4 J 1 velchi b Wot 5kutdow~-IL.c 1 CPI. - EC.P R Ud -01/l5 h e le,- No. 2 -//77 %v,a'.a.J 15 aldl4.. ~ I AJCR k s a p l..: co~f,; --. J o c. g - <3+ ^%f a s o-vehe,<-c.- u s, J-Te.L L,.1 T - Lskat 6 p ,. or i-, kam A\\.- egui p <.b o << 6 -~\\ hvo.s<14.. CP-CPM-6. 3 Re. Io i2c : W Fv..,,, I).,, p s,- c N. 4.ti.~c g oc.- b+ -- a l e u o usca t,, e,J,,a, L s eat.._ - s 4 i..:g-se.~t g -r,s tv L E.. - a g*ce-qne37.t
- h. T Rec.Jie ' 3L a.ae p
m s:*cP-tva -8.1 h.1 heT h, M.~. & L.s o.s ce.+ d < +.~.s p M W C.?- QRP-f l.. L 'Re,i 2.I C-a dv.I d M.s do - -. de .s ~ Tamle-. 2 m %:g+.n cca. t. u.) sg.ac 3 o. . +a..~ .. A.. J u 1.,x,.2 14g c,.A. <..< Co n eral C.I.L A..k 'Pr. c. 4 ov e s. - L/R CPM-13.1 'b. '? e - L 'R# DCP 'S Rev.17 CPSES 'Decu-<d Co bl &,.- - h 'R CP-tPM.2./ Rev.1. C. \\k.tia ' Pes..s..,,I 'Re vi/e-.< t.: +fi.,,. A - StK* CP-CPM-17.1 'Rev O Conshyct.J-S.h.2d qA %co,J.s 'b.K* CP-CPh.1.1 % l %.k.1 of %.s.na.I in 'f?.cclo./ R yJ., - b 2 '.D 5 _ _ _ -.,Tuq.20, /tri' r,.;. 4 o E di, T<. L.,,. ( R.,l,- L _ % ;.t.L,,o.et n17po r,j. unt_ ~Pv.' Cha,ged Div e < b.- ak-ug nA., a d,n.Ja. appe p,a.J<. cap,a., ,,,c,ss .fo ,,.,...+ : d Tw:p' R.f.;-t. 9 i O .?- :!: .c
.... IDoco_<~tt.E Suppo,bd No n - con C. - - a-ec-Re7.,t s TUGCO W CP-Q P - K. O Rev. M Inspec.E.J~ Rego.Es CP-QP - /s. O
- h. /7 Repa<dia, approv.1, a 1 TuGco #
CP-C.PM - /,. 3 h /c cub.) J Ogerdis-~l %eles b e[vsl L spec.t..'~ .hR* CP -Q R P - T. I Rev. ff ' Receipt, sbora c. & issuavsc.c. 34 R
- C P-C_'P M - T(.1 Re v. 1 c4 Me-s C.o.h.r al o4 Mon - C..&.<-,
%s %. R
- CP - qnP - M.1 Rev.1f 4
Gewe<.1 C.Idv.t. 1 % <.eJ e e. &R CP M -13.1 R e v. '7 CP.5ES Doco.-emb co 6.1 Pro EsR .D C P.3.
- h. /r
.~ Ca.t1% t.h *%..,nel uJa ~hs & ? * ^ CP-LPV1.t. / %.1 a J. IL,, ' Cc shv.a a )r.A., J Gn Reen>s 3re& ee-cen -/r.1 %. c % l-.lof Ws.--al(3,.oe-ebvI 3 s-R
- C P-C Pt1.2. 2.
yy,,~ u O er g 4 g
s;sb Mc.RI. 7~ # 7 ' #i' V 13-c - 8 6 e9:- 9 ,er E1 F'! - 003 G - 8"{ ~ Od 2.S *5
- 5. o s,1M. -[~
F, - 9'h - $5.Rs 0./ W& 3 - ss - 03 23s' - E 013 5 7 5 E-s s - 0 W 69 / 1,: - g 5 - D1l96 / l E-93 0(3edle / 7-/ 7-P'y l E-tl ogz,3 C-M - o s, Ts-C - E - og o z.z / c-es - o zer, v c ts-os,n T'~ D ~ 07- %, C o 2 7 24 l' G- $ $ - o 7, &N%S f h I62 3 1 ,,. ~~
h"f Thd FEB 6 inn s ANL v' may' s i 13 At 0 fl . _t f.. X =-M // 4 4 ~ *1 3 11 23 O l' // f 15 .0. O 9 Y _.. g'. It. 0... 4. 7 7 f, 2. V. Y O -~-----l-- S h ..3. L. _.. - .. L L.. ( o 7 Y 5 9 2. // /3 L3 Y l I le /- f /0 _. to... f. .j/ O f 3 0 . /3 /b t ia o 7 2 Y iz r y 7 6 0 4' // Y .N N /f \\) / -...-. 3.. ./2' - 0- .../.s'... h ' ' r /c li.... A-. L l 1
- a....
....O A i.t.. $w. _. 7.. . 4.... - t.___.. _ _ _ O. ... A.... (' b.1. l' - ...i9._ ..O.. b lb: ' )C" Y, b- .9 6. O w .v /3 1 O m m o c -.. _23... 10 /3 2-1L 's v..
- . / 0 ~.
. /q O //. / l V _ . 13 6 6 /#. I // 0 /$. 2c j i e /0 V /0 hh ... s e A z 1 5 M / 4 9 0 3o 7 . M 3 b-eaf-/ .n p. e-gn 4 V ,c Pk jp y,c 9 i %9 L 'b//63 _1 a L
c 1g/jy Gk 5 ty' ~r m -4 C.o b, l 4 tyky in hul Ir 4 4 h Ik.jkME (614) 2 'A (f /0 >4 h C'/' / &G %,, p 6 b 6% y -CN 2 M 'mA r o 70/ My a r C CIH l A T/{ (cmpu k- -h i 1/7/1Y m u % h -1 sprio I..a f ci)L p,LGA ^ a %. IFL & W,m. [ TttL M4 TM rtu tthL 'fQ yy ^ THI I% tM W un T m > 114. m L 39 p') dnyt 3 00 I 38 4[ m. ^l h* M M 7thL lli 3 T ~ iht Mttrk Im. 74 w#_ f '78 DH itn Ttti M 1/ Tty ps. n pu - ps.- 7 '* M W Titk '*3 o dop 4-sr 2 i 4,
- 7. c/r. _
THI 1 I b KM 7N) t?q % ftg. Am t - wn v v u vau ,.ri, W N 114 TML llIl HL M ' tin trH. 7tg. M 'Mkh4 MME ' l % 7 tit Irn M q ' uit vti M. m a. b p,,, < ' 1%I Il 93 eley5 N
- 1 a
6 4r E 1/%. I ' a m m) im / .w W NU.nanu i .i / m:. i _ gg ) i4 4.- l? 2y y 4-Gv3 c.
e 9 -h, a@9y-e es "M' 4 h &m~ wer-.an.m oc n-Loca 8sak p,% Coa ~ % M p u m a n c r 2.- o4~ M ' 1Ls y ak LA N [ed A 6 ) Dq pWa ch %A W A CM dC -(JEene iN'vit.v 6 s CAuce t ~. a G TN 'Y S %n,- ) o e. h e vi. ~Dfw-M4 4 u um W k%L-M QWe @W V *C~~ g g w... o f ?. K A.lC M; Ie> M aes w, M
- u. n ea A.J & c, <
Dq WRmww. Go rw,s-cm q pemn
- u u u o - ~~.
(m m f,pp J, -e rv,=- m ss ,~c m b Mt ot$ Q t vWU' M AU. & %cM-<., c d "6*'*=' wo _. w. u. , = or STAM d/wwn,~et. 3 gs p-A h 9 twe-m, a s. VWD Thh C N "* b k y @f ** L 1 'UMfh S bNb W6 hU' I - i,
N / .e o COMANCHE PEAK OPEN ISSUE ACTION PLAN Task: M AQW-15, AQW-16, AQW-17, AQW-18, AQW-19, AQW-27, h A0E-h Ref. No.: AQB-2, AQ-38, AQ-39, AQ-50, AQO-7, AQO-14 Characterization: Inadequate and/or improper certification of the qualifications of QC personnel. Initial Assessment of Significance: Possibly indicative of a general breakdown in the QA program. Source: Various Aoproach to Resolution: 1. Review procedures, codes / standards, design requirements, NRC requirements, and licensee commitments for adequacy at time work w'as performed; were codes / standards, FSAR, contractor requirements, and other commitments met? 2. Discuss adequacy of procedures with personnel involved. Examine installation, as appropriate, that is associated with any inadequate procedures ide tified. 3. Refer any examples of wrongdoing or significant deficiencies to TRT manager. Evaluate allegations for generic / safety implications. 4. 5. Report on results of review / evaluation of allegations. Related Open Issues Review activities necessary to close or partially close related items, either based on inspection conducted above or reasonable additional inspection while the inspector is familiar with the areas. t PGA-899 b 1h4
- j!
~. -........ -. COMANCHE PEAK OPEN ISSUE ACTION PLAN Task: Failure to follow procedures related to welding, concrete, documentation, installation, carry out work requirements, and report defects and other problems or concerns. A % 4.lku M. a se,m h /~ M A g,-y nam Ref. No.. A0W-14.ADW-?S.A0W-2d.A0W-203IAOC-10,AOC-12.AOC-13,AOC-14, ' AQC-15g0-5, AQ0-26,yE-2, AQE*"::yy-43, AQ-47, AQ-51 -c.m e ~ m m ree,a.coe. 3 c Characterization: Various broad scope concerns involving procedures; werkmanship; documen.tation; installation; control of documentation; reporting problems, defects, unauthorized work, and backfitting of completed work; repair work, and generaliy poor workmanship. Initial Assessment of Sionificance: There appears to be sufficient specificity to warrant followup of each of these allegations. Initial disposition was made in IR 81-12 for AQC-10. Coatings concerns in-AQO-5 may be discussed in Brookhaven National Lab Report. Source: QA/QC Category 18 - Undocumented Activity / Rework Approach to Resolution: 1. Review the May 1984 SNL interim report. If the second BNL report is available, this report should be reviewed in-depth. Determine if adequate documentation is available to support BNL report (s). Take appropriate action to close allegations. 2, Review licensee's 3 documents entitled: TUGC CPSES " Analysis of the Clogging of ECCS Sump Trash Racks by Debris and Paint Peels Following Accident"; "Model Testing of. the Recir.culation Containment. Sump"; and " Evaluation of Paint and Insulation Debris Effects on Containment Emergency Sump performance." 3. Review IR 81-12 to determine if documentation adequately supports findings of AQC-10. If documentation does not support findings, take appropriate action to close allegations. 4. Review repair, installation, welding, and documentation procedures, codes / standards, repair and documentation requirements, NRC requirements, and licensee commitments for adequacy at time work was performed; were codes / standards, FSAR, contractor requirements, and other co&mitments met? 5. Discuss adequacy of repair installation, and documentation procedures with personnel involved with these activities. Discuss adequacy of other related procedures. Examine installation repair, documentation and authorization requirements, as appropriate, that are associated with any inadequate procedures identified during interviews. 6. Review sample of similar-types of procedures for adequacy. 7. Refer any examples of wrongdoing or significant deficiencies to TRT manager. J 8. Evaluate allegations for generic / safety implications 9. Report on results of review / evaluation of allegations. Related Open Issues 1. Using system codes, pull open items, previous inspection findings, etc., from the tracking system open item list. (Regien IV identify and add to this work package.) 2. Review activities necessary to close or partially close related items', eitner based on inspection conducted above r reasonable additional inspection while the inspector is famili;r ith the areas. e
w--- ---- ~ Beand.Ccq G CCMANCHE PEAK OPEN ISSUE ACTION PLAN Task: -Failure to complete, process, issue, void, and disposition NCR's.
- Also, allegation that inspection reports were used instead of NCR's.
Ref. No.: AQ-30, AQ-31, AQ-32, AQ-4 J "' 10-17 AQO-8, AQO-9, AQO-10, AQO-11, AQO-12, AQO-13, AE-1, 2Q6-4, AQE-{} AQP-1, AQH-2 Characterization: Various concerns involving NCR program, including: a. Generation of NCR's b, Disposition of NCR's c. Volding of NCR's d. Use of inspection reports instead of NCR's Initial Assessment of Significance: NCR's may not have been issued, when required or NCR's may have been improperly dispositioned.. This makes the validity of construction, inspections, or rework subject to question. Source: QA allegations; see allegations list Approach to Resolution: 1. Review NCR procedures for adequacy. Review procedure changing NCR system to inspection report system. 2. Examine a sample of NCR's and see if they conform to procedural requirements. Sample-should include craft areas mentioned in allegations and some areas outside those mentioned in allegations. --- 3. Examine a sample of inspection reports and determine if inspection repor't items should have been NCR's. 4. Examine a sample of items reworked or actions taken in response to NCR's to conform disposition in accordance with NCR and procedural requirements. 5. Interview sample of QC inspectors, supervisor;, and craft personnel to ascertain implementation and knowledge of NCR procedures. 6. Evaluate threshold for generating NCR's and placing them in system. 7. Refer any examples of wrongdoing to TRT manager. 8. Evaluate allegations for generic / safety implications. 9. Report on results of review / evaluation of allegations. Related Ocen Issues 1. Using system codes, pull open items, previous inspection findings, etc., from the tracking system open item list'. (Region IV identify and add. ~ to this work package.) 2. Review activities necessary to close or partially close related items, either based on inspection conducted above or reasonable additional inspection while the inspector is familiar with the areas. 3. While performing physical inspections above, examine surrounding systems, components, and structures for related apparent defects or indicators of faulty workmanship. 4 If workmen are still in the area of a physical inspection, interview them for related knowledge of other potential deficiencies. 5. Complete portion of IE Module on QA/QC Nonconformances. E k 6 .m
~ T!; L.~E .~1 i sTa nAy6 ~ 0 ;.. i r5 v d ',*[ '. {...,_. ? , h*ch-- } w. .~
- pp. =
- 'r p
f_ ,., r/ ..' n Q':. -. s i .n ,-> ~ C = m% >u _,~: s-m~ nw, v.o - p {~'~YedonCnottowriteNCRs.[ . stated that within the past month,h indicated there were several instances in whichQ' felt pressure had been ) k(e exer [. learned of a problem in the Control Room of Unit-I in which electrical cables were being removed without proper documentation.. () indicated that{wan.ted to a QC supervisor, write an NCR on the lack of documentation, but thaty ~ k had instructedQnot to write the NCR. [ yr 4 told of another situation which ' occurred within the past month in the Safeguards Building in which cable was removed without documentation. fE..'said Qagain tried toMrite an NCR and that it was rejected p.cygr4,T{., said that after the P43' ' submitted the NCR, it was accepted but that '9did ' not know if it was placed in the system. . ? . 1,d. 4 S described another situation within the last couple of weeks involving flex I-co.nduit in the Fuel Building. Conduit was 'rdplaced and dot repaired as described by an NCR. N isaid Q had been told by .}. o disposition the NCR, but that _' : had not yet complied with d '._....., orders. [-(( recalled another occasion in which [ rected p' to "close 6, /U-YPf[.5.N to do.x[.'<.. said that this NYR con,cerned Y h, $ cut" an NCR.thatd.h
- a--
p. Q conduit and that { tol ,j[p [,gQ_.p.p 7.'$.[ to do the job, but thpyg toldQto do it anyway. dsaid 2/~ closed out the NCR and it was late' r " kicked back" and corrected. [ [.-.( recalled another situation, in April 1983 in Unit 1, in which craft needed 'HCR closed so they could proceed with the pulling of cable. 7 :said that d{- ' problems with the cable tray had riot been corrected. Csaid i S re'embered, m I there was trash in the cable tray, cuts in parts of the cable, and the cable w'as [. -n1saidthat also interwoven Q,}saidk,.. refused to close out the NCR. 'e C' ' was contacted by someone in craft (identification unknown) who told him tohave[
- clos $ out the NCR. [ said that/r told [ "I'm not telling you' that yo'u have to.'do it,'I'm telling you that they want it done." []
p,d( ~ g e
^' jf V Curae 2 G 3 da-2."w uA>Av7 west % C A s s et- %w ac Caste 79 Gm
- J cm..
es P.e be e Aa ~24 ~ Aa i Loo.c th iv b c, i ME - I MOT w wi e.w NCI't - edur %v r w/o D oc. e h e - 2. M CI't (
- CWW TWoh t.-4/g%CC.
Ag e. - 3 MCit-Rowe 36 m c-+ h w A-oe - + hew c c.s e m e NcTA o. kQe.- )? l JJC 17- " b y A w A : A.>o,v e. ~f T. ,~ MQF. -I'5 erw o w re c.er hje. h77. CD c. s%p o ~ D -3 t USA-As-gt Q n -io o proe.-3t Men + % h a de>di.sc. 'Q' m hen.m ASE-33 AQe - 34 Mc.p_-am-c.= %. L u c. s A ec T.sn m 8<.oc L Se loa k 4Qe - ts kJc R * }d t (2._7 :P 6 pee.<e,o be t _ Stif=_.3G h e.-38 o7-pett M-t oc Ma - 39 Nc (2_ + No' N kt_pe-4o y er ro w cr a bk as i h ns~ O
4 'r. 65 Inspector Name: A-2 Date Interviewed: General
Background:
Interviewee Comments: Has some concern with use-as-is NCR situations, use-as-is seems particularly prevalent when using Specification ES-100. Specific Technical Concern: NCR was writter when cable damage occurred during Biso Seal removal using a threaded rod. This ~ ~ 2# occurred in Auxiliary Building, elev. 832'. NCR said no damage dIIIEEE was done to cable but some insulation had been scraped off by rod. Feel further eval, ation may be in order for these cables and there may be similar problems elsewhere. Specific: Wrote 2 NCR's regard.c; + ;eability of fuse blocks. Blocks _were not marked "Q". NCR said OK as-is because no non-Q blocks were purchased via order MS-605. Feels other similar e" g)I. non-Q blocks have been purchased via different ourchase order and could have been installed as Q. Thinks 4. ' a possible paperwork problem. Specific: Wrote recent NCR (not yet evaluated) on GE Motor Control Centers. Compression legs have bends as much as 180 (?,.. V degrees) (more than normally done done by site construction), j][]l[ Don't think GE can violate.equirements and may be a problem elsewhere in GE MCC's. Also have some broken wire strands which we are fixing as we find. Specific: Had previous paperwork conflict problem in solving rework.of terminal blocks. 6 page RFIC involved and Proc. SAP-6 involved. Wrote 2 NCR's. N7C inspectors Creek and Johnson were aware, Creek told NRC inspector Taylor, Taylo'r told to have an answer. Never got feedback as to results. Specific: Repaired a solenoid, shortly af ter coming to Comanche fgg3E 7 Peak in craf t, without paperwork. Don't know if it was safety related. Not concerned with solenoid technically - did a good job. ? Notes: The specific concerns were given verbally to the SRI - Construction on 4/12/84 for further, followup. It was indicated durian tha intarview he would cet more soecifics for SRI. MCC problem was still being evaluated. I suggest allowing the licensee to evaluate and then followup for adequacy of corrective action.
s 66 Inspector Name: A-3 Date Interviewed: General
Background:
Interviewee Comments: Generally concerned with findirig numerous problems during past construction inspection and procedure being changed to delete 4GF - 3 inspection,'e.g., loose terminations found in lighting. Some NCR's are answered simply that th'e problem is not addressed in Specification ES-100. Recent NCR written because restraint cable (lighting) crimp gages were worn & therefore, inspection was inadequate. This is still being evaluated. Wires of two different gages were terminated at some lugs and many. /f d#- 3 terminations are loose. Have more pressure not to write NCR's during turnover. /jdamist y Found loose LB's (elbow termination fittings) @ East & South ends of Unit 1 Diesel Generators, wrote two NCR's, was accepted as is. ,ggs.,,. ~ Found cables not trained (routed) in workmanlike manner in Unit 1 Cable Spread Room @ junction. boxes 1058 and 1059. NCR said OK because fft 'E cable radius was OK but did not admit workmanship problem. Feels post constructior, inspectors were transferred to Unit 2 as retaliation for finding problems. Heard second hand that IR's (inspection reports) were being written falsely (without reinspection) to clear IIRN's (discrep- // 4 6 - ancy report) on cable trays. Heard from_ lady in Paper Flow Group (PFG) and lady in vault. Said he would get back to NRC with more specifics. Notes: Some review of the lighting termination issue and post check procedure was conducted by te&m member Ruff. The site inspector indicated he had told of most of these issues and QA was evaluating. I forwarded concern relative to 1058 & 1059 junction boxes to RIV: Martin and he indicated he inspected these boxes and sees no technicai proosem. Resident Inspector: Smith eartie-ipated in most of the interview and indicated he was aware of the C/G loose fittings and sees no technical problem. I evaluated reasons why 6 personnel including were transferred to Unit 2 and this move does not appear to be discriminatory. m.
-. _ -.. -. - ~. 67 Inspector Name: A-4 Date Interviewed: General
Background:
Interviewee Comments: Uncomfortable with some use-as-is situations, e.g., cable separation problem found in fuel building during walkdown did not /% 6" f meet procedure but was evaluated as use-as-is. He can show someone where it is. Wrote NCR. on lack of 5-thread engagement on a con'duit fitting poor evaluation in that the/ simply said that couldn't see it; a second NCR was written on th;s area for cable damage, seemed to be looking for a way to buy this.2rea off, took two tries to get everything evaluated. knows about this but didn't get back to him on fact that NCR's were poorly handled, i.e., non-tech-nical aspects. Feels discriminated against in that he was transferred to Unit 2 where there is no overtime. Got grilled on cable damage NCR at M the same time as being counseled on a personnel issue so it appeared that his transfer had something to do with NCR. Management is aware of this concern. Note: I did not review this person's transfer situation. l h
~* ~~ q g / -1 SAKS1. SAKS 3 H SAKS 4 W"1 M M"M amas r+ p M a r y[ftwgM iWEMGMEaw "SA'KS 1 3081.2 2 SAK53 sAKs 4 3214J .u i.isny,ac. ueiamine mned -m ruu Fa 0 2 su nsns, ace ueiamin.cor2 p c knoge Snsrac. ueiamin. ir. moscating Neon. 220V) fuses 1m a %in) SAKS3 2489.2 20 H$nsraos Meiamine (for 250V cartridge p fuses 1 %in a %e) l Po3ASE-SA Dl i4 I 75mm '2.95m; j 54mm 54mm (2.13 n) { j: (2.13:n) j it u .ma$ .~ m 4., nx agg 6 .qh 2-bem - e p re-inai rscanen tamm o Sizin) r.rmin. mc=n.u i3mm o Si2m) termine tscanen 24mm e0 945am ins on Stnecing Lorstn 12mrtt (0.4722ri) Insuiation Stricoing Lengtn 12mm (0.472m) insuiaten Sirteomg Lengm 12mm to.472in) ) acd.; 2vois%AWG ' Mb&s 1 ~ AAp' ? von; iAWGi der== 4 M M@kAWG. ~ Acer== w 6 300 22 8 m 10 300 20 10 m .J 600 22 8 0 10 300 e 10 300 .e 600 20-8 . Catalog standard J'.A.fCataiog= Standard
- T'
,- ' P' ' '.T.atacqi T.Starcard' .s ' No r Pack. '. Type' Tyse_ __ No ' Pact _ Type _ 2 1_ . No._ s_ Pack _ m, + ,Coquired Accessones Required Accessonee Required Accessor$es T,5 32 1228.0 TS 32 1228.0 TS 32 1228.0 EWK1 S_5mm to 335+nt 2081.8 50 EWK1 8 5mm to 335m) 2081.8 50 EWK2 15mm10 591in) 1993.8 20 AP 3mrm :0.118im 1913.2 20 AP 3mm:0118ml 1913.2 20 Cotional Accassones cotional Accessones Cptional Accessortes CL2 1914.0 50 QL2 3280.0 20 OL3 1915.0 50 CL3 3281.0 20 QL4 1918.0 20 CL4 3282.0 20 QL 10 3384.0 QL10 3390.0 FCS 2421.0 FCS (for 21112P 4288.0 FCS 3J94.0 S8L_ 4480.0 58L (for 211121 4482.0 $8L (for 2489 2) 4483.0 85 M3s 7 1997.0 200 BS M4 9 1033.0 100 i*for 2489 2. use FCS 4289 C1 Newc:cator Canrgge Fuse Cartncge Fuse tm a 'J.m SUSS AGx. 2M" ' 5"_m E.U.SS GMA Ltt:efuse 862000 CEFCC 8AG. t to 30 ames 3 arnes
- 25. 50. t. 2. 3. 4. 5. 8 to amos 3 25 ar' o l
3; a.c l 4amcs Cannoge Fuse t 5.in s ". in BUSS ABC. Ltt:eFuse 314CCC CEFCO 3A8 i 5 amos .'*C
- 25. 50.1. 2.15 7.10ames
- 5 amc1 6 amos 2 ames to ames i
Detalia 8.5mm. etc. See Section G Detalia 6.5mm. etc. See Section G Dekafin 8.5mm. etc. See Sect 6on G i .___.__.._.2_.__..-.u_.___..,._.__ ... ~ -
,e.a., .a_ ^ e. ..d-m ..e 4 y f SAK 2.5 SAK4 SAK6N wr - T _..... ca, ~.m.., T
- ,m ua,.. m.m
. m.sca_ dad _KeM*- ?J4 - fio. 1 Type y_ 4 T*" ,T,rc g .. e. O ;_ T_ype. s ' - - 4. m : $_*
- No_.-..J ' _W ed v
l SAK 2.5 2796.2 SAK 4 [ 1283.2 SAK6N 1932.2 40mm 40mm t O 57.n) j M5mm I 't 57in) j r N , r-57 D b ,d
- C-4' i
M h 9.9'%~ qqw qp C 'O WO a m.- n-Te - mas T oness 6mm so.236,m Terminas Thickness 6 Smm(0.256.m Termmal Thickness 8mm to 315em ave 9 Cr-comg Lengtn 9mm to.35tn) insulaton Stnoomg Lengtn t 2mm (0.472m) Insuiata:in Strecmg Lengrn 12mm 40 472.r9 T
- aa._ _ W.wifAWG " b
%s ' 'vars _ ' AWG. Acor== - ! Amp. yars AWG w 25 600 22 12 m 36 600 2212 = 47 600 16-8 e 25 600 22 12 4 36 600 22 10 e 47 600 20 8 ~ _ Cataiog Cataiog . Catalog ,s his 1,. r_ .s, - ' No. _' _Tyos _ _No ig;e,, Jut - . 'r Required Accessones Required Accessortes Required Accessories TS 32 _, 1228.0 .TS 32 1228.0 TS 32 1228.0 EWK tl5mm_iG 335 m 2M1.8 EWK1 8 5mm to 335em 2061.6 .EWK1 8 5mm to 335 m 2061.6 AP t 5m_mic 059im 2796.2 AP 1 Smm(0 059'm 1179.2 AP 1 Smm to 059 m 1179.2 Optional Accessories Opteensi Accessortes Optional Accessortes TW__2 !mr9 i0 098 m 3028.2 TW 2 $mm 40 098m) 1301.2 TW 2 5mm to 098im 1301.2 TSch1~~ 3198.8 TSch1 3191.8 TSch1 3191.6 l Ste s.S. 200E.0 Sie 14 1644.0 St814 1899.0 l PS,., j.1m,mo r0 090im 1904.0 PS 2 3mmit0 090im 1804.0 PS 4mm # (0.157im 1996.0 052 2127.0 QS2 2709.0 Q 2 __,, 3370.0 02 3347.0 _02 4567.0 Q3, 3371.0 03 3368.0 03 4568_.0 04 3372.0 04 3369.0 04 4569.0 0 to 3447.0 0 to 3688.0 0 to 4570.0 j / AO4 4 Teem naisi 3756.0 AD 4 ta 'ermma:s> 3761.0 AD4 e4 ferminaisi 3760.0 BSK v3,;2 12s9.0 asK V3422 1289.0 SSK V3:22 1289.0 Dekafia 6mm. etc. See Master _Catasog _ .Dekstis 6.5mm. etc._ _See M. aster Catalog.. -. Dekall 8.5mm.etc. See Master Catalog Sechen0,, , _See!1on,0,,,,,,,,,,,,,, , Section O l u. 'u
CM E S/ F S AR W 6 TABLE OF CONTENTS Section Title Page 17.0 OUALITY ASSURANCE (OA) 17.1 00ALITY ASSURANCE DURING DESIGN AND CONSTRUCTION 17.1-2 17.1.1 ORGANIZATION 17.1-2 17.1.1.1 TUGC0/TUSI 17.1-3 17.1.1.1.1 Ouality Assurance Division 17.1-3 17.1.1.1.2 Project Management 17.1-6 17.1.1.2 Gibbs & Hill 17.1-6 17.1.1.3 Brown & Root 17.1-9 17.1.1.4 Consultants 17.1-11 17.1.1.5 Organizatioral Interfaces 17.1-13 17.1.2 OUALITY ASSURANCE PROGRAM 17.1-14 17.1.3 DESIGN CONTROL 17.1-16 17.1.3.1 Design Control for Preparation of Drawings 17.1-17 17.1.3.2 Engineering Specifications 17.1-18 17.1.3.3 Review of Vendor Equip.T.ent Drawings, 17.1-18 Specifications, and Procedures 17.1.3.4 _ Engineering Calculaticns 17.1-18 17.1.3.5 ,rgsign Review and verification 17.1-19 17.1.3.6 Ccsign and Engineering Surveillance 17.1-19 17.1.~.7 R2 crd Acc;mulation and Control 17.1-20 17.1.4 PROCURF. MENT DOCUMENT Cf.? fROL 17.1-20 17.1.5 INSTRUCTIONS,- PROCEDURES, Af40 DRAWINGS 17.1-22 17.1.6 00CUMENT CONTROL 17.1-24 17.1.7 CONTROL OF PURCHASED MATERIAL, ECulFMENT 17.1 -.? S AND SERVICES 17.1.8 IDENTIFICATIONANDCONTROLOFMATERI$LS 17.1-27 PM T S, A':D C C.".; C'. Q T S b /q L s ,,r Kr**
. - -... -.... -..... ~ .~ CPSES/FSAR TABLE OF CONTENTS 1(Continued) Section Title Page I 17.1.9 CONTROL OF SPECIAL PROCESSES 17.1-29 l 17.1.10 INSPECTION 17.1-30 17.1.11 . TEST CONTROL 17.1-32 f 17.1.12 CONTROL OF MEASURING AND TEST EQUIPMENT 17.1-34 i 17.1.13 HANDLING, STORAGE, AND SHIPPING 17.1-35 17.1.14 INSPECTION,. TEST, AND OPERATING STATUS 17.1-36 j ' 17.1.15 NONCONFORMING MATERIALS, PARTS, OR COMPONENTS 17.1-37 j 17.1.16 CORRECTIVE ACTION 17.1 40 t q 17.1.17 OUALITY ASSURANCE RECORDS 17.1 41 { 17.1.18 AUDITS 17.1 43 i i I { 17.2 QUALITY ASSURANCE DURING THE OPERATIONS PHASE 17.2-1 17.2.1 ORGANIZATION 17.2-1 l 17.2.1.1 Organizational Stru'cture. 17.2-1 1 17.2.1.1.1 Executive Vice-President and General Manager 17.2-1 17.2.1.1.2 Vice President, Nuclear? 17.2-2 17.2.1.1.3 Manager, Nuclear Operations 17.2-3 17.2.1.1.4 Managir, Plant Operations 17.2 4 j 17.2.1.1.5 Manager, Quality Assurance 17.2-5 j 17.2.1.1.6 Manager, Nuclear E6sineering 17.2-6 17.2.1.2 Guality Assurance Division 17.2 6 17.2.I'.3 CPSES 0;erations cuality Assurance Section 17.2-7 17.2.1.4 Operations Review Ccmmittee 17.2-2a 17.2.1.5 Delegation of Ouality Assurance Functient 17.2-9 17.2.1.6 ' Pery ennel. Cuali fications 17.2-9 4 17.2.1.6.1 . Anager, Quality Assurance 17.2-9
- ~
.17.2.1.6.2 C;arations Ouality Assurance Supervisor 17.2-10 i -17.2.1.7 . Inspection F,cticas 17.2-10 17.2.2 CU*llTY ASSLP.U.CE FROGRAM '17.2 11 i 4 17.2.3 DES.GN CGNTROL 17.2 '5 i::. i - 17-ii 1, y '1, 3 i ~ 1-s. 'N Y Is' . '*)'.~
........ _. ~.. -......_., CPSES/FSAR-provided, and they contain the identification of quality characteristics to be.in'spected, identification of those individuals, or the organization responsible for performing the -inspection operation, criteria for acceptance or rejection, description of the method of inspection, evidence of-completion and certification of inspection operation, and record of the results of the inspection operation.
- 3. -
Inspection procedures or instructions are available with necessary drawings and inspections for use prior to performing the inspection operation. 4. Each inspector is qualified and those qualifications are kept c urrent. 5. Inspection equipment is within calibration prior. to performing an 3 inspection operation. 6. Inspection of modifications, repairs, and replacement items that are made after initial inspection are performed in acccrdance with the original design and inspection requirements or acceptable alternatives to verify acceptability. 1 The ver. dor or rub-verdor shall od- ;tand that h4 bst SLEnit' to 'U*;C0 6 ard'or the prL a contractor a Quality Assurance /Ccntrol lunual, '.'.e f j purpose 'of yhich shall be to fulfill the applicable requira.~ents of 1
- ,indix B to 10 CFR Pcct 50 in rr. gard to Quality Centrol. This
- r.ual.
6 is. 5f act to ~ 0GC0's a..d/or t' a pcime centractor's approval. 17.1.5 INSTRUC: NS, FROCEDURES, AND OR.O!!NGS .y;rc;riate i. :i.- :nts have *.'. : : < Ibli:' :d by the. C/TUSI S:lli-ty Assurance progr a to assure that gi/ality-e e'; tad activi ties for 4 GSES crar prescri';.ed ij dectantad in '.rt cL b.'s,,r..: . s, or S IT !, 11 tg-.". a i 8
I .s. 1._, y._ - CPSES/FSAR drawings; accomplished in accordance with such documents; and that-ap-proved acceptance criteria are met. The responsibility for the development of the methods that assure this is delegated to the various participating organizations; however, the developed methods are sebject to TUGC0 audit. The TUGC0/TUSI QA program requires F
- measures be established by the prime contractors to assure tha'
. proved changes are promptly included into instructions, procedures, and drawings where appl.icable. The TUGC0/TUSI QA Plan requires that changes be reviewed for their effect on present instructions, procadures and/or drawings. The TUGC0/TUSI QA program requires that an inspection procedure include 4 ficw charts, shop travelers or narrative description of the sequence of activities or operation for fabrication,' processing, assembly, inspec-tion, and test. Instructions shall indicate the operations or proces-ses to be perfomed, type of characteristics to be' ceasured or cbserv-ed, the methods of examination, the applicable acceptance criteria and documentation requirements. The program also requires establishment of 4 those inspection, test, and hold points from raw material through fabrication, processing, and assembly at which confomance of parts, ccaponents, ud subsystems to requirements are verified. Held points identify those inspections which are rendered im;ossible by subseqt.ent operations, and these inspections must be car.ifted co :plete before start of the next operation by the use of prccess st.ats (e.g. travelacs). Each process sheet shall include the dt. a ;f e.: ;'ation of the c;2 ration er test and the 'sienture er stamp of t'. :gru'or or in-s;ector. TUGC0 QA reviews select +d doct.nantation to asnre that it ad-e;cately reflects applicable quality requi. e.cSnts. !n its raf aw... tivi-ties, TcGC0 QA..:ssuras that instructicos, proceder.as, :..d dc cins. ;n-tain. appropriate que.ntitative (such as, dicansicas, telcrar.cas, a.d op. rating limits) or qualitative (such as horkaanship samples) acceptance criteria for datcrz.ining that im;;rtrit activitics Ma.a ' un satis f'ctorily accc :pli v.d. i Thrtssh its audit: g s ?c t ';res, a.s ' cr iM in 17.1. '3,
- 0 1 7, $. ;. 3
/, 1 ~ .., a:
.a.______._._ CPSES/FSAR determines that quality activities are accomplished in accordance with those approved ~ instructions, procedures, and drawings. 17.1.6 DOCUMENT CONTROL TUGC0/TUSI has established requirements to assure that documents, including changes, are reviewed for adequacy and approved for release by authorized personnel. These requirements provide that prime contrac-tors include in their internal programs measures to assure that changes to ' documents will be reviewed and approved by the same organizations .that performed the original review and approval. TUGC0 will verify -implementation of these requirements. through audits of prime con-tractors. The CPSES QA Plan requires that changes to documents that have been reviewed and approved by TUSI organizations will be reviewed and approved by those same TUSI organizations that perforced the,origi-nal review and approval unless the applicant designates another organ-4 ization. These requirements also provide that the documents are dis-tributed to and used at the location where the prescribed activity is performed. The.sce;e of these requirements applies to TUSI as well as to the prime contractors and sub-contractors. TUGC0/TUSI employs within its cwn internal organization a control system that utilizes registering of documents requiring centrol, distribution, and review and approval procedures. The-TUGC0/TUSI Quality Assurance Fragram requires design enginearir.g and procurcr qt doczentation for all safety-related equiprant 9.Sich consi,ts of specifications, drawi,ngs, PS1.R/FSAR material, instructions, ;cac':Lres, - reports and changes thereto, and manufacturing and constructicn docu- .ts and records riwired fcr traceability, evidence of gnlity, and s.estantiation cf the "as built" configuration be ccntrpiled. F: ccc-d res identify th.cse individuals or groups responsible for reviesing, a;;, roving and issuing documents and revisions thereto. 1.$.o re &.. ed acessary, TUGC0 uill require that fer' dic Ocnnt < cy li> c 2 e_Sr.itted by an cegani ation to variff.he use of tha,.. :e ' t 17.1-24 ... 31,,.e.;9 .o ..,.i C; ' p
- 4
_E ~..._.c._.__._......_.~~ ~ ~ ~ 1 CPSES/FSAR i Examinations, tests, and inspectians are conducted to verify conform-i ance to the specified requirements. Written procedures also are required to cover training, examination, qualification, certification, and verification of personnel as well as l the maintenance of all required personnel records. Compliance with these procedures is required for prime contractors, subcontractors, and-venders. Procedures for control of special processses are subject to review and approval by TUGC0 on a case basis. TUGC0 assures conformance with these requirements by: 1. Review of procedures for inclusion of special processes requiring control; proper definition of requirements for operator training, qualification, and certification; conformance to applicable codes, standards, drawing, specifications, or other criteria. c 2. Audits to verify the adequacy of selected site and vendor shop i activities and the effectiveness of the special process procedures being implemented. 1 f 17.1.10 INSPECTION i l TUGC0/TUSI este.511shes with each of-its prire contractcrs a d$ision of respensibility 1,h';h determines the services, structures, systr. s, cc - onents, and materials for which each is respons'ble. The organization { Wing the responsibility for previsicn of such itea.s also has the ,rtiry ecsrcnsibility to assure that adaquate f rapection is 6. 2 by the supplier. TUGC0/TUSI,'bmiever, reserves the right to review, ) disapprove and perform surveillance or audits of the inspection crocadures utilized by thcse organizaticas. i 6 6 I l i ,-_.,_~-._-._-,m__, , -,,. - -,, - ~ .E--.-
- 1-* --
4 ,. w e, w- , - -v-b.= c
CPSES/FSAR The review and approval of a prime contractor's inspection programs and procedures is accomplished as an integral part of TUGC0's review of the organization's Quality Assurance / Quality Control Programs. The Manager, Quality Assurance uses the following criteria in evaluating inspection methods proposed by organizations under contract to TUGC0/TUSI: 1. Inspection procedures for functional groups such as procurement, project management, construction, and shop inspection are described including measures to identify inspection and test status. 2. Duties and responsibilities of perse.,nel performing inspection are clearly established. 3. Qualifications of personnel performing inspections are commensurate with their duties and responsibilities. '4 Documentation methods for inspection activities of each group are established (e.g., inspection forms, reports). 5. Documentation control systems for identifying a.'d distributing inspection documents are defined. 6. Review and approval procedures for int;ection dc:;. .taticn are provided. 7. Surveillance methods are established to issure prcper impic.antation of inspecti n proceducts. S. Planning of inspection sequence activities by the c;ntracicrs include the type of chirecteristics to te
- s r :d, t' ?
's of examin ticn, cnd the critaria. 17.1-31 3, ) 4
... ~.. CPSES/FSAR Inspection planning is utilized to assure confomance to procedures, drawings, specifications, codes, standards and other documented instructions. Inspections are perfomed by individuals not responsible for the activity being inspected. Sufficient inspections are conducted to verify confomance particularly in areas rendered inaccessible by further processing. 1_ G W g e ts-ne m M W e W P m M"rftradvanta-6 '4 hen required for adequate control, a combination of inspection and process monitoring is employed. Hold points are established and enforced as required by the supplier and the purchaser. TUGC0 and/or its representatives verifies by review of inspection reports, visits to vendor shops, and onsite surveillance that inspections are being perfomed and documented by personnel in confomance with approved procedures. 17.1.11 TEST CONTROL .The TUGC0/TUSI Quality Assurance program requires that price contrac-tors, subcontractors, and vendors designate appropriate tests to be perfomed at specific stages of manufacturing, fabrication, and ccnstruction. Conduct of test is governed by written procedures which incorporate requirements and acc :ptance limits to assure that the structures, syste'.s, and cc ;;r.0nts tested perfor.n sMisfac'.crily in s erv ic e. Tests are corducted in accordance with t!ase pr:ce f.res aad are properly docu. anted. T':e ;r!.e ccrtract.rs libbs & Hill, " tir.;h:cse, 'd Ec.n 5 '. t) as:cre tht all necessary tests are revired :.r.d c: Lcted. S.ch testing is perfomed in accordance with q tality assurance and engirr:ar-i g test proced*.res t.hich f rcor;; rate cr refic -:e the test requirc- _ ts -cd accc t :. ca l' r.its c. : ' af ned in., ;iir :la /n';n 'c '. s. e Test requic- -.ats v.J a. c y t.r.c a cri t..e f a t ra ;cmv i' d by U.a cr anizat':n rer; asible for t; ? spec.f h" tion of the ita.r'er test, -1as s ct' ir'il sc : s ' ;r. - t ad. Tha ca t !. a '. s t, c. 1 e:.;rs all 2 . f i, 21 37.1. 2
4 OVERSIZE DOCUMENT PAGE PULLED SEE APERTURE CARDS NUMBER OF PAGES: ACCES$lON NUMBER (5): 2 6 0 / 0 2 0 3 9 [1 - O I 2(o0/0203 ~7 I 860 lD X 3(o d-- 860/03C3'7V 362-ol l 260/020 % (o 760/O 2.0 367 367-c/ 362-CA APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH,TIDC FTS 492-3939 1 - ~~~-
' ~ TEXAS UTILITIES SERVICES INC. [0 Vf CPP-4947 OFFICE MEMOR ANDUM To 6.'Pravin Patel' Glen Rose, Ten. Aoril 29. 1991 subject COMANCHE PEAK STEAM ELECTRIC STATION TRAIN C CONDUIT VERTICAL RUNS We are aware that Train C Conduit, greater than two inches,in diameter in protected areas, is seismically supported in vertical run sections and seismically restrained (in conjunction with dead weight hangers) in hori-zontal run sections. During an earthquake, this can result in axial loads induced in the horizontal run of a conduit being transferred to the sup-port for the adjoining vertical run. Depending on the conduits' config-uration, this could cause support failure in the vertical run and the re-sulting unsupported run may cause unacceptable damage. The possibility of unacceptable damage resulting from this condition will be determined on a case by ca:e basis during an As-Built field review. As unacceptable interactions are identified, recomended resolutions will be sent to the apprcpriate Site Discipline..- I Mr R. O. Baco Field Damage Stuuy Group Supervisor ROB: EW:kss cc: R. M. Kissinger L. M. Popplewell C. Britt i
s, i., ..o I,, y z. Y c.t s .s g m- ~*~t.*- e' 9 l } } i,,s g a l
- s s ~ ~
. -m c =: .t :t*;- s-i
- o.o e,
ss w is i I tv 3v 2 yI a. 't !I = p .... i. s; "a o a 4.- s a,.n se a v.
- "' *t ' t..~ "t 4
9 n ec e s s ee ( .C !.06. 't. i.m %S ~, J,-}- V-e ~- i i C is bJ L'
- rV
.g'm N 3 N,2-3 i 10 n g: o y C -C I u =%n c9 n c e,s = o e e w 5 o .c.* j n g a. o e te es" c Wa c c cs ,,.? : ~ a ~ .o o!. = s m S = 3 ~ ,o,,v ,o s ,v u, ,,. a, - .< w c u, s s e* e ks / i h~, 4u r, w c e o o s'/ d y l D @d 5k. /* D w N e 9 k .C,s,6.s s .s,.s.s .o k vt. = = a.s,s 3 5 n ,5 & e i;5 e ~c .c N = ..= z - t *' g 'f'.g I v, = y [ - a 8. t-g e j f. h.,1 >s.4 1 $ s. Qi n Lu -- 7 YC.. S 5 i -w as 3
- q. q,
- 2
-4 ,-e er t a t-aun 3%. t = y ' % += =?, 2 9 t. e-e (' v. s-R$w n 1, :. J.
- o,3 c o o at nc
,2 = re v n WCSE h b c ~nqC*e**q 40 L. n e n O T vi W c v olo k l"!!433 ! ? s": p 4"t "* ( Ed 2
- a 4q g
73 'i;5B6%e "S* -is t D
- l j g j FEl3 3
.:. 3 -J f 2.-in ! ., n s - s 'I g 4 w A 0 3 E M St s " =5 E >, O c=
- n = w- = s s ~ S 1.C2E
>~ ~ .s o Cc5 >-w
- * * *=
M.- S g,1.O<Q. e o 2eegest o S uC .= li; E E "E g v se35hM*te=$s==3E,c ? " g,. g d?4 c 7 b h $8j 1 g i ii CE <t"w 'O i 4 : t' M ME!k=! c&,0E54j$$5$5ht a = B.- 0 '[" E W C !!5 it' illlll!I 4 [. e - =2 P i.i. *- w " Q 4 ; c' ' O '~s4: 0 4 e., w .a s a bg'.n II' w
- = n g w B : p., k,.,X i. m:=. p t. S B l ?. - k,w.h!III!
"n P e c ens n Euw m w a c op 3 &o 11.l ' ll 'l.II d. , e u s
- a. n c e n = < - e s t.e p4.
ese as-us es sgg I I,l d: s ut-m wuc lHI-e v = s ec c v a= a lll lI 4.; e.,. Ng i-.
- t 2.,
- g *., 3 < =. 2.-
- c. -ae e= s n1
>=, w. w w.:. w - c ~. w. ps, v = gr' i.1,! q o -n e o al' + s
- 3.., e s s sg s
5 5 h [3N.i.ON'E!ce w 6 4 w O MI,j. 5 d:: !N,.Qi $9!@% " N. i3 .m~., = 4.- %s o a.- og nnnmnn a u. c, u t,,4 g s, o y 4 4
- g, *
~ c;i h, e~ 3 ~5 w w = w.o
- k o pNN v.
T P ; w-y w me cwv g
- v. e j
OC< = 4 w =' c k NyN-,". p'" ! ' -'hi i M vw4R.'2*nEo w 4-3' [*d e ?$,l *k ka'N[ = 3 c - +9 E-d eh4c h h. '$3kE5'sE* N 2 - ::.s a $ O h U k k, c y-c % ,,4 % $ ~n e _ h"m u s t k h o c t $:" ~ k 'd >k $r ' u -),,f m a 9 - a g y,,e o w
- ec e
p h ) dak
- b 5
hbbb f w g a e E e -. ) Dhp - ~34 ~hC0L =. e s D " C,w n= e \\ i w et C4
- 4 ir =
Y s-lC- ~ ~ f~ I,l C le) IN ~ s a 'd =t em*=:Cn 334~ > C w i' b - h *'.g $ v e .-* cd r cc D u,, i emee s u 4.,, r a D-2 n ne u w Ovakst$4eq-ur W An.4=>pgChmtsgwCx5(g"8gEhangr2, 2 b q lme 2;m-s 4 I* llljl6l1llll. eg w 's ? E E C-;:l E ' j % v. n w.C.,5 % $ e FI:D A2 0 34 9 6',d4 h 4~4 49 l l l l M n g e = b O 2 g x v q. N %..IT.k.N'*I4(q s.'ez,e os ee n n.n,a ,O 4 b E csa,c "w s a m n.a wicq N VO 6-2 r Q 4
- k tt E s kl bw V
M 4* - g E
- 4 4*g 4tv=% :
y g % *1 N Y EQ4*. e y c %, = 3. p [ 423 rYVocyan p 3 g,y ocswte&.jRE"2 o s +- y 30 J' a& 24.Jt>g REC, 3 R C C C ( C 3_ w
- s 6..*, e h s c u,3 %,
Va w o e=
- ta
=4
e*C 4Ga43 v >~ n w w-
- w~ n u " Q v.--aws
~ 0 CTY $ }kb4 e R 4.g% - QQ * * *' V A *g e s 4 $j D I 4E y - e c ' c-n J. s w m.,,3 . e 3..s., N 4 g 2 M O q $ g~ e" w < h,, % 4 9 s c
- V $ * < s e e t e tS gFUN' Dygs O e
e $4 g J g g* Q k y.w,,n.w A 5,g t s -,% * -.,r 4 ' y yg,g ! c
- 4 a
qup y3*Ec Q *i, q. - c 4 w s w ^ kE _,., NC.- 2 k hk.. s,M y c & n. m...,p U,C m,,,,- w >. .. s.d - - ~ s* $ .e % .?y bakb. M% 4 f* M
- k "w N9 y Z 2 T1, Vw Q g g
~.
- S6
?-{- O e l,:.w C; ,i ,g 4 g *3 g e ant e.;,4 e E 4 k 4 h E*v N ' * " N *E M O M Q,, s. $.", g h C Q
- ,-"N a;
lp 4 - Q
- "cD m
e &#Pe b
= _ _ _ h5. N>, uafica. wewu:1 nuns : 11. FoR, ALL con reocTioN/ susP6cTe0H AFTf r. Nov. 85,sBat. : a) ffa%1st sorroni5 ktAT tt 60t6TITUTip F0st L(no wtGli SureDetTS ON Att CONOUlTO W6tK TH6H 2"4 ML To r1 tit TRAlHtp. IN A that GP Nt LticAL RUMS ONLT* HOWEVEd, veninAINT CAttt$ Ast 6fitL 00NDutT ftuNS :P (Luth ( 6t'4) AND LAFG6 DE*O A84 Surfunfto R200:49 UNLits ArthvED Bt DK,1NEtt4 NCn. ON COMMON ltA0 %tlGHT HAN64RS. THtN ONt GA THE PotocatlN4 'W~ %~ CAiTtA A Mui,T Et fATI6Fito
- b) FOC ALL CONSTAotis0N AFTER Ps0V.15 SS2 g VmTiCAL. (DNDOst RUNS a) De st97 TAINT fct.THt LARGSK CONDulf SHAU. 64 ARLE TD WITH-Luv 26 surfoticp ef LOO wtGli HAP 6tAS.
6TAND ADDITIONAL L4A0 0F GMALLEA CONDuris Indo660 T14Ro0GH COMMON E4AP w&G4T MGMeht. THt6 ADDITIONAL LOAO put 10 6L4ALL64 ConousTS 544ALL e4 toutVALENT OF ONE Puu. bPAN ON C) VERTICN. WESTRAlliTS Art sei staulkto ON A VEATICAL CONDolf WHICH HA6 CAIittA StCC OF COMMON PtAO WEeGHT HANG 4R. t A E8tv. PoiHT ( AN(, TION 804, EQUIPNCNT ftEE Ai4DADP) ArtD TH6 6f?+4 utAtosto Facu Tai 6 Itas.f wM t%:NT tt1JJteN k (A6J TWO HOKil0NTAL b) FROVi[4 INCEftreO6NT LEAD W4GHT H4466AS POR. # MALL 03NoutT8, e PEtl#NNiir TO TH6 trtAst POINT l$ Ltir$ D4AN OR tau %L TO L6e lett ECTAIL E, SH. LSK-2od istLet as notto ON s.se t. c) Et$TNAtH SMALL CONDusTS ON THE COMMON CfAD wilGHT Nm646A$) To 1W4 NtnT ed6M. fulHT ON EITHEA 6tDL. l BN60stt#JNG APPROVAL slauiRio Pon ANY DEvlAT40HS.
- attF 4 CavS Tet 8tr80rVATE TON 6 NUMcER POR EAcH BUfWING 6T ltf$4CN.
ALLosAStin AtSTRAaNT Sf'ANS A9 6440wa4 ON Wett t,6H.CSR-la AR& Gevtu et Cowt. Poet. A thetricutAnt perfA troNt) THE ActowAett SrAN 4/ t.ani Ncf ex4101HE vm.ut eHowN IN Tr4tt. I, GH. dSR la. [4(pqDett:40tNfLT ourf0fft0 %f I o teso wi.N**4eets atit.1, As fes( NOTE 2'!b) TA85t.E 4 'l'I i [4 D --m0N D6AO $4rtGAtw $ tu t AusloanA 1 ELE G. Mr. 57tuttlt.ttra FUEL 6LD&. GLic.fcDeff. 6Ltc. it.tlGHT H844bA i -- g atw.oM aw e44. Tow r.m iuafma w aevArias at nevar:08 mt o o c: U-M' 44 3%*Ci t(W. 41 339'c ~ 20519' [81 96*-0* [4) STSL
- 1; O 1 0 hh OO OO 4
eue-E eere ees'r 4 ane W as4t4a S we acosci g *SHAYttA tk A Connot j 1 k,,p, est v 3 oTyr o awo* 2) o&oto*/ I aSo'-o' t gi'4 0 are 2 es w W ewe t 44c.o 1 i aov0-w wr. men rm 4:es3=n s f g ~ N CAPPCITT i 60' G* 2 851*.d 145 608'0" E ots'-o* ' T 7'IS' 0* t A 1 M 680* 0* [ ) ! 190'.G* I alo* G* ( S
- E St1*
I g 'r T 4 F h M N N0*t M4 h ('n'(4A AS ADO TIONAL 1c3:p 34 vsosc S ( f^~ r 4 773tp g) - ~ " ~ N 3 / J6 LDAD ON RSGTRNNT) l ~ ccettMATic SiteTC4dfilh 41G 1 PLEMENil0N OF N0ft.ET (3i 2,cr,i_ o7 4 v 90 6 u. TEEKA5 UTH,lTIE6 6CKVICEG,lHC. ikAIN '(,' CONousi $tl6MIC f46TILAIM = %yg3 ' " =.,16( /f aum M uorco 3 g7gggg .T MJM T .itV6t0 f6 tNTED M @hj AntrgApr r,Agtgg %+ t 3 ~' tam m f 8tvt'4D M N01tO 4IN 4.3410_ COMANCI E 8-. cowsTructsoun.m 64io 6fEW LLf4TFJC $1ADoN .. j g5g3 g,3 'S" 8" 0" (AbJ Kost,Teshr SH. -Id I
11N41' lit.HI Ottth. not pet ( toeta rf- (tstthesT CLle rtir 'at'I's Os(TS pit.T rm s*J; (41ESTITisif.1)
- J f.
r
- 0:. scttT64ktt1T$ Latte I b9 th'TC.O.
O,g g plit{* ~ ttl6-llnLF,.Mucre + ~ es) -(t0*t t tit eWTs A.L t'in s100 atrali. 6 8t. I esiteYc eMel. !p L) ;t.tt#C felfttst$ (MCD (*lLT 8000 A IT*llop{ er isPS. Seatt(F0Vt000 A f, ,. [ilff. rwSteHi!Natif t.stSt$ At t Atti t.ND Os* 18168 tttit0N Ot *M8tl. e 4 5 M I'l,8 (t.C., J*eC.iuti EfW,118tL top, IliiF, ti1L.) ([r,y>-. - A :41 tPiaL () sosp4ec Sassivwas sus'erer tesy (tass 10 routitHl3 MAv EL Ulit.ife.P AS l'l(TOl Clos $ 04: Pt'.SS (500 SWE1Clit S 3881$ 388* 4.T). _f _ _ ]. f Pbl C.N t( Ats t.s>Au tans >At*16.ovtDtts(. (sest litt.t. Sit AP I$ U54.0 IN Lit.O of _f' e j __ l' 60 6 6 _ s. sr N, 90t* g / bTa O Als 'tt.tes g,g,g.g 3 l l hf, LT,IAlt. I ct. 4 etw:raint t'sitansenh.EttICKtHG INIQ 05t $2111Nf, f KOH Tilt" fWCM-N N c (N.u n.o m ise e xi o occinc.e si.'Of fxouti M (ANJuvit,1 goH { "._b- ._t a_ g, { \\, VFellt t%CL Ai f=tt-IChilcti GLM $ $. $1480(, 'Jlltitt E6 jlT't'OftI6D A$ g, ) ( J "' f(LLC ~ii% !I I ( 1 [ th 'P
- t tite.*,igiti (*10 rWE. I't (O (e** f M trrif 641'ti, Estti'i' tN (,$R
,de / 4 Lt.lset4 stilettrl Is't t A8C' AL CA(*-) lift.N 1*lt ti$f Ot fetCII Ft'fT'rW ib 'O T AOi UOL I 6"g gq 3I e=w i oss).e. net av ir. este : es. r Lebwarittis'd N tett CONOsitf(C,) (AUtKNAIC 00LTIMfi 0 -/ ~ a t, Jiw4tisve eeu, situ. tes, Itt,zit tC Cott04'sT, ETC. (1GTAll. IN LXil(f ggggg fot.r tiikin ucs Art l } IP f t/!*tWC pct (Ta*AfHi$ Adf LIIILI2tLD,(A$ fil! Lhlfstr.0$so,CCC f11J5) gg g,j g g (rg,g,ggg (gggyl pp,t gggg.,g F8 (Pre la'*ttilot4 velf st. itAD Vlt lf.st! 1N*S TWi!. Wifelett TitC tWfs . e lff.4. es 6 3 tge oce se tc. etteg4 (p,31 eNOE Pet 0142 ft31.5, &ted rAdrT Al 'Nk.fbY e T.et treTLtsqG ot Ex Ts G futetr. M INO O"'O ' M ON issF.sessaoo.e ga( .,t.-T. t_s) :, ers oscA*'st Mn $tss' acts spe3tAttt0/are5PdCT90 tititt TO, =, = n,,a. #u, yr w ,m, o p. . 3 n,,, ,w.wt. n~ a ...,.-t..
- ., _,u~
tIEt.tal MiD s Q' - Af' tth"D) " T g-iw i,l II. ..d (rs1T m e6.~ WA dth it Oli i'410'VJtwit <Q' - ',.) ftP4WTifdlif..y 8kb I .uso.- i a.W4ff Mull. C 84LMr45f0P-g g iu,mio,s or. (vmno) ,, /c- ,e gg..,! ..i.ocexnIr.;c u u.t. u u... - .ri'A ishdLrts: LG 13,5f i4 bit. f G [ ~'k 'L8JI'U*Il 's,'T&lPI CM8113' StttiLib 5 i8?til-p' 3 1 tot 4AL,) i s !SII OR ENGINEERING si,cn n.4 tu,m., tar " 'M * *U. til E [ 'At-:ist M1t'ATi-(M TEM (J t Lli.fcLE tw tiert4 cu ,,y g,.., , m m u m )HKrediE.;sr...._ __,m -_,hoESGEcMSE ONLhun t "'E 1 e a e o e c..o n =. m w e \\* # ',feest w.o tat. cur;tG e>Ietsigt r.:we+ sentwp) t v.
- it 3, d5TtAlHT:. (s4 Iiii, L C
'4%g 3rf _. y g .tvwto ee, Nato m.Itri 0F 5-C90 t% Ai.). NO,O, q M V .Grwe 34 ris .uve n,,g,g gy g> e T* Airl CoaWIT ntre witt, et IN51Att.- C 4.% %fi. Z Ty, Z r Z ZZ Z Z eg,vit.co y N6 in ygvg gg cgegg geg,ggq n[Ar C $ MD 9 C NY'5* en' N""I" N ' e,. ~,., m m, w a =.tw' dam = n C ~~ UIlllllNCi e c IL e 4 utim mmr uem
==
f-M'i h 5 5 --~ r ~ ~ NNN)bs~r:AT.LWNCII& IDK W za amiau = . o..c :=4.u cowon s.$ uin itu .". m** * '. 'c ,'O -,,,,.o,, 4 ~wu1= ,n as e. , se en s. O t.itti 6ta,n.5i'- 'n. c, .le,
~, E 19 t "3s 55 gS e WIk21_.I!!' j! z.l-l.gM. ! Q ...........e3 g $..u J l5# hs 5g 's s!! $5 l Sq e [bj! 4 J: E =ig a w. 1.34: 8 m _o 5 g sig si ea' E6 su~ @o E! !$ M EM$ 5$ $d 'g 8 35 *+ a sgI r2 }318 e#s :?e se u; g$ =st @ g' p: !W E. ** g fg 2 E$a 2g wp. 3 '$h!:!!bu a gud 18 dol!ip !! b5 5 h fk ~ ya b a ;* a it ilnaj11!
- I lil l s$21f.og&'!!ig$bii$5
$*EiYE.6455_BI m$c s$ g 'p gsc 50 N55 ni M. $@j8@f@e 4. $s 7 s . 4..L:s._. - 3 g; es s' __ o a l;; a p E' ~ 4 3 2 2 1 a y, si [_ S ~T 3 o o a 3;m-7 18 f ~g s7 a Lo hYN - #l# g y i 4_ >i> g IE NL '- j pf {g 5 i it I l r v Ie L
- ]
I I i 1 EO he E [8 j l 'll /\\ / TI 8 s2 l l h[ $!e kf hl l l 'lf b f $ 1 gl 1[- bt*
- et :
,I i 51% !.MI I !JLE ! ! E! I 'I aie <, e e in, f 8 lilli lllllll li i ~gs w $ _w g y 5 \\ $ m*t ~ \\ $3 I I .D. fis '- 5pc A i w g b 5 5 ^ .nzy l l 8 g i 4 g
- 1 se gg
~$ \\ d esame w' WY
? N A I h l} . %f
== i cr m W g 4w Il itt,s50 U.C2%NCE SM C STATICN c.1. , yr,,cR::mIC, (WII.:.) OIIZE0EHX BE DC::1GCSATED IN CGICN CCC::MCC DG NO. 4693 REV.10 /S 1. SAET:T RE:.mD
- XX YES N3 2.
CRIGD ECR: CPPE YV CRIGDEI. DESIGER 3. CESCRIPTICN 2323-El-0900 13 A. APPt. GBI.E @@tNG/uCGniniX 2323-El-1701 _REv. 10 8. EE:AIIS THIS REVISION VOIOS AND SUPERSECES DCA #4693 REV.9. "See aTTacHr0 SHECTS."* REV. 9: Changes drawing 2323-El-1701 Note 40 and drawing 2323-El-0900 Note 7. Reinstates attachments 1 thru 9. Adds attac hent'10. ccV in-opvita< mcoe si and 4 and 7 =, nn+.,4 nC m 4 3 y. j, J. J r oCIV bh ng.v.- ...co A g g1 J. v
- 4. E7PCR:'OG MMJC"CNr
_ _,,,ueMT CONTROL CPP.1n.opo. cooa 47.in1 gww m 5. AFPPcvAr. s :ateFrs: JHO:dw May 3, 1984 W. O. A <I. CA 5 3 8 J. A. CRIG a O R: c. B. CES:CI RIZESECATI'JEs [ ttN fd CA:T
- 6. h..,bi
@ em s. 9 - ra 1 c. c
- =,,E
,awa w - 6. 5-mcAPD u b - a.rt AMS (CRIGUEI.) (1) Mark Welch OA 1) ocAIr:Y. cc=tEr?.nc (1) W. I. Vogelsang EE 1) DC:o rea CRIG. cEsI=t (1) Civil Engineering 1) WESTINGHOUSE. (1) . Civil -Design Review 1) G. M. Trieste R/B Task Force DCA ICFM 3-44 C. A. Themas E/C Task Force C. R. Hotton Aux. Task Foyce g[4O gi 'Y 'k 1Wa US,0yer, EE j%i bh[jq={T' kip [
- 0. B. Jones S/G Task Force M/5-4 I h
}{ F ~ ~ ^ ~ .~ au... ..a....
], OCA# 4693 Rev. 10 l' Page 2 of 16 i -i.i REVISE DRAWING El-1701 As Follows: 3 i NOTE 1: Revise the third sentence to read: Typical details shown on Drawings El-1705 and El-1705-01 apply only to non safety related equipment and raceway systems. See general note 10 for cable tray support req-uf rements.See General Note 40 for conduit system support requirements. NOTE 10: Revise the first sentence to read: i Cable trays shall be supported as follows: Revise paragraph a to read:
- a. Category I Buildings-Cable trays shall be supported as shown on structural drawings.
j Revise the first sentence of paragraph b. to read:
- b. Non-Category I Suf1 dings - Cable trays shall be supported as shown on drawing El-1705 j
Add Note 40 as Follows: NOTE !40 : Exposed conduit systems shall be supported as follows: A. Category I Butidings-Supports for the Class IE (Note 36) yste*m and those identified by Suf fix "S" Conduit S shall be provided as shown on the structural 4 drawings. Supports for Non-Class IE conduits.( Electrica Tra in "C" ) shall be as shown on Drawings El-1705 and El-1705-01 unless otherwise noted. Attachments 1 thru 9 And Table 1 define the requirements fc the support of Train "C" conduits. The cross hatched areas on the attachments denote where supports are 4 to be seismic or deadweight with seismic restrain' In the uncross hatched areas, certain Train"C" conduits ( larger than 2") ) are required to be supported or 3 restrained seismi cally. These conduits are noted on 2323-5-910 Sheet CSR 15. + i S S I i ^ -~ _
DCAf 4693 Rev. 1 Page 3 of 16 1 TABLE (1) SERVICE l TRAIN C SAFEGUARD REACTOR AUXILIARY ELECTRICAL WATER FUEL j CONOUIT BUILDING BUILDING BUILDING BUILDING BUILDING BUILDING 1 I 3REATER SEISMIC SEISMIC SEE SEE SEISMIC SEE THAN OR OR LTTACHMENTS ATTACHMENTS OR LTTACHMENTS 2" DEAD WEIGHTDEAD WEIGHT DEAD WEIGHT WITH WITH WITH SEISMIC SEISMIC SEISMIC RESTRAINTS RESTRAINTS RESTRAINTS EQUAL NON-NON. NON-NON-NON. MON-TO OR SEISMIC SEISMIC SEISMIC SEISMIC SEISMIC SEISMIC LESS THAN j 2" i ) i i
- 8. Non-Category I Butidings-Conduit system supports shall be as shown on Drawings El-1705 and El-1705-01, i
4 DCAA 4693 Rev. 10 + Page 4 o f 16 4 REVISE DRAWING 'El-0900 AS ~ FOLLOWS : s '. i NOTE 7: In Category 1 Butidings, Class 1E lighting fixtures shall ~ be installed with seismic fixture restraints as shown on drawings El-1704, El-1704-01 and El-1704-02. ~ Attachments 1 thru 9 and Table 2 define the requirements for the support of Non-Class IE ( Electrical Train "C* ) lighting fixtures. The cross hatched areas on the attachments denote where Train "C" fixtures are to have seismic restraints. As a result of a damage study walkdown, certain Train "C" i If ghting fixtures in the uncrosshatched areas rsquire seismic j restraints. These fixtures are listed on Attachment 10. To preclude another walkdown at a later date, all Train "C" i Itghting fixtures installed af ter 2-24-84 shall be installed with seismic fixture restraints in accordance with Drawings El-1704, El-1704-01 and El-1704-02. l ~ I e i J l I 4 .i TABLE (2) i j SERVICE SAFEGUARD REACTOR AUXILIARY ELECTRICAL WATER FUEL t SUILDING BUILDING BUILDING BUILDING BUILDING BUILDING l .j " C" Re:traints Restraints ATTACHMENT IATTACHMENT: Restraints ATTACHMENTS TRAIN Seismic Seismic SEE SEE Seismic SEE j e LIGHT Required Required Required i FIXTURE: i I 2 i \\ i i i 4 l r .,,-.,._--_3 ,-,..__,,.,__m,._..,_.m..., __,,-....-7_-__.-....7__
_...m. j DCA# 4,693 Rev. j Page 5 of 16 ATTACHMENT 10 e s A00M - SLOG. ELEV. LIGHT # LOCATION ~ AUX. 790' 174-12 5 ' E o f J-A AU4 ' 6 " S o f 7 A 4 -174-13 2' E o f J-A & 5' S of 7A o f F-A & C.L. o f 6 A 174-30 j 180-46 l'
- N o f 7 A & 9 ' W o f FA C
7 180-56 11' W of FA & C.L. of 8A 180-4 8' W of FA & 8' N of 1 A 810' 190-6 2' E of KA & 4' N of 4A 193-10 7' W of LA & l' S of 3A 207-6 7' 5 of 3A & 9' E of JA 207-19 8' 5 of 4A & 8' W of KA t 207-20 ' 5 of 5A & 8' W of KA 207-46 C.L. of 8A & IL' E of JA 207-110 N o f 7 A &(2 J' E o f E-A 207-115 7' E of EA & 2T 3 o f 9-A j l 206-5 E of FA & C.L. of 3A 10 206-6 11' 5 of 3A 2' E of FA 2C6-7 4' E of FA & 1 ' 1 of 2A i 831 ' 226-36 C.L. o f 3-A & 2 ' E of E-A 226-41 131 o f 2A & l ' n_f FA 226 40 12 ' N of 2 A & 2 ' E of EA I i 219-10 l' 5 of 2A & 3 E of GA 219-16 3' N of 3A & 3' W of NA 219-29 14' S of 6A & 3' W of HA 1 219-36 8' W of GA & 11' N of 6A 211 -71 11' E of KA & 9' N o f SA 213-90 10' N of 7A & 10' E of J-A l 21 2 -1 4' E of JA & 3' S o f 8-A 842' 230-8 8' W of JA & 5' N of 6A 230-16 10' 5 of 5A & 3' W of JA 230-30 11' W of JA & 8' S of 3A l I l 230-40 12' E of KA & 4' S of 3A of 4A & 12' E of KA 230-49 .852 235-11 '6" S of 8A & C.L. o f KA 241-1-11 S of 7A & 15' W of GA I 873' 245-68 C.L. of HA & 3' N of SA 244-44 13' W of LA & 3' S of 3A i 244-58 1' E of JA & 14' N of 4A 4 244-24 6' S of 7A & l' E of JA l 244-3 12' S of 9-A & 5' W o f KA 244-4 of KA & 18' S of 7A 886' 246-5 ' N of 8A & C.L. of KA 246-31 18' of 1 A & C.L. o f KA E&C 779' ALL-C l 792' 125-C 127-C 129-C Stairwells EC-1C, EC-2C 840' ALL-C i SWI ALL ALL-C i l
i-f DCA# 4,693 Rev. 10 3 - Page 6 of 16 1 ATTACHMENT 10 s ROOM - 1 BLOG. ELEY. LIGHT # LOCATION AUX. 790' 179-1C 7'6" N of 2A & 6' E of GA 179-2C 4'9" W o# HA & l' N of 2A 3 5 N of 2A C.L. HA(% 179-3C 3 31 ' 220-1C 10' S o f 6-A & 4' W o f GA 220-2C 16 ' S o f 6 A & 3' W o f GA 220-3C 10' S o f 6A & 10' W o f GA 220-4C 16 ' S o f 6 A & 10' W o f GA 852' 234-1C 16' W of JA & 8' N of 6A ~* 234-2C 16 ' W o f JA & 5 ' N o f 7A 234-3C - 16" W o f JA & 15' N o f 7A 235-lC 7' N of SA & C.L. of HA c'. _._" 235-2C 7' E of HA & C.L. of 8A 235-4C 15' E o f H A & 7 ' N o (~0L 5 ( y (___ 235-7C 13' W of JA & 7' S of 6A 235-8C 13' W of JA & 7' N of SA 235-9C 13' W of JA & 6' N of 4A 235-10C 13' W of JA & 7' S of 4A 235-11C 13' W of JA & 9' N of 3A 235-12C 13 ' W o f JA & 5 ' S o f 3 A 235-13C 13' W of JA & 16' S of 3A 235-14C C.L. o f JA & 16' S o f 3A 235-15C C.L. o f JA & 4' S of 3A 235-16C C.L. of JA & 9' N o f 3A 2 35-17 C C.L. o f JA & 6' S o f 4 A 235-18C C.L. of JA & 7' S of SA 235-19C C.L. of JA & 6' N of SA 235-20C C.L. of JA & 6' S o f 6A 235-21C C.L. of JA & 13' S of 8A 235-22C 12 ' E o f JA & 4 ' N of 7A 235-23C 12' E of JA & 7' S of 7A 235-24C 12' E of JA & 8' N of 6A 235-25C 12' E o f JA & 6' S of 6A 235-26C 12' E of JA & 6' N of SA e 235-27C 12 ' E o f JA & 6 ' S of SA 235-28C 12 ' E o f JA & 6 ' N of 4A } 235-29C 12' E o f JA & 6' S of 4A 235-30C 12' E o f JA & 9' N of 3A 2 3 5-31 C 12' E o f JA & 6' S of 3A 235-34C C.L. of KA & 6' S o f 4A 1 I ......... ~..,
,3. DCAP 4,693 R;v. 10 + Page 7 of 16 ATTACHMENT 10 T ROOM - j BLOG. ELEV. LIGHT # LOCATION k-AUX. 852' 235-32C 12' E o f JA & 16 ' S.o f 3 A 235-33C C.L. o f KA & 9' N of 3A 235-35C C.L. o f KA & 6' N of 4A 235-35C C.L. o f KA & 6' S of SA 235-37C C.L. o f KA & 6' N of 5A 235-38C 13' E of KA & 8' N of 6A 235-39C 13' E of KA & 6' S of 6A o f S A ))dhi i 235-41C 13' E of KA & 6' 235-42C 13' E o f KA & 6' N of 4A + 235-43C 13' E of KA & 6' of 4A 235-44C 13' E of KA & 9' N of 3A 235-45C 13' E o f KA & 6' S of 3A E4L-1C 9' W of FA & 9' N of 8A 241-2C 17 ' W o f FA & 9 ' N of 9A 241 - 3 C 10 ' W o f FA & 2 ' N o f 8A 241-4C 17' W of FA & 2' N of 8A 241-5C 8' S o f 8 A & 8 ' W o f FA 241-6C 8' S o f 8 A & 1&' W o f FA 241-7C 9' W o f FA & 13' N of 7A i 241-8C 5 ' N o f 7A & 10 ' W o f FA 241-9C 8' N o f 7 A & 14 ' W o f FA 241-10C l' E of FA & 5' N of 7A 241 -11 C 2' E o f FA & 14' N of 7A 241-12C l ' E o f FA & 6 ' S of 8A 2 41.-13 C 3' E of FA & 6' N of 8A A 241 -14 C 5' E o f FA & L mof 8 MA o 241-15C 7 ' E o f FA & 9 ' N of IA s 2 41 -16 C 9' W of GA & N of 8A ' 241-17C C.L. o f GA & 6' N of 8A 241-18C o 7' S of 2A & 7' E of HA 241-19C _Z ' E o f J A & 6 ' S of 2A 241-20C u2 2 ' - 6 ") E o f JA & 5 ' N o f 2 A 242-1C z ' E o f FA & 4 ' S Of 3A 873' 244-1C 8' 9" N o f 2 A & 6' 6" E of KA 244-2C 6' W of LA & 13' N of 2A 244-3C 10' N o f 4 A & 5 ' 6" E o f KA 886' 246-1C 13'6" W of LA & 9'6" S of 3A y } 246-2C 3' S o f 3 A & 13 ' 6" W o f LA 246-3C 4' 3" N o f 3A & 13' 6" W of LA 246-4C 9 ' 3 " N o f 3 A & (L3 ' 6 "/ W o f L A 246-SC 13' N o f 3 A & 18 ' 3" W o f LA 246-6C 4 ' 3" S o f 4 A & 14' W o f LA 246-7C C.L. 4 A & 13' 3" W o f LA 246-8C 15' S o f SA & 13'6" W o f LA 246-9C 7' S o f S A & 13'6' W of LA 246-10C 9' N o f 6 A & 13' 6" W o f LA 246-11C 14 ' 6" N o f 7 A _ & 17 ' W of LA -( 246-12C l' E of JA & (f 3 ' 3 f 5 o f 8 A 246-13C l' E o f JA A 6' 6 N of 7A i ("_ 246-14C l' E o f 4A 4~7' S o f S A k
~ l ')- V Drcf t 4 - 8/6/84 ~ Electrical 5/CP3 COMANCHE PEAK OPEN ISSUE ACTION PLAN Task: Electrical 5 - Control Roca Ceiling Fixture Supports Ref. No.: AE-17 Characterization: Allegation concerning field run conduit. " drywall and lighting installed in the area above the panels in the control room. Initial Assessment of Significance: Components may not have been installed properly. These components may have safety-related significance. ( Source: Refer to CP Allegation Chart and Statement of Allegations from source documents attached. Approach to Resolutions: 1. Inspect electrical component installation referenced in allegation. 2. Review NRC regulations and the applicant's FSAR comaltaents. 3. Interview personnel with responsibility for the electrical comporant. pd 0 ._J l L
i . 4. Refer any deficiencies to TRT manager. 5. Evaluate allegations for generic / safety implications. 6. Report on results of review / evaluation of allegations. 7. Review IR-83-24 to determine if documentation adequately supports I findings for this allegation. Related Open Issue Identification: N/A i Status: Open Review Lead: Jose A. Calvo Support: None Estimated Resources: 12 man / days Estimated Completion: Augu st 10. 1984 CLOSURE: Reviewed by: TRT Leader 1 m
= -l g ) 3 ') g UNITED STATES NUCLEAR REGULATORY COMMISSION e ig jj N wasmmeTom. o, c. zones OR/ May 4,1981 kr CEIVED TO ALL LICENSEES OF OPERATING PLANTS AND HOLDERS OF CONSTRUCTION PERM 15Y 2 21E T.U.S.I. - NUCLEAR DIV. t.! CENSING Gentlemen:
SUBJECT:
QUALIFICATION OF INSPECTION, EXAMINATION, AND TESTING AND AUDIT PERSONNEL (Generic Letter 81-01) Appendix B. " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50 establishes overall quality assurance requirements for nuclear power plants. Two Regulatory Guides, discussed below, have been issued which provide guidance on an acceptable way to meet Appendix B requirements. Enclosed for your information and use is a copy of Regulatory Guide 1.58 Revision 1, dated September 1980, " Qualification of Nuclear Power Plant Inspection Examination, and Testing Personnel." Regulatory Guide 1.58 endorses ANSI N45.2.6 with certain exceptions. The NRC staff has determined that the intent of regulatory positions C.5, 6, 7, 8 and 10, which provide additional guidance conceming the qualification of 1 nuclear power plant inspection, examination, and testing personnel, should be implemented by all operating nuclear plants and those under construction. Also enclosed for your information and use is a copy of Regulatory Guide 1.146, dated August 1980, "0ualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants." This guide endorses ANSI /ASME N45.2.23-1978 with certain exceptions. The NRC staff has determined that the intent of this guide should be implemented by all operating nuclear plants and those under construction. Therefore, you are requested to furnish the following by 90 days from the date of this letter: 1. Connitments to meet regulatory positions C.5, 6, 7, 8, and 10 of Regulatory Guide 1.58. Revision 1, and Regulatory Guide 1.146, and your planned date for doing so; or 2. If you elect not to adopt the methods given in Regulatory Guides 1.58, Revision 1, and 1.146 describe your alternative methods of complying with 10 CFR Part 50, Appendix B regarding qualification of nuclear power plant inspection, examination, and testing personnel, and qualification of audit personnel, and your schedule for implementing the alternative methods. q ~ g p) bl % 2 n- ) v I g
l D 3 o In your response please refer to this letter by title and number. Any questions regarding this matter may be addressed to your project manager.
- incerely, a
Y $$h h 11 b' Darrell G. Ei nhub,Directo'r ~ Division of L ensing ~ Office of Nuclear Reactor Regulation
Enclosures:
1. Regulatory Guide 1.58, Revision 1, dated September 1980 2. Regulatory Guide 1.146, dated August 1980 cc: Service List 9 9
) ) i 5 N August 1980 ) ["'**%, U.S. NUCLEAR REGULATORY COMMISSION @.m(. ) OFHCE OF STANDA GUIDE REGULATORY GUIDE 1.148 (Task RS 810-5) QUALIFICATION OF QUALITY ASSURANCE PROGRAM AUDIT PERSONNEL FOR NUCLEAR POWER PLANTS A INTRODUCTION with the pettinent quality assurance requirements of Appen-diz 3 to 10 CFR Part 50, subject to the following: Appendix B, "Quakty Assurance Criteria for Nuclear Power Flaats and Fuel Reprocommas Plants," to 10 CFR I.Secnoa 1J of ANSI /ASME N45.2.23-1978 states that Part 50,
- Domesas Uen. mas of Production and Utilization documents that an referenced in this standard an identfied Facili,4
- estabisshes overaR quality assurance requartments at the point of reference and desenbed in Section 6 of the for the deman, construcnos, and operatson of safety-related standard. The specific appucability of thess listed documents structures srseses, and consponents of socieer power has been addressed in the latest revison of the following pa.ne Catenos XVIII," Audits,"of Appendix B establishes regulatory guidest nquarements for conducung sedits of the quality assurance program. Thas guide descnbes a method acceptable to the AN515tandard Regulatory Guide NRC staff for complytog with the Co====aa's regulations with regard to qualille=*4a= of quality assurance program N45.2 1.28
} eudit perunamal for nacisar power plaats. N45.2.9 1.88 N45.2.10 1.74 j The Advisory Comanuttee on Reactor Safeguards has been ea==itt.d concernans this guide and has concurred in
- 2. ANSI /ASME N412.23-1978 does not include the stats-the regulatory pomaan.
meat that is found in other N45.2 series itsadards excluding activities covered by ASME Boiler and Pressure Vessel Code B. DISCUSSION Sectioa III, Divisiona l and 2. and Section XI from the requWments of the standard. The NRC staff connders that Working Group N45 2.23 of the American National AN51/ASME N45.2.231978 applies to these Code covend Standards Co==itt.e M45.1 sector F! ants and thest Mam-activiti s where the ASME Code does not address the require-tenance, has prepared a standard that provides requartments monts covered by ANSI /ASME N45.2.23-1978. and guadance for the q "ta*w= of personnel who partic-ipate la audits of quahty womrance programs for nuclear D. lMPI.EMENTATION power plaats. The standard was approved and dengnated N45.2.23-1978' by the American Nanonal Standards The purpc,se of this section is to provide information to lastitute on Apnl 20,197L applicants and licensees regarding the NRC staff's plans for uang this regulatory guide. C. AEGUI.ATORY POSITION This regulatory guade will be used in the evaluanon of The requartments that me incinded in ANSI /ASME applications for construction permits and opesating licertses N412.231978 for quahfication of quality assurance pro-docketed after August 29.1980. In addinon. the NRC gram audit personnel for nuclear power plaats are acceptable intends to apply this regulatory guade to operating plants to the NRC staff and provide an adequate hans for complytag and plants under construe: ion. Implementation scheduies i wi!! be determined on a case.by<ase bans for these facilines ANst/Asnes M.S.2.2319ts, u.a.t Q sty A by the Office of Nuclear Reactor Regulanon. It is espected ,'***,,,$8',',,',Af,'. gg 'Q=8"y Q[,t**"{"*g that this tegulatory gunda wd! be requared to be impiemented s Ens.ita strws N.w Y,o,qr s eet1. by these facdities by February 2,1981. O I 3 PP-usnac ar oui aroav ausoas c.m . w ,,e e s=,w.v.. i. e M O'tti ":,,:'t.:: Jan::"...~"."e.'."...,c .......,.,.,......... c. v, ...c e. l '3"*E..".,.5.'.M.,.5. 5'6..,E...M.. 53...E55 l:. :=. ",t:','.*? e t t='.'., o.
- a. co.
- 't,' '.,",., *t.,.,"..lcr.",,",. ". ".,',::".:' :' ".=:*.' "t.'A'".:
t 2". =",:"*n".:. i6. 3:: =""* "~'" ""-- .v e.,.,,.,,,.....
- c.,.i
..o m o.. .o. .v... e. ... n. 1 ......~~.o o. .......e...- m........,.,..........,..~o.o...sv .J.c--..u..a ~.... .."L.c ....v........ 4 . se s s s. n.... l
. _.. ~. [ ) ) ) s VALUE/lMPACT STATEMENT
- 1. TEE ACTION associated with NRC endorsement of the standard should be as fouowst f
1.1 Demmipeloa I. Some ladividuals may not qualify as lead auditors. The appiacent (laceasse) of a nuclear power plant is thereby creating a need for more sapenence and tramms seqiared by the Commasson's regulatsoas to estabush and of editors. j impleasst a quality assurance program. The applicant l (liceasse) is also seguired to carry out audits to venly
- 2. Conformance to the standard with the exceptions l
coatplisses with the quality assurance program. This noted will require admmastrauve effort on the part cf regulatory paide passants psadance for qualiracation of the employer. i. personnel who perfona qualiry assarance audats. These impacts may have an inarial monetary effect on i 1.2 Need the industry but should be compensated by increased quality assurance as a result of the audit. UntG ANSI N45.2.23 was pubianhed, ao defanition of 4 f gn=Ime= edam saidelanes for quality assurance audit perna===8 JJ.4 h'orkers freienne to ALARA/ had been published by the NRC or the industry, reamleing is acauaiform medit propens with verytas standards of Not applicable. i
= a===
A draft standard ANSI N45.2.23 (Draft 3, Revtsien 1), "Qualifisemos of Quality Asanrance Program IJJ AsMie Audit Pa=====I for Nacient Power Planta, was approved on j Apal 20,1978, and desiseased ANSI /ASME M45.2.23-1978. Fedme
- Unifone standards for auditors and lead auditors Gedamos em qualMisation of quality assurance audit should reesis is more unaform audits. More uniform audits personnai is proended la this roadstory guide endormag the should lead to increased reliability of nuclear power 1
i appresed==ss===I standard to emesse more ensfonsdty is plants. l audit programs and asseanted standards of onceusace. /mpeer - Amy costs pseersted by upgrading traanans to j 1.3 Vales /Impest of the Aseen qualify auditors and lead auditors will eventually be passed on to the public as rate increassa. IJ.1 NRC Regalatory Pontaca I provides lafonaanoa to the user Fonse. Ptior ts the assiance of this guide endonnes a of the paide on how to apply referenced standards and has standard, so guadames has esisted in the area of auditor and so impact. lead meditor q==M==sinam The NRC has been making l case.bygens detersusseions la this ares, which has reunited Regalatory Poacon 2 clarifles the coverage of ANSI /ASME is asemaifona practices with regard to requirements N45.2.23-1978 concenung ASME Code covered activiues } placed as q==Ma=*6a= of auditors and lead auditors in the by stating that the code abould be used la conjunction with ladustry. This guidance will summate the need for most ANSI /ASME N45.2.231978. case-bygase deternunations, which abould (a) reduce l staff review time, and (b) provide for more uniformity la 1.4 Decisies en the Acties qualifiestlos of auditors and lead auditors. This genide is beans issued to provide recommendations i linport.No impact cam be foressen. asseptabis to the NRC staff os qualification of quahey asastanes audit personnet for nuclear power plants. IJJ Other Genernment Agencser
- 2. TECHNICAL APPROACH Not applicable, unless the sovernment agency is as applicant.
There are several approaches that could be taken to the i quahfication of lead auditors and auditors. They are as JJJ Indastery follows: This action estabhshes an NRC postion to an exisang
- 1. Quahfication by National Board of Examiners.
national standard and therefore reduces uncertaiary as to
- 2. Qualificanon by Management (subjective dectsson).
what the staff consdors acceptable in the arpe of qualification
- 3. Qualification by establishment of minunum atandards.
of quauty assurance audit personnel Most of the impact on i industry has already occurred during development, review, The pros and cons of these approaches will be analyted and approval of the national standard. Addinonal impact in the fouowtas paragraphs: i i 1.144 2 l
aa l ~% l Approech I Approech 1. The NRC's regulauon (10 CFR Part 50, Appendix B. Cnterion XVi!!) has a requartment to conduct ho. It would provide a derutite and uniform standard audita. ANSI N45.2.231978 provides sufficient guidance to of quahfication. meet the requuements of than sectaca. Ces.It would be expeauve to mauttana the Board and Approach 2. A regulatory guide endornas the nanonal pay for the travel of the candidates. standard provides the ladustry with the NRC staff pon-Com. The physicalnumbers of auditors and lead auditors tion relauwe to a method that is acceptable for quahrica-make this approach impractical. tion of auditors and lead auditors. Since there are many alternanves for qualifyms auditors and lead audators, it is Approach 2 act deared to make any single method a requirement through the regulatory process; thcefore, a regulatory ho. It provides the samest method of qualificanos for guide endorung a naconal standard is the proper procedural the employer, approach. Com. It makes it difficult for outade agencies each as
- 4. 5TATUTORY CONSIDERATIONS the NRC to deterdme or review qualiracanons.
Con.It prcmdes for armaailorm standards of qualiracation 4.1 NRC Anthority of auditors and lead auditors. Authortty for this guide is derived from the safety Approach J requusments of the Arc. sic Energy Act as imple-mested by the Commusce's regulanons; in particular, ho. It provsdes minimum acceptable standards for Criterion XVIII of Appendix 3 to 10 CFR Part 50 quah ion aBowing easy determination of quahfications requires, in part, that a conspreheneve system of t by outside agencies like the NRC. planned audits be performed by appropriately traaned ho. It provsdes usafornury in quahfication. ] Com. It can reduce the flexibility of an orgamasation to 4.2 Need for NEFA Ammmmment recossage excepnonal talent. ./ This action is not a major action as defined by paragraph ANSI /ASME Nes.2.23-1978 uses a cossbinance of SlJ(a)(10) of to CFR Part $1 and does not requare an Approaches 2 and 3.The NRC staff commeers this combustion environmentalimpact statemest. an acceptable approech and has been involved is the develop. meat of this standard. Endorsement of thisstandard,asbject
- 5. RELATIONSHIP TO ODIER EXISTING OR PROPOSED to the supplemental profunons, is the proper method for the RECULATIONS OR POLICIES NRC to recosasse the acceptability of the standard.
No conflicts or overlaps with regarements promulgated
- 3. PROCEDURAL AFPROACH by other associos are forcessa. Implementation of this aetica is discussed la Section D of thas guide.
The foBowtag an alternative approaches for issuing this paidance.
- 6.
SUMMARY
AND CONCLUSIONS
- 1. Regulation.
Regulatory Guide 1.146. " Qualification of Quaiity Assur.
- 2. Regulatory Guide, ance Program Audit Personnel for Nuclear Power Plants /* has been prepared. This guide, with certaan exceptions, endorses These alternatives are discussed below; AN51/ASME N45.2.231978.
1.146-3 , ~. _,_,..-__.__.y-
3 3 ) Revision 1* September 1980 p mee'%'* U.S. NUCLEAR REGULATORY COMMISSION m o, M, OFFICE OF STANDARDS DEVELOPME GUIDE y%,. REGULATORY GUlOE 1.54 (Task R$ 9015) QUALIFICATION OF NUCLEAR POWER PLANT INSPECTION, EXAMINATION, AND TESTING PERSONNEL A. INTRODUCTION try the ANSI Board of Standards Review on August 31 1778. The standard contams requirements indicated by the Appendix B. " Quality Assurance Criteria for Nuclear wrb "shall" and a set of recommendations is.dicates by the Po'wer Plants and Fuel Reprocesang Plants," to 10 CFR verb "should." The recommendauons as well as the require-Part 50.
- Domestic Litenans of Production and Utilizanon ments of the standard were evaluated =sth respect to Facilit es." requires that the quality assurancs program importanca to safety. Applicabdity of the set of remsnanda.
provide for indoctrmation and training of personnel perform-tions an Section 3.5 of the standard is addressed in Regula-ing actmtiss affecung quality as necessary to ensure that tory Position 6. quality assurance penonnel achaeve and maintain suitable profic:ency. This guide describes a method acceptable to The American Society for Nondestrucuve Testing the NRCr staff for complying with the Commission's regula-(ASNT) has developed Recommended Practica No. SNT-tions with regard to qualification ofinspection, examination. TC lA 1975,3 which establishes guidelines for the qualifi-and testing personnel for all types of suclear power pla;sts. cation and certification of nondestructive testms personnel The applicability of ANSI Standard N45.2.6-1978, ASNT The Advisory Committee on Reactor Safeguards has Recornmended Practice No. SNT-TC l A 1975, and the ) been consulted w=ng this guide and has concurred in ASME BoGet and Pressure Vessel Code to personnel perform-the regulatory postion. Ing noodestruct2ve examinations is clarified in this guide. ASNT Recommended Pracuce No. SNT.TC l A 1975 has S. DISCUS $10N been revsewed by the NRCstaff and is conndered acceptable for the quahfintion of nondestrucuve testms penonnel for Working Group N45-2.4 of the ASME Committee on the nondestructive test methods covered by that document Nuclear Quality Assurance has prepared a standard that subject to certam exceptions. For those nondestructive delineates the qualificanons of personnel who perform examinanons required by Secuan !!! and Secnon XI of the inspections exammations, and tests during fabrication, ASME Boder and Pressure Yessel Code,it is indicated that receipt at the constructson site, construction,preoperational ASNT Recommended Practice No. SNT TC.1 A.1975 should 8 and startup testing, and the operation phase of nuclear be used in conjunction with the addinonal provisions of the power plants. This standard was approved by the ASME Code. Committee on Nuclear Quality Assurance and the ASME Nuclear Power Codes and Standards Committee and was Where conformance to th.s regulatory guide is indicated 8 subsequently approved and designated ANSI N45.2.6-1978 in an oppilcation without further qualification, ttus means that the requirements of ANSI N45.2.61978, as supple-mented or modified by the regulatory positions of this guide, will be followed. e The seDatantial number of chaseos in this revision has made it isepractscal to ind&cate the caanees wita liase is the margsa. / ANSI N4s.2.4197: does not apply to NRC41 censed operstors g and sesuor operators for the performance of suties spectfled 6a 40 I CFR Part ss."Opersters' taceasse." l IANSI M4s.2.6197s. "Qualifkatsons of taspection. Esamsme-Copies of SNT.TC.l A.197s, " Recommended Practice for tion. ase Testias Perseasei for Nuclear Power Maats." may be Nondestructive Testine Personnet Quaisncarsoa sne Certincation." ottaaned froen the American Society of Mechanscal Eagaaeers. 34s may be ottaaned from the American Societr for Noneestrusttve East 47ta Street New York, New Y k g 00 3 7. Testing 3200 Riverssde Drive.Columnus. Ohse 4 322 8. ~ ~ f3 USNRC eECut.ATORh dutOES Comraents enouse,usatory es seat to tne Secretary of tne commesseea. U.s. Poucseat me c ommesseen, wasneaston. O.c. 20ss 5 segusatory Gueces see issued to descreae see maee ave 46aese to tne Attent6eas Doceesent ene Servoce eranca. eusses metnoes acceptaaee to tne eenc statt of ernesementing soecif6 earts of tne casamesseea's roguaatsoas. to eeelaease teen. Tne guados are issuee la tne fosse = sag ten erose saveseensi aseues useo ov ene state la evaevateag soecafia proosome or sestu-lates accioents or to eroveee gueeence to aseeecants. neguestery ) power neacters 1
- 4. preovets Guedes are not suestitutes for reguaations, aae comostance with mesauca ane Test meestors F. vraassortation inom es not reeveree uetnees aae soeutions oefferent from taose ut
- 3. Puees aae Materians Facneties
- 8. occteanoaae eaesets out sa tne gueses aus ce acceetanee of tney orovede a casas for tne
- 4. eeversamentae one setene
- 9. Aatitruss one Phaeacias now.ew flassage reoussete to tne issuaace er constavance of a swmet er
- s. Matereess aae maat protection to. General 16 cease av tne Cemenessnea.
Coe6es of issueo evades raay se ovetnasee at tne cuersat Government coenments ane suggeseleas for.ees o.vements in tneee gueses are preattag office erece. A suescreetten servece for future guages sa see. imsr encourages at sit temes, aae eu ee no eevosee, as aceroersato. cafie sevessoas se avsesseee tereuva tne oevernment o eating cense. i to accommoease comraeats aae to restect aew enformasten or Informateen on ene suoscristeen servoce sae curreat Gro ereces may i esperience. Tnes guese was revesse as a resust of sue se oetaeaee av writing tne U.S. Poussear segusatory Cemen.sa.ca, j monts receevee from tae ovesic ano eeetteenes staff eev.staattve com-ew. W asneagion. O.C. 20:55. Atteatleat Puesacaseeas sases usaager,
T 3 3 7 C REGULATORY POSITION personnel deseribed in ANSI Standard N45.2.61978. ANSI N45.2.61978, subject to the saceptions of the regulatory The requirennents for qualification of nuclear gewer positions, should he used in conjunction with Section III plant inspestion, examination, and testing personnel that and Section XIof the ASME Boiler sad Pressure VesselCode are included in ANSI N45.2.61978 are acceptable to the for tne qualification of Inspection, namination, and testing NRC staff and provide an adequate basis for complying personnel where the A5ME Code does not address the with the pertinent quality assurance requirements of tequirements covered by ANSI N45.2.6-1978. Appendix B to 10 CFR Part 50, subject to the following:
- 4. Section 1.5, " Referenced Documents," of ANSI
- 1. Section 1.2, "ApplicabGity," of ANSI N45.2.61978 N45.2.61978 states: "Other documents that are required states that the standard applies "to personnel who perform to be included as a part of this Standard are eitheradentified inspections, examinations, and tests during preoperational at the point of reference or described in Secucn 6 of this and startup tesang, and during operational phases of nuclear Standard." The specific applicability or acceptabdity of power plants." However, for qualification of personnel (1) listed standards has been or will be covered separately who approve preoperational, startup, and operational in other regulatory guides, whe e appropnate.
test W in e. and test resulta and (2) who direct or S Section 3.4, "I.sve! III Personnel Capabdities," of napervtas the conduct of individual preoperational, startup. and operational tests, the guidelines contained ia Regulatory ANSI N45.2.61978 specifies the capabdity requzrements of Guide 1.3, "Personne! Selection and Training," should be LevelIII personnel. In addition, the individual should followed in lieu of the guidelines of ANSI N45.2.6-1978. be capable of reviewing and approvinginspection,exarnina-tion, and testing procedures and of evaluating the adequacy
- 2. Section 1.2, "ApplicabGity," of ANSI N45.2.61978 of such procedures to accomplish the inspection, examina-states:"The requtwnents of this Standard are not intended tion, and test objecoves.
to apply to personnal *bo only perform inspection, exaauna-tion, or testing in accordance with ASNT ' Recommended $$ection 3.5," Education and Expertence-Recommen. Pracuse No. SNT TC l A', mace these personnel are cerufled dations," of ANSI N45.2.6-1978 states that the education in accordance with the requirements of SNT TC I A and its and experience specified are recommendations and that applicable napplements." SNTTC-IA-1975 is acceptable other factors may provide reasonable assurance that a for the quah&= tion of personnel performing nondestructive person can competently perform a particular task. The set
=="am and should be used where applicable, subject of recommendations has been reviewed by the NRC staff to the following: and fouad to be acceptable with one exception. In addition to the recommendations listed under Section 3.5 for
- a. INT TC I A 1975 applies to quahfication of 1.svell, II, and 111 personnel, the candidate should be nondestructive tesans personnel for the following non-a high school graduate or have earned the General Education destrucave test methods.
Development owivalent of a high school diploma. Since only one set of recommradations is provided for the (1) Radaographic Testing education and experience of personnel, a commitment to (2) Magnetic Particle Testing comply with the regulatory posinons of this guide in lieu of (3) Ultrasonic Testing providing an alternative to the recommendations of the (4) Liquid Penetrant Testing standard means that the specified education and experience (5) Eddy Current Testing recommendations of the standard will be followed. (6) Neutron Radiographic Testing "M5ection 4 " Performance," of ANSI N45.2.61978 (7) Leak Tesung states:"When asingleinspection or test requires implementa-
- b. For qualification of personnel performing non-tion by a team or group, personnel not meeting the require-destructive examinations required by Section !!! and ments of this Standard may be used in data-takmg assign-Section XI of the ASME Boiler and Pressure Vessel Code, ments or in plant or equipment operation provided they are SNT-TC IA 1975 should be used in conjunction with the supervised or overseen by a qualified individual parncipat-additional provisons of the Code.
ing in the inspecnon,examinauon,or test." These personnel should have sufficient tratning to ensure an acceptable level
- 3. Secuan 1.2, "Appiscability." of ANSI N45.2.61978 of competence in the performance of their activities.
states: "The ASME Botter and Pressure Vessel Code, as well '8,r An important concept that is not addressed direct!y as other ANS15tandards,have been considered in the develop-ment of the Standard, and this Standard is intended to be in ANSI N45.2.6-1978, ANST Recommended Practice i companbie with their requirements." While Section III and No. SNT-TC 1 A-1975, or the ASME Boder and Preuure Seenon XI of the ASME Boder and Pressure Vessel Code Ves el Code is that occupational radiation exposure should address requarements for the qualifications of certain ' be maintained as low as is reasonably achievable ( ALARA). personnel who perform inspection, examination, and in all cases where inspection, examination, and testing testing, these secnons do not address the qualification of all personnel may be exposed to radiation fields during their activities in restncted areas, these personnel should re:cive instruction in radiation protection and radiation dose-
- N senes "taspecuoa." "narninsuon." and "tesdas."l e78.
are eenned in seenon i.e. "DeGamons," or ANSI M4 s.2.6 reduction considerations related to work they are expected 1.54-2 e -,,.m y w_ ..,,.-on- --ypw---. y s. w-, v n-a yo
{ 3 m i i to perform. Regulatery Guide 8.3, "Information Relevant written test) demonstrating that the individualindeed does i N Ensunns that Occupational Radiation Exposures at have comparable' or Nquivalent* competence to that which luclear Power Stations Will Be As Low Aa is Reasonably would be gained from having the required education and Achievable," describes techmques, features, and recom-experience. mendations to maintain occupational exposures ALARA. D. IMPLEMENTATION
- 9. Section 1.2, " Applicability," of ANSI N45.2.6-1978 i
states: "The requirements of 3is Standard do not apply The purpose of this section is to provide information to l t3 pomaal who perform inspections for government applicants and licensees regarding the NRC staff's plans for or municipal authorities, or who perform as authorized unns this regulatory guide. inspectors in accordance with the ASME Boiler and Pressure Vesal Code." The tequirements and recommen-This regulatory guide wi!! be used in evaluation of I dations of ANSI N45.2.61978, sabject to the provisions applications for construction permits and operating licenses l of Regulatory Poetions I through 8, are conadered docketed after September 30,1980. l acceptabis for use by c for aR NRC permit holders and i hcensess, uebent those that are government or municipal In addition, the NRC intends to apply Regulatory Pon-t authorttass. tions C.5,6,7,8, and to of this regulatory guide to operating plants and plants undrr construction. The remaining regula-i - h Sectica 2.2." Deter===Ha= of Initial Capability " tory positions cover areas of concern that were addressed [ ad Section 2.3, " Evaluation of Performance," of ANSI by the August 1973 version of Regulatory Guide 1.58 and l N45.2.6-1978 deal with the use of evaluation ofjob perform-are already beiris implemented by operating plants and ance and deternmade of initial capabahty to perform the plants under construction. Implementation schedules for l job. Use of the measures outlined in theos sections to estab. Regulatory Positions C.5,6,7,8, and 10 ws!! be determined 1:sh that as individual has the requared qualdications in lieu on a case-by case baas by the Office of Nuclear Reactor i of required education and esperaense should result in docu-Regulation. It is expected that these positions wd! be f mented objectzve evidence (Ls., procedures and record of required to be implemented by February 27,1981. l F l t i t ? i l I i f i r 1.58-3 l f 6 ,-,,.-n-,----
D ) ] ] .s
- s VALUE/ IMPACT STATEMENT
- 1. ACTION concern the addition or modification of regulatory posi.
tions ' included in this revison to the regulatory guide.) 1.1 Deenripdes
- a. Ties revised standard expands the applicability of its The Com'aiads regulations require that an applicant requirements and recommendations from personnel who establish a quality assurance program that provides for the perform inspections, examinations, and tests during the Ddoctrination and tranaams of personnel performing activ-construction phase to personnel who perform these activities ities affecting quality as necessary to ensure that quality during fabrication, receipt at the construction site.construc-assurance personnel achaeve and maintain suitable profa-tion, preoperational and startup testing, and the operation ciency. This action, issmance of Revisoa I to Regulatory phase. Therefore, Regulatory Position 1 in the August 1973 Guide 1.58, will provide updated guidance concernang the verson of Regulatory Guide 1.58, which expresses this qualificados of personnel who perform inspections, exaauna-applicability,is unnecessary and has been deleted from this tions, and tests dunas fabricados, receipt at the construc-revison. There is no change in the current ponnon of Regula.
tion site, construcdos, preoperanomal and startup tesang, tory Guide 1.58 and present regulatory bases will not be and the operation phes of nuclear power plaats. altered. I 1.2 Need for Acties
- b. la the August 1973 version of Regulatory Guide 1.58,
~ Regulatory Postion 3 provides additional guidance concern-Regulatory Guide 1.58," Qualification of Nuclear Power las the laformation to be laciudad in the certificate of . Plant ' ; - % 8-- ' "-- and Testing Personnel," qualiftatia= under the category of "beeis used for certifica-j dated August 1973, provides smidance on the qualifications tion." The revised standard incorporates this additional J of 8 &-da= awaawametaa, and testing personnel and rideaea that was lacking in the previous verson of the endorses ANSI Standard N45.2.61973. Os ' August 31, standard. Therefore, thie regulatory poedon is unnecessary 1978, a revised verson of the mandard was approved by the and has been deleted from this revision to the regulatory ANSI Board of Standards Review and was deugsased ANSI smide. There is no change la staff position and present N45.2.61978. The revemos to the standard reflects increased regnastory bases will not be altered. experience in the quainfication of anciser power plant inspection, emanaatiaa and tesdas P==aaama Some confu-
- c. The revised national standard states that it is appli-sion has arisen over the applicabihty of Regulatory Guide 1.58 cable to perseasel who perform preoperational and startup and ANSI Standard N45.2.6 to certain categories of key per-tesdag. Regulatory Guide 1.3, " Personnel Selection and sonnel favolved in preoperational and startup test programs.
Trannans," is being revised to encompass requirements for j The g==^a= in Revueon I to Regulatory Guide 1.58 reflects personnel who perform proeperational startup and opera-exponence in the applicados of quahfication critona that tional testing and will provide more deflaitive criteria for removes any confumoa with regard to acceptance criteria these,-- ' Modifications to the requirements for the i and that establishes an NRC position on the approved q==aine=Maa of these peraaanal wiR be addressed la the i nadonal standard. vekse/isspect aamaa==ent for the revison to Regulatory Gelde 1.3. Regulatory Posidos I of this revision to Regula-1.3 Value/!apact of Action tory Guide 1.58 references Regulatory Guide 1.8 for the qinatificataos of these perna==al Guidance on the qualification of nuclear power plant inspection, examination. and testlas personnet was contained The value of this action is the clanfication of the in Regulatory Guide 1.58 (August 1973) and was being applicability of Regulatory Guide 1.58 and Regulatory l used by the NRC staff in the evaluation of applications for Guide 1.8 to personnel who perform preoperational startup operanas licenses. Since the purpose of this action is to and operational testing. This action will benefit the NRC provide updated smdaam to reflect exponence with use of staff by providias addinonal guidance forlicense evaluations. current guidance, to remove any confumon with regard to The additional guadance is a clanrication of regulatory acceptance criteria, and to establish as NRC position on the requiremsats and win ressovo any confuaon concermns 1 approved national standard, this value/ impact is based on quahfication requirements of these personnel. Since there changes to guidance contained in Regulatory Guide 1.58 win be no change in the regulatory bases for license evalua. I (August 1973) and subsequently published (July 1979) for dons, the impact wiB be negligible I s comment in proposed Revision I to Regulatory Guide 1.58 (Task RS 901-5).
- d. The August 1973 version of Regulatory Guide 1.58 endorses ASNT Recommended Practice No.SNT.TC.! A as The following is a list of changes to be made to Reguia-acceptable for the qualification of nondestrucnve testing tory Guide 1.58 (August 1973) as a result of the revision of personnel for the test methods covered by that document.
the standard and the associated value/ impact assessment for Revision I to the regulatory guide endorses SNT.TC.1 A.1975 Cach change. (The first two changes result in the deletion of in Regulatory Position 2. For those nondestructive examina-two regulatory positions contained in the August 1973 tions required by Section ill and Section XI of the ASME version of Regulatory Guide 1.58. The last seven changes Boiler and Pressure Vessel Code, SNT.TC l A 1975 is 1.58 4 _ _ _ _ _ _ _ _ _ - _ _ ~. _ _ _ _ _ _. _. _ _ _ _ _, _
1 recommended for use in conjunction with the additional the supervimos of a qualified individual participating in the ) provisions of the Code. inspection, examination, or test. To prevent posuble abuse of this authorization, Regulatory Position 7 of this Thas action clarifies *he applicability of ASNT revison to the regulatory guide states that personnelinvolved - Recommended Practice No. SNT-TC-1A 1975 and the ASME la inspections, examinations, or tests who do not meet the Boiler and Pressure Veses! Code to personnel performing requirements of the standard should have sufficient trauung acadestructive examinations and does not represent a to ensure an acceptable level of competence in the perform-chasse in NRC staff or industry practice. There should be ance of their acuvaties. no impact. The value to industry will be the ability to use less
- s. Regulatory Positica 3 of this revisos to the regulatory extensvely trained personnel for those tasks that require guide addrummes the compatibility of ANSI Standard N45.2.6-little formal trautias, This action wC1 not represent a signifi-1978 and taeaaa III and Sectaos XI of the ASME Boiler cast change in present NRC staff practice. There should be and Pressure Vessel Code for the quahnention of personnel no impact as a result of this postion, who perform inspection,== ame=atina, and testing at nuclear power plants. It is stated that ANSI N45.2.61978, subject
- i. An important concept that is not addressed directly to the exceptions of the regulatory position, should be used la ANSI N45.2.6-1978, ASNT Recommended Practice No.
in @="dwith the ASWE Code where the ASME Code SNT TC l A 1975, or the ASME Boiler and Pressure Vessel does not address the requirements covered by ANSI N45.2.6-Code is that occupational radiation exposures should be 1978. The crismal verzica of the standard, ANSI N45.2.6-maintained as low as is reasonably achievable (ALARA). To 1973, widch was endorsed by the August 1973 version of provide guidance in this area, Regulatory Poetion 8 of this Regulatory Guide 1.38, did not cattain the Code exclusion revisoa to the regulatory guide states that inspection, statsmaat and was considered applicable to Codecovered exanunation and testing personnel who may be exposed to actrettaen. This new regulatory position does not represent a radiation fields during their activities should receive instruc-change from pr.amat staff practace. De impact should be tion in radiation protection and safety.
==- as The value of this action will be to provide increased L De revised standard, together with Regulatory awareness of the ALARA corcept. Present practice within .h Postions 5 and 6 of this revimos to the regulatory guide, the industry should not be affected. Therefore, the impact da8==a'== the capability requarements for Levels I, II, and on industry should be minunal Since the proposed action / III p---
- in greater detail and repressats a apinaat does not repressat a chanes in NRC staff postion, there change in qualificaticut requirements forLa-~3an,examana-wG1 he no impact on the NRC staff.
tion, and teattas per===al for Level! q"-"ht The action provides additional PMaa~ to the NRC staff and
- 2. TECHNICAL APPROACH industry and alters present regulatory bases for license evaluations. The impact should bo mmimal.
This section is not applicable to this value/ impact statement since this action is an update of previously issued
- 3. The education sad expensace recommendations
=h -~ presented in the standard for the quahfication of nuclear power plant i-W, eva=mation, and testing personnel
- 3. PROCEDURAL APPROACH have been revised to reDect current experience in the use of the standard. The revised standard also encompasses more Since this action is an update of information contained alternatzves for meeting the education and expenence in an existing regulatory guide, the only appropriate proce-prmistons of the standard, dural alternative is a revision to the exasting guide.
Regulatory Position 6 of this revision to the regulatory
- 4. STATUTORY CONSIDERATIONS guide states that a commitment to comply with the regula-tory guide wd1 mean that the education and experience 4.1 NRC Authority recommendations of the standard wd! be followed.
Authority for this guide is dertved from the safety The value to the NRC staff should be reduced effort requirements of the Atomic Energy Actt in particular, in determmms the acceptability of various alternative Appendix B to 10 CFR Part 50 requares that the quality proposals submitted by applicants. The revision of the assurance program provide for the indoctnnation and education and experience-recommendations reflects current training of personnel performing actrvitaes affecting quality expenence in the use of the standard and does not represent as necessary to ensure that the personnel achieve and a significant change in the regulatory basis for license maintain suitable proficiency. evaluations. Therefore, the impact should be minimal 4.2 Need for NEPA Assessment h.The revtsed standard - includes a statement that personnel not meeting the requirements of the standard This action is not a major action, as defined by para-I may be used in data-taking sampments or in plant or graph $1.5(a)(10) of 10 CFR Part 51 and does not require an { equipment operation provided these personnel are under environmental impact statement. 1.58-5
i S. RELATIONSHIP TO OTHER EXISTING ORPROPOSED schievable. This revised guide will be consistent with the REGULATIONS OR POLICES guidance furnished in these aforementioned regulatory guides. Regulatory Guide 1.5 contains recommendations for the selection and trauung of nuclear power plant person-
- 6.
SUMMARY
AND CONCLUSIONS no!. Regulatory Guides 8.8 and 3.10. "Operatins Philos. ophy for Maintaining Occupational Radiation Exposures As Revision 1 to Regulatory Guide 1.58,"Qualifleation of Low As Is Reasonably Achievable," both deal with the Nuclear Power Plant Inspection, Examination, and Testing ALARA concept and provide guidance that ensures that Perscanel," has been prepared. This reytnen endorses, occupational exposures will be as low as is reasonably with esttain exceptions, ANSI N45.2.6-1978. unives svaves avessas neoviavoav cowwsason suasset=GTo=, o, c. Jetes l l 1.58-6
9) 1 o o I E l PRCCEDURE PAGE NUMBER l REVISICN DATE TEXAS UTIUTIES GENERATING CO CPSES f 8 ;j CP-QP-2.3 4 1 JAN 2 0 1983 i l PREPARED BY. D N II4!63 DOCUhENTATION WITHIN ) DATii QA/QC PERSONNEL QUALIFICATION FILE APPROVED EY:t / 3
1.0 REFERENCES
1-A CP-QP-2.1, " Training of Inspection Personnel" 2.0 GENERAL l The purpose of this Instruction is to supplement the technict.1 training requirements of Reference 1-A by: a. Defining typical content of a CPSES QA/QC individual's personnel training file; ~ . Defining responsibility and procedure for maintenance b. of the QA/QC personnel file; CONTROLLED COPY 3o tssTRuC m x CONTROL N0.46N 3.1 INITIAL HIRE Individuals hired for CPSES QA/QC functions by TUGC0 or an integrated organization subcontractor shall be processed l appropriately by the personnel office of their imployer. i l The new employee will receive a QA/QC Resume Draft (Figure 1). j The QA or QC Secretary will assist, if necessary, by typing a finished resume for personnel file inclusion. A previously prepared resume is optional, at the discretion.of the ' QA Supervisor, for TUGC0 or contract employees. A completed resume will be maintained in the Permanent Plant Records Vault by the Training Coordinator. I D BI l I TUGOO CA s,,,i Na 2 _m. e-4
~ ~~~ de 9 PROCEDURE ISSUE REVISION PAGE NUMBER DATE TEXAS UTILITIES GENERATING CO. W ES CP-Q P-2.3 4 JAN 2 0 19h 2 of 8 3.2 PERSONNEL FILE FORMAT Each QA Quality Engineer, QC Technician or Inspector shall be interviewed and trained in accordance with Reference 1-A. Thus, for example, each QC Technician or Inspector will have in a personnel file at least the following: a. Record of QA/QC Indcctrination b. Record of Eye Exam, with color-discrimination waiver, if required, signed by TUGC0 Site QA Supervisor c. Record copy of Resume d. General Training Outline (Required in Reference 1-A, completed in 60 days following employment) e. CPSES QC (Specific Discipline) General Training Outline (An example - is Figure II of QI-QP-2.1.-3,which is required for Qualification of Electrical Inspection and Test Personnel.) f. Certification for each QC instruction / function / activity for which individual hasbeen certified knowledgea ble (Documentation of certification is per Reference 1-A and content of this certification is discussed below.) g. Certification as OJT Instructor in each QC instruction / function / activity for which the individual has-been quali fied. (Content of OJT Instructor Certification is discussed below.) 3.3 CONTENT.0F CERTIFICATION FILE 3.3.1 Examinations a. An examination for Level I personnel is required prior to certification per Reference 1-A. b. The minimum passing grade on an examination is 80%. c. Examinations shall be prepared by, and administered by, Quality Engineering staff using written questions which have been approved by an individual qualified as CPSES Level III. TUGCO CA y ,v 7
~' ~'7..... PROCEDURE ISSUE REVISION PAGE NUMBER DATE TEXAS UTILITIES GENERATING CO. CMES l CP-QP-2.3 4 JAN % 0 c:sa 3 of 8 l ) j d. Each examination shall be signed and dated by the individual being tested; cach page of multiple page examinations will be initialed or signed, and dated. e. Each examination shall be signed and da t.ed by the individual evaluating the examiration; an evaluation shall be made to a prepared answer key. i f. Any change of answer made on an examination shall be initialed / dated by the individual being tested, g. Each change of evaluation of an answer shall be initialled / dated by the examiner, who will also make brief explanation of any test response marked " acceptable" if it is not the correct response. on the prepared answer key. h. " Whiteout" or " Liquid Paper" shall not be used on an examination. 3.3.2 Formal Training Records A~ record of Fonnal Training shall contain at least~ the following: a. Individuals receiving the instruction shall sign an 2 Attendance Record. Use of a Social Security number as identification of an otherwise illegible signature is optional. b. Instructors shall sign.and date the Attendance Record, which shall include: 1) CPSES Title of Procedure / Instruction; i 2). Name of Procedure / Instruction / Activity; 3) Length of Time of Instruct'un; 3.3.3 OJT Training Records It is the responsibility of the QC Supervisor to ensure that all OJT Training following the date of this Instruction shall be instructed only by an individual for whom an TUGCO OA 3 .__n__. x -.._m___ y
- .,,,__.,,4
.u_.__~
- -.. T ~ -PROCEDURE .lSSUE REVISION PAGE NUMBER DATE TEXAS UTILITIES GENERATING CO. CPSES CP-QP-2.3 4 JAM 2 0 % 4 of 8 Instructor Certification Certificate signed by the QA Site Supervisor / Level III designee has been issued. Each OJT Training Record Sheet (Figure 2) shall bear both the identification number and the CPSES title of the procedure / instruction for which it is valid. The Training Record Sheet shall identify the date(s) of instruction, including month, day (s), year. The Training Record shall identify the 1".dividual being trained, and shall be signed and dated by the Instructor. The content of the Training and an appraisal of the individual 's responsiveness are encouraged, bu t are not obligatory. 3.4 ' CONTENT OF OJT INSTRUCTOR'S PERSONNEL FILE 3.4.1 Certification as OJT Instructor The personnel file "bu il t" for CPSES QA/QC Technicians / Inspectors to perfom inspection, test and evaluation functions for a ' specific QA/QC procedure / instruction / activity shall include an Instructor Certification Form (Figure 3), when the Level I has qualified as a CPSES QA/QC OJT Instructor. A QA/QC Level II Certifica' tion shall qualify the Level II Inspector.as an OJT Instructor. It is intended to certify that the individual's proficiency in the procedure / instructions / activity is sufficient to train other individuals in the specific activity. It is issued only upon review of the inspector / technician's pro-ficiency in a specific activity and must be signed / dated by the QA Site Supervisor / Level III designee. 3.5 00CLNENTATION Qualification and certification records of CPSES QA/QC in-spection, test, and examination personnel shall be monitored and maintained by the CPSES QA/QC. Training Coordinator in the Pemanent Plant Records Vault per Reference 1-A and this Instruction. Forms referenced herein and identified as " TYPICAL" may be substituted for by similar forms which serve the same purpose (s) aad which may pre-date this In-struction. Nothing herein is intended to obsolete pre-viously satisfactory records / files' content. TUGCO CA 3
= PROCEDURE REVISION ISSUE PAGE NUMBER DATE TEXAS UTILITIES GENERATING CO. CPSES CP-QP-2.3 4 ! JAis 2 0 i% g af g FIGURE 1 .~
- WQC REsuf DRAFT M PHONE EXT.'-
cart _ i IWE SSN . fissi Mi n i. LAsi BADGE f i DATE & PLACE OF BIRTH EDICATICM: IWE OF MI31 SOIDG., CITY & STATE PG1TH 4. TEAR GRAcuhiE3 !WE OF $LLEGE, CITY & STATE (Alse' Itst sidor or degree obtained, no. of sama tar hours, months & years attended) I $7?CTAL MIMMG (Lfs't names of sc.N1s or businesses where training oc:urred, ~ city and state, and length of courses, i.e., hours or months, sonth'and year of courses) e b) T v 'iUCLEAR CA/DC EXPEFENCI (List name of c:mpany, city, stata, job title and j n .C de'scription - begin with current Br:wn & Root eenloyet and wrt hach. arts . 3. & Yr. from there) (If cartified in any area list those and levels co-tified in.) i l I i TUGCO CA Forn No. 3 l l l [ r. I e r
9.*we g ~ ~ r PROCEDURE ISSUE REVISION PAGE NUMBER DATE TEXAS UTILITIES GENERATING CO. CPSES [ CP-QP-2,1 4 JAN 2 0 iSs3 6 of 8 L __. FIGURE 1 (Continued) i i * ~ ~ - - NUC1 EAR CA/QC EIPERIENCE (continued) I STES an. & Tr.
- 4 QTHER WCAK EPERIENCE (List sost recent work fikt. name of casg:any, etty and STE3 Mtit. & Tr.
state, job title. Joe description) 1-4 i i AI Af % ' tjJM 4,44 ' 4 .I PRO E!! C AL $0C!!TTE3: i MTLUARY SERVICE (List branch of service, morttn and year entered and discharsed.) 1 ? t e-TUGCO OA ,, g 3 ~ ~ - * ~ --- - ~ ~..... -.., -...... ' ' ~ ~ ' __e__ e ,0*
PROCEDURE ISSUE REVISION PAGE NUMBER DATE TEXAS UTILITIES GENERATING CO. SES
- h%0 m 7 of g CP-QP-2.3
-4 l FIGURE 2 , RECORD OF' WCRK PERFORNED PROCEDURE TITLE: INSTRUCTCA: WEEK OF TO S t ~ ~ 2 ~ l-t / 3
- I : ::. ! A i J / 4:.r?$.
,k
- -~3 ;3 a:i
,e,. ~ a 1 ~ MCN TUES 'WED 'THUR FR1 REMARKS. 2 . j.. j v.V V/ V >v v lA y V f.y .y. y ,7
- /
\\/ V /! V ~-v v_ y y y p "V V V. V: vl y 7y;y y; -V VIVIV1Vil -- VV V V VI V) l COMP'ENTS : gJ i* I INSTRUCTOR'S SIGNATURE TUGCO OA ,, g 3 99 ~_
6 d = e e -....... ~ PROCEDURE ISSUE REVISION PAGE g NUMBER DATE TEXAS UTILITIES GENERATING CO. CPSES JANz0 deJ CP-QP-2.3 4 9 8 of a FIGURE 3 >? TEXAS UTTLITIES GENERATING C34PANY @ALITY A15"RANCE CEPARTPENT IP:5TRUCTCR @ALIFICATICM !W4E: CATL LEVEL OF C DTIFICATION: ACTIVITY CERTIFIED TO PDFCm: TUGC3 PROCDURE/L%TRUCTION '90.: TYPE 7 EIMIMTICM GIYD: ORAL WRITTD PRACTICAL REIULT CF EIMIMATICM(s): + C3MNT5: Based upon a consideration of the education. previous mort ?, enperience, forms) training in the current revision the CPSE3 procedure / 3, instruction. and the individual's own on-the-je a previous certification has been made for this Q.C.
- i this activity.
I M A satisfactory evaluation of the ind' trated proficiency "i in the performance of daily mort ha made, and, with recognition v .q .;o that the CPSE3 QC inspector training, gram addresses specific QC inspect-ice functions, it is felt that there is reasonable assurance that the individual can cospetently perdare as an OJT CC Instructor in this activity. This cartification specifically ccvers g'ving OJT instruction in.nis procedivs. including the use of personal knowledge and coservation to participate in the Cn-The4ot Q.C. Trainee's instnaction. This OJT Training.Cartificaticn exstres in one year if no inspections are performed in this activity by the individual and regardless, on s Supervi ser Approval t ~ - TUGCO OA %g3 -, _ ~. 9 O g .n, .. ~.. .}}