ML20129H051

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Summary of 900621 Plant Review Board Meeting 90-84.Items Unanimously Recommended for Approval,Listed
ML20129H051
Person / Time
Site: Vogtle  
Issue date: 06/21/1990
From:
GEORGIA POWER CO.
To:
GEORGIA POWER CO.
Shared Package
ML20128F432 List: ... further results
References
FOIA-95-81 NUDOCS 9610070412
Download: ML20129H051 (25)
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.. f w. m.L. ' s~. y,.. s'M P.jff g. T,,VEGP' PLANT ~REVI'EW B6 AMP MS.ETINdMINUS25WW I'F 1 w f.. r - ;. -. u. ..e q 5 MEETING NO. 90-84 OATE 6/21/90 PAGE 1 OF 4 MEETING CUNVENED 1:00 W/PM-EE!NG At:c cJEO 3:20 Agj; g '( o VIA TELECON) THIS MEETING CHAIRED BY: <(X) CHAIRMAN () VICE CHMRMAN W. F. Kitchens VOTING MEMBERS PRESENT: J. E. Swartzwelder J. G. Aufdenkampe j 4 PRD SECREARY C. Cross Tynan NON-VOTING MEAbEi$ PRESENT: 1 -- n m. .u. m.u.. m.s iVOTING ALTERNATES PRESENT: -9 M. I. Hobbs FOR H. M. H.ndfinger I. A. Kochery DP R L. LeGrand - u. ~ ~.._,._ ]NON-VOTING ALT nhATES PRESENT: R. E. Folker FJK G. R F: e.ls: Ich FOR C. c~t ~ / FOR e,% g,3,/ ,/ArseuE y;.p, j .tr,n TK e' w ,ma - --.-. - ..us. u 'UESTS/TECHNICAI.OVISORS: R. A. Moye T. E. Webb H. L. Beacher F. J. Ealick A S. Parton W. C. Guthrie ..,.,-.2,...m.-s...,.~.m.--=- ?RB ACTION ITEMS OPENED: Norc )RB ACTION ITEMS CLOSED: Ncnc >RE MINUTES APPROVEL 5 0 - 2 :.. _-L. i. 9610070412 960827 - - + - - + = ~ - - - - - * * = -- " - - - ~- PDR FOIA WILMOTH95-81 PDR PRB SECRETAP.Y bib Q.C RMAN .n. .~.s~ ~ = = -~

(l R ' ~. Vfj b] f $ f ? q & ~ Q 2 Q q.; M( .5; Gun. *n,.b- < g, - ,d. s pg,g , g..,, p,, - cm g r.; m.p ig,,, g,aggg_o ,,f{,, J . y*;t tr % % g. w. k y. t J ~ . u, y.: -f ~ :.k. q, _., .- u ~ :, u.. .,Y p.o ; <. -s,y I - - e% s PRB HTiETING MINTITY8 CONTINITATION SKIRT i a - ' :. 3 'l t.;-;' ?/ed ac A. Meeting Minutci t'-E: r' 8 presented. B. The following items were unaramoasly recommended for approval. No unreviewed oc.fety juat. tion ir,volved. 19010-C, Rev. 6 "E-1 L.,ss of Reactor or Seconde,ry Coolant" 19223-C, Rev. 4 "FR-C.3 Response to Saturated Core Cooling" TCP 18019-C-7-90-4 " Loss of Residual Heat Removel" 00700-C, Rev. 9 " General Emp2.oyee Training" s LER 1-90-013 " Improper /.pplication of Grace Peric i to Containment Air Lock Surveillance" LDCR FS 90-026 Modify FSAR 3.11 - Revise current VEGP position on ~ Environmental Qualification (EQ) of safety-related eqaipment located in mild envircnmente. LDCR FS 90-027 P.ev:.se FSAR 8.3.1, 9.5 and '

Wies 9.2.1-2 and 9.S.5.-2 to allow bypausing of High Jacket Water Diesel Trip ICT3-00420 Unit 1 Cycle 5 Startup Rt. port LDCR TS 89-022 Revios Tech. Spac. 3.5.3.2 and essociated bases to allow 31P's to be operable in Modes 5 & 6 for reduced inventory
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Letter to NRC - Detailec Cci.irt1 Prher. imsigh Review - LLV-c159v ' a v.'. ww 'R".R) findings Responses t. NE ~ F ee. 2 ': u :, I :< w.... r 93641-C, Rev. 1 ' D+M. I '..pw nt and '.y'e.'en.etici of ths Fuel

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00404-C, Rev. 14 "S.t r.no ' ' 1 s nee Test Program". Section 4.5.3 (page 21) Reword to follow last statenent in 4.5.4 ) LER 1-90-12 dinajequate Testing Leads to Ir. adequate.ly Parf ormed Surveillance". Add in the Abstract / Corrective Actions - ...are being prepared to test the sequencer and determine response times". i 92030-C, Rev. 4 " Fire Drill Frogram". Step 4. 3.1-Feword similar to the following: "...should be asedled by the FPE and chould include sufficient 9 canpower from Fire Brigade Training Staff, operations Department staff and FPE (The

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st is to ng.t specify the exact nas e: of individuals).

19251-C, Rev. 4 "FK-3.1 Responsa to High Conte.insee.t Pressure". The Safety Evaluation should be/ceal.1 be improved (wording). 13216-1, Rev. 15r/ ":,1 32Ld b.tste Release". 13216-2, Rev. 6

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asistsney in referring to U.iste Monitor Tank 009/09/99/9 in the proeddure and tagging in the field.

LER 1-90-6, Rev. 1 Rewrite " Loss of offsite Power Leads te Site Area Emergency". Ox:ructive Action f4 - Change "61" valid starts to "69".

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s..,,e.p + v .,e uSafety and Environment [al Evaluations". Step 4.6.3. Reword such that Section B in

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Step 4.6 - Review for including Energency Plan increase / decrease in etfectiveness as Security Plan is included. Step 2.6 - Review and delete as preparer / reviewer definition should override. Unless avaluator is needed for Environmental Evaluation or 1 preparar should be~ stated instead. Note: The training on 00056-C is to be decided by K. R. Holmes. Procedure will not be signed / approved until that determination is made. ? D. The board unanimoutly evacur: e. .th *he follo.iing items. Event Report 2-90-00* " Reactor Trip Due to Loop 3 MSIV Closure a i Unit 1 - 1R2 Integrated Leak Fate Test Final Report E. The board unanimously concurreo. it h the repmability determination for the following Defi s ency Cards. ) 1-90-263 1-90-2"/1 l 1-90-266 1-90-272 1-90-268 1-90-273 i 1-90-270 F. The board tabled DC i-90-269, "Pt. trol checks that was initiated j on 6-1-90 for system problen.s (see f,R #'s 4066-90 and 4089-90) was not done correctly". The DC will be reviewed at a later meeting when a related LER is uade available f*)r review. G. The board tabled procedure 00410-C, Eev. 5, " Control of Computer Software", with the follov'.ng ementn. - Minimize quality requizeh nti fo:- i.en e.gc 2 A software - Change final apprcval frce. Assiccant. Gcucra; Manager to Department Manager for Categ,.ry E.scft u:.e che.nges. H. The board discussed the prcrowd ;encion to procedure 00400-C, " Plant Detign Centrel-1.e,oggest. ion was made to add a check sheet te list itsas r..q.; red for Return to Service and this sheet shet.id be e ;e' : W 'F p:-ange.

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0470 i Docket No. 50-424 . S. Nuclear Re u14 tory Comrrission A TN: Document ontrol Desk W}athington,D.C. 20555 j Gen emen: V0GTLE ELECTRIC CCHERAllNG PLANT \\ \\ LICENSEE EVENT REPORT \\ LOSS OF OFFSITE POWER LEADS TO SITE AR*tA EMERGENCf \\ In accordan'e with 10 cfR 50.73 Georgia Power Company (GPC) hereby submits the ed report related to an event which occurred on March 20, 1990. enclosed rey necessary to clarify the information related to the number of This revision enerator starts as discussed in the GPC letter dated April 9, successful diese 1990 and the LER d d April 19. 1990 and to update the status of corrective 'ha evitarta rar tne comoietton or the test prograins__ actions in the LER. ") i daritood in be the first successful test in accordance XLthWogtie r.lectric 81==t May pr0CV5iire lesso-T piesel Generator Ooerabjl11x13 ,3 _ neratia,' l (TIien there were 16 cLiccessful stTPt1 of witgel f.eiIerator IA and il successfu 1 'Gtarts of Olesel Generator 15 Detween Ine compionen or inTYTsT / s t 19, 1990, %!sdofApril 'he number of successful starts included in the original LER included some of the starii dhat were part of the test pro.qtAn Tine oiscrepancy is attributed to } ~ diesel start recora Keeping pracuces and the definition of the end of the test. Qrocram. In order ta.carrec.t. the LER and to provide more useful and up to date information the LER has been revised to state the number of' valid diesel' generator tests in accordance with Regulatory Guide 1.108 rather than of successful starts since the event. by reviewing diesel generator testing data from Maren 21 through June 7, 1990. Sincerely, 4 W. G. Hairston, 111

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L R,50-424/1990,006;01, x ~$U-it? 3.'; .f,. l. E 34

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ktakuur 424/90 04 2, .. + 8Als'J1E TO EkSUWE PRUWEk kJU!% AkD it"lDi N ik.F/ttB 7-07 90 Adal!!NL UT VIDLAf!0N kESP. 5 *4-90 424/l0 10-0L 70 THE RCS TEleP0kARY LEVEL ;4liCAfluh QESPC6i s ' LUSS OF DiFSITE PunE2 LEA 05 it. S TF Arts w I 1 h/ in mLsi .C cck? t[k REVISION (LERl-30-00601) t#EWO5sCf 5 's 10 LER kEVIS'UN m;LL!A'J!a01AS6 SHff! L;w: % nGW r: e 't 'em %s; " ut (lek 2-10'001 01) ictrt<!0A:. Set 0lrits? ic w..; ains

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y Arry e i interoffice Correspondence Georgia Power m DATE: August 23, 1990 RE: Voatle Electric Generatino Plant g,, N NRC Areas of Concern /.C ~> 9 J.,?p *g... Log: SRBS-00044 Security Code: NC

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.. i FROM: M. J. Aj1 uni TO: Distribution Attached for your information is a copy of the recent NRC Operational Safety Inspection areas of concern and VEGP's position. M. J. Aj1 uni MJA/ghj W. B. Shipman cc: G.Bockhold,Jr./ S. C. Ewald L. K. Mathews C. C. Miller W. C. Ramsey P. D. Rushton NORMS SRB File Y ACTIoy C0Py g. V i d!., IN NApr hie;SQ; g ks v~ ' b;ti ~ ~~! ISEt;f,..l. - ~ l%&. gg ? . w :. : : : - g \\a ~' ch.y .~ ) yy ]i, /

._g 1 AUGUST 17. 1990 I AREAS OF ramrrman unC VEGP CONTACT CORPORATE CM TACT l

  • D/G Records Starts / Failures s

Pete Taylor G. Frederick

  • 3/1/90 5 R Monitor Inop Mode Change Neal Nunemuller JES/D. Carter i
  • Missed Sury. Cont. Isol.

Neal Huneauller JES/S. Swanson l l

  • March 15 RHR Train B Ron Aiello JES/J. Gasser P. D. Rushton Temp. Change Notice to AOP Robert Carrol JES/J. Cash 18028-C-7-90-1 ESFA Sequencer Out of Service Robert Carrol JES/Horton J. A. Bailey i
  • Alternate Radwaste Building Ron Aiello Ron LeGrand/JES P. D. Rushton
  • Snubber Reduction /

Larry Garner Gus Williams Ward /Stringfellow f LCO Action Statement Coni. Integrity Hydrogen Monitor Morris Branch Dean Gustafson Ward /Stringfellow a i Valve Opened i

  • Precision Heat Salance Morris Branch Gus Williams
8. Florian

( Personnel Accountability C. VanDenburgh JES/G8 Methodology for Reporting J. D. Wilcox J. E. Swartzwelder J. Stringfellow Tech. Spec. 3.0.3 Philosophy J. D. Wilcox R. M. Odon J. A. Baffey l ESFAS Reportability l 0 Plant Review Board (PRS) Composition C. VanDenburgh G. Bockhold 0 Morris Branch J. E. Swartzwelder J. Stringfellow Tech. Specs. Interpretation l J. E. Swartzwelder Overtime / Training & Qualification Larry Garner P. D. Rushton M. Norton Larry Garner Electrical Separation Zone 80 i l J. E. Swartzweider c J. D. Wilcox i I. S. 3.4.7.3 CCW i o et

  • Training Department Comments or OSTI Shif t Experience Plant Equipment Operator Morale
  • Shift Communications Anniyzer Operation Following SI Chilling Affect / Intimidation of PRS Members Quality Concern Program
  • Manictina Statements While Containment Cooler is Inoperable DGIB is Rendered Inoperable t

Exit of Diesel Generator LCO i I 2 i [ s "o b .m

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DIESEi.STARTSANDFAILUREREPORTING 8/22/90 / Time: 13:00 { Page 1 of 2 l j NRC Concern i 1. The NRC is concerned about the incorrect number of diesel starts reported i in LER 1-90-06 and the number of starts presented to the NRC on April 9, 1990 and in the confirmation response letter of April 9,1990. The major 1ssue remaining is to try and determine through personal interviews, how the number of 19 for diesel 18 was arrived at in the April 9 letter to the NRC. The NRC believes the intent of the April 9 letter and the ~ presentation discussed consecutive successful starts. The revised response to LER 90-06 did not clarify the number of starts reported to the NRC April 9, and did not clarify that the 19 Starts were not consecutive. 2. The inspector noted that documentation provided by Operations to support i j diesel trending (14980-C and 13145-C data sheets) does not.contain an adequate description of what happens during tM :+ art attempt. The plant j is not interpreting Reg Guide 1.108 propedy A th regard to reporting valid and non-valid failures. There may be valid and non-valid failures that were not reported. The NRC does not coat 1@/ the current status of i reporting diesel failures to be in compliance with commitments made to the NRC in Violation 50-424/87-57. NRC Documentation The NRC has reviewed the diesel start log and supporting documentation ) i (14980-C and 13145-C data sheets). The NRC currently believes some problems identified on 14980's and 13145's should be classified as non-valid failures and reported to the NRC. The NRC has requested and received written analysis i to explain the disposition of the following 18 diesel starts:

  1. 's 123, 124, 132, 133, 134, 136, 160, 161, 162, 164, 165, and 190.

LER 1-90-06, revision 1; QA Audit Report OP26-90/33; QA Audit Report OP09-90/31; and Special R7 ort 1-90-05, dated August 7, 1990; GPC confirmatory action letter dated April 9, 1990. VEGP Position 0 1.' The error made in the number of diesel starts reported to the NRC on April ( ~9, 1990, and in LER 1-90-06 is attributed to two factors:__ a. The testing as described in LER 90-06, revision 0, was in the " context of" and "in reference to" the diesel control svstems. The first two sentences of the 5th paragraph explain actions taken with regard to sensor calibrations and control system testing. In this context, the test nroaram correlates to testing discussed with the NRC on April 9,1990, and reported in the April 9,1990, confirmatory letter. The LER 90-06 comment of " subsequent to the test program" was not intended to exclude successful diesel starts before declaring the diesel operable. As a result, diesel starts after testing of the control

systems, but before a

declaration of operability were counted. The transmittal letter for LER 90-06, revision 1, describes the confusion and attempts to clarify the concern by redefining the types of starts and the point of counting.

DIESEL STARTS AND FAILURE REPORTING Page 2 of 2 i b. LER 90-06, revision 1, was intended to clarify any inadvertent " misleading" of the NRC on successful operation of the diesel control systems.. When Vogtle Management was aware of the problem in LER @ Me-06,_re_v_ision 0, management notified the NRC Residents. 90 Al soat corporate office ~on 6/11/90. W.' Shipman contacted Ken Brockman and on about 6/11/90 H. G. Hairston, III, contacted Mr. S. Ebneter of NRC Region II. The revised LER was submitted on 6/29/90. The 19 starts discussed on April 9 were based on operator assessments of the starts as successful using VEGP proceduresJ Additional revifw of these starts by both the NRC and Vogtle pedonnel indicates start-s #134, performed on March 23, 1990, could be counted as unsuccessful. e If start ( #134)is not counted, only 14 successful starts occurred C s before April 9, 1990.. This s~t&t will be reviewed in detail and an appropriate report"to clarify the number of starts reported April 9, 1990 will be made. 2. After a thorough review of Reg Guide 1.108 Engineering Support (Mike Hocton) agreed that all diesel start nrobleem have not been reported as fai?ures. GPC's response to NRC Violation 424/87-57 committed to report such equipment problems as failures;

however, due to internal administrative problems, the commitaent was not implemented.

Engineering Support intends to review diesel start records for any unreported failures. VEGP Documentation o LER 1-90-06, revision 1; QA Audit Report OP26-90/33; 04 Audit Report OP09-90/31; and Special Report 1-9045, dated August 7, 1990; GPC confirmatory action letter dated April 9,1990. 18 diesel start analysis available 8/15/90 and Reg Guide 1.108 position o from Engineering Support. a J.CNch % y+ m..Y 5 Vcf;, hogemsakway mde am.> c( Sbe Sd.brea c'n.:AaAs *)34 o.,ftbz r % te,..;:~h-:h g W L.e8. Trey +ere in4 r~/ d' A f6/w a en abx A I9-'7c. p,JI( n >cde a-are c f 4he in o<ntab idermahc> % LER-% l % 1le %y m J wo n 9 t e v. c ch 4 -30 "/C hy meme 4e k y n + ral ma., ayr.. Obh / v t d4 =i G (C sk. e Y8e ///[L

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ii 8/22/90 Response to NRC Question Concerning Time: 13:00 j Diesel Starts Reported on April 9,1990 and in LER 90-06, Revisions 0 and 1 i Ouantion #1 i 1. Who prepared the slide for the 4/9/90 presentation? i Answer: G. Sockhold, Jr., J. P. Cash, cnd K. Burr working as a group 2. Who approved use of the slide? M M *** b );[ [- fhsl Md *@ heco Ne$ Off S$ES k f #,, p,. Answer: G. Sockhold, Jr. ) i Wh r, -h A,.ewledy 16' N USPc*'[ b#j. n Question #2 C. K. McCoy, J. A. Bailey, N. G. Hairston, III g g ,,,g., I 1. Who prepared the confirmatory letter of April 9, 19907 > 23 40 pg Answer: g l 2. Who approved the letter? Answer: N. G. Hairston, III Question #3 (with regard to LER 90-06, revision 0, dated 4/19/90) 1. Who prepared the LER7 l Answer: Several draft revisions of the LER were prepared by Tom Nebb and j others of the NSAC group of the Vogtle Site Technical Support. These drafts were reviewed and commented on by the Plant Review l vhen h sedem was Board. The final revision of LER 90-06, revision 0 was prepared ! gwd i, e.crh.p b - a phonecon between site management and cereerata== =t-l 9 g,f,.u-7e wiM se7articipat111g are ot1Tivea to se G. Bockhold, Jr..y i ,,,A M.y tid a t Mosbaugh, J. G. Aufdenkampe N. Shjpman.,. f'.,g & g,(,$s 1. i *,! [7 Qt.

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'O ,r arr fnrencWo}y,lf wed :< wMe redd**; ea=4 M #a ,g e, i Who reviewed the LER7 Answer: All revisions D EF JI 7 Ee We,we e PR and the l General Manager-Plant Vogtle. At;restap.an tv.i5fe=S o re M *"S i rede.wd ly %e Pfl8 R j wr,KCF,eseeled*'***"h' 34 the Anal vers.= ) 3. Who approved the LER7 j Answer: The LER was approved by M. G. Hairsten, III Aix e Ae.,e co wo nd f i l Ouestion #4 W ;e b*f**' 53P ' bY i k rio4e m ew & n no. 1. Who prepared the cover letter for LER 90-06, revision It i Answer: The cover letter was prepared by H. W. Majors of the corporate i staff. This letter was prepared under the guidance of H. G. Hairston. 2., What was the purpose (intent) in the wording of the cover letter with regard to the number of diesel starts? Answer: The cover letter was intended to document discussions with NRC Region II to clarify the starte documented in LER 90-06, intan

0. 3 8y picking a well defined point to specify

" subsequent to the test procram" it was possible to identify a y@ ubstantial number of successful diesel starts. This was ntendedtoremoveanyadditionalambiguity.J n. v v. r.n....- .- 9_.. u 4 . ? *- ce 1. Who in corporate added the words " subsequent to the test program" in LER 90-06, revision.07 x it "y .1 m.,., .l, - Answeri.} Corporate. Licensing "; personnel in conjunction with the phone,g.. - n.c ,djMV* /@Mz.,d,[]A.dfrect g conversa on described above made editorial . changes as. ~ ' onver'sitid C ire

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