ML20138F454

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Advises That Commission Agreed Not to Review Director'S Decision DD-84-21.Review Time Allowed Expired on 841025. Commission Also Agreed W/Forwarding Ofc of General Counsel Ltr to Jacksonians United for Livable Energy Policies
ML20138F454
Person / Time
Site: Grand Gulf  Entergy icon.png
Issue date: 10/26/1984
From: Chilk S
NRC OFFICE OF THE SECRETARY (SECY)
To: Plaine H
NRC OFFICE OF THE GENERAL COUNSEL (OGC)
Shared Package
ML20138F391 List:
References
FOIA-85-187 DD-84-21, NUDOCS 8512160095
Download: ML20138F454 (1)


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UNITED STATES

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E 'o NUCLEAR REGULATORY 'COMMISSIC,,4 1 W ASHIN GTON. D.C. 20555 y

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October 26, 1984 / >

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OFFICE OF THE s SECRETARY ~/ f MEMORANDUM FOR: Herr.el H. E. Plaine, Ge pSpl Counsel I FROM: Samuel J. Chilk, Secre i/)  !

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SUBJECT:

SECY-84-396 - REVIEW OF IRECTOR'S DECISION UNDER 10 CFR 2.206, DD l 8 (4-21 This is to advise you that the Commission, by negative consent, has agreed not to. review DD-84-21. Accordingly, the review time was allowed to expire on October 25, 1984.

The Commission, by negative consent, also agreed with the .

proposed OGC letter to JULEP that provides the excised OIA ,

report. Accordingly, you should proceed with forwarding the letter to JULEP. ,

(OGC) (SECY SUSPENSE: 11/2/84)

J cc: Chairman Palladino ,

Commissio<er Roberts Commissioner Asselstine f Commissioner Bernthal  !

Commissioner Zech '

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$EMOM.'EUM EOR: Chairman Palladino ,

Cor.raissioner Roberts Comaissioner Asselstine .

Co:caissioner Bernthal -

Corr.nissioner Zech 6-

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Office of Inspector und Audit d . --

SUBJECT:

GRAND GULF NUCLEAR STATION - 10 CFR 2.206 PETITION

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Attached is the Office of Inspector and Auditor (OIA) Raport of Investigation concerning allegations relating to the Grand Gulf Nuclear Station, Unit 1 (GGNS) .thich were raised by Jacksonians' United for Livable Energy Policies (JULEP) in a 10'CFR 2.205 Petition (the Petition) submitted by them to the

-U.S. I!uclear Regulatory Co:::aission (NRC).

, Through review of the Petition and OIA interviews of JULEP representatives, CIA concluded that three issues raised by JULEP warranted an investigation ,

b.3cause of their potential impact on the integrity of !QC's operations. Those issues were (1) that an NP,C inspector allegedly advised a representative of JULE? that JULEP representatives were excluded from a portion of a raeeting between 4RC and Mississippi Power and Light (MP&L), because draft inspection reports v:ere being discussed; (2) NRC inspectors advised a representative of JULE?, in private, that NRC knew MP&L had not always baca truthful with the IRC and had lied in a press release about an NRC directed inspection; and (3)

NRC steff either did not read or ignored the technical si.acifications submitted. by UPal for GGN5, Unit 1. Furthermore, the NEC staff permitted low pcuar testing based en those technical specifications,.which did not. match the plant design, and after acknowladging that the technical specifications submitted by MP&L were wrong continued to allow GGNS,.-Unit 1, to operate.

'!ith respect to issue (1), investigation determined that the NPC Project Manager for CGNS. Unit 1, attended a June 5,1984, meeting at GGHS between.NRC .

2nd MF&L representatives regarding the Transaracrica :Delaval, Inc. (TDI)

. Generatoys. The m.;eting was divided into two segnants, a working session between NRC cad MPLL and a public portion. Because -the 4:orking session involved discussions of MPal reports containing proprietary information, the public, including intervenors, was excluded. A JULEP.rcpresentative, who entered the tr.2eting rcc:a while the working session was ongoing, was escorted CG;iY!IT:  ;'.a rk P : sr,e r , OI A ,F/'"M *1 p

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fro'n tne roca ny M. Dean Houston, tne NR Project lianager for GGNS, Unit 1, At tna; time, Housten explainet to Ken Lawrence, the JULEP rapresentative,

nat In cualic portion of the meeting .had not yet started and that the draft reports beinc reviceed were.;he general types of utility reports that were handled as propriate.ry information. DIA ceveloped no evidence to indicate

' draft NRC information was discussed between NRC tad MPSL.

Regarcing issue (2) thzt NRC knew MP&L had not alucys been truthful with NRC,

., DIA investigation disclosed that JULEP representative Ken Ltwrence had questioned Houston about a May 22, 1934 MP&L press. release wherein MPEL -

apparently stated the "tcar desn" of the TDI Diesel Generators at GGNS, Unit 1, was voluntary on their part. Houston alivised Lawrence that NRC did not concider MPEL's action to be voluntary because the " tear dcwn" had been required by an NRC or Sr issued on May 22, 1934. Houston did not charactecize to Lawrence that MP&L's alleged statement in their press relcase vas a lie.

. With respect to issue (3) concerning the NRC staffs' handling of the technical specifications for GCNS, OIA learned that the Comissica had previously been inforced of this issue.during a Comission briefing and frcm responses to inquiries on that subject made by former Comissioner Gilinsky. DIA reviewed related available information to determine if the Coranissicn had been cc.T.pletely infenncd. While conducting this review, it was disclosed durino an interview of the NRC Senior Resident Inspector (SRI) for GGNS

Attachment:

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As stated r-cc: W. Dircks, EDO w/ attach .

H. Plaine, 0GC w/ attach G. Cunningham, ELD w/ attach .

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TITLE: GaAND GULF NUCLEAR STAi!0N - 10 CFR 2.206 Pfi1 TION i .

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PREPAF.ED BY: f yk. i Res DB.TE d2"- 'l- f' Investigator /

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CpiceofInsp Auditor 7 ca.e0A. V' gtor rw a donald it. Smitb Investigator Office of Inspector and Auditor APPROVED BY:f'dlis fr- Bowers. -

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OFF!CE OF INSPECTOR & AUDITOR ' ^/f' '

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t Backcrounc By mzmorandum dated April '_7,1934, frcm J;nes Lieberiaan, Directer and Chief Counsel, Regicnal Operations and Enforcem:mt Division, Office of the Ext.cutive Legsl Director (ELD), U.S. NuclMr Regulatory Comaission (NRC), to George H.

Messenger, Acting Director, Office of inspector.and Auditor (01A); a 2.205 Petition submitted to NRC by the Jacksonians United for Livable Energy -

Policies (JULEP) was.. forwarded to 01A. OIfi's revicu of the Petition

. identified thrt.e issues bearing on the integrity of the operations'of the liRC.

they fire (1) "possii;le improprieties and illegal acts by MRC inspectors and investigators"; (2) "the handlin previcusly identified";* and (3)g"the by effectiveness OIA of the improprieties

of. NRC Region which II in have been fulfilling the mandated respcasibility to enforce the regulations of the tiRC -

, which exist to ensure protection of -the public health and safety."

. Subsequent to 0IA review of the 2.206 Petition, CIA . conducted interviews of .

- JULEP representatives on June 28, 1984, to ~ determine .t'ie specifics, if any, to the allegations. Froa the infonntion learned during those interviews, OIA -

concluded that'investication of the following allegations was warranted:

1. An NRC inspector allegedly advised a representative of JULEP on or about

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June 12 and 13, 1984, that JULEP representatives were excluded from a portion 'of a meeting between NRC rnd the utility (ITississippi Power and ,

Light, MP&L) because draft inspection reports were Leing discussed by NRC with MP&L. .

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2. NRC inspectors adviscd a representative of JULEP, in private, that !{RC knew MP&L had not always been truthful with the NRC. More specifically, that MP&L lied in a press release about an NRC directed inspection.
3. NRC staff either did not read or ignorcd the technical specificatiens for Grar@ Gulf Nuclear Station (GGNS), Unit 1, sub:nitted by MP&L.

. Furthermre, NRC staff permitted low pcwer testing br. sed on those

. technical specifict.tions, uhich did not match the plcut design, and after acknowledging that the technical specifications were.urong, NRC continued to allow GGNS, Unit 1, to operate. .- .

Investigation of these allegations was initiated by OIA ca July 18, 1984.

7Investigctor's inte: During interview by OIA of JULEPTrepresentHEive

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Cynthia Stewart, the NRC organization and functions were explained to her and ,

, she said that she probably was in error when she referred to 01A in the second I cc:, plaint enumerated in the 10 CFR 2.206 Poition. Also, she could provide no l furthar information c. bout in.pmprietics by N.lC employees.

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8u =arv Alioced. discussion of draf t insoection renorts -be_t_een NRC and MP&L.

Sen L2Wence, JULEP, stid that on or about June 12 and 13,1934, there was an on-signt inspection concerning Transa:a_rica Delaval, Inc. (TDI) generaters at GGNS involving NRC, l'Phl, and MP&L contractors. During z. related meetin.; in that tina frame, Dean Houston, NRC, atte:apted to assist the utility by having

. a portion of the meeting in a sccure area to which JULEP representatives would not be granted access. .

d JULEP reoresc 'tatives were excluded from a*public portion of the facility (GGNS) bhcausu, according to Houston, draf t inspection reports ware beirig discussed by NRC with.ttra utility (Attachment 1).

M.. Dean P Pston, Project Menacer, Licensing Branch #4, Division of Licensina,

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. Ofrice o; :ucl' car Paector Regulation (N!iR), said that he recalled advising Lawrence on June 5,1984, during a working. session meetir.g between NRC and M?LL that the public portion of the meeting had not yet started and that the draft reports being revicwed were the general types of utili.ty reports that are handled as prcprietary data and not. intended for the public. He explained that the public portion of that meeting had been scheduled for 1:00 p.m.,

however, the working session between NRC and the utility had not been completed by that tiae. Consequently, Lawrence walked into the meeting rcom at 1:00 p.m. and was irmediately escorted from the room Sy him (Houston) who advised him of the type of reports being discussed. Houston said that he did not discuss or in any manner cc:r.nunicate any NRC draft information to MP&L and' he is not aware of any NRC employee who did.

Houston noted that he was at NRC Headquarters on June 12 and 13,1934, and was at GGNS on June 4 and 5, 1984 (Attachment 2).

Alan G. L'agner, Senior Resident Inspector, GGNS, NRC, said that he did not hear Houston make a statement that draft reports were being discussed stith M?&L. He,.did recall that Houston escorted Lawrence from the meeting roca during the working session between MP&L and NRC (Attachmant 3).

NRC inscectors' advised a renresentative of JULEP, in private, that the NRC knew MP&L had not always been truthTul with the HRC and that MPEL lied iTa press release about an HRC directed inspection. - . . . . . . - . . .

Lawrence said that Houston ad:aitted to him privately. that the NRC knew the litTiity had not always been truthful with' the HRC arid"the public.

Also, an NRC Resident Inspector present during the on-site inspection of the TDI cenerator at GGHS made cctmnts about knowing the utility had lied to the ERC in the past.

Specifically, Houston told of a lie concerning a press release about an NRC directed inspection. MP&L indicated in the press release that they were conducting an inspection on their own ( Attachment 1).

Hcusten recalled that on June 5,1534, he discussed the utility's actions regarding the "tcar down" inspcction of the diesel sencrator at GGNS with

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Lawrence. Lawrence had curstioned .him abot t the utility's cress release on apuroximately May 22, 1934, relatin(i to the "tedr cown" of tne diesel generator. Apuarently, in that press release MPEL said that the " tear cown" was vaiuntaiy on thsir part. He responded to Lawrence inat NRC did not consid2r the utility's action to b'e voluntary bacause the " tear down" had been cecuired by an i!RC order i*ssued on May 22, 1984. He did not characterize to Laurance M?nL's statcent in their press releasd as a lie or as being untruthfui (litrachment 2). ,

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Alan G. Wacner, said that subsequent to the. public portion of a meeting on .

June 5,19W, between NRC and MP&L concern $ng the TDI generators at GGNS, ht,

. Ken Lawrence and Dean Houston briefly spoke uutside the meeting room.

Lawrence was upset -ibout the fact that MP&L had apparently said in their press release that the tear down of the TOI generators was voluntary, when in fcct, it had been ordered by NRC. He (Wagner) told Lawrence that he did not have control over what MP&L released to the press. He did not characterize MP&L's

. press release as a lie but simply stated that NRC had issued the order for the tear down of the TOI generators (Attachment 3).

' ~ IGC staff either did not read or ignored the technical specifications for ~

GGNS, Unit 1, submitted by MP&L. Furthermore, !!RC staff pemitted low powsF-'

Testing based on those technical specifications, which did not match the olInt -

desion, and af ter acknowledoino that the technical specifications submittea 6y ~

TiPM. were wrono, liRC continued to allow GG3, Unit 1, to operate.

Cynthia Stewart, JULEP, said that at some point prior to low power licensing .

Tc7 GTIS, IKsent MP&L 'an example of technical specifications for the Mark II containment for their use. MP&L resubmitted the Mark II technical specifications which.did not match the plant being built (GGNS). The URC staff either did not read or ignored the specifications because they permitted low power testing of GGNS, Unit 1, and when they finally acknowledged that

- MP&L hed the wrong specifications, NRC continued to let the plant operate (Attachment 4).

Ucuston Js. aid that the entire matter concerning the issues surrounding the technical specifications for the Mark II containment hc'd been addressed in a Cor.issicn briefing believcd to have been on March 20, IS84. Also, a January 13, 1984, mamorandum from William J. Dircks, Executive Director for Operatiens, to Ccnissioner Gilinsky, addresses the .NRC staff's handling of ~ '

theGGNStechnical' specifications (Attachment 2).

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Lwestigilt3P s Note:

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Donald S. Brinkmn, Section Leader, Standard Technical Specifications Section, Str.noaronation and Special Projects Branch, Division cf Licensing, NRR, said th:t he hutho' red a February 2,1984, memoitadum from Dircks Enclor.ure to Cecnissioner 1.to that

  • Cilinsky -(Exhibit 1 to Attachment 2) with enclosures.

n:e:aarandum explains the NRC procedures used in the prepa.rutica of technical -

specifications for new operating licenses.

He believes that the procedures used by the HRC staff regarding the CGNS,-

Unit 1, technic'al specifications adh'ered to the precedures delineated in Enclosure 1.

Regarding any prcblems concerning the NRC staff's handling of the GGNS xechnical. specifications, he believes the Comr.issica has been mde fully aware of thtm. -

He said that, in his analysis, the allegatien that HRC allowed GGHS, Unit 1, to ccatinue to cperate even after acknowledging that there were proble:ns with the technical specifications is not factual, lie explained that subsequcnt to .

NRC becoming aware of the problems with the technical specifications, Region i

11 issued a confirmation of action letter dated October 20, 1907., to MP&L that .

,i recuited cold shutdown of the plant until the problems identified were >

corrected (Attachment 5).

-4 Attachmer.ts:

1. Report of Interview dated June 28, 1984 - Ken l.awrence

, 2. Repo,rt of Interview dated July 18, 1954 - 11. Dean Houstan ,

3. Report of Interview dated July 30, 1984 - Alan G. l'cgner i3 4. Report of Interview dated June 28, 1984 - Cynthia steuart I 5. Report of Interview dated July 24, 1984 - Donald L. Un-inkmn l.

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. . Dave of transcreatser Recort cf intervieg den Lawrence, P. O. Box 3568, Jachon, Mississipai 39207, upon interview, cencerning a possible allegati,on that NRC employees had co.uitted improprietics or illegal acts, provided the fell.owing infoor,ation: ,

Dean Houston,' Headquarters, U.S. Nuclear Pdgulatory Com;ission (Licensing -

Eranch 22, Division of Licensing, Huclecr Reactor Regulation (NRR)), on or about June 12 and 13, 1984, at the Grand Gulf Facility as part of an on-sight inspection of the Transamerica Delaval, Inc. (TDI), generators and during a ~

m2eting between HRC staff representatives. and the licensee and its contrac-tors, also attended by Ken Lawrence,' Jackson,14ississippi and Dale Wallace, .

. Vicksburg,141ssissippi (JULEP), trie'd to assist the utility in a portion of the rxeting having to do with the discussion of the generators by having the meeting in a secure area from which the JULEP representatives would be ex- -

cluded. The next day they also were excluded from the public portion of the facility because, according to Houston,1 draft inspection reports were being discussed by the HRC with the utility. Houston had defended utility actions in the public part of.the maeting by saying that they were being forthright in dealing with the NRC,. but 1cter admitted to 1.awrence p'rivately that the NRC

. knew the utility had not always been truthful with the HRC and the public.

(Lawrence bel.ievc:d that a complete attendance list for both days is in the hands of the NRC).

An HRC Resident Inspector wa's also present at the above described coeting and made the sa:ria kind cf cc: mnts about knowing that the utility had lied to the NRC in the past. Specifically, Houston told of a lie concerning a press release about an l'RC directed inspection. The utility indicated in the press release that they were doing the inspection en their own. The Resident Inspector also corrented that he was horrified at the difference between what he saw ch.the television about the plant and the actual plant as he .saw it.

Investigator's Note: 'According to Lawrence, Jacksonians United for Livable Energy Policies (JULEP).uses the same mail address as hi_s cited above.

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. . , s r,m .. u ,m. u , _ July 1E, 198c Rer'or: of ihrerview t'. Dean Hourton, Project Manacer, Licensing ~ Branch #4, Division of Licensing, C ~ fire of l'uclear Reactor Regulation, U.S. Nuclear Reguiatory Co:rmission, was inervisted concerning allegations levied by representatives of Jacksonians United far Livable Eneroy. Policies (JULEP)'that (1) draft inspection reports care discussed by the NRC with the utility,(Mississippi Power and Light .

Company) in a meeting between NRC and the'ptility on June 4 and 5, 1984; (2) that he made a coment to Ken Lawrce.ce, JULEP, in private subsecuent to the .

neding 'on June 5, *1984, that the NP.C kncw the utility. had not always been truthful. with the NRC and the public, and (3) purported irregularities rec:rd-ing the NRC staff's handling of the technical specifications for the Mark II cbntainment to be used by the utility. He provided the following inrormation: - .

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Recarding the alleged discussions of draft inspection reports between NRC and the utility, he recalled advising Lawrence on June 5,19?A, during a working session meeting between NRC and the utility that the public portion of the.

. m:eting had not started yet and that the draft rcoorts beino reviewed were the

.- c neral types of utility reports that are handled as proprietary data and not

.iatended for the public. (He explained that the public portien of that meeting had been scheduled for 1 p.m., however, the working session between

, URC and the utility had not been ccmpleted by that time. Consequently, Lawreace walked into the meeting room at 1 p.m. and was irniediately escorted .

frca the rocm by Houston who advised him of the nature of the reports - draft utility inspection reports - being discussed in the meeting.) He (Houston) did not discuss or in any manner com.unicate any NRC draft infomation to the licensee and is not aware of any NRC employees who did. .

He noted that during th'e closing session for the public meeting on June 5, 1984, Emmett Murphy, NRC spokesman for the Transamerica Delaval, Inc. (TDI),

NRC Review Group, indicated that the NRC would expect the final, utility inspectic.a. reports to be submitted to the NRC and these final reports uculd be made available to the public through the local public document room. ,

Regarding any coment to' Lawrence that the utility had noti always been truth-ful with the NRC and the public, he recalled that on June 5,1984, he discussed th'e utility's actions regarding the " tear down". inspection of the diesel generator at Grand Gulf uith Lawrence. Lawrencat hcd questioned him about the utility's press release on approxinately May 22, 1984, relating to the tecr down of a diesel generator. Apparently, in,.that press relepse, the ,

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l 3 OtC.f:f d.id,,tha , @a m - d kn'was talur. sry es egir par.. R resPonced to !

- L1xrence$:qt !?RC dit nei consider the 'utilit !s 'a;;icn to De 4diu'ntai-p

,because the' tear down had been recuired 'by af. URC order issued on May 22,

. 1934, 'He cid not characterize .to Lawrence the utility's statenant .in the ph.i:s release as a lie er' as beir,g untruthful

. He noted that pt;ior to the June 4 and 5,1984, me: tings, he telephoned Lawrence c.nd infot.nd him that there would be a . site. visit meeting at Grard Guif on those dates for the purpose of discussing the utility's inspection cf the TOI diesel. He indicated to Lc...rence tt that time that the public part of this maeting weuld be the " kick off" and "svimary" portions. Laurence was l  : also ndvised at that tima that the NRC conwltants woulde spend considerable i time inspecting the individual disasseabled parts that were within the secure area of the Grand Gulf facility and'public participation in that portion of l the inspcction was solely between the utility and the public. He further l . explained to Lawrence that NRC had no jurisdiction concerning public access to l the facility.

With respect to the issues surrounding the technical ~ specifications for the liark II containment, he noted this entire matter had been. addressed in a

! Comission bridfing (he believed the date to be March 20,1984). In that elyriefing, Frank Miraglia, NRR, presented testimony to the Comission in that regard. He also neted that a January 13 , 1984, memorandum from L'illiam J.

i Dircks, Executive Director for Operations (EDO), NRC, to Comissioner i Gilinsky, subject: Grand Gulf Technical Specifications addressed the issues .

surrounding the NRC staff's ' handling of the Grand Gulf Technical Specifications. He provided a copy of that acmorandum tnd other related correspondance on that subject (Exhibit 1).

Investigator's Note: Lawrence stated during his interview on June 28, 1984, t

c6nducted by Senior Inv'estigator Ronald M. Smith, that Houston was present at l the Grand Gulf facility on or about June 12 and 13,1984; however, Houston was l

at NRC Headquarters on those dates. He was at Grand Gulf on June 4 and l 5, 1934....

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  • o.w c e ie. sc ni.. -Y'2I' I900 Report of Interview klan G. Macner, Senior Resident Inspector, Grand Gulf Nuclear Station (GGNS),

U.S. Sucleir Regulatory Comai.5sion (HRC), was interviewed concerning an alleged conversation on June 5,1984, between Dean Pohstan, HRC and Ken Lawrence, a representative of Jacksonians United.for Livable Energy Policies.

(JULEP), whercin Houston allegedly stated 'that draft reports were bein discussed by NRC with the licensee (Mississippi Power cad Light, MP&L)g . He .

was also interviewe'd with respect to the issues regarding the technical specifications for the Mark II and Mark III containment. He provided the *-

following infonnation: ,

. Subsequent to the public portion of"a meeting on June 5,1984, between NPC and M?&L concerning the Transamerica Deldval 'Inc. (TDI) generators at GGNS, Unit 1, Ken Lawrence, Dean Houston, and himself briefly spoke in the hallway outside the meeting room. Lawrence was upset about the fact that MP&L had apparently said in their press release that the tear down of the TDI generators was voluntary,'when in fact, it had been ordered by NRC. He (Wagner) told him ~

'that he did not have control over what MP&L released to the press. He did not chcracterize MP&L's press release as a lie but simply stated that NRC had issued the order for the tear down of the EI generators.

Concerning an alleged statedent by Houston that draft reports were being discussed with MP&L, he did not hear Houston make such a statement. He recalled that Houston did escort Lawrence frcm the meeting rocm during the -

werking session between MP&L and NRC.

ilegarding the issue of the technical specifications concerning the Mark II and ,

Mark III containment Wagner was provided with all available related documents and asked to review then. He was asked if he believed from his review of the docum nts.,that all the significant issues involving the technical specifications at GGNS had been properly addressed. He provided the fbilowing

' additional information'.

. . . w e , e ,, July 20, 1984 . ,,

Bethesda, MO ,.,,,

84-28 7-

" irk E. 'Nodd ,inves tigd.or, CI A '

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Ja r.dar'y n , 19E4 MEM0?)fGUM FDP.: Comissioner Gilinskv .

FROM: 'n'ili.iam J. Dircks I

  • Executive Director for 'Operajions .

G?AliD. GULF TECHNICAL SPECIFICATIONS

SUBJECT:

. ~:. .. .. .

s Yeer mamarandum dated December 13, 1983 incuired about the Technical

, Specificaticns which were issued for Grand Gulf with the low power license pn June 16, 1932.

  • The G2neral Electric Standard Technicalospecifications (GE-STS) for Mark II conta.inment plants were used to develop the Technical Specifications for Grand Gulf which has a Mark III containment. At the' time preparation of the Grand

' Gulf Technical Specifications was initiated '(early 1980), we knew that Grand

  • Gulf had a Mark itII containment; however, we had not yet prepar ed GE-STS for ..

< . Mr.r.k 1II containmant plants. Preparation of GE-STS for I: ark III containment

. - plants 2 curred concurrently with the preparation' of the Grand Gulf Technical -

i specifications. ine Grand Gulf applicant was provided 1.-ith a copy of the GE-STS for Mark II containment plants and was instructed to identify'those Tcchnical Specifications which were not applicabic or which recuired modifications due to design differences. We took this approach since there.

.. are only a few differences betwcen the Technical Specificz.tions .in the GE-STS for Mark II. . containment plants and these for Mark III containment plants The-~ F  !

Ass ~of t'ri GSTS' foicMirk II E56tainhunt~rilants to develop the Grand Gui1<T.~ ~ -

4Technicr.1..SpecNidatio'n's, did poi (~ result..in iny .s i'gaificint~ contFibdtisii m to diijy .

7.%e m :%f.5f=thEnces - + - - - - +ecuired.ftbicorh_cti

,-: the Gr.indi. Gulf.IichiMch17SpTcific.atio.ns ;25zy..l

-~ .

The pecian II inspections performad shortly after the issuance of the Grand Gulf license indicnted that the plant procedures were not completely adequate .

to implement 'therequiremarits of the Technical Specifications. The findings .

,o i

o f thase inspections promoted Grand Gulf to do a m2ticulous review of their ,

Technical Specifications 'and surveillance proceoures... This review revealed

. . - deficiencies in the Technical Specificatioris'an'd surveillance procedures. -

I The Grand Giilf applicant

  • proposed Technical Specification chances and .;

! revised existin'g surveillance procedur.es andyrp,te nevi._survei)lar.c to corre..c.t .t.has,e,..d2f..iciencjes..,g*fhe

. .:.n-- . .- .

.ptc-op2r.ational tests and ~.

powertest3(J .

did not' reyear.:non171calit...lecun3 cal . Spec 17.1ca tion d.i.screpanciesp. - .inis is not

'unu;ual in that tiie 7 Elves used for acceptance tests prior to licen?.ing arc Sued on ihe best available parameter . values cohtained in vendor manuals, desi;;i specificatienq and calculations i.r.d the pjaased,Technicxl

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.Sheifications. - .

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' y; to=bssioner Gilinsky .

2

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t Since the low power l'icense was issued, the Go.nd Cuif licensee h'as recuested 205 changes to the Technical Specifi' cations. - Approximately M of the recuested cnungts ware admin 3strative and approxitutely C Ucre associated -

with se.m function of the as-built plant. Of the .e regt'ested chances, '120 i have be.7n granted, 32 have been , denied and 43 aru unace, review. It is important to note that none of the proposed changes involved a finding, proposed or final, that a significar.t hazards consideration exists. ,

. . .p , . u. ,

s ' discussed above, a,nudber of factors"contribut'ed - to the problems ' .

-~ .

~~

encountered with the Grand Gulf Technical Specifications. However, we -

believe in retrospect that *the single :aost impartint factor was' tha failure -

on the part of the Grand Gulf applicant to ensyre that the proposed Technical .

Specifications were properly reviewed.. . Although we understand that copies of

' . the proposed Technical Specifications were provided to General Electric and *'

Bechtel for their review, the Grand Gulf applicant assigned primry .

responsibility for review of the proposed Techaical-Specifications to a .

consultant. This consultant had no experience in the operation of comerical Bh'P.s and only 1imited experience in the, operation of other power reactors.

The proposed Technical Specifications wave not reviewed by the Grand Gulf plant operations staff to ensure that they reflected the actual plant design.

Ue believe this was an isolated instance. Usually, utilities' plant operations staffs are intirately involved in the development of their plants' '

Technical Specifications. b'e have become sensitiand to the importance of this aspect of the utili. ties' review of their propesed Technical .

Specifications and if in the future we detect a similar situation develop;rk, we will take appropriate measure's to prevent its recurrence. *

. , ,SimMlillind

( Ditch , .: . .

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  • - ~~

William J. Dircks .

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,: Executive Director for Operations '

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' cc: Chairman *Pd11adino ' t ,

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d,. ./% k Robc?ts -

Co:missioner*Asselstine..

Co;missioner .

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Cca. mis'sioner

  • Bernthal ,. ,

.SECY .:.

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DIkTRIBUTIOll:

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!EIC uriOUF. FOR- Cor .issir.aer Gilinsky; .

. .FROM: b'illiar. J. Dircks .

Execu ;ive Dirett'or for Operations SU3 JECT: P?.E?ARAT10 i 0F TECHNICAL SPECIFICATIONS .

.' -,-...:.. ... .. .. . ~

~

As a folicwup to my Janucry 13,1.!84 raer.orandu;r. to.you en the Grand Gulf

~I::chnical Specifications and in response to 'ycur verbal request to Edson Case for additional infortnation regarding the procedufes used for preparation of.

-the developent of the Grand Gulf 'fechnical('Specificatiers, the NRC stafftechnical s

. hr.s prepired .the enclosed infori.iation. Enclosure 'l describes the procedures the !!RC stcff has baen using for. preparing technical specifications-for tieu operatin'g licer.ses. Enclosure 2 des'cribes how these procedures were applied to Grand Gulf and includes a discussion of the reasons for the many changes -

required in the Grand Gulf Technical Specifications follcuing issuance of '

its low power operating license.

' ~

.WidlciD l'iilliam L Dirsks .- .

William .J. Dircks txecutive Direc,t.or Tor Operations

~ " Encl osures:- *

, 1. Procedures Used for Preparation or sechnical Spec 1rications

,for New. Operating Licenses .

i 2. ' Preparation of Grand Gulf Tcchnical '

Specificati.ons

  • cc: Chairinan Pallh.dino . .

.Cc.c. tissioner Rcherts - -

' Craisiihner Assel stin~e '

Co:r aissioner Bernthal '

SECY. -

OPE - -

GGC. .. a

.DISTRIDUTIDN: .

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Docket :-lie D. ,o, ri n,.c.a n - - -

URC PDR - F. !iircglia

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DCS . D. Eisenhut .s 55P3 Reading ~ " H. Denton/E. Care -

C. Thocas' l!. Dircks -

P. Ander. son. M..Bridoers -- -

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, EtCLOSURE 2

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'P':0CEDURES' USED FOR PREPARATI('il 0F TECliliiCAL

~$W0lTJTMGsDCA Ndi CEGimi L fGTST .

Technical s,5:cificat'itns fo? neioperating licenses are prepared by the NRC

~

with e nensive input by the applicant. The H2C staff han prepared a' set of ... -

Standarc Technical Specifications (STS) fo'r each of the fcur light water reactar vendors. These STS are the starting point for preparing technical specifications for each new plant. The STS(are revised periodically by ihe ..

NRC staff to reflect ravised or new regulatory . requirements and design changes. .

The following procedures for preparing plant-specific tech'nical $pecifications frca the STS have been in use since the NRC staff began using STS in 1974 and ' -

are dascribed in the Foreword (see attachment >'of each of' the four STS documents. -

Approximataly one year before the plant's scheduled fuel. load date, the applicEnt.

is provided a copy of the applicable STS and instructed to review the STS doce: rent, to fill in the applicable plant-specific information, to identify non-applicable specifications or requireinants, to identi'fy areas where technicaf specifications arf-required but not inc'luded in the STS and to' return the udked-up docutent to the NRC staff for review. The marked-up document is then reviewed by the NRC staff and ccmpared with chimitments made in the FSAR and with requirements established in the staff's SER. Draft technical specifications

. are then prepared and a copy of these draft technical spacifications is provided

. -to the applicant for review. Some plant-specific information will usually'still be lacking sinie it may not be available for various reasons, e.g., completion

. of. construction, analyses, or preoperational testing. Therefore, several NRC

, staff / applicant meetings are normally held to resolve the differences and to

,chtain the lacking information! ,.

Following the review of the draft technical specifications and approximetely three months prior to the scheduled fuel loading date, the NRC staff issues the proof arid Review Cooy of the technical specifications. The Proof and ~~

' Review copy is issued to the NRC staff review branches .and to the applicant for a final review prior to issuing the operating license. The plant-specific technical speci.tications are essentially' complete when the Proof and Review  :.

copy.is issued. The HRC staff and tpplicant are requested to identify ary '

required changes.

  • Tne typical' time alloted for this review is four weeks. Any

,coranents frca this ' review are then resolved and the final technical specifications are prept. red for issucnce with the operatihg. license.

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Durinc preparation and review cf piant-spacmc technica r specifications, - .

..n e m. . . . strr7- ceoenes signmctn:ry uoan :ne appiltsa: ro . perform. a 'thorcuch

- review of the information submitted in the marked-up STS document and tr at~

cca:;ined in the-dr' aft. technic 11 specifications and in the Proof and Review -

Copy to ensure that the informtion is reilective of actua.i piant desion, ~

configuration and nomenclature. Car experience shcws that for r viers per-fo med by the applicant, it is preferable to have this r.; view performed by menhurs of the applicant's plant operations staff since they are usually the most fc.miTicr with the plant's actual design and configurEtion. The inforr..ation provided. by the applicant. to be included in the plant-spe~cific-technical specifications is reviewco a, y ,cne h,RCta.s. . r_t ouring its review or th.e o.rart technical specifications and the Fraaf and Rgv-iew Copy but only da an audit basis and with 'little emphtsis on inputs that reflect plant-specific.nomenclqture, e.g., component or system

, titics. The staff'.s review and acceptance of the draft technical specifications are based mare upon ensuring that the ' safety criteria described in the applicants FSAR and in the staff's SER are maintained than upon ensuring that actual plant

. . nomenclature is accurately reflected irl the . technical specif.ications. Ensuring

. -that actual plant nom 2nclature is accurately reflected in the technical .

specificatidn is a. function left primarrily .to' the applicant.. - . ..

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,'.i ERCLOSURE.2 l~~'

PPe ARATJON OF;GRANDfGULF.TECHNICN S'?:CI?! CATIONS Copies of the Standard Technical Specific ~ations for General Elecd-it Soilinc

~

~

~

U3ter Reactors (GE-STS) for Mark-II cantainmant plants were provided to the ".

Grand Gulf applicant in P. arch 19D0. Althouah we knew that Grand Gulf had a . '

Eark III cor.tainment, we provided -them with the GE-STS for a Mark ~ II contain- s mant since wa had not-yet prepared a GE-STS'for Mark III containment plants and since thera are only a few differences' between the technical sp cifications in the GE-STS for Mark II contaimaant plant's~ and those for Mark III containment -

plants. furthermore, we instructed the: Grand. Gulf applicant to identify those technical specifications which were not cpplicable or unich recuired modifications -

~

dua .to desiga differences and to identify areas where technical specifications tere required but not provided in the GE-STS. /The applicant marked up the GE-STS and raturned it to .the NRC staff in June 1980. 'The applicant was not able to . "

' provide all the requested information,i i.e. , plant-specific parameters, values, nomenclature,. figures, graphs, etc. . at that time because some infomation was

. still being developed and analyzed. .The NRC. staff. reviewed the applicant's

. proposed mark-up and prepared a draft of the Grand Gulf Technical 5;)ecifications -

in August 1980. A. copy of this draft was pro'vided N the appFicaht for review.

Several NRC staff /applicr ' cactings were held over the course of the ne:rt" 16 tonths to resolve noted ferences between .the NRC staff and the applicant'.

- During this period, the applicant supplied the outstanding infornation required'

' to complete.the Technical Specifications. Proof and Review Copies of the Grand

' Gulf Unit 1 Technical Specificaticns were issued on~ January 5,1982. The comients frca this review were resolved and incorporated in the Technical Speci-fications during the March-April 1982 time frame. The Grand Gulf Technical -

Specificaticns were issued.as Appendix A to the Grand Gulf Un-it 1 License on June 16,.1982 .

~

As.noted in Enclosure 1, we b511 eve Tt is ' preferable to hava the plant's operation staff review the draf t technical specifications during their development.

Mowever, this- was r.ot the ctse with Grand Gulf. The technical specificatioris -

were prepared by the NRC staff and a consultant acting cs . tie contact for and on behalf.of Grand Gulf Although provided to the reactor vendor and the

. Architect Engineer for their review and connent,.the proposed technical specifications were not. reviewed by .the Grand Gulf plant operations staff, during the . initial development period up to and including the Prcof and Revitw. Rever-theless, when the license vas issued, the NRC staff, based on its work with the applicant's depgnated contact,. believed that the technical spacifications were reflective of factual plant nomenclature and .that. the technical specifications were consistent with. the . operational requirements  ;. ,.s of Grand Gulf. - -

,,. . . . s

.. . ~

The Grcnd Gulf licensie has requested 205 changes-to..the Technical Specifications

. .since the low power. license was issued on '0une 15, '1982. Of the 205 requested -

changes,120 have bcan : granted,43 are under review to be issued and' 32 have been. denied. ' For ccaparison, Pennsylvania. Power .and.'t.ight with its -first '

nuclear plant, Susquehanna Unit 1 (Mark ;11 centain:iunt), requested 24 chances ~

to cits technical spacifications in the sage post-licens.ina s- tim frad.

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Tin N.C stari nas ana'tyaec the'20, recuestec caa'nges and has determined that t.:e rec.u=r.ed chances generally fell in o four categories: (1) Editorial o' -

b6encia .ure Correct, ions-62 items (36%), .(2) Consistency wi~ thin Technical

.Snec.ificatio'as-25 iteras (15L'), (3) Confermance to the As-Built Piant-78 items (45%), and (4) Channes -to the Bases Section-G items (4%). Cateocries (1) and ~'

(2) were purely cdministrative ghanges. Category (4) involved clarific$ tion s:ctements for a.better understanding of the reasons for the Techiiical Specifications. . In accordance with 10 CFR 50.3S, Category (4) itcms are ~nof considered as part of the Technical Specifica.tions. Since Catecaries h

~(2) and (4) are administrative in nature, we find that 55%' of tim ~propo,$e)$ ~

changes are administrative .and 45% are. associated 4with some iunction of tha '

.as-built pb.nt. 'In accord 7.nce with our procedures for preparina technical '

i -

specif-ications, the requested changes .in Catepry (1), (2) and (4) weie of the

, type tnat we primarily depend upon the appli.c' ant to detect while some of the '-

items in Category (3) should have been detected by the NRC staff during our

review. - -

- A review of the Category (3) items shoded'that only nine of 'Ehe 78 ' items wIere -

concerned with non--existent equipment ch 'a mi'srept esented function associated with scoe equipment or. system. Mest of these nine items should have been detected and corrected during the staff reviens. One item (Explosive Valves in

, !P. System) clearly was a carry-over from the Mark I and II concepts. Three items (Fuel Grapple Interlock, Load Shedding and Sequencer Automatic Function,

. , and I;.aw Co:) denser Vacuum Bypas s ) were consistent with the Grand Gulf desion as -

. rcTl: ted in the Grand Gulf.FSAR. However, the Grand Gulf FSAR Das in error

, gita regard to the actual plant design. One (Lever Arm on Yacuum Ereaker) was Ine cirect, result or a . change. that was specifically requested by the licensee cud approved in L1 cense Amenoment No. 4. Later, the licensee determined that Whcse 1ever arms ,did not,'in fact, exist. As a result, another' technical spec 1T1 cation change rcquest had to be processed. One discrep'ancy was .related -

to equipment unique to the Mark III containment p~lants (Fuel Tu'ae T'ransfer System). There are two options available, horizontal and vertical.

Grand Gulf * -

, has a horizontal system but incorrectly selected some teciurLcal speci'fications appropriate for a vertical system. Two items involved details of the as-built '

plant that are generally not available in the FSAR for staff review (Voltaca "'

Instrumentation on MCC Panels and Control Room Filtration Bypass). One itYa piydrogen Pecombint,r Penetrations) was accurately described in the FSAR but incorrectly addressed in the technical specifications and should have.been detected by the NRC staff. ,

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fiDuncan HEMORANDUM FOR
-Jcne A. Axelrad, Director DHoust_on .

Enforcemant Staff LKintnar Office of Inspection L Enforcement DEisenhut/RPurple

~

FRC.i: Darrell G. Eisenhut, Director .

Division of Licensing 3

-Office of liuclecr Reactor Regulation e

r

. SU5 JECT: GRAND CULF - MATERIAL FALSE STATEMENT On March 13, 1984, P.apresentative E. Harkey wrote to'the Comission reques;.ing o responses to certain questions. One ~ question (Enclosure 1) asked the

omission's view as to the errors in Grand Gulf TS and surveillance procedures  ;

constituting miterial false statements. As a result of that request. vie have rddressed curselves to the question of a material false statement in the TS ,

and reached the following determination. .

On Decembcr 15, 1980, the licensee submitted a markup of the Standard Technical Specifications.for General Electric Boiling Hater Reactors (liUREG-0123) uhich he stated reflected plant specific design. factors.

~

Additional subr.ittals and chances ~

wtre transmitted in letters dated June 26, and December 31, 1981, January 12, .

February 25, March 23, April '5, 6, 7 and 30, May 26, June 1, 9 (2 letters) and 10, 1982. Copies of the treasmittal letters are included as Enclosure 2. * - '

On June 16, 1982, l'RC' issued a lcw power (57.) license to MP&L for Grand Gulf Unit I with appended TS. Tnose IS were subsequently found to include many

~

errors (see October 20,1982, C0A). Some of these errors wei e of cn adminis-trative nature.

Others, hoyever, wera instances where the YS did not corr:-ctly reflect the piant specific dcsign feature.s described in .tha FSAR and cctually built in the plcnt. For exampic, the Technical Specifications only reeuired 7 ads valves to be cperable while the FSAR cnalyses and the SER evaluation considered, and the cctual plant has, 8 valves.

'Because these TS were based on inforcation providca by the licensee, on v:hom te rely to provide correct. reflection of plant specific design features, and because the tiRC would not have issued the licenr.e with incorrect TS had we knoc:n of the errors at the tima, it 6ppears that this situation constitutes

Contact:

L. Kintn2r, NRR

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. . ganeTJ.Axelrnd C grounds for a finding that.a material falsd statcment iras cade by the lic.ensee.

Therefore ,2:e reco:.:aind tht: this issue be pursued for possible enforcement cction, ,

U !r.Lnalni ncdy y

, t%"nll G. Eise,43 Darrell G. Eisenhut, Director Division oT L'icensing Office of fluclear Reactor Regulation

Enclosures:

1. Question 10(a)

.  ?. . Ccpics of transmittal letters .

cc: J. Liebercan "

T. l'ovak H. Denton F. Miraglia .

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3 in thrte ,p? > .es. , %9 :: jog steps within nach ph::f.c cre indicnt d below,' 73m)

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1. Obtain copies of the STS from the* LPH. .'. . '
2. .

Idcr.tify and r. ark these specificatio'ns .not renuired because of plen

, da:1t.n or other fac. ors. Specifications within this cateco'ry should be retained in position within tha.- ;'ocuacnt package int lEter review

. and discus:non. .

3. Identify ghose areas where specifications are required but. are not '

. provide.f in the 575 -

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4. Provi/cc tha applicable valuep ' f the ptramters and variable: .

identified by blanks or pcrentheses in ti;e STS.

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Provida

..he STS pac, thac age. figures, gr phs tnd other irifur.a .f ion required to complete e..

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Th3 Commission staff willi i eview the inferration prov ded in [hc carked

.up 5 a5 pachage resul. ting fers the Phe',e I preparation.

2.

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@plicant/ staff nectins vill be held to rer.olve n/ited differu'ncas -

pos1t*.on and other related ccmants frca tha appljcant(. ve'ndup

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Tha Commission will provide a Proof and P.eview edition of the technicd speel .1ct.tivo for final reviev by all parties based upon he rth,1ution of cc.rcat:. cnd positions in Phase II.

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..'.3., JW7echnical r.,pacifi. atiens vill be issutd'by,the Cetaission as '

2: Appendix "A" of the Opbrating Lictinse, c* ,

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Se:ticut: R .,n ,rt ilos . 50-41tVEE- 5 :nd 50--417/32-12 This refers to the . cutine safety inspection c.inducn.d by ih . .W. H. T::ller, Jr. ,

of thi.:; office on July 20-23, 1932.. of activities authorized b .- f..f o n a e 1:o. !:PF--13 and Constructic.n Per:ait No. CPPR--119 for the Grand C-.1 . ~.li".y and to the d.scussica of our finding.; held with lie. C. K. !!cCoy, Plc nt Manage; , at

, the. conclusion of the inspection. -

/.tcas extained durir.g the inspection and our findings are discussed'in the enclos_d in:,paction report. Within thcsc areas , ~ the inspection consirted of sele.ctive exa. min .tions of procedures cad representative records, interviews with personnel, and observations by the inspector.

Uithin the scope cf this inspection, no violations ce devittions wcro disclosed.

Ve have c<:cr. tined cctions you, have taken with . regard to previously rcported d .?.*Junre.,olved itens.

h The status of thcse i tclas is discussed in the enclosed

% f a:,p tctica report. -

Four new careceived items resulted frc:a this inspection and are discussed in the inclosed report. These items will be examinud during subsequenc inspections.

In zccordance with 10 CFR 2.7SO(a), a copy of this letter and the enclosure will be placcd in the IEC's Public Document Rooa unless you notiry cnis office, by talcpn.one, m. a,in ten o,ays or. the dcte or. this letter ano. sue alt written appli.-

catica to uithhold infor:aation contained therein within thirty days of the date I of this lettir. Sech application nust be censistcnt with the rcquircr.: ants of 10 CF2 ?..~i?0(S)(1).

Should you h.sve any questions concerning this letter, we will be . glad to discuss the:a trith you.

Sincerely, -

(.

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V g., a., .'..

D. H. Verrelli, Chief Reactor Pro jects Granch 1 Division of ProJcct and e s,'. c I3 N f ' o I I s' blsi b l

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Nc.ic: !!as. 50-?IG and 50 e17 .

Licensd *.'2:: . !!?!~-13 cc:d CF?il-119 inspactica at Grand Gult site necr I, ort. ga bson,1.i ssissippi.

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. . EuspectorC <7-/ JN. A.f'-%?: . L.R W. ' / G-Es .% ~ // ..$, . f.

'. / . it. !!i11er, Jr. Date Signed

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0 e f.-- ?~r-1 . ,,c . L. e a l e n , S.-,. ,d. cC..ntur:. y. .-

ectica .

U-.ta M.e r.ca-uagineering Inspcctie.1 Branch in. .

vision or :aga .e ncering cnd ..icca,nica.1 Programs qt.;.. ...< 's. . e, f Insp etica ca July 20-23, 1932 e

4....s. t,. . ea T .l ap- ,. . ,-v. U 5 wt .

inis routino, ar.nctaccd inspec. .cica involved .'.8 insp ctor-nours en .: ..ite i n tr..a arcas of fir.q 4.rutaction/prever.tica. -

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s Of :50 areas inspected, no violaticas or devictions were identified.

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f iEFORIT5 AILS

'.. n;rtons C.m.tactad -

Liccana Faioyees "C . K. FrCoy , Plan t l's. nger *

. T.' A. l tr?sino, l wistant Plant Mnaager, ' ' -

1 .J. t!. Ye!verton, Site QA i'ancger Y' ~ -

i!. H. %rm:r, QA Rep t.<cntnti.ve FA. V.1:o}uberg, Fil i protection ....

YD. .-r aa rn< s , icensinu E.na.ineer Oth:r Organi.utions .

"it. D. Castles, Risk Control Specialist / Middle South Services, Inc.

"'ttended

.. exit interview  :

7. . E,it Int 2rvieu -

Tha inrp tica sr:cpc and findings were summari7.ed cc: July 23, 1902, with thosa persons inoicated in pcragraph 1 a, aove. t he ic: a,c. ting nr.w items were

~

  • discussed: .
a. Inspector Follevup Item (41G/82 01), Automatic sprinklar systeu to be provided for c.cea IA424 prior to the first refuelir.g outage -

paragraph 3.a. .

b. Un; esolved Item (415/87.-55-02), Inadequate fire protection surveillance ir.spectica and test peccadures paragraph 5.a.(1).-
c. Ihip~ector Follmcup Itca (416/c2-5G-03), Automatic ~. sprinkler systems for sr.foty-rela ^ . ! a rea.s of cuxiliary~ and ' control . buildings are not t

included in tha Technical Specifi:ation paragraph 5.a.(1).

. d. Inspector Folimtup Itta (41G/82-EG-Oe.), List of : .:.dund:.nt safe shutc:own circ.uits wh:ch are co'. :;apc.rtted by at least .I 1-hcu t- fi, e rated ba rr i er i s net provir.,ad

. .s i. te pc re. graph 5. a . (c...f. .

e. linessolved Itna (416/82~56-05), Sdety related cables in a numbe: .of areas of the plant are r.ot provided with'sufficitrit stparation between safety divisicos parc;r.?ph 5.2.(7.). .
f. Unresolved U ma (/.16/P?. .C-0G), Tc..porary struchres withiri auxilicry i;uil fing should :e r_n.v?.d or equir. ped tith uppmpricto fi ra protecnica f e e. :res par;g ..ph 6.c. s h

..q,- + w e _ , ,---+

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c. Unresnivat h .' . (W:/E ;347) . E0 C i ': m Y C ~2 'd in h ;i"C Or0ETL7

.6 ~

neuvin2:i ~ : 5 .nd Ih ncu.: ..i.. rj ':.n./ D m .. / ; r 12:

Ii'shtinii uni ts -

a r ri.c: tan 2. 2.

h. In ;;..:::cr Folio.<up i. : t..: ( ?. i .~ /? . ~:5 - fG ) , Li r.m s ae '. .s evaluttion of tn..

..et u:y oc. m. cr.al e i i re. e:r 1 r.gu i r ae r s ca d ice,. ..m , 01sr inutica, rau in: .rior fira hu: e e . 3 ..

r: 7. ! i :'h 3 C -

i. Iir: retor Failurup N a (?16/57. ~;G 09), n:vieu of licer.sca's cvaluacioa ac c. r::an c.a cxine acunctica sys u.... par. ,'r pu. o.

s Ue. lic m. .a 1. .d no di rrenzing cr . crc c.n i.l.2ie iteus.

~

3. Licensee /.ctica on Previeus In pactica Fiadings
a. (Cicscd) Uarereived R",.n (415/01-01--01) - Autcmntic sprinklcr protec-
v. or t.v. arecs uv '.,a c tuxillcry builc..ing cs :equired t1cn not pro..,ud vi.

by the SE2. Th i s i t; .a ha s b.'.e n rcevale ';ed by fiRR. The requirer,ent for spinkler protection has baen delettd fer are s IA101, IA117. IAzis, cad 1A314 but is still required fr.r arca 1A?Z4. The licensee hcs ec.c..ai ttcd f ta provide prctaction for this aren prior to tha fi rnt rare::T og vutage. .l ais ine::: 1s closed u.ut. a ncu itera is opened to t

scura.t!.at this protr:.tica is providcd. The ne.! itea is identificd .s '

Insper.' or Folic,:vp Itcu ?1G/87_-56-01, Aute.aatic sprinkler protection to I:a provic'ed for area LVE? prior to the first rcfualing cuurga. This itt.a vill be revicized c urir.g a subscquerit URC inspection.

b. (Closad) Unrzpived Itc:a (416/32-34-01) - Fire protection systens rcquired '.y FSla not provid.d for recus 1A305, IM02, IA529, cnd 1/.50: .

o : a s ta l ,i r.d l an noca .3 so.c n, enac..a ch.tctor nu . t:n e ~ .a . has beea icn.e .~c~.*R

. avi s eu, (. a2::c;. . , . enta . -) to. iacocate that tire suppression c.;utpment is n :essibl a ta row.s IA305, IM0P. , .=.nd 1 AGOG . This itea i s. el o:.ed >

houuvar, t.aa 11canr+. a-s v.,. cat 1n ad sevni al other areas in which cha fim detection system had aat been in' stalled as cc:.m:itted. This hcr.

L:-en reparad to the !!.C cr.d is id1nnified by Licensee Event Report

, (LER) 32-07. This it a vill b? revicued during a subsequent ?{RC inspect:cn.

.. . , u- ] .x.. ,. a .r .- ... .a-s....a .

Unresolvcd it=as al e : cat.ws about :hich r. ore i n for: .ation is required in

.& te rai a e . a a th .=. . '.h zy , 0 cceeptebla er .. y involve violations or dcvice-ticas. ::w v. arc':olv2d it ..s identific.d during this inspection are discussed in _ parac.aph 5.;(1), 5.:.(?.), rad 5.c ( t,ca itras) .

t 6

~

F. Fire 'cc entien/ .ar :: . ion Pr @rta Imai e:..:.nna icn' (F. v :le G'704)

a. Prece "rcs (1) Su:". .:ill e r.ce of Fi ra Prate.:ti .;n Futyres iha insyrt6- rnvimred the surveillanta inspection :.nd test pccee-br;s for ;e fin protcetion i c en.s i r..:1 ued in the Technical the

.eo c a v i c t v :) (in). es n ..ber cf di scr*.pr icies were no.ted.

principle iv::a incledad the foIlu. i ting:

nnuil r.unctional terts av t.ne vare detection dev.. ices (a) .S-:.i ..

ror t.a.e nr2 s upprer.sl on systens, r .o ke c,etector zcr -

ncs. 2c-15 and 2 -13, ar.d the de.tector systelas for the chcrcoal f;1ter trains cre not rpecified as required by TS 4.3.9.'1.

(b) All supervisecy features ' of the fire protection alar:a and srppression panels are not required to be demonstrated cperable at laast once per six r:onths as required by TS

. 4.3.7.9.2.

'(c) Proccdures' have not yet bc:n -issuad for an inspection and tast of tha vr.1ves and " puff tast" of the carbon dioxide systea required by TS 4.7.G.3.2. .

(d) PCCC h;. lou cylinders are not requircd to be v.eight and pressure verified each six months as rcquired by T.5

?.7.5.4.b.

(e) Fleu test of cer:puter room halen syste$ is not required each 13 cunths as raquired by TS4.7.6.4.c.

. . .(f)

Inspectica prccedures h -c/c not beza i.s sued for . vise:1 in s.pection or each n-. re rcutd essembly and barrier penetra-tion seals as required by TS 4.7.7.1.

All of the above tests and inspections were recently conducted d' ring tha startup t': sting prograa at the plant. Therefore, this ita is i&ntificd as Unresolved Itea (416. 27.-55-07.), Inadcquate

. fire proccction survcillarice ,inspcc^ ion and test procedures, and.

uill be revirued during a subsequent :'.RC inspectioti.

'c.'hile ravicuing the above proc;dures it was note.d that none of the -

.u.;oraatic sprinkler systeus ia tha coxiliary and control builcings t he licensna is star t inclun,ad in i. ...a .l.echnical ape:T rica clons .

eviiuating t. .nis i t e:1. inis item is idt..i;1iled as Inspector i ,l i s.ec s .Itaa ( ~. 5/8 7.--5 5 -0 3 ) , i.utom ti c Sprinkler synter.s for s .a c . y . i c t eu,

. a.. .s or. u, e.u:. . 3 a r ry and centrol holidings are

. . c: t i.iclu '.d in i.a T.;c:.aic.:1 d.v.:1Ticatica, cod uill be cavisued

' .. ie g e. subsequu... S '.C insp::c . inn.

(2) .h scuan: Safe $hunco ca Circuits i:5AR Naenwnn . 55 neved the lis ts of redunnit safe shu: Faun 21=r.ed crui n no s e pa ranz.: by at leas: & 1 nour fin r- 'd barri c.-  ? r .. -

Su .ian 7.2 of rV.R Apnen fi:. o.i. Tha Fi'Jt tv :s i m ais list t.u to I a n.i:mained it the siva. As of July 23, l'R2, this li st hcd ;m. yet b .: e n scn: to the sine by necntai. tais inro;eix w n is cc ,M

- p : cr. ' ed by DEN 1 m drwing no. E-0/31 1 hich uas scn.duled ta ba isn 4 -he uc.d of July EG-79, 19S2. This itta is identified rs In c . .,-r Follen.:p Itha (416/82-5G--04), liathf redtu&nt stre inan a un a waits' not saprrated .by at least a1.nour vira rateu,.ocrricr. ch a . .

'.a ,i i be revi wad during a subscquent !.T.C inspectica.

The inspcctor also noted that c large number of cituaticas e::icttd in several areas of the plant in which.the separatica bct.t a divisicas of stfaty relat:d cables did not conform to the 5 faet verzical and 3 feet hcrizontal criteria of Reguiatory Guide 1.75 ts cc:r.:itted by F.'i ' R Apr.endix 9A Section 7.1. These ;reas are identified by a tec:.tel Repart dated June 3,1982. The-licensee ucs cdvised that this problem t.ust ba..corracted , prior to criticality or cdequr te .'ustificatica j provid d Lad approved by HRR and to Region II. This it a is idrc.tified f as Unrasolved Itca (?16/82-55-05), Safety related cables an a nu.1;2r of arcas c' the plant tre not provided with sufficient sepcration b rcif2cn safety division, and will be rcviewed during a subscqc .at i:RC inspt-q-rion.

)- - - m __ .

.b.

rire Brigade ,

(1) Training and Drills The inspector revicc.!ed the training r2 cords for tha bri p ~ d :

.c cbers cr.d nottd that all members bzd receivcd initial ur aining

.. and :.dditional training the first rad seccad c;uru .ar of 1932.

Most of the acabers had participcted in a pracc...ica vire n r.. .;i n g 3

' sessien in July 1981 and all m:bers are sca.. nu,wa ror mather . . -

session in August 19S2. The lictasee stated that practically all of the bricade mem5crs hr.d received a rccent physical er.auir.. tion and til $rbers are sch:duled to receive a pnysical by July 27,

. 1932. 7.np: oxiin .tely four drills hnd been conductnd in 129. but the iictnsea stated that a suf?icicat number of drilis . Vere to be schedul:sd for the reminder of 1982 to cssure th4t 211 cci:crs would pcr icipate in at lecst two drills during the year. The annual drill uith the local fire depare.:ent had acz yet been c..nductad.

inis crill is to 52 schedul ed to be ccct : .pii sh-d ;wior o the enti of 1982. Tha brigcde training i r.d drill p:.rtic;;=.tica .

utli-be reviu ad during m b c ry ::n t rcutism s, ,..

.sd. .':.S;cctie.is to v3rify F.hi.t 1..J liCChsCJ is M'.dLin9 tbe W 1 Ef "

  • C 13 UbC WC.

..+. .

. ( . .) C i r a S ci ._ .ui.2 Ecuip.cn bet:, h e l n. re.s ,

A nc 3.1 of 13 full o .s of :p acu: 9;.u.-in( 1cgn:1.ini .

r.2.

s e ;uipma:: t ra s gioves, e : . . ) '. a r p mc i dad f o r

,cuiliy divit.:cd in s~on lochern ict td on IB'.. ele m.lon or m..Telcvition os. . urm : 2 . u t t n r ; a n:.,, .ia the

- ux1,.1..:y nuilaias, _3 r;ilrcmi ccess br.y to the :.uxiliary buildinc. A total of 14 nelf can::ir _d brc athing armtratus ver,e designa :.:d 7or i T re ari."- da f er.a .' h e imi th p h.v.; i n s usa. , , iiticnal uni;.s \; :ra , avail. '>le .

group. ..he equ i p..<.m t ;opn red to ,n,3 acer;us.e ty r .w21ncu tna in t

survica. A total of G make c.iectors are to na locr.ted cdjacent to the ' star:.ge lcck1rs . The equipun?. ic.e -?cs the ccamitacircs t.o 7.h 2 [ I.'.~$ .

c. ' plant Tour- -

A tour . as .cr.de of the plant to revitu ccneral housckceping, centrol of flewaabie c: d combustible materials and general fira p.ctaction fct.-

tures. The general horsekciping was considared typical for a plant undergojpg the transition frca construction to cperation phase. Most of the taapcrcry construction materials and supplies had bcen rer::cved; houever, ?.hree structures, two en 139 ' . al evation and oae en 119: . .

eltyxtion av t, ae auxiliary building, remain in p e ace cnd reperredly are rc:iuir'ed to be used during .the loustructures pouar testin, phase. The licensee

,;cs advised that these tauporary pn. zide an exposure fii e h=zard to :,afety relatcd equipment and should either be removed or additional appropriate fire protection featur:_s should be provided.

This itea is identified as Unrcsolved Item (41/22--5G-05). To::?arcry structures ti .hin adniliary building should be re.mved or equipped with copropriate fire protection ieatures, and vill c2 reviewed during a

.chsagrent EC inspectica.

/_l) .of the installed fire protection systens cwnrtd by the t<:chnice.1 spaca rications vare round in service. H.. r e ,n ... a t equipment house

~ . . . .

nos. 9,19, 20, 23, 7.4 and 25 vere inspu.ted u.d foend to contain the raquired cuantity of cquipment. The inspcctc. cated unat, in some arer.s of the plant, the travr:1 di stance to fil : 2xtinquishers' appec; ed .

cxcessiva, the ureng type rara extinguis,ser uas provic,ed , 2nd the av rTre hose on a ,ccw or t.ne interior , ose c pac.es apper.ced to be l e n g ..n, too thort. This_problan had also becn irLntified.by the licansee and an evaluation w.s being made to 'idrentify prohica areas ar.d initia,te cppropria .e correctiva action. This ^_p.luatica .uas bei ng m.7.de Th2 by Eechtei under Design Chr.nge Assistance ficqu ut No. Hi@2 -311.

r". ing a subscquent 12C results of this evaluation will be reviour.d inis 1 tem is i t,e n t l i l a';.. as 7.. n ! , _ Jt or ,..- o1 1 C'.tu p .rtem la ycctica, (415/92--59-03), License 2's evalentica of the ic ution, di stributi on ,

v.i cd'ruacy of poruble fire extiaguishars c d innerice fire hose system. s

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. n t .an e c of t r. 2 5 -hr . z od % --n o u :- gency 1 i g.::i n g uni.s were ,

insar . ;d. m:ec and f ,unc te ha in service :y %2 inspector; heuever,  ;

i: 1::s ne d that c, m;ine mai n ne:r uce 2.:d inucc;ica p ree rtm. fer tmm lig.. .ing units ird net 3 :: c'en ini'.iatx. T!:is di scrapn.ncy is i.vt rc.n i-; M is Unrucci at I n ci.: (C.6/82 -EG -G7) , h'o naintenando cnd l

i.ispi c::ic.n pren: .a far 8 rnd W hour < r cr.pncy . t ery lighting unius, '

2.nd ici li b2 ;;vicved durin; ; subsequan: fi {C i nsp 2.;ti on. -

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. i ; o n tne cru s ex:minea, na. vu.lcu. .oie ar ce"i .tiens ure ideat171cd.

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6. - r .rbon Dinxide Systh:n Acte =.tica

. f The inspector . avir.ccd the events cc a c t.rn i t:g t.he July 13, 1922 cars:n cacxic,a rire protection .ctuar.w.a into t.u.a E w- switc,;nar rocn: on elevation a i 119of the auxilicry building. Tha cartan dio :ide systen activated ibout 3  ;

ti es du2 to a defective relty in the acin cc.ntrol ptael (short in s u p e r-- i visory coil). Ecch activation dischar;cd approxite=.tely 2000 pounds of '

carben dioxide into the reca. The liceasce estintad that a total af cppra:anctcly u,,0,00 pouna.s cv carben o,loxice .tas ai:caarced into the recm.

iais qucntity..or carnen dioxide created sur.-.rici ant , ores sure '.1t,ain the reca to form cpen the normal.ly lected entrance door. Thir. dcor v.=.s rcpaired on July 13 cad th2 defective relay was replac :d on J Iy 14. The licensee maintcined a fii e uttch within this reca s require-1 by the Technical i Sp icificatiens until the cccessary Npairs tei e made. The licensee s Ited

.ht t Qis actectica did not damage any equip..,2nt rithin this room. The licensea is evaluating the d2 sign of the tcte2 tion syst m to deterr..ine c if

=ny design mcdifications shculd be cade. This iten vill be reviewed during a subscquent NRC nisp ction and is identificd as Ir.spector Follovup Itera (416/22-55-G3), Peview or lictasee's evalea' ica of carbon dioxide actuation system.

,:. ,12,n n tn.a creas exzaines,, no vio:ations er o,eviations ure identiried.

7. Licensed Identifi2d Itcas (Closed)

CDR 415/80-67 and 417/SO-57, Inadequate specificatica for

,c a, e szm fea previously installation er. rire d. x rs. ,

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i hererore, ,

this CDR is closed. .

I:npactor Folloitup Itcus (IFI)

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I.I. S. Hu .la.'.: Reguldcory Con .ssica ~

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'.ecion II $,

101 ?-nietta St., R. W., Suite 3200 -

.t Lau c.a , v.,s 3 0.ava Attention: 'h . J. P. O'Railly, Regiona.1 Aduinistrator

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Unit 1

, Docket l'o. 50-416 Licence :'o. N~'L-13 File 0250/15525/15526 Report No. 416/83--26 of June 27, 1933 - July 1, 1983 c..J

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,$ u-: ,10313 Refercnce: MJ.2C--8 3 /02 35 , dated July 29, 1983.

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This letter provid23 car responsa to Violation 416/S3-26--02 (Attach =ent A) nad Devic.tica 416/53;-26-01 (Arrachnint 3).

Yours truly,

/Jf5$D g -

,s.-/ .v. -

L. F. "al o

10. nager c,f Nuclear S arvices 11FD: ch 4

Attac!. rents . .

cc: Mr. R. 3. "$2 2h-c (u/o)

Mr. T. 3. Corc, - r (a/o)

"r. C. 3. Tayloc ( ..' / o)

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o; 1M asinnippi Tot .;r ad 1.i.ht (KPTV ) c ? nit;; to the clie;;~1 vini:. tion.

,-cver, there vere na .sdv 'rae ef f e,".ss on tha h2s. lth d safety of ,

fa public. '

re- a -- nn yT2_o.t TI- = =.m: ='.. .o:: . r.-mag :Ty:.j~w'iTTT..=RU

".ae spacif' c requircu t-at to test tha PGCC Halon Systen cas overlcohed rhe a 'the initial Ealon systen surveillance procedurc '

uas t.ritten.

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As -cented in paragraph 5.d(13) of P.eport No. 50-416/33--26, Frecedure 06 -rR-S?64-SA-002, '.'2GCC Union - Syste.u Bottle Ucight and Pressure

(.hr..:k" .:ac issued in Febru:.ry, 1933 to. insure that the ?GCC Ealon Sf sten is properly tested as recuired by Technical Specificction 4.7.5.4.b. Also, as 2:ated in the report, the above procedure uc.s ,

sa-infactorily perforted on various dates during P.sy and Jun2 1933, for the first six ncnths c,f 1983. These actiens were being cc.pleted at the titie the violation uns discovered, and no corrective susps ..: ave beca deer.ed necessary u nce the c..:Lscevery of t,c2 nolatica.

IV. CORFICTIT.'E SI"?S %~iICH UILL BE TAKE' TO AVOID FI'?.; R VIOLATION No further c .rrective steps are planned.

V. DriZ t_.._i_E_'..i..FU..LL COh~?L7 ti!CE ' JILL BE " CHI ~VED . _. . .. _ . . .

Full co::pliance is in effect for the specific activity tchich led to this violation. . .

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- reque:.c bc beca fornialined ',into .FSAR Cheng'.: Nitice #1903 . nd is presently enticipette.d to be 7 .rt of 2 aendraeut 57 6f th? FSAR.

.C.0_F_~.W.. VE AC_T_It' NS U;!ICH UILL SE TAKEN TO .A'/0?D TGTiiER' DE7IATIONS No fu. ::: ;r action ic concidered tjecensary at thi s tin 2. . Daletion of .this require:ent in the FSAR still leavea KPf,t. in c.caplu.nce uith the S.'t? and FdC anarcvr.1 is antici ated.

DATR "_.'.iEN._F_.TTLL CO!f?LI A.NCE WILL 3E ACHIEVED - .

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4 Full corplisnce -ill be F.chieved t/ned the relief rc. quest is approved by NRC. .

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SEP 2 1;q3 i 1"tsissicpi Pc eer and Light Company ATTN: Mr. J. 5. Richard 5 :aior Vice President, h'uclear P. D. Box 1640 - -

J ch.ca, MS 39205 -

-t G:nti eahn:

SUBJECI: REPORT tiO.'50-415/S3-26 Th:-m.k you for yo::r letter of August 25,;1983, informing us.of steps you have takun to correct the violation and devihtion ccacerning r.ctivities under NRC

'Lic:nse No tiPF-43 brought to your attention in our letter of July 29, 1983.

e wiil er.cmine your corrective actions cnd plcns during stasequent inspc-ctions.

L'e ppreciate'your cooperation with us. ,

Sincerely,

/ .

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D. M. Verrelli, Chief .

Proje -t Branch 1 Division of Project and Resident Programs cc: J. F. Fager, Vice President .

Engincgring end Construction Middle South Services, Inc.

, C. K. . McCoy, Plant Manager

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'- LIR 83.-073/03 La AECM-83/0410 C2 Septenber 1,1982, it ::ac diccovered that the thirty (30) cecend elec.re tin 2 for tha scre:2 disc'inrge volunc vent t.nd drain val'ics stere not c r'/.ied c.c tecuited by. 'Achaical Specification 4.1.3.1.4 prior tr> curry '.ato Cpc;nt < tl Cceditica 2 (Startup) ca Au-;us: 13,.1932. A picat .'.!,.c.1r.t

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c.-Matica ca June '/.3, 1983, datetrined t'ne cveat chuu?l bcra be.a .npc;ted.

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