ML20214V505

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Summary of 870501 Meeting W/Util in Bethesda,Md Re Scope & Schedule for Licensing Actions.Meeting Agenda & Handouts Encl
ML20214V505
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 06/05/1987
From: Kintner L
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8706120130
Download: ML20214V505 (17)


Text

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June 5, 1987 4

Docket No. 50-416 DISTRIBUTION LICENSEE: System Energy Resources, Inc.

6~PDRir NRC & Local PD22 Reading

,_ OGC-Bethesda E. Jordan J. Partlow L. Rubenstein NRC Participants FACILITY: Grand Gulf Nuclear Station, Unit 1 L. Kintner ACRS (10)

SUBJECT:

SUMMARY

OF MAY 1, 1987 MEETING IN BETHESDA, MARYLAND REGARDING LICENSING ACTIONS SCOPE AND SCHEDULE 4

The purpose of the meeting was to discuss the scope and schedule for licensing actions. Participants for the licensee were Guy Cesare and Matt Crawford.

Participants for the NRC staff were L. L. Kintner, J. Unda, J. Buzy, D. Notley and T. Michaels. Enclosure 1 contains the agenda and a handout prepared by System Energy Resources, Inc. This report was prepared by L. Kintner and J. Unda.

During the meeting, the licensee described the status of Unit 1. Unit 1 is operating at about 100% power with no significant problems since restart January 9, 1987. Engineered safety feature (ESF) room coolers are being moni-tored weekly to see that service water flow meets the required flow. When flow approaches the required flow, the service water system piping is flushed to re-store flow. Changes to the service water piping to the coolers are being con-

sidered. The cooling tower modifications that were completed during the first refueling outage have increased cooling tower efficiency.

The licensee described its present thinking about the second refueling schedule.

The licensee stated that the earliest date for beginning the second refueling outage (RF02) is November 15, 1987; hewever, a reduced load demand may extend the starting date to January 8, 1988. The refueling outage is scheduled to be an eight week outage. A meeting with the NRC staff to describe the plans for RF02 was proposed for June 8 or June 9,1987. (Subsequent to the meeting, a

the licensee and staff agreed to include this item in the agenda for a meeting at the site on June 2, 1987).

The staff described some of the new aspects of the new NRC organization which was published in NUREG-0325, Revision 10. Some of the functions and responsibi-lities from the old Office of Inspection and Enforcement-have been included in the new Office of Nuclear Reactor Regulation. These functions include reactor inspection, safeguards, emergency preparedness, human factors, and quality assur-ance programs. It is expected that NRR will participate to a greater extent in inspections. Another change is the new Division of Operational Events Assessment which will provide greater emphasis on performance evaluation of operating reac-tors and reconnendations of near term improvements. A new Technical Specifications Branch will provide greater emphasis on evaluatien and interpretation of Technical Specifications.

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  • The following comments were made with regard to specific items in the Agenda, Enclosure 1. '

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j Item I.C.

The licensee has received accreditation for the remainder of its GGNS training 4

programs from the Institute of Nuclear Power Operations (INPO) on April 29, 1987.

The licensed operator training program was accredited by INPO in April 1986. i The staff commented that portions of the INPO Guidelines86-025 regarding i requalification training and 86-026 regarding a systematic approach to training were used in the September 4,1986 submittal on the GGNS Licensed Operator Requalification Program but the staff had reconnended additional considerations

, in February.

i The licensee indicated that Revision 6 of Procedure 01-S-04-2 incorporated these recommendations made by the staff regarding the use of a systematic approach

i to training and that further revision will be made in accordance with the new

' rule on operators' licenses (10 CFR 55) which became effective on May 26, 1987 and in accordance with guidance to be developed from public meetings on the new rule. This guidance will be published as NUREG-1262.

Item I.D.1 The licensee plans to submit several requests for changes to Technical Specifi-j cations (TSs) to be made prior to RF02. One change will be clarificatien of refueling mode operability requirements for containment isolation instrumentation to be consistent with containment integrity operability requirements. During i

RF01, it was noted that isolation instrumentation is required when containment integrity is not required. Other contemplated changes are: revision of the definition of core alteration to exclude movement of the source range monitor i and intermediate range monitor; changes to the snubber sample size, consistent

] with changes made at other facilities; and clarification of operability require-j ments for the reactor pressure vessel (RPV) water level during the refueling mode when the water level is above the RPV flange. In addition, the licensee will propose TSs to replace the present License Condition 2.C.(38) which imposes  !

t a limiting condition on plant operation for control room inleakage, but without specifying surveillance tests. Some changes to TSs may be necessary for an i

18-month fuel cycle to be initiated after RF02. Applications to change TSs will i be filed in June 1987.

1 Item I.D.2 1

1 Plant are: modifications changes needed toand associated implement TSs currently the ATWS rule 10 CFR (required to be made 50.62); neutron flux during RF02 i monitoring instruments to meet recommendations in Regulatory Guide 1,97; and

' addition of containment isolation valves to instrument lines. The licensee requested guidance on TSs to be submitted for ATWS systems. (Subsequent to the meeting, the staff advised that TSs should be submitted, together with logic

diagrams for instrumentation, as soon as design is completed. Present TSs for ATWS-RPT and standby liquid control system may need to be revised to meet new requirements. TSs for the alternate rod injection system can use surveillance test intervals consistent with present TSs on ATWS-RPT. The licensee will also use information from the BWR Owners Group).

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Item I.E.  ; l A license amendment will be applied for in May to replace License kondition 2.C.(23) " Fire Protection r i This amendment will replaco;rogram" with the present that recommended license in Generic condition requirement Letter 85-10.

to meet l the " intent" of Appendix R to 10 CFR 50 with a reference to the Fire Protection Program in the Updated Final Safety Analysis Report (UFSAR) and will delete fire protection instruments in the TSs and place then in the plant procedures.

Changes to the Fire Protection Program will require analyses similar to those now required for FSAR changes in 10 CFR 50.59. The staff is reviewing Section 9.5

" Fire Protection Program" in the UFSAR and the referenced Fire Hazards Analysis Rev. O and requested a conference call to discuss some of the matters being reviewed. (A telephone call was made on May 7,1987 in which staff concerns were discussed. The licensee will arrange a conference call the week of May 18th to respond to the concerns). The licensee said Region II is planning an inspec-tion of recent modifications to fire protection systems this summer.

Item I.F.

The licensee plans to request deferrals of (1) the installation of neutron flux monitors for use in post accident monitoring per Regulatory Guide 1.97, and (2) the installation of containment isolation valves in six instrument lines -

four in the main steam isolation valve leakage control system (MSIV-LCS) and two others. Regarding neutron flux monitors, the licensee will request deferral until RF03 on the basis that none are yet commercially available. Experimental incore instruments are installed in Nine Mile Point and are to be installed in WNP-2. Excore detectors are installed in Susquehanna. The licensee presently prefers the incore type because they would replace IRMs which presently have caused some scrams. Regarding the instrument line isolation valves, the licensee believes the BWR Owners Group can demonstrate that the MSIV-LCS is not needed and referred to the Nine Mile Point design.

Item I.G.

The licensee stated that some of the certificates for pro l were made out to Mississippi Power & Light Company (MP&L)perty damage rather than insurance SERI and they are being corrected and resubmitted. Another insurer does not issue the i l

certificate until the insurance period begins. However, SERI was informed by i the insurers that GGNS insurance is in effect. Copies of certificates will be '

submitted when received.

Item I.H.

Containment purge isolation tests have been successfully completed. Results will be submitted in May 1987.

Item I.I.

Relief from the requirements of ASME Boiler & Pressure Vessel Code Section XI for reactor vessel nozzle weld inspections will be requested June 1,1987. This relief will be needed for RF02 inspections.

Item I.J.

The licensee has submitted a request to extend the latest construction completion date on Grand Gulf Unit 2 until January 1, 1997. Presently Grand Gulf 2 is being maintained in its present status under the GGNS Quality Assurance (QA) Program.

A special QA program and preservation method will be submitted June 1,1987, to supplement the information provided for the staff's review of the completion date extension request. The staff said that Region II should be consulted regarding guidance on special Ouality Assurance Programs for preservation of equipment and records during lengthy delays in construction.

Item II.A.

Dates for completion of licensing actions are indicated in Enclosure 1. The staff's letter of April 30, 1987 accepted SERI's position on its capability to control activities within the exclusion area, with ownership of 89% of the mineral rights. The licensee stated the FSAR would be updated to show current ownership of mineral rights on June 15, 1987.

Item II.B.2 The licensee has been reviewing potential interactions between Unit 1 and the partially completed Unit 2. A special report, submitted April 9, 1987, described results of the review. One result was that large storage tanks filled with fuel gases were identified in the Unit 2 area. The tanks were emptied and purged pending completion of an analysis of the explosion potential to Unit 1. A followup report will give results of the explosion potential of the "as-found" condition.

I Item II.B.3 i A summary report on the results of the design review of the standby service water system was submitted to the NRC on May 8,1987 Item III.

The licensee said that Grand Gulf is the lead plant for the BWR 5 and 6 TS improvement program being undertaken by the BWR Owners Group. Hatch is the lead plant for the BWR 3 and 4 TS improvement program.

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i The licensee said that Sandia National Laboratory personnel working on NUREG-1150 Probability Risk Assessments (FRA) are planning to visit GGNS personnel at the site in May 20 and 21, 1987 to address SERI comments on the Grand Gulf PRA.

Lester L. Kintner, Project Manager Project Directorate II-2 Division of Reactor Projects-I/II

Enclosure:

As stated cc/ enclosure:

See next page L) k P I-2 PD:PDII- g DP r LKintner:bg LRubens 5/ 87 5/;_j/87 g/3/87

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. Mr. Oliver D. Kingsley, Jr.

System Energy Resources, Inc.

Grand Gulf Nuclear Station (GGNS) cc:

2 Mr. Ted H. Cloninger Mr. C. R. Hutchinson Vice President, Nuclear Engineering . GGNS General Manager {-

and Support System Energy Resources Inc.

System Energy Resources, Inc. Post Office Box 756 Post Office Box 23054 Port Gibson, Mississippi 39150 Jackson, Mississippi 39205 Robert B. McGehee, Esquire The Honorable William J. Guste, Jr.

Wise, Carter, Child, Steen and Caraway Attorney General P.O. Box 651 Department of Justice Jackson, Mississippi 39205 State of Louisiana Baton Rouge, Louisiana 70804

! Nicholas S. Reynolds, Esquire

Bishop.- Liberman, Cook, Purcell Office of the Governor i and Reynolds State of Mississippi 1200 17th Street, N.W. Jackson, Mississippi 39201 Washington, D. C. 20036 Attorney General Mr. Ralph T. Lally Gartin Building Manager of Quality Assurance Jackson, Mississippi 39205 Middle South Utilities System Services, Inc.

P.O. Box 61000 Mr. Jack McMillan, Director New Orleans, Louisiana 70161 Division of Solid Waste Management

  • Mississippi Department of Natural Mr. John G. Cesare Resources 4

Director, Nuclear Licensing and Safety Bureau of Pollution Control System Energy Resources, Inc. Post Office Box 10385 P.O. Box 23054 Jackson, Mississippi 39209 Jackson, Mississippi 39205

' Alton B. Cobb, M.D. '

Mr. R. W. Jackson, Project Engineer State Health Officer Bechtel Power Corporation State Board of Health 15740 Shady Grove Road P.O. Box 1700 l Gaithersburg, Maryland 20877-1454 Jackson, Mississippi 39205 Mr. Ross C. Butcher President Senior Resident Inspector Claiborne County Board of Supervisors U.S. Nuclear Regulatory Commission Port Gibson, Mississippi 39150 Route 2. Box 399 Port Gibson, Mississippi 39150 Regional Administrator, Region II U.S. Fuclear Regulatory Comission l a a, o a $33 i

Mr. James E. Cross GGNS Site Director System Energy Pesources. Inc.

! P.O. Box 756 l' Port Gibson, Mississippi 39150 ,

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ENCLOSURE 1 NRC-SERI LICENSING ACTION STATUS MEETING May 1, 1987 t

AGENDA I. GENERAL & SPECIAL TOPICS OF INTEREST A. Plant Status / Schedule (RF02 forecast) JGC B. NRC Reorganization LLK C. INP0 Accreditation of Training Program JGC D. Technical Specifications MLC

' 1. RF01 Lessons Learned

2. RF02 (DCPs)

E. Fire Protection

1. Generic Letter 86/10 MLC
a. TS Deletion / Procedure Generation
b. OL Condition Revision
c. UFSAR Changes
2. FHA Rev. 0 & Exceptions (SER) LLK F. RF02 Deferral Items JGC
1. Neutron Flux Monitoring (R.G.1.97)  !
2. MSIV LCS l

G. Property Damage Insurance -

MLC H. Containment Purge Isolation Test MLC I. RPV Nozzle Relief Request MLC J. GGNS Unit 2 CP Extension MLC

1. Fonnal Request
2. Proposed Policy Statement on Deferred Plants
3. Preservation Methods /QA Program J16 MISC 87043002 - 1

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II. KEY LICENSING ACTIONS (NEAR TERM)

A. NRC Action ,

1. AnnualOperatingReport(Deleteduplicateinformation)kf/15/I7C-
2. ATWS RAI (SLCS/RPT) N[ 7
3. FHA Rev. O and exceptions 6,[3 ci // 7.
4. Mineral Rights '9./f S(( 7 C,
5. GGNS Unit 2 CP extension f[p///

B. SERI Action

1. Disposition of NRC coments on FHA Rev. 0 5/6

! 2. Followup Special Report on Unit 1/ Unit 2 5/7 Interface Concerns

3. Report on Results of Design Review of 5/8 SSW/HPCS
4. Proposed Deletion of Fire Protection 5/14

, Tech Specs and Addition of the Standard License Condition

5. Containment Isolation Test Results 5/18
6. Additional Info Re: CRD Housing ISI 5/22 Relief Request
7. Relief request for RPV Nozzle Welds 6/1 1

1 8. Additional Info to Support Unit 2 CP 6/1 i Extension Request

9. Neutron Flux Monitoring Deferral (R.G. 1.97) 6/15 III. OTHER DISCUSSION ITEMS A. SERI Review of 50.59 Evaluation Process B. UFSAR, Recent NRC Resident Inspection of Action to Address Violation C. UFSAR, Special Update (Exclusion Area and Mineral Rights)

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SCHEDULEDDATE NRC FEkESTDATE

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05/0e/87 04/14/87 FIREHAAR$0SANAL SU!MITAECMDESCRIBINGTHERES$.UTIONOFN80COMMENi$0NTHE ID 7023! Mi!-57/0033 FIRE HAIARDS ANALYS!$. REY O.

05/0'/87 // Ul/L'2 INTEAFACE SUBM!iF0LLNUF$8ECIALREFORTONUNIT!/UN!i2INTE8 FACE IDelD3 I CONCERNS, 05/08/S7 04/0!/67 INSURANCE SUBMITCOR*ECTEDCERi!FICATEOFNUCLEARF80FERifINSUFANCE.

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05/15/3' 01/20/87 Ct'N?A NMEhi FLRSE t!MIT 8ESULTS (f T'E C:NIAIN"ENT I DLAi!0N TEST i) M C.

D'C013 FMI-27/0N5 O!/:2/37 //  !$1RELI!F8!0. n!"It 8!!F'A!E TO INFOR"At 8A1 re: FURCE OF MAIEUF FLN

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06/10/97 03/13/87 GL 87-06 $U6MIT AE;FONSE FEGARDING GGNS FRES!URE !!0LAf!(4 VALVES

!D70233 MAEC-37/0071 (F!vd.

Ce/15/87 // FINANCIAL !UBM!iCORF0FATEFINANCIALAEF0AISFORMFtL/"ESI/!in!AND 10613Al NLSAP2.4 SMEFA FOR 1986.

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06/15/87 // NEUTRON FLUr MON  ::: ::::::::: :::::::: ::::: :d::::: :FG 197 REQ' SUEMIT TO NRC FEGUEST FOR DEFE AL OF . J ICEME ID '02 9 i FOR NEUTRON FLU 1 MONITORING 06/15/87 03/20/87 F!AROFDATE SL'!"If SPECIAL FEVISED FSAR UPDATE To THE NRC 10 REFLE07 ID 70255 F"I-87/1361 CVG8ENT INF0FMATION (IN MINERAL RIGHTS WITHIN TWE ENS EXCLUSION A:EA.

06/It/87 // INSURANCE SUSMit GdARANTEE OF DEFERRED FREMIUMS TO NRC.

l ID(1342 NL!AF2.4 C'!01/'d 04/2:/27 C0UTINE REFjui  %!MIT ANALYSIS /t!! Utis OF SFILED SA"FLE! TO N:.0 F?5 NEC itti;;4 "AEC-87/0!!! CNIENAiO8f MEASJEMENT FR AM.

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MF&L NUCLEAR LICENSING & SAFETY l DATE: 04/3C/37 ACfDN TRACIING MANAGEMENT SYSTEM RECENT MPat LICENSING ACTIVITIES PAGE: I SU!M!iTALDATE NRC FEvl'EST DATE MF&L CORRES. NUM FESPONSE MF6L CORRES. NUM TOPIC 0F SUBMITTAL 2ESCRIPTI0N MFil ID NJM NEEDED TAChuMiER 01/28/87 01/21/87 OPERaiOR REWAL. SUBMIT AFFLICATION F6R FEWALI{! CATI'>N V STEVE !.iRFIS.

AECM-87/0022 F"I-S?/0513 t ID 70038 O!/29/07 12/02/S6 MINERAL RIGHTS SL:BMITTONFCREVIEW0FMINESALRIGHTS/EXCLUSIONARIA AECM-87/0023 AECM-86/03S4 CONTROL ID 70200 01/30/87 11/26/66 MINERAL FIGHTS SU591T TO NRC

SUMMARY

6F RELEVANT FACTS FELATING TO FSAR AECM-67/0017 MTI-66/ ERFORSDETEFMINEDFROMINVESTIGATIONFE:FF0FERTY/ MINERAL ID 7029] FIGNTSOWNERSHIP 01/30/87 12/05/86 ENV WAL MOVs FE6VICE REFORTABILITY tETER9?Nat!0N OF AS FAUN 3 00N:li!0N 0F AEC"-!7/00!i AEC"-9e/0P2 LI"IT70VE SVi D 90.

D '00:5 01/30/87 12/18/0o ENV. QUAL. AdV F50 VIDE REFORTABILITY DETERMINTAION OF ADV ACICATOR WIFING.

AECM-67/0m AECM-86/0A00 ID 'C027 02/02/67 / / ROUTINE REFORT CLBMIT SEM!-ANNUAL RE; ORT TO N C D" FILING MONTHLY INTEFNAL AECM-A7/2-00^1 NLSAF 2.A EWIR3 MENTAL FF3?ECIDN FR6 GRAM REPORTS.

ID 60522 02/C4/37 05/22/81 SECURiff RiMIT CLARIFICATION LETTER ON !ECLAITY TRAINING AECM-37/0006 FMI-51/13I5 WALIFICATION FLAN TO REGION II.

ID700:0 02/04/S7 10/le/36 C SFIFM "EASURE E!9IfAECMDCUMFNTINGFESULTS0FTRITIUMCONFIR"ATORf I AECM-87/02I3 MAEC-ei!T:0 "EAsrFE9ENis8008AMINVESTIGAi!0N. j ID 70214 '

02/06/s7  !!/0!!81 HfU0GENCCN!OL ';"I! in M0 ?#8TE8tY STATJe EENET ON *:EG8A:EDCCFE AECM-47/3015 MAEC-44/0367 A:CI;ENT stW6EN CONIFOL FROGRAf F:n diH GR;ER,146 ID 70292 02/06/87 01/08/i7 LER SCB9IT LER CONCEFNING INVALID SAMFLES TAtEN FFOM 0FF GAS AECM-07/002) IR 87-1-2 FFETREAIMENT SYSTEM TO NRC.

!D 70029 1

02/10/87 / / FERS%NELEXFOSURE SUBMITANNUALFERSONNELEtF0SbREANDM:iNITORINGFEFORTTO AEC" 37/0027 NLSAF 2.4 NRC.

ID 6lm l 02/13/87 01/05/87 WA!TE CI!P;!AL sh'.'EST AF5F0 VAL FOR REGISTERED CA!IS FEM N'C.

AECM87'0002 FMI 97/0405 D '00:2 7

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.:::::::: :::::: ::::::::  ::::::::::::::: :::::s:::: .::::::  :::::::::::- :::::::::::::::::::::: .::: : :::: ::::::.::::

02/18/37 11/26/66 UCh4 50.54 REFORT SUEMIT UCNR 50.59

SUMMARY

REF00 TO MC AECM-67/0019 AECM-86/0:82  !

ID 70023 02/18/87 02/26/E6 Uf!AR NRC ACTION FREFARE AND SU!MIT UFSAR ' FACILITY CHA%E' LISTING TO NcC.

AECM-87/0019 NLSAF 2.16 ID60482 02/23/67 01/15/07 SALPRESFONSE WSMIT TO NRC SERI COMMENTS ON SALF CEFCRT FOR GSNS AECM-87/0042 MAEC-87/0009 ID 70293 02/24/87 02/01/87 AS"E CODE N343 SUEMIT AECM TO M C 8ECUESTING AcFR N AL FOR USE OF A!ME C JE AECM-8'/000 FMI47/0:56 CA!E N34:

D 'CO'3 02/2'/E 7 // R.iUTINE FEFe8.T U!MIT !E9I-AW.'AL EFFLUENT C! LEASE RiFORT 70 MC AEC M 7/0:50 NLSAP 2.4 ID 60458 02/27/87 02/03/S7 LER SU!MIT LER CONCERNING SFUPIOUS SIA8.1 V 'A' C;NTL 'iOM AECM-87/0043 IR67-2-1 HVAC SYSTEM T0 NRC.

D 70072 C2/27/57 02/17/87 ANNUAL 0FER FEFORT ?U5917 AECM TRAN?MIfii% 15S6 AWJAL tFE8Ai! % RE8 Mi.

AECM7/%47 FMI87/1245 ID 70;14 03/02/37 11/25/E6 CONIAIk"ENT FUGE F80 Vite A ;ESF3?E TO NEC FEV.'EST F?C GCliPNA'. IWMAi!0N AE;"??!%:2 MfMe/02S1 CONCEFN! % THE C6NT. FU ME EEFORT (A!:H 6/023'I.

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ID70061 l 0:!C2/87 02/10/87 FEQUAL EXAM AECM SUIMIT AECM ON RESF0NSE TO RESULTS OF NFC RECUAL EtAM.  !

AECH7/0076 FMI-87/C893 10 70071 l

07/02/87 02/12/87 R0/!F0LIC.AFFLS !UlMlfAFFLICATICNSFORR0/SR0LICENS!!FORMAY1297E4At AECM7/3043 FMI67/CS00 i ID ' P5 l l

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!D 70137 03/11/87 11/07/86 IRAININGINSP SUEMIT TO NRC ADDIi!0NAL MFORMAi!0N TO DISCUSS & CLARIFY AECM-87/0051 MAEC-e6/0376 $UBJECT FROCESSES INVOLVED IN TRAINING AREA ID 70204 03/11/87 02/13/S7 "NCR REDUCi!0N !LEMIT AECM TO F0DIFY C0MMITMENTS C0NCERNING TFE MNCF AECM-87/0052 MH7/000A REDUCTIONFROGRAM.

ID 70113 03/l:/S7 / / R?UTINE8EFORT 3UIMIT "0NTHLY REF^.RT F00 M: NTH 0F "ARH.

AEC"-S?/?M Y.!A5 2.2

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03/1o/87  ?!S / / 'RANSFORT CA!IS ?l8MIT AICM 70 FIGISTE: AS A U?E8 6f Vi A * !*NSFC'8I CAIES.

AECM-67/0053 100FR'l-12 ID 70215 03/17/87 TES 02/27/87 m uAL 0F. #EFORT *F"IfAECMTFN"ITf!NG!!!0.00AFFLICATI:N FEE FOR AECM-27/0N4 AE:P f l0047 8it.E!i M !.!CM-87/3047 ID 70216 03/19/87 / /  :.ER ."!MIT TO NGC FhAL 5.E:0Ri CN LCW FL%$ TO C:F!sMCCCLERS AECM-87/00t3 1 AND RELATED MAliERS

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0 /15/97 C:ll3/i' -2';4 S;!LL CJi"It8E!KNSET'NtC*ErJE!iF0RA:D!!!:NALINF08"Ai!0N AECM-67/C:e MAEC-8?l:93 *! Gait!G THE SULFURIC ACID ! PILL OF 3/22/67 IL.'0127 07/20/8' 1:/!Neo  %; hi0 FE)L'EST .i"If LETi!4 FFM! SING (80A*ED hF'/t " Ail:W CA!NG AECM67/;U$ AECN-ae/ 0 5 h!FECihh5uFAUCHEMv!AtSHRINItyilh3.

10t!!S1 0!/20/87 12/IS/86 ENY QUAL AArCHEM 880V!tERERRfAl!LlifIETERMMAi!040FASFOUNDC00!il:1 A!CM-87/0045 A!CM-86/0409 0F RAfCHEM !EALS TO NRO.

ID70026 03/23/07 12/02/86 RULE pal!NG !LIMITC?M"ENTSONA%FRUNLOWLEVELbaifE.

AECM-87/0059 $1FR433e ID70212 03/24/07 02/25/67 L!R  :;t"If LE8 CnNCE:NI 6 10iH ti;T FILTER isA h5 IEING ACCM-47/0070 !P8?2-4 NFE8AILECONOM8ENTLYTONRC. I ID701:8

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NFil NUCLEAR LICENSING 1 $AFETY DATE: 04/;0/S7 ACTION TRACI!NG MANAGEMENT SYSTEM RECENTMPILLICENSINGACTIVITIES FAGE: 4 SUIMITIAL IATE NRC REQUESTDATE MFil CORRE$. NUM RESFONSE MFil CORRES. NUM TOPIC 0F SUBMIffAL DE!CRIFi!0N MFilIDNUM HEEDED TACNUMBER

t: ::::.::: :::::::: :::::::::::::::: ::::::::::::::::::  ::::: :::::::::::::::::.::::::;: : : ::. .: - : - :: .-

03/27/37 02/27/87 LER SUBM!iLERCONCERNINGIN0PF11 AJE3 CAJIED !r Aw!VER$ARY AECM-87/0072 IR87-2-6 DATEMISTAIENLfCHANGED10hRC ID 70204 03/31/37 03/16/87 FSAR-MINERAL RTS SL'BM!i TO NRC SUFFLEMENTAL lhFARMAi!0N 0N F!AR ERF05$ -

AECM-87/0073 Mf!87 REGARDING PROFERTY L M!hERAL RIGHTS W hER!HIF INVESf! GAT!cN ID 702'6 01/01/87 // ROUTINE REPORT SUIMIT ANNUAL REPORT OF M SITE FR0FERTY DAMAGE INSUFANCE AECM87/C071 NLSAP2.4 TO NRC.

ID 60'09 04/01/37 03/05/87  ! FECIAL REFORT $UEMIT!RCMCEFNINGDIV.!03^UTFUtIFE4tEP0FENING AECM-U/r4 IR87I-2 OUR!% t'.'RV!!LLANCE in N80 ID 70217 04/0!!s7 YES 02/11/87 ATWS NL TO !"lMIT RESF R!ES TO NRC CESAFDING THE RA! AB0UT ATWS l AECM-87/C55 MAEC-87/0039 RULECr9FLIANCE.

ID 7Me*

, 04/06/87 0*/13/37 F)!i8801!UTEST FFEtATE AO !U!M!i AECM TFAM9ffi!G AE! ULT! 0F 80!i RF01 l A!CM-87/D0e? FMI871600 $fARTUPTESTA0f!V! TIES.

10702P 04/07/87 05/18/65 FIREFAAtt! ANAL $UlMIT IwE SE M PED HEV. 1) FICE 'A Att! A6AL*!!! Ti htC.

A!CM 67/0T3 AECM85/0!(4 ID 7C016 1

04/03/87 05/05/66 151SUMMART $UIMIT THE !$1

SUMMARY

FEF0Ri 10 IFE Nic W!iw!N 'O DAt!

AECM87/00'6 FMI66/3414 ArtER TWE OUTA3E IN ACC(t!ANCE kits A!ME C::[ SE0tttN XI.

IDe0520 Ali!CLEIWA0:0.

04/N/27 08/27/n t!EN3ECN.04 RE KE!T R.ETION 4 LIO. 2.01201 W!im N N car! ta' .L<.1!%

AECM 87/00S! MAEC-56/026o PE51 ART FRGM Ar01.

1061157 04/0*/87 02/26/87 INTERFACEUl/U2 Si.'IMIT TO NRC FESPON!E TO RECEhi EVENf 3 FELATED TO AECM-87/0077 NRCMEETING INTERACTIONOFACT!V!i!E5A330CIATEDW!iHGGN$2ON6FERA!I%

l 10 70297 FLANT, GGNSI l

04/20/87 // ILS $UlM!i !LS EVALV4i!CN 10 htC FER MFil RESPNE 10 GL 65 OL AECM 87/0009 AECM85/0233 ID 60903 l

t l 04/21/87 03/18/87 LER $UIM!i LER TO NRC CONCERN!% !!W 10F t'.'E T3 F0$f0L4 FED AECM87/00s? 1R 97 $ $!CLE FA[LU!E C)ULD CAg!! A LO$$ OF !!W thyENidf.

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. MFLL NUCLEAR LICEN3!NG l SAFEff DATE: 04/30/67 ACTIONTRACt!NGMANAGEMENT313 FEM FECENTMFilLICEN3143 ACTIVITIES FAGE: 5

::: ::::- ::: :::::::- :: ::::::::::::: *::::: ::::: :* ::  ::::- .:::::::: :: : ::* ::::::: :::::e :: .::::::.::: i

$UIP!ITALDATE NEC REQUESTCATE "Fil C'4FES. NV" FE!P0NSE MFil CORFE!. NUM T6PIC (F !UBM!iiAL DESCRIFi!0N M'll ID WM hE!DED TAC NL"!ER e

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Os/22/0? C4/14/07 $'jFP.$R0/R0 INFO  :::::::::::- ::: :: :n re ::\N $A0/R0 CANDIDATE SUIMITADD!!!0NAL[hT0AMAi!0N AECM-87/00% PMI87/2383 ACCDRDANCE WIIP IEC REQUE$f, ID 70237 04/23/R7 0?/22/85 EGNS2CPElf PROVIDE NEW ESTIMATE TO NRC FOR C0MFLEi!CN OF GGk! 2, IN A!CM87/2-0002 MAEC-85/028) $UFF0Af0FN8CSEVIEW0FREQUESTtoEITENDCP, D 5!!79 04/24/67 / / APP N IX J $UIMIT CMMENTS ON FA0 POSED AFFEhDIX J IEV!$10N AND AN AECM-67/0063 FMI6e/8737 AELATEDDRAFTREG.GU!CETA$tMS0215.

1 ID70282 04/24/67 04/CS/S7 0FER REGUAL FROG t'.'!MIT AECM $TAllhG !ER!s INTENT 10 t'FDATE Tr! 0FER FEsAL I A!CP-37/XE4 "LCEE;UE57 FOGRaiIAWIHEREv!!!DF4RT!5. ,

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