ML17250B077

Provides Info Re Status of USI Requirements,Per Generic Ltr 89-21.Status of Issues Encl

ML17250B077
Person / Time
Site:	Ginna
Issue date:	11/27/1989
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
REF-GTECI-MI, REF-GTECI-SC, TASK-***, TASK-OR GL-89-21, NUDOCS 8912050119
Download: ML17250B077 (8)

Text

ACCELERATED D UTION DEMONS TION SYSTEM f 'e P Y~

REGULATORY XNFORMATXON DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8912050119 DOC.DATE: 89/11/27 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. Project Directorate I-3 R

SUBJECT:

Provides info re status of=-USI requirements,per Generic Ltr 89-21.

DXSTRXBUTION CODE: A012D COPIES RECEIVED:LTR ENCL SIZE: D TITLE: Generic Ltr 89-21 Response,Xmplementation of Unresolved Safety Xssue S

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244

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RECXPIENT COPIES RECIPIENT COPXES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 PD 1 1 JOHNSON,A 1 D INTERNAL: BARBER G PTSB 1 1 NUDOCS-ABSTRACT 1 1 D L 01 1 1 WESSMAN1R PD13 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 D

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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP, US TO REDUCE WASTEl CONTACI'HE.DOCUMENI'ONTROLDESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISHUBUTION LISIS FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9

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ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 November 27, 1989 TELEPHONE AREA CODE Tla 546-2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555

Subject:

Response to Generic Letter 89-21

, Status of Unresolved Safety Issue, Requirements R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

By Generic Letter 89-21 from James G. Partlow, dated, October 19, 1989, you requested information regarding the status of unresolved safety issue requirements. The attachment to the October 19 letter has been marked to show the status as requested and is enclosed with this letter.

Very truly yours, Robert C. Mec y General Manager Nuclear Production JRJK069 Enclosure xc: Mr. Allen R. Johnson (Mail Stop 14D1)

Project Directorate I-3 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior, Resident Inspector 8912050 119 S91127 p PDO CK 0500024+ > \

PDR PDC P

ENCLOSURE 1 UNRESOLVED SAFFTY ISSUES FOR WHICH A FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVED US I/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* REMARKS A-1 Mater Haraner SECY 84-119 All C/Mar 1984 NUREG-0927 NUREG-09?7, Rev. 1 SER Dec 20, 1979 NUREG-0993, Rev. 1 NUREG-0737 Item I.A.2.3 SRP revisions A-2/ Asynmetri c Bl owdown NUREG-0609 PWR C/Sept 1986 NUREG-0609 HPA A-3 0-10 Loads on Reactor Primary Coolant Systems Westinghouse Steam GL 84-04, NUREG-0844 GDC-4 W-PMR C/Sept 1988 GL 84-04 NRC Ltr Sept NUREG-0844 9, ~

Generator Tube Integrity SECY 86-97 T.S. Aaandrrent I35 SECY 88-F72 Apr 24, 1989 GL 85-02 (No requirements)

Cf 'Steam Generator Tube NUREG-0844, SECY 86-97 CE-PWR N/A Integrity SECY 88-272 GL 85-02 (No requirements)

A-5 HEW Steam Generator NUREG-0844, SECY 86-97 RAM-PWR N/A Tube Integrity SFCY 88-272 GL 85-02 (No Requirements)

E A-6 Hark I Containment NUREG-0408 Hark I-BWR N/A Short-Term Program

• C - COMPLETE NC - NO CHANGES NECESSARY NA - NOT APPLICABLE I - INCOMPLETE F. - FVALUATING ACTIONS REQUIRED

US I/MPA NUMBFB TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* REMARKS A-7/ Mark I Lonq-Term NUREG-0661 -

Mark I-BWR N/A .

n-01 Program NUREG-0661 Suppl. 1 GL 79-57 A-8 Mark II Containment NUREG-0808 Mark I I-BWR N/A Pool Dynamic Loads NUREG-0487, Suppl. 1/2 A-9 Anticipated Transients Without Scram NUREG-0802 SRP 6.2.1.1C GDC 16 NUREG-0460, Vol. 4 10 CFR 50.62 Al 1 C/Mar 1989 SER Mar 16,1989 I

A-10/ BWR Feedwater Nozzle NUREG-0619 ,'N/A MPA 8-25 Cracking Letter from DG Eisenhut dated 11/13/80 GL 81-11 A-11 Reactor Vessel Material NUREG-0744, Rev. 1 All C/Oct 1982 MHKG-0744, Rev. 1 Touohness 10 CFR 50.60/ T.S. Amendrrent N15 82-26 June 12, 1986 A-l2 Fracture Toughness of NUREG-0577, Rev. I C/June 1978 RG&E Ltr June 26, 1978 Steam Generator and SRP Revision MJREG-0577, Rev. 1 Reactor Coolant Pump 5.3.4 NUREG-0944 Supports 1.GL 88-20, Supp 1 Response (IPE) inc A-17 Systems Inter actions Ltr: DeYoung to A>l ocmnit to perform licensees - 9/72 internal flooding anal NUREt.,-]174, NUREG- 2.NUT-0737 Item I.C.5 1229 NUREG/CR-3922 completed per Procedure NUREG/CR-4261, NUPEG/ A-1404, Jan 13, 1981 CR-4470, GL 89-18 (No requirements) 1. Inspectian 87-03

2. RG&E response, A-24/ Qualification of Class NUREG-0588, Rev. 1 All Mar 6, 1987 HPA B-60 lE Safety-Related SRP 3.11 3.Insp Rpt, June 11, 1987 Equipment 10 CFR 50.49 4.EEQ C1oseout Insp 89-24 GL 8 -09, GL 84-24 5.Insp Rpt not issued GL 85-15

US I, NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE+ R FMAR KS A-26/ Reactor Vessel Pressure DOP, Letters to PWR GL 88-11/Itty3.event.

NPA B-04 Transient Protection Licensees 8/76 Ltr fxan RG&E NUREG-0224 Jan 23, 1989 NUREG-0371 Estimate Conformance 5.2 'RP Date of May 1991 GL 88-11 A-3> Pesidual Heat Removal NUREG-0606 All OLs After N/A Shutdown Requirements RG 1.113, 01/79.

RG 1.139 SRP 5.4.7 A-36/

C-10, Control of Heavy Loads Near Spent Fue>

NUREG-0612 SRP 9.1.5 Al 1 C/June 1985 Phase 1 Saa Jan 18, 1984 e

C-15 GL 81-'07, GL 83-42, Phase II Not Req'd GL 85-11 Per GL 85-11 Letter from DG June 26, 1985 Eisenhut dated 12/22/80 A-39 Determination of SPV NUREG-0802 BWR N/A Pool Dynamic Loads tgREGs-0763,0783,0802 and Pressure Transients NUREG-0661 SRP 6.2.1.1.C A-40 Seismic Design SRP Revisions, NUREG/ All Integrated Into Criteria CR-4776) NUREG/CR-0054, QBI A-46 Resolution NUREG/CR-3480, NUREG/ (SHRUG)

CR-1582, NUREG/CR-1161, NUREG-1233, NUREG-4776 NUREG/CR-3805 NUREG/CR-5347 NUREG/CR-3509 A-42/ Pipe Cracks in Boiling NUREG-0313, Rev. 1 BWR N/A HPA B-05 Water Reactors XUREG-0313, Rev. 2 GL 81-03, GL 88-01

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~UMIUER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* REMARKS A-43 Containment Emergency NOR EG-0510, C/Dec 1985 GL 85-22 Exc1uded Operating Performance 'ump

'tUREG-0869, Rev. I Reactors lcm Requireaants

. NUREG-0897, R.G.I.BP of Reg Guide 1.82, Rev. 1 (Rev. 0}, SRP 6.2.2 GL 85-22 No Requirements RG&E Apr 17, 1989 Res to 10CFR50.63 Stated 'Xt.

A-44 Station Blackout RG 1.155 Al 1 Mods/Procedure Chngs to NUREG-1032 Completed in 2 Years After NUREG-1109 Accept by Director, Office 10 CFR 50.63 of Nuclear Regulation A-45 Shutdown Decay Heat SECY 88-260 Al 1 In Accordance with GL 88-20, Removal Requirements NUREG-1289 Supp 1, USI A-45 to be NUREG/CR-5230 Assessed as Part of PRA/IPE SECY 88-260 (No requirements}

A-46 Se~smic gualification NUREG-1030 Al 1 RG&E Ccmnitted to SQUG of Equipment in NUREG-1211/ Methodology per Ltr of Operating Plants GL 87-02, GL 87-03 May 26, 1987 A-47 Safety Implication NUREG-1217, NUPEG- Al l Ginna not Explicit1y R o~ Control Systems 1218 in GL 89-19 as Requirin GL 89-19 Changes, GL is Being Reviewed. Scheduled Response A-48 Hydrogen Control 10 CFR 50.44 All, except N/A Date is Nar 19, 1990.

Measures and Effects SECY 89-IP2 PMRs with o< Hydrogen Burns large dry Ginna Has Large on Safetv Equipment containments Dry Containment A-49 Pressurized Thermal RGs 1..154, 1.99 PWR C/Nov 1986 NRC Ltr wLth Safety Shock SFCY 82-465 Evaluation of Nov 17, 1986 SECY 83-288 SECY 81-687 10 CFR 50.61/

GL 88-11

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