ML17255A804

Informs That Significant Fire Protection Features Installed Inside Containment,Per App R Interim Actions Identified in 840409 & 17 Ltrs

ML17255A804
Person / Time
Site:	Ginna
Issue date:	04/27/1984
From:	Kober R ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
NUDOCS 8405040229
Download: ML17255A804 (6)

Text

REGULATOR NFORMATION DISTRIBUTION b TEN (RIDS)

ACCESSION NBR ~ 8405040229 DOC ~ DATE ~ 84/04/?7 NOTARIZED NO DOCKET FACIL:50 244 Rober t Emmet Gi nna Nuclear P) ante Unit lt Rochester 6 05000244 AFFILIATION KOBERrR ~ If'ochester AUTH INANE REC IP ~ NAME AUTHOR RECIPIENT Gas & Electric Corp.

AFFILIATION.

CRUTCHFIELDg D ~ Operat.ing Reactors Branch. 5

SUBJECT:

Informs that significant fire.protectjon.features jnstalled inside containmentiper App .R interim actions- identified in

,840409 L 17 ltrs.

DISTRIBUT'ION CODE: A006S COPIES RECEIVED:LTR L ENCL O SIZE:

TITLE: OR Submittal: Fire Protection NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAVE LTTR EN L ID CODE/NAME LTTR ENCL BC 01 INTERNAL: ELD IE FILE 06 IE/WHITNEY L NRR HAMBACH NRR/DL DIR NRR REG FILE EB

'4 FIORAVANT07 09 EXTERNAL: ACRS 11 LPDR 03 NRC PDR 02 NSIC, 05 NTIS TOTAL" NUttIBER OF COPIES REQUIRED: LTTR 19 ENCL 7 J

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t ///////////I// //////I///// ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649 0001 ROGER Wi KO8ER VKE PRESIDENT TELEPHONE ELECTRIC & STEAM PRODUCTION AREA CODE 7IS 546.2700 April 27, 1984 Director of Nuclear Reactor Regulation Attention: Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Subject,: Appendix R Interim Actions R. E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Crutchfield:

Previous RGSE letters dated April 9 and April 17, 1984 described the interim actions that RGSE will take until full compliance with 10 CFR Part 50 Appendix R is achieved. Interim actions inside the containment building were not proposed or addressed in the earlier letters for the following reasons. Significant fire protection features have been installed inside the containment which provide an adequate level of safety. Area fire detection has been provided as well as detection which covers specific hazards. Detection is provided over the reactor coolant pumps and thermister wire detectors are provided in all cable trays that have a significant cable loading. Detection and automatic suppression capability is also provided for the post accident charcoal filters inside the containment'wo manual hose stations have been installed on each floor elevation to provide additional suppression capability. Pire hazards inside containment have been minimized to the extent possible. Each reactor coolant pump motor has been modified to add an oil collection system which will divert any spilled or leaked oil away from hot surfaces and direct it to a collection tank. Only three instrument circuits have been identified as requiring modifications inside containment to achieve compliance with Appendix R. One of these circuits is source range nuclear instrumentation. Boron sampling will provide adequate redundant capability to confirm reactor shutdown at least during the interim period requested in the schedular exemption. The other two circuits are located in a low hazard area separated from piping systems that operate at high temperature during power operation. 'The containment building is generally inaccessible during operation so that the fire hazard resulting from transient combustibles or resulting from modification or construction work is very low. 8405040229 840427 PyaC PDR ADOCK 05000244 PDR F l/p

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April 27, ROCHESTER GAS AND ELECTRIC CORP. SHEET NO. pATE 1 984 To Mrs Dennis M. Crutchfield Therefore, adequate fire protection features have been provided and the existing fire hazard inside containment is sufficiently low such that no interim actions are required. er truly yours, R er W. Kober

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