NUREG-1364, Requests Review of Results of Inel Risk Estimates & Findings Pertaining to Plant as Summarized in NUREG/CR-5759 & NUREG-1364 (When Published) & Address Potential Vulnerability as Part of IPEEE Per Suppl 4 to GL 88-20

Requests Review of Results of Inel Risk Estimates & Findings Pertaining to Plant as Summarized in NUREG/CR-5759 & NUREG-1364 (When Published) & Address Potential Vulnerability as Part of IPEEE Per Suppl 4 to GL 88-20

ML17250B265
Person / Time
Site:	Ginna
Issue date:	06/24/1993
From:	Andrea Johnson Office of Nuclear Reactor Regulation
To:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
References
REF-GTECI-106, REF-GTECI-NI, RTR-NUREG-1364, RTR-NUREG-CR-5759, TASK-106, TASK-OR GL-88-20, IEIN-89-044, IEIN-89-44, NUDOCS 9306290223
Download: ML17250B265 (6)

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Docket No. 50-244 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055~01 dune 24, 1993 Dr. Robert C. Mecredy Vice President, Nuclear Production Rochester Gas 5 Electric Corporation 89 East Avenue Rochester, New York 14649

SUBJECT:

RISK ASSOCIATED WITH HYDROGEN STORAGE FACILITY AT GINNA As part of the work on Generic Safety Issue 106 (GSI-106),

"Piping and the Use of Highly Combustible Gases in Vital Areas,"

Idaho National Engineering Laboratory

( INEL), contractor to the NRC, performed a scoping study of the risk associated with the hydrogen storage facilities (HSF) for the volume control tank (VCT) and main electric generator at pressurized water reactors (PWRs).

The work performed by INEL was in support of NRC concerns regarding the Trojan plant and the issuance of NRC Information Notice

( IN) 89-44.

In this study, INEL used the separation distances to safety-related structures and air intakes given in EPRI Topical Report NP-5283-SR-A (EPRI Guidelines) which was prepared and approved by the staff for hydrogen water chemistry installations in 1987.

For the GSI-106 scoping study, several plants did not meet the EPRI Guidelines for separation distance criteria and were further evaluated to identify any mitigating factors.

The results identified several plants needing a further more detailed review.

The results of the INEL risk estimates for these plants are summarized in NUREG/CR-5759 "Risk Analysis of Highly Combustible Gas Storage Supply and Distribution Systems in Pressurized Water Reactor Plants",

June 1993.

Specifically, as part of the resolution of GSI-106, the staff has identified a

concern associated with the HSF at the Ginna plant.

The concern relates to the potential impact that the HSF at Ginna may have on the two emergency diesel generators (EDGs) during a seismic event.

If a seismic event were to

occur, a loss of offsite power could occur as a result of the failure of the ceramic insulators on the station transformer.

This would start the EDGs.

This seismic event could also cause a failure of the HSF.

The loss of the EDGs could then result in a station blackout (SBO).

At Ginna, the HSF is adjacent to the end wall of a building with three compartments in line.

The compartment immediately next to the storage area contains a large turbine oil storage tank.

The other two compartments contain the two EDGs.

The failure of the HSF could result in a piping or bottle failure leading to a hydrogen detonation/deflagration.

Due to the limited separation between the HSF and the building wall, the resulting hydrogen accident could impact the operation of the EDGs and the turbine lube oil tank.

The loss of EDGs could thus result in a station blackout (SBO).

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Robert C. Mecredy June 24, 1993 A report entitled NUREG-1364 "Regulatory Analysis for the Resolution of Generic Safety Issue 106: Piping and the Use of Highly Combustible Gases in Vital Areas," providing a cost-benefit analysis and supporting information for the staff's resolution of GSI-106, is currently being prepared by the Office of Nuclear Regulatory Research (RES),

and is scheduled to be published in July 1993.

You are requested to review the results of the INEL risk estimates and findings pertaining to the Ginna plant as summarized in NUREG/CR-5759, and NUREG-1364 (when published) and address this potential vulnerability as part of your individual plant examination of externally initiated events (IPEEE) pursuant to Supplement 4 to Generic Letter 88-20.

Additionally, you should assure yourself that you are"meeting your licensing basis for the EDG.

A more detailed discussion will be forthcoming in NUREG-1364, and will present an opportunity for you to review any proposed modification alternatives involving your HSF that could affect the qualitative/quantitative measures of your risk reduction/achievement calculations associated with your probabilistic risk assessment/IPEEE.

Sincerely, Original signed by:

Allen R. Johnson, Project Manager Project Directorate I-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation cc:

See next page

, DISTRIBUTION:

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Robert C. Hecredy 3une 24, 1993 A report entitled NUREG-1364 "Regulatory Analysis for the Resolution of Generic Safety Issue 106: Piping and the Use of Highly Combustible Gases in Vital Areas," providing a cost-benefit analysis and supporting information for the staff's resolution of GSI-106, is currently being prepared by the Office of Nuclear Regulatory Research (RES),

and is scheduled to be published in July 1993.

You are requested to review the results of the INEL risk estimates and findings pertaining to the Ginna plant as summarized in NUREG/CR-5759, and NUREG-1364 (when published) and address this potential vulnerability as part of your individual plant examination of externally initiated events (IPEEE) pursuant to Supplement 4 to Generic Letter 88-20.

Additionally, you should assure yourself that you are meeting your licensing basis for the EDG.

A more detailed discussion will be forthcoming in NUREG-1364, and will present an opportunity for you to review any proposed modification alternatives involving your HSF that could affect the qualitative/quantitative measures of your risk reduction/achievement calculations associated with your probabilistic risk assessment/IPEEE.

Sincerely, ccc6 Allen R. Johnson Project Nanager Projec Direct ate I-3 Division o eactor Projects - I/II Office of Nuclear Reactor Regulation cc:

See next page

Dr. Robert C. Hecredy R.E.

Ginna Nuclear Power Plant cc:,

Thomas A. Hoslak, Senior Resident Inspector

,R.E. Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road

Ontario, New York 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Hs.

Donna Ross Division of Policy Analysis

& Planning New York State Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223 Charlie Donaldson, Esq.

Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Nicholas S.

Reynolds Winston 8 Strawn 1400 L St.

N.W.

Washington, DC 20005-3502 Hs.

Thelma Wideman

Director, Wayne County Emergency Management Office Wayne County Emergency Operations Center 7370 Route 31

Lyons, New York 14489 Hs. Nary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 111 West Fall Road, Room 11 Rochester, New York 14620

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