ML17264B035
| ML17264B035 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/16/1997 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17264B037 | List: |
| References | |
| GL-88-20, TAC-M74414, NUDOCS 9710020017 | |
| Download: ML17264B035 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 16, 1997 Dr. Robert C. Hecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REVIEW OF R.
E.
GINNA NUCLEAR POWER PLANT INDIVIDUALPLANT EXAHINATION (IPE)
SUBHITTAL INTERNAL EVENTS (RESPONSE TO GENERIC LETTER 88-20)
(TAC NO. H74414))
Dear Dr. Hecredy:
Enclosed is the
NRC Staff Evaluation
(SE) Report for the Ginna IPE submittal for internal events and internal flood.
Also attached with the SE is the contractor's Technical Evaluation Report (TER).
A "Step 1" review of the Ginna IPE submittal was performed which examined the IPE results for their "reasonableness" considering the design and operation of Ginna.
The staff employed Brookhaven National Laboratory to review the front-end analysis, human reliability analysis (HRA), and back-end analysis of the IPE submittal.
Their TER is attached as an appendix to the SE.
This TER was reviewed by the IPE "Senior Review Board" (SRB) as part of Office of Nuclear Regulatory Research quality assurance process.
The SRB is. comprised of RES staff and consultants at Sandia National Laboratories with probability risk assessment expertise.
A more detailed review, a "Step 2" review, was not performed for this IPE submittal.
The SE is based on the revised IPE submitted on January 15,
- 1997, which included front-end and HRA sections.
Despite the fact that the back-end and internal flood results have not been provided, you have responded to our request for additional information (RAI) which covered all areas of the
- IPE, including the back-end.
The information gleaned there, coupled with our review of the original IPE back-end, enabled us to conclude that the back-end portion is equally acceptable.
(PI The IPE has estimated a total core damage frequency (CDF) of 5E-05 per reactor
- year, not inclIIding the contribution from internal flooding which will be provided at a later date.
Loss-of-coolant accidents (LOCAs) contribute 59
- percent, steam generator tube rupture contributes 16 percent, station blackout contributes 12 percent, transients contribute 9 percent, interfacing systems LOCA contributes 2 percent, and anticipated transients without scram contributes 2 percent.
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R. Mecredy September 16, 1997 Based on the "Step 1" review, we conclude that you have met the intent of GL 88-20.
We will not perform a "Step 2" review.
Based on the findings in the enclosed SE, the staff notes that:
(1) your IPE is complete with regard to the information requested by GL 88-20.(and associated guidance in NUREG-1335),
and (2) the IPE results are reasonable given the Ginna design, operation, and history.,
As a result, the staff concludes that your IPE process is capable of identifying the most likely severe accidents and severe accident vulnerabilities, and therefore, that the Ginna IPE has met the intent of GL 88-20.
It should be noted that the staff's review primarily focused on your ability to examine Ginna for severe accident vulnerabilities.
Although certain aspects of the IPE were explored in more detail than others, the review is not intended to validate the accuracy of your detailed findings (or quantification estimates) that stemmed from the examination.
Therefore, this SE does not constitute NRC approval or endorsement of any IPE material for purposes other than those associated with meeting the intent of GL 88-20.
Sincerely, ORIGINAL SIGNED BY:
Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
Safety Evaluation w/attached TER cc w/encl:
See next page DISTRIBUTION:
Docket File PUBLIC PDI-1 R/F B. Boger A. Dromerick S. Little G. Vissing T. Harris (e-mail'E only)
Hermann G. Holahan J.
Flack J.
Lane DOCUMENT NAME:
G: iGINNAiM74414.SER To receive a copy of this document, indicate in the box:
"C" = Copy without attachment enclosure "E" = Co with attachment enclosure "N" = No co OFFICE PH:PDI-1 E
LA:PDI-D:
1-1 IIAME GVissing/rsI SLItt i
A)
DATE 09/ 9'97 09/
/97
/97 Official Record Copy'
4 4e
R. Mecredy
~ 2-Based on the "Step 1" review, we conclude that you have met the intent of GL 88-20.
We will not perform a "Step 2" review.
Based on the findings in the enclosed SE, the staff notes that:
(1) your IPE is complete with regard to the information requested by GL 88-20 (and associated guidance in NUREG-1335),
and (2) the IPE-results are reasonable given the Ginna design, operation, and history.
As a result, the staff concludes that your IPE process is capable of identifying the most likely severe accidents and severe accident vulnerabilities, and therefore, that the Ginna IPE has met the intent of GL 88-20.
It should be noted that the staff's review primarily focused on your ability to examine Ginna for severe accident vulnerabilities.
Although certain aspects of the IPE were explored in more detail than others, the review is not intended to validate the accuracy of your detailed findings (or quantification estimates) that stemmed from the examination.
Therefore, this SE does not constitute NRC approval or endorsement of any IPE material for purposes other than those associated with meeting the intent of GL 88-20.
Sincerely, ORIGINAL SIGNED BY:
Guy S. Vissing, Senior Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
Safety Evaluation w/attached TER cc w/encl:
See next page DISTRIBUTION:
~Docket File~
PUBLIC PDI-1 R/F B. Boger A. Dromerick S. Little G. Vissing T. Harris (e-mail SE only)
Hermann G. Holahan J.
Flack J.
Lane DOCUMENT NAME:
G: iGINNAiM74414.SER To receive a copy of this document, indicate in the box:
"C" = Copy without attachment enclosure "E" = Co with attachment enclosure "N" = No co OFFICE PM:PDI-1 E
LA:PDI-D:
I-1 Gvissing/rsI SLitt i
A)
DATE 09/ 5I'97 09/
/97
/97 Official Record Copy
Dr. Robert C. Hecredy R.E.
Ginna Nuclear Power Plant CC:
Peter D. Drysdale, Senior Resident Inspector R.E.
Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road
- Ontario, NY 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. F. William Valentino, President New York State
- Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension
- Albany, NY 12203-6399 Charlie Donaldson, Esq.
Assistant Attorney General New York Department of Law 120 Broadway New York, NY 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 7336 Route 31
- Lyons, NY 14489 Hs. Nary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness ill West Fall
- Road, Room 11 Rochester, NY 14620 Hr. Paul Eddy New York State Department of Public Service 3 Empire State
- Plaza, Tenth Floor
- Albany, NY 12223