ML17250B039
| ML17250B039 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/27/1989 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson Office of Nuclear Reactor Regulation |
| References | |
| GL-88-20, NUDOCS 8911080338 | |
| Download: ML17250B039 (5) | |
Text
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REGULATORY INFORMATION DISTRIBUTION S STEM (RIDS)
ACCESSION NBR:8911080338 DOC.DATE: 89/10/27 NOTARIZED: NO DOCKET. I, FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas a Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3
SUBJECT:
Responds to Generic Ltr 88-20,Suppl 1, "Initiation of Individual Plant Exam for Severe Accident Vulnerabilities."
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ROCHESTER GAS AND ELECTRIC CORPORATION D 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 October 27, 1989 TELCPNONE ARLA CDOGS 710 546.2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate 1-3 Washington, DC 20555
Subject:
Generic Letter 88-20, Supplement No. 1, "Initiation Of The Individual Plant Examination For Severe Accident Vulnerabilities - 10 CFR f50.54(f)"
R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
Rochester Gas
& Electric Corporation (RG&E) is undertaking a focused Level 2 probabllistic risk assessment (PRA) for the R. E. Ginna Nuclear Power Plant.
This PRA will meet the intent of Generic Letter 88-20, "Individual Plant Examination For Severe Accident Vulnerabilities - 10 CFR f50.54(f),"
dated November 23, 1988; Generic Letter 88-20, Supplement No. 1, "Initiation Of The Individual Plant Examination For Severe Accident Vuinerabilities - 10 CFR f50.54(f)," dated August 29, 1989; and NUREG-1335, "Individual Plant Examination:
Submittal Guidance," dated August, 1989.
RG&E has taken the following steps to date to lay the groundwork for the Ginna PRA:
(1)
Two engineers with extensive nuclear PRA experience have been hired as permanent, full-time RG&E employees; (2)
RG&E personnel have participated in industry-wide workshops, including the NRC-sponsored IPE workshop in Fort Worth, Texas; the EPRI IPE workshop in Saint Louis, Missouri; and the EPRI Engineering Systems Analysis Forum in Boston, Massachusetts; (3)
'G&E personnel are actively participating in NUMARC severe accident/IPE/PRA activities, and are currently serving on NUMARC's Ad Hoc Advisory Committee on Other External Events; (4)
Discussions were held with engineering consulting organizations to support the Ginna PRA program.
A detailed request for proposals (RFP) was sent to six potential bidders.
Bids are currently being evaluated by the RG&E PRA staff; (5)
RG&E has collected information on Ginna's operating history, and has categorized reactor trip information to facilitate the selection and quantification of Ginna-specific initiating events; and, (6)
RGB E is currently collecting and evaluating Ginna plant-specific component failure and demand data from January 1, 1980, to December 31, 1988.
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RG8E Response To Gen Letter 88-20 Supplement 1
October 27, 1989 Page 2 of 3 RG8E intends to begin the Ginna PRA on or before January 1, 1990.
The Ginna PRA will be a full Level 1 and focused Level 2 PRA (a Level 2 PRA without plant-specific source term calculations), and will address all appropriate internal initiating events.
The Ginna PRA will not address external initiating events other than internal plant flooding at this time.
RG8E participated in the Systematic Evaluation Program (SEP), which evaluated the impact of most external events at Ginna; we anticipate making extensive use of SEP analyses and results to meet any future NRC requirements for an Individual Plant Examination for External Events (IPE-EE).
The Ginna PRA will utilize the soealled large linked fault tree / small event tree approach described in NUREG/CR-2300, Generic Letter 88-20, and NUREG-1335.
Exact schedules and milestones for the Ginna PRA will not be established until RGSE selects an engineering support consultant.
We have established a goal of completing the Ginna PRA within an 18 to 24 month time frame.
This translates into draft results being available to RGSE on or before January 1, 1992.
RGSE anticipates submitting the final results to the NRC on or before September 1, 1992.
RGRE has established several major goals for the Ginna PRA, including:
(1)
Obtaining a tool that will help achieve corporate goals related to the continuation of safe, reliable, and efficient operation of Ginna; (2)
Giving RGSE the ability to evaluate changes in component and system design, operating and maintenance procedures, NRC licensing requirements, component and system availability, human reliability, Technical Specifications, safety margins identified by deterministic
- analyses, and new information on accident progression, containment
- response, and source terms; and, (3)
Establishing models that will allow the qualitative and quantitative evaluation of failure probabilities, plant damage
- states, and release categories through identification of significant risk contributors.
RGSE has designed a preliminary format for the Ginna PRA to optimize the presentation of inputs, data, models and results to meet our goals.
This format does not completely follow the NRC-suggested format shown in NUREG-1335, Table 2.1.
RG8E will provide the NRC staff, as part of its submittal of the Ginna PRA results, a cross-reference table to assist in comparing the two formats.
Very truly yours, Robert C. Mecredy General Manager Nuclear Production TADi062
RGRE Response To Gen Letter 88-20 Supplement 1
October 27, 1989 Page 3 of 3 xc:
Ms. Donna Ross New York State Energy Office Agency Building 2 Empire State Plaza Albany, New York 12223 United States Nuclear Regulatory Commission Region I
475 Allendale Road King Of Prussia, Pennsylvania 19406 Mr. Charles Marschall, USNRC Senior Resident Inspector R. E. Ginna Nuclear Power Plant 1503 Lake Road Ontario, New York 14519 Mr. R. Wayne Houston, Director, Division Of Safety Issues Resolution United States Nuclear Regulatory Commission Office Of Nuclear Reactor Regulation Washington, DC 20555 Mr. David Modeen Nuclear Management And Resources Council 1776 Eye Street North West, Suite 300 Washington, DC 20006-2496