ML17263A997
| ML17263A997 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/24/1995 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9503310291 | |
| Download: ML17263A997 (4) | |
Text
P 8.163R.I EY' (ACCELERATED RIDS PROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NOR:9503310291 DOC.DATE: 95/03/24 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 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-1 (PD1-1)
(Post 941001)
SUBJECT:
Informs that util intends to implement formal industry position on severe accident mgt approved by Nuclear Energy Inst Nuclear Strategic Issues Advisory Committee on 941104.
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ANn ROCHESTER GASANDEIECTRIC CORR7RATION ~ 89EASTAYENUE, ROCHESTER, N. Y Idbf9000I AREA CODE716 546-2700 ROBERT C. MECREDY Vice President Nvctear Operations March 24, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-1 Washington, D.C.
20555
Subject:
Severe Accident Management R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
The purpose of this letter is to inform you that Rochester Gas and Electric intends to implement the formal industry position on severe accident management approved by the Nuclear Energy Institute's Nuclear Strategic Issues Advisory Committee on November 4, 1994.
That formal position, previously communicated in a letter dated November 21,
- 1994, from NEI to the Director, Office of Nuclear Reactor Regulation, stated that:
Each licensee will:
Assess current capabilities to respond to severe accident conditions using Section 5 to NEI 91-04, Revision 1, "Severe Accident Issue Closure Guidelines."
Implement appropriate improvements identified in the assessment, within the constraints of existing personnel and hardware, on a schedule to be determined by each licensee and communicated to the NRC, but in any event no later than December, 31, 1998.
Based on previous interactions between NEI and NRC staff, we understand that NRC staff agrees with the need for licensee flexibilityin their methods of assessing and establishing severe accident management guidance.
Utilizing the associated implementation guidance (contained in NEI Report 91-04, Revision 1),
we intend to complete the assessment of severe accident management capabilities and make any identified enhancements by the December 31, 1998 date.
- However, we are actively pursuing completion of these tasks in 1997.
A team of individuals comprised of Operations, Engineering,
- Training, and Emergency Planning has been established and an initial plan devised.
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This implementation schedule is complementary to efforts currently"underway to address the individual plant examination of exterhal events (IPEEE).
Ver Truly Yours, Robert C.
Mec edy GAH'II,368 xc:
Mr. Allen R. Johnson (Mail Stop 14D1)
Project Directorate I-1 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 U.S.
NRC Ginna Senior Resident Inspector