ML17262B078
| ML17262B078 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/03/1992 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-1407 GL-87-02, GL-87-2, GL-88-20, NUDOCS 9211090152 | |
| Download: ML17262B078 (5) | |
Text
ACCELERATED DISTRIBUTIONDEMONSTRATION SYSTEM
SUBJECT:
Lists summary of util positions re three facets of IPEEE,per util 911226 response to GL 88-20,Suppl 4
a 920921 response to GL 87-02,Suppl 1 re seismic events. Fire PRA will be performed using guidance in NUREG-1407,Section 4.1.
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2 TITLE: Generic Ltr 88-20 re Individual Plant Evaluations I
S 05000244 /
A NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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I ACCESbION NBR:9211090152 DOC.DATE: 92/ll/03 NOTARIZED: NO 'OCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.K~V'4E AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
! Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSONPA.R.
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IIu(zzssz ROCHESTER GAS AND ELECTRIC CORPORATION ROBERT C. MECREDY Vice President Cinne Nudeer Production a aar oar ~
89 EAST AVENUE, ROCHESTER N. Y. 14649-0001 7B.EPHONE AREACODE 7t B 546-2700 November 3, 1992 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555
Subject:
Individual Plant Examinations. for External Events (IPEEE)
R.E.
Ginna Nuclear Power Plant Docket No. 50-244 Ref. (a):
Letter from R.
C. Mecredy, RG&E, to A. R. Johnson,
- NRC,
Subject:
IPEEE, 180-day Response to Generic Letter 88-20 Supplement 4, dated December 26, 1991 (b)
(c):
(d):
Letter from R.
C. Mecredy, RG&E, to A. R. Johnson,
- NRC,
Subject:
Response
to Generic Letter 87-02 Supplement 1
(SQUG) and Generic Letter 88-20 Supplement 4,
(SEISMIC EUENTS), dated September 21, 1992 Letter from A. R. Johnson, NRC, to R.
C. Mecredy, RG&E,
Subject:
Review of Response to Generic Letter 88-20 Supplement No.
4 Individual Plant Examinations for External Events, dated June 30, 1992 Letter from D. M. Crutchfield, NRC, to J.
E. Maier, RG&E.
Subject:
Integrated Plant Safety Assessment Report (IPSAR), Section 4.5, Plant Flooding by Deer Creek, dated August 19, 1983.
Dear Mr. Johnson:
In RG&E's letter of December 26, 1991 Reference (a), responding to Generic Letter 88-20, Supplement 4,
we provided our approach to resolution of the issue of Individual Plant Examinations for External Events (IPEEE).
Our response was divided into three categories:
Internal Fires; Seismic; and High Winds, External
- Floods, and Transportation Accidents.
Additional detail was requested by the NRC in Reference (c).
A summary of our positions regarding these three facets of the IPEEE are provided below:
1.
Internal Fires:
As stated in Reference (a),
we are planning on performing a fire PRA using the guidance of NUREG-1407, Section 4.1.
OSOosj 2.
Seismic:
A more detailed description regarding our seismic IPEEE plans was provided by letter dated September 21, 1992 Reference (b), in response to the NRC's June 30, 1992 request for additional information (Reference c).
We described our I
9211090!52 921-103 PDR ADOCK 05000244
plans for int grating our resolution of
- SI A-46 (SQUG) with the seismic IPEEE.
3s~
Hi h Winds External Floods and Trans ortation Accidents:
In accordance with Section 5
of NUREG-1407, a
progressive screening approach was performed for this part of the IPEEE analysis.
This progressive screening was performed during the Systematic Evaluation Program (SEP) and consisted of perform-ing a comparison of the design of'inna Station against the criteria in the Standard Review Plan (NUREG-75/087).
Within that a'ssessment, it was determined that:
'a ~
for high winds, Ginna Station can withstand a 10" tornado within design limits, and a 10~ tornado without structur-al failure.
This is considered to meet Section 5.2.4 of NUREG-1407.
b.
for external flooding, a Probable Maximum Flood with a recurrence interval of 5X10~ was used as the basis for modifications to Ginna Station.
These modifications were judged to provide the necessary protection from this
- event, consistent with 10CFR50.109, as described in the NRC's Safety Evaluation Report of August 19,
- 1983, Reference (d).
This is considered to meet Section 5.3 of NUREG-1407.
c.
for transportation accidents, the SEP Topic II-l.C SER concluded that the Standard Review Plan was met.
This is considered to meet Section 5.2.3 of NUREG-1407.
Based on this progressive screening approach performed as part of the
In accordance with Section 5.2.3 of NUREG-1407, RG6E will perform a walkdown to assure that no potential plant vulnerabilities were excluded in the original design basis analysis.
This walkdown/evaluation will be completed by May 22, 1995.
A copy of any of the Safety Evaluation Reports for the above-listed SEP topics is available for review by the NRC staff, if desired.
Ver truly you s, obert C. Mecredy GJW/262 xc:
Mr. Allen R. Johnson (Mail Stop 14D1)
Project Directorate I-3 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector