ML17264A285
| ML17264A285 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/04/1995 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9512120378 | |
| Download: ML17264A285 (4) | |
Text
,PRIC)RI EY (ACCELERATED RIDS P ROCESSli REGULATORY INFORMATXON DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9512120378 DOC.DATE: 95/12/04 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.
SUBJECT:
Proposes amend to improved STSs re maint of containment function during fuel movement inside containment,per 951117 meeting. License amend application will be submitted by 960110.
DISTRIBUTION CODE:
AOOID COPIES RECEIVED:LTR l ENCL ~
SIZE:~
TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 RECIPXENT ID CODE/NAME PDl-1 LA JOHNgQN~
INTERNAL LE CENTER 0
NRR/DRCH HICB NRR/DSSA/SRXB OGC/HDS3 EXTERNAL: NOAC COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL Y'OTE TO ALL"RlDS" RECIPIENTS; PLEASE IRELP US TO REDUCE iVKSTE!COYTACT'IHE DOC!:WIEYTCONTROL DESK. ROOM Pl-37 IEXT. 504-0083 ) TO ELIAII.PATE YOUR HAMIL' f<OiI DISTRIBUTIONLIS'I S FOR DOCUNIEY,'I'S YOU DOY,"I'IED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 12 ENCL 11
AND ROCHESTER GASANDElECTRIC CORPORATION ~ 89 EASTAYEhlUE, ROCHESTER, MY 14649-0001 ARFA CODE 716 5'-2700 ROBERT C. MECREDY Vice President Nvdeor Operations December 4,
1995 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-1 Washington, D.C.
20555
Subject:
Conversion to Improved Standard Technical Specifications R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
In our meeting of November 17, 1995 concerning the conversion to the Improved Standard Technical Specifications for Ginna Station, the question of maintaining containment function during fuel movement inside containment was discussed.
As a result of your decision to disallow our proposed option to relocate these containment requirements during fuel movement outside of the technical specifications (since no credit is taken for containment in the accident analysis),
we are proposing an alternative option.
This alternative is to pursue the option described below as an Amendment to the Improved Technical Specifications after they are approved.
RG&E will define containment function, as related to mitigation of a fuel handling accident, as follows:
CONTAINMENT FUNCTION:
Capability of containment to maintain radiological consequences well within (i.e.
< 75 rem thyroid) Part
- 100, assuming:
RG 1.25 analysis methodology; conservatively calculated containment. penetration closure times; and conservatively calculated containment leak rates, once closed.
The details of the conservative calculations remain to be discussed.
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I We plan to submit this license amendment application by January 10, 1996.
It is needed to be
- approved, and effective, by April 1,
- 1996, so that it can be used during our Steam Generator replacement outage. It is estimated that this amendment, if not approved, will extend the duration of the outage by three full days.
Very truly yours, GJW5410 Robert C.
Mec dy xc: Mr. Allen R. Johnson (Mail Stop 14B2)
Project Directorate I-1 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector
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