ML17263A975
| ML17263A975 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/13/1995 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17263A976 | List: |
| References | |
| NUDOCS 9503160204 | |
| Download: ML17263A975 (5) | |
Text
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(ACCELERATED RIDS PROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9503160204 DOC.DATE: 95/03/13 NOTARIZED: NO FACIL:50-244 Robert Emmet, Ginna Nuclear Plant, Unit 1, Rochester G
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:
Forwards request for amend to license DPR-18,proposing rev to TS 4.4.2.4.a to replace specific leakage testing frequencies for containment a.solation valves.
DISTRIBUTION CODE:
A017D COPIES RECEIVED:LTR
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ENCL 2 SIZE:
TITLE: OR Submittal:
Append J Containment Leak Rate Testing DOCKET 05000244 0
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 R
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N NOTE TO ALL"RIDS" RECIPIENTS:
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TOTAL NUMBER OF COPIES REQUIRED:
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AND ROCHESlER GASANDEIECTRTC CORPORATION ~ 89 EASTAYENUE, ROCHESTER, N. Y Idio-0001 AREA CODE716 $6-2700 ROBERT C. MECREDY Vice President hlucteor Operations Harch 13, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-l Washington, D.C.
20555
Subject:
Application for Amendment to Facility Operating License Containment Isolation Valve Testing Frequency Rochester Gas h Electric Corporation R.E.
Ginna Nuclear Power Plant Docket No. 50-244
References:
(a)
NUREG-1431, Standard Technical Specifications, h'estinghouse
- Plants, September 1992.
Dear Hr. Johnson,
The enclosed License Amendment Request (LAR) proposes to revise Ginna Station Technical Specification 4.4.2.4.a to replace specific leakage testing frequencies for containment isolation valves with a reference to 10 CFR 50, Appendix J, as modified by approved exemptions.
This change is required to support the proposed Exemption to 10 CFR 50, Appendix J, Section III, D.3 which is being requested under separate cover to exempt Type C testing of certain valves during the 1995 refueling outage.
Since R8GE expects to exit Cold Shutdown conditions on April 27,
- 1995, we request NRC approval prior to, or on, this date to support the planned Hode'hange.
The proposed application is consistent with NUREG-1431 (Reference a),
LCO 3.6. 1, "Containment."
We request that upon NRC
- approval, this application should be considered effective immediately and implemented within 10 days to provide the necessary training and procedure and program changes.
Very ruly yours, Robert C. Hecre HDFN730
'st503160204 95021K PDR
'ADOCK 05000244 P
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U.S. Nuclear Regulatory Commission Hr. Allen R. Johnson (Hail Stop 14B2)
PWR Project Directorate I-l Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector