ML17262A416
| ML17262A416 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/08/1991 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 50-244-89-81, NUDOCS 9103180375 | |
| Download: ML17262A416 (4) | |
Text
ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR: 9103180375 DOC. DATE: 91/03/08 NOTARIZED:
NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Advises of error made in completion date of PRA/individual plant exam. Correct submittal date should be on or before 920901.
DISTRIBUTION CODE:
AOOID COPIES RECEIVED:LTR g ENCL +
SIZE:
TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
DOCKET 05000244 05000244 R
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D RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: NRR/DET/ECMB 9H NRR/DOEA/OTSB11 NRR/DST/SELB 8D NRR/DST/SRXB 8E OC/LFMB E
01 EXTERNAL: NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DET/ESGB NRR/DST 8E2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB NSIC COPIES LTTR ENCL D
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D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP VS TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 18 ENCL A
D D
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ROCHESTER GAS AND ELECTRIC CORPORATION
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o 89 EAST AVENUE, ROCHESTER N.K 14649-0001 ROBERT C. MECREDY Vice Prerldent Ctnna Nudear Production March 8, 1991
'tELEPHOME AREA CODE 71B 546 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3.
Washington, D.C.
20555
Subject:
Completion Date of Probabilistic Risk Assessment/Individual Plant Examination (PRA/IPE)
R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
In a letter dated June 8,
- 1990, RG&E provided its initial 30-day response to the Safety System Functional Inspection (SSFI) of the Residual Heat Removal (RHR) system (50-244/89-81).
In attachment E of that letter, RG&E stated that unresolved items 89-081-01 and 89-081-08 would be evaluated during the PRA/IPE effort scheduled for submittal in the third quarter of 1991.
This completion date of 1991 was a typographical error.
The correct submittal date for the PRA/IPE is on or before September 1,
1992.
This schedule was transmitted'. to you in a letter dated October 27, 1989.
Your letter of January 10, 1990 concludes that this schedule is acceptable.
Very truly yours, SK/148 Robert C. Mecredy 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
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