ML17262A880
| ML17262A880 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/01/1992 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9206150001 | |
| Download: ML17262A880 (6) | |
Text
ACCELERATED DISTRIBUTION DEMONSTPA,TION SYSTEM REGULATORY INFOR"CATION DISTRIBUTION SYSTEM (RIDS)
ACCESSIQN NBR:9206150001 DOC.DATE: 92/06/01 NOTARIZED: NO DOCKET FACIL:50-24) Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244
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0TH. N!Q4E AUTHOR AFFILIATION CREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3
SUBJECT:
Responds to NRC 910717 ltr re unresolved items noted in EDSFI Rept 50-244/91-80.Final dynamic loading analysis expected to demonstrate increased margin beyond margin of preliminary analysis. Software to be completed by 921231.
DISTRIBUTION CODE:
ROOID COPIES RECEIVED:LTR g ENCL 0 SIZE:
TITLE: OR Submittal: General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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05000244 RECIPIENT ID CODE/NAME PDl-3 LA JOHNSON,A INTERNAL: NRR/DET/ECMB 7D NRR/DOEA/OTSB11 NRR/DST/SELB 7E NRR/DST/SRXB 8E OC/LFMB REG%'FEZ E"~ "-
.-. 1 EXTERNAL: NBC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-3 PD NRR/DET/ESGB NRR/DST 8E2 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB NSIC COPIES LTTR ENCL D
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D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE W~! CONTACT THE DOCUMENT CONTROL DESK ROOM PI-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISES FOR DOCUMENTS YOU DON'T NEED!
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LTTR 18 ENCL
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ROCHESTER GAS AND ELECTRIC CORPORATION o
I tone 89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C. MECREDY Vtce Ptetldent Clnne Nudeer Production June 1,
1992 1HEPHONE AAEACOOETte 546-2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson (Mail Stop 14D1)
PWR Project Directorate I-3 Washington, D.C.
20555
Subject:
Electrical Distribution System Functional Inspection (EDSFI) Unresolved Item 50-244/91-80-03 R.E.
Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a):
Letter from R.C. Mecredy (RG&E) to M.W. Hodges (NRC),
"Electrical Distribution System Functional Inspection (50-244/91-80)
Unresolved Items", dated. July 17, 1991.
Ref.(b):
Letter from R. Mecredy (RG&E) to M. Hodges (NRC),
"Reply to Notification of Violation 50-244/91-80-04, Notice of Deviation 50-244/91-80-01,
-02 and EDSFI Inspection Report 50-244/91-80" dated September 30, 1991.
Dear Mr. Johnson:
By letter dated July 17, 1991 (Reference a), in response to an unresolved item identified at the EDSFI exit meeting held on June 7, 1991, RG&E committed to complete a dynamic loading analysis of the emergency diesel generators by May 31, 1992.
RG&E also committed to complete verification and validation of the model software by September 30, 1992.
These commitments were further clarified by letter dated September 30, 1991 (Reference b).
This letter provides the status of these commitments.
Available commercial software has been procured, and is being adapted to perform the dynamic loading analysis.
During this process several enhancements to the software were necessary for the level of model development required for this analysis.
Currently, the majority of the initial software development is complete.
Field testing of the diesel generators and safeguards motors was required to obtain adequate data for computer modeling.
This testing was performed during the 1992 refueling outage.
This data is currently being incorporated into the simulation model.
The preliminary dynamic analysis reviewed during the EDSFI, which was based on conservative assumptions, demonstrates that the 920615000i 920601 PDR ADOCK ~05000244 o
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~ P diesel generators can adequately supply the required loading following a postulated accident.
Field testing demonstrates that the assumed motor characteristics are indeed conservative.
Therefore, the final dynamic loading analysis is expected to demonstrate increased.
margin beyond. that of the preliminary analysis.
As a result of the delays in the software model development it is now anticipated that completion of the dynamic loading analysis and verification and validation of the software will be completed by December 31, 1992.
Very truly yours, Robert C. Mecredy SCK/230 xc:
U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Nr. Allen R. Johnson (Nail Stop 14D1)
PWR Project Directorate I-3 Washington, D.C.
20555 Ginna Senior Resident Inspector i
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