ML17262A195
| ML17262A195 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/04/1990 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, TAC-53985, NUDOCS 9010250029 | |
| Download: ML17262A195 (3) | |
Text
ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9010250029 DOC.DATE: 90/10/04 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 JOHNSON,A.R.
Project Directorate I-3
SUBJECT:
Informs that util endorses Westinghouse Owners Group repts re Generic Ltr 83-28 on reactor trip reliability.
DISTRIBUTION CODE:
A055D COPIES RECEIVED:LTR ( ENCL SIZE:
TITLE: OR/Licensing Submittal:
Salem ATWS Events GL-83-28 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
DOCKET, 0 05000244 05000244 D
RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: NRR/DEST/ESB 8D NRR/DOEA/OGCB11 NRR/DST/SPLB 8D OGC/HDS2 RES/DSIR/EIB EXTERNAL: NRC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-3 PD NRR/DLPQ/LPEB10 NRR/DST/SICB 7E OC/LFMB NSIC COPIES LTTR ENCL A
D D
R 1
Q NOTE TO ALL"RIDS" RECIPIENTS:
D D
PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 15 ENCL
I'SIE/
BiTZ ROCHESTER GAS AND ELECTRIC CORPORATION 4
89 EAST AVENUE, ROCHESTER N. Y. 14649-0001 ROBERT C MECREDY Vice President Cinna Nucleat Psoduction October 4,
1990 TELEPHONE AREACODE 715 546 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555
Subject:
Safety Evaluation for Generic Letter 83-28, Item 4.5.3, Reactor Trip Reliability On-line Functional Testing of the Reactor Trip System (TAC No. 53985)
R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Reference:
Letter of same subject, dated July 26, 1989, from Allen R. Johnson of the NRC to Robert C. Mecredy of RG&E
Dear Mr. Johnson:
The Westinghouse Topical Reports (WCAPS) referenced in enclosure 2
of your letter of July 26,
- 1989, address the issue of testing frequency of the Reactor Trip System.
These references document the efforts by the Westinghouse Owners Group to develop a
comprehensive analysis used to justify testing frequencies for the Reactor Trip System.
In their evaluation of these references, as documented in EGG-NTA-
- 8341, March
- 1989, the Idaho National Engineering Laboratory concluded that all Westinghouse plants are covered by the analyses documented in these WCAPs.
Specifically, Ginna Station has the two loop reactor coolant system configuration, and the reactor trip system using relays in the implementation of trip logic, that is referenced in WCAP 10271, Supplement 1, paragraph 4.4.
On March 10, 1987, RGEE submitted an application to amend the Ginna Operating License to implement guidance in response to Generic Letter 83-28.
Based on that submittal and subsequent clarifi-
- cations, the NRC approved Amendment 34 of the Operating License which incorporates changes to reactor trip breaker testing reflecting the analyses in the WCAPs.
Therefore, as requested by your letter of July 26,
- 1989, RGGE endorses the Westinghouse Owners Group reports applicable to Ginna.
Very truly
- ours, JRJ/123 Siot025002P Pot004 PDR ADOCK 05000244 J
p PDC It; Robert C. Mecr dy gA
zc: Mr. Allen R. Johnson (Mail Stop 14Dl)
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