ML17261A691
| ML17261A691 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 12/15/1987 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Stahle C NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8712220234 | |
| Download: ML17261A691 (5) | |
Text
- CCESSION NBR FAC-IL'0-244 AUTH. NAME KOBER> R. W.
RECIP. NAME STAHLE> C.
REGUL Y INFORMATION DISTRIBUTI SYSTEM (RIDS) rt%'L 8712220234 DOC. D*TE: 87/12/15 NOTARIZED:
NO DOCKET 0 Robert Emmet Ginna Nuclear Plant>
Unit 1> Rochester G
05000244 AUTHOR AFFILIATION Rochester Gas h Electric Corp.
RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
Prospect Directorate I-1
SUBJECT:
Discusses util 870714 supplemental rept re CRDR control switch relocation. Informs of intent to delalg mod which addresses both existing CRDR commitments Sc offsite power reconf iguration until 1989 refueling outage.
DISTRIBUTION CODE:
AOQID COPIES RECEIVED: LTR I
ENCL 0 SIZE:
TITLE:
OR Submittal:
General Distribution'OTES:
License Exp date in accordance with 10CFR2> 2. 109(9/19/72).
05000244 RECIPIENT ID CODE/NAME PD1-3 LA STAHLE> C INTERNAL: '*RM/DAF/LFMB NRR/DEBT/CEB NRR/DEST/RSB NR S/ILRB RE+
01 EXTERNAL:
LPDR NSIC COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-3 PD NRR/DEST/ADS NRR/DEST/MTB NRR/DOE*/TSB OGC/HDS2 RES/DE/EIB NRC PDR COP IES LTTR ENCL TOTAL NUMBER OF COPIES REQUIRED:
LTTR 20 ENCL
III h
t 1
Cj
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ZK, ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 ROGER W. KOBER VICC RRCSiDCNT ELECTRIC PRODUCTION December 15, 1987 TCLCRRONC hRCh COOC TIC 546-2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Mr. Carl Stahle PWR Project Directorate No.
1 Washington, D.C.
20555
Subject:
Control Room Design Review (CRDR)
Control Switch Relocation R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Stahle:
On July 14, 1987 Rochester Gas and. Electric submitted to you a Supplemental Report of our Control Room Design Review (CRDR) effort at the Ginna Nuclear Power Plant.
That report, among other things, described our response to a number of HEDs that involved relocation of circuit breaker control switches on the main control board.
- Further, the report declared that the control switch relocation work would be completed by the end of the 1988 refueling outage.
Concurrently, LER 87-001 further committed RG&E to a long term plan to reconfigure the station offsite power supply system.
This power system reconfiguration is presently in the design stage and will be installed in 1989.
The new design requires additional circuit breaker control switches to be added to the main control board in the area intended to be modified to satisfy the require-ments of the CRDR.
In consideration of operator training, it is better to modify the control board once and retrain the operators only one time rather than to introduce two modifications at different times and potentially create confusion with the operators.
It is our intent then, to delay the modification for the CRDR until such time as the station offsite power supply system design is installed.
The controls for the reconfigured offsite power supply will receive human factors review to assure that no human engineering deficiencies are introduced by the modification when integrated with the control modifications of the CRDR.
The modifications which address both the existing CRDR commitments and the offsite power reconfiguration will be completed during the 1989 refueling
-outage.
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If you have any questions regarding this matter or if you need additional information, RGGE staff will respond to your requests.
Ve truly yours,
,~a lc'oger W. Kober
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