ML17309A488
| ML17309A488 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/08/1992 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9205210005 | |
| Download: ML17309A488 (6) | |
Text
~. ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ESSION NBR:9205210005 DOC.DATE: 92/05/08 NOTARIZED:
NO CIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
UTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3 DOCKET 05000244 R
SUBJECT:
Responds to NRC 910821
& 900509 ltrs re violations noted in EDSFI Rept 50-244/91-80
& Insp Rept 50-244/89-81, respectively. Corrective actions:new molded-case circuit breaker will be tested during 1993 refueling outage.
DISTRIBUTION CODE:
AOOID COPIES RECEIVED:LTR I
ENCL 0 SIZE:
TITLE: OR Submittal:
General Distribution D
/
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: NRR/DET/ECMB 7D NRR/DOEA/OTSB11 NRR/DST/SELB 7E NRR/DST/SRXB 8E OC G PILE Ol r lERNAL NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 1
RECIPIENT ID CODE/NAME PD1-3 PD NRR/DET/ESGB NRR/DST 8E2 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS 1 RES/DS IR/EIB NSIC COPIES LTTR ENCL D
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PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
jTAL NUMBER OF COPIES REQUIRED:
LTTR 18 ENCL
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< z8N imzz ROCHESTER GAS AND ELECTRIC CORPORATION ROBERTC MECREDY Vice President rr Kw Lear owl's o
89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 TELEPHONE AstEA coDE 71B 548 2700 Clnne Nucteer Production May 8, 1992 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555
Subject:
Update/Extension Request for Corrective Actions to be Taken in Response to Notice of Violation Molded Case Circuit Breaker Testing - NRC Inspection Repor No. 50-244/89-81-06 dated May 9, 1990 R.E.
Ginna Nuclear Power Plant Docket No. 50-244 Ref. (a): Letter dated. August 21, 1991 from M. W. Hodges, NRC, to RG&E, Subject Electrical Distribution System Functional Inspection for Ginna Nuclear Power Station (Report No.
50-244/91-80)
Dear Mr. Johnson:
On page 27 of reference (a), the NRC closed Violation 50-244'/89 06 pertaining to a lack of scheduled periodic testing of Class 1E 480 V molded case circuit breakers (MCCB) as follows:
"In response to the NOV, the licensee stated that it was developing appropriate test methods for MCCBs as part of the Reliability Centered Maintenance (RCM) program.
Corrective Action Report 1985 was initiated to formally track and.
address the lack of MCCB testing.
A corrective action plan was developed to systematically evaluate the identified violation.
This consisted. of:"
"Initiation of 'a program for periodic MCCB testing by the next refueling outage."
"The team concluded that the corrective action plan initiated, to address the lack of MCCB testing was comprehensive and addressed the essential elements to develop an effective testing program.
Based on the licensee's continuing MCCB test program development and the revision of appropriate test procedures, this violation is closed."
Since the "next refueling outage" referred to above is the 1992 Refueling Outage, RG&E is providing the following update/extension request for corrective actions to be taken in response to Violation 50-244/89-81-06:
9205210005 920508 PDR ADOCK 05000244
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1)
Development of the
'MCCB test program is in progress and is being coordinated. with Reliability Centered Maintenance (RCM) program commitments as well as the Maintenance Procedure Upgrade Project (MPUP) schedule.
The RCM preventive main-tenance (PM) enhancements and the MCCB testing program are being implemented into interactive PM procedures.
The RCM project has a
MCCB PM initiation date of 12/31/92.
Current plans are to procure MCCB test.
equipment and finalize pro-cedures for the MCCB program during 6/92 8/92.
2)
To gain breaker testing experience, a non-safety related MCC will be tested first under the new program.
In keeping with the EPRI breaker maintenance guidelines, the initial testing will proceed cautiously and will not be conducted during a
plant outage.
This will facilitate resource allocation and keep the initial testing from becoming a
critic@1 path activity.
Initial MCCB testing will be conducted sometime late in 1992.
3)
Scheduling for safety related MCC's will be completed by 12/92.
Testing of safety related'CC's wi21 be initiated during the 1993 refueling outage.
Very truly yours, GJWN225 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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