ML17262A961
| ML17262A961 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/17/1992 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9208250084 | |
| Download: ML17262A961 (3) | |
Text
ACCELERATED DISTRIBUTION,DEMONSTRATION SYSTEM REGULATORY INFQRNATION DISTRIBUTION SYSTEN (RIDS)
CCESSI ON NBR: 9208250084 DQC. DATE: 92/08/1T NQTARIZED:
NO Cll: 50-244 Robert Emmet Ginna Nucleav Plant>
Unit 1>
Rochestev G
UTH. NAME AUTHOR AFFILIATION NECREDY> R. C.
Rochestev Gas h Electv ic Cov p.
RECIP. NANE RECIPIENT AFFILIATION JOHNSON> A. R.
Pv o Ject Div ectov ate I-3
SUBJECT:
Responds to unresolved items noted in Electrical Distribution Sgs Functional Insp Rept 50-244/91-80.
Completion oF analyses for 480 volt ac Zc 41b0 volt ac bv eakev s scheduled bg 930b30.
DISTRIBUTION CODE:
IE01D COPIES RECEIVED: LTR J ENCL G
SIZE:
TITLE:
Genev al (50 Dkt)-Insp Rept/Notice oF Violation Response NOTES: License Exp date in accov dance eith 10CFR2> 2. 109(9/19/72).
DOCKET 0 05000244 S
05000244 REC IP IENT ID CODE/NAME PDi-3 PD 02 INTERNAL: AEQD
- EQD/DSP/TPAB DEDRQ NRR/DLPG/LHFBPT NRR/DQEA/OEAB NRR/PNAS/ILRB12 OEE(~~ LE COPIES LTTR ENCL REC IP IENT ID CODE/NAME JOHNSON> A AEOD/DEIB AEOD/TTC NRR NQR ISSEAU> D NRR/DLPG/LPEB10 NRR/DREP/PEPB9H NUDQCS-ABSTRACT OGC/HDSi RGN1 FILE 01 CQP IES LTTR ENCL 0
EXTERNAL:
EGSG/BRYCE> J. H.
NSIC NRC PDR NOTE TO ALL "RIDS" RECIPIENTS:
A D
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.
ROOM Pl-37 (EXT. 504-'2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF CQP IES REQUIRED:
LTTR 22 ENCL
ROCHESTER GAS AND ELECTRIC CORPORATION net
<< ~ << ~ V
~ ~
<<'j~ s 1Oec ssksc
~
89 EAST AVENUE, ROCHESTER N. Y. 14649-0001 ROBERT C. MECREDY Vice Psesideni Oinno Nuclees Psoducsion August 17, 1992'ELEPHONE AREA CODE 716 546'2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:Allen R. Johnson PWR Project Directorate I-3 Washington, D.C.
20555
Subject:
Electrical Distribution System Functional Inspection (EDSFI)
Unresolved Item 50-244/91-80-06 R.E.
Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a):
Letter from M.W.
- Hodges, NRC, to R.C.
- Mecredy, RG&E,
Subject:
Electr'cal Distribution System Functional Inspection Report No. 50-244/91-80, dated August 21, 1991 (b):
Letter from R.C.
- Mecredy, RG&E, to M.W.
- Hodges, NRC,
Subject:
EDSFI Unresolved Items, dated July 17, 1992 I
Dear Mr. Johnson,
The Electrical Distribution System Functional Inspection Report, Reference (a), Section 2.8, identified. an unresolved item involving protection coordination of motors at degraded voltage conditions while attempting to start or while operating in a service factor zone during an accident condition. Preliminary calculations were provided to demonstrate that, there 'was no immediate cause for concern.
RG&E indicated that a coordination analysis was being conducted to resolve this concern and made a commitment [Reference (b)] to complete the analyses for the 480 Vac and 4160 Vac breakers by the end of June and November 1992, respectively.
Our estimated completion dates for these analyses were based on acquiring documented motor information calculations.
- However, we have now learned that in order to perform these calculations certain specific motor and load data information must be determined by motor testing since the manuf acturer '
information is not available.
During the Spring 1992 refueling outage the safety-related 480 Vac motors were tested.
During the 1993 refueling outage the necessary 4160 Vac motors will be tested.
During the EDSFI the NRC was concerned, in particular, with overcurrent protection of the containment recirculation fans and the service water pump motors.
Field testing performed during the 1992 refueling outage and subsequent modeling shows that a greater margin of safety exists than that which was calculated during the time of the inspection.
Specifically, the starting currents and 9208250084 920817 PDR ADOCK 05000244 8
PDR (qsi $
<i times are less than previously had been assumed.
In addition, field testing and analysis to date has shown that these motors are loaded less than had been assumed.
The combination of these findings has increased the margin between the full load current and the lower band of the breaker pickup current.
The 480 Vac coordination analysis for the safety-related motors is approximately 80t complete and the 4160 Vac coordination analysis will require input from planned motor testing during the 1993 refueling outage before it can be completed.
As a result, completion of both of these analyses is scheduled by June 30, 1993.
Very truly yours, GAHN244 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 U.S.
NRC Ginna Senior Resident Inspector