ML20133J657
| ML20133J657 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 08/09/1985 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Bright G, Gleason J, Kline J Atomic Safety and Licensing Board Panel |
| References | |
| TASK-AS, TASK-BN85-071, TASK-BN85-71 BN-85-071, BN-85-71, NUDOCS 8508120093 | |
| Download: ML20133J657 (2) | |
Text
_ - _ _ _ - _ - _ _ _.
M coK~
J
/
g uenTED STATES 8
NUCLEAR REGULATORY COMMISSICN o
3 l
wasumorow, o.c. zones k*****/
AUG 0 91985 Docket Nos.: 50-440 and 50-441 MEMORANDUM FOR:
The Atomic Safety and Licensing Board for Perry:
(J. P. Gleason, G. O. Bright, J. R. Kline)
~'
The Atomic Safety and Licensing Appeal Board for Perry:
(A.Rosenthal,W. Johnson,G.Edles)
FROM:
Thomas M. Novak, Assistant Director for Licensing Division of Licensing
SUBJECT:
DEVIATION ANALYSIS REPORT OF EXCESSIVE VOLTAGE DROPS IN ELECTRICAL CIRCUITRY WHICH MAY PREVENT OPERATION OF PERRY HYDROGEN CONTROL SYSTEM GLOW PLUGS (BOARD NOTIFICATION NO. 85- 071)
Board Notification 85-069, dated July 9, 1985, advised the Licensing Board of a CEICO Deviation Analysis Report, dated June 18, 1985, indicating the need to assess the safety impact caused by excessive voltage drop conditions
' found ii electrical circuits associated with several plant systems, including J
the Hydrogen ~ Control System glow plugs. CEICO has since completed its eval-uation of voltage drops and has determined that the Hydrogen Control System electrical circuitry is not among those systems for which voltage drop cor-rective action is needed.
Board Notification 85-069 addressed a " draft" Deviation Analysis Report of affected systems, which by either analysis or test later revealed that voltage drops in the glow plug circuity did not impair operation of the glow plugs to perform their safety function.
h D
p)pf'
.p
a Those systems requiring voltage drop corrective actions, to be pursued in accordance with 10 CFR 50.55(e), are identified in the enclosed CEICO letter to the NRC Region III Administrator (M. R. Edelman to J. G. Keppler) dated July 25, 1985.
The CEICO findings on these systems as well as the glow plugs will be verified by the NRC regional inspection staff prior to Perry Unit 1 licensing, currently scheduled in late September 1985.
M Thomas M. Novak, Assistant Director for Licensing Division of Licensing
~
Enclosure:
CEICO Letter dated July 25, 1985 cc: ACRS(10)
EDO Parties to the Proceeding See next page 6
D
ENCLOSURE THE CLEVELAND ELECTRIC ILLUMINATING COMPANY CLEVELANO. CHIO 44101 - TELEPHONE (216) 622-9000 - ILLUhelNATweG SLOG. - $$ PU5UCSQUAAE P.O. 80X 5000 Serving The Best Location in the Nanon July 25, 1985 fs o~rN PY-CEI/0IE 986 L NUCLEAll Mr. James G. Keppler Rtgional Administrator, Region III office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 69137
~
RE:
Perry Nuclear Power Plant Docket Nos.59-449; 59-441 Voltage Drop Evaluation (RDC 142(85)]
Dear Mr. Keppler:
This letter is the final report pursuant to 18CFR58.55(e) concerning the potential for insufficient voltage to some equipment when source voltage is degraded and/or when long cable lengths are used to supply the equipment.
This deficiency was reported by telephone to Mr. R. Knop of your office on June 25, 1985 by Mr. B. D. Walrath of The Cleveland Electric Illuminating company.
This deficiency has been evaluated per Deviation Analysis Report 246.
Description of Deficiency A review was conducted to assess the effects of degraded supply voltage and long cable lengths.
This review identified instances where the voltage drops associated with these conditions could adversely affect the operation of plant equipment.
Components in the following systems are affected:
P47:
Control Complex Chilled Water M32:
Emergency service Water Pump House Ventilation M43:
Diesel Generator Building Ventilation The other systems originally identified as having potentially degraded operation due to excessive voltage drop have been evaluated and found acceptable.
This evaluation considered either the use of the manufacturer's test data, a component specific calculation, or a functional test of the equipment to demonstrate operability under degraded voltage conditions.
e Mr. Jamea G. K:pplcr July 25, 1985 PY-CEI/OIE 9986 L analvnis of Safety Tmnlications This deficiency could prevent or delay the start of the affected systems if a LOCA occurs when offsite power is in a degraded voltage condition.
Corrective Action Design changes (ECN-28522-86-2283 and associated cable pull slips) are being initiated to increase the size of the cables to the affected components in order to prevent excessive voltage dropa.
If you have any questions, please call.
Sincerely,
~
h Murray R. Edelman Vice President Nuclear Group MREspab 4
cc:
Mr. J. A. Grobe USNRC, Site Office (SBB58) l Mr. D. E. Keating USNRC, Site Office (SBB59)
Director i
Office of Inspection and Enforcement I
,U.S. Nuclear Regulatory Commission l
~
Washington, D.C.
20555 l
U.S. Nuclear Regulatory Commission Document Control Desk l
Washington, D.C. 20555 Records Center, SEE-IN Institute of Nuclear Power Operations 1180 Circle 75 Parkway, suite 1500 l
Atlanta, Georgia 33839 l
I i