ML20114C954
| ML20114C954 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/09/1985 |
| From: | Mangan C NIAGARA MOHAWK POWER CORP. |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| (55(E)-84-32), (NMP2L-0320), (NMP2L-320), (SS(E)-84-32), NUDOCS 8501300595 | |
| Download: ML20114C954 (3) | |
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.;a NUMOHAWK Y NIAGARA HlAGARA MOHAWK POWER CORPORATION /300 ERlE BOULEVARD WEST. SYRACUSE. N.Y.13202/ TELEPHONE (315) 474-1511 January 9,1985 (NMP2L 0320)
Mr. R. W. Starostecki, Director U. S. Nuclear Regulatory Commission Region I Division of Project and Resident Programs 631 Park Avenue King of Prussia, PA 19406 Re: Nine Mile Point - Unit 2 Docket No. 50-410
Dear Mr. Starostecki:
Enclosed is a final report in accordance with 10CFR50.55(e) for tne problem concerning tne hign pressure core spray diesel generator.
This problem was reported via tel-con to P. Russ of your office on August 9,1984 An interim report was submitted via our letter dated September 10, 1984.
Very truly yours, k All[LAl b (
C. V. Mangan' Vice President Nuclear Engineering and Licensing CVM/GG:csb (0642H) xc: Director of Inspection and Enforcement U. S. Nuclear Regulatory Commission Wasnington, DC 20555 R. A. Gramm, NRC Resident Inspector Project File (2) 8501300595 850109 PDR ADDCK 05000410 S
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-NIAGARA M0 HAWK POWER-CORPORATION NINE MILE POINT --UNIT 2 DOCKET N0.-50-410 Final Report for Problems Concerning High Pressure Core Spray Diesel Generator
'(55(e)-84-32)
Description of the-Problem i
During r review of the high pressure core spray diesel generator equipment, various modifications to this ~ equipment -were identified which we believe are necessary for the proper operation of the high pressure core spray system.
The following safety-related problems were~ identified.
1.
.In switchgear 2 ENS *SWG102, current transformer terminals-on nonsafety-related short-circuiting terminal block A are not properly ~
spaced and/or separated fro _m similar_~ terminals on safety-related short-circuiting terminal block-8.
2.
In _ relay panel H22-P028, nonsafety-related panel ' light. terminal 2
block points A-1 and A-2 are not properly spaced and/or separated from safety-related points A-7 and A-8.
3.
Non-Class lE station battery monitor relays were connected to the Division III Class lE battery cystem with only single fusing.
4.
General Electric has identified a problem with its NGV _ relays in Panel 2CES*1PNL413 containing defective ohmite model E
potentiometers, that were manufactured between October 1,1973, and i
November 1, 1976.
]
Analysis of Safety Implications 2
i-One and/or more of che first three conditions ~ detailed above-could have i
prevented - tie Division III diesel generator from performing its intended design function.
Therefore, the safety of operations of the plant.could have j-been adversely affec;ed.
t l
Corrective Actions l.
The improper separation between the nonsafety-related short-circuiting l
terminal block A and terminal block B will be repaired according to the i
repair -procedures specified in GE FDDR-KGl-2396.
This corrective action will be completed in accordance with Engineering and Design Coordination Report No. F41,601A by February 25, 1985.
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d 2..
The improper -separation between the nonsafety-related terminal block points A-1 and A-2 and safety-related points A-7 and A-8 has been repaired according to the repair procedures specified in GE FDDR-KGI-2398.
This corrective action has been completed in accordance with Engineering & Design Coordination Report No. F41,597.
3.
Additional fusing will be provided to the non-Class 1E station battery monitor connected to the Division III Class lE battery system in accordance with FDDR-KGl-2776.
This corrective action will be completed in accordance with Engineering & Lesign Coordination Report No. F41,754.
4.
The defective GE type NGV relay K54 is to be replaced with a new Brown -
Boveri relay part number 15208149P001 according to the replacement procedures specified in GE FDDR No. KGl-2974.
This corrective action will be completed in accordance with Engineering & Design Coordination Report No. F41,896 by February 7, 1985.
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