05000341/LER-2003-001, Loss of High Pressure Coolant Injection Safety Function Due to Closure of Steam Supply Valve
| ML032520581 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/29/2003 |
| From: | O'Connor W DTE Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC-03-0068 LER 03-001-00 | |
| Download: ML032520581 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 3412003001R00 - NRC Website | |
text
William T. O'Connor, Jr.
Vice President, Nuclear Generation Fermi 2 6400 North Dixie Hwy., Newport, Michigan 48166 Tel: 734-586-5201 Fax: 734-586-4172 DTE Energy 7
10CFR50.73 August 29, 2003 NRC-03-0068 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555
Reference:
Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
Subject:
Licensee Event Report (LER) No.03-001 Pursuant to 10 CFR 50.73(a)(2)(v)(D), Detroit Edison is submitting the enclosed LER No.03-001. This LER documents the loss of the High Pressure Coolant Injection safety function due to closure of a steam supply valve.
No commitments are being made in this LER.
Should you have any questions or require additional information, please contact Mr. Norman K. Peterson of my staff at (734) 5864258.
Sincerely, cc:
H. K. Chernoff M. A. Ring M. V. Yudasz, Jr.
NRC Resident Office Region m Regional Administrator, Region m Wayne County Emergency Management Division
Abstract
On July 13, 2003, at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, during surveillance testing of the High Pressure Coolant Injection (FCI) system, valve E4150-F003, the Outboard Steam Supply Isolation Valve, failed to close when the close pushbutton was depressed. E4150-F003 is a normally closed valve and had just been successfully stroked open. In accordance with Technical Specification (TS) 3.6.1.3, Primary Containment Isolation Valves (PCIVs), the E4150-F003 valve was declared inoperable and the penetration flow path was isolated by closing and deactivating E4150-F002, the Inboard Steam Supply Isolation Valve. Isolating the HPCI steam supply rendered HPCI inoperable and TS 3.5.1, Emergency Core Cooling System (ECCS) and Reactor Core Isolation Cooling (RCIC) System, was entered. All other ECCS systems remained operable.
The event was caused by an electrical contact failure. The normally open auxiliary electrical contact that provides the seal in feature for closing the E4150-F003 valve failed to close when the close pushbutton was depressed. Without the seal in feature the E4150-F003 valve stopped stroking closed when the operator released the close pushbutton.
The auxiliary electrical contact that provides the seal in feature for closing the E4150-F003 valve was replaced during the scheduled system maintenance outage. Post maintenance testing was completed and the HPCI system was declared operable on July 18, 2003, at 2107 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.017135e-4 months <br />.
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Additional Information
No systems other than those already mentioned in this report were affected by this event.
A. Failed Components:
Component:
Contact Block
Description
DC Electrical Auxiliary Contact Assembly for Motor Control Center Manufacturer:
TE-Gould Corporation Model Number: FIONOCR B. Previous LERs on Similar Problems:
There were no HPCI failures or similar events in the last two years.
NRC FORM 368A (7-2001)