05000244/LER-2003-001, Inadequate Consideration of System Interactions for Bus Tie Breaker Maintenance Results in a Condition Prohibited by Technical Specifications
| ML031550363 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/23/2003 |
| From: | Mecredy R Rochester Gas & Electric Corp |
| To: | Clark R Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 03-001-00 | |
| Download: ML031550363 (9) | |
| Event date: | |
|---|---|
| Report date: | |
| 2442003001R00 - NRC Website | |
text
Robert C. Mecredy Vice President Nuclear Operations May 23, 2003 Mr. Robert L. Clark Office of Nuclear Regulatory Regulation U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
LER 2003-001, Inadequate Consideration of System Interactions for Bus Tie Breaker Maintenance Results in a Condition Prohibited By Technical Specifications R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Clark:
The attached Licensee Event Report (LER) 2003-001 is submitted i. accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(i)(B), which requires a report of "Any operation or condition prohibited by the plant's Technical Specifications."
This event has in no way affected the public's health and safety.
Very truly yours, Robert C. Mecredy 1000742 An equal opportunity employer 89 East Avenue I Rochester, NY 14649 tel (585) 546-2700 www.rge.com E e t An Energy East Company RWe Always at Your Service
MDF/293 xc:
Mr. Robert L. Clark (Mail Stop 0-8-C2)
Project Directorate I Division of Licensing Project Management Office of Nuclear Regulatory Regulation U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector 1000742
Abstract
to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On April 2, 2003, the plant was in Mode 1 at approximately 100% steady state reactor power. At approximately 0930 EST, it was discovered that over the last three years, on two separate occasions (June 8, 2000 and January 16, 2002), maintenance activities associated with non-safety-related bus tie breakers 52/BTA-A and 52/BTB-B had rendered the Main Feedwater Pump Discharge Valves (MFPDVs) inoperable with respect to the Ginna Station Technical Specifications. This inoperability was not recognized by plant staff at the time of the maintenance. As a result, LCO 3.7.3 Condition A was not entered and the Required Action Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> was not met. Since these were previous occurrences, no immediate actions were required.
The cause of operating in a condition prohibited by Technical Specifications was plant staff not recognizing the impact of removing the bus-tie breakers from service and their impact on the MFPDVs due to inadequate consideration of system interactions.
Corrective action to prevent recurrence is listed in Section V.B.
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C.
THE ENERGY INDUSTRY IDENTIFICATION SYSTEM EIIS) COMPONENT FUNCTION IDENTIFIER AND SYSTEM NAME OF EACH COMPONENT OR SYSTEM REFERRED TO IN THIS LER:
COMPONENT IEEE 803 FUNCTION IDENTIFIER IEEE 805 SYSTEM IDENTIFICATION Flow Control Valve Isolation Valve FCV ISV SJ (Feedwater System)
SJ D.
SPECIAL COMMENTS:
None