05000443/LER-2002-002, Re Non-Compliance with Requirements of TS 3.8.1.1 Action B
| ML022820198 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/27/2002 |
| From: | Feigenbaum T North Atlantic Energy Service Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NYN-02090 LER-02-002-00 | |
| Download: ML022820198 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 4432002002R00 - NRC Website | |
text
N1 I,North Atlantic Energy Service Corporation North P.O. Box 300 Seabrook, NII 03874 Atlantic(603) 474-9521 The Northeast Utilities System September 27, 2002 Docket No. 50-443 NYN-02090 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station Licensee Event Report (LER) 02-002-00 for Non-Compliance With The Requirements of Technical Specification 3.8.1.1 Action b.
Enclosed is Licensee Event Report (LER) 02-002-00. This LER reports an event that occurred at Seabrook Station on July 31, 2002. This event is being reported pursuant to the requirements of 10 CFR 50.73(a)(2)(i)(B).
Should you require further information regarding this matter, please contact Mr. James M.
Peschel, Manager - Regulatory Programs at (603) 773-7194.
Very truly yours, NORTH ATLANTIC ENERGY SERVICE CORP.
Ted C. FeigVenbw Executive Vife President and Chief Nuclear Officer cc:
H. J. Miller, NRC Region I Administrator R. D. Starkey, NRC Project Manager, Project Directorate 1-2 G. T. Dentel, NRC Senior Resident Inspector
ENCLOSURE TO NYN-02090
Abstract
On July 24, 2002, with the plant operating at 100 % power, a surveillance test was performed on emergency diesel generator [EK] DG-1 B (DG-1 B). After approximately three hours of fully loaded operation of DG-1 B, plant operators noted that the kilovolt amperage reactive (WAR) indication was fluctuating. As a result of the fluctuation, plant operators subsequently shutdown the engine and declared DG-1 B inoperable at 2302 on July 24, 2002.
Technical Specification (TS) 3.8.1.1 Action statement b. requires that when one diesel generator is inoperable, the operability of the remaining diesel must be demonstrated operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. TS 3.8.1.1 Action b. also identifies that the operability of the remaining diesel generator need not be verified if it has been successfully operated within the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or if currently operating, or if the diesel generator became inoperable due to 1.) Preplanned preventive maintenance or testing; 2.) An inoperable support system with no potential common mode failure for the remaining diesel generator, or 3.) An independently testable component with no potential common mode failure for the remaining diesel generator. Subsequent analysis of the event determined that the decision not to test DG-IA within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> was not consistent with guidance provided in TS Bases section 3/4.8.1.
The failure to meet the requirements of TS 3.8.1.1 action b. is a condition prohibited by the Technical Specifications and is reportable pursuant to the requirements of 10 CFR 50.73(a)(2)(i)(B). Subsequent testing of DG-lA was satisfactorily completed at 0247on July 31, 2002. Additional corrective actions to prevent recurrence have been identified. There were no adverse safety consequences as a result of this event.
NRC FORM 366 (7-2001)
(If more space is required, use additional copies of (If more space is required, use additional copies of NRC Forn 366A) (17)
IV. Corrective Actions
- 1.
DG-1A was tested satisfactorily on July 31, 2002.
- 2.
The details of this event have been reviewed by the licensed plant operators to ensure that they are aware of the requirement to prove that no common mode failure exists prior to determining that the remaining diesel generator does not have to be run in accordance with TS 3.8.1.1 Action b.
- 3.
A review of the Seabrook Station Technical Specifications was performed to determine if there were other requirements similar to TS 3.8.1.1 Actions b and c. This review indicated that the requirements of TS 3.8.1.1 Actions b. and C. are unique and do not apply to other Technical Specification requirements.
- 4.
Plant operators will receive formal training on the requirements of TS 3.8.1.1 to ensure that the changes and associated bases are clearly understood.
V. Additional Information
None
Similar Events
There have been no similar events reported by Seabrook Station.
Manufacturer Data Not Applicable.