05000333/LER-2008-004, Regarding Loss of Power Instrumentation Inoperable and Technical Specification Required Action Time Exceeded Due to Relay Set Point Drift
| ML083460338 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/05/2008 |
| From: | Peter Dietrich Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-08-0126 LER 08-004-00 | |
| Download: ML083460338 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 3332008004R00 - NRC Website | |
text
n-En tergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 Pete Dietrich Site Vice President - JAF December 5, 2008 JAFP-08-0126 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Docket No. 50-333 License No. DPR-59 LICENSEE EVENT REPORT: LER-2008-004-00 Loss of Power.Instrumentation Inoperable and Technical Specification.
Required Action Time Exceeded Due to Relay Set Point Drift Dear Sir or:Madamr:i This report is submitted in accordance with 10 CFR 50.73(a)(2)(i)(B)-, "Any operat'ion :r condition which was prohibited'by'the plant's Technical Specifications".
There are no commitments contained. in this report.
Questions concerning this report may be addressed to Mr. Gene Dorman, Acting Licensing Manager, at (315) 349-6810.
Site Vice President PD:jm Enclosure cc:
USNRC, Region 1 USNRC, Project Directorate USNRC Resident Inspector INPO Records Center kH~i2~
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010 (9-2007)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE James A. FitzPatrick Nuclear Power Plant 05000 333 1
OF 5
- 4. TITLE Loss of Power Instrumentation Inoperable and Technical Specification Required Action Time Exceeded Due To Relay Set Point Drift
- 5. EVENT DATE
- 6. LER NUMBER I
- 7. REPORT DATE I,
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR 09 23 2008 YERSEQUENTIALI REV Y
NUMBER NO.
I FACILITY NAME YEAR N/A DOCKET NUMBER 05000 I
I 2008 004.
00 2 FACILITY NAME 2008 N/A DOCKET NUMBER 05000
- 9. OPERATING MODE 5
- 10. POWER LEVEL 000
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
O 20.2201(b)
[
20.2203(a)(3)(i)
[
50.73(a)(2)(i)(C)
EJ 50.73(a)(2)(vii)
C] 20.2201 (d)
[]20.2203(a)(3)(ii)
[]50.73(a)(2)(ii)(A)
[]50.73(a)(2)(viii)(A)
O 20.2203(a)(1)
[
20.2203(a)(4)
C] 50.73(a)(2)(ii)(B)
[]
50.73(a)(2)(viii)(B)
O 20.2203(a)(2)(i)
Q 50.36(c)(1)(i)(A)
[]
50.73(a)(2)(iii)
[:
50.73(a)(2)(ix)(A) o 20.2203(a)(2)(ii)
Q 50.36(c)(1)(ii)(A)
[]
50.73(a)(2)(iv)(A)
[]
50.73(a)(2)(x)
[
20.2203(a)(2)(iii) 5 50.36(c)(2) 5 50.73(a)(2)(v)(A) 5 73.71 (a)(4)
O 20.2203(a)(2)(iv)
E] 50.46(a)(3)(ii)
E] 50.73(a)(2)(v)(B) 5 73.71(a)(5)
O] 20.2203(a)(2)(v) 5] 50.73(a)(2)(i)(A)
E] 50.73(a)(2)(v)(C) 5 OTHER iJ 20.2203(a)(2)(vi)
E] 50.73(a)(2)(i)(B)
E] 50.73(a)(2)(v)(D)
Specify in Abstract below or in (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)
ASSESSMENT OF SAFETY CONSEQUENCES
Plant barriers providing safety to the public were not compromised as a result of this event and the safety significance of this event is considered low. Though the as-found values for the degraded time delay relays exceeded the TS AVs, and were inoperable, the relays remained capable of performing their safety functions. The plant design bases accident analyses credit calculated allowable values for the LOCA and non-LOCA degraded voltage time delay relays of 9.94 seconds and 58.5 seconds, respectively (Ref. 5). The "as-found" values measured in September, 2008 for the LOCA and non-LOCA time delay relays were within these bounding limits.
SIMILAR EVENTS
There have been no similar events at the plant within the previous ten (10) years involving Agastat Model E7012(004) relays.
REFERENCES
- 1. JAF Condition Report CR-JAF-2008-03286, "During the performance of ISP 1 for the 10600 Bus, 71-27T2-1 HOEB03 and 71-27T3-1 HOEB03 were found outside (HI) their NO ADJUST range."
- 2. JAF Condition Report CR-JAF-2008-03546, "During performance of WO 51193792; ISP-91 -1 timer was high out of tolerance. This is a level 1 criteria."
- 3. JAF Condition Report CR-JAF-2008-03796, "CR-JAF-2008-03286 failed to identify that the effected components failed LEVEL 1 acceptance criteria and the CR was screened incorrectly."
- 4. JAF Condition Report CR-JAF-2008-04044, "The Extent of Condition (EOC) for CR-JAF-2008-03796 and CR-JAF-2008-03546 found that several additional model Agastat E7012 relays are susceptible to the apparent cause and need operability reviews."
- 5. JAF Engineering Calculation JAF-CALC-ELEC-01488, Revision 5, 4KV Emergency Bus Loss of Voltage, Degraded Voltage and Time Delay Relay Uncertainty and Set-Point Calculation
- 6. JAFNPP Modification F1 001, Second Level of Under-voltage Protection-Addition of 45 Second Time Delay and associated Safety Evaluation JAF-SE-88-067.