05000333/LER-2008-003, NPP Regarding Loss of Emergency Bus and Auto-Start of B Edg(S) Due to Re-Scheduled Relay Functional Test W/O Risk Assessment Review
| ML083460339 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/04/2008 |
| From: | Peter Dietrich Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-08-0125 LER 08-003-00 | |
| Download: ML083460339 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x) |
| 3332008003R00 - NRC Website | |
text
" Enbtergy 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 December 04, 2008 JAFP-08-0125 Pete Dietrich Site Vice President - JAF United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Docket No. 50-333 LICENSEE EVENT REPORT: LER-2008-003-00 Loss of Emergency Bus and Auto-Start of "B" EDG(s) Due To Re-Scheduled Relay Functional Test without Risk Assessment Review
Dear Sir or Madam:
This report-is submitted. in accord ance with1:CFR 5,0.7 3(a)(2)(i v)(A), "Any event-or: condition that resulted in manual o"rautomatic actuation of(B)(2) General containment isolation sighals affecting containment: isolation valvesin more than one system, and (B)(8) Emergency AC electicalpower-,'%;-:
systems, including Emergency-Diesel.Generators".
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.
Pete Dietrich PD:jm Enclosure cc:
USNRC, Region 1 USNRC, Project Directorate USNRC Resident Inspector INPO Records Center VA ý2,ý
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 Emergency Bus and Auto-Start of "B" EDG(s) Due To Re-Scheduled Relay Functional Test w/o Risk Assessment Review
- 5. EVENT DATE
- 6. LER NUMBER 1
- 7. REPORT DATE I
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR I YEAR SEQUENTIAL REV O
NUMBER NO.
10 07 2008 2008 003.
00 FACILITY NAME N/A DOCKET NUMBER 05000 FACILITY NAME DOCKET NUMBER N/A 05000 THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
- 9. OPERATING MODE 4
- 10. POWER LEVEL 000
- 11. THIS REPORT IS Q 20.2201(b)
O] 20.2201(d)
[]
20.2203(a)(1)
O] 20.2203(a)(2)(i)
O 20.2203(a)(2)(ii)
El 20.2203(a)(2)(iii)
O 20.2203(a)(2)(iv)
[]
20.2203(a)(2)(v) o] 20.2203(a)(2)(vi)
JBMITTED PURSUAN' jJ 20.2203(a)(3)(i)
O 20.2203(a)(3)(ii)
E] 20.2203(a)(4)
[]
50.36(c)(1)(i)(A)
E] 50.36(c)(1)(ii)(A)
O 50.36(c)(2)
El 50.46(a)(3)(ii)
E] 50.73(a)(2)(i)(A)
[]
50.73(a)(2)(i)(B) 0 0
El C:
50.73(a)(2)(i)(C) 50.73(a)(2)(ii)(A) 50.73(a)(2)(ii)(B) 50.73(a)(2)(iii) 50.73(a)(2)(iv)(A) 50.73(a)(2)(v)(A) 50.73(a)(2)(v)(B) 50.73(a)(2)(v)(C) 50.73(a)(2)(v)(D)
E]
El 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(ix)(A) 50.73(a)(2)(x) 73.71 (a)(4) 73.71 (a)(5)
OTHER 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)
FAILED COMPONENT IDENTIFICATION There were no component failures as a result of this event.
SIMILAR EVENTS
LER-2008-001 / CR-JAF-02997 On September 16, 2008 at 0734, with the plant shutdown and in the refueling mode (Mode 5), a fuse was removed during an equipment tag-out evolution resulting in the closure of two Primary Containment Isolation System (PCIS) valves and a loss of Shutdown Cooling (SDC). The cause of the event was ineffective implementation of the outage risk assessment procedure.
REFERENCES JAF Condition Report CR-JAF-2008-03805, "Loss of Emergency Bus (10600) and Auto-Start of Train "B" EDG Due To Work Task Schedule Error".