05000219/LER-2005-004, Regarding Actuation of an Emergency Diesel Generator Due to Unexpected Breaker Opening
| ML053050393 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/19/2005 |
| From: | Swenson C AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2130-05-20211 LER 05-004-00 | |
| Download: ML053050393 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2192005004R00 - NRC Website | |
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AmerGen SM AmerGen Energy Company www.exeloncorp.com An Exelon Company Oyster Creek US Route 9 South. PO. Box 388 Forked River, NJ 08731-0388 10 CFR 50.73 October 19, 2005 2130-05-20211 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 - 0001 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
Licensee Event Report 2005-004-00, Actuation of an Emergency Diesel Generator due to Unexpected Breaker Opening Enclosed is Licensee Event Report 2005-004, Revision 0. This event did not affect the health and safety of the public or plant personnel. This event included a safety system functional failure of the 4160 VAC electrical distribution system. Attachment 1 lists the regulatory commitments made in this LER submittal.
If any further information or assistance is needed, please contact William Stewart at 609-971-4775.
Sincerely,
/
C. N. Swenson Vice President, Oyster Creek Generating Station CNS/WVS : Summary of Commitments
Enclosure:
NRC Form 366, LER 2005-004-00 cc:
S. J. Collins, Administrator, USNRC Region I P. S. Tam, USNRC Senior Project Manager, Oyster Creek R. J. Summers, USNRC Senior Resident Inspector, Oyster Creek File No. 05049
ATTACHMENT 1 OCGS Licensee Event Report 2005-003-00 SUMMARY OF COMMITMENTS The following table identifies commitments made in this document by Exelon Nuclear. (Any other actions discussed elsewhere in the submittal represent intended or planned actions by Exelon Nuclear. They are described to the NRC for the NRC's information and are not regulatory commitments.)
Commitment
Committed Date or "Outage" Perform failure analysis of the failed light bulb December 30, 2005 from the D bus breaker closed indication.
Remove light bulb from the D bus and EDG 2 November 30, 2005 breakers closed indication and maintain removed until current limiting resistors are installed.
Develop and implement a modification to install November 30, 2006 current limiting resistors in the D bus and EDG 2 breakers closed indication circuit.
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/30/2007 (6-2004)
, the NRC may not conduct or digits/characters for each block) sponsor, and a person Is not required to respond to, the Information collection.
- 3. PAGE Oyster Creek, Unit 1 05000 I219 1
OF
- - 4
- 4. TITLE Actuation of an Emergency Diesel Generator due to Unexpected Breaker Opening-.
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED S
SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO MONTH DAY YEAR 05000 08 24 2005 2005 004 - 00 10 19 2005 FACIL rY NAME DOCKET NUMBER
- 9. OPERATING MODE
- 1. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 20.2201 (b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii)
N 20.2201 (d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A)
X 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 1 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71 (a)(4) 100 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71 (a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)
OTHER 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 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 NFRC Form 366A)
B. Previous Similar Events
LER 96-009 - Actuation of Engineered Safety Feature caused by Loss of Power due to a Faulted Cable LER 97-007 - Inadvertent Initiation of Diesel Generator 2 during Surveillance Testing due to Personnel Error (Voluntary)
LER 97-010 - Manual Reactor Scram, ESF Actuation, and Design Deficiencies after Main Generator Exciter PM LER 00-003 - Manual Scram Following Multiple Recirc Pump Trips C. Identification of components referred to in this Licensee Event Report:
Component IEEE 803A Function IEEE 805 System Bulb EIIS-IL EIIS-EA Breaker EIIS - JX EIIS - EA Diesel Generator EIIS - DG EIIS - EK NRC FORM 366 (6-2004)