05000382/LER-2011-003, Regarding Emergency Diesel Generator Output Breaker Failed to Automatically Close During Surveillance Testing
| ML111810100 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/29/2011 |
| From: | Steelman W Entergy Nuclear South |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| W3F1-2011-0055 LER 11-003-00 | |
| Download: ML111810100 (11) | |
| 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 |
| 3822011003R00 - NRC Website | |
text
Entergy Nuclear South Entergy Operations, Inc 17265 River Road Killona, LA 700573093 Tel 504 739 6665 fl Fax 504 739 6698 wsteelmentergycom William J. Steelman Licensing Manager Waterford 3 W3F1-201 1-0055 June 29, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Licensee Event Report 2011-003-00 Waterford Steam Electric Station, Unit 3 (Waterford 3)
Docket No. 50-382 License No. NPF-38
Dear Sir or Madam:
Entergy is hereby submitting Licensee Event Report (LER) 2011-003-00 for Waterford Steam Electric Station Unit 3. This report provides details associated with the A Emergency Diesel Generator output breaker failing to automatically close during a Technical Specification surveillance test.
Based on this failure, it was determined that this condition is reportable under 10 CFR 50.73(a)(2)(i)(B) and I OCFR5O. 73(a)(2)(v)(D) requirements.
This report contains no new commitments. Please contact William J. Steelman at (504) 739-6685 if you have questions regarding this information.
WJS/RJP
Attachment:
Licensee Event Report 2011-003-00
W3F1-2011-0055 Page 2 cc:
Mr. Elmo E. Collins, Jr.
Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam Mail Stop O-8 E9 Rockville, MD 20852 Kaly.Kalyanam@nrc.gov
W3F1-2011-0055 Licensee Event Report 2011-003-00
NRC FORM 366 (10-2010)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (10-2010)
LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
APPROVED BY OMB NO. 3150-0104 EXPIRES 10/31/2013
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Waterford 3 Steam Electric Station 05000 382 1 OF 8
- 4. TITLE Emergency Diesel Generator Output Breaker Failed to Automatically Close During Surveillance Testing
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 04 30 2011 2011 - 003 - 00 06 29 2011 05000
- 9. OPERATING MODE
- 11. 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) 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) 5 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) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 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) 00 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)
OTHER Specify in Abstract below or in verification techniques, critical steps and accountability for these errors. An exercise on disconnecting and reconnecting leads was conducted with each electrical technician. This error only affected annunciator function, not affecting operability. Therefore, this condition did not require a root cause evaluation.
ADDITIONAL INFORMATION
Energy industry identification system (EIIS) codes are identified in the text within brackets [ ].