05000266/LER-2012-002, Regarding Condition Prohibited by Technical Specification 3.7.5, Auxiliary Feedwater
| ML12230A227 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/17/2012 |
| From: | Meyer L Point Beach |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NRC 2012-0060 LER 12-002-00 | |
| Download: ML12230A227 (4) | |
| 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)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 2662012002R00 - NRC Website | |
text
August 17,2012
/
BEACH N RC 20 1 2-0060 10 CFR 50.73 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Unit 1 Docket 50-266 Renewed License No. DPR-24 Licensee Event Report 2661201 2-002-00 Condition Prohibited bv Technical Specification 3.7.5. Auxiliaw Feedwater Enclosed is Licensee Event Report (LER) 26612012-002-00 for Point Beach Nuclear Plant, Unit 1. NextEra Energy Point Beach, LLC is providing this LER regarding Technical Specification 3.7.5 not being met for the Unit 1 turbine driven auxiliary feedwater pump.
This submittal contains no new or revised regulatory commitments.
If you have questions or require additional information, please contact Mr. Jim Costedio at 9201755-7427.
Very truly yours, NextEra Energy Point Beach, LLC Larry Meyer Site Vice President Enclosure CC:
Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241
NCR FORM 366 (10-2010)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (10-2010)
LICENSEE EVENT REPORT (LER)
- 1. FACILITY NAME Point Beach Nuclear Plant APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/3112013 Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the FOIA/Privacy Section (T-5 F53). U.S. Nuclear Regulato Commission. Washington. DC 20555-0001, or by internet e-mail to in?bcollects.resourse@nrc.gov, and to the Desk Officer. Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Ofice of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC ma not conduct or sponsor, and a person is not required to respond to, the inrormation collection.
- 2. DOCKET NUMBER
- 3. PAGE 05000266 1 of 3
- 4. TITLE Condition Prohibited by Technical Specification 3.7.5, Auxiliary Feedwater
- 8. OTHER FACILITIES INVOLVED
- 5. EVENT DATE
- 9. OPERATING MODE MODE 1
- 10. POWER LEVEL 100%
FACILITY NAME N A
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFRS: (Check all that apply) 20.2201(b)
[7 20.2203(a)(3)(i)
[7 50.73(a)(2)(i)(C) 17 50.73(a)(2)(vii)
[7 20.2201(d)
[7 20.2203(a)(3)(ii)
[7 50.73(a)(2)(ii)(A)
[7 50.73(a)(2)(viii)(A) 17 20.2203(a)(I) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B)
[7 20.2203(a)(2)(i) 50.36(c)(l)(i)(A)
[7 50.73(a)(2)(iii)
[7 50.73(a)(2)(ix)(A)
[7 20.2203(a)(2)(ii)
[7 50.36(c)(l)(ii)(A) 50.73(a)(2)(iv)(A)
[7 50.73(a)(2)(x)
[7 20.2203(a)(2)(iii) 50.36(~)(2) 50.73(a)(2)(v)(A)
[7 73.71 (a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii)
[7 50.73(a)(2)(v)(B) 17 73.71(a)(5)
[7 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(@(2)(v)(C)
[7 OTHER 20.2203(a)(2)(vi)
IXI 50.73(a)(2)(i)(B)
[7 50.73(a)(2)(v)(D)
Specify in Abstract below or in Analysis of Safety Significance NextEra determined that the internal risk for increase in core damage probability to be of very low safety significance.
The determination of the safety significance from external events is not yet complete. A supplement to this LER will be submitted when this determination is complete.
Corrective Actions
The cold spring was resolved from 1 P-29 Turbine Exhaust Steam Piping on June 20, 2012, by installing a tapered wedge in the exhaust flange connection.
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