05000266/LER-2012-004, Regarding Unit 1 Manual Reactor Trip
| ML12277A325 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/03/2012 |
| From: | Meyer L Point Beach |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NRC 2012-0090 LER 12-004-00 | |
| Download: ML12277A325 (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)(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 |
| 2662012004R00 - NRC Website | |
text
October 3, 2012 ENERGY f
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BEACH NRC 201 2-0090 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 2-004-00 Unit 1 Manual Reactor Trip Enclosed is Licensee Event Report (LER) 26612012-004-00 for Point Beach Nuclear Plant, Unit I.
NextEra Energy Point Beach, LLC is providing this LER regarding the Unit 1 manual reactor trip.
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 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: 10/31/2013 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 FOlAtPrivacy Section (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects.resourse@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office 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 may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 2. DOCKET NUMBER
- 3. PAGE 05000266 1 of3
- 4. TITLE Unit I Manual Reactor Trip
- 8. OTHER FACILITIES INVOLVED
- 9. OPERATING MODE 1
- 10. POWER LEVEL 100%
FACILITY NAME NA FACILITY NAME NA
- 7. REPORT DATE
- 5. EVENT DATE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFRS: (Check all that apply)
I7 20.2201(b) 20.2203(a)(3)(i)
- 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 1 20.2201(d) 20.2203(a)(3)(ii) 1 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 0 20.2203(a)(I)
I7 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50,73(a)(2)(viii)(B) 20.2203(a)(2)(i) 0 50.36(c)(l)(i)(A) 1 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 0 20.2203(a)(2)(ii)
- 50.36(c)(l)(ii)(A)
IXI 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 1 20.2203(a)(2)(iii)
I7 50.36(~)(2)
- 50.73(a)(2)(v)(A) 73.71 (a)(4) 0 20.2203(a)(2)(iv) 0 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 Analysis of Safety Significance A manual reactor trip was initiated in response to the turbine governor valves closing and the loss of generator load while the reactor was still at power. No automatic reactor protection setpoints were exceeded, and the automatic reactor protection system was not actuated nor needed. Plant systems functioned as required following the trip.
The reactivity effects during this particular event had no impact on the safety of the core. The initial event resulted in reactor coolant system (RCS) temperature rising as steam demand was reduced by the closing governor valves. At this stage in core life, the moderator temperature coefficient is largely negative (approximately -22 pcmldeg F); thus, the rising temperature added significant negative reactivity. The control rods began to insert into the core to control the temperature increase as designed. The Shift Manager and operating crew responded appropriately by manually actuating the reactor protection system to shut down the reactor.
Corrective Actions
The 'A' and '6' main speed cards were replaced with spares and calibrated.
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