05000301/LER-2012-001, Regarding Unit 2 Manual Reactor Trip
| ML12236A329 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/23/2012 |
| From: | Meyer L Point Beach |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NRC 2012-0066 LER 12-001-00 | |
| Download: ML12236A329 (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) 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 3012012001R00 - NRC Website | |
text
August 23,2012 ENERGY POINT BEACH NRC 201 2-0066 10 CFR 50.73 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Unit 2 Docket 50-301 Renewed License No. DPR-27 Licensee Event Report 3011201 2-001 -00 Unit 2 Manual Reactor Trip Enclosed is Licensee Event Report (LER) 30112012-001-00 for Point Beach Nuclear Plant, Unit 2. NextEra Energy Point Beach, LLC is providing this LER regarding the Unit 2 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 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 FOlAlPrivacy 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 ~nformation 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 05000301 1 of 3
- 4. TITLE Unit 2 Manual Reactor Trip
- 5. EVENT DATE
- 9. OPERATING MODE 1
- 10. POWER LEVEL 100%
- 7. REPORT DATE MONTH 06
- 6. LER NUMBER
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFRS: (Check all that apply) 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C)
[7 50.73(a)(2)(vii) 20.2201(d)
[7 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A)
I7 20.2203(a)(I) 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(l)(i)(A) 0 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A)
[7 20.2203(a)(2)(ii) 50.36(c)(l)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(~)(2) 0 50.73(a)(2)(v)(A) 73.71 (a)(4)
I7 20.2203(a)(2)(iv) 50.46(a)(3)(ii)
[7 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)(~)(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 NRC Form 366A MONTH 08 YEAR
- 8. OTHER FACILITIES INVOLVED DAY 27 FACILITY NAME NA FACILITY NAME NA YEAR 2012 2 0 1 2 - 001 - 00 NUMBER DAY 26 DOCKET NUMBER NA DOCKET NUMBER NA
- 12. LICENSEE CONTACT FOR THlS LER REV NO.
YEAR 2012 NAME Kim Locke - Engineering Analyst TELEPHONE NUMBER (Include Area Code) 920/755-7655 CAUSE B
- 14. SUPPLEMENTAL REPORT EXPECTED YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
IXI NO SYSTEM JJ REPORTABLE TO EPlX YES ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On June 27, 2012 at 2046, a Point Beach Nuclear Plant (PBNP) Unit 2 manual reactor trip was actuated due to indications of a loss of load to the main turbine.
At approximately 2045 alarms were received in the control room indicating reduced PBNP Unit 2 turbine first stage pressure and generator megawatts, indicative of a significant reduction in turbine load. Control rods were responding as designed by inserting into the reactor to reduce reactor power. Operations noted that the turbine speed indication on the EH control panel was reading high with the generator output breaker closed, indicating a control system failure. Based on these indications, the Shift Manager directed that the reactor be shutdown by manually actuating the reactor protection system. No automatic reactor protection setpoints were exceeded and an automatic shutdown was not actuated or required.
Based on troubleshooting, NextEra determined that the loss of turbine load was due to a failure of the speed channel card in the EH system. The speed channel card was replaced.
Pursuant to 10 CFR 50.73 (a)(2)(iv)(A), the event is reportable as an event or condition that resulted in manual actuation of the reactor protection system.
COMPONENT SC
- 15. EXPECTED SUBMISSION DATE
CAUSE
MANU-FACTURER WEST MONTH SYSTEM DAY COMPONENT YEAR MANU-FACTURER REPORTABLE TO EPlX high. This also caused the Auxiliary Governor to close the governor valves, which caused the generator to shed load. These indications were the initiating event for the PBNP Unit 2 manual reactor trip.
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 -25 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 'B' speed cards were replaced with spares and calibrated.
Similar Events
None Failed Components NAND gate location A8B, Motorola HTL logic chip MC662L