05000266/LER-2016-003, Regarding Operation or Condition Prohibited by Technical Specifications
| ML16153A159 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/01/2016 |
| From: | Coffey B Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 16-003-00 | |
| Download: ML16153A159 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(v), Loss of Safety Function 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 2662016003R00 - NRC Website | |
text
June 1, 2016 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 266/2016-003-00 Unit 1 Operation or Condition Prohibited by Technical Specifications NRC 2016-0025 10 CFR 50.73 Enclosed is Licensee Event Report (LER) 266/2016-003-00 for Point Beach Nuclear Plant, Unit 1. NextEra Energy Point Beach, LLC is providing this LER to report an operation or condition prohibited by Technical Specifications.
This letter contains no new regulatory commitments.
If you have any questions please contact Mr. Bryan Woyak, Licensing Manager, at 920/755-7599.
Sincerely, NextEra Energy Point Beach, LLC BobiCoffey 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
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 1013112018 (11-2015)
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, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Point Beach Nuclear Plant Unit 1 05000266 1 OF 3
- 4. TITLE Operation or Condition Prohibited by Technical Specifications
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED YEAR I SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.
MONTH DAY YEAR NA 05000 FACILITY NAME DOCKET NUMBER 04 02 2016 2016 - 003
- - 00 06 01 2016 NA 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
D 20.2201 (b)
D 20.2203(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A) 4 D 20.2201 (d)
D 20.2203(a)(3)(ii)
D 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
D 20.2203(a)(1)
D 20.2203(a)(4)
D 50.73(a)(2)(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(i)
D 50.36(c)(1 )(i)(A)
D 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL D 20.2203(a)(2)(ii)
D 50.36(c)(1 )(ii)(A)
D 50.73(a)(2)(v)(A)
D 73.71 (a)(4)
D 20.2203(a)(2)(iii)
D 50.36(c)(2)
D 50.73(a)(2)(v)(B)
D 73.71 (a)(5)
D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 73.77(a)(1) 0%
D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
D 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 20.2203(a)(2)(vi)
I:2J 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii)
D 50.73(a)(2)(i)(C)
D OTHER Specify in Abstract below or in
Corrective Actions
05000266 YEAR 2016 SEQUENTIAL NUMBER 003 REV NO.
00 The two containment accident recirculation fans were immediately positioned to the required position for the MODE of operation. Corrective actions have been created to conduct training to all crews that will cover command and control, implementation of technical specifications, operating experience of this event, and revision to the cold to hot shutdown procedure.
Similar Events
LER 2013-002-00 has reported a similar event of LCO Application 3.0.4 in the past 3 years. However, the cause and corrective action of LER 2013-002-00 are not the same as this event.
Component Failure Data
None Description of the Event:
SEQUENTIAL NUMBER 003 REV NO.
00 At 0229 on April 2, 2016, Unit 1 entered MODE 4 from MODE 5 without satisfying all of Technical Specification 3.6.6, Containment Spray and Cooling System Limiting Conditions for Operation (LCO) as required by LCO Applicability 3.0.4.
LCO Applicability 3.0.4 does not permit entry into a MODE of applicability when an LCO is not met, unless the associated actions to be entered permit continued operation in the MODE for an unlimited time or after performance of an acceptable risk assessment and the appropriate risk management actions have been established. At 0307 on April 2, 2016 it was discovered that components were not operable as required by Technical Specification LCO 3.6.6 to permit entry into MODE 4 per LCO 3.0.4. At 0308 on April 2, 2016, the affected control switches for the two Containment Accident Recirculation Fans were positioned to auto, operability was restored and LCO 3.6.6 was met.
This 60 day licensee event report is being submitted in accordance with the requirements of 10 CFR 50. 73(a)(2)(i)(B).
Cause of the Event
The cause of the operation or condition prohibited by technical specifications was failure to physically validate indications to ensure required equipment operability. Less than adequate oversight of the MODE transition contributed to the event.
Analysis of the Event
The condition was discovered during reactor startup activities after the reactor had been shut down for several weeks for a planned refueling. The condition of the fuel in the reactor at the time of the event had a low residual heat capacity. Adequate heat removal capability for the containment is provided by two separate engineered safety features systems. These are the containment spray system and the containment air recirculation cooling system.
The containment air recirculation cooling system is designed to recirculate and cool the containment atmosphere in the event of a loss of coolant accident and thereby ensure that the containment pressure cannot exceed its design values. The containment air recirculation cooling system is designed on the conservative assumption that the core residual heat is released to the containment as steam. Two of the four containment cooling units and one of two containment spray pumps will provide sufficient heat removal capability to maintain the post-accident containment pressure below the design values assuming the core residual heat is release to the containment as steam.
Safety Significance
The condition was determined to be of very low safety significance. Any design basis accident that could have occurred during the 39 minutes that the containment accident recirculation fans were not operable would not have exceeded design containment pressure or temperature limits because of the relatively low reactor coolant system residual heat. Two of the four containment accident recirculation fans were operable with the balance of the safety systems, structures or components needed to shut down the reactor, maintain safe shutdown conditions, remove residual heat, control the release of radioactive material or mitigate the consequences of an accident were operable or available. There was no impact on the health and safety of the public as a result of this condition.
Corrective Actions
05000266 YEAR 2016 SEQUENTIAL NUMBER 003 REV NO.
00 The two containment accident recirculation fans were immediately positioned to the required position for the MODE of operation. Corrective actions have been created to conduct training to all crews that will cover command and control, implementation of technical specifications, operating experience of this event, and revision to the cold to hot shutdown procedure.
Similar Events
LER 2013-002-00 has reported a similar event of LCO Application 3.0.4 in the past 3 years. However, the cause and corrective action of LER 2013-002-00 are not the same as this event.
Component Failure Data
None