LER-2005-004, Regarding Noncompliance with the Technical Specification for Offsite AC Sources |
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| Report date: |
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| 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)
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
10 CFR 50.73(a)(2)(1) |
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| 4432005004R00 - NRC Website |
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FPL Energy Seabrook Station FPL Energy Seabrook Station P.O. Box 300 Seabrook, NH 03874 (603) 773-7000 May 19, 2005 Docket No. 50-443 SBK-L-05084 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station Licensee Event Report (LER) 2005-004-00 for Noncompliance with the Technical Specification for Offsite AC Sources Enclosed is Licensee Event Report (LER) 2005-004-00. This LER reports an event that occurred at Seabrook Station on March 29, 2005.
This event is being reported pursuant to the requirements of 10 CFR 50.73(a)(2)(i)(B).
Should you require further information regarding this matter, please contact Mr. James M.
Peschel, Regulatory Programs Manager (603) 773-7194.
Very truly yours, FPL ENERGY SEABROOK, LLC Mark E. Warner Site Vice President cc:
S. J. Collins, NRC Region I Administrator V. Nerses, NRC Project Manager, Project Directorate I-2 G. T. Dentel, NRC Senior Resident Inspector
)~2i2 an FPL Group company
ENCLOSURE TO SBK-L-05084
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may digitstcharacters for each block)
Inot ont or sponsor, and a person is not required to respond to, the
- 3. PAGE Seabrook Station 05000 4 1 OF 3
- 4. TITLE Noncompliance with the Technical Specification for Offsite AC Sources
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEA SEUMERTA NO MONTH DAY YEAR 'N/A 05000 FACILITY NAME DOCKET NUMBER 03 29 2005 2005 - 004 -
00 05 19 2005 N/A 05000
- 9. OPERATING MODE
.THISREPORT IS SUBMITEDPURSUANT)TOTHE REQUIREMENTSOF OCFR§: (Checkallthatapply) o 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii) 1CE 20.2201 (d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)viii)(A) o 20.2203(a)(1) 0 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
E 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
E 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
D 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
E 20.2203(a)(2)(iii)
El 50.36(c)(2) a 50.73(a)(2)(v)(A)
E 73.71(a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(li) a 50.73(a)(2)(v)(B)
El 73.71 (a)(5) 95 El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
ED OTHER El 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)
Specify In Abstract below or in (if more space Is required, use additional copies of (if more space is required, use additional copies of NRC Form 366A) (17) physically independent circuits (one UAT and one RAT) from the transmission network to the onsite distribution system. On this basis, the actions of TS 3.8.1.1 were not applied to the loss of the RAT supply to the train A emergency bus. However, the licensing basis review and NRC meeting determined that the two independent power supplies should be provided to each train of the 1 E distribution system.
For this reason, the unavailability of the RAT supply to the emergency bus rendered one offsite AC source inoperable.
This event is of regulatory significance because it met the reporting criterion of 10 CFR 50.73 (a)(2)(1)(B) for a condition prohibited by the TS. In addition, the event was reported to the NRC on March 29, 2005 at 1524 (event # 41543) in accordance with the Facility Operating License Condition 2.G for a violation of the TS.
This event had no adverse impact on the plant or on the health and safety of the public. No plant transients, systems actuations, or consequences resulted from this event. This event did not involve a Safety System Functional Failure since two independent offsite AC sources remained available to the train B emergency bus. No inoperable structures, systems, or components contributed to the event.
IV. Corrective Actions
The corrective actions for this event included:
- 1. Revising the TS bases and the UFSAR as necessary to reflect that operability of an offsite AC source requires the source be available to both trains of emergency buses, and
- 2. Communicating to station managers, supervisors, and licensed operators the revised criteria for operability of offsite AC sources.
Similar Events
Seabrook Station has had one previous occurrence of an event in which incorrect procedure implementation resulted in a condition prohibited by the TS. On August 15, 2003, LER 2003-001 reported that station personnel incorrectly concluded that surveillance testing of an emergency diesel generator was not required to meet the actions of a TS. A review of the condition determined that such testing was required, and the failure to meet the actions while in noncompliance with the LCO resulted in a condition prohibited by the TS.
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| 05000443/LER-2005-001, Regarding Noncompliance with the Requirements of Technical Specification 3.6.3 | Regarding Noncompliance with the Requirements of Technical Specification 3.6.3 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000443/LER-2005-002, Regarding Momentary Loss of Power to Emergency Bus While Transferring Power Supplies | Regarding Momentary Loss of Power to Emergency Bus While Transferring Power Supplies | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000443/LER-2005-003, Regarding Plant Shutdown Due to Inoperable Reactor Trip Breaker | Regarding Plant Shutdown Due to Inoperable Reactor Trip Breaker | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000443/LER-2005-004, Regarding Noncompliance with the Technical Specification for Offsite AC Sources | Regarding Noncompliance with the Technical Specification for Offsite AC Sources | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000443/LER-2005-005, Re Reactor Protection System Actuation on Low Steam Generator Low Level in Mode 6 | Re Reactor Protection System Actuation on Low Steam Generator Low Level in Mode 6 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000443/LER-2005-006, Manual Reactor Trip Due to Main Turbine High Vibration | Manual Reactor Trip Due to Main Turbine High Vibration | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | | 05000443/LER-2005-007, Re Noncompliance with the Technical Specifications Due to Circuit Card Failure | Re Noncompliance with the Technical Specifications Due to Circuit Card Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000443/LER-2005-008, Regarding Technical Specification Violation Due to Inoperable Instrument Bus Inverter | Regarding Technical Specification Violation Due to Inoperable Instrument Bus Inverter | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
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