LER-2015-006, Regarding Secondary Containment Differential Pressure Excursion |
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--- Entergy JAFP-15-0135 November 23, 2015 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Te! 315-349:6024 Fax 315-349-6480 Brian R. Sullivan Site Vice President - JAF
Subject:
LER: 2015-006-00, Secondary Containment Differential Pressure Excursion
Dear Sir or Madam:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 This report is submitted in accordance with 10 CFR 50. 73(a)(2)(v)(C).
There are no commitments contained in this report.
Questions concerning this report may be addressed to Mr. Chris M. Adner, Regulatory Assurance Manager, at (315) 349-6766.
Sincerely, r
BRS/CMA/ds Enclosure( s ): JAF LER: 2015-006-00, Secondary Containment Differential Pressure Excursion cc:
USNRC, Region 1 USNRC, Project Directorate USNRC, Resident Inspector
NRC FORM 366 (02-2014)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (02-2014)
LICENSEE EVENT REPORT (LER)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2017
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET
- 1. FACILITY NAME
- 2. DOCKET
- 6. LER NUMBER
- 3. PAGE James A. FitzPatrick Nuclear Power Plant 05000333 YEAR SEQUENTIAL NUMBER REV N0.
3 of 3 2015 -
006
00 Cause
Information relative to the cause of this condition will be provided in the supplemental report.
Similar Events
Internal Events Similar historical events that are potentially reportable were identified during preparation of this report. A more detail list will be provided in the supplemental report.
External events:
Susquehanna Steam Electric Station; Unit 1: LER 2015-005, Loss of Secondary Containment Differential Pressure During Ventilation Damper Testing.
Columbia Generating Station; LER 2013-007-01, Secondary Containment Pressure Exceeded During Severe Weather Conditions.
Corrective Actions
Corrective actions associated with this event will be tracked in the JAF CAP; additional information in this regard will be provided in the supplemental report.
Safety Consequence
There were no actual consequences caused by this event. SC provides a control volume to contain fission products that leak from primary containment, or are released directly to the secondary containment as a result of a Loss of Coolant Accident (LOCA) or Refueling Accident (RA).
The Design Basis (DB) LOCA event results in a rapid primary containment pressure increase and reactor water level decrease. Drywell High Pressure or Low Reactor Water Level signals directly isolate the RBV, and start SBGT. Fuel damage caused by a DB LOCA is not expected until a rise in fuel cladding temperature after coolant is lost. The SC differential pressure was positive for approximately 10 seconds during the RBV isolation reported in this LER. Therefore, it would have occurred early in the DB LOCA event. RBV isolation and initiation of SBGT would have been completed prior to fuel failure and release of radiological materials.
The DB RA event results in a release of radioactive material by a dropped fuel assembly during refuel operations. Radiation detectors would detect the release and initiate SC isolation. The pressure change reported in this LER would have caused some exfiltration before the isolation was complete; however, the amount of exfiltration, consequentially the offsite and control room doses, would remain below regulatory limits.
References Condition Report: CR-JAF-2015-04198, September 22, 2015, Secondary Containment Differential Pressure Excursion Condition Report: CR-JAF-2015-04893, Failure to Immediately Report the Condition Documented in CR-JAF-2015-04198 Nuclear Safety Evaluation: JAF-SE-96-071, Revision 2
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| | | Reporting criterion |
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| 05000333/LER-2015-001, Regarding COLR Thermal Limits Exceeded with Elevated Fuel Support Piece | Regarding COLR Thermal Limits Exceeded with Elevated Fuel Support Piece | 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) | | 05000333/LER-2015-002, Regarding Safety Relief Valve Upward Setpoint Drift | Regarding Safety Relief Valve Upward Setpoint Drift | 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) | | 05000333/LER-2015-003, Regarding Roof Maintenance Results in Secondary Containment Vacuum Below Technical Specification Limit | Regarding Roof Maintenance Results in Secondary Containment Vacuum Below Technical Specification Limit | 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) | | 05000333/LER-2015-004, Regarding Concurrent Opening of Reactor Building Airlock Doors | Regarding Concurrent Opening of Reactor Building Airlock Doors | 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) | | 05000333/LER-2015-005, Regarding Damper Failure Leads to Secondary Containment Vacuum Below Technical Specification Limit | Regarding Damper Failure Leads to Secondary Containment Vacuum Below Technical Specification Limit | 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) | | 05000333/LER-2015-006, Regarding Secondary Containment Differential Pressure Excursion | Regarding Secondary Containment Differential Pressure Excursion | | | 05000333/LER-2015-007, Regarding Slow Exhaust Fan Start Leads to Secondary Containment Vacuum Below Technical Specification Limit | Regarding Slow Exhaust Fan Start Leads to Secondary Containment Vacuum Below Technical Specification Limit | 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) | | 05000333/LER-2015-008, Regarding Containment Atmosphere Dilution System Reliability Degraded Due to Manufacturer Defect in Temperature Transmitters | Regarding Containment Atmosphere Dilution System Reliability Degraded Due to Manufacturer Defect in Temperature Transmitters | 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 21.21(d)(3)(ii), Failure to Comply or Defect
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) |
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