LER-2016-005, Regarding Plant Startup with Anticipatory Reactor Trip System in Main Turbine Bypass |
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10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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| 3462016005R00 - NRC Website |
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FE NOC' FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, Ohio 43449 Brian D. Boles Vice President, Nuclear July 11, 2016 L-16-177 ATTN: Document Control Desk United States Nuclear Regulatory Commission Washington, D.C. 20555-0001
Subject:
Davis-Besse Nuclear Power Station, Unit 1 Docket Number 50-346, License Number NPF-3 Licensee Event Report 2016-005 10 CFR 50.73 419-321-7676 Fax: 419-321-7582 Enclosed is Licensee Event Report (LER) 2016-005-00, "Plant Startup with Anticipatory Reactor Trip System in Main Turbine Bypass." This event is being reported pursuant to 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications.
There are no regulatory commitments contained in this letter or its enclosure, The actions described represent intended or planned actions and are described for information only. If there are any questions or if additional information is required, please contact Mr. Patrick J. McCloskey, Manager-Site Regulatory Compliance, at (419) 321-7274.
Sincerely,
~d~
Brian D. Boles GMW Enclosure: LER 2016-005 cc: NRC Region Ill Administrator NRC Resident Inspector NRR Project Manager Utility Radiological Safety Board
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (11-2015)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 2. DOCKET NUMBER 346 YEAR 2016
- 3. LER NUMBER SEQUENTIAL NUMBER 005 REV NO.
00 In support of the Operations Continuous Improvement Action Plan, operating crews will document at least one example of the Operator Fundamental Aspects of inquiry (validate assumptions) and advocacy from the Shift Crew Critiques. The Shift Manager will discuss these documented results during the End of Cycle Crew Performance Evaluation Meetings.
The TemporaryTest Procedure DB-TP-10405 has been voided, and operating procedures that manipulate/verify the ARTS Trip Bypass switches (such as DB-OP-06902) will be modified to provide more specific guidance for the operation of the switches.
PREVIOUS SIMILAR EVENTS
There have been no LERs at the DBNPS in the past three years involving the inoperability of the ARTS.
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| 05000346/LER-2016-001, Regarding Reactor Trip During Nuclear Instrumentation Calibrations and Steam Feedwater Rupture Control System Actuation on High Steam Generator Level | Regarding Reactor Trip During Nuclear Instrumentation Calibrations and Steam Feedwater Rupture Control System Actuation on High Steam Generator Level | | | 05000346/LER-2016-002, Regarding Unanticipated Steam and Feedwater Rupture Control System Actuation | Regarding Unanticipated Steam and Feedwater Rupture Control System Actuation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000346/LER-2016-003, Regarding Leak from Reactor Coolant Pump Seal Piping Flexible Hose Due to Undetected Manufacture Weld Defect | Regarding Leak from Reactor Coolant Pump Seal Piping Flexible Hose Due to Undetected Manufacture Weld Defect | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | | 05000346/LER-2016-004, Regarding Reactor Coolant System Hot Leg Resistance Temperature Detector Wire Insulation Degradation | Regarding Reactor Coolant System Hot Leg Resistance Temperature Detector Wire Insulation Degradation | 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) | | 05000346/LER-2016-005, Regarding Plant Startup with Anticipatory Reactor Trip System in Main Turbine Bypass | Regarding Plant Startup with Anticipatory Reactor Trip System in Main Turbine Bypass | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000346/LER-2016-006, Potential to Trip Emergency Diesel Generator on High Crankcase Pressure | Potential to Trip Emergency Diesel Generator on High Crankcase Pressure | 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)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(viii)(A) | | 05000346/LER-2016-007, Regarding Pressurizer Code Safety Valve Setpoint Test Failures | Regarding Pressurizer Code Safety Valve Setpoint Test Failures | 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)(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) | | 05000346/LER-2016-008, Regarding Application of Technical Specification for the Safety Features Actuation System Instrumentation | Regarding Application of Technical Specification for the Safety Features Actuation System Instrumentation | 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)(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)(B) | | 05000346/LER-2016-009, Regarding Reactor Trip Due to Rainwater Intrusion and Auxiliary Feedwater Actuation on High Steam Generator Level | Regarding Reactor Trip Due to Rainwater Intrusion and Auxiliary Feedwater Actuation on High Steam Generator Level | 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)(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) |
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