Letter Sequence Request |
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Results
Other: GO2-13-034, Northwests Response to NRC Order EA-12-049 - Overall Integrated Plan for Mitigating Strategies, GO2-13-121, First Six Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation, GO2-15-032, Fourth Six-Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation, ML13071A470, ML13337A266, ML13357A322, ML14254A403, ML14254A408, ML15006A322, ML15139A462
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MONTHYEARML12040A0772012-01-31031 January 2012 NEDO-33697, Revision 1, Columbia Generating Station Power Range Neutron Monitoring System Design Analysis Report Project stage: Request GO2-12-135, Response to Request for Additional Information Regarding License Amendment Request to Implement Prnmiarts/Mellla2012-10-0505 October 2012 Response to Request for Additional Information Regarding License Amendment Request to Implement Prnmiarts/Mellla Project stage: Response to RAI ML13015A2722012-12-31031 December 2012 NEDO-33685, Rev 2, Digital I&C-ISG-06 Compliance for Columbia Generating Station Numac Power Range Neutron Monitoring Retrofit Plus Option III Stability Trip Function Project stage: Request ML13071A4702013-02-28028 February 2013 Response to NRC Order EA-12-051-Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation Project stage: Other 05000397/LER-2012-007, For Columbia Generating Station Regarding Secondary Containment Inoperable Due to Both Airlock Doors Being Open2013-02-28028 February 2013 For Columbia Generating Station Regarding Secondary Containment Inoperable Due to Both Airlock Doors Being Open Project stage: Request GO2-13-034, Northwests Response to NRC Order EA-12-049 - Overall Integrated Plan for Mitigating Strategies2013-02-28028 February 2013 Northwests Response to NRC Order EA-12-049 - Overall Integrated Plan for Mitigating Strategies Project stage: Other GO2-13-059, Response to Request for Additional Information Regarding License Amendment Request to Implement Prnm/Arts/Mellla2013-04-11011 April 2013 Response to Request for Additional Information Regarding License Amendment Request to Implement Prnm/Arts/Mellla Project stage: Response to RAI ML13165A0932013-06-20020 June 2013 Redacted, Request for Additional Information, Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: RAI ML13179A1402013-07-0909 July 2013 Online Reference Portal for Review of Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order EA-12-049) Project stage: Approval GO2-13-100, Response to Request for Additional Information Related to the Overall Integrated Plan for Spent Fuel Pool Instrumentation2013-07-19019 July 2013 Response to Request for Additional Information Related to the Overall Integrated Plan for Spent Fuel Pool Instrumentation Project stage: Response to RAI GO2-13-121, First Six Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation2013-08-23023 August 2013 First Six Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation Project stage: Other ML13302C1362013-11-0707 November 2013 Redacted Letter, Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation Project stage: RAI ML13357A3222013-12-21021 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Columbia Generating Station, TAC No.: MF0796 Project stage: Other GO2-14-016, Update to Response to NRC 10 CFR 50.54(F) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Flooding - Review of Available Physical Margin (APM) Assessments2014-01-29029 January 2014 Update to Response to NRC 10 CFR 50.54(F) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Flooding - Review of Available Physical Margin (APM) Assessments Project stage: Request ML13337A2662014-01-29029 January 2014 Interim Staff Evaluation and Audit Report Related to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) Project stage: Other ML14254A4032014-08-28028 August 2014 Third Six-Month Status Update Report for the Implementation of NRC Order EA-12-049, Mitigation Strategies for Beyond Design Basis External Events Project stage: Other ML14254A4082014-08-28028 August 2014 Third Six-Month Status Update Report for the Implementation of NRC Order EA-12-051, Reliable Spent Fuel Pool Instrumentation Project stage: Other ML15006A3222015-01-16016 January 2015 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other GO2-15-032, Fourth Six-Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation2015-02-27027 February 2015 Fourth Six-Month Status Update Report for the Implementation of NRC Order EA-12-051 Reliable Spent Fuel Pool Instrumentation Project stage: Other ML15139A4622015-06-16016 June 2015 Report for the Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other 2013-06-20
[Table View] |
LER-2012-007, For Columbia Generating Station Regarding Secondary Containment Inoperable Due to Both Airlock Doors Being Open |
| Event date: |
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| Report date: |
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| Reporting criterion: |
10 CFR 50.73(a)(2)(v), Loss of Safety Function
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)(i)(B), Prohibited by Technical Specifications |
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| 3972012007R00 - NRC Website |
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text
W. Grover Hettel ENERGY Columbia Generating Station P.O. Box 968, PE23 Richland, WA 99352-0968 Ph. 509.377.8311 I F. 509.377.4150 wghettel @energy-northwest.com February 28, 2013 G02-13-033 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 LICENSEE EVENT REPORT NO. 2012-007-00
Dear Sir or Madam:
Transmitted herewith is Licensee Event Report No. 2012-007-00 for Columbia Generating Station. This report is submitted pursuant to 10 CFR 50.73(a)(2)(v)(C) and (D), which requires the reporting of any condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to: control the release of radioactive material and mitigate the consequences of an accident.
There are no commitments being made to the NRC by this letter. If you have any questions or require additional information, please contact Mr. ZK Dunham at (509) 377-4735.
Respectfully, WG Hettel Vice President, Operations Attachment: Licensee Event Report 2012-007-00 cc: NRC Region IV Administrator NRC NRR Project Manager NRC Senior Resident Inspector/988C AJ Rapacz - BPA/1 399 WA Horin - Winston & Strawn
P NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 10/31/2013 (10-2010)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Columbia Generating Station 05000397 1 OF 3
- 4. TITLE Secondary Containment Inoperable due to both Airlock Doors being Open
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER NUMBER NO.
05000 FACILITY NAME DOCKET NUMBER 12 30 2012 2012 - 007 - 00 02 28 2013 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITITED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1 El 20.2201(b)
El 20.2203(a)(3)(i)
[3 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
El 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203 (a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
-] 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [3 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x) 100 [1 20.2203(a)(2)(iii)
El 50.36(c)(2)
C3 50.73(a)(2)(v)(A)
El 73.71(a)(4)
C3 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
C3 50.73(a)(2)(v)(B)
El 73.71 (a)(5)
El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)
Specify in Abstract below or in provide warning to personnel outside the airlock when the airlock is in use.
- 2. Revise Technical Specification bases for SR 3.6.4.1.2 and SR 3.6.4.1.3 to ensure that the wording clearly identifies that Secondary Containment operability requires that one door in each airlock be closed at all times when Secondary Containment is required.
ASSESSMENT OF SAFETY CONSEQUENCES
There was no equipment damage, injuries or dose exposure to station personnel. There was no change in plant status or operating condition and there was no actual risk to the public at any time. There was no impact to public health and safety as the Primary Containment was intact, and Secondary Containment ventilation system maintained the designed negative pressure inside the Reactor Building during the event.
There was a potential significance if there had been an event where the Primary Containment was breached concurrent with a loss of coolant accident or a fuel handing accident such that radioactive materials were released to the Reactor Building. Having both Reactor Building airlock doors open would potentially provide a release path for radioactive materials to enter the external environment.
SIMILAR EVENTS
A review of various databases at Columbia found a total of 40 similar events dating back to 1995. Not all of these events resulted in a loss of Secondary Containment. Some of these events occurred during a Mode in which Secondary Containment was not required to be operable. Some were an interlock failure only and both doors were not opened simultaneously.
A review of the NRC Event Notification database found the following similar events:
Event Notification 45975, 6/3/10 at Monticello Event Notification 46155, 8/5/10 at Monticello Event Notification 46394, 11/4/10 at Monticello Event Notification 48282, 9/6/12 at Quad Cities Event Notification 48295, 9/10/12 at Cooper ENERGY INDUSTRY IDENTIFICATION SYSTEM (EIIS) INFORMATION CODES EIIS codes are bracketed [] where applicable in the narrative.
26158 R5
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| 05000397/LER-2012-001, Regarding DG-3 Inoperable for Longer than Allowed by TS Due to Failed Governor | Regarding DG-3 Inoperable for Longer than Allowed by TS Due to Failed Governor | 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) | | 05000397/LER-2012-002, Regarding Technical Specification Non-Compliance Due to Inadequate Procedure Guidance | Regarding Technical Specification Non-Compliance Due to Inadequate Procedure Guidance | 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) | | 05000397/LER-2012-003, Regarding Secondary Containment Pressure Exceeded During Plant Maintenance | Regarding Secondary Containment Pressure Exceeded During Plant Maintenance | 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) | | 05000397/LER-2012-004-02, Regarding Failure to Meet Technical Specifications Completion Time for Offsite Power | Regarding Failure to Meet Technical Specifications Completion Time for Offsite Power | 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) | | 05000397/LER-2012-004-01, Regarding Failure to Meet Technical Specifications Completion Time for Offsite Power | Regarding Failure to Meet Technical Specifications Completion Time for Offsite Power | 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) | | 05000397/LER-2012-004, Regarding Failure to Meet Technical Specifications Completion Time for Offsite Power | Regarding Failure to Meet Technical Specifications Completion Time for Offsite Power | 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) | | 05000397/LER-2012-005, Regarding Violation of Technical Specifications Due to the Failure to Enter the Appropriate Technical Specification | Regarding Violation of Technical Specifications Due to the Failure to Enter the Appropriate Technical Specification | 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) | | 05000397/LER-2012-006-01, Regarding Both Visions of SDC Isolation Valves Made Inoperable | Regarding Both Visions of SDC Isolation Valves Made Inoperable | | | 05000397/LER-2012-006, Regarding Both Divisions of SDC Isolation Valves Made Inoperable | Regarding Both Divisions of SDC Isolation Valves Made Inoperable | 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) | | 05000397/LER-2012-007, For Columbia Generating Station Regarding Secondary Containment Inoperable Due to Both Airlock Doors Being Open | For Columbia Generating Station Regarding Secondary Containment Inoperable Due to Both Airlock Doors Being Open | 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) |
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