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Category:Letter
MONTHYEARLIC-25-0002, Independent Spent Fuel Storage Installation - Transmittal of Annual Radioactive Effluent Release Report2025-01-30030 January 2025 Independent Spent Fuel Storage Installation - Transmittal of Annual Radioactive Effluent Release Report LIC-25-0001, Independent Spent Fuel Storage Installation - Response to Acceptance of Requested Licensing Action License Amendment Request to Revise the License Termination Plan (L-2024-LLA-0095)2025-01-16016 January 2025 Independent Spent Fuel Storage Installation - Response to Acceptance of Requested Licensing Action License Amendment Request to Revise the License Termination Plan (L-2024-LLA-0095) LIC-24-0017, ISFSI - Phase 1 Final Status Survey Report to Support Approved License Termination Plan, Revision 1; and Technical Support Document for the Ludlum 44-20 Detector Sensitivity2024-11-21021 November 2024 ISFSI - Phase 1 Final Status Survey Report to Support Approved License Termination Plan, Revision 1; and Technical Support Document for the Ludlum 44-20 Detector Sensitivity LIC-24-0015, Response to Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (DQAP) – Clarification of Request for Additional Information Response2024-11-20020 November 2024 Response to Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (DQAP) – Clarification of Request for Additional Information Response LIC-24-0016, Independent Spent Fuel Storage Installation - 2024 Decommissioning Funding Plan Required 72.30(c) Updated Financial Information2024-11-19019 November 2024 Independent Spent Fuel Storage Installation - 2024 Decommissioning Funding Plan Required 72.30(c) Updated Financial Information ML24318C2532024-11-18018 November 2024 Acceptance of Requested Licensing Action License Amendment Request to Revise the License Termination Plan (L-2024-LLA-0095) IR 05000285/20240032024-10-29029 October 2024 NRC Inspection Report 05000285/2024003 LIC-24-0013, Independent Spent Fuel Storage Installation - Intent to Submit a Supplement to 2021, and 2024 Nuclear Decommissioning Funding Plan Required 72.30(c) Update2024-10-10010 October 2024 Independent Spent Fuel Storage Installation - Intent to Submit a Supplement to 2021, and 2024 Nuclear Decommissioning Funding Plan Required 72.30(c) Update LIC-24-0014, Independent Spent Fuel Storage Installation - Supplement to 2021, and 2024 Nuclear Decommissioning Funding Plan Required 72.30(c) Update2024-10-10010 October 2024 Independent Spent Fuel Storage Installation - Supplement to 2021, and 2024 Nuclear Decommissioning Funding Plan Required 72.30(c) Update LIC-24-0012, Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information2024-10-0707 October 2024 Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information LIC-24-0011, Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-00952024-10-0202 October 2024 Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-0095 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24243A1042024-09-12012 September 2024 Proposed Revision to the OPPD FCS DQAP - Request for Additional Information (License No. DPR-40, Docket Nos. 50-285, 72-054, and 71-0256) ML24255A0962024-09-12012 September 2024 License Amendment Request to Revise the License Termination Plan - Request Supplemental Information (License No. DPR-40, Docket No. 50-285) IR 05000285/20240022024-08-21021 August 2024 NRC Inspection Report 05000285/2024002 ML24235A0822024-08-10010 August 2024 Response to Fort Calhoun Station, Unit No. 1 - Phase 1 Final Status Survey Report to Support Approved License Termination Plan - Request for Additional Information - Request for Additional Information (EPID L-2024-DFR-0002) July 8, 2024 ML24183A3222024-07-0808 July 2024 Proposed Revision to the Omaha Public Power District Fort Calhoun Station Decommissioning Quality Assurance Plan - Acceptance Review ML24180A2082024-07-0808 July 2024 Phase 1 Final Status Survey Reports Request for Additional Information Letter LIC-24-0007, License Amendment Request (LAR) to Revise License Termination Plan (LTP)2024-06-18018 June 2024 License Amendment Request (LAR) to Revise License Termination Plan (LTP) IR 05000285/20240012024-06-0505 June 2024 NRC Inspection Report 05000285/2024001 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities LIC-24-0008, Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI2024-05-16016 May 2024 Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI LIC-24-0003, Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report2024-04-25025 April 2024 Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-24-0006, (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan2024-04-17017 April 2024 (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan ML24079A1702024-03-10010 March 2024 ISFSI, Unit 1 - 10 CFR 50.59 Report, Quality Assurance (QA) Program Changes, Technical Specification Basis Changes, 10 CFR 71.106 Quality Assurance Program Approval, Aging Management Review, Commitment Revisions and Revision of Updated Safe LIC-24-0005, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2024-03-0101 March 2024 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-24-0002, Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report2024-02-27027 February 2024 Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report ML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements IR 05000285/20230062023-12-21021 December 2023 NRC Inspection Report 05000285/2023006 LIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information IR 05000285/20230052023-11-0202 November 2023 NRC Inspection Room 05000285/2023005 ML23276A0042023-09-28028 September 2023 U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 – (License No. DPR-40, Docket No. 50-285) IR 05000285/20230042023-09-13013 September 2023 NRC Inspection Report 05000285/2023-004 LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request IR 05000285/20230032023-07-10010 July 2023 – NRC Inspection Report 05000285/2023003 ML23082A2202023-06-26026 June 2023 Consultation on the Decommissioning of the Fort Calhoun Station Unit 1 Pressurized Water Reactor in Fort Calhoun, Nebraska IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 ML23151A0032023-06-0505 June 2023 – Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML23020A0462023-01-19019 January 2023 Threatened and Endangered Species List: Nebraska Ecological Services Field Office IR 05000285/20220062023-01-0505 January 2023 NRC Inspection Report 05000285/2022-006 ML22357A0662022-12-30030 December 2022 Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan IR 05000285/20220052022-10-26026 October 2022 NRC Inspection Report 05000285/2022-005 2025-01-30
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000285/LER-1917-001, Regarding Unprotected Vital Area Barrier Due to Maintenance2017-05-11011 May 2017 Regarding Unprotected Vital Area Barrier Due to Maintenance 05000285/LER-2016-003, Regarding Unplanned Turbine Trip During DCS Modification Due to Failure to Identify and Disable the Transmitter Deviation Based Trip2016-08-22022 August 2016 Regarding Unplanned Turbine Trip During DCS Modification Due to Failure to Identify and Disable the Transmitter Deviation Based Trip 05000285/LER-2016-002, Regarding Unanalyzed Condition Shutdown Heat Exchanger Isolations2016-07-0707 July 2016 Regarding Unanalyzed Condition Shutdown Heat Exchanger Isolations 05000285/LER-2016-001, Regarding Technical Specification Violation Due to Installation of an Unqualified Part in a Radiation Monitor2016-04-0808 April 2016 Regarding Technical Specification Violation Due to Installation of an Unqualified Part in a Radiation Monitor 05000285/LER-2015-006, Regarding Unanalyzed Fire Vulnerability Due to Inadequate Design2015-12-11011 December 2015 Regarding Unanalyzed Fire Vulnerability Due to Inadequate Design 05000285/LER-2015-005, Regarding Reactor Coolant Leak at Reactor Coolant Pump Seal Due to Cyclic Fatigue2015-09-17017 September 2015 Regarding Reactor Coolant Leak at Reactor Coolant Pump Seal Due to Cyclic Fatigue 05000285/LER-2015-004, Regarding Inoperability of Auxiliary Feedwater Trains Due to Failure of Steam Generator Isolation Valve2015-08-0303 August 2015 Regarding Inoperability of Auxiliary Feedwater Trains Due to Failure of Steam Generator Isolation Valve 05000285/LER-2015-003, Regarding Containment Spray Inoperable Due to Original Design Error2015-06-15015 June 2015 Regarding Containment Spray Inoperable Due to Original Design Error 05000285/LER-2015-002, Regarding Inoperable Auxiliary Feedwater System Due to Inadequate Procedure Change2015-05-28028 May 2015 Regarding Inoperable Auxiliary Feedwater System Due to Inadequate Procedure Change 05000285/LER-2015-001, Regarding Inadequate Design of High Energy Line Break Barriers2015-03-27027 March 2015 Regarding Inadequate Design of High Energy Line Break Barriers 05000285/LER-2014-007, Regarding Plant Trip Due to Moisture Intrusion Into a Transformer Control Cabinet2015-02-13013 February 2015 Regarding Plant Trip Due to Moisture Intrusion Into a Transformer Control Cabinet 05000285/LER-2013-014-02, Regarding Unqualified Components Used in Safety System Control Circuit2015-01-29029 January 2015 Regarding Unqualified Components Used in Safety System Control Circuit 05000285/LER-2014-006, Regarding Inoperability of Radiation Monitors Due to an Error in Technical Specifications2014-11-12012 November 2014 Regarding Inoperability of Radiation Monitors Due to an Error in Technical Specifications 05000285/LER-2014-005, Regarding Technical Specification Violation of Containment Integrity2014-08-25025 August 2014 Regarding Technical Specification Violation of Containment Integrity 05000285/LER-2014-004, Regarding Unqualified Limit Switches Render Safety Equipment Inoperable2014-06-20020 June 2014 Regarding Unqualified Limit Switches Render Safety Equipment Inoperable 05000285/LER-2014-003, Regarding Reactor Trip Due to Stator Water Cooling Leak During Maintenance2014-05-14014 May 2014 Regarding Reactor Trip Due to Stator Water Cooling Leak During Maintenance 05000285/LER-2013-014-01, 1 for Fort Calhoun Station Regarding Unqualified Components Used in Safety System Control Circuit2014-05-0202 May 2014 1 for Fort Calhoun Station Regarding Unqualified Components Used in Safety System Control Circuit 05000285/LER-2013-019-01, 1 for Fort Calhoun Regarding Non-Seismic Circulating Water Pipe Could Disable Raw Water Pumps2014-04-14014 April 2014 1 for Fort Calhoun Regarding Non-Seismic Circulating Water Pipe Could Disable Raw Water Pumps 05000285/LER-2014-002, Regarding Reactor Manual Trip Due to Control Rod Misalignment2014-03-12012 March 2014 Regarding Reactor Manual Trip Due to Control Rod Misalignment 05000285/LER-2014-001, Regarding Reactor Shutdown Due to Sluice Gate Failure2014-03-0707 March 2014 Regarding Reactor Shutdown Due to Sluice Gate Failure 05000285/LER-2013-015-01, Regarding Unqualified Coating Used as a Water Tight Barrier in Rooms 81 and 822014-02-14014 February 2014 Regarding Unqualified Coating Used as a Water Tight Barrier in Rooms 81 and 82 05000285/LER-2013-019, Regarding Non-Seismic Circulating Water Pipe Could Disable Raw Water Pumps2014-01-31031 January 2014 Regarding Non-Seismic Circulating Water Pipe Could Disable Raw Water Pumps 05000285/LER-2013-016, Regarding Reporting of Additional High Energy Line Break Concerns2014-01-0606 January 2014 Regarding Reporting of Additional High Energy Line Break Concerns 05000285/LER-2013-017, Regarding Containment Spray Pump Design Documents Do Not Support Operation in Runout2013-12-27027 December 2013 Regarding Containment Spray Pump Design Documents Do Not Support Operation in Runout 05000285/LER-2013-018, Regarding Postulated Fire Event Could Result in Shorts Impacting Safe Shutdown2013-12-26026 December 2013 Regarding Postulated Fire Event Could Result in Shorts Impacting Safe Shutdown 05000285/LER-2013-008-01, Regarding Previously Installed GE Iva Relays Failed Seismic Testing2013-12-18018 December 2013 Regarding Previously Installed GE Iva Relays Failed Seismic Testing 05000285/LER-2013-014, Regarding Unqualified Components Used in Safety System Control Circuit2013-12-18018 December 2013 Regarding Unqualified Components Used in Safety System Control Circuit 05000285/LER-2012-017-02, Regarding Containment Valve Actuators Design Temperature Ratings Below Those Required for Design Basis Accidents2013-12-0606 December 2013 Regarding Containment Valve Actuators Design Temperature Ratings Below Those Required for Design Basis Accidents 05000285/LER-2013-013, Unqualified Components Used in Safety System Control Circuit2013-12-0202 December 2013 Unqualified Components Used in Safety System Control Circuit 05000285/LER-2013-015, Regarding Unqualified Coating Used as a Water Tight Barrier in Rooms 81 and 822013-11-12012 November 2013 Regarding Unqualified Coating Used as a Water Tight Barrier in Rooms 81 and 82 05000285/LER-2012-009-01, Inoperable Equipment Due to Lack of Environmental Qualifications2013-10-31031 October 2013 Inoperable Equipment Due to Lack of Environmental Qualifications 05000285/LER-2013-010-01, Regarding HPSI Pump Flow Imbalance2013-10-23023 October 2013 Regarding HPSI Pump Flow Imbalance 05000285/LER-2012-015-01, Fort Calhouns Station Re Electrical Equipment Impacted by High Energy Line Break Outside Containment2013-09-30030 September 2013 Fort Calhouns Station Re Electrical Equipment Impacted by High Energy Line Break Outside Containment 05000285/LER-2013-012, Regarding Intake Structure Crane Seismic Qualification2013-09-30030 September 2013 Regarding Intake Structure Crane Seismic Qualification 05000285/LER-2013-006-01, Regarding Use of Teflon in LPSI and CS Pump Mechanical Seal2013-08-26026 August 2013 Regarding Use of Teflon in LPSI and CS Pump Mechanical Seal 05000285/LER-2013-007-01, Regarding Containment Air Cooling Unit (VA-16A/B) Seismic Criteria2013-08-16016 August 2013 Regarding Containment Air Cooling Unit (VA-16A/B) Seismic Criteria 05000285/LER-2013-011, The Fort Calhoun Station, Inadequate Design for High Energy Line Break in Rooms 13 and 19 of the Auxiliary Building2013-08-12012 August 2013 The Fort Calhoun Station, Inadequate Design for High Energy Line Break in Rooms 13 and 19 of the Auxiliary Building 05000285/LER-2013-005-01, Regarding Control Room HVAC Modification Not Properly Evaluated2013-07-31031 July 2013 Regarding Control Room HVAC Modification Not Properly Evaluated 05000285/LER-2013-010, Regarding HPSI Pump Flow Imbalance2013-07-0202 July 2013 Regarding HPSI Pump Flow Imbalance 05000285/LER-2012-016-01, Regarding Unanalyzed Charging System Socket Welds to the Reactor Coolant System2013-06-25025 June 2013 Regarding Unanalyzed Charging System Socket Welds to the Reactor Coolant System 05000285/LER-2013-009, Regarding Tornado Missile Vulnerabilities2013-06-14014 June 2013 Regarding Tornado Missile Vulnerabilities 05000285/LER-2013-008, The Fort Calhoun Station, Previously Installed GE Iav Relays Failed Seismic Testing2013-06-0707 June 2013 The Fort Calhoun Station, Previously Installed GE Iav Relays Failed Seismic Testing 05000285/LER-2013-007, Regarding Containment Air Cooling Units (VA-16A/B) Seismic Criteria2013-06-0404 June 2013 Regarding Containment Air Cooling Units (VA-16A/B) Seismic Criteria 05000285/LER-2012-019-01, Regarding Traveling Screen Sluice Gates Found with Dual Indication2013-05-14014 May 2013 Regarding Traveling Screen Sluice Gates Found with Dual Indication 05000285/LER-2012-018-01, Regarding Containment Air Cooling Units Not Properly Tested During Cycle 262013-05-0808 May 2013 Regarding Containment Air Cooling Units Not Properly Tested During Cycle 26 05000285/LER-2013-006, Use of Teflon in LPSI and CS Pump Mechanical Seals2013-05-0303 May 2013 Use of Teflon in LPSI and CS Pump Mechanical Seals 05000285/LER-2013-005, Regarding Control Room HVAC Modification Not Properly Evaluated2013-04-29029 April 2013 Regarding Control Room HVAC Modification Not Properly Evaluated 05000285/LER-2013-004, Regarding Inverters Inoperable During Emergency Diesel Generator Operation2013-04-23023 April 2013 Regarding Inverters Inoperable During Emergency Diesel Generator Operation 05000285/LER-2013-003, Regarding Calculations Indicate the HPSI Pumps Will Operate in Run-out During a DBA2013-04-0101 April 2013 Regarding Calculations Indicate the HPSI Pumps Will Operate in Run-out During a DBA 05000285/LER-2013-002, Regarding CVCS Class 1 & 2 Charging Supports Are Unanalyzed2013-03-26026 March 2013 Regarding CVCS Class 1 & 2 Charging Supports Are Unanalyzed 2017-05-11
[Table view] |
LER-2010-003, Regarding Inadequate Margin Renders Auxiliary Feedwater Pump Inoperable |
Event date: |
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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)(v)(8)
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)(v), Loss of Safety Function |
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2852010003R00 - NRC Website |
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text
August 10, 2010 L I C-1 0-0063 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Reference: Docket No. 50-285
Subject:
Licensee Event Report 2010-003, Revision 0, for the Fort Calhoun Station Please find attached Licensee Event Report 2010-003, Revision 0, dated August 10, 2010. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B) and 10 CFR 50.73 (a)(2)(v)(8).
No regulatory commitments are contained in this submittal. If you should have any questions, please contact me.
JARlepm Attachment c:
E. E. Collins, NRC Regional Administrator, Region IV L. E. Wilkins, NRC Project Manager J. C. Kirkland, NRC Senior Resident Inspector INPO Records Center Employment with Equal Opportunity
NRC FORM 366 U.S. NUCLEAR REGULATORYCOMMISSION (9-2007)
LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME Fort Calhoun Station
- 2. DOCKET NUMBER 05000285
- 3. PAGE 1 OF 4
- 4. TITLE Inadequate Margin Renders Auxiliary Feedwater Pump Inoperable
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTI AL NUMBER REV NO MONT H
DAY YEAR FACILITY NAME DOCKET NUMBER 05000 04 06 2009 2010
- - 003 -
00 08 10 2010 FACILITY NAME 05000
- 9. OPERATING MODE 1
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 20.2201(b)
20.2203(a)(3)(i)
50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d)
20.2203(a)(3)(ii)
50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1)
20.2203(a)(4)
50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i)
50.36(c)(1)(i)(A)
50.73(a)(2)(iii) 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 100 20.2203(a)(2)(ii)
50.36(c)(1)(ii)(A)
50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii)
50.36(c)(2)
50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv)
50.46(a)(3)(ii)
X 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v)
50.73(a)(2)(i)(A)
50.73(a)(2)(v)(C)
OTHER 20.2203(a)(2)(vi)
X 50.73(a)(2)(i)(B)
50.73(a)(2)(v)(D)
Specify in Abstract below or in
EVENT DESCRIPTION
On April 6, 2009, FW-10 tripped off while performing Attachment 1 of OI-AFW-4 (FW-10 Turbine-Driven AFW Pump Operations) per OP-ST-AFW-0004 (Auxiliary Feedwater Pump FW-10 Operability Test). FW-10 tripped approximately one minute after it was successfully started. FW-10 discharge pressure switch (PS-1122) white indicating light was found lit on control panel AI-279 (Auxiliary Feedwater Pump FW-10 Discharge Overpressure Control Panel). This light indicates the pump tripped on high discharge pressure. In response to FW-10 tripping off, the control room operators entered TS 2.5(1)B which requires the inoperable pump to be restored to service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A troubleshooting plan was initiated to perform calibration of PS-1122 using IC-CP-01-1122 (Calibration of AFW Pump FW-10 High Discharge Pressure Shutdown Switch PS-1122) and to determine if calibration of the switch was within tolerance. The calibration verified the pressure switch was within tolerance, measuring 1464 pounds per square inch gage (psig) (acceptance criteria 1450 psig plus or minus 35 psig). Pump discharge pressure and speed were measured. The highest observed pump discharge pressure was approximately 1280 psig. The highest pump speed measured was 7927 revolutions per minute (rpm). The initial troubleshooting plan did not find the cause of the pressure switch actuation. Additional troubleshooting activities were performed, but the highest discharge pressure measured was less than 1290 psig, and steady state pressure was observed at 1240 psig. In addition, the pumps minimum recirculation valve FCV-1369 remained open during multiple pump starts.
On February 26, 2009, Facility Design Change Request (FDCR) 45607 (Revise the Acceptance Criteria in EC 45105) revised the acceptance criteria in Engineering Change (EC) 45105 (FW-10 Speed Limiting Governor Setting) to allow the discharge pressure to be increased beyond the 1170 to 1210 psig target range prescribed in the EC 45105. A new maximum pressure limit of 1280 psig was prescribed to ensure the typical minimum flow recirculation mode pressure was well below the surveillance test limit.
On April 6, 2009, it was concluded that the discharge pressure increase on February 26, 2009, may have contributed to this event, and it was recommended to increase the pressure switch setpoint from the current 1450 psig to 1600 psig. The setpoint was subsequently increased to 1600 psig on April 6, 2009. The event is documented in condition report (CR) 2009-1611.
During an NRC inspection the operability of FW-10 was questioned, during the period the speed limiting governor for FW-10 was increased until the discharge pressure trip was increased. Subsequently, on June 11, 2010, it was determined that FW-10 was inoperable from February 26, 2009, until April 6, 2009. The event was determined to be reportable pursuant to 10 CFR 50.73(a)(2)(i)(B) and 10 CFR 50.73(a)(2)(v)(B).
This event is being reported per 10 CFR 50.73(a)(2)(i)(B) and 10 CFR 50.73(a)(2)(v)(B).
CONCLUSION The root cause of this event was that EC 45105 (FW-10 Speed Limiting Governor Setting) and FDCR 45607 (Revise the Acceptance Criteria in EC 45105) reduced the discharge pressure margin to trip setpoint resulting in FW-10 becoming more susceptible to tripping on high discharge pressure.
On February 26, 2009, FDCR 45607 revised the acceptance criteria in EC 45105 to allow the discharge pressure to be increased beyond the 1170 to 1210 psig target range prescribed in the EC 45105. A new maximum pressure limit of 1280 psig was prescribed to ensure the typical minimum flow recirculation mode pressure was well below the surveillance test limit. It should also be noted that FDCR 45607 was implemented after maintenance adjusted the speed of the pump to approximately 7900 rpm. The 7900 rpm pump speed resulted in a steady state discharge pressure of approximately 1240 psig. Based on interview, it was decided that re-adjusting the speed to obtain a 1210 psig pressure would take too much TS limiting condition for operation (LCO) time. FDCR 45607 revised the maximum discharge pressure limit for FW-10 from 1210 psig to 1280 psig. This revised limit resulted in a 170 psig margin to the trip setpoint of 1450 psig (PS-1122 trip setpoint).
The reduction in the pressure margin to trip from approximately 290 psig (before EC 34435, June 2008) (1450 psig [PS-1122 setpoint] - 1160 psig [FW-10 discharge pressure before EC 34435]) to approximately 170 psig (1450 psig [PS-1122 setpoint] - 1280 psig [FW-10 discharge pressure after FDCR 45607]) after FDCR 45607 resulted in the pump tripping on April 6, 2009. The EC process did not identify or analyze this reduction as adverse because engineering personnel made the judgment that a 170 psig margin to trip was adequate. Engineers did not have the operational pressure data to conclusively determine if 170 psig was adequate.
CORRECTIVE ACTIONS
The setpoint for the AFW Pump FW-10 High Discharge Pressure Shutdown Switch PS-1122 was increased from 1450 psig to 1600 psig. Additional actions are being addressed by the stations corrective action system.
SAFETY SIGNIFICANCE
As previously described, any of the three auxiliary feedwater pumps are capable of supplying water to the steam generators to remove heat following potential accident scenarios at the station. For a short period of time the emergency power source for FW-6, Diesel Generator (DG)-1, was inoperable during routine surveillance testing.
Had DG-1 been needed for operation it could have been quickly returned to service. Periodic testing of FW-10, by starting the pump, prior to, and after the failure, demonstrated that the pump was likely to start as designed.
In addition, FW-54, although not safety related, was functional and able to supply water to the steam generators if needed. Therefore this event had very little impact on the health and safety of the public.
SAFETY SYSTEM FUNCTIONAL FAILURE This event does result in a safety system functional failure in accordance with NEI-99-02.
PREVIOUS SIMILAR EVENTS
No previous incidence of inadequate margin for the auxiliary feedwater pumps has occurred. PRINTED ON RECYCLED PAPER
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05000285/LER-2010-001, For Fort Calhoun Station, Regarding Containment Integrity Violated During Performance of Leak Test | For Fort Calhoun Station, Regarding Containment Integrity Violated During Performance of Leak Test | 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) | 05000285/LER-2010-002, Regarding Failed Feeder Cable Due to Inadequate Procedure Causes Station Shutdown | Regarding Failed Feeder Cable Due to Inadequate Procedure Causes Station Shutdown | 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) | 05000285/LER-2010-003, Regarding Inadequate Margin Renders Auxiliary Feedwater Pump Inoperable | Regarding Inadequate Margin Renders Auxiliary Feedwater Pump 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) 10 CFR 50.73(a)(2)(v)(8) | 05000285/LER-2010-004, For Fort Calhoun Station, Regarding Acoustic Monitor Failure Due to Inadequate Barriers for Protection of Cable | For Fort Calhoun Station, Regarding Acoustic Monitor Failure Due to Inadequate Barriers for Protection of Cable | 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) 10 CFR 50.73(a)(2)(i)(8) | 05000285/LER-2010-005, Regarding Inoperability of the Emergency Diesel Generator Fuel Oil Transfer System | Regarding Inoperability of the Emergency Diesel Generator Fuel Oil Transfer System | 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) 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) 10 CFR 50.73(a)(2)(i)(8) | 05000285/LER-2010-006, Regarding Reactor Trip Due to Erroneous Moisture Separator Trip Signal | Regarding Reactor Trip Due to Erroneous Moisture Separator Trip Signal | 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)(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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