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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-2005-001, Re Unplanned Reactor Trip Due to a Feedwater Transient at Low Power During Plant Shutdown |
Event date: |
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Report date: |
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Reporting criterion: |
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(vi)
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
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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2852005001R00 - NRC Website |
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text
Omaha Public PowerDistrict 444 South 16th Street AMall Omaha NE 68102-2247 April 27, 2005 LIC-05-O03 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, DC 20555
Reference:
Docket No. 50-285 Licensee Event Report 2005-001 Revision 0 for the Fort Calhoun Station
Subject:
Please find attached Licensee Event Report 2005-001, Revision 0, dated April 27, 2005. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(iv). If you should have any questions, please contact me.
Sincerely, D. J. Bannister Manager - Fort Calhoun Station DJB/EPM/epm Attachment c:
INPO Records Center 7::r"2, 4171 Einploynent wi'ith Equal Opportunity
NRC FORM 366 U.S. NUCLEAR REGULATORY COM APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 Estimated burden per response to comply with this mandatory collection request 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.
Reported lessons learned are incorporated into the licensing process and fed back to Industry.
Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission. Washington, DC 205554001 or by Internet e-mail LICENSEE EVENT REPORT (LER) to infocollectsenrc.gov, and to the Desk Officer, Office of Information and RegulatoryAffairs, NEOB-10202, (3150-0104), Office of Management and Budget. Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control (See reverse for required number of number, the NRC may not conduct or sponsor, and a person is not required to respond to. the digits/characters for each block)
- 3. PAGE Fort Calhoun Station 05000285 1 OF 5
- 4. TITLE Unplanned Reactor Trip Due to a Feedwater Transient at Low Power During Plant Shutdown
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEUNILRVFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SENUMBER N
NO.
MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 02 26 2005 2005 - 001 -
00 04 27 2005 05000
- 9. OPERATING 11.THIS REPORTIS SUBMITTED PURSUANTTO THE REQUIREMENTS OF 10 CFR§: (Checkallthatapply)
MODE o 20.2201(b) -
a
.20.2203(a)(3)(i).
.- O.50.73(a)(2)(i)(C) 50.73(a)(2)(vi) -'--
o 20.2201(d) a 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) 1I 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B) 0o 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x)
Ol 20.2203(a)(2)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71(a)(4)
O 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B) 0 73.71(a)(5) 15 E 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C) 0 OTHER O 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 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 (If more space is required, use additional copies of NRC Form 366A) (17)
In addition four contributing causes were identified in the course of the analysis:
- 1.
SG level and pressure control procedures did not provide adequate guidance for low power operation.
- 2.
SG feedwater flow indication is inadequate for low power operation
- 3.
Insufficient supervisory oversight regarding activities involving operators with limited experience during low power operation.
There is a minimal amount of recurring low power operation training leading to over reliance on the limited amount of individual operating experience in controlling certain processes at low power operations.
The analysis determined that there was not a failure of the feedwater or steam dump and bypass valve control systems.
SAFETY SIGNIFICANCE
The Loss of Load trip is not significant to nuclear safety because this type of trip is an analyzed event. Although the trip challenges plant equipment, all structures, systems and components (SSCs) responded appropriately, and the trip was uncomplicated.
In addition, the relatively low power level of the reactor (-12%) prior to the trip contributes to the assertion that the event was non-safety significant due to the minimal increase in core damage risk. No reactor safety functions were challenged during the event. Therefore, this event had no impact on the health and safety of the public.
CORRECTIVE ACTIONS
Immediate Corrective Actions The plant shutdown was completed as required by plant procedures and EOP-00 was exited. The SG levels were restored to the normal band.
Long Term Corrective Actions to Correct the Root Cause Provide enhanced low power procedure guidance for operators on steam dump/bypass valves and feedwater bypass valves control. This will be completed by Julyj, 2005.__
Revise OPD4-19, "Reactivity Management," and other procedures as necessary to ensure that there are clear expectations for monitoring reactivity manipulations. This will be completed by July 1, 2005.
Additional actions to correct the contributing causes will be tracked by the FCS corrective action program.
SAFETY SYSTEM FUNCTIONAL FAILURE This event did not result in a safety system functional failure in accordance with NEI-99-02.
PREVIOUS SIMILAR EVENTS
LERs 2003-003 and 1996-007 documented low power reactor trips.
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05000285/LER-2005-001, Re Unplanned Reactor Trip Due to a Feedwater Transient at Low Power During Plant Shutdown | Re Unplanned Reactor Trip Due to a Feedwater Transient at Low Power During Plant 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vi) 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-2005-002, Inoperability of Pressurizer Power Operated Relief Block Valve Due to Human Error | Inoperability of Pressurizer Power Operated Relief Block Valve Due to Human Error | 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)(8) |
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