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Category:Licensee Event Report (LER)
MONTHYEAR05000461/LER-2023-002-01, Reactor Core Isolation Cooling Inoperable Prior to Mode Change2024-09-24024 September 2024 Reactor Core Isolation Cooling Inoperable Prior to Mode Change 05000461/LER-2023-002, Reactor Core Isolation Cooling System Inoperable Prior to Mode Change2024-02-16016 February 2024 Reactor Core Isolation Cooling System Inoperable Prior to Mode Change 05000461/LER-2023-001, Grid Fault Results in Switchyard Breaker Trips and Reactor Scram2023-03-31031 March 2023 Grid Fault Results in Switchyard Breaker Trips and Reactor Scram 05000461/LER-2021-002-02, Core Alterations with Source Range Monitor Inoperable Results in Condition Prohibited by Technical Specifications2022-11-0101 November 2022 Core Alterations with Source Range Monitor Inoperable Results in Condition Prohibited by Technical Specifications 05000461/LER-2021-002-01, Core Alterations with Source Range Monitor Inoperable Results in Condition Prohibited by Technical Specifications2022-02-24024 February 2022 Core Alterations with Source Range Monitor Inoperable Results in Condition Prohibited by Technical Specifications 05000461/LER-2021-002, Core Alteration with Source Range Monitor Inoperable Results in Condition Prohibited by Technical Specifications2021-12-0101 December 2021 Core Alteration with Source Range Monitor Inoperable Results in Condition Prohibited by Technical Specifications 05000461/LER-2021-001, Core Monitoring System Software Modeling Error Results in Condition Prohibited by Technical Specifications2021-08-19019 August 2021 Core Monitoring System Software Modeling Error Results in Condition Prohibited by Technical Specifications 05000461/LER-2020-003, Reactor Core Isolation Cooling System Card Fuse Failure Results in a Condition Prohibited by Technical Specifications and That Could Have Prevented Fulfillment of a Safetv Function Needed to Control2021-02-22022 February 2021 Reactor Core Isolation Cooling System Card Fuse Failure Results in a Condition Prohibited by Technical Specifications and That Could Have Prevented Fulfillment of a Safetv Function Needed to Control. 05000461/LER-2020-002, Simultaneous Lnoperability of Main Control Room Ventilation Subsystems a and B2021-01-15015 January 2021 Simultaneous Lnoperability of Main Control Room Ventilation Subsystems a and B 05000461/LER-2019-004-01, Safety Relief Valve Wiring Issue Results in Condition Prohibited by Technical Specifications2020-01-29029 January 2020 Safety Relief Valve Wiring Issue Results in Condition Prohibited by Technical Specifications 05000461/LER-2019-004, Safety Relief Valve Wiring Issue Results in Condition Prohibited by Technical Specifications2019-11-29029 November 2019 Safety Relief Valve Wiring Issue Results in Condition Prohibited by Technical Specifications 05000461/LER-2019-003, Reactor Water Cleanup System Differential Flow Instrumentation Inoperable2019-11-14014 November 2019 Reactor Water Cleanup System Differential Flow Instrumentation Inoperable 05000461/LER-2019-001-01, Main Feed Breaker Failed to Close During Bus Shift2019-11-0101 November 2019 Main Feed Breaker Failed to Close During Bus Shift 05000461/LER-2019-002, For Clinton Power Station, Unit 1, Turbine Driven Reactor Feed Pump Hydraulic Control Failure Results in Automatic Scram2019-10-0101 October 2019 For Clinton Power Station, Unit 1, Turbine Driven Reactor Feed Pump Hydraulic Control Failure Results in Automatic Scram 05000461/LER-2019-001, Main Feed Breaker Failed to Close During Bus Shift2019-07-19019 July 2019 Main Feed Breaker Failed to Close During Bus Shift 05000461/LER-2018-005-02, Unplanned Reactor Scram During Maintenance Outage Due to High Intermediate Range Monitor Flux2019-04-24024 April 2019 Unplanned Reactor Scram During Maintenance Outage Due to High Intermediate Range Monitor Flux 05000461/LER-2018-005-01, Unplanned Reactor Scram During Maintenance Outage Due to High Intermediate Range Monitor Flux2019-03-0505 March 2019 Unplanned Reactor Scram During Maintenance Outage Due to High Intermediate Range Monitor Flux 05000461/LER-2018-003-01, Load Driver Card Failure Resulting in High Pressure Core Spray Inoperability2019-02-0505 February 2019 Load Driver Card Failure Resulting in High Pressure Core Spray Inoperability 05000461/LER-2018-005, Unplanned Reactor Scram During Maintenance Outage Due to High Intermediate Range Monitor Flux2018-12-21021 December 2018 Unplanned Reactor Scram During Maintenance Outage Due to High Intermediate Range Monitor Flux 05000461/LER-2018-004, Undervoltage Condition Caused by an Offsite Ameren Transformer Bushing Failure Initiates an Automatic Start of an Emergency Diesel Generator2018-11-21021 November 2018 Undervoltage Condition Caused by an Offsite Ameren Transformer Bushing Failure Initiates an Automatic Start of an Emergency Diesel Generator 05000461/LER-2018-003, Load Driver Card Failure Resulting in High Pressure Core Spray Lnoperability2018-08-17017 August 2018 Load Driver Card Failure Resulting in High Pressure Core Spray Lnoperability 05000461/LER-2018-002, Division 2 Diesel Generator Inoperability Due to Air Receiver Remaining Isolated Following Clearance Removal Resulting in Unplanned Shutdown Risk Change2018-07-16016 July 2018 Division 2 Diesel Generator Inoperability Due to Air Receiver Remaining Isolated Following Clearance Removal Resulting in Unplanned Shutdown Risk Change 05000461/LER-1917-010, Regarding Division 1 Transformer Failure Leads to Instrument Air Isolation to Containment Requiring a Manual Reactor Scram2018-02-0505 February 2018 Regarding Division 1 Transformer Failure Leads to Instrument Air Isolation to Containment Requiring a Manual Reactor Scram 05000461/LER-1917-009, Regarding Trip of Emergency Reserve Auxiliary Transformer Static Var Compensator Causes Positive Secondary Containment Pressure Following Voltage Transient on 138 Kv Offsite Source2018-01-0404 January 2018 Regarding Trip of Emergency Reserve Auxiliary Transformer Static Var Compensator Causes Positive Secondary Containment Pressure Following Voltage Transient on 138 Kv Offsite Source 05000461/LER-1917-008, Re Division 3 Shutdown Service Water Pump Start Failure2017-08-11011 August 2017 Re Division 3 Shutdown Service Water Pump Start Failure 05000461/LER-1917-007, Re Manual Reactor Scram Due to Loss of Feedwater Heating2017-08-0909 August 2017 Re Manual Reactor Scram Due to Loss of Feedwater Heating 05000461/LER-1917-006, Re Secondary Containment Inoperable During Mode Change Due to Doors Propped Open2017-08-0101 August 2017 Re Secondary Containment Inoperable During Mode Change Due to Doors Propped Open 05000461/LER-1917-005, Regarding Automatic Reactor Scram During the Performance of Scram Time Testing as a Result of an Invalid Oscillating Power Range Monitor Growth Rate Trip2017-07-27027 July 2017 Regarding Automatic Reactor Scram During the Performance of Scram Time Testing as a Result of an Invalid Oscillating Power Range Monitor Growth Rate Trip 05000461/LER-1917-004, For Clinton Power Station, Unit 1 Main Steam Isolation Valve Local Leak Rate Test Limit Exceeded During Refueling Outage2017-07-10010 July 2017 For Clinton Power Station, Unit 1 Main Steam Isolation Valve Local Leak Rate Test Limit Exceeded During Refueling Outage U-604357, Special Report: Inoperable Drywall High Range Gamma Radiation Monitor2017-07-0505 July 2017 Special Report: Inoperable Drywall High Range Gamma Radiation Monitor 05000461/LER-1917-003, Regarding Implementation of Enforcement Guidance Memorandum (Egm) 11-003, Revision 32017-07-0303 July 2017 Regarding Implementation of Enforcement Guidance Memorandum (Egm) 11-003, Revision 3 05000461/LER-1917-002, Regarding Failure of the Division 1 Diesel Generator Ventilation Fan Load Sequence Relay Circuit During Concurrent Maintenance of RHR Division 2 Results in an Unanalyzed Condition2017-05-0404 May 2017 Regarding Failure of the Division 1 Diesel Generator Ventilation Fan Load Sequence Relay Circuit During Concurrent Maintenance of RHR Division 2 Results in an Unanalyzed Condition 05000461/LER-2017-001, Regarding Failure of the 138 Kv Offsite Power Source Results in a Loss of Secondary Containment Vacuum2017-04-21021 April 2017 Regarding Failure of the 138 Kv Offsite Power Source Results in a Loss of Secondary Containment Vacuum U-604333, Regarding Residual Heat Removal (RHR) C Pump Failure During Surveillance Testing as a Result of Breaker Latch Check Switch Adjustment Results in a Condition Prohibited by Technical Specification2017-02-0101 February 2017 Regarding Residual Heat Removal (RHR) C Pump Failure During Surveillance Testing as a Result of Breaker Latch Check Switch Adjustment Results in a Condition Prohibited by Technical Specification U-604328, Regarding Incorrect Calculation Method Used to Demonstrate Control Room Habitability2017-01-13013 January 2017 Regarding Incorrect Calculation Method Used to Demonstrate Control Room Habitability 05000461/LER-2016-010, Regarding Failure to Complete Technical Specification Required Actions within the Completion Time Resulted in a Condition Prohibited by Technical Specifications2016-12-13013 December 2016 Regarding Failure to Complete Technical Specification Required Actions within the Completion Time Resulted in a Condition Prohibited by Technical Specifications 05000461/LER-2015-004-01, Regardomg Trip of Emergency Reserve Auxiliary Transformer Static Var Compensator Causes Positive Secondary Containment Pressure Following Lightning Strike on 138 Kv Offsite Source2016-08-22022 August 2016 Regardomg Trip of Emergency Reserve Auxiliary Transformer Static Var Compensator Causes Positive Secondary Containment Pressure Following Lightning Strike on 138 Kv Offsite Source 05000461/LER-2016-009, Regarding Trip of Fuel Building Fans Due to Damper Failure Results in Loss of Secondary Containment2016-08-22022 August 2016 Regarding Trip of Fuel Building Fans Due to Damper Failure Results in Loss of Secondary Containment 05000461/LER-2016-008, Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 32016-07-15015 July 2016 Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 05000461/LER-2016-007, Regarding Main Steam Line Flexible Hose Lntergranular Stress Corrosion Cracking Identified During Refueling Outage2016-07-15015 July 2016 Regarding Main Steam Line Flexible Hose Lntergranular Stress Corrosion Cracking Identified During Refueling Outage 05000461/LER-2016-006, Missed Surveillance Results in a Condition Prohibited by Technical Specifications2016-06-10010 June 2016 Missed Surveillance Results in a Condition Prohibited by Technical Specifications 05000461/LER-2016-005, Regarding Insulator Failure on the Reserve Auxiliary Transformer Results in a Loss of Secondary Containment Vacuum2016-05-31031 May 2016 Regarding Insulator Failure on the Reserve Auxiliary Transformer Results in a Loss of Secondary Containment Vacuum 05000461/LER-2016-004, Regarding Trip of Emergency Reserve Auxiliary Transformer Static Var Compensator Causes Positive Secondary Containment Pressure Following Lightning Strike on 138 Kv Offsite Source2016-05-26026 May 2016 Regarding Trip of Emergency Reserve Auxiliary Transformer Static Var Compensator Causes Positive Secondary Containment Pressure Following Lightning Strike on 138 Kv Offsite Source 05000461/LER-2016-003, Regarding Bypassing Both Divisions of Reactor Water Cleanup Leak Detection System Is a Reportable Loss of Safety Function2016-05-23023 May 2016 Regarding Bypassing Both Divisions of Reactor Water Cleanup Leak Detection System Is a Reportable Loss of Safety Function 05000461/LER-2016-002, Regarding Trip of Fuel Building Ventilation Exhaust Fan Due to Moisture Formation Resulting in the Loss of Secondary Containment Vacuum2016-04-13013 April 2016 Regarding Trip of Fuel Building Ventilation Exhaust Fan Due to Moisture Formation Resulting in the Loss of Secondary Containment Vacuum 05000461/LER-2015-005, Regarding Containment Ventilation Radiation Monitors Inoperable During Operations with the Potential for Draining the Reactor Vessel Activities2016-03-16016 March 2016 Regarding Containment Ventilation Radiation Monitors Inoperable During Operations with the Potential for Draining the Reactor Vessel Activities 05000461/LER-2014-005-01, 1 for Clinton, Unit 1, Regarding Failure of Shutdown Service Water Pump Results in Loss of Division 3 Emergency Diesel Generator and High Pressure Core Spray Safety Functions2015-12-31031 December 2015 1 for Clinton, Unit 1, Regarding Failure of Shutdown Service Water Pump Results in Loss of Division 3 Emergency Diesel Generator and High Pressure Core Spray Safety Functions 05000461/LER-2015-004, Regarding Trip of Emergency Reserve Auxiliary Transformer Static Var Compensator Causes Positive Secondary Containment Pressure Following Lightning Strike on 138 Kv Offsite Source2015-08-24024 August 2015 Regarding Trip of Emergency Reserve Auxiliary Transformer Static Var Compensator Causes Positive Secondary Containment Pressure Following Lightning Strike on 138 Kv Offsite Source 05000461/LER-2015-003, Regarding Condition Prohibited by Technical Specification 3.9.4 for Failing to Disarm Control Rod Drive Prior to Fuel Moves in Modes 5 with One Control Rod Position Indication Channel Inoperable2015-06-29029 June 2015 Regarding Condition Prohibited by Technical Specification 3.9.4 for Failing to Disarm Control Rod Drive Prior to Fuel Moves in Modes 5 with One Control Rod Position Indication Channel Inoperable 05000461/LER-2015-001, Regarding Division 1 and Division 2 Reactor Water Cleanup System High Differential Flow Instruments Become Incapable of Performing Their Safety Function2015-04-0707 April 2015 Regarding Division 1 and Division 2 Reactor Water Cleanup System High Differential Flow Instruments Become Incapable of Performing Their Safety Function 2024-09-24
[Table view] |
LER-2011-001, Regarding Postulated Spurious High Pressure Core Spray Initiation Result Unanalyzed |
Event date: |
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Report date: |
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Reporting criterion: |
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
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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4612011001R00 - NRC Website |
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text
Exel1n Nuclear Clinton Power Station 8401 Power Road Clinton, IL 61727-9351 10 CFR 50.73 SRRS 5A. 108 U-604011
- April, 6,
2011 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461
Subject:
Licensee Event Report 2011-001-00 Enclosed is Licensee Event Report (LER) No. 2011-001-00: Postulated Spurious High Pressure Core Spray Initiation Result Unanalyzed. This report is being submitted in accordance with the requirements of 10 CFR 50.73.
There are no regulatory commitments contained in this letter.
Should you have any questions concerning this report, please contact A. Khanifar, at (217)-
937-3800.
Respectf ully, F. A. Ke2r~~i Site Vice President Clinton Power Station RSF/blf
Enclosures:
Licensee Event Report 2011-001-00 cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector - Clinton Power Station Office of Nuclear Facility Safety - IEMA Division of Nuclear Safety
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (10-2010)
, the NRC may e for each b
,lock not conduct or sponsor, and a person is not required to respond to, the digits/characters finformation collection.
- 3. PAGE Clinton Power Station, Unit 1 05000461 1 OF 4
- 4. TITLE Postulated Spurious High Pressure Core Spray Initiation Result Unanalyzed
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED FEUNTA ACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NSEUENTIAL REV MONTH DAY YEAR I
05000 NUMBER NO.
05000______
___________I FACILITY NAME DOCKET NUMBER 02 08 11 2011 001 00 04 06 2011 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
[1 20.2201(b)
[I 20.2203(a)(3)(i)
[I 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii) 1 [E 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) 0 50.73(a)(2)(ii)(B)
[I 50.73(a)(2)(viii)(B)
[I 20.2203(a)(2)(i)
[I 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [E
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)
[E 20.2203(a)(2)(iii)
[] 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71 (a)(4) 96.9 El 20.2203(a)(2)(iv)
[E 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5)
E3 20.2203(a)(2)(v)
[I 50.73(a)(2)(i)(A)
[I 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi)
E] 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in actuation of the HPCS pump and reactor core injection. In this scenario, the faults would also impair the capability to shut off the HPCS pump and stop it from injecting water into the core.
Engineering completed an evaluation to address this event and determine additional actions to be taken. The evaluation reviewed the adequacy of the proposed alternative compensatory measures, as compared to the existing required alternate compensatory measures developed for Multiple Spurious Operations (MSO)
(required shiftly Operator rounds, the shiftly transient combustible surveillance, Fire Marshal tours, administrative controls on combustible material and Operations fire brigade training). The evaluation demonstrated that the alternative compensatory measures would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire and that compliance with 10 CFR 50, Appendix A, General Design Criterion III, and 10 CFR 50.48(a), "Fire Protection," is met.
The station implemented an alternative compensatory action by adding Fire Zone CB-5a as a line item in eSOMS for Operator rounds.
No inoperable equipment or components directly affected this event.
Issue Report 1172335 was initiated to investigate this event and initiate corrective actions.
The NRC Operations Center was notified about this condition via Event Notification 46603 on 2/8/11 at 1406 hours0.0163 days <br />0.391 hours <br />0.00232 weeks <br />5.34983e-4 months <br /> EST.
C. CAUSE OF EVENT
The cause of this event is attributed to a failure to follow procedure AD-CL-101 -1004, "CPS SPECIFIC
'xxxx.xx' NUMBERED PROCEDURES WRITERS GUIDE." The writer's guide establishes performance of disciplinary reviews for specifically coded procedures to ensure the procedures are technically and functionally accurate for all functional areas. Procedure CPS 4003.01 is a procedure that specifically requires an engineering review of changes for impacts. Operations procedure writers did not ensure an engineering review of changes to procedure CPS 4003.01.
D. SAFETY CONSEQUENCES
This event is reportable under the provisions of 10 CFR 50.73(a)(2)(ii)(B) as a condition that resulted in the nuclear power plant being in an unanalyzed condition that degraded plant safety.
The risk significance of an overfill event is low. An overfill event represents a deviation from the intended shutdown strategy and reactor response, but does not result in any immediate core cooling challenges. The steam lines downstream of the SRV discharge flange are not part of the reactor coolant pressure boundary.
Damage to this piping inside the drywell would pressurize the drywell with flashing steam. This steam pressure would act through the drywell Loss of Coolant Accident (LOCA) vents rather than the SRV quenchers and remain bounded by LOCA drywell/containment performance. It would not impact safe shutdown per 10 CFR 50, Appendix R. The continued operation of HPCS will ensure adequate RPV water inventory to maintain adequate fuel temperatures to protect the fuel cladding, and plant capability to operate multiple SRVs will control pressure and dedicated safe shutdown equipment can be controlled from either the Control Room or RSP for a fire in any plant area. Review of calculations related to the quenchers identified that sufficient margin is available to provide assurance that the quenchers will not fail even with LOCA and earthquake loads being considered.
E. CORRECTIVE ACTIONS
Operations procedure writers and supervisor have been briefed on the requirements of procedure AD-CL-101 -1004, and the need to formally request review by other departments, as required.
Operations will validate that procedures related to arc flash concerns have had the cross-disciplinary reviews performed for procedure technical and functional accuracy.
Operations will review a sample of procedures with certain Class Codes related to Engineering, Environmental and In-Service Inspection procedure revisions for the past five years to ensure the cross-disciplinary reviews were performed to ensure the procedure was technically and functionally accurate, if necessary.
A transient and stress analysis of high pressure, high temperature, two phase SRV discharge flow will be completed.
F.
PREVIOUS OCCURRENCES
The condition discussed in this report is similar to NRC URI 2005006-01 identified 6/30/2005. This document discusses postulated fire-induced electrical faults in the control cables and control logic of the HPCS pump and discharge valve from a fire in the Division 3 switchgear room which could result in spurious actuation of the HPCS pump and core injection. These faults could impair the capability to shut off the pump and stop it from continually injecting into the core.
In 2005, the ability to trip the HPCS breaker was still an action in procedure CPS 4003.01, and the ability to shutoff the HPCS pump before it could lead to an overfill event that would lead to SRVs opening as designed to relieve pressure, with water exiting a fully flooded reactor pressure vessel through open SRVs, through the downcomers to the suppression pool was considered achievable by Engineering and Operations.
In the July, 2008 CPS NRC Triennial Fire Protection Inspection (2008006), the inspectors followed-up on the URI, but again concluded that no action was required on the part of the licensee, and that the issue required resolution by NRC Office of Nuclear Reactor Regulation.
G. COMPONENT FAILURE DATA
None
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05000461/LER-2011-001, Regarding Postulated Spurious High Pressure Core Spray Initiation Result Unanalyzed | Regarding Postulated Spurious High Pressure Core Spray Initiation Result Unanalyzed | 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) | 05000461/LER-2011-002, Regarding Main Control Room HVAC Return Fan B High Vibrations | Regarding Main Control Room HVAC Return Fan B High Vibrations | 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) | 05000461/LER-2011-003, Regarding Inadequate Procedure Direction Results in Missed Response Time Testing | Regarding Inadequate Procedure Direction Results in Missed Response Time Testing | 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) | 05000461/LER-2011-004, Regarding Automatic Reactor Scram During Removal of Main Generator | Regarding Automatic Reactor Scram During Removal of Main Generator | 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) | 05000461/LER-2011-005, Regarding Missed Surveillance Due to Preconditioning Valve Prior to Leak Rate Test | Regarding Missed Surveillance Due to Preconditioning Valve Prior to Leak Rate 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) | 05000461/LER-2011-006, Regarding Condition Prohibited by Technical Specifications Due to Failed Missed Surveillance | Regarding Condition Prohibited by Technical Specifications Due to Failed Missed Surveillance | 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) | 05000461/LER-2011-007, Regarding Unfused DC Ammeter Circuits Result in Unanalyzed Condition | Regarding Unfused DC Ammeter Circuits Result in Unanalyzed Condition | 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) | 05000461/LER-2011-008, Reactor Protection System Actuation and Loss of Shutdown Cooling | Reactor Protection System Actuation and Loss of Shutdown Cooling | 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) | 05000461/LER-2011-009, Regarding Missed Surveillance Due to Preconditioning Valve Prior to Leak Rate Test | Regarding Missed Surveillance Due to Preconditioning Valve Prior to Leak Rate 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) |
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