08-11-2017 | On June 15, 2017, Clinton Power Station ( CPS) commenced procedure CPS 9069.01, Shutdown Service Water Operability Test. The purpose of this procedure is to verify operability of the Division 3 Shutdown Service Water ( SX) System Pump 1SX01PC and selected valves per the Inservice Testing program on a quarterly basis. At 0958, SX pump 1SX01PC was started and after approximately 30 seconds, it tripped due to thermal overload. The pump was declared inoperable and operations entered Technical Specifications (TS) Limiting Condition for Operation (LCO) 3.7.2, Condition A which requires the High Pressure Core Spray ( HPCS) system to be declared inoperable and enter TS LCO 3.5.1 Condition B which requires verification by administrative means that the Reactor Core Isolation Cooling ( RCIC) system is operable and within 14 days restore the HPCS system to operable status. The cause of the event is under investigation. A supplemental report will be provided when the cause has been established. An ENS notification was made at 1214 ( EN 52806). Because the HPCS system is a single train safety system, this event is reportable under 10 CFR 50.73(a)(2)(v)(D) as a condition that could have prevented the fulfilment of a safety function to mitigate the consequences of an accident. |
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Category:Letter
MONTHYEARIR 05000461/20230042024-02-0202 February 2024 Integrated Inspection Report 05000461/2023004 ML23361A1572024-01-24024 January 2024 Audit Plan in Support of Review of License Amendment Request Regarding Revision of Technical Specifications Related to Reactor Water Cleanup Isolation ML24004A0792024-01-18018 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0041 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000461/20234022023-12-27027 December 2023 Security Baseline Inspection Report 05000461/2023402 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 IR 05000461/20235012023-12-0505 December 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000461/2023501 ML23284A2512023-11-22022 November 2023 Amendment No. 250 to Adopt TSTF-332 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000461/20230032023-11-0808 November 2023 Integrated Inspection Report 05000461/2023003 ML22300A2212023-11-0202 November 2023 Preliminary Decommissioning Cost Estimate and Fuel Management Plan RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans IR 05000461/20233012023-09-12012 September 2023 NRC Initial License Examination Report 05000461/2023301 RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs IR 05000461/20234202023-08-29029 August 2023 Security Baseline Inspection Report 05000461/2023420 RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation IR 05000461/20230022023-08-0404 August 2023 Integrated Inspection Report 05000461/2023002 RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023 Supplemental Information Related to Request for Partial Site Release ML23209A8102023-07-28028 July 2023 05000461; Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23198A0152023-07-27027 July 2023 License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23202A0992023-07-24024 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000461/2023004 ML23200A2592023-07-24024 July 2023 June 27, 2023, Clinton Power Station License Renewal Environmental Pre-application Public Meeting-Meeting Summary IR 05000461/20234012023-07-19019 July 2023 Cyber Security Inspection Report 05000461/2023401 ML23194A1662023-07-19019 July 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Partial Site Release ML23191A8772023-07-11011 July 2023 Operator Licensing Examination Approval Clinton Power Station July 2023 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release IR 05000461/20230102023-05-26026 May 2023 Triennial Fire Protection Inspection Report 05000461/2023010 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23143A3182023-05-23023 May 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Clinton Power Station, Unit 1 IR 05000461/20230012023-05-0404 May 2023 Integrated Inspection Report 05000461/2023001 ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 IR 05000461/20220062023-03-0101 March 2023 Annual Assessment Letter for Clinton Power Station, Unit 1 (Report 05000461/2022006) RS-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air ML23031A2972023-03-0101 March 2023 Issuance of Amendment No. 248 Adoption of TSTF-269, Revision 2 RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 ML23039A1852023-02-10010 February 2023 Integrated Inspection Report 05000461/2022004 07201046/2022001 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 IR 05000461/20220112023-01-27027 January 2023 Biennial Problem Identification and Resolution Inspection Report 05000461/2022011 RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023 Application to Adopt TSTF-332, ECCS Response Time Testing ML23005A0682023-01-0505 January 2023 Notification of NRC Fire Protection Team Inspection Request for Information: Inspection Report 05000461/2023010 ML22341A6042022-12-0808 December 2022 Confirmation of Initial License Examination IR 05000461/20224022022-12-0606 December 2022 Security Baseline Inspection Report 05000461/2022402 RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI 2024-02-02
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000461/LER-2017-0102018-02-0505 February 2018 Division 1 Transformer Failure Leads to Instrument Air Isolation to Containment Requiring a Manual Reactor Scram, LER 17-010-00 for Clinton Power Station, Unit 1 Regarding Division 1 Transformer Failure Leads to Instrument Air Isolation to Containment Requiring a Manual Reactor Scram 05000461/LER-2017-0092018-01-0404 January 2018 Trip of Emergency Reserve Auxiliary Transformer Static VAR Compensator Causes Positive Secondary Containment Pressure Following Voltage Transient on 138 kV Offsite Source., LER 17-009-00 for Clinton, Unit 1, 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-2017-0052017-09-28028 September 2017 Automatic Reactor Scram During the Performance of Scram Time Testing As a Result of an Invalid Oscillation Power Range Monitor Growth Rate Trip, LER 17-005-01 for Clinton, Unit 1 Regarding Automatic Reactor Scram During the Performance of Scram Time Testing As a Result of an Invalid Oscillation Power Range Monitor Growth Rate Trip 05000461/LER-2017-0082017-08-11011 August 2017 Division 3 Shutdown Service Water Pump Start Failure, LER 17-008-00 for Clinton, Unit 1 re Division 3 Shutdown Service Water Pump Start Failure 05000461/LER-2017-0072017-08-0909 August 2017 Manual Reactor SCRAM due to Loss of Feedwater Heating, LER 17-007-00 for Clinton, Unit 1 re Manual Reactor SCRAM due to Loss of Feedwater Heating 05000461/LER-2017-0062017-08-0101 August 2017 1 OF 3, LER 17-006-00 for Clinton, Unit 1 re Secondary Containment Inoperable During Mode Change Due to Doors Propped Open 05000461/LER-2017-0042017-07-10010 July 2017 Main Steam Isolation Valve Local Leak Rate Test Limit Exceeded During Refueling Outage, LER 17-004-00 For Clinton Power Station, Unit 1 Re: Main Steam Isolation Valve Local Leak Rate Test Limit Exceeded During Refueling Outage 05000461/LER-2017-0022017-07-0505 July 2017 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, LER 17-002-01 for Clinton, Unit 1, 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 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-2017-0032017-07-0303 July 2017 Implementation of Enforcement Guidance Memorandum (EGM) 11 - 003, Revision 3, LER 17-003-00 for Clinton Power Station, Unit 1 Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 05000461/LER-2017-0012017-04-21021 April 2017 Failure of the 138 kV Offsite Power Source Results in a Loss of Secondary Containment Vacuum, LER 17-001-00 for Clinton, Unit 1, Regarding Failure of the 138 kV Offsite Power Source Results in a Loss of Secondary Containment Vacuum 05000461/LER-2016-0102017-03-0606 March 2017 1 OF 3, LER 16-010-01 for Clinton Power Station, Unit 1 RE: Failure to Complete Technical Specification Required Actions within the Completion Time Resulted in a Condition Prohibited by Technical Specifications 05000461/LER-2016-0092016-08-22022 August 2016 Trip of Fuel Building Fans Due to Damper Failure Results in Loss of Secondary Containment, LER 16-009-00 for Clinton Power Station, Unit 1 Regarding Trip of Fuel Building Fans Due to Damper Failure Results in Loss of Secondary Containment 05000461/LER-2016-0072016-07-15015 July 2016 Main Steam Line Flexible Hose Intergranular Stress Corrosion Cracking Identified During Refueling Outage, LER 16-007-00 for Clinton Power Station, Unit 1, Regarding Main Steam Line Flexible Hose lntergranular Stress Corrosion Cracking Identified During Refueling Outage 05000461/LER-2016-0082016-07-15015 July 2016 Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3, LER 16-008-00 for Clinton Power Station, Unit 1, Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 05000461/LER-2016-0062016-06-10010 June 2016 Missed Surveillance Results in a Condition Prohibited by Technical Specifications, LER 16-006-00 for Clinton Power Station Unit 1 RE: Missed Surveillance Results in a Condition Prohibited by Technical Specifications 05000461/LER-2016-0052016-05-31031 May 2016 Insulator Failure On the Reserve Auxiliary Transformer Results In A Loss of Secondary Containment Vacuum, LER 16-005-00 for Clinton Power Station, Unit 1, Regarding Insulator Failure on the Reserve Auxiliary Transformer Results in a Loss of Secondary Containment Vacuum 05000461/LER-2016-0042016-05-26026 May 2016 Trip of Emergency Reserve Auxiliary Transformer Static VAR Compensator Causes Positive Secondary Containment Pressure Following Lightning Strike on 138 kV Offsite Source, LER 16-004-00 for Clinton, Unit 1, 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-2016-0032016-05-23023 May 2016 Bypassing Both Divisions of Reactor Water Cleanup Leak Detection System is a Reportable Loss of Safety Function, LER 16-003-00 for Clinton Power Station, Unit 1 Regarding Bypassing Both Divisions of Reactor Water Cleanup Leak Detection System is a Reportable Loss of Safety Function 05000461/LER-2016-0022016-04-13013 April 2016 Trip of Fuel Building Ventilation Exhaust Fan Due to Moisture Formation Resulting In the Loss of Secondary Containment Vacuum, LER 16-002-00 for Clinton, Unit 1, Regarding Trip of Fuel Building Ventilation Exhaust Fan Due to Moisture Formation Resulting In the Loss of Secondary Containment Vacuum 2018-02-05
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comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor. and a person is not required to respond to, the information collection.
3. LER NUMBER
2017 - 00 008
PLANT AND SYSTEM IDENTIFICATION
General Electric -- Boiling Water Reactor, 3473 Megawatts Thermal Rated Core Power Energy Industry Identification System (EMS) codes are identified in text as [XX].
EVENT IDENTIFICATION
Division 3 Shutdown Service Water Pump Start Failure
A. Plant Operating Conditions Before the Event
Unit: 1 Event Date: 6/15/17 Mode: 1 Mode Name: Power Operation
B. Description of Event
Event Time: 0958 Reactor Power: 97 percent On June 15, 2017, Clinton Power Station (CPS) attempted to perform the quarterly surveillance test of the Division 3 shutdown service water (SX) [BI] pump [P] (1SX01PC). The pump ran for approximately 30 seconds before thermal overloads tripped the pump motor [M]. A second pump run was attempted with video recording that showed the motor spinning the shaft more quickly for the first rotation, then immediately slowed down to approximately 70 RPM. The run lasted approximately 8 seconds before the pump was manually secured.
At 0958, Operators declared the Division 3 SX, Division 3 Emergency Diesel Generator (EDG) [EK], Division 3 Inverter [EF], Division 3 Direct Current Distribution [EJ], Division 3 Alternating Current Distribution [ED] systems, and the High Pressure Core Spray (HPCS) [BG] system inoperable due to the pump trip. Operators entered the Technical Specification Actions Requirements for Limiting Conditions for Operation (LCO) 3.7.2 and LCO 3.5.1, ECCS - Operating. Operators verified within one hour that the RCIC system was operable, and entered the action to restore HPCS to Operable status within 14 days.
At 2220 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br />, Operators completed an 8-hour non-emergency notification to the NRC (Event Notification Number 52806) under 10 CFR 50.72(b)(3)(v)(D) due to the loss of a single train safety system, that is, the loss of the HPCS system function. This event is reportable under 10 CFR 50.73(a)(2)(v)(D) due to a condition that could have prevented the fulfillment of the safety function needed to mitigate the consequences of an accident.
C. Cause of the Event
A decoupled run of the motor was performed with no issue. The motor was then sent to an off-site vendor for analysis, and pump disassembly commenced. The disassembled pump was inspected with the help of the pump vendor and site SMEs. No abnormalities were noted that were deemed significant enough to cause the motor to fail to accelerate the pump.
The Root Cause Evaluation has not been completed. A supplement is to be submitted once this information is available.
comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infccollects.Resource@nrc.goy, and to the Desk Officer. Office of Information and Regulatory Affairs, used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
3. LER NUMBER
2017 - 00_ 008 D. Safety Consequences The purpose for the Division 3 SX system is to provide cooling water to Division 3 cooling loads including the HPCS pump room coolers [CLR], the Division 3 EDG and the Division 3 Switchgear Heat Removal System (VX). The Division 3 SX header is normally supplied by cooling water from the non- safety related Plant Service Water System (WS) [KG]. Under design basis event conditions such as Loss of Offsite Power (LOOP) or Loss of Coolant Accidents (LOCAs), a Division 3 SX pump start signal is generated and the cross-tie valve [V] (1SX014C) from the plant service water system closes. At this point the Division 3 SX pump would be providing cooling water flow from the lake to the Division 3 SX cooling loads.
Divisions 1 and 2 safety-related equipment are fully capable of mitigating the consequences of an accident and were available during the period of this event.
The failure of the Division 3 Shutdown Service Water Pump results in loss of Division 3 Emergency Diesel Generator safety function and a loss of the High Pressure Core Spray System safety function.
The cause of the failure of the pump has not been determined. Once determined, this information will be provided.
E. Corrective Actions
In parallel with the testing described above, several component changes were made to the overall pump/motor assembly. A new motor with higher starting torque characteristics was approved and installed. The pump breaker and thermal overloads were replaced with new units. The pump shaft sleeves were replaced and the pump packing was replaced with a flexible style equivalent.
On June 23, 2017, following a successful uncoupled run of the new motor, a coupled run was performed with no abnormalities noted. All monitored points showed normal starting characteristics for the pump. The baseline and surveillance test procedures were performed without incident.
The Division 3 SX system, including the Division 3 EDG and HPCS system were declared operable at 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br /> on 6/23/17.
Additional corrective actions for this event will be provided in the follow-up LER comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
3. LER NUMBER
2017 - 00 008 F. Previous Similar Occurrences Emergency Diesel Generator and High Pressure Core Spray Safety Functions On 9/16/14 at approximately 1905 hours0.022 days <br />0.529 hours <br />0.00315 weeks <br />7.248525e-4 months <br />, Operators were performing an operability test of the Shutdown Service Water (SX) system. The Division 3 SX pump (1SX01PC) was started to support the 2-year Comprehensive Pump Test and the motor thermal overload protection tripped off the pump after approximately 36 seconds. The cause of the event was that procedures used to develop plant modification change packages contained an inadequate process to identify the need for further reviews and the level of design detail required by those reviews. A new pump was installed and the pump was restored to operable status on 9/21/14. (ML16006A047)).
G. Component Failure Data
The Division 3 SX pump is a Sulzer model 8X14A VCM pump with a Siemens-Allis type RGV motor.
The pump is a vertical two-stage deep well pump that consists of a discharge head, six columns, and a bowl assembly to extend 30 feet below the floor elevation. The pump is driven by a 75 horsepower, 1800 RPM, 480-volt motor.
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05000461/LER-2017-010 | Division 1 Transformer Failure Leads to Instrument Air Isolation to Containment Requiring a Manual Reactor Scram LER 17-010-00 for Clinton Power Station, Unit 1 Regarding Division 1 Transformer Failure Leads to Instrument Air Isolation to Containment Requiring a Manual Reactor Scram | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000461/LER-2017-001 | Failure of the 138 kV Offsite Power Source Results in a Loss of Secondary Containment Vacuum LER 17-001-00 for Clinton, Unit 1, Regarding Failure of the 138 kV Offsite Power Source Results in a Loss of Secondary Containment Vacuum | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000461/LER-2017-002 | 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 LER 17-002-01 for Clinton, Unit 1, 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 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000461/LER-2017-003 | Implementation of Enforcement Guidance Memorandum (EGM) 11 - 003, Revision 3 LER 17-003-00 for Clinton Power Station, Unit 1 Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000461/LER-2017-004 | Main Steam Isolation Valve Local Leak Rate Test Limit Exceeded During Refueling Outage LER 17-004-00 For Clinton Power Station, Unit 1 Re: Main Steam Isolation Valve Local Leak Rate Test Limit Exceeded During Refueling Outage | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000461/LER-2017-005 | Automatic Reactor Scram During the Performance of Scram Time Testing As a Result of an Invalid Oscillation Power Range Monitor Growth Rate Trip LER 17-005-01 for Clinton, Unit 1 Regarding Automatic Reactor Scram During the Performance of Scram Time Testing As a Result of an Invalid Oscillation Power Range Monitor Growth Rate Trip | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000461/LER-2017-006 | 1 OF 3 LER 17-006-00 for Clinton, Unit 1 re Secondary Containment Inoperable During Mode Change Due to Doors Propped Open | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000461/LER-2017-007 | Manual Reactor SCRAM due to Loss of Feedwater Heating LER 17-007-00 for Clinton, Unit 1 re Manual Reactor SCRAM due to Loss of Feedwater Heating | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000461/LER-2017-008 | Division 3 Shutdown Service Water Pump Start Failure LER 17-008-00 for Clinton, Unit 1 re Division 3 Shutdown Service Water Pump Start Failure | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000461/LER-2017-009 | Trip of Emergency Reserve Auxiliary Transformer Static VAR Compensator Causes Positive Secondary Containment Pressure Following Voltage Transient on 138 kV Offsite Source. LER 17-009-00 for Clinton, Unit 1, Regarding Trip of Emergency Reserve Auxiliary Transformer Static VAR Compensator Causes Positive Secondary Containment Pressure Following Voltage Transient on 138 kV Offsite Source | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material |
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