11-22-2017 | During the Clinton Power Station ( CPS) Refueling Outage (C1 R17) on May 12, 2017 at 0045 [CDT], CPS tested its Main Steam Isolation Valves ( MSIV) and discovered the as-found leakage for main steam line ( MSL) `D' exceeded the Technical Specifications (TS) 3.6.1.3, Primary Containment Isolation Valves, Surveillance Requirement (SR) 3.6.1.3.9 limit placed on an individual MSL and total leakage from all four MSLs. During Modes 1, 2, and 3, TS SR 3.6.1.3.9 requires MSIV leakage for a single MSL to be less than or equal to 100 standard cubic feet per hour (scfh) (47,195 standard cubic centimeters per minute (sccm)) and requires the combined leakage rate for all MSLs to be less than or equal to 200 scfh (94,390 sccm) when tested at 9 psig. The as-found leakage for the 'D' MSL was 53,921.61 sccm for the 'D' inboard MSIV (1 B21 F022D) and 59,698.8 sccm for the 'D' outboard MSIV (1B21F028D). The as-found combined min-path leakage for all four MSLs was 102,463 sccm. An event investigation determined the as found condition of MSIVs 1B21F022D and 1B21F028D did not reveal any damage, only normal wear indications. Thus, the apparent cause for the excessive leakage past all affected MSIVs is expected wear. Valves 1621F028A, 1B21F022D, and 1B21F028D were repaired so that as-left leakage values complied with limits established by TS SR 3.6.1.3.9. This event is reportable due to principle plant safety barriers being seriously degraded, under the provisions of 10 CFR 50.73(a)(2)(ii)(A) and a condition prohibited by TS under 10CFR50.73(a)(2)(i)(B). |
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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 infor1nation collection.
3. LER NUMBER
2017 - 01 004
PLANT AND SYSTEM IDENTIFICATION
General Electric—Boiling Water Reactor, 3473 Megawatts Thermal Rated Core Power Energy Industry Identification System (EIIS) codes are identified in the text as [XX]
EVENT IDENTIFICATION
Main Steam Isolation Valve Local Leak Rate Test Limit Exceeded During Refueling Outage A. Plant Operating Conditions before the Event Unit: 1 Mode: 5 Event Date: May 12, 2017 Event Time: 0045 Mode Name: Refueling Reactor Power: 00 percent
B. DESCRIPTION OF EVENT
On May 12, 2017 0045 CDT during Refueling Outage C1R17, Clinton Power Station (CPS) performed a local leak rate test (LLRT) on its Main Steam Isolation Valves (MSIV) and discovered that the as-found leakage for the `D' main steam line (MSL) exceeded the Technical Specification (TS) 3.6.1.3, Primary Containment Isolation Valves, Surveillance Requirement (SR) 3.6.1.3.9 limits. During Modes 1, 2, and 3, TS SR 3.6.1.3.9 requires MSIV leakage for a single MSL to be less than or equal to 100 standard cubic feet per hour (scfh) (47,195 standard cubic centimeters per minute (sccm)) and requires the combined leakage rate for all four MSLs to be less than or equal to 200 scfh (94,390 sccm) when tested at 9 psig. The as-found leakage for the `D' MSL was 53,921.61 sccm for the `D' inboard MSIV (1621F022D) and 59,698.8 sccm for the `D' outboard MSIV (1621F028D). The as-found combined min-path leakage for all four MSLs was 102,463 sccm. It was also identified that MSIV 1621F028A exceeded the administrative allowable limit established by plant procedures.
An event investigation determined the as-found condition of MSIVs 1621F028A, 1621F022D, and 1621F028D did not reveal any damage, only normal wear indications were noted. The valve dimensions were within tolerance. The extent of the condition identified in this report was limited to the CPS MSIV LLRTs and the frequency with which maintenance is performed. Prior LLRT results were evaluated for component failure that would be indicated by an abrupt rise in leak rates, however, no failures were noted. Evidence of gradual increase in LLRT rates were apparent on all valves tested.
The internal maintenance for the MSIVs are based on as-found LLRT test and diagnostic test results. There are no internal valve preventative maintenance tests that are performed at a given frequency.
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 - 01 004
C. CAUSE OF EVENT
The apparent cause the leakage rate of affected valves exceeding TS SR limits is expected wear. An event investigation determined the as found condition of MSIVs 1621F028A, 1621F022D, and 1621F028D did not reveal any damage only normal wear indications.
D. SAFETY ANALYSIS
There were no safety consequences associated with this condition. This event is reportable under the provisions of 10 CFR 50.73(a)(2)(ii)(A) for the condition of the nuclear power plant including its principal safety barriers being seriously degraded. The event described in this report is also a condition prohibited by TS under the provisions of 10 CFR 50.73(a)(2)(i)(B). The MSIV LLRT leakage values observed during the surveillance during C1R17 exceeded TS limits.
A plant shutdown was not required since the plant was in Mode 5 at the time of discovery.
Discovery of the reportable conditions was the result of a planned activity to perform leak rate testing on the MSIVs. Systems necessary to maintain the plant per TS requirements during the performance of refueling outage activities in Mode 5 remained available to perform their safety function.
This event report does not identify any safety system functional failures.
E. CORRECTIVE ACTIONS
The MSIVs were refurbished to rectify the condition that caused local leak rate test failures. The cause of the leakage values which exceeded TS requirements was expected wear. CPS repaired valves 1B21F028A, 1621F022D, and 1B21F028D so that as-left leakage values complied with TS SR 3.6.1.3.9. Repair activities included cleaning or replacing valve internals and repacking valves to correct the condition which caused the event.
F. PREVIOUS SIMILAR OCCURENCES
On February 3, 2010, after entering Mode 2 (Startup) following refueling outage C1R12, it was discovered that a primary containment LLRT performed on feedwater check valve, 1621-F032B, exceeded its acceptance criteria. Technical Specification SR 3.6.1.3.11 requires that the combined leakage rate for both primary containment feedwater penetrations 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 - 01 004 to be less than or equal to 2 gallons per minute (gpm) for the worst of the isolation valves.
The measured leakage rate for 1621-F032B was reported to be 2.5 gpm.
This leakage rate is greater than that assumed in the plant safety analysis. The cause of the 1B21-F032B check valve to fail its leak rate test was age-related degradation of the lubrication causing increased friction in the actuator. Corrective action for this event included establishing preventive maintenance activities to lubricate and overhaul the actuators.
Program and Initial Plant Operation Results in Unacceptable Main Steam Isolation Valve Leakage Rates On March 20, 1988, at 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br />, with the plant in Mode 4 (Cold Shutdown) and the reactor at approximately 150 degrees Fahrenheit and atmospheric pressure, local leak rate testing by test engineers identified that the primary containment leakage rates of the MSIVs on MSL D exceeded TS limits of 13,214 sccm (28 scfh) per line. The cause of the excessive leakage has been attributed to component wear based on service seen during the power ascension program and initial plant operation. The corrective action included reworking the two MSIVs by lapping the seats and machining the poppets. Subsequent leak rate testing of MSL D was satisfactorily performed.
G. COMPONENT FAILURE DATA
Main Steam Isolation Valves 1621F028A, 1621F022D, and 1621F028D are manufactured by Atwood & Morrill Company. The model number for the valves is 40012.
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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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