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). |
---|
|
---|
Category:Letter
MONTHYEARML24285A1422024-10-24024 October 2024 Ltr. to Darwin Kaskaske, Chairman, Kickapoo Tribe of Oklahoma Re CPS Section 106 Consultation ML24285A1442024-10-24024 October 2024 Ltr. to Estavio Elizondo, Sr., Chairman, Kickapoo Traditional Tribe of Texas Re CPS Section 106 Consultation ML24285A1482024-10-24024 October 2024 Ltr. to Joseph Rupnick, Chairman, Prairie Band Potawatomi Nation Re CPS Section 106 Consultation ML24285A1462024-10-24024 October 2024 Ltr. to Gena Kakkak, Chairwoman, Menominee Indian Tribe of Wisconsin Re CPS Section 106 Consultation ML24285A1472024-10-24024 October 2024 Ltr. to Geoffrey M. Standing Bear, Principal Chief, Osage Nation Re CPS Section 106 Consultation ML24285A1452024-10-24024 October 2024 Ltr. to Gail Cheatham, Kickapoo Tribe of Indians of the Kickapoo Reservation in Ks Re CPS Sect 106 Consult ML24285A1412024-10-21021 October 2024 Ltr. to Craig Harper, Chief, Peoria Tribe of Oklahoma Re CPS Section 106 Consultation ML24285A1432024-10-21021 October 2024 Ltr. to Douglas Lankford, Chief, Miami Tribe of Oklahoma Re CPS Section 106 Consultation RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing 05000461/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 ML24211A2302024-09-11011 September 2024 – Request for Partial Site Release for Facility Operating License No. NPF-62 IR 05000461/20240112024-09-0909 September 2024 Commercial Grade Dedication Inspection Report 05000461/2024011 RS-24-087, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2024-09-0909 September 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station IR 05000461/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Clinton Power Station (Report 05000461/2024005) ML24222A3952024-08-23023 August 2024 Regulatory Audit Report to Support the Review of the Amendments to Revise Reactor Water Cleanup Valve Isolation Timing ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000461/20240022024-08-0909 August 2024 Integrated Inspection Report 05000461/2024002 ML24220A2772024-08-0707 August 2024 Request for Information for the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000461/2025010 ML24212A2212024-08-0202 August 2024 License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-LNE-0000) (Docket Number: 50-461) ML24157A3242024-07-11011 July 2024 Issuance of Amendment No. 254 Revision of Reactor Water Cleanup Isolation Valve Timing ML24158A0772024-07-0303 July 2024 Notice of Consideration of Approval of Partial Site Release, Public Meeting, and Request for Comments (EPID L-2023-LLA-0088) - Letter ML24163A3252024-06-28028 June 2024 Aging Management Regulatory Audit Plan ML24163A3242024-06-28028 June 2024 LRA - Portal Letter ML24179A3112024-06-27027 June 2024 05000461; Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML24176A0272024-06-25025 June 2024 Confirmation of Initial License Examination, July 2025 RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes IR 05000461/20240122024-05-20020 May 2024 Biennial Problem Identification and Resolution Inspection Report Report 05000461/2024012 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-050, Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2024-05-0909 May 2024 Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation IR 05000461/20240012024-05-0707 May 2024 Integrated Inspection Report 05000461/2024001 ML24103A1032024-05-0101 May 2024 SHPO Consultation Letter for Clinton License Renewal RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24120A3432024-04-30030 April 2024 Ltr. to Darwin Kaskaske, Chairman, Kickapoo Tribe of Oklahoma; Re., CPS Section 106 Consultation ML24120A3452024-04-30030 April 2024 Ltr. to Lester Randell, Chairman, Kickapoo Tribe of Indians of the Kickapoo Reservation in Kansas; Re., CPS Section 106 Consultation ML24103A0992024-04-30030 April 2024 Achp Scoping Letter for Clinton License Renewal ML24120A3442024-04-30030 April 2024 Ltr. to Gena Kakkak, Chairman, Menominee Indian Tribe of Wisconsin; Re., CPS Section 106 Consultation ML24103A1152024-04-30030 April 2024 Ltr. to Geoffrey Standing Bear, Principal Chief, the Osage Nation; Re., CPS Section 106 Consultation ML24120A3462024-04-30030 April 2024 Ltr. to Douglas Lankford, Chief, Miami Tribe of Oklahoma; Re., CPS Section 106 Consultation ML24107B0312024-04-29029 April 2024 Notice of Intent to Prepare an Environmental Impact Statement and Conduct Scoping Process ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24089A2222024-04-11011 April 2024 LRA - Acceptance and Opportunity for Hearing - Letter ML24092A3452024-04-0101 April 2024 Updated Safety Analysis Report (Usar), Revision 23 ML24092A3552024-04-0101 April 2024 Request for Information for NRC License Renewal Inspection: Inspection Report 05000461/2024010 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. ML24045A1422024-02-29029 February 2024 License Renewal Application Receipt and Availability - Letter IR 05000461/20230062024-02-28028 February 2024 Annual Assessment Letter for Clinton Power Station (Report 05000461/2023006) 2024-09-09
[Table view] 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-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 2024-09-24
[Table view] |
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.
|
---|
|
|
| | Reporting criterion |
---|
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 |
|