06-07-2017 | On April 10, 2017, the Personnel Airlock, X-2, failed to meet local leak rate test acceptance criteria. This failure is reportable under 10 CFR 50.73(a)(2)(i)(B), any operation or condition which was prohibited by the plant's Technical Specifications.
On April 22, 2017, the High Pressure Coolant Injection System turbine exhaust line check valves both failed to meet local leak rate test acceptance criteria. The test volume for each valve could not be pressurized when flow was greater than 100 Standard Liters per Minute. Significant air flow was coming out of the test vent, indicating that each check valve was either degraded or not seated.
This failure resulted in the current Refueling Outage summation of Type B and Type C testing results exceeding the 10 CFR 50, Appendix J local leak rate test criteria limit of 0.6 La and the primary containment total leakage criteria limit of 1.0 La. This created an event that is reportable under 10 CFR 50.73(a)(2)(i)(B), any operation or condition which was prohibited by the plant's Technical Specifications,10 CFR 50.73(a)(2)(ii)(A), any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded, 10 CFR 50.73(a)(2)(v)(C), any condition that could have prevented the fulfillment of a safety function of a system needed to control the release of radioactive material, and 10 CFR 50.73(a)(2)(v)(D), any condition that could have prevented the fulfillment of a safety function of a system needed to mitigate the consequences of an accident.
There was no impact to public health and safety from this condition. |
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Category:Letter
MONTHYEARL-24-002, Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G2024-02-0202 February 2024 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G ML23342A1182024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23334A1822023-11-30030 November 2023 Biennial Report for the Defueled Safety Analysis Report Update, Technical Specification Bases Changes, 10 CFR 50.59 Evaluation Summary, and Regulatory Commitment Change Summary November 2021 Through October 2023 L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) L-23-011, 10 CFR 72.48 Biennial Change Summary Report2023-10-27027 October 2023 10 CFR 72.48 Biennial Change Summary Report IR 05000293/20234012023-08-31031 August 2023 NRC Inspection Report No. 05000293/2023401 & 2023001 (Cover Letter Only) IR 05000293/20230022023-08-0404 August 2023 NRC Inspection Report No. 05000293/2023002 L-23-008, Correction to Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations Holtec Decommissioning International, LLC (HDI)2023-05-23023 May 2023 Correction to Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations Holtec Decommissioning International, LLC (HDI) ML23136A7792023-05-15015 May 2023 Annual Radiological Environmental Operating Report, January 1 Through December 31, 2022 ML23135A2152023-05-15015 May 2023 Annual Radioactive Effluent Release Report, January 1 Through December 31, 2022 L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance ML23069A2782023-03-13013 March 2023 Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1 Subsequent License Renewal Application ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000293/20220042023-02-15015 February 2023 NRC Inspection Report No. 05000293/2022004 ML22356A0712023-01-31031 January 2023 Issuance of Exemption for Pilgrim Nuclear Power Station ISFSI Regarding Annual Radioactive Effluent Release Report - Cover Letter ML22347A2782022-12-21021 December 2022 Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022 L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 L-22-041, Supplemental Information to Enhance Exemption Request Detail for Pilgrim ISFSI Annual Radioactive Effluent Release Report Due Date Extension2022-12-0909 December 2022 Supplemental Information to Enhance Exemption Request Detail for Pilgrim ISFSI Annual Radioactive Effluent Release Report Due Date Extension IR 05000293/20220032022-11-18018 November 2022 NRC Inspection Report No. 05000293/2022003 L-22-036, Decommissioning Trust Fund Agreement2022-11-0808 November 2022 Decommissioning Trust Fund Agreement ML22276A1762022-10-24024 October 2022 Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22266A1922022-09-23023 September 2022 and Pilgrim Nuclear Power Station - Request to Withdraw Prior Submissions from NRC Consideration ML22272A0352022-09-22022 September 2022 S. Lynch-Benttinen Letter Regarding U.S. Citizen Intent to Sue U.S. Fish and Wildlife and NOAA Fisheries Representing the Endangered Species (Na Right Whale) Which Will Be Adversely Affected by Holtec International Potential Actions ML22269A4202022-09-22022 September 2022 Citizen Lawsuit ML22241A1122022-08-29029 August 2022 Request for Exemption from 10 CFR 72.212(a)(2), (b)(2), (b)(3), (b)(4), (B)(5)(i), (b)(11), and 72.214 for Pilgrim ISFSI Annual Radioactive Effluent Release Report IR 05000293/20220022022-08-12012 August 2022 NRC Inspection Report No. 05000293/2022002 ML22215A1772022-08-0303 August 2022 Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22206A1512022-08-0101 August 2022 NRC Office of Investigations Case Nos. 1-2022-002 & 1-2022-006 ML22221A2592022-08-0101 August 2022 LTR-22-0217-1-NMSS - Town of Duxbury Letter Opposing the Irradiated Water Release from Pilgrim (Docket No. 05000293) ML22193A1662022-07-28028 July 2022 LTR-22-0154-1 - Heather Govern, VP, Clean Air and Water Program, Et Al., Letter Regarding Radioactive Wastewater Disposal from the Pilgrim Nuclear Power Station (Docket No. 05000293) ML22175A1732022-07-28028 July 2022 LTR-22-0153-1 - Response Letter to D. Turco, Cape Downwinders, from A. Roberts, NRC, Regarding Holtec-Pilgrim Plans to Dump One Million Gallons of Radioactive Waste Into Cape Cod Bay ML22154A4882022-06-0101 June 2022 Letter from Conservation Law Foundation Regarding Irradiated Water Release from Pilgrim ML22154A1622022-05-26026 May 2022 Letter and Email from Save Our Bay/Diane Turco Regarding Irradiated Water Release from Pilgrim ML22136A2602022-05-16016 May 2022 Submittal of Annual Radiological Environmental Operating Report for January 1 Through December 31, 2021 ML22136A2572022-05-16016 May 2022 Submittal of Annual Radioactive Effluent Release Report for January 1 Through December 31, 2021 ML22102A0932022-05-12012 May 2022 LTR-22-0067 Response to Matthew P. Levesque, President, Barnstable Town Council Regarding Irradiated Water Release from Pilgrim IR 05000293/20220012022-05-11011 May 2022 NRC Inspection Report No. 05000293/2022001 ML22104A0542022-04-30030 April 2022 LTR-22-0093 Response to Sheila Lynch-Benttinen, Regarding Irradiated Water Release from Pilgrim L-22-026, Occupational Radiation Exposure Data Report - 20212022-04-29029 April 2022 Occupational Radiation Exposure Data Report - 2021 ML22152A2592022-04-25025 April 2022 Zaccagnini Letter Dated 04/25/22 ML22152A2642022-04-19019 April 2022 Flynn Letter Dated 04/19/22 ML22091A1062022-04-0101 April 2022 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) L-22-022, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec.2022-03-25025 March 2022 and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec. ML22130A6762022-03-14014 March 2022 Decola Ltr Dtd 03/14/22 Re Potential Discharge of Radioactive Water from Pilgrim Nuclear Power Station ML22041B0762022-03-0707 March 2022 03-07-22 - Letter to the Honorable William R. Keating, Responds to Letter Regarding Proposed Release of Irradiated Water at Pilgrim Nuclear Power Station Into Cape Cod Bay ML22054A2962022-02-23023 February 2022 Annual ISFSI Radioactive Effluent Release Report for 2021 2024-02-02
[Table view] Category:Licensee Event Report (LER)
MONTHYEARML18179A1632018-06-21021 June 2018 Retraction of Licensee Event Report 2018-002-00, Diesel Generator a Inoperability, a Condition Prohibited by the Plant Technical Specifications 05000293/LER-2017-0132018-01-25025 January 2018 1 OF 4, LER 17-013-00 for Pilgrim Nuclear Power Station Regarding Reportable Conditions Involving Standby Gas Treatment System and Secondary Containment lnoperability Not Reported During the Previous Three Years 05000293/LER-2017-0122017-11-13013 November 2017 Start-Up Transformer Degraded Voltage Relay Found Outside Technical Specification Limit, LER 17-012-00 for Pilgrim Nuclear Power Station Regarding Start-Up Transformer Degraded Voltage Relay Found Outside Technical Specification Limit 05000293/LER-2017-0112017-08-15015 August 2017 Simultaneously Opened Reactor Building Airlock Doors Caused Loss of Secondary Containment, LER 17-011-00 for Pilgrim Nuclear Power Station Regarding Simultaneously Opened Reactor Building Airlock Doors Caused Loss of Secondary Containment 05000293/LER-2017-0102017-08-0707 August 2017 Air Accumulation Creates Small Void in Core Spray Discharge Piping, LER 17-010-00 for Pilgrim re Air Accumulation Creates Small Void in Core Spray Discharge Piping 05000293/LER-2017-0012017-07-17017 July 2017 Reactor Building Isolation Dampers Failed to Isolate, LER 17-001-01 for Pilgrim Nuclear Power Station Regarding Reactor Building Isolation Dampers Failed to Isolate 05000293/LER-2017-0092017-07-17017 July 2017 Supplement to Potential Primary Containment System Inoperability Due to Relay Concerns, LER 17-009-00 for Pilgrim Nuclear Power Station Regarding Potential Primary Containment System lnoperability Due to Relay Concerns 05000293/LER-2017-0082017-06-30030 June 2017 Supplement to 480V Bus B6 Auto Transfer Function Degraded Due to Time Delay Relay Failure, LER 17-008-00 for Pilgrim re 480V Bus B6 Auto Transfer Function Degraded Due to Time Delay Relay Failure 05000293/LER-2017-0072017-06-22022 June 2017 Supplement to Potential Inoperability of Safety Relief Valve 3A, LER 17-007-00 for Pilgrim Regarding Potential Inoperability of Safety Relief Valve 3A 05000293/LER-2016-0102017-06-14014 June 2017 MSIV Inoperability Led to a Condition Prohibited by the Plant s Technical Specifications, LER 16-010-01 for Pilgrim Nuclear Power Station re MSIV Inoperability 05000293/LER-2017-0062017-06-13013 June 2017 Source Range Monitor Inoperable During Fuel Movement, LER 17-006-00 for Pilgrim Nuclear Power Station Regarding Source Range Monitor Inoperable During Fuel Movement 05000293/LER-2017-0052017-06-0707 June 2017 10 CFR 50, Appendix J, Option B, Leak Rate Criteria Exceeded, LER 17-005-00 for Pilgrim Regarding 10 CFR 50, Appendix J, Option B, Leak Rate Criteria Exceeded 05000293/LER-2017-0042017-06-0202 June 2017 Secondary Containment Testing Led to Loss of Safety Function to Both Trains of Standby Gas Treatment System, LER 17-004-00 for Pilgrim Nuclear Power Station Regarding Secondary Containment Testing Led to Loss of Safety Function to Both Trains of Standby Gas Treatment System 05000293/LER-2017-0022017-05-25025 May 2017 Isolation of HPCI, LER 17-002-00 for Pilgrim Regarding Isolation of HPCI 05000293/LER-2017-0032017-05-25025 May 2017 Supplement to Suppression Pool Declared Inoperable Due to High Water Level, LER 17-003-00 for Pilgrim Nuclear Power Station Regarding Pressure Suppression Pool Declared Inoperable Due to High Water Level 05000293/LER-2016-0082016-12-0909 December 2016 Emergency Diesel Generator 'A' Past Inoperability, LER 16-008-00 for Pilgrim Nuclear Power Station Regarding Emergency Diesel Generator 'A' Past Inoperability 05000293/LER-2016-0072016-11-0404 November 2016 Manual Reactor Scram Due To Feedwater Regulating Valve Malfunction, LER 16-007-00 for Pilgrim Nuclear Power Station Regarding Manual Reactor Scram Due To Feedwater Regulating Valve Malfunction 05000293/LER-2016-0032016-07-11011 July 2016 Spent Fuel Storage Design Feature Exceeded, LER 16-003-00 for Pilgrim Nuclear Power Station Regarding Spent Fuel Storage Design Feature Exceeded 05000293/LER-2016-0042016-07-11011 July 2016 Salt Service Water Pump B Past Operability - Operation or Condition Prohibited by Technical Specifications, LER 16-004-00 for Pilgrim Nuclear Power Station Regarding Salt Service Water Pump B Past Operability - Operation or Condition Prohibited by Technical Specifications 05000293/LER-2016-0022016-06-20020 June 2016 Online Maintenance Test Configuration Prohibited By Technical Specifications, LER 16-002-00 for Pilgrim Nuclear Power Station Regarding Online Maintenance Test Configuration Prohibited By Technical Specifications 05000293/LER-2016-0012016-06-0909 June 2016 Both Emergency Diesel Generators Inoperable, LER 16-001-00 for Pilgrim Nuclear Power Station Regarding Both Emergency Diesel Generators Inoperable ML13149A1722013-05-26026 May 2013 E-mail from Micheal Mulligan to R.Guzman, Pilgrim Evacuation Plan Broken During Blizzard Nemo and Unenforced by the Nrc. ML0613706222006-05-11011 May 2006 LER 06-01-000, Pilgrim Re Manual Scram Due to High Offgas Recombiner Temperature Resulting from Inadequate Preventive Recombiner Preheater Pressure Control Valve Controller ML0416706152004-06-0808 June 2004 LER 99-008-01 for Pilgrim Regarding Automatic Scram at 100 Percent Power Due to Turbine Trip ML0207700612002-02-27027 February 2002 LER 99-003-01 for Pilgrim Nuclear Power Station Re Local Leak Rate Test Results Exceeding Allowable Technical Specification Leakage Rates 2018-06-21
[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 information collection.
Pilgrim Nuclear Power Station 05000-293 2017 - 00 - 005
BACKGROUND
The safety objective of the Primary Containment System is to provide the capability in conjunction with other safeguard features to limit the release of fission products in the event of a postulated design basis accident (DBA) so that offsite doses would not exceed the guideline values set forth in 10 Code of Federal Regulation (CFR) 100 and to prevent excessive fuel cladding temperatures.
EVENT DESCRIPTION
On April 10, 2017, the Personnel Airlock, X-2, failed to meet local leak rate test (LLRT) acceptance criteria of 0.05La (10.25 Standard Liters per Minute (SLM)) during the as-found LLRT.
On April 22, 2017, the High Pressure Coolant Injection (HPCI) turbine exhaust line check valves, 2301-74 and 2301- 45, both failed to meet LLRT acceptance criteria. The test volume for each valve could not be pressurized to test pressure when flow was greater than 100 SLM. Significant air flow was observed to be coming out of the test vent, indicating that each check valve was either degraded or not seated. The turbine exhaust line check valves must open during HPCI turbine operation. The valves also must close promptly upon reverse flow.
The HPCI check valves satisfied the leak rate test acceptance criteria in May 2015 during Refueling Outage (RFO) 20. Although unlikely that both valves failed shortly after RFO 20, without any data to determine the time of the failures, the primary containment function of Penetration X-223 was declared inoperable over the entire operating cycle between RFO 20 and RFO 21. Check valve leakage greater than 100 SLM results in exceeding the overall Technical Specification (TS) as-found minimum path Appendix J acceptance criteria (126.3 SLM).
During the current RFO, summation of Type B and Type C testing results exceeded the 10 CFR 50, Appendix J, LLRT criteria limit of 0.6 La and the primary containment total leakage criteria limit of 1.0 La.
Because of data collected during RFO 21 regarding Appendix J, LLRT, retrospectively two main steam isolation valves (MSIV) penetrations, X-7D Main Steam Line D pathway and X-7C Main Steam Line C pathway each exceeded their TS Leakage Limit during part of Operating Cycle 21 between May 2015 and December 2016. The leakage through the X-7C Pathway also exceeded the 1.0 La leakage limit. The MSIV penetration leakage is being addressed in a supplement to LER 2016-010-00.
CAUSE OF THE EVENTS
The personnel airlock, X-2, failure was due to the displacement of the 0-ring(s) on the inner pressure equalizing device (PED). The airlock PED 0-ring(s) were replaced, correcting the leakage condition of the inner containment barrier. Once the PED 0-ring(s) were replaced, the integrated airlock leak rate test was re-performed to verify the as- found outboard airlock barrier leakage results demonstrated that the primary containment personnel airlock was capable of performing the radioactive material barrier safety function.
The HPCI turbine exhaust line check valves both failed to meet LLRT acceptance criteria. The test volume could not be pressurized when flow was greater than 100 SLM. Subsequent disassembly and inspection showed that the inboard (2301-74) check valve was not fully seating in the closed position, and the outboard (2301-45) check valve had internal degradation that prevented the valve disk from closing properly.
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.
Pilgrim Nuclear Power Station 05000-293 2017 - 00 - 005
CORRECTIVE ACTIONS
The HPCI turbine exhaust check valves, the MSIVs, and the containment personnel airlock PED were all repaired and subsequently retested, declared Operable and returned to service.
SAFETY CONSEQUENCES
The actual consequences of the two HPCI turbine exhaust check valves were a primary containment loss of safety function. Since two of the four inboard MSIVs failed their respective LLRTs, then, it is assumed that at least some time during Operating Cycle 21 there may have been a pathway from primary containment via two of the main steam lines, into secondary containment (the main stream line tunnel area) whose atmosphere is filtered through Standby Gas Treatment. The personnel airlock interior boundary failed but the exterior boundary was intact to perform the safety function. No actions to reduce the frequency or consequence are necessary.
REPORTABILITY
During the current RFO, summation of Type B and Type C testing results exceeded the 10 CFR 50, Appendix J, LLRT criteria limit of 0.6 La and the primary containment total leakage criteria limit of 1.0 La. This created an event that is reportable under 10 CFR 50.73(a)(2)(i)(B), any operation or condition which was prohibited by the plant's Technical Specifications and 10 CFR 50.73(a)(2)(ii)(A), any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded, as well as 10 CFR 50.73(a)(2)(v)(C), any condition that could have prevented the fulfillment of a safety function of a system needed to control the release of radioactive material, and 10 CFR 50.73(a)(2)(v)(D), any condition that could have prevented the fulfillment of a safety function of a system needed to mitigate the consequences of an accident.
This submittal also addresses the personnel airlock which did not meet its local leak rate test leakage acceptance criteria limit of 0.05La. This also created a situation that is reportable under 10 CFR 50.73(a)(2)(i)(B), any condition which was prohibited by the plant's TS.
PREVIOUS EVENTS
A review of Pilgrim Nuclear Power Station LERs for the last 10 years did not find a similar event as described in this LER. However, there was a previous personnel airlock PED failure in 2013 as reported in CR-PNP-2013-2276.
REFERENCES:
CR-PNP-2017-3184 CR PNP-2017-4047 CR PNP-2017-4048 CR-PNP-2017-3531 CR-PNP-2017-3588 CR-PNP-2017-5075
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05000293/LER-2017-010 | Air Accumulation Creates Small Void in Core Spray Discharge Piping LER 17-010-00 for Pilgrim re Air Accumulation Creates Small Void in Core Spray Discharge Piping | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000293/LER-2017-011 | Simultaneously Opened Reactor Building Airlock Doors Caused Loss of Secondary Containment LER 17-011-00 for Pilgrim Nuclear Power Station Regarding Simultaneously Opened Reactor Building Airlock Doors Caused Loss of Secondary Containment | | 05000293/LER-2017-001 | Reactor Building Isolation Dampers Failed to Isolate LER 17-001-01 for Pilgrim Nuclear Power Station Regarding Reactor Building Isolation Dampers Failed to Isolate | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000293/LER-2017-012 | Start-Up Transformer Degraded Voltage Relay Found Outside Technical Specification Limit LER 17-012-00 for Pilgrim Nuclear Power Station Regarding Start-Up Transformer Degraded Voltage Relay Found Outside Technical Specification Limit | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000293/LER-2017-002 | Isolation of HPCI LER 17-002-00 for Pilgrim Regarding Isolation of HPCI | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000293/LER-2017-013 | 1 OF 4 LER 17-013-00 for Pilgrim Nuclear Power Station Regarding Reportable Conditions Involving Standby Gas Treatment System and Secondary Containment lnoperability Not Reported During the Previous Three Years | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000293/LER-2017-003 | Supplement to Suppression Pool Declared Inoperable Due to High Water Level LER 17-003-00 for Pilgrim Nuclear Power Station Regarding Pressure Suppression Pool Declared Inoperable Due to High Water Level | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000293/LER-2017-004 | Secondary Containment Testing Led to Loss of Safety Function to Both Trains of Standby Gas Treatment System LER 17-004-00 for Pilgrim Nuclear Power Station Regarding Secondary Containment Testing Led to Loss of Safety Function to Both Trains of Standby Gas Treatment System | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000293/LER-2017-005 | 10 CFR 50, Appendix J, Option B, Leak Rate Criteria Exceeded LER 17-005-00 for Pilgrim Regarding 10 CFR 50, Appendix J, Option B, Leak Rate Criteria Exceeded | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000293/LER-2017-006 | Source Range Monitor Inoperable During Fuel Movement LER 17-006-00 for Pilgrim Nuclear Power Station Regarding Source Range Monitor Inoperable During Fuel Movement | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000293/LER-2017-007 | Supplement to Potential Inoperability of Safety Relief Valve 3A LER 17-007-00 for Pilgrim Regarding Potential Inoperability of Safety Relief Valve 3A | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000293/LER-2017-008 | Supplement to 480V Bus B6 Auto Transfer Function Degraded Due to Time Delay Relay Failure LER 17-008-00 for Pilgrim re 480V Bus B6 Auto Transfer Function Degraded Due to Time Delay Relay Failure | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000293/LER-2017-009 | Supplement to Potential Primary Containment System Inoperability Due to Relay Concerns LER 17-009-00 for Pilgrim Nuclear Power Station Regarding Potential Primary Containment System lnoperability Due to Relay Concerns | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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