12-09-2016 | On September 28, 2016, while performing the pre-start checks prior to running the Emergency Diesel Generator ( EDG)-A for the monthly Technical Specification (TS) surveillance, the oil level in the EDG radiator fan right angle gearbox was found to be low and additional checks found the gearbox oil pressure relief valve in a loose state which provided a pathway for gear oil to be pumped out of the gear box while the EDG was operating. EDG-A was declared inoperable, the relief valve was repaired, pressure tested and the pressure adjusting threaded union was staked to eliminate any risk from vibration induced motion in the future, the gearbox oil was replaced and the EDG run for a post-maintenance test.
A Functional Failure Determination completed on October 11, 2016 determined that the EDG would not have been able to run for its stated mission time of 30 days. This condition existed for a period of 28 days since the last surveillance test on August 31, 2016 which is greater than the TS Allowed Out of Service Time (AOT) of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. However, the Station Black Out Diesel Generator was available during this time frame. This issue is reportable under 10 CFR 50.73(a)(2)(i)(B) as an Operation or Condition which was Prohibited by the plant's TSs.
On September 15, 2016 EDG-B was made inoperable to perform its monthly operability run. This created a situation where for a brief period of time both EDGs were inoperable which is a condition that could have prevented the fulfillment of the safety function of a system needed to shut down the reactor and maintain it in a safe condition, remove residual heat, and mitigate the consequences of an accident which is reportable in accordance with 50.73(a)(2)(v)(A), 50.73(a)(2)(v)(B), and 50.73(a)(2)(v)(D). EDG-B remained available and could quickly have been restored by manual action to an operable condition if needed during the operability run.
There was no impact to public health and safety from this condition. |
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Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 05000293/20240022024-08-21021 August 2024 NRC Inspection Report No. 05000293/2024002 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24129A1042024-05-26026 May 2024 Preapplication Readiness Assessment Plan for the Holtec Decommissioning International License Termination Plan ML24135A3212024-05-14014 May 2024 Annual Radioactive Effluent Release Report, January 1 Through December 31, 2023 ML24136A2382024-05-14014 May 2024 Annual Radiological Environmental Operating Report for 2023 IR 05000293/20240012024-05-0707 May 2024 NRC Inspection Report No. 05000293/2024001 L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024 HDI Annual Occupational Radiation Exposure Data Reports - 2023 L-24-010, Request for Preapplication Readiness Assessment of the Draft License Termination Plan2024-04-22022 April 2024 Request for Preapplication Readiness Assessment of the Draft License Termination Plan L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI) IR 05000293/20230032024-02-29029 February 2024 NRC Inspection Report Nos. 05000293/2023003 and 05000293/2023004 L-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) ML23300A0022023-10-27027 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 ML23143A0872023-05-23023 May 2023 Correction to Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI) ML23135A2152023-05-15015 May 2023 Annual Radioactive Effluent Release Report, January 1 Through December 31, 2022 ML23136A7792023-05-15015 May 2023 Annual Radiological Environmental Operating 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 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 ML22221A2592022-08-0101 August 2022 LTR-22-0217-1-NMSS - Town of Duxbury Letter Opposing the Irradiated Water Release from Pilgrim (Docket No. 05000293) ML22206A1512022-08-0101 August 2022 NRC Office of Investigations Case Nos. 1-2022-002 & 1-2022-006 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 2024-09-18
[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] |
The safety objective of the emergency diesel generators (EDGs) is to provide a source of on-site AC power adequate for the safe shutdown of the reactor following abnormal operational transients and postulated accidents assuming a complete loss of off-site power, as described in Pilgrim Nuclear Power Station (PNPS) Updated Final Safety Analysis Report (UFSAR). Two EDGs and their associated fuel supply systems provide a single failure proof source of standby AC power. Pilgrim EDGs are 2600 KW ALCO 251-F type diesel generators. These EDGs are designed to automatically start upon receiving a valid signal, and come to operating speed ready to assume load. Each generator is sufficient to power all loads on its emergency bus upon failure of all off-site power. Each generator has the ability to pick up loads in sequence within a specified time period. The two EDGs at PNPS are cooled by a self-contained system consisting of radiators and a fan that is driven through a right angle gearbox.
The standby AC power source provides two independent diesel generators as the onsite sources of AC power to the emergency service portions of the station Auxiliary Power Distribution System. Each onsite source provides AC power to safely shut down the reactor, maintain the safe shut down condition, and operate all auxiliaries necessary for station safety.
Historical review revealed that this fan drive gearbox was replaced on the EDG-A in the May 2000 time frame. At that time, the original gearbox, Cotta Transmission Model Number J1327-2 was replaced with an upgraded Model Number J1327-3. Correspondence with the OEM vendor indicated the inside of the cases were identical with the only major physical change on the outside which was the addition of a relief valve in the oil circuit. Changes to the gearbox inspections were not updated to include any inspections or preventive maintenance for the relief valve.
EVENT DESCRIPTION
On September 28, 2016, while performing the pre-start checks prior to running the Emergency Diesel Generator (EDG)-A monthly Technical Specification (TS) surveillance, the oil level in the EDG radiator fan right angle gearbox was found low and additional checks found the gearbox oil pressure relief valve was loose.
The two EDGs at PNPS are each cooled by self-contained systems consisting of radiators and fans that rotate through a right angle gearbox. At the time of discovery, even though the oil level was low, the EDG would have started on a valid start signal. However, it would have been losing gearbox oil and we conservatively assumed it would have overheated due to failure of the cooling fan from gearbox damage.
A Functional Failure Determination completed on October 11, 2016 conservatively determined that the EDG would not have been able to run for its stated mission time of 30 days. This condition existed for a period of 28 days, which is greater than the TS Allowed Out of Service Time (AOT) of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. However, the Station Black Out Diesel Generator was available during this time frame.
CAUSE OF THE EVENT
The failure was determined to be low oil level found in the EDG-A radiator fan right angle gearbox due to the external relief valve pressure setting screw and the cap which goes over it being disconnected from the valve body. This allowed a pathway for oil to escape the gearbox when the EDG was running.
The radiator fan right angle gearbox oil level is checked prior to every monthly EDG run and the last time it was performed was August 31, 2016 with no problem identified during the pre-start checks. The last maintenance performed on the EDG radiator fan right angle gearbox was part of the routine examination and checks during the 2 year Preventive Maintenance (PM), which was completed on March 7, 2015. The inspection includes draining and changing the oil, performing internal inspection of the drive gears and bearings and performing backlash measurements of the drive and driven gears. However, the two (2) year PM does not perform any maintenance on the gearbox oil pressure relief valve. The relief pressure of 15 psig was set at the time of installation in 2000.
Changes to the gearbox inspections were not updated to include any inspections or preventive maintenance for the relief valve.
The failure is attributed to minimal engagement of the pressure adjusting threaded union for the relief valve setting of 15 psig, and there is some contribution from either engine vibration or possibly human error which makes the cause indeterminate.
CORRECTIVE ACTIONS
EDG-A was declared inoperable, the relief valve was repaired, pressure tested and the pressure adjusting threaded union was staked to eliminate any risk from vibration induced motion in the future, the gearbox oil was replaced and the EDG run for a post-maintenance test.
PNPS conducted an extent of condition review for EDG-B by performing an inspection to ensure that a common mode failure did not exist.
The following are additional corrective actions to address this issue which are being processed through the PNPS Corrective Action Program:
1. Update station procedure 8.9.1, "Emergency Diesel Generator and Associated Emergency Bus Surveillance," to identify the plug that is used to check the oil level and visually inspect the relief valve to ensure the cap is appropriately aligned before and after each EDG run.
2. Incorporate a vendor manual change to capture the upgraded EDG's Cotta Transmission gear box. The gear box was updated in the 2000 time frame but the drawings/vendor manual was never updated.
3. Establish PM's for both EDG radiator fan right angle gearbox relief valves.
SAFETY CONSEQUENCES
There were no consequences to the safety of the general public, nuclear safety, industrial safety, and radiological safety due to this event.
The safety objective of the EDGs is to provide a source of on-site AC power adequate for the safe shutdown of the reactor following abnormal operational transients and postulated accidents assuming a complete loss of off-site power, as described in PNPS UFSAR.
At the time of the event, the preferred AC and the secondary AC power sources were Operable and available to perform their intended safety function. In addition, the Station Blackout AC Power Source was Functional and available as the onsite source of AC power to the emergency service portions of the Auxiliary Power Distribution System.
REPORTABILITY
In a determination completed on October 11, 2016 it was conservatively determined that EDG-A would not have been able to run for its stated mission time of 30 days. This condition existed for a period of 28 days, which is greater than the TS Allowed Out of Service Time (AOT) of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. However, the Station Black Out Diesel Generator was available during this time frame. This issue is reportable under 10 CFR 50.73(a)(2)(i)(B) as an Operation or Condition which was Prohibited by the plant's Technical Specifications.
In addition, on September 15, 2016 EDG-B was made inoperable to perform its monthly operability run. This created a condition that could have prevented the fulfillment of the safety function of a system needed to shut down the reactor and maintain it in a safe condition, remove residual heat, and mitigate the consequences of an accident which is reportable in accordance with 10 CFR 50.73(a)(2)(v)(A), 50.73(a)(2)(v)(B), and 50.73(a)(2)(v)(D).
The date the condition was discovered was September 28, 2016. As such, this 60-day 10 CFR 50.73 Licensee Event Report was due to the NRC Staff on November 27, 2016. This LER is being submitted late, and PNPS is addressing this through the Corrective Action Program.
PREVIOUS EVENTS
Events involving LERs where both EDGs were inoperable were reviewed. One related LER was identified and is summarized as follows:
was out for maintenance, EDG-A was declared inoperable due to a 130 dpm leak from the jacket water pressure boundary.
There were no other LERs involving EDG inoperability at PNPS identified in a search of the past five (5) years.
REFERENCES:
CR-PN P-2016-7443 CR-PNP-2016-9552 CR-PNP-2016-9653 CR-PNP-2016-9831
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05000293/LER-2016-010 | 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 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000293/LER-2016-001 | Both Emergency Diesel Generators Inoperable LER 16-001-00 for Pilgrim Nuclear Power Station Regarding Both Emergency Diesel Generators Inoperable | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | 05000293/LER-2016-002 | 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 | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System | 05000293/LER-2016-003 | Spent Fuel Storage Design Feature Exceeded LER 16-003-00 for Pilgrim Nuclear Power Station Regarding Spent Fuel Storage Design Feature Exceeded | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000293/LER-2016-004 | 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 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000293/LER-2016-005 | Ultimate Heat Sink and Salt Service Water System Declared Inoperable | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000293/LER-2016-006 | 1 OF 4 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000293/LER-2016-007 | 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 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000293/LER-2016-008 | Emergency Diesel Generator 'A' Past Inoperability LER 16-008-00 for Pilgrim Nuclear Power Station Regarding Emergency Diesel Generator 'A' Past Inoperability | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000293/LER-2016-009 | HPCI Declared Inoperable Due to Failure of 1ST Surveillance Test | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident |
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