02-13-2017 | On December 15, 2016, at 1500 [EST], with the reactor at approximately 22 percent power, the Main Steam Isolation Valves ( MSIVs) 2C and 2D were discovered to have steam leaks while performing a steam tunnel walkdown. MSIV 2D, which had a body to bonnet steam leak, was declared inoperable and Technical Specifications (TS) Limiting Condition for Operation Action Statement (LCOAS) 3.7.A.2.b was entered at 1530 on December 15, 2016. Outboard MSIV 2D and inboard MSIV
- 1D both were closed and deactivated to isolate Main Steam Line D. On December 16, 2016, at 1524 [EST] Operations entered TS LCOAS 3.7.A.2.b for outboard MSIV 2C. Actions were also taken to close and deactivate the inboard MSIV 1C, which included a controlled plant shutdown to reduce reactor pressure below the MSIV closure scram bypass setpoint.
Based on the evidence found, it was reasonable to conclude that the MSIV 2D valve body to bonnet steam leak and the MSIV 2C packing leak had likely started sometime prior to the event date and both were leaking for a period of time greater than that allowed by TS. Therefore, PNPS is making this submittal in accordance with 10 CFR 50.73(a)(2)(i)(B), any operation or condition prohibited by the plant's TS. In addition, PNPS closed the inboard MSIV 1C in accordance with TS LCOAS 3.7.A.2.b prior to going to Cold Shutdown. However, PNPS is also conservatively making this submittal in accordance with 10 CFR 50.73(a)(2)(i)(A), the completion of any nuclear plant shutdown required by the plant's TS.
The plant was placed in Cold Shutdown and both the outboard MSIV 2C and 2D were repaired and returned to service.
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 function of the Main Steam Isolation Valves (MSIVs) is to prevent reactor coolant inventory loss in the event of a steam line break outside primary containment. Also, MSIVs provide a primary containment boundary after a loss of coolant accident inside primary containment. The MSIVs are 20-inch air/spring operated, balanced "Y"-type globe valves. There are four main steam lines. Each steam line has two MSIVs; one inside primary containment and one outside of primary containment. The MSIV outboard valves are located inside the steam tunnel in secondary containment.
The MSIVs are part of the primary containment isolation system (PCIS) which provides timely protection against the gross release of radioactive materials from the fuel, nuclear system process barrier, and from the primary containment. The PCIS automatically initiates whenever monitored variables exceed preselected operational limits. Immediate shutdown of the reactor is appropriate in such a situation. The scram initiated by the MSIV closure anticipates a reactor vessel low water level scram. The main steam line isolation scram setting is selected to give the earliest positive indication of isolation valve closure.
EVENT DESCRIPTION
On December 15, 2016, at 1500 [EST], with the reactor at approximately 22 percent power, while performing a steam tunnel walkdown the MSIVs 2C (AO-203-2C) and 2D (AO-203-2D) were discovered to have steam leaks.
MSIV 2D, which had a body to bonnet steam leak, was declared inoperable and Technical Specifications (TS) Limiting Condition for Operation Action Statement (LCOAS) 3.7.A.2.b was entered at 1530 on December 15, 2016. Outboard MSIV 2D and inboard MSIV 1D were both closed and deactivated to isolate Main Steam Line D at 1753 [EST] on December 15, 2016, in accordance with TS requirements. Input to Operability for the outboard MSIV 2C packing leak was requested. On December 16, 2016, it was concluded there was not reasonable assurance of Operability and MSIV 2C was declared inoperable,. Accordingly, on December 16, 2016 at 1524 [EST] TS LCOAS 3.7.A.2.b was entered for the outboard MSIV 2C. Actions were also taken to close and deactivate the inboard MSIV 1C, which included a controlled plant shutdown to reduce reactor pressure below the MSIV closure scram bypass setpoint.
Based on the evidence found, it was reasonable to conclude that the MSIV 2D valve body to bonnet steam leak and the MSIV 2C packing leak had likely started sometime prior to the event date and both were leaking for a period of time greater than that allowed by TS. Therefore, PNPS is making this submittal in accordance with 10 CFR 50.73(a)(2)(i)(B), any operation or condition prohibited by the plant's TS. In addition, PNPS closed the inboard MSIV 1C in accordance with TS LCOAS 3.7.A.2.b prior to going to Cold Shutdown. However, PNPS is also conservatively making this submittal in accordance with 10 CFR 50.73(a)(2)(i)(A), the completion of any nuclear plant shutdown required by the plant's TS, because PNPS chose to shutdown the plant while completing the action required by TS 3.7.A.2.b to close and deactivate the inboard MSIV 10 with Main Steam Line D previously isolated.
The plant was placed in Cold Shutdown on December 17, 2016, to repair both of the leaking outboard MSIVs, 2C and 2D. MSIV 2D was seal welded, Post Work Tested (PWT) and returned to service. The outboard MSIV 2C packing was repaired stopping the packing leakage. MSIV 2C PWT was performed and the valve returned to service.
Although the discovery date of the two outboard MSIV steam leaks was December 15, 2016, the last time both of these MSIVs were tested and confirmed to be operable was during Refueling Outage 20, which ended on May 23, 2015. MSIV 2D outboard valve body to bonnet leak and MSIV 2C outboard valve packing leak both likely occurred sometime during the operating cycle following restart from the refueling outage. However, there is no way to pinpoint the specific dates.
CAUSE OF THE EVENT
The causal factor for MSIV 2D leakage was that the gasket that was used in the valve body to bonnet interface was out of specification. The extent of condition review identified that the only other valve with the possible incorrect gasket material was MSIV 2A which will be dispositioned during the upcoming refueling outage.
The causal factor for MSIV 2C leakage was scoring on the valve stem. The valve stem was polished to remove obtrusions for a smoother finish.
CORRECTIVE ACTIONS
The immediate corrective action to prevent recurrence was to shut down the reactor and repair both of the , leaking outboard MSIVs 2C and 2D. MSIV 2D was seal welded, PWT was performed, and the valve returned to service. MSIV 2C repair involved polishing the scoring on the valve stem to remove obtrusions and repacking the valve which stopped the packing leakage. MSIV 2C PWT was performed and the valve was returned to service.
The outboard MSIV 2C will be disassembled, inspected, and additional repairs will be made if needed, during the upcoming Refueling Outage 21. If additional repairs are needed for the outboard MSIV 2C, it will be handled within the Corrective Action Program.
SAFETY CONSEQUENCES
There were no consequences to the safety of the public, nuclear safety, industrial safety or radiological safety due to this event because there was no loss of safety function. Main Steam Line D was isolated on December 15, 2016, in accordance with TS requirements. Main Steam Line C was isolated on December 17, 2016, also in accordance with TS requirements. In addition, on December 15, 2016 the plant was shutdown and the two outboard MSIVs were repaired and returned to service.
Based on the defense in depth of redundant inboard and outboard MSIVs, risk is considered to be Low.
No actions to reduce the frequency or consequence are necessary.
REPORTABILITY
This report is submitted in accordance with 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)(i)(A),the completion of any nuclear plant shutdown required by the plant's Technical Specifications.
PREVIOUS EVENTS
A review of Pilgrim Nuclear Power Station Licensee Event Reports for the past three years did not identify any similar occurrences of declaring two MSIVs inoperable due to steam leakage.
REFERENCES:
CR-PNP-2016-10039 CR-PNP-2016-10040
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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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