|
---|
Category:Letter
MONTHYEARL-24-018, Independent Spent Fuel Storage Installation - Only Security, Training and Qualification, and Safeguards Contingency Plan, Revision 12024-12-11011 December 2024 Independent Spent Fuel Storage Installation - Only Security, Training and Qualification, and Safeguards Contingency Plan, Revision 1 L-24-017, Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations2024-12-10010 December 2024 Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations ML24344A0692024-12-0909 December 2024 Proof of Financial Protection 10 CFR 140.15 ML24331A0422024-11-26026 November 2024 NRC Independent Spent Fuel Storage Security Inspection Report 07201044/2024402 (Public) IR 05000293/20240032024-11-20020 November 2024 Decommissioning International, Llc., Pilgrim Nuclear Power Station - NRC Inspection Report 05000293/2024003 ML24240A1692024-09-18018 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 ML24136A2382024-05-14014 May 2024 Annual Radiological Environmental Operating Report for 2023 ML24135A3212024-05-14014 May 2024 Annual Radioactive Effluent Release Report, January 1 Through December 31, 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-24-008, Reply to a Notice of Violation EA-2024-0232024-03-29029 March 2024 Reply to a Notice of Violation EA-2024-023 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) 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 ML22269A4202022-09-22022 September 2022 Citizen Lawsuit 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 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) 2024-09-18
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000293/LER-2019-004, Manual Reactor Scram Due to Degrading Condenser Vacuum2019-06-11011 June 2019 Manual Reactor Scram Due to Degrading Condenser Vacuum 05000293/LER-2019-003, Condition Prohibited by Technical Specifications Involving the Mechanical Vacuum Pump2019-06-10010 June 2019 Condition Prohibited by Technical Specifications Involving the Mechanical Vacuum Pump 05000293/LER-2019-002, Failure of Main Steam Isolation Valve Limit Switch Results in a Condition Prohibited by Technical Specifications2019-03-0404 March 2019 Failure of Main Steam Isolation Valve Limit Switch Results in a Condition Prohibited by Technical Specifications 05000293/LER-2019-001, Reactor Core Isolation Cooling System Declared Inoperable During Surveillance Testing2019-02-28028 February 2019 Reactor Core Isolation Cooling System Declared Inoperable During Surveillance Testing 05000293/LER-2018-006, Automatic Reactor Scram Due to Feedwater Regulating Valve Malfunction2018-11-29029 November 2018 Automatic Reactor Scram Due to Feedwater Regulating Valve Malfunction 05000293/LER-2018-005, Condition Prohibited by Technical Specifications Involving Standby Gas Treatment System Pneumatic Leakage Rate2018-09-12012 September 2018 Condition Prohibited by Technical Specifications Involving Standby Gas Treatment System Pneumatic Leakage Rate ML18179A1632018-06-21021 June 2018 Retraction of Licensee Event Report 2018-002-00, Diesel Generator a Inoperability, a Condition Prohibited by the Plant Technical Specifications 05000293/LER-2018-004, Automatic Emergency Diesel Generator System Actuation Caused by Loss of Offsite Power2018-05-14014 May 2018 Automatic Emergency Diesel Generator System Actuation Caused by Loss of Offsite Power 05000293/LER-2018-003, Target Rock Relief Valve Pilot Assembly Failed As-Found Lift Test, a Condition Prohibited by Plant Technical Specifications2018-04-27027 April 2018 Target Rock Relief Valve Pilot Assembly Failed As-Found Lift Test, a Condition Prohibited by Plant Technical Specifications 05000293/LER-2018-002, Diesel Generator a Inoperable, a Condition Prohibited by the Plant Technical Specifications2018-03-0606 March 2018 Diesel Generator a Inoperable, a Condition Prohibited by the Plant Technical Specifications 05000293/LER-2018-001, Regarding Manual Reactor Scram Due to Loss of One Offsite Transmission Line2018-03-0505 March 2018 Regarding Manual Reactor Scram Due to Loss of One Offsite Transmission Line 05000293/LER-1917-013, Regarding Reportable Conditions Involving Standby Gas Treatment System and Secondary Containment Lnoperability Not Reported During the Previous Three Years2018-01-25025 January 2018 Regarding Reportable Conditions Involving Standby Gas Treatment System and Secondary Containment Lnoperability Not Reported During the Previous Three Years ML18004A0642017-12-20020 December 2017 Regarding Supplement to Potential Inoperability of Safety Relief Valve 3A 05000293/LER-1917-012, Regarding Start-Up Transformer Degraded Voltage Relay Found Outside Technical Specification Limit2017-11-13013 November 2017 Regarding Start-Up Transformer Degraded Voltage Relay Found Outside Technical Specification Limit 05000293/LER-1917-011, Regarding Simultaneously Opened Reactor Building Airlock Doors Caused Loss of Secondary Containment2017-08-15015 August 2017 Regarding Simultaneously Opened Reactor Building Airlock Doors Caused Loss of Secondary Containment 05000293/LER-1917-010, Re Air Accumulation Creates Small Void in Core Spray Discharge Piping2017-08-0707 August 2017 Re Air Accumulation Creates Small Void in Core Spray Discharge Piping 05000293/LER-1917-009, Regarding Potential Primary Containment System Lnoperability Due to Relay Concerns2017-07-17017 July 2017 Regarding Potential Primary Containment System Lnoperability Due to Relay Concerns 05000293/LER-1917-008, Re 480V Bus B6 Auto Transfer Function Degraded Due to Time Delay Relay Failure2017-06-30030 June 2017 Re 480V Bus B6 Auto Transfer Function Degraded Due to Time Delay Relay Failure 05000293/LER-1917-007, Regarding Potential Inoperability of Safety Relief Valve 3A2017-06-22022 June 2017 Regarding Potential Inoperability of Safety Relief Valve 3A 05000293/LER-1916-010-01, Re MSIV Inoperability2017-06-14014 June 2017 Re MSIV Inoperability 05000293/LER-1917-006, Regarding Source Range Monitor Inoperable During Fuel Movement2017-06-13013 June 2017 Regarding Source Range Monitor Inoperable During Fuel Movement 05000293/LER-1917-005, Regarding 10 CFR 50, Appendix J, Option B, Leak Rate Criteria Exceeded2017-06-0707 June 2017 Regarding 10 CFR 50, Appendix J, Option B, Leak Rate Criteria Exceeded 05000293/LER-1917-004, Regarding Secondary Containment Testing Led to Loss of Safety Function to Both Trains of Standby Gas Treatment System2017-06-0202 June 2017 Regarding Secondary Containment Testing Led to Loss of Safety Function to Both Trains of Standby Gas Treatment System 05000293/LER-1917-002, Regarding Isolation of HPCI2017-05-25025 May 2017 Regarding Isolation of HPCI 05000293/LER-1917-003-01, Regarding Pressure Suppression Pool Declared Inoperable Due to High Water Level2017-05-25025 May 2017 Regarding Pressure Suppression Pool Declared Inoperable Due to High Water Level 05000293/LER-2017-001, Regarding Reactor Building Isolation Dampers Failed to Isolate2017-03-15015 March 2017 Regarding Reactor Building Isolation Dampers Failed to Isolate 05000293/LER-2016-009, Regarding HPCI Declared Inoperable Due to Failure of IST Surveillance Test2017-01-0505 January 2017 Regarding HPCI Declared Inoperable Due to Failure of IST Surveillance Test 05000293/LER-2016-008, Regarding Emergency Diesel Generator a Past Inoperability2016-12-0909 December 2016 Regarding Emergency Diesel Generator a Past Inoperability 05000293/LER-2016-007, Regarding Manual Reactor Scram Due to Feedwater Regulating Valve Malfunction2016-11-0404 November 2016 Regarding Manual Reactor Scram Due to Feedwater Regulating Valve Malfunction 05000293/LER-2016-005, Regarding Ultimate Heat Sink and Salt Service Water System Declared Inoperable2016-10-13013 October 2016 Regarding Ultimate Heat Sink and Salt Service Water System Declared Inoperable 05000293/LER-2016-006, C Main Steam Isolation Valve Inoperable2016-10-13013 October 2016 C Main Steam Isolation Valve Inoperable 05000293/LER-2016-003, Regarding Spent Fuel Storage Design Feature Exceeded2016-07-11011 July 2016 Regarding Spent Fuel Storage Design Feature Exceeded 05000293/LER-2016-004, Regarding Salt Service Water Pump B Past Operability - Operation or Condition Prohibited by Technical Specifications2016-07-11011 July 2016 Regarding Salt Service Water Pump B Past Operability - Operation or Condition Prohibited by Technical Specifications 05000293/LER-2016-002, Regarding Online Maintenance Test Configuration Prohibited by Technical Specifications2016-06-20020 June 2016 Regarding Online Maintenance Test Configuration Prohibited by Technical Specifications 05000293/LER-2016-001, Regarding Both Emergency Diesel Generators Inoperable2016-06-0909 June 2016 Regarding Both Emergency Diesel Generators Inoperable 05000293/LER-2015-004-01, Regarding 480V Bus B6 Auto Transfer Function Degraded2016-03-0808 March 2016 Regarding 480V Bus B6 Auto Transfer Function Degraded 05000293/LER-2015-010, Regarding Motor-Operated Valve Control Circuit Vulnerability to Information Notice 92-18 Concern2015-11-19019 November 2015 Regarding Motor-Operated Valve Control Circuit Vulnerability to Information Notice 92-18 Concern 05000293/LER-2015-007, Regarding Single Main Steam Isolation Valve Closure Resulting in Automatic Reactor Scram2015-10-20020 October 2015 Regarding Single Main Steam Isolation Valve Closure Resulting in Automatic Reactor Scram 05000293/LER-2015-006, Regarding Ultimate Heat Sink and Salt Service Water System Declared Inoperable2015-10-0707 October 2015 Regarding Ultimate Heat Sink and Salt Service Water System Declared Inoperable 05000293/LER-2015-005, Regarding Degrading Condenser Vacuum Resulting in Manual Reactor Scram2015-07-21021 July 2015 Regarding Degrading Condenser Vacuum Resulting in Manual Reactor Scram 05000293/LER-2015-004, Regarding 480 Volt Bus B6 Auto Transfer Function Degraded2015-06-22022 June 2015 Regarding 480 Volt Bus B6 Auto Transfer Function Degraded 05000293/LER-2015-002, Regarding Main Steam Safety Relief Valves Determined to Be Inoperable Following Evaluation2015-05-12012 May 2015 Regarding Main Steam Safety Relief Valves Determined to Be Inoperable Following Evaluation 05000293/LER-2015-001, Regarding Loss of 345KV Power Resulting in Automatic Reactor Scram During Winter Storm Juno2015-04-0101 April 2015 Regarding Loss of 345KV Power Resulting in Automatic Reactor Scram During Winter Storm Juno 05000293/LER-2014-001, Regarding Condition Prohibited by Technical Specifications2014-07-0707 July 2014 Regarding Condition Prohibited by Technical Specifications 05000293/LER-2013-010, Regarding Automatic Group I Primary Containment Isolation Actuation During Plant Startup Due to Reactor High Water Level2013-12-18018 December 2013 Regarding Automatic Group I Primary Containment Isolation Actuation During Plant Startup Due to Reactor High Water Level 05000293/LER-2013-009, Regarding Loss of Offsite Power and Reactor Scram2013-12-13013 December 2013 Regarding Loss of Offsite Power and Reactor Scram 05000293/LER-2013-002, Regarding Revised Schedule SRV-3B Safety Relief Valve Declared Inoperable Due to Leakage and Setpoint Drift2013-11-12012 November 2013 Regarding Revised Schedule SRV-3B Safety Relief Valve Declared Inoperable Due to Leakage and Setpoint Drift 05000293/LER-2013-008, Manual Scram - Reactor Feed Pump Trip2013-10-21021 October 2013 Manual Scram - Reactor Feed Pump Trip 05000293/LER-2013-007, Regarding Ultimate Heat Sink and Salt Service Water System Declared Inoperable2013-09-13013 September 2013 Regarding Ultimate Heat Sink and Salt Service Water System Declared Inoperable 05000293/LER-2013-006, And LER 13-006-00 for Pilgrim Regarding Primary Containment Declared Inoperable During HPCI Testing & HPCI Controller Failure to Achieve Rated Flow While in Auto Mode2013-07-22022 July 2013 And LER 13-006-00 for Pilgrim Regarding Primary Containment Declared Inoperable During HPCI Testing & HPCI Controller Failure to Achieve Rated Flow While in Auto Mode 2019-06-11
[Table view] |
LER-1917-013, Regarding Reportable Conditions Involving Standby Gas Treatment System and Secondary Containment Lnoperability Not Reported During the Previous Three Years |
Event date: |
|
---|
Report date: |
|
---|
Reporting criterion: |
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)(B)
10 CFR 50.73(a)(2)(ix)(A)
10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i) |
---|
2931917013R00 - NRC Website |
|
text
~Entergx January 25, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 SUBJECT: Licensee Event Report 2017-013-00, Reportable Conditions Involving Standby Gas Treatment System and Secondary Containment lnoperability Not Reported During the Previous Three Years Pilgrim Nuclear Power Station Docket No. 50-293 Renewed License No. DPR-35 LETTER NUMBER: 2.18.001
Dear Sir or Madam:
The enclosed Licensee Event Report 2017-013-0.0, Reportable Conditions Involving Standby Gas Treatment System and Secondary Containment lnoperability Not Reported During the Previous Three Years, is submitted in accordance with Title 10 Code of Federal Regulations 50. 73.
If you have any questions or require additional information, please contact me at (508) 830-7127.
There are no regulatory commitments contained in this letter.
Peter J.
ner Acting Manager, Regulatory Assurance PJM/sc Attachment: Licensee Event Report 2017-013-00, Reportable Conditions Involving Standby Gas Treatment System and Secondary Containment lnoperability Not Reported During the Previous Three Years (4 pages)
Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station cc:
Mr. David C. Lew Acting Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Mr. John Lamb, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8C2A Washington, DC 20555 NRG Senior Resident Inspector Pilgrim Nuclear Power Station Letter No. 2.18.001 Page 2 of 2
Attachment Letter Number 2.18.001 Licensee Event Report 2017-013-00, Reportable Conditions Involving Standby Gas Treatment System and Secondary Containment lnoperability Not Reported During the Previous Three Years (4 Pages)
BNRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2017) htt12://www.nrc.gov/reading-rm/doc-collections/nur§9s/staff/sr1022/r3/)
the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
.PAGE Pilgrim Nuclear Power Station 05000 293 1 OF4
- 4. TITLE Reportable Conditions Involving Standby Gas Treatment System and Secondary Containment lnoperability Not Reported During the Previous Three Years
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR REV MONTH DAY YEAR N/A NUMBER NO.
05000 N/A 11 26 2017 2017
- - 013
- - 00 01 25 2018 FACILITY NAME DOCKET NUMBER N/A 05000 N/A
- 9. OPERA TING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
N D 20.2201(b)
D 20.2203(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A)
D 20.2201(d)
D 20.2203(a)(3)(ii)
D 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
D 20.2203(a)(1)
D 20.2203(a)(4)
D so.73(a)(2)(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(i)*
D 50.36(c)(1 )(i)(A)
D 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL D 20.2203(a)(2)(ii)
D 50.36(c)(1)(ii)(A)
D 50.73(a)(2)(v)(A)
D 73.71(a)(4)
D 20.2203(a)(2)(iii)
D so.36(c)(2)
D 50.73(a)(2)(v)(B)
D 73.71(a)(5) 100 D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
~ 50.73(a)(2)(v)(C)
D 73.77(a)(1)
D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
~ 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii)
D 50.73(a)(2)(i)(C) 0 OTHER Specify in Abstract below or in NRG Form 366A
- 12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT IILEPHONE NUMBER (Include Area Code}
IMr. Peter J. Miner -Acting, Regulatory Assurance Manager
~08-830-7127
, CAUSE SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TOEPIX FACTURER TO EPIX X
BH y
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR igj YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
D NO SUBMISSION 04 18 18 DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On November 26, 2017, with the Reactor in the Run Mode at 100 percent power, while reviewing a procedure to be performed during normal scheduled testing it was determined that the test as written would cause both trains of Standby Gas Treat_ment System (SGTS) to be made inoperable during the test. This also made secondary containment system (SCS) inoperable. This LER is submitted to acknowledge that Pilgrim Nuclear Power Station missed providing Event Notifications and LERs for past occurrences. With both trains of SGTS and SCS inoperable while in Run, this event is reportable in accordance with Title 10 Code of Federal Regulations 50.73(a)(2)(v)(C) and 50.73(a)(2)(v)(D) as conditions that could have prevented the fulfillment of the safety function of a structure or system needed to control the release of radioactive material and mitigate the consequences of an accident. This has been determined to be a reportable condition that has not been reported during the past three years involving SGTS and secondary containment inoperability. The reportable conditions have occurred several times within the past three years during scheduled testing of SGTS.
This event had no impact on the health and/or safety of the public.
BACKGROUND SEQUENTIAL NUMBER
- - 013 REV NO.
- - 00 The Pilgrim Nuclear Power Station (PNPS) Standby Gas Treatment System (SGTS) is part of the Secondary Containment System (SCS) and addresses the SGTS air filtration trains, including the ducting, the exhaust fans, the dampers, and the various filtration media. SCS is designed, in conjunction with other engineered safeguards and nuclear safety systems, to limit the release of radioactive material during normal plant operations within the limits of Title 10 Code of Federal Regulations ( 10 CFR) Part 20 and to limit the release of radioactive material so that off-site dose from a postulated design basis accident will be below the guideline values in 10 CFR Part 100.
The SGTS discharges processed gases to the Main Stack via underground piping. The Main Stack provides an elevated release point for the processed gases. The mission time for tre SCS is 30 days.
PNPS Technical Specification (TS) 3/4. 7.B.1 governs the operability requirements of the SGTS. The specification requires that with certain exceptions, the SGTS shall be operable during periods that include reactor power operation (RUN, STARTUP, and HOT SHUTDOWN modes), during movement of irradiated fuel assemblies in secondary containment, during movement of new fuel over the spent fuel pool, during CORE ALTERATIONS, and during operations with a potential for draining the reactor vessel (OPDRVs).
PNPS TS 3.7.C.1 requires secondary containment shall be OPERABLE when in the RUN, STARTUP, and HOT SHUTDOWN modes, <:luring movement of recently irradiated fuel assemblies in the secondary containment, and during OPDRVs.
There are two principal accidents for which credit is taken for secondary containment operability. These are a loss of coolant accident and a fuel handling accident involving "recently irradiated fuel." The SCS performs no active function in response to each of these limiting events; however, its leak tightness is required to ensure that the release of radioactive materials from primary containment is restricted to those leakage paths and associated leakage rates assumed in the accident analysis and that fission products entrapped within the SCS will be treated by the SGTS prior to discharge to the environment.
EVENT DESCRIPTION
On November 26, 2017, with the Reactor in the Run Mode at 100 percent power, while reviewing procedures to be performed during a normal scheduled work week it was determined that if the procedure was performed as written would cause both trains of SGTS and SCS to be made inoperable. A follow up review determined that procedures have been performed several times within the past three years that caused both trains of SGTS and SCS to be made inoperable during scheduled testing of SGTS.
Page 2 of 4 (04-2017)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 3/31/2020
/"'"'""
=
i
\\
I" LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET (See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r30
, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITYNAME
- 2. DOCKET NUMBER
- 3. LER NUMBER Pilgrim Nuclear Power Station 05000- 293 YEAR 2017 SEQUENTIAL NUMBER
- - 013 REV NO.
- - 00 This has been determined to be a reportable condition that has not been reported during the past three years involving the SGTS and SCS inoperability.
With both trains of SGTS and SCS inoperable in the Run mode this event is reportable per the requirements of 10 CFR 50. 73(a)(2)(v)(C) and* 1 O CFR 50. 73(a)(2)(v)(D), any event that could have prevented the fulfillment of the safety functions to control the release of radioactive material and mitigate the consequences of an accident.
A Root Cause Evaluation is underway and additional information will be provided at the conclusion of this ongoing investigation.
CAUSE OF THE EVENT
The direct cause of this event is still under investigation and will be provided in a supplement to this LER.
CORRECTIVE ACTIONS
~n interim corrective action to place the identified procedures on administrative hold has been implemented.
SAFETY CONSEQUENCES
rThere were no consequences to the safety of the general public, nuclear safety, industrial safety, or radiological safety due to this event. The actual consequences were a loss of safety function for SCS and SGTS while performing the surveillance.
There was no adverse impact on the public health or safety.
(
REPORT ABILITY With both trains of SGTS and SCS inoperable in the Run mode, this event is reportable per the requirements of 10 CFR 50.73(a)(2)(v)(C) and 10 CFR 50.73(a)(2)(v)(D), any event or condition that could have prevented the
'"ulfillment of the safety functions to control the release of radioactive material and mitigate the consequences of an accident.
Page 3 of 4 (04-2017)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 3/31/2020
/""
R
..... /
LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET (See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/readinq-rm/doc-collections/nuregs/staff/sr1022/r3Q
, the NRG may not conduct or sponsor, and a perlion is not required to respond to, the information collection.
- 3. LERNUMBER Pilgrim Nuclear Power Station 05000- 293 YEAR 2017 PREVIOUS EVENTS SEQUENTIAL NUMBER
- - 013 REV NO.
- - 00 A review was conducted of PNPS LERs issued in the past five (5) years. The review focused on LERs that involved similar events where the SGTS function was lost. This review identified similar events documented in:
- 1) LER 2017-004-00 "Secondary Containment Testing Led to Loss of Safety Function"
- 2) LER 2012-003-00 "Both Trains of Standby Gas Treatment System Inoperable" REFERENCES CR-PNP-2017-02900 CR-PNP-2017-11714 Page 4 of 4
|
---|
|
|
| | Reporting criterion |
---|
05000293/LER-1917-002, Regarding Isolation of HPCI | Regarding Isolation of HPCI | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000293/LER-1917-003-01, Regarding Pressure Suppression Pool Declared Inoperable Due to High Water Level | Regarding Pressure Suppression Pool Declared Inoperable Due to High Water Level | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000293/LER-1917-004, Regarding Secondary Containment Testing Led to Loss of Safety Function to Both Trains of Standby Gas Treatment System | Regarding Secondary Containment Testing Led to Loss of Safety Function to Both Trains of Standby Gas Treatment System | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000293/LER-1917-005, Regarding 10 CFR 50, Appendix J, Option B, Leak Rate Criteria Exceeded | Regarding 10 CFR 50, Appendix J, Option B, Leak Rate Criteria Exceeded | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000293/LER-1917-006, Regarding Source Range Monitor Inoperable During Fuel Movement | Regarding Source Range Monitor Inoperable During Fuel Movement | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000293/LER-1917-007, Regarding Potential Inoperability of Safety Relief Valve 3A | Regarding Potential Inoperability of Safety Relief Valve 3A | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) | 05000293/LER-1917-008, Re 480V Bus B6 Auto Transfer Function Degraded Due to Time Delay Relay Failure | Re 480V Bus B6 Auto Transfer Function Degraded Due to Time Delay Relay Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000293/LER-1917-009, Regarding Potential Primary Containment System Lnoperability Due to Relay Concerns | Regarding Potential Primary Containment System Lnoperability Due to Relay Concerns | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000293/LER-1917-010, Re Air Accumulation Creates Small Void in Core Spray Discharge Piping | Re Air Accumulation Creates Small Void in Core Spray Discharge Piping | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000293/LER-1917-011, Regarding Simultaneously Opened Reactor Building Airlock Doors Caused Loss of Secondary Containment | Regarding Simultaneously Opened Reactor Building Airlock Doors Caused Loss of Secondary Containment | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000293/LER-1917-012, Regarding Start-Up Transformer Degraded Voltage Relay Found Outside Technical Specification Limit | Regarding Start-Up Transformer Degraded Voltage Relay Found Outside Technical Specification Limit | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000293/LER-1917-013, Regarding Reportable Conditions Involving Standby Gas Treatment System and Secondary Containment Lnoperability Not Reported During the Previous Three Years | 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)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
|