|
|
Line 3: |
Line 3: |
| | issue date = 07/07/2016 | | | issue date = 07/07/2016 |
| | title = Temporary Instruction 2515/191 Inspection Report 05000293/2016013 | | | title = Temporary Instruction 2515/191 Inspection Report 05000293/2016013 |
| | author name = Ferdas M S | | | author name = Ferdas M |
| | author affiliation = NRC/RGN-I/DRP | | | author affiliation = NRC/RGN-I/DRP |
| | addressee name = Dent J | | | addressee name = Dent J |
Line 9: |
Line 9: |
| | docket = 05000293 | | | docket = 05000293 |
| | license number = DPR-035 | | | license number = DPR-035 |
| | contact person = Ferdas M S | | | contact person = Ferdas M |
| | document report number = IR 2016013 | | | document report number = IR 2016013 |
| | document type = Inspection Report, Letter | | | document type = Inspection Report, Letter |
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD. KING OF PRUSSIA, PA 19406-2713 July 7, 2016 | | {{#Wiki_filter:July 7, 2016 |
|
| |
|
| Mr. John Dent Site Vice President Entergy Nuclear Operations, Inc.
| | ==SUBJECT:== |
| | | PILGRIM NUCLEAR POWER STATION - TEMPORARY INSTRUCTION 2515/191 INSPECTION REPORT 05000293/2016013 |
| 600 Rocky Hill Road Plymouth, MA 02360-5508
| |
| | |
| SUBJECT: PILGRIM NUCLEAR POWER STATION - TEMPORARY INSTRUCTION 2515/191 INSPECTION REPORT 05000293/2016013 | |
|
| |
|
| ==Dear Mr. Dent:== | | ==Dear Mr. Dent:== |
Line 40: |
Line 37: |
| Docket No. 50-293 License No. DPR-35 | | Docket No. 50-293 License No. DPR-35 |
|
| |
|
| Enclosure: | | ===Enclosure:=== |
| Inspection Report 05000293/2016013 w/Attachment: Supplementary Information | | Inspection Report 05000293/2016013 w/Attachment: Supplementary Information |
|
| |
|
| cc w/encl: Distribution via ListServ
| | REGION I== |
| | |
| ML16189A066 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRS RI/DRP RI/DRP NAME WCook/WAC ABurritt/ALB MFerdas/MSF DATE 6/27/16 6/23/16 7/7/16
| |
| | |
| 1 Enclosure U.S. NUCLEAR REGULATORY COMMISSION
| |
| | |
| ==REGION I==
| |
| Docket No. 50-293 | | Docket No. 50-293 |
|
| |
|
Line 209: |
Line 200: |
| None | | None |
| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| ===Procedures===
| | |
| : 5.3.26, RPV Injection During Emergencies, Revision 29
| |
| : 5.3.31, Station Blackout, Revision 21 5.3.36, Extensive Damage Mitigation Guidelines (EDMG) Support Procedures and Strategies, Revision 11 5.9.1, Extended Loss of AC Power (ELAP), Revision 1
| |
| : 5.9.2, (FSG-1) Alternate Reactor Vessel Cooling, Revision 1
| |
| : 5.9.2.1, FLEX Low Pressure Injection - Pre-Staged Equip (5.2. Use as 1
| |
| st option if pre-staged) 5.9.2.2, FLEX Low Pressure Injection - CST through Fire Water X-Tie Injection Point to RPV, Revision 2 5.9.2.3, FLEX Low Pressure Injection - FRAC Tank to RPV, Revision 3 5.9.2.4, FLEX Low Pressure Injection - Seawater through CST Injection Point to RPV, Revision 1
| |
| : 5.9.2.5, FLEX Low Pressure Injection - Seawater through Fire Water X-Tie Injection Point to
| |
| : RPV, Revision 1
| |
| : 5.9.4, DC Bus Load Shed & Repower Battery Chargers and Safeguards Panels (FSG-4)
| |
| : 5.9.4.1, DC Load Shedding, Revision 2 5.9.4.2, Repower Battery Chargers D11, D12, D13, D14 and D15, Revision 1
| |
| : 5.9.4.3, Repower Safeguard Panels Y3/Y31, Y4/Y41, Y13 and Y14
| |
| : 5.9.5, Initial Assessment and FLEX Equipment Staging (FSG-5), Revision 2
| |
| : 5.9.5.1, Debris Removal from Deployment Pathways, Revision 2 5.9.5.2, Retrieval and Staging of FLEX Equipment, Revision 2 5.9.5.3, Refuel Diesel Engines, Revision 1
| |
| : 5.9.7, Alternate Spent Fuel Pool Makeup and Cooling (FSG-11), Revision 2
| |
| : 5.9.7.1, Secondary Containment Ventilation, Revision 1
| |
| : 5.9.7.2, Spent Fuel Pool Makeup Using Sandpiper, Revision 2 5.9.7.3, Spent Fuel Pool Makeup through Fire Water X-Tie to RHR/SSW X-Tie 5.9.8, Alternate Containment Cooling and Hydrogen Control (FSG-12), Revision 2
| |
| : 5.9.8.1, Emergency Primary Containment Venting, Revision 1
| |
| : 5.9.8.2, Direct Torus Vent Condensate Removal
| |
| : 5.9.8.3, Backup Nitrogen to Open
| |
| : AO-5025 and
| |
| : AO-5042B, Revision 0
| |
| : 5.9.8.4, Main Stack Condensate Removal and Alternate Vent Path 5.9.9, Transition from FLEX Equipment (FSG-13), Revision 1 5.9.10, BDBEE/ELAP Emergency Response (FSG-100)
| |
| : 5.9.11, BDBEE Communications (FSG-101)
| |
| : 5.9.12, SAFER National Center Equipment Utilization
| |
| : EOP-01, RPV Control, Revision 14
| |
| : EOP-02, RPV Control, Failure-To-Scram, Revision 14
| |
| : EOP-03, Primary Containment Control, Revision 11
| |
| : EOP-11, Figures, Cautions and Icons, Revision 6
| |
| : EOP-16, RPV Flooding, Revision 7
| |
| : EOP-17, Emergency RPV Depressurization, Revision 6
| |
| : EOP-18, Steam Cooling, Revision 3
| |
| : EOP-26, RPV Flooding, Failure-To-Scram, Revision 8
| |
| : EOP-27, Emergency RPV Depressurization, Failure-To-Scram, Revision 5
| |
| : 8.E.19, Fuel Pool and Skimmer Surge Tank Instruments - Critical Maintenance, Revision 40
| |
| : 2.1.49, FLEX Equipment Prestaging Prior to Reactor Head De-tensioning and Re-tensioning" Revision 1
| |
| : 2.2.17, Communications Systems, Revision 43 2.2.85, Fuel Pool Cooling and Filtering System, Revision 94
| |
| : SEP-PNPS-IST-006, Administration of Non-Code Class Pressure Relief Device Test Program to meet 10CFR50 Appendix B Criterion, Revision 2 8.E.19, Spent Fuel Pool Level Instrument Channel Functional Test, Revision 39
| |
| : 2.1.35, Control Room Readings, Revision 58
| |
| : EN-OP-201-06, Pilgrim Nuclear Power Station FLEX Program Document, Revision 0 Air Operated S1F Metallic Design Level 1 Ball Valve Sandpiper Double Diaphragm Pump Manufacturer Data Manual, Revision 0508
| |
| : EN-OP-201-06, Pilgrim Nuclear Power Station FLEX Program Document, Revision 0.
| |
| : PLP-NS-FLEXINTRO, Training Material for Introduction to Flex Mitigation Strategies, Revision 0
| |
| : PLP-EP-FLEXINTRO, Training Material for Introduction to Flex Mitigation Strategies, Revision 2
| |
| : O-RO-03-04-14, Simulator Scenario #1, Extended Loss of AC Power (ELAP), Revision 0 O-RQ-06-02-98 (03), Simulator Scenario #3, Earthquake, Loss of Off-Site Power, A5 Bus Lockout, Torus Leak, Direct Torus Vent, Loss Level Indication, Revision 1 O-RQ-04-01-206, Training Material for FLEX Modification Overview, Revision 2
| |
| : O-RQ-04-01-210, Training Material for EOP Revision 3 Changes, Revision 1
| |
| : O-RQ-04-01-232, Training Material for PNPS Flex Mitigation Strategies, Revision 0
| |
| : O-RQ-04-01-236, Training Material for Extended Loss of AC Power (ELAP), Revision 0 O-RQ-04-01-232, PNPS Flex Mitigation Strategies, Training Attendance Records O-RO-03-04-14, PNPS Flex ELAP Simulator Scenario, Training Attendance Records
| |
| : O-RQ-04-01-206, FLEX Modification Overview, Training Attendance Records
| |
| : O-RQ-04-01-210, EOP Revision 3 Changes, Training Attendance Records
| |
| : O-RQ-06-02-98(03), EOP Revision 3 FLEX/ELAP Scenario, Training Attendance Records
| |
| : PLP-NLO-46, FLEX Case Wheel Loader 1121F, Training Attendance Records
| |
| ===Drawings===
| |
| : Drawing No. E304, Rev. 6, Conduit & Cable Tray Layout; Reactor Building - Area 1 & 3, Elevation 117'-0"
| |
| : FLEX-05
| |
| ===Calculations===
| |
| : Calculation No. M1411, Temperature Response of Key Rooms During an ELAP Event, Revision 0
| |
| : Engineering Changes
| |
| : Engineering Change (EC) 45088
| |
| : EC 45566 Attachment 6.001, Hose Length Evaluation, dated 11/1/2013
| |
| : EC 55678 Calculation No. M1411, Temperature Response of Key Rooms during an ELAP
| |
| : Event, dated 3/26/15
| |
| ===Work Orders===
| |
| : 00408542
| |
| : 00407421
| |
| : 00403338
| |
| : 00403353
| |
| : 00403357
| |
| : 00403334
| |
| : 00410890
| |
| : 52690199
| |
| : 00408538
| |
| : 00408526
| |
| : 00408530
| |
| : 51542829
| |
| : 51542428
| |
| : 00444317
| |
| : 00407400
| |
| : 00407365
| |
| : 00407638
| |
| : 00407657
| |
| : 00409150
| |
| : 00409147
| |
| : Other Report No.
| |
| : PNPS-RPT-13-00004, MOHR
| |
| : EFP-IL SFPI System Battery Life Report, Revision 0
| |
| : Report No.
| |
| : PNPS-RPT-13-00006, MOHR
| |
| : EFP-IL SFPI System Supplemental EMC Information, Revision 0 PNPS - Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders
| |
| : EA-12-049 and
| |
| : EA-12-051 (TAC
| |
| : Nos. MF0777 and MF0778) (ML16008B077) Entergy Nuclear Operations, Inc. Letter Dated July 17, 2015, PNPS's Notification of Full Compliance with Order
| |
| : EA-12-049 and the Final Integrated Plan (ML15202A536)
| |
| : Conditions Reports
| |
| : 2016-2737 2016-1646 2016-3385 2016-2039 2016-1838
| |
| : 2016-1846 2016-1415 2016-3504 2015-9724 2015-0261
| |
| : 2016-0164 2016-2613 2016-3730* 2016-3736* 2016-3737*
| |
| : 2016-3739* 2016-3746* 2016-3747* 2016-3749* 2016-3750* 2016-3753* 2016-3755* 2016-3657* 2016-3760* 2016-3763*
| |
| : 2016-3764* (*indicates that Condition Report was generated as a result of this inspection)
| |
| ==LIST OF ACRONYMS==
| |
| : [[ADAMS]] [[Agencywide Document Access and Management System]]
| |
| : [[DRS]] [[Division of Reactor Safety]]
| |
| : [[ELAP]] [[extended loss of all]]
| |
| : [[AC]] [[power]]
| |
| : [[FLEX]] [[Diverse and Flexible Coping Strategies]]
| |
| : [[FSG]] [[]]
| |
| : [[FLEX]] [[Support Guidelines]]
| |
| : [[NRC]] [[Nuclear Regulatory Commission,]]
| |
| : [[U.S.]] [[]]
| |
| SFP spent fuel pool
| |
| : [[TI]] [[temporary instruction]]
| |
| }} | | }} |
|
---|
Category:Inspection Report
MONTHYEARIR 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 IR 05000293/19570012023-05-26026 May 2023 635390- Amendment 8 Providence Imaging Center 50-29357-01/030-38077 IR 05000293/20220042023-02-15015 February 2023 NRC Inspection Report No. 05000293/2022004 IR 05000293/20220032022-11-18018 November 2022 NRC Inspection Report No. 05000293/2022003 IR 05000293/20220022022-08-12012 August 2022 NRC Inspection Report No. 05000293/2022002 IR 05000293/20220012022-05-11011 May 2022 NRC Inspection Report No. 05000293/2022001 IR 05000293/20210042022-02-0909 February 2022 NRC Inspection Report No. 05000293/2021004 IR 05000293/20210032021-11-12012 November 2021 NRC Inspection Report No. 05000293/2021003 IR 05000293/20210022021-08-10010 August 2021 NRC Innspection Report No. 05000293/2021002 ML21187A2702021-07-12012 July 2021 NRC Independent Spent Fuel Storage Security Inspection Report No. 07201044/2021401 IR 05000293/20214022021-07-12012 July 2021 Security Decommissioning Inspection Report 05000293/2021402 IR 05000293/20210012021-05-13013 May 2021 NRC Inspection Report No. 05000293/2021001, Holtec Decommissioning International, LLC, Pilgrim Nuclear Power Station IR 05000293/20214012021-04-27027 April 2021 Security Decommissioning Inspection Report 05000293/2021401 IR 05000293/20200042021-02-22022 February 2021 NRC Inspection Report No. 05000293/2020004, Holtec Decommissioning International, LLC, Pilgrim Nuclear Power Station, Plymouth, Massachusetts IR 05000293/20204012020-12-17017 December 2020 Security Decommissioning Inspection Report 05000293/2020401 Without OUO Enclosure (Public Cover Letter Only) ML20335A0092020-11-30030 November 2020 NRC Inspection Report No. 05000293/2020002 & 2020003, Holtec Decommissioning International, LLC, Pilgrim Nuclear Power Station, Plymouth, Massachusetts IR 05000293/20200022020-11-30030 November 2020 NRC Inspection Report No. 05000293/2020002 & 2020003, Holtec Decommissioning International, LLC, Pilgrim Nuclear Power Station, Plymouth, Massachusetts ML20070P3342020-03-10010 March 2020 NRC Inspection Report No. 07201044/2019001, Holtec Decomissioning International, LLC, Pilgrim Nuclear Power Station, Plymouth, Massachusetts IR 05000293/19820012020-01-0303 January 2020 David Paul Dba C.Q.C. Company; Termination; License 50-29382-01; Docket 030-38241; Control 616184 IR 05000293/20190022019-07-24024 July 2019 Integrated Inspection Report 05000293/2019002 and Assessment Follow-up Letter IR 05000293/20190012019-05-13013 May 2019 Integrated Inspection Report 05000293/2019001 IR 05000293/20180062019-03-0404 March 2019 Annual Assessment Letter for Pilgrim Nuclear Power Station (Report 05000293/2018006) and Confirmatory Action Letter Closure IR 05000293/20180042019-02-13013 February 2019 Integrated Inspection Report 05000293/2018004 and Independent Spent Fuel Storage Installation Report 07201044/2018201 IR 05000293/20180132019-01-23023 January 2019 Confirmatory Action Letter (EA-17-086) Follow-Up Inspection Report 05000293/2018013 IR 05000293/20185012018-12-0606 December 2018 Evaluated Emergency Preparedness Exercise Inspection Report 05000293/2018501 IR 05000293/20180152018-11-21021 November 2018 Triennial Fire Protection Inspection Report 05000293/2018015 IR 05000293/20180032018-11-13013 November 2018 Integrated Inspection Report 05000293/2018003 and Independent Spent Fuel Storage Installation Inspection Report 07201014/2018001 IR 05000293/20180122018-11-0101 November 2018 Confirmatory Action Letter (EA-17-086) Follow-Up Inspection Report 05000293/2018012 IR 05000293/20180112018-10-0909 October 2018 Confirmatory Action Letter (EA-17-086) Follow-Up Inspection Report 05000293/2018011 IR 05000293/20184112018-09-24024 September 2018 Baseline Security Inspection Report 05000293/2018411 IR 05000293/20180052018-08-28028 August 2018 Assessment Follow-up Letter and Updated Inspection Plan (Inspection Report 05000293/2018005) IR 05000293/20180022018-08-14014 August 2018 Integrated Inspection Report 05000293/2018002 IR 05000293/20184102018-06-20020 June 2018 Baseline Security Inspection Report 05000293/2018410 (Letter Only) IR 05000293/20180102018-06-13013 June 2018 Confirmatory Action Letter (EA-17-086) Follow-Up Inspection Report 05000293/2018010 IR 05000293/20180012018-05-14014 May 2018 Integrated Inspection Report 05000293/2018001 IR 05000416/20170142018-03-12012 March 2018 Confirmatory Order, NRC Inspection Report 05000416/2017014, and NRC Investigation Reports 4-2016-004 and 4-2014-021 IR 05000293/20170062018-02-28028 February 2018 Annual Assessment Letter for Pilgrim Nuclear Power Station (Reports 05000293/2017006, 05000293/2017402, and 05000293/2017501) IR 05000293/20170042018-02-14014 February 2018 Integrated Inspection Report 05000293/2017004 IR 05000293/20170102018-02-0101 February 2018 Confirmatory Action Letter (EA-17-086) Follow-Up Inspection Report 05000293/2017010 IR 05000293/20170092017-12-21021 December 2017 Problem Identification and Resolution Inspection Report 05000293/2017009 IR 05000293/20172012017-11-21021 November 2017 NRC Security Inspection Report 05000293/2017201 IR 05000293/20170032017-11-14014 November 2017 Integrated Inspection Report 05000293/2017003 IR 05000293/20174042017-10-17017 October 2017 Material Control and Accounting Program Inspection Report 05000293/2017404 (Letter Only) IR 05000293/20174032017-10-12012 October 2017 Baseline Security Inspection Report 05000293/2017403, (Letter Only) IR 05000293/20170072017-09-28028 September 2017 Design Bases Assurance Inspection Report 05000293/2017007 IR 05000293/20174052017-09-0505 September 2017 Problem Identification and Resolution Sample Inspection Report 05000293/2017405 (Letter Only) IR 05000293/20170052017-08-28028 August 2017 Quarterly Assessment and Updated Inspection Plan for Pilgrim Nuclear Power Station (Report 05000293/2017005) IR 05000293/20170022017-08-14014 August 2017 Integrated Inspection Report 05000293/2017002 IR 05000293/20170082017-08-0909 August 2017 Final Significance Determination for a Green Finding and Results of Regulatory Conference - Inspection Report 05000293/2017008 2023-08-04
[Table view] Category:Letter
MONTHYEARL-24-002, Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G2024-02-0202 February 2024 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G ML23342A1182024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23334A1822023-11-30030 November 2023 Biennial Report for the Defueled Safety Analysis Report Update, Technical Specification Bases Changes, 10 CFR 50.59 Evaluation Summary, and Regulatory Commitment Change Summary November 2021 Through October 2023 L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) L-23-011, 10 CFR 72.48 Biennial Change Summary Report2023-10-27027 October 2023 10 CFR 72.48 Biennial Change Summary Report IR 05000293/20234012023-08-31031 August 2023 NRC Inspection Report No. 05000293/2023401 & 2023001 (Cover Letter Only) IR 05000293/20230022023-08-0404 August 2023 NRC Inspection Report No. 05000293/2023002 L-23-008, Correction to Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations Holtec Decommissioning International, LLC (HDI)2023-05-23023 May 2023 Correction to Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations Holtec Decommissioning International, LLC (HDI) ML23136A7792023-05-15015 May 2023 Annual Radiological Environmental Operating Report, January 1 Through December 31, 2022 ML23135A2152023-05-15015 May 2023 Annual Radioactive Effluent Release Report, January 1 Through December 31, 2022 L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance ML23069A2782023-03-13013 March 2023 Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1 Subsequent License Renewal Application ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000293/20220042023-02-15015 February 2023 NRC Inspection Report No. 05000293/2022004 ML22356A0712023-01-31031 January 2023 Issuance of Exemption for Pilgrim Nuclear Power Station ISFSI Regarding Annual Radioactive Effluent Release Report - Cover Letter ML22347A2782022-12-21021 December 2022 Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022 L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 L-22-041, Supplemental Information to Enhance Exemption Request Detail for Pilgrim ISFSI Annual Radioactive Effluent Release Report Due Date Extension2022-12-0909 December 2022 Supplemental Information to Enhance Exemption Request Detail for Pilgrim ISFSI Annual Radioactive Effluent Release Report Due Date Extension IR 05000293/20220032022-11-18018 November 2022 NRC Inspection Report No. 05000293/2022003 L-22-036, Decommissioning Trust Fund Agreement2022-11-0808 November 2022 Decommissioning Trust Fund Agreement ML22276A1762022-10-24024 October 2022 Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22266A1922022-09-23023 September 2022 and Pilgrim Nuclear Power Station - Request to Withdraw Prior Submissions from NRC Consideration ML22272A0352022-09-22022 September 2022 S. Lynch-Benttinen Letter Regarding U.S. Citizen Intent to Sue U.S. Fish and Wildlife and NOAA Fisheries Representing the Endangered Species (Na Right Whale) Which Will Be Adversely Affected by Holtec International Potential Actions ML22269A4202022-09-22022 September 2022 Citizen Lawsuit ML22241A1122022-08-29029 August 2022 Request for Exemption from 10 CFR 72.212(a)(2), (b)(2), (b)(3), (b)(4), (B)(5)(i), (b)(11), and 72.214 for Pilgrim ISFSI Annual Radioactive Effluent Release Report IR 05000293/20220022022-08-12012 August 2022 NRC Inspection Report No. 05000293/2022002 ML22215A1772022-08-0303 August 2022 Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22206A1512022-08-0101 August 2022 NRC Office of Investigations Case Nos. 1-2022-002 & 1-2022-006 ML22221A2592022-08-0101 August 2022 LTR-22-0217-1-NMSS - Town of Duxbury Letter Opposing the Irradiated Water Release from Pilgrim (Docket No. 05000293) ML22193A1662022-07-28028 July 2022 LTR-22-0154-1 - Heather Govern, VP, Clean Air and Water Program, Et Al., Letter Regarding Radioactive Wastewater Disposal from the Pilgrim Nuclear Power Station (Docket No. 05000293) ML22175A1732022-07-28028 July 2022 LTR-22-0153-1 - Response Letter to D. Turco, Cape Downwinders, from A. Roberts, NRC, Regarding Holtec-Pilgrim Plans to Dump One Million Gallons of Radioactive Waste Into Cape Cod Bay ML22154A4882022-06-0101 June 2022 Letter from Conservation Law Foundation Regarding Irradiated Water Release from Pilgrim ML22154A1622022-05-26026 May 2022 Letter and Email from Save Our Bay/Diane Turco Regarding Irradiated Water Release from Pilgrim ML22136A2602022-05-16016 May 2022 Submittal of Annual Radiological Environmental Operating Report for January 1 Through December 31, 2021 ML22136A2572022-05-16016 May 2022 Submittal of Annual Radioactive Effluent Release Report for January 1 Through December 31, 2021 ML22102A0932022-05-12012 May 2022 LTR-22-0067 Response to Matthew P. Levesque, President, Barnstable Town Council Regarding Irradiated Water Release from Pilgrim IR 05000293/20220012022-05-11011 May 2022 NRC Inspection Report No. 05000293/2022001 ML22104A0542022-04-30030 April 2022 LTR-22-0093 Response to Sheila Lynch-Benttinen, Regarding Irradiated Water Release from Pilgrim L-22-026, Occupational Radiation Exposure Data Report - 20212022-04-29029 April 2022 Occupational Radiation Exposure Data Report - 2021 ML22152A2592022-04-25025 April 2022 Zaccagnini Letter Dated 04/25/22 ML22152A2642022-04-19019 April 2022 Flynn Letter Dated 04/19/22 ML22091A1062022-04-0101 April 2022 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) L-22-022, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec.2022-03-25025 March 2022 and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec. ML22130A6762022-03-14014 March 2022 Decola Ltr Dtd 03/14/22 Re Potential Discharge of Radioactive Water from Pilgrim Nuclear Power Station ML22041B0762022-03-0707 March 2022 03-07-22 - Letter to the Honorable William R. Keating, Responds to Letter Regarding Proposed Release of Irradiated Water at Pilgrim Nuclear Power Station Into Cape Cod Bay ML22054A2962022-02-23023 February 2022 Annual ISFSI Radioactive Effluent Release Report for 2021 2024-02-02
[Table view] |
Inspection Report - Pilgrim - 2016013 |
---|
|
|
Text
July 7, 2016
SUBJECT:
PILGRIM NUCLEAR POWER STATION - TEMPORARY INSTRUCTION 2515/191 INSPECTION REPORT 05000293/2016013
Dear Mr. Dent:
On May 26, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Pilgrim Nuclear Power Station (PNPS). The enclosed report documents the inspection results, which were discussed on May 26, 2016, with you and other members of your staff.
The inspection examined activities conducted un der your license as they relate to the implementation of mitigation strategies and spent fuel pool instrumentation orders (EA-12-049 and EA-12-051) and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, your compliance with the Commission's rules and regulations, and with the conditions of your operating license. Within these areas, the inspection involved examination of selected procedures and records, observation of activities, and interviews with plant personnel.
Based on the results of this inspection, no violations of NRC requirements were identified.
In accordance with Title 10 of the Code of Federal Regulations 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/readingrm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/ Marc S. Ferdas, Chief Technical Support and Assessment Branch Division of Reactor Projects
Docket No. 50-293 License No. DPR-35
Enclosure:
Inspection Report 05000293/2016013 w/Attachment: Supplementary Information
REGION I==
Docket No. 50-293
License No. DPR-35 Report No. 05000293/2016013
Licensee: Entergy Nuclear Operations, Inc. (Entergy)
Facility: Pilgrim Nuclear Power Station
Location: 600 Rocky Hill Road Plymouth, MA 02360
Dates: May 23 - May 26, 2016
Inspectors: W. Cook, Senior Reactor Analyst, Division of Reactor Safety (DRS) E. Carfang, Senior Resident Inspector, Pilgrim T. Dunn, Operations Engineer, DRS B. Pinson, Resident Inspector, Pilgrim
C. Cahill, Senior Reactor Analyst, DRS (Observer) M. Brown, Chief, Orders Management Branch, Japan Lessons-Learned Division, Office of Nuclear Reactor Regulations, (Observer) D. Jackson, Chief, Operations Branch, DRS (Observer)
Approved by: Marc S. Ferdas, Chief Technical Support and Assessment Branch Division of Reactor Projects
2
SUMMARY OF FINDINGS
Inspection Report 05000293/2016013; 05/23/2016 - 05/26/2016; Pilgrim Nuclear Power Station (PNPS); Temporary Instruction (TI) 2515/191, Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness
Communication/Staffing/Multi-Unit Dose Assessment Plans.
The inspection covered a one week inspection by a senior reactor analyst, an operations engineer, a senior resident inspector, and a resident inspector. No findings were identified. The U.S. Nuclear Regulatory Commission's (NRC's) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 5.
3
REPORT DETAILS
4.
OTHER ACTIVITIES
4OA5 Other Activities
TI 2515/191 - Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans The objective of TI 2515/191, "Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans," is to verify:
- (1) that licensees have adequately implemented the mitigation strategies as described in the licensee's Final Integrated Plan (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15202A415)and the NRC's plant safety evaluation (ADAMS Accession No. ML16008B077);
- (2) that licensees have installed reliable water-level measurement instrumentation in their spent fuel pools (SFPs); and
- (3) that licensees have implemented emergency preparedness enhancements as described in their site-specific submittals and NRC safe ty assessments, incl uding dose assessment capability, enhancements to ensure that staffing is sufficient, and that communications can be maintained during beyond-design-basis external events.
The team verified that plans for complying with NRC Orders EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events," (ADA MS Accession No. ML12054A735) and EA-12-051, "Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation," (ADAMS Accession No. ML12056A044) were in place and were being implemented by Entergy. The team also verified that Entergy had implemented staffing and communication plans provided in response to the March 12, 2012, request for information letter and multi-unit dose assessment information provided per COMSECY-13-0010, "Schedule and Plans for Tier 2 Order on Emergency Preparedness for Japan Lessons Learned," dated March 27, 2013 (ADAMS Accession No. ML12339A262).
The team discussed the plans and strategies with Entergy personnel, reviewed documentation, completed a tabletop exercise involving a beyond-design-basis event leading to an extended loss of offsite power and, where appropriate, performed plant walk downs to verify that the strategies could be implemented as stated in Entergy's submittals and the NRC staff prepared safety evaluation. For most strategies, this included verification that the strategy was feasible, procedures and/or guidance had been developed, training had been provided to plant staff, and required equipment had been identified and staged. Specific details of the team's inspection activities are described in the following sections.
Documents reviewed for each section of this report are listed in the Attachment.
1. Mitigation Strategies for Beyond-Design-Basis External Events
a. Inspection Scope
The team examined Entergy's established guidelines and implementing procedures for the beyond-design-basis mitigation strategies. The team assessed how the Entergy staff coordinated and documented the interface/transition between existing off-normal and emergency operating procedures at PNPS with the newly developed mitigation strategies. The team selected a number of mitigation strategies and conducted plant walk downs with licensed operators and responsible plant staff to assess: the adequacy and completeness of the procedures; familiarity of operators with the procedure objectives and specific guidance; staging and compatibility of equipment; and the practicality of the operator actions prescribed by the procedures, consistent with the postulated scenarios.
The team verified that a preventive maintenance program had been established for the Diverse and Flexible Coping Strategies (FLEX) portable equipment, and that periodic
equipment inventories were in place and being conducted. Additionally, the team examined the introductory and planned periodic/refresher training provided to the Operations and PNPS staff most likely to be tasked with implementation of the FLEX mitigation strategies. The team also reviewed the introductory and planned periodic training provided to the Emergency Response Organization personnel.
b.
Assessment Based on samples selected for review, the team verified that Entergy satisfactorily implemented appropriate elements of the FLEX strategy as described in the plant specific submittals and the associated safety evaluation. The team determined that Entergy was in compliance with NRC Order EA-12-049.
The team verified that Entergy satisfactorily:
- Developed and issued FLEX Support Guidelines (FSGs) to implement the FLEX strategies for postulated external events;
- Integrated their FSGs into their existing emergency operating procedures and off-normal procedures such that entry into and departure from the FSGs were clear when using existing plant procedures;
- Protected FLEX equipment from site-specific hazards;
- Developed and implemented adequate testing and maintenance of FLEX equipment to ensure their availability and capability;
- Trained their staff to ensure personnel proficiency in the mitigation of beyond-design-basis events; and
- Developed procedures to ensure that the necessary off-site FLEX equipment would be available from off-site locations.
The team verified that observations made during the inspection were entered into Entergy's corrective action program.
c. Findings
No findings were identified.
2. Spent Fuel Pool Instrumentation
a. Inspection Scope
The team examined PNPS's newly installed SFP in strumentation. Specifically, the team verified the sensors were installed as described in the plant specific submittals and the associated safety evaluation, and that the cabling for the power supplies and the indications for each channel were physically and electrically separated. In addition, the team verified that Entergy had evaluated the environmental conditions and accessibility of the instrumentation.
The team verified that Entergy had approved procedures for maintenance, testing, calibration, and use of the primary and backup SFP instrumentation channels. The team also verified that the procedures followed the industry guidance contained in Nuclear Energy Institute 12-02, "Industry Guidance for Compliance with NRC Order EA-12-051, "To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," and that these procedures were part of an existing Entergy process to be maintained.
b. Assessment Based on samples selected for review, the team determined that Entergy satisfactorily installed and established appropriate operating and maintenance controls for the SFP instrumentation as described in the plant specific submittals and the associated safety evaluation. The team determined that Entergy was in compliance with NRC Order EA-
12-051. The team verified that Entergy satisfactorily:
- Installed the SFP instrumentation sensors, cabling, and power supplies to provide physical and electrical separation as described in the plant specific submittals and safety evaluation;
- Installed the SFP instrumentation display in the accessible location, and environmental conditions as described in the plant specific submittals;
- Trained their staff to ensure personnel proficiency with the maintenance, testing, and use of the SFP instrumentation; and
- Developed and issued procedures for maintenance, testing, and use of the reliable SFP instrumentation.
The team verified that observations made during the inspection were entered into Entergy's corrective action program.
c. Findings
No findings were identified.
3. Staffing and Communication Request for Information
a. Inspection Scope
Through discussions with plant staff, review of documentation, and plant walk downs, the team verified that Entergy had implemented required changes to staffing, communications equipment, and facilities to support an extended loss of all AC power (ELAP) scenario as described in Entergy's staffing assessment and the NRC safety evaluation. The team also verified that Entergy had implemented dose assessment (including releases from SFPs) capability using site-specific dose assessment software, as described in Entergy's dose assessment submittal.
b.
Assessment The team reviewed information provided in Entergy's dose assessment submittal and in response to the NRC's March 12, 2012, request for information letter (ADAMS Accession No. ML12053A340), and verified that Entergy satisfactorily implemented enhancements pertaining to Near-Term Task Force Recommendation 9.3, response to a large scale natural emergency event that results in an ELAP and impedes access to the site.
The team verified the following:
- Entergy satisfactorily implemented required staffing changes to support an ELAP scenario;
- Entergy implemented dose assessment capabilities (including releases from SFPs) using PNPS's site-specific dose assessment software and approach.
The team verified that observations identified during the inspection were entered into Entergy's corrective action program.
c. Findings
No findings were identified.
4OA6 Meetings, Including Exit
On May 26, 2016, the team presented the inspection results to Mr. John Dent, Site Vice President, and other members of the PNPS staff. The team verified that no proprietary information was retained by team members or documented in this report.
ATTACHMENT:
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- P. Benbort, Security Manager
- J. Bonner, Fukushima Project Engineer
- R. Byrne, Regulatory Assurance
- D. Calabrese, Emergency Preparedness Manager
- B. Chenard, Engineering
- F. Clifford, Operations Assistant Manager
- J. Dent, Site Vice President
- J. Edelhauser, Fukushima Project
- G. Flynn, Operations Manager
- R. German, Nuclear Plant Operator
- W. Hendy, Training Instructor
- M. Jacobs, NIOS Manager
- K. Jenks, Fukushima Project Manager
- J. Macdonald, General Manager Plant Operations
- D. Noyes, Recovery Director
- J. Parmenter, Emergency Preparedness Senior Planner
- E. Perkins, Regulatory Assurance Manager
- B. Rancourt, Design Engineering
- M. Romeo, RAPID
- E. Skorupski, Maintenance Manager
- W. Townes, FLEX Marshal, Palisades Operations Department
- G. Vonderesch, Recovery Manager
LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED
Opened and Closed
None
Discussed
None
LIST OF DOCUMENTS REVIEWED