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Category:Inspection Report
MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 IR 05000282/20230112023-05-16016 May 2023 Biennial Problem Identification and Resolution Inspection Report 05000282/2023011 and 05000306/2023011 IR 05000282/20230012023-05-10010 May 2023 Integrated Inspection Report 05000282/2023001 and 05000306/2023001 IR 05000282/20220062023-03-0101 March 2023 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report, Units 1 and 2 (Report 05000282/2022006 and 05000306/2022006) IR 05000282/20224042023-01-30030 January 2023 Material Control and Accounting Program Inspection Report 05000282/2022404 and 05000306/2022404 (Public) IR 05000282/20220042023-01-26026 January 2023 Integrated Inspection Report 05000282/2022004 and 05000306/2022004 IR 05000282/20224032023-01-24024 January 2023 Security Baseline Inspection Report 05000282/2022403 and 05000306/2022403 IR 05000282/20220022022-12-0808 December 2022 RE-Issue Prairie Island Nuclear Generating Plant Integrated Inspection Report 05000282/2022002 and 05000306/2022002 IR 05000282/20224022022-11-30030 November 2022 Cyber Security Inspection Report 05000282/2022402 and 05000306/2022402 IR 07200010/20222012022-11-0909 November 2022 TN-40HT, Dry Storage Cask, Inspection Report No. 07200010/2022201 IR 05000282/20220032022-11-0101 November 2022 Integrated Inspection Report 05000282/2022003 and 05000306/2022003 IR 05000282/20220112022-09-26026 September 2022 Phase 4 Post-Approval Site Inspection for License Renewal Report 05000282/2022011 and 05000306/2022011 IR 05000282/20223012022-08-31031 August 2022 NRC Initial License Examination Report 05000282/2022301; 05000306/2022301 IR 05000282/20220052022-08-29029 August 2022 Updated Inspection Plan for Prairie Island Nuclear Generating Plant (Report 05000282/2022005; 05000306/2022005) IR 05000282/20225012022-08-22022 August 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000282/2022501 and 05000306/2022501 ML22227A1902022-08-16016 August 2022 Island Nuclear Generating Plant, Unit 1 - Notification of NRC Baseline Inspection and Request for Information: Inspection Report 05000282/2022004 ML22222A1732022-08-11011 August 2022 Integrated Inspection Report 05000282/2022002 and 05000306/2022002 IR 05000282/20220102022-06-24024 June 2022 Triennial Fire Protection Inspection Report 05000282/2022010 and 05000306/2022010 IR 05000282/20224012022-05-23023 May 2022 Security Baseline Inspection Report 05000282/2022401 and 05000306/2022401 ML22103A2522022-05-0404 May 2022 Review of the 2021 Steam Generator Tube Inspection Report IR 05000282/20220012022-05-0303 May 2022 Integrated Inspection Report 05000282/2022001, 05000306/2022001, and 07200010/2020001 IR 05000282/20210062022-03-0202 March 2022 Annual Assessment Letter (Report 05000282/2021006 and 05000306/2021006) IR 05000282/20210042022-02-11011 February 2022 Integrated Inspection Report 05000282/2021004 and 05000306/2021004 ML22017A0052022-01-17017 January 2022 (PINGP) 2021 Unit 2 180-Day Steam Generator Tube Inspection Report IR 05000282/20214032021-12-0202 December 2021 Security Baseline Inspection Report 05000282/2021403 and 05000306/2021403 IR 05000282/20210032021-11-12012 November 2021 Integrated Inspection Report 05000282/2021003 and 05000306/2021003 IR 05000282/20210122021-10-27027 October 2021 NRC Inspection Report 05000282/2021012 and 05000306/2021012 IR 05000282/20210052021-09-0101 September 2021 Updated Inspection Plan for Prairie Island Nuclear Generating Plant Units 1 and 2 (Report 05000282/2021005 and 05000306/2021005) IR 05000282/20215012021-08-25025 August 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000282/2021501 and 05000306/2021501 IR 05000282/20210022021-08-0606 August 2021 Integrated Inspection Report 05000282/2021002 and 05000306/2021002 IR 05000282/20214022021-07-28028 July 2021 Security Baseline Inspection Report 05000282/2021402 and 05000306/2021402 IR 05000282/20210102021-06-22022 June 2021 Design Basis Assurance Inspection (Teams) Inspection Report 05000282/2021010 and 05000306/2021010 IR 05000282/20210112021-06-0303 June 2021 Biennial Problem Identification and Resolution Inspection Report 05000282/2021011 and 05000306/2021011 IR 05000282/20210012021-05-0606 May 2021 Integrated Inspection Report 05000282/2021001 and 05000306/2021001 IR 05000282/20214012021-04-21021 April 2021 Security Baseline Inspection Report 05000282/2021401 and 05000306/2021401; Independent Spent Storage Security Inspection Report 07200010/2021401 IR 05000282/20200062021-03-0404 March 2021 Annual Assessment Letter for the Prairie Island Nuclear Generating Plant (Report 05000282/2020006 and 05000306/2020006) IR 05000282/20200022021-02-16016 February 2021 Reissue - Prairie Island Nuclear Generating Plant - Integrated Inspection Report 05000282/2020002; 05000306/2020002; and 07200010/2020001 IR 05000282/20200042021-02-0404 February 2021 Integrated Inspection Report 05000282/2020004 and 05000306/2020004 ML20352A1562020-12-21021 December 2020 Review of the 2018 Steam Generator Tube Inspection Report IR 05000282/20204022020-11-12012 November 2020 Security Baseline Inspection Report 05000282/2020402 and 05000306/2020402 IR 05000282/20200032020-11-10010 November 2020 Integrated Inspection Report 05000282/2020003; 05000306/2020003; and 07200010/2020002 IR 05000282/20203012020-09-22022 September 2020 NRC Initial License Examination Report 05000282/2020301 and 05000306/2020301 IR 05000282/20200052020-09-0101 September 2020 Updated Inspection Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2020005 and 05000306/2020005) 2024-02-01
[Table view] Category:Letter
MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 ML23311A3572023-11-0707 November 2023 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0 ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT ML23181A0192023-06-30030 June 2023 Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 ML23150A1722023-05-30030 May 2023 Preparation and Scheduling of Operator Licensing Examinations 2024-02-01
[Table view] |
Text
August 27, 2019 Mr. Scott Sharp Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company, Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642 SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT
- TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000282/2019012 AND 05000306/2019012
Dear Mr. Sharp:
On July 25, 2019
, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Prairie Island Nuclear Generating Plant and discussed the results of this inspection with Ms. Dominique Wilson, Director of Site Performance Operation Support, and other members of your staff.
The results of this inspection are documented in the enclosed report. The NRC inspectors did not identify any finding or violation of more than minor significance
. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding
."
Sincerely,
/RA/ Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket No s. 05000282 and 05000306 License No s. DPR-42 and DPR-60
Enclosure:
As stated
Inspection Report
Docket Number s: 05000282 and 05000306 License Numbers:
DPR-42 and DPR-60 Report Numbers:
05000282/2019012 and 05000306/2019012 Enterprise Identifier:
I-2019-012-0020 Licensee: Xcel Energy Facility: Prairie Island Nuclear Generating Plant Location: Welch, Minnesota Inspection Dates:
June 24, 2019 to July 25, 2019 Inspectors:
A. Dahbur, Senior Reactor Inspector M. Domke, Reactor Inspector D. Szwarc, Senior Reactor Inspector Approved By:
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensee's performance by conducting a triennial fire protection inspection at Prairie Island Nuclear Generating Plant in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information
. List of Findings and Violations No findings or violations of more than minor significance were identified.
Additional Tracking Items None.
3
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading
-rm/doc-collections/insp
-manual/inspection
-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, "Light
-Water Reactor Inspection Program - Operations Phase." The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.05XT
- Fire Protection
- NFPA 805 Fire Protection Inspection Requirements (IP Section 02.01a)
(3 Sample s) The inspectors evaluated fire protection program implementation in the following selected areas and/or fire zones, including analyzed electrical circuits:
- (1) 18 Unit 2 Relay and Cable Spreading Room;
- (2) 32 "B" Train Hot Shutdown Panel; and
- (3) 59 Auxiliary Building Mezzanine Level.
Analyzed Circuits:
CV-31084, Steam Generator Power Operated Relief Valve; and X-HIAW 48-22, 12 Diesel Cooling Water Pump.
B.5.b Inspection Activities (IP Section 02.03)
(2 Sample s) The inspectors evaluated the following B.5.b Mitigating Strategies:
- (1) Attachment H
- Containment Flooding; and
- (2) Attachment K
- Recovery of D1/D2 Cooling.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 25, 2019, the inspector s presented the triennial fire protection inspection results to Ms. Dominique Wilson, Director of Site Performance Operation Support, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Procedure Type Designation
Description or Title
Revision or Date 71111.05XT
Calculations
P2117-2400-03-00 Calculation for NFPA 805 Safe Shutdown Analysis
- Decay Heat Removal
Corrective Action Documents 01515933 Missing Fire Barrier Between FA 15 And FA 59
03/16/2016
1536541 Unacceptable Thinning Found During Planned MIC Inspection
10/03/2016
500001538543
Issues While Performing SP 1197
10/19/2016
501000016344
Sprinkler Heads Need Cleaning
08/30/2018
501000016839
PENF 19 Concrete Needs Repair
09/13/2018
501000020789
NOS ID: Seal Inspection Justification
2/07/2018
501000028647
B5b Cell Phones Not Tested
06/18/2019
Corrective Action Documents Resulting from Inspection
501000028783
CAP Closed to Lower Severity Level CAP
06/20/2019
501000028976
EDMG Cell Phones
06/26/2019
501000029050
EDMG-1 And PINGP 1385 Not At Gate House
06/27/2019
501000029210
B.5.b Enhancement
06/28/2019
501000029213
Duplicate Calculations Issued
07/02/2019
501000029319
Incorrect Reference In Engineering Change
07/08/2019
501000029377
F5 Appendix D Unit 1/Unit 2 Error
07/0/2019 501000029377
F5 Appendix D U1/U2 Error
07/09/2019
501000029388
PRA Notebook Editorial Error
07/10/2019
501000029467
Error in Compensatory Measure Evaluation
07/12/2019
501000029680
Fire PRA Model Credit For Incipient Detectors
07/17/2019
Drawings 97FP02-2 (97FP02) AFW Pump Room Fire Protection Piping System WPS-10 0 NE-40009 Sheet
12 Diesel Cooling Water Pump
NE-40009 Sheet
12 Diesel Cooling Water Pump
NF-40022-1 Circuit Diagram
- 4KV And 480 Safeguard Buses Unit 1
NF-40322-3 Logic Diagram
- Main Steam System Unit 1
Engineering Changes 21572 NFPA 805 - PINGP Station Fire Damper
-NFPA 805 Transition Activity
-LAR L-PI-12-089, Attachment S, Table S
-02/12/2015
Inspection Procedure Type Designation
Description or Title
Revision or Date 2, Item 16
23914 NFPA 805 - Incipient Detection Project, LAR L
-PI-14-045, Table S-2, Item 5, 8
EC 25100 NFPA 805 - Unit 1 And 2 Auxiliary Feedwater Pump Room Separation
2/02/2016
EC 25124 NFPA 805 12 And 22 DDCLP Modification
Engineering Evaluations
FPCE 18-008 Change Evaluation For H77.3
07/19/2018
FPCE 18-010 Camera To Monitor 22 RCP Motor Lower Oil Reservoir Level
FPCE 18-013 Clearance Order For Pinhole Leak On Pipe 6
-FP-18 2 FPEE 12-010 Access Control (FA15) To Auxiliary Building Mezzanine Level Unit 1 (FA59)
FPEE-12-006 Fire Area 85 Boundaries And F5 Appendix K Barriers
FPEE-14-003 Explosion Analysis For Compressed Gas Cylinders
2/18/2014
FPEE-17-002 NFPA 805 LAR S
-2 Compensatory Measures 0 FPRA-PI-CF Circuit Failure Mode Likelihood Analysis Notebook
04/13/2018
FPRA-PI-MCA Multi-Compartment Analysis Notebook
04/13/2018
FPRA-PI-MSO Fire Multiple Spurious Operation Notebook
04/13/2019
FPRA-PI-RRA Relay Room Analysis Notebook
5.3 V.SMN.15.007
Relay Room Incipient Detection Modification Sensitivity
03/10/2015
Miscellaneous
FL-BSE-100-003L Introduction to Nuclear Security
PINGP 1385
Emergency Response Organization Activation
V.SMN.19.006
PINGP [Prairie Island Nuclear Generating Plant] NFPA [National Fire Protection Association] 805 Monitoring Program Risk Target Values
Operability Evaluations
F5 APP B Control Room Evacuation (Fire)
Procedures
EDMG-2 Guideline for Damage Mitigation Strategies
F5 Appendix A
Detection Zones and Fire Areas
F5 APPENDIX D
Impact of Fire Outside Control/Relay Room
F5 Appendix D
Impact of Fire Outside Control/Relay Room
F5 Appendix F
Fire Hazards Analysis
F5 Appendix K
Fire Protection Systems Functional Requirements
FP-PE-PRA-02 PRA Guideline for Model Maintenance and Update
Inspection Procedure Type Designation
Description or Title
Revision or Date H77 Fire Protection Program
H77.1 Fire Protection Program NFPA 805 Chapter 3 Compliance Summary (NEI 04
-02 Table B
-1) 2 H77.2 Fire Protection Program NSCA Methodology Compliance (NEI 04-02 Table B
-2) 0 H77.3 Fire Area Assessmen
ts 0 Work Orders
700010880 SP 1192 Safeguards Electrical And Mechanical Penetrations Surveillance Inspection
10/15/2018
700025089 SP 1197 Annual Header/Drains Flush Fire Protection System
06/18/2018
700028970 SP 1275 18 Month Safe Shutdown Fire Barrier Inspection
08/01/2018
700030214 SP 1196 Fire Protection Safety Related Sprinkler System Test 08/30/2018
700032679 TP 1423 Portable Diesel Fire Pump Test
09/17/2018
700041404 SP 1197 Annual Header/Drains Flush Fire Protection System
07/13/2018