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MONTHYEARML0629000372006-10-20020 October 2006 Summary of 09/21/2006 Teleconference Re Extension of Relief Requests 2 & 3 for the Fourth 10-Year Inservice Testing Program Interval Project stage: Meeting ML0627604452006-10-20020 October 2006 Extension of Relief Requests 2 & 3 for Fourth 10-Year Inservice Testing Program Interval Project stage: Other 2006-10-20
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Category:Letter
MONTHYEARIR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24158A5912024-06-0606 June 2024 CFR 50.46 LOCA Annual Report L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24128A2572024-05-16016 May 2024 ISFSI A13 Acceptance Letter IR 05000282/20240012024-05-15015 May 2024 Integrated Inspection Report 05000282/2024001 and 05000306/2024001 ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent Report ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report ML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML24128A0882024-04-30030 April 2024 Submittal of Updated Safety Analysis Report (Usar), Revision 38 ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 ML24100A8042024-04-24024 April 2024 – Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing ML24114A0882024-04-23023 April 2024 Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP) ML24113A1182024-04-12012 April 2024 NRC Letter Re NRC Office of Investigations Report No. 3-2023-004 ML24100A1212024-04-0909 April 2024 Submittal of Revised Pressure and Temperature Limits Report L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction Report ML24089A2402024-03-29029 March 2024 Guarantee of Payment of Deferred Premiums ML24060A1232024-03-27027 March 2024 to Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) ML24088A1102024-02-25025 February 2024 Fairbanks Morse (Fm) Part 21 Notification Report Number 23-01 Re Asco Stainless Steel Solenoid Valves L-PI-24-009, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing2024-02-13013 February 2024 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing ML24040A1712024-02-0909 February 2024 Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software IR 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, IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 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 ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota 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 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 2024-08-05
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October 20, 2006Mr. Thomas J. PalmisanoSite Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -EXTENSION OF RELIEF REQUESTS 2 AND 3 FOR THE FOURTH 10-YEAR INSERVICE TESTING PROGRAM INTERVAL (TAC NOS. MD3123 AND MD3124)
Dear Mr. Palmisano:
By letter dated July 25, 2005, the Nuclear Regulatory Commission granted interim relief untilSeptember 30, 2006 to Prairie Island Nuclear Generating Plant, Units 1 and 2, for Relief Requests 2 and 3 associated with the fourth 10-year inservice testing interval. In a letter dated June 28, 2004, NMC requested relief for Diesel-driven cooling water pumps 12and 22, and motor-driven cooling water pump 121. Relief was requested from ISTB-3550, which requires that a rate or quantity meter be installed in each of the pump test circuits. If a meter does not indicate the flow directly, the record shall include the method used to reduce the data. The Licensee proposed alternative pump testing using non-instrumented bypass lines that feed a jacket cooler and a gear oil cooler. Additional unmetered flow feeds the chemical treatment, and filtered water system. In a letter dated July 25, 2005, the staff evaluated these alternate methods and concluded thatthe bypass lines are not fixed resistance systems and fouling of the associated equipment could change the resistance of the bypass lines and potentially mask pump degradation. Long-term relief could not be granted due to the lack of information in the relief request explaining how the testing will account for potential masking of degrading flow rates. However, interim relief was granted pursuant to 10 CFR 50.55a(f)(6)(i) based on theimpracticality of the design and the burden that would result if the Code requirements were immediately imposed, such as a plant shutdown because testing in accordance with the Code could not be performed. The staff also concluded that the current test method will identify significant degrading trends for an interim period, providing an adequate level of assurance of the operational readiness of the pumps.The staff further concluded that granting relief would not endanger life or property or thecommon defense and security and was otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. The licensee was requested to respond prior to September 30, 2006, to inform the staff T. Palmisano-2-of actions taken to achieve compliance with the code requirements. The licensee responded ina letter dated September 19, 2006, and requested an extension of the interim relief for Relief Requests 2 and 3 until May 30, 2007.
The licensee determined that a modification to the system piping was necessary to comply with the Code requirements. Implementation of the modification was originally planned so that the requirements of the Code could be met prior to the expiration of the interim relief period.
However, it was recently identified that some components received for the modification do not reflect parameters assumed in the modification design and therefore, portions of the modification require reanalysis and will delay installation of the modification. Additionally, the onset of colder weather will decrease plant cooling water loads, thus making it difficult to achieve adequate flows for the required pump tests. The licensee requested an extension of interim Relief Requests 2 and 3 until May 30, 2007, toallow completion of the modification and to allow testing during a period of higher cooling water loads. The staff has determined that the proposed extension to May 30, 2007, of interim Relief Requests 2 and 3 is acceptable based on the time frame required to complete installation of the modification package and to allow testing of the pumps during a period of higher cooling water loads. The current test method will continue to identify any significant degrading trends during the extension period, which will provide an adequate level of assurance of the operational readiness of the pumps. Verbal relief was granted to Prairie Island Unit 1 and 2, during a telephone conference held on September 21, 2006 (ML062900037). If you have further questions, please contact Mahesh Chawla at (301) 415-8371. Sincerely, /RA/Martin C. Murphy, Acting ChiefPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-282 and 50-306
cc: See next page T. Palmisano-2-The licensee determined that a modification to the system piping was necessary to comply withthe Code requirements. Implementation of the modification was originally planned so that the requirements of the Code could be met prior to the expiration of the interim relief period.
However, it was recently identified that some components received for the modification do not reflect parameters assumed in the modification design and therefore, portions of the modification require reanalysis and will delay installation of the modification. Additionally, the onset of colder weather will decrease plant cooling water loads, thus making it difficult to achieve adequate flows for the required pump tests. The licensee requested an extension of interim Relief Requests 2 and 3 until May 30, 2007, toallow completion of the modification and to allow testing during a period of higher cooling water loads. The staff has determined that the proposed extension to May 30, 2007, of interim Relief Requests 2 and 3 is acceptable based on the time frame required to complete installation of the modification package and to allow testing of the pumps during a period of higher cooling water loads. The current test method will continue to identify any significant degrading trends during the extension period, which will provide an adequate level of assurance of the operational readiness of the pumps. Verbal relief was granted to Prairie Island Unit 1 and 2, during a telephone conference held on September 21, 2006 (ML062900037). If you have further questions, please contact Mahesh Chawla at (301) 415-8371. Sincerely, /RA/Martin C. Murphy, Acting ChiefPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-282 and 50-306
cc: See next pageDISTRIBUTIONPUBLICLPLIII-1 R/FRidsNrrPMMChawlaRidsNrrLATHarrisRidsNrrDorlLpleRidsOgcRpTLiuWPoertner RidsAcrsAcnwMailCenterRidsRgn3MailCenterTBloomer, EDO RIIIADAMS Accession Number: ML062760445OFFICELPL3-1/PMLPL3-1/LACPTB:BCOGCLPL3-1/BC(A)NAMEMChawlaTHarrisJHuang forTLiuTCampbellMMurphyDATE10/ /0610/17/0610/17/0610/19/0610/20/06OFFICIAL RECORD COPY Prairie Island Nuclear Generating Plant, Units 1 and 2 cc:
Jonathan Rogoff, EsquireVice President, Counsel & Secretary Nuclear Management Company, LLC 700 First Street Hudson, WI 54016Manager, Regulatory AffairsPrairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089Manager - Environmental Protection DivisionMinnesota Attorney General's Office 445 Minnesota St., Suite 900 St. Paul, MN 55101-2127U.S. Nuclear Regulatory CommissionResident Inspector's Office 1719 Wakonade Drive East Welch, MN 55089-9642Regional Administrator, Region IIIU.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351AdministratorGoodhue County Courthouse Box 408 Red Wing, MN 55066-0408CommissionerMinnesota Department of Commerce 85 7th Place East, Suite 500 St. Paul, MN 55101-2198Tribal CouncilPrairie Island Indian Community ATTN: Environmental Department 5636 Sturgeon Lake Road Welch, MN 55089Nuclear Asset ManagerXcel Energy, Inc.
414 Nicollet Mall, R.S. 8 Minneapolis, MN 55401Michael B. SellmanPresident and Chief Executive Officer Nuclear Management Company, LLC 700 First Street Hudson, MI 54016Craig G. AndersonSenior Vice President, Group Operations Nuclear Management Company, LLC 700 First Street Hudson, WI 54016