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Category:Letter
MONTHYEARIR 05000282/20244032024-10-25025 October 2024 – Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403 05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-10-22022 October 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies L-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML24277A1012024-10-0303 October 2024 Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software ML24221A3622024-09-27027 September 2024 Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3 ML24241A1682024-09-23023 September 2024 Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation 05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies IR 05000282/20243012024-09-13013 September 2024 NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301 IR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter IR 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 05000306/LER-2024-001-01, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-05-31031 May 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24149A3712024-05-29029 May 2024 (Ping) - 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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) 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 ML24081A1532024-03-21021 March 2024 Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables ML24262A1512024-03-15015 March 2024 L-PI-24-011 150 Day Letter 2024 PINGP ILT NRC Exam ML24010A0582024-03-0505 March 2024 Amendment No. 12 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation 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 2024-09-27
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November 16, 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, UNIT 2 - TELEPHONECONFERENCE TO DISCUSS THE RESULTS OF THE STEAM GENERATOR INSPECTION DURING UPCOMING UNIT 2 REFUELING OUTAGE (TAC NUMBER MD3441)
Dear Mr. Palmisano:
The Nuclear Regulatory Commission (NRC) staff would like to discuss results of the steamgenerator (SG) tube inspections to be conducted during the upcoming Prairie Island Nuclear Generating Plant, Unit 2 refueling outage. Please review the enclosed discussion points, which have been prepared to facilitate the phone conference with your representatives. We would like to schedule this phone call towards the end of the planned SG tube inspection interval, but before the unit completes the inspections and repairs.If you have any questions regarding this response, please contact me.Sincerely,/RA/Mahesh Chawla, Project ManagerPlant Licensing Branch III-1Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-306
Enclosure:
As statedcc: see next page
ML063120515OFFICENRR/LPL3-1/PMNRR/LPL3-1/LABC:AFPBNRR/LPL3-1/BCNAMEMChawla: caTHarrisPaul KleinLRaghavanDATE11/ 9/0611/9/0611/15/0611/16/06 STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTSPREPARED BY THE OFFICE OF NUCLEAR REACTOR REGULATIONNUCLEAR MANAGEMENT COMPANYPRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2DOCKET NO. 50-306The following discussion points have been prepared to facilitate the phone conference arrangedwith the Nuclear Management Company licensee to discuss the results of the steam generator(SG) tube inspections to be conducted during the upcoming Prairie Island Nuclear GeneratingPlant, Unit 2 refueling outage. This phone call is scheduled to occur towards the end of the planned SG tube inspection interval, but before the unit completes the inspections and repairs.The staff plans to document a brief summary of the conference call as well as any material thatis provided in support of the call.1.Discuss any trends in the amount of primary-to-secondary leakage observed during therecently completed cycle.2.Discuss whether any secondary side pressure tests were performed during the outageand the associated results.3.Discuss any exceptions taken to the industry guidelines.
4.For each SG, provide a description of the inspections performed including the areasexamined and the probes used (e.g., dents/dings, sleeves, expansion-transition, U-bends with a rotating probe), the scope of the inspection (e.g., 100 percent of dents/dings greater than 5 volts and a 20 percent sample between two and five volts),
and the expansion criteria.5.For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide asummary of the number of indications identified to-date of each degradation mode (e.g.,
number of circumferential primary water stress corrosion cracking indications at the expansion transition). For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., provide the voltage, depth, and length of the indication). In particular, address whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle. In addition, discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this unit (e.g., observed circumferential primary water stress corrosion cracking at the expansion transition for the first time at this unit).6.Describe repair/plugging plans.
7.Describe in-situ pressure test and tube pull plans and results (as applicable and ifavailable).8.Provide the schedule for steam generator-related activities during the remainder of thecurrent outage. 9.Discuss the following regarding loose parts:*what inspections are performed to detect loose parts*a description of any loose parts detected and their location within the SG
- if the loose parts were removed from the SG
- indications of tube damage associated with the loose parts
- the source or nature of the loose parts if known10.Discuss the results of any secondary side inspections.
11.Discuss any unexpected or unusual results.
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 54016November 2005