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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML24288A0112024-10-14014 October 2024 L-PI-24-048 Prairie Island Nuclear Generating Plant (PINGP) Unit 1 Inservice Testing Proposed Alternative RR-10 ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24042A0012024-02-11011 February 2024 L-PI-24-008 Prairie Island Nuclear Generating Plant (PINGP) Unit 2 Inservice Testing Proposed Alternative RR-09 L-PI-23-027, Revision to 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2023-10-0303 October 2023 Revision to 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals ML23062A5112023-03-0303 March 2023 Refueling Outage Unit 1 R33 Owners Activity Report for Class 1. 2, 3 and Mc Inservice Inspections L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report2022-12-21021 December 2022 Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report ML20009F3312020-01-0909 January 2020 Refueling Outage Unit 2 R31 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations ML19108A2912019-04-18018 April 2019 Submittal of 2018 Unit 1 180-Day Steam Generator Tube Inspection Report ML19018A2042019-01-18018 January 2019 Inservice Inspection Summary Report Unit 1, Interval 5, Period 2, Outage 1 Refueling Outage Dates: 9/21/2018 to 10/26/2018 L-PI-18-003, Inservice Inspection Summary Report Unit 2, Refueling Outage Dates: 10/13/2017 to 11/20/2017, Fuel Cycle 29: 12/07/2015 to 11/20/20172018-02-12012 February 2018 Inservice Inspection Summary Report Unit 2, Refueling Outage Dates: 10/13/2017 to 11/20/2017, Fuel Cycle 29: 12/07/2015 to 11/20/2017 ML17046A6592017-02-15015 February 2017 Lnservice Inspection Summary Report Unit 1, Interval 5, Period 1, Outage 1, Refueling Outage Dates: 10/15/2016 to 11/20/2016, Fuel Cycle 29: 11/23/2014 to 11/20/2016 L-PI-16-030, Transmittal of 2015 180-Day Steam Generator Tube Inspection Report2016-05-20020 May 2016 Transmittal of 2015 180-Day Steam Generator Tube Inspection Report L-PI-16-013, Inservice Inspection Summary Report Refueling Outage Dates: 10/17/2015 to 12/06/2015, Fuel Cycle 28: 01/05/2014 to 12/06/20152016-03-0202 March 2016 Inservice Inspection Summary Report Refueling Outage Dates: 10/17/2015 to 12/06/2015, Fuel Cycle 28: 01/05/2014 to 12/06/2015 L-PI-15-025, Inservice Inspection Summary Report Unit 1, Interval 4, Period 3, Outage 2 - Refueling Outage Dates: 10/08/2014 to 11/22/2014, Fuel Cycle 28: 01/03/2013 to 11/22/20142015-02-18018 February 2015 Inservice Inspection Summary Report Unit 1, Interval 4, Period 3, Outage 2 - Refueling Outage Dates: 10/08/2014 to 11/22/2014, Fuel Cycle 28: 01/03/2013 to 11/22/2014 L-PI-15-016, Supplement to 10 CFR 50.55a Requests (RR) 1-RR-4-9 and 2-RR-4-9 (TACs MF4795 and MF4796) Associated with Prairie Island Nuclear Generating Plant (PINGP) Fourth Ten-Year Interval Inservice Inspection (ISI) Program2015-02-0404 February 2015 Supplement to 10 CFR 50.55a Requests (RR) 1-RR-4-9 and 2-RR-4-9 (TACs MF4795 and MF4796) Associated with Prairie Island Nuclear Generating Plant (PINGP) Fourth Ten-Year Interval Inservice Inspection (ISI) Program L-PI-15-013, Supplement to 10 CFR 50.55a Requests (RR) 1-RR-5-5 and 2-RR-5-5 (TACs MF4839 and MF4840) Associated with Prairie Island Nuclear Generating Plant (PINGP) Fifth Ten-Year Interval Inservice Inspection (ISI) Program2015-02-0404 February 2015 Supplement to 10 CFR 50.55a Requests (RR) 1-RR-5-5 and 2-RR-5-5 (TACs MF4839 and MF4840) Associated with Prairie Island Nuclear Generating Plant (PINGP) Fifth Ten-Year Interval Inservice Inspection (ISI) Program L-PI-14-127, Fifth Interval Inservice Inspection Plan December 21, 2014 Through December 20, 20242014-12-18018 December 2014 Fifth Interval Inservice Inspection Plan December 21, 2014 Through December 20, 2024 L-PI-14-117, Withdrawal of 10 CFR 50.55a Request RR-01 Associated with the Fifth Ten-Year Interval for the Inservice Test Program (TAC Nos. MF3928 and Mf 3929)2014-11-24024 November 2014 Withdrawal of 10 CFR 50.55a Request RR-01 Associated with the Fifth Ten-Year Interval for the Inservice Test Program (TAC Nos. MF3928 and Mf 3929) L-PI-14-096, Supplement to 10 CFR 50.55a Requests RR-01, RR-03, RR-05, RR-06 and RR-07 Associated with the Fifth Ten-Year Interval for the Inservice Test Program2014-09-19019 September 2014 Supplement to 10 CFR 50.55a Requests RR-01, RR-03, RR-05, RR-06 and RR-07 Associated with the Fifth Ten-Year Interval for the Inservice Test Program L-PI-14-095, 10 CFR 50.55a Requests 1-RR-5-7 and 2-RR-5-7 Associated with the Fifth Ten-Year Interval for the Lnservice Inspection Program2014-09-15015 September 2014 10 CFR 50.55a Requests 1-RR-5-7 and 2-RR-5-7 Associated with the Fifth Ten-Year Interval for the Lnservice Inspection Program L-PI-14-085, 10CFR 50.55a Requests Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program2014-09-15015 September 2014 10CFR 50.55a Requests Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program L-PI-14-080, 10 CFR 50.55a Requests 1-RR-4-9, 2-RR-4-9 and 2-RR-4-10 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program2014-09-0303 September 2014 10 CFR 50.55a Requests 1-RR-4-9, 2-RR-4-9 and 2-RR-4-10 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program L-PI-14-015, 10 CFR 50.55a Requests RR-01, RR-03. RR-05, RR-06 and RR-07 Associated with the Fifth Ten-Year Interval for the Lnservice Test Program2014-04-0909 April 2014 10 CFR 50.55a Requests RR-01, RR-03. RR-05, RR-06 and RR-07 Associated with the Fifth Ten-Year Interval for the Lnservice Test Program L-PI-14-029, Lnservice Inspection Summary Report Unit 2. Interval 4, Period 3, Outage 2, Refueling Outage Dates: 09/21/2013 to 01/04/2014, Fuel Cycle 27: 05/29/2012 to 01/04/20142014-04-0303 April 2014 Lnservice Inspection Summary Report Unit 2. Interval 4, Period 3, Outage 2, Refueling Outage Dates: 09/21/2013 to 01/04/2014, Fuel Cycle 27: 05/29/2012 to 01/04/2014 L-PI-13-089, Supplement to Aging Management Program Submittals2013-10-0808 October 2013 Supplement to Aging Management Program Submittals L-PI-13-027, Inservice Inspection Summary Report, Interval 4, Period 3, Outage 1, Refueling Outage Dates: 10-23-2012 to 01-02-2013 Unit 1, Fuel Cycle 27: 06-12-2011 to 01-02-20132013-03-29029 March 2013 Inservice Inspection Summary Report, Interval 4, Period 3, Outage 1, Refueling Outage Dates: 10-23-2012 to 01-02-2013 Unit 1, Fuel Cycle 27: 06-12-2011 to 01-02-2013 L-PI-12-077, Inservice Inspection Summary Report, Interval 4, Period 3, Outage 1, Refueling Outage Dates: 02-21-2012 to 05-29-2012 U2, Fuel Cycle 26: 05-26-2010 to 05-29-20122012-08-23023 August 2012 Inservice Inspection Summary Report, Interval 4, Period 3, Outage 1, Refueling Outage Dates: 02-21-2012 to 05-29-2012 U2, Fuel Cycle 26: 05-26-2010 to 05-29-2012 L-PI-11-087, Lnservice Inspection Summary Report, Interval 4, Period 2, Outage 2 Refueling Outage Dates: 04-29-2011 to 06-11-2011 Unit 1, Fuel Cycle 26: 11-23-2009 to 06-11-20112011-09-0808 September 2011 Lnservice Inspection Summary Report, Interval 4, Period 2, Outage 2 Refueling Outage Dates: 04-29-2011 to 06-11-2011 Unit 1, Fuel Cycle 26: 11-23-2009 to 06-11-2011 L-PI-10-099, Unit 2 180-Day Steam Generator Tube Inspection Report2010-11-12012 November 2010 Unit 2 180-Day Steam Generator Tube Inspection Report L-PI-10-083, Inservice Inspection Summary Report, Interval 4, Period 2, Outage 2, Refueling Outage Dates: 04-16-2010 to 05-24-2010 Unit 2, Fuel Cycle 25: 11-02-2008 to 05-24-20102010-08-20020 August 2010 Inservice Inspection Summary Report, Interval 4, Period 2, Outage 2, Refueling Outage Dates: 04-16-2010 to 05-24-2010 Unit 2, Fuel Cycle 25: 11-02-2008 to 05-24-2010 L-PI-10-051, Revision to Inservice Inspection Summary Report, Interval 4, Period 1, Refueling Outage Dates: 04-28-2006 to 06-06-2006 Fuel Cycle 23: 11-23-2004 to 06-06-2006 and Revision to 2008 Unit 1 180-Day Steam Generator Tube Inspection Report2010-06-0101 June 2010 Revision to Inservice Inspection Summary Report, Interval 4, Period 1, Refueling Outage Dates: 04-28-2006 to 06-06-2006 Fuel Cycle 23: 11-23-2004 to 06-06-2006 and Revision to 2008 Unit 1 180-Day Steam Generator Tube Inspection Report L-PI-10-013, Inservice Inspection Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage Dates: 09-12-2009 to 11-23-2009, Unit 1, Fuel Cycle 25: 03-23-2008 to 11-23-20092010-02-22022 February 2010 Inservice Inspection Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage Dates: 09-12-2009 to 11-23-2009, Unit 1, Fuel Cycle 25: 03-23-2008 to 11-23-2009 L-PI-09-015, Submittal of Inservice Inspection Examination Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage, Dates: 09-19-2008 to 11-01-2008 Unit 2, Fuel Cycle 24:12-15-2006 to 11-01-20082009-01-28028 January 2009 Submittal of Inservice Inspection Examination Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage, Dates: 09-19-2008 to 11-01-2008 Unit 2, Fuel Cycle 24:12-15-2006 to 11-01-2008 L-PI-08-082, Amendment to Unit 2 Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2, Refueling Outage Dates: 11-15-2006 to 12-15-2006, Fuel Cycle 23: 06-11-2005 to 12-15-20062008-10-0707 October 2008 Amendment to Unit 2 Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2, Refueling Outage Dates: 11-15-2006 to 12-15-2006, Fuel Cycle 23: 06-11-2005 to 12-15-2006 L-PI-08-055, Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2 Refueling Outage Dates: 02-13-2008 to 03-23-2008, Fuel Cycle 24: 06-06-2006 to 03-23-20082008-06-19019 June 2008 Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2 Refueling Outage Dates: 02-13-2008 to 03-23-2008, Fuel Cycle 24: 06-06-2006 to 03-23-2008 ML0727800262007-10-31031 October 2007 Relief Request from ASME Code, Section X1, Inservice Inspection Program Relief Requests Nos. 1-RR-4-7 and 2-RR-4-7 L-PI-07-037, 10 CFR 50.55a Request 1-RR-4-6 for the Prairie Island, Unit 1, Fourth Ten-year Interval Inservice Inspection Program2007-05-11011 May 2007 10 CFR 50.55a Request 1-RR-4-6 for the Prairie Island, Unit 1, Fourth Ten-year Interval Inservice Inspection Program L-PI-07-023, Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2, Refueling Outage Dates: 11-15-2006 to 12-15-2006, Fuel Cycle 23: 06-11-2005 to 12-15-20062007-03-14014 March 2007 Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2, Refueling Outage Dates: 11-15-2006 to 12-15-2006, Fuel Cycle 23: 06-11-2005 to 12-15-2006 L-PI-06-102, Unit 2 Steam Generator Inspection Results - 15 Day Report2006-12-18018 December 2006 Unit 2 Steam Generator Inspection Results - 15 Day Report L-PI-06-096, CFR 50.55a Requests 1-RR-4-7 and 2-RR-4-7 for the Units 1 and 2 Fourth 10-Year Interval Inservice Inspection Program2006-12-14014 December 2006 CFR 50.55a Requests 1-RR-4-7 and 2-RR-4-7 for the Units 1 and 2 Fourth 10-Year Interval Inservice Inspection Program ML0627701952006-10-0202 October 2006 Notification of NRC Inspection and Request for Information L-PI-06-072, Inservice Inspection Summary Report, Interval 4, Period 1, Refueling Outage Dates: 04-28-2006 to 06-06-2006, Fuel Cycle 23: 11-23-2004 to 06-06-20062006-09-0101 September 2006 Inservice Inspection Summary Report, Interval 4, Period 1, Refueling Outage Dates: 04-28-2006 to 06-06-2006, Fuel Cycle 23: 11-23-2004 to 06-06-2006 L-PI-05-082, Request for Relief No. 21, for the Plant 3rd 10-Year Interval Inservice Inspection Program2005-09-0808 September 2005 Request for Relief No. 21, for the Plant 3rd 10-Year Interval Inservice Inspection Program L-PI-04-135, Inservice Inspection Summary Report, Interval 3, Period 3, Interval 4, Period 1 Refueling Outage Dates: April 16, 2005 - June 10, 2005, Fuel Cycle 22: October 11, 2003 - June 10, 20052005-09-0808 September 2005 Inservice Inspection Summary Report, Interval 3, Period 3, Interval 4, Period 1 Refueling Outage Dates: April 16, 2005 - June 10, 2005, Fuel Cycle 22: October 11, 2003 - June 10, 2005 L-PI-05-074, Response to Request for Additional Information Regarding the Unit 1 Lnservice Lnspection Summary Report, Interval 3, Period 3, Refueling Outage Dates: 9-10-2004 to 11-23-2004 Fuel Cycle 22..2005-08-22022 August 2005 Response to Request for Additional Information Regarding the Unit 1 Lnservice Lnspection Summary Report, Interval 3, Period 3, Refueling Outage Dates: 9-10-2004 to 11-23-2004 Fuel Cycle 22.. L-PI-05-012, Request for Relief No. 17, Revision 0, for the Plant 3rd 10-year Interval Inservice Inspection Program2005-02-22022 February 2005 Request for Relief No. 17, Revision 0, for the Plant 3rd 10-year Interval Inservice Inspection Program L-PI-05-013, Inservice Inspection Summary Report, Interval 3, Period 3, Refueling Outage Dates 09-10-04 Fuel Cycle 22: 12-7-2002 to 11-23-042005-02-22022 February 2005 Inservice Inspection Summary Report, Interval 3, Period 3, Refueling Outage Dates 09-10-04 Fuel Cycle 22: 12-7-2002 to 11-23-04 L-PI-05-002, 60-Day Report Pursuant to NRC Bulletin 2003-02 for 2004 Prairie Island Unit 1 Lower Head Penetration Inspection2005-01-24024 January 2005 60-Day Report Pursuant to NRC Bulletin 2003-02 for 2004 Prairie Island Unit 1 Lower Head Penetration Inspection L-PI-04-009, Inservice Inspection Summary Report, Interval 3, Period 3, Refueling Outage Dates: 9-13-2003 to 10-10-2003 Fuel Cycle 21: 3-3-2002 to 10-10-20032004-01-0707 January 2004 Inservice Inspection Summary Report, Interval 3, Period 3, Refueling Outage Dates: 9-13-2003 to 10-10-2003 Fuel Cycle 21: 3-3-2002 to 10-10-2003 L-PI-04-005, Request for Relief No. 16, Revision 0 for the Third 10-Year Interval Inservice Inspection Program2004-01-0707 January 2004 Request for Relief No. 16, Revision 0 for the Third 10-Year Interval Inservice Inspection Program 2024-05-31
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WEB-BASED PROPOSED ALTERNATIVE SUBMISSION 10 CFR 50.55a(z)(2)
Submission Date: 10/14/2024 Submitted By: Jeffrey Kivi Submission Availability: Non-Publicly Available Licensee: Northern States Power Company Plant Unit(s) and Docket No(s): Prairie Island 1 ( 05000282 )
Licensee
Contact:
Jeffrey Kivi (612) 330-5788 jeffrey.l.kivi@xcelenergy.com
Project
Title:
L-PI-24-048 Prairie Island Nuclear Generating Plant (PINGP) Unit 1 Inservice Testing Proposed Alternative RR-10
Request Type:
10 CFR 50.55a(z)(2)
Inservice Inspection (ISI) or Inservice Testing (IST)
Inservice Testing (IST)
Requested Completion Date:
November 04, 2024
Proposed Alternative Number or Identifier:
IST Fifth Interval RR-10
Brief Description of Proposed Alternative Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"),
hereby requests NRC authorization of this 10 CFR 50.55a alternative for the Prairie Island Nuclear Generating Plant (PINGP) Unit 1. The proposed alternative is to defer the quarterly and post-replacement testing of certain valves in the Auxiliary Feedwater (AFW) system until startup following the current refueling outage when plant conditions support performance of the tests.
This request makes no new commitments or changes to existing commitments.
Proposed Duration of Alternative (in terms of ISI/IST Program Interval with Start and End Dates):
The duration of this request will continue in the IST Fifth Interval until startup testing from the fall 2024 Unit 1 refueling outage is complete, which is scheduled for November 22, 2024.
Applicable ASME Code Requirements
ISTC-3310 Effects of Valve Repair, Replacement, or Maintenance on Reference Values. When a valve or its control system has been replaced, repaired, or has undergone maintenance that could affect the valve's performance, a new reference value shall be determined or the previous value reconfirmed by an inservice test run before the time it is returned to service or immediately if not removed from service. This test is to demonstrate that performance parameters that could be affected by the replacement, repair, or maintenance are within acceptable limits.
ISTC-3510 Exercising Test Frequency. Active Category A, Category B, and Category C check valves shall be exercised nominally every 3 months, except as provided by ISTC-3520, ISTC-3540, ISTC-3550, ISTC-3570, ISTC-5221, and ISTC-5222. Power-operated relief valves shall be exercise tested once per fuel cycle.
ISTC-3521 Category A and Category B Valves.
(a) full-stroke exercising of Category A and Category B valves during operation at power to the position(s) required to fulfill its function(s).
ISTC-3522 Category C Check Valves. Category C check valves shall be exercised as follows:
(a) During operation at power, each check valve shall be exercised or examined in a manner that verifies obturator travel by using the methods in ISTC-5221.
ISTC-3560 Fail-Safe Valves. Valves with fail-safe actuators shall be tested by observing the operation of the actuator upon loss of valve actuating power in accordance with the exercising frequency of ISTC-3510.
ISTC-3570, Valves in Systems Out of Service. For a valve in a system declared inoperable or not required to be operable, the exercising test schedule need not be followed. Within 3 months before placing the system in an operable status, the valves shall be exercised and the schedule followed in accordance with requirements of this Subsection.
ISTC-5131 Valve Stroke Testing.
(a) Active valves shall have their stroke times measured when exercised in accordance with ISTC-3500.
ISTC-5221 Valve Obturator Movement.
(a) The necessary valve obturator movement during exercise testing shall be demonstrated by performing both an open and a close test.
(2) Check valves that have a safety function in only the open direction shall be exercised by initiating flow and observing that the obturator has traveled either the full open position or to the position required to perform its intended function(s) (see ISTA-1100), and verify closure.
Applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPV Code),
or ASME Operation and Maintenanceof Nuclear Power Plants (OM Code), Edition and Addenda
ASME OM Code 2004, 2006 Addenda
Current ISI or IST Program Interval Number and Start/End Dates
Fifth IST Interval; started December 21, 2014, with the ten-year interval ending December 20, 2024, and a planned 12-month extension to December 20, 2025.
Applicable ASME Code Components and/or System Description
The AFW System supplies feedwater to the steam generators during normal transients, such as startups and shutdowns when the Main Feedwater System is not available. Each train can supply auxiliary feedwater to either or both steam generators as determined by the valve lineup. The capacity of the AFW System prevents the steam generators from boiling dry or the pressurizer relief and safety valves from lifting following a blackout or plant trip.
The AFW System provides three essential functions during abnormal conditions:
a.) prevents thermal cycle of the steam generator tube sheet upon loss of main feedwater pump; b.) removes residual heat from the reactor coolant system until the reactor coolant system (RCS) temperature drops below 300-350 °F and the residual heat removal (RHR) system is capable of providing the necessary heat sink; c.) maintains a head of water in the steam generator following a loss of coolant accident.
The applicable components and their function/operation are as follows:
The 11 TDAFWP Main Steam Supply Control Valve, CV-31998, is a Category B air operated valve that must reposition for the Turbine-Driven AFW Pump (TDAFWP) to start and provide design basis flow.
The 11 TDAFWP Recirculation/Lube Oil Cooling Control Valve, CV-31153, is a Category B air operated valve that must open on automatic signals to allow recirculation flow to the lube oil coolers.
The 11 TDAFWP Recirculation Lube Oil Cooling Line Check Valve, AF-28-1, and the 12 Motor-Driven Auxiliary Feedwater Pump Recirculation Lube Oil Cooling Line Check Valve, AF-28-2, are Category C check valves that must open to provide a minimum recirculation flow path to protect the associated pump from overheating during low flow conditions. AF-28-1 and AF-28-2 do not have safety functions in their closed positions. Note that the PINGP Fifth Interval IST Program IST Valve Data Sheets contain a documentation error indicating AF-28-1 and AF-28-2 have safety functions in the closed position. This error is documented in the PINGP Corrective Action Program.
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Reason for Request===
The valves subject to this request are tested per ISTC-3510 every 92 days including grace period allowed by Code Case OMN-20 as authorized by the NRC with PINGP Fifth Interval IST Program Relief Request RR-06 (References 3 and 4). The tests (last conducted July 18, 2024) will become overdue for testing on November 10, 2024 (92 days plus OMN-20 grace), during the refueling outage; however, the AFW system will be out of service at that time. These valves are normally tested at power and are not required to be tested during cold shutdowns or refueling outages.
Testing AF-28-2, CV-31153, and CV-31998 per ISTC-3570 prior to declaring the AFW system operable would result in a hardship or unusual difficulty without a compensating increase in quality and safety as described herein. Post-replacement testing of AF-28-1 per ISTC-3310 prior to declaring the AFW system operable would result in a hardship or unusual difficulty without a compensating increase in quality and safety as described herein.
Full Description of Proposed Alternative
The proposed alternative is to extend the ISTC-3310 and ISTC-3570 required test interval for the subject valves until startup testing from the fall 2024 refueling outage is complete, which is scheduled for November 22, 2024. CV-31153, CV-31998 will be tested in accordance with ISTC-3521(a), ISTC-5131(a), and ISTC-3560 after Unit 1 reaches MODE 3 and conditions that support testing using normal test procedures. AF-28-1 will be replaced in the refueling outage and will be tested in accordance with ISTC-3310 upon reaching normal plant conditions for testing after Unit 1 reaches MODE 3. AF-28-2 will be tested in accordance with ISTC-5221(a)(2) after Unit 1 reaches MODE 3.
Description of Basis for Use
As detailed below, compliance with the specified requirements of the applicable OM Code sections for the affected components prior to Unit 1 reaching MODE 3 and declaring the AFW system operable would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
NSPM reviewed maintenance and testing history of the subject valves since 2018 (3 refueling outages excluding the current Unit 1 2024 refueling outage) and found:
For CV-31998, 11 TDAFWP Main Steam Supply Control Valve, seat leakage was identified in October 2020. A valve and actuator overhaul was performed in October 2022. The valve and actuator were repaired and tested satisfactorily. All subsequent testing has been satisfactory.
For CV-31153, 11 TDAFWP Recirculation/Lube Oil Cooling Control Valve, no maintenance has been performed and all testing has been satisfactory.
The quarterly test of the 11 TDAFWP Main Steam Supply Control Valve, CV-31998, is normally performed with high pressure steam. The actuator pressure is reduced at lower steam conditions to prevent valve seat damage.
The 11 TDAFWP Recirculation/Lube Oil Cooling Control Valve, CV-31153, is interlocked to actuate in tandem with CV-31998. New test equipment or plant modifications to provide motive force to the TDAFWP would be required to perform testing of the air operated valves prior to unit startup. As a result, testing per ISTC-3570 would result in a hardship without a compensating increase in the level of quality and safety.
For check valves AF-28-1 and AF-28-2, all testing has been satisfactory since 2018. In 2023, NSPM replaced AF 2 at its regularly scheduled preventative maintenance frequency. Subsequent quarterly open and closure tests have been satisfactory.
AF-28-1 is scheduled to be replaced in 2024 during the Unit 1 refueling outage due to results of a 2012 inspection that found that the disc/spring were in good condition, but that the valve seats were degraded. Return to service testing includes open and closure tests, which cannot be performed until Unit 1 is in MODE 3 without a system modification and/or special test equipment/procedures. Returning Unit 1 to MODE 3 requires the AFW system to be operable per the PINGP Technical Specifications.
Testing of the check valves in cold shutdown prior to declaring the AFW system operable would require removal of small sections of piping to create a test connection point or utilizing a cross-tie to Unit 2 and elevating the risk of the operating unit. These test methods would result in a hardship without a compensating increase in the level of quality and safety.
Include Any Additional Information
Precedents
References
- 1. ASME OM Code 2004, 2006 Addenda
- 2. Prairie Island Nuclear Generating Plant ASME Inservice Testing Program
- 3. NSPM Letter L-PI-14-015, 10 CFR 50.55a Requests RR-01, RR-03, RR-05, RR-06 and RR-07 Associated with the Fifth Ten-Year Interval for the Inservice Test Program, dated April 9, 2014. (ADAMS Accession Number ML14099A283)
- 4. NRC Letter re: Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief Requests for Fifth 10-Year Inservice Testing Program Interval (TAC Nos. MF3928 and MF3929), dated December 5, 2014. (ADAMS Accession Number ML14329A185)
Attachments