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MONTHYEARL-PI-22-004, L-PI-22-004 Prairie Island Nuclear Generating Plant, Unit 2, 10 CFR 50.55a Request No. RR-08, Request for Alternative to ISTC 3630(f)2022-02-0808 February 2022 L-PI-22-004 Prairie Island Nuclear Generating Plant, Unit 2, 10 CFR 50.55a Request No. RR-08, Request for Alternative to ISTC 3630(f) ML20111A2412020-05-28028 May 2020 Enclosure 2: PI Tribal List POCs and Addresses ML20118C3552020-04-24024 April 2020 PIIC Enrolled Tribal Members 2019 ML17067A5032017-04-0707 April 2017 Prairie Island'S Record of Review of Internal Events and Fire PRA for NFPA 805 SE Section 3.4 ML16285A3342016-10-12012 October 2016 ROP PI Frequently Asked Questions (Faqs): 15-02 ML16285A3302016-10-12012 October 2016 ROP PI Frequently Asked Questions (Faqs): 14-08 ML15182A0332015-06-16016 June 2015 Enclosure 3 - Reactor Oversight Process Task Force FAQ Log- June 17, 2015 ML15035A3842015-02-0404 February 2015 2-4-15 Prairie Island Notice of Change of Party Info ML15014A1602015-01-14014 January 2015 Attachment 2 - NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML15014A1532015-01-14014 January 2015 Attachment 1- NEI Comments on NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML14345A6392014-12-11011 December 2014 Response to a Request for Additional Information for Proposed Revision to NSPM QATR ML14357A2752014-12-0505 December 2014 Enclosure 3, Prairie Island Nuclear Generating Plant Unit 2 Piping and Instrumentation Diagrams ML14363A5142014-12-0101 December 2014 Underlying Decisions from Which Petition Arises ML14247A0432014-08-28028 August 2014 Answers to Steam Generator Replacement Questions and Email Reply to Public Availability Question Regarding the PI ISFSI License Renewal L-PI-14-020, Enclosure 3 - Prairie Island Nuclear Generating Plant, Unit 2 - NTTF Recommendation 2.3 - Seismic Updated Seismic Walkdown Report (Redacted)2014-03-0404 March 2014 Enclosure 3 - Prairie Island Nuclear Generating Plant, Unit 2 - NTTF Recommendation 2.3 - Seismic Updated Seismic Walkdown Report (Redacted) ML13101A0432013-04-12012 April 2013 Final Site Visit Summary for Prairie Island ISFSI ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1120701752011-07-22022 July 2011 Response to Request for Additional Information Related to Decommissioning Funding Status Reports, Enclosure 1 ML1120701842011-07-18018 July 2011 2010 Taxes Paid, Enclosure 4 ML1021002312010-07-21021 July 2010 Response to Question 20c ML1021002102010-07-16016 July 2010 Response to Question 6 ML1021002522010-07-16016 July 2010 Turbine Building Licensing Bases for PINGP TB Flooding ML1021002352010-07-16016 July 2010 Response to Question 23 ML1021002322010-07-16016 July 2010 Response to Question 22 ML1021002172010-07-16016 July 2010 Response to Question 14 ML1021002152010-07-16016 July 2010 Response to Question 13 ML1021002092010-07-15015 July 2010 Response to Question 5.b ML1021002132010-07-15015 July 2010 Response to Question 12 ML1021002192010-07-15015 July 2010 Response to Question 19 ML1017301232010-06-0909 June 2010 Green Ticket Tritium Releases ML1008406392010-01-31031 January 2010 Attached to E-mail from Kristen Eide Tollefson for the PINGP Study Group, Outline of Modernizing NEPA Implementation, Adaptive Management and Monitoring from NEPA Task Force. Submitted with Comments on Draft Generic Environmental Impact Sta ML0933507512010-01-14014 January 2010 Temporary Instruction 2515/180, Managing Fatigue ML1001206272009-09-0101 September 2009 Inspection Report Regarding Steam Generator Tube 2008 Responses ML0922405592009-08-11011 August 2009 8/11/09 Prairie Island Request for Information ML0907210882009-03-12012 March 2009 Enclosure 1, Non-Proprietary Responses to Requests for Additional Information License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 422V+ Fuel ML0834500212008-12-10010 December 2008 PINGP License Renewal - 2008 Minnesota Statute 216H: Greenhouse Gas Emissions ML0834000622008-12-0505 December 2008 PINGP License Renewal - Environmental Monitoring for Nuclear Plants by Wisconsin Department of Health Services. 2008 ML0834001062008-12-0505 December 2008 PINGP License Renewal - Minnesota Rule 7001. Reference 2008 ML0834001332008-12-0505 December 2008 PINGP License Renewal: Minnesota Rule 7045 Hazardous Waste. Refer.2008b ML0904001762008-12-0505 December 2008 PINGP Lr - Minnesota Administrative Rule, Chapter 7035: Solid Waste. 2008a ML0834003672008-12-0505 December 2008 PINGP License Renewal: Daily Average and Annual Total Vehicle Miles. 2007. Refer. Mndot 2008 ML0834001382008-12-0404 December 2008 PINGP License Renewal: Minn. Rule 7046. Refer. 2008c ML0833803642008-12-0303 December 2008 PINGP - NOAA National Climatic Data Center, Tornado in Minnesota May 9, 2001. 2008h ML0833803222008-12-0303 December 2008 PINGP - NOAA National Climatic Data Center, Climate of Minnesota. 2008d ML0833803052008-12-0303 December 2008 PINGP - NOAA North Central River Forecast Center Climate and Topography. 2008c ML0833802802008-12-0303 December 2008 PINGP - Minnesota Pollution Control Agency, Air Quality Division. 2008a ML0834000442008-11-19019 November 2008 PINGP License Renewal: Reports Prairie Island Independent Spent Fuel Storage Installation. 2007-2008. Reference 2008 ML0832203652008-09-22022 September 2008 Scoping Comments from Communities United for Responsible Energy ML0833802922008-09-16016 September 2008 PINGP - Ambient Station Information: Stanton Air Field. Minnesota Pollution Control Agency. 2008b ML0834702812008-05-0909 May 2008 PINGP - License Renewal: PM (Particulate Matter) Health Effects 2022-02-08
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2008 Unit 2 Steam Generator Tube Inspection Report An August 21, 2009 Nuclear Regulatory Commission (NRC) email asked four questions with respect to the 2008 Unit 2 steam generator (SG) tube inspection report, which was submitted on April 27, 2009 (ADAMS Accession No. ML091180466):
NRC question 1.) Confirm that no crack-like indications were left in service except for those that would have been permitted to be left in service with the F*
repair criteria.
Northern States Power company, a Minnesota corporation (NSPM) response: NSPM confirms no crack like indications detected were left inservice except those permitted to be left in service by the F* and/or EF* alternate repair criteria.
NRC question 2.) Confirm that the only crack-like indications detected were either located in the tubesheet crevice or the sludge pile at the top of the tubesheet.
NSPM response: NSPM confirms that all the crack like indications detected were located either completely within the tubesheet or in the case of three tubes (SG21 R21 C30, SG22 R12 C31 and SG22 R17 C74) a portion of the crack length mathematically appears to extend above the top of the tubesheet into the freespan sludge accumulation zone of the tube. A review of the raw data on the three suspect tubes indicates the entire crack length to be completely within the tubesheet crevice (entirely below the top of the tubesheet). NSPMs practice is to report cracks in the tubesheet crevice from the TRH, 1BH, 2BH or EBH landmark location and to report cracks located above the tubesheet from the TSH landmark location (see Figure 1 and the Legend of Fields and Codes in the subject report).
NRC question 3.) Confirm that no degradation was observed during the inspections of the upper internals of the steam generators.
NSPM response: The upper internals of 22 Steam Generator were inspected as described in Table 1, footnote 3, of our submittal. NSPM confirms no degradation was observed on any of these components.
- 4. Confirm that no wear was attributed to loose parts. In addition, confirm that if any loose parts were left in the steam generators, an evaluation was performed and that it confirmed the acceptability of leaving the parts in service.
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NSPM SG RAI responses NSPM response: NSPM confirms that two tubes in SG21 (R8 C59 and R9 C59) were left in service with legacy loose part wear. These two tubes were previously subject to an NRC staff request for additional information (NRC Question 2) on the 2006 Unit 2 steam generator tube inspection report which was dispositioned in responses dated February 21, 2008 (ADAMS Accession No. ML080520187). No additional wear attributed to loose parts was detected or left in service. A secondary side inspection was performed on all potential loose parts (PLP) identified by the tubing inspection.
The items observed by this secondary inspection were evaluated based on size, shape, potential to wear adjacent tubes, and potential damage that could result from removal of the item, and were acceptable for leaving service.
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