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Category:Report
MONTHYEARML23073A3982023-03-31031 March 2023 TMI-2 ISFSI Biennial Update Report for 2023 TMI-23-005, Updated Spent Fuel Management Plan2023-03-21021 March 2023 Updated Spent Fuel Management Plan ML22335A4632022-12-0101 December 2022 Chronology of Significant Events in Operator Licensing Since the Three Mile Island Accident (1979) ML22101A0792022-03-23023 March 2022 TMI2-EN-RPT-0001, Revision 1, Determination of the Safe Fuel Mass Limit for Decommissioning TMI-22-008, 2021 Aircraft Movement Data Annual Report for TMI-12022-02-28028 February 2022 2021 Aircraft Movement Data Annual Report for TMI-1 ML22105A0932021-12-16016 December 2021 Attachment 3 - RSCS Technical Support Document (Tsd) No. 21-078 Rev 00 TMI-2 Source Term Limitations and Administrative Controls to Prevent Exceeding the 1 Rem EPA PAG ML21236A2882021-08-10010 August 2021 TMI-2 Pdms SAR Update 14 & QA Plan (Rev 18 & 19) Biennial Submittal 08-10-21 ML21133A2642021-05-0505 May 2021 Supplemental Information to License Amendment Request Decommissioning Technical Specifications ML21084A2292021-03-17017 March 2021 Notification of Amended Post-Shutdown Decommissioning Activities Report Accordance with 10 CFR 50.82(a)(7), Revision 4 ML21085A6922021-03-15015 March 2021 Plan for Management of Debris Material ML21056A0052021-02-25025 February 2021 2020 Aircraft Movement Data Annual Report ML21133A2652021-02-0101 February 2021 Calculation TMI2-EN-RPT-0002, Revision 0, MCNP Version 6.2 Bias Determination for Low Enrichment Uranium Using the ENDF/B-VIII.0 Cross Section Library ML18107A2152018-04-10010 April 2018 Biennial 10 CFR 50.59 and Commitment Revision Reports for 2016 and 2017 ML17289A0532017-10-15015 October 2017 Case Study Overview ML17165A4092017-06-14014 June 2017 T1R22 Refuel Outage MRP-227-A Reactor Internals Scope Deferral Review RS-16-087, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-06-29029 June 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-16-104, Mitigating Strategies Flood Hazard Assessment Submittal2016-06-29029 June 2016 Mitigating Strategies Flood Hazard Assessment Submittal ML15306A5032015-12-17017 December 2015 Closure Evaluation for Report Pursuant to 10 CFR 50.46 Requirements Related to Thermal Conductivity Degradation ML15223A2152015-08-14014 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the NTTF Review of Insights TMI-15-076, Submittal of TMI White Paper-TMI Bwst Cleanup Path Issue2015-06-22022 June 2015 Submittal of TMI White Paper-TMI Bwst Cleanup Path Issue ML15043A1442015-02-13013 February 2015 Review of Steam Generator Tube Inspection Report for Fall 2013 Outage ML14297A4112014-12-19019 December 2014 Letter and Non-Proprietary Safety Evaluation of Reactor Vessel Internals Inspection Plan RS-14-301, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.2014-12-17017 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14163A0242014-06-10010 June 2014 Response to Request for Additional Information - Review of the Cycle 20 Core Operating Limits Report ML14189A2852014-04-30030 April 2014 Topical Report 213, 40th Year Reactor Building Tendon Surveillance (Period 10), (Rev 0) ML14189A2862014-04-17017 April 2014 Final Report for the 40th Year (10th Period) Tendon Surveillance at Three Mile Island, Unit 1 TMI-14-053, Biennial 10 CFR 50.59 and Commitment Revision Report for 2012 and 20132014-04-16016 April 2014 Biennial 10 CFR 50.59 and Commitment Revision Report for 2012 and 2013 RS-14-032, Report RS-14-032, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal 1 (Annex a) for the Three Mile Island Nuclear Station, Uni2014-02-28028 February 2014 Report RS-14-032, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for the Three Mile Island Nuclear Station, Unit ML13225A5522013-12-17017 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13338A6712013-12-0909 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Three Mile Island, Unit 1, TAC MF0803 ML14189A2872013-11-12012 November 2013 TMI 40TH Year Tendon Surveillance, Tendon No. 1-146-34, Tendon End Buddress 4 TMI-14-061, 40th Year Tendon Surveillance Engineering Report (Topical Report 213), Precision Surveillance Corporation in-Service Inspection Quality Control Procedure, Monitoring Tendon Force (Lift-Offs)2013-09-0303 September 2013 40th Year Tendon Surveillance Engineering Report (Topical Report 213), Precision Surveillance Corporation in-Service Inspection Quality Control Procedure, Monitoring Tendon Force (Lift-Offs) TMI-13-107, Attachment 1 - Areva Document No. ANP-3102Q1, Response to NRC Ria Regarding License Amendment Request to Update Pressure -Temperature Limit Curves for Three-Mile Island Unit 1, Revision 0, Dated August 20132013-08-31031 August 2013 Attachment 1 - Areva Document No. ANP-3102Q1, Response to NRC Ria Regarding License Amendment Request to Update Pressure -Temperature Limit Curves for Three-Mile Island Unit 1, Revision 0, Dated August 2013 ML13232A2172013-07-31031 July 2013 Attachment 2 - Areva Document No. ANP-3102, Revision 3,Three-Mile Island Unit 1 Appendix G Pressure-Temperature Limits at 50.2 EFPY with Mur, Revision 3, Dated July 2013 TMI-13-041, Post-Shutdown Decommissioning Activities Report Submittal2013-06-28028 June 2013 Post-Shutdown Decommissioning Activities Report Submittal TMI-12-148, Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-022013-05-16016 May 2013 Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02 IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML12362A0422012-11-0707 November 2012 Report No. 12Q0108.70-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Three Mile Island Unit 1, Page C-1 Through Page C-161 2023-03-31
[Table view] Category:Miscellaneous
MONTHYEARTMI-23-005, Updated Spent Fuel Management Plan2023-03-21021 March 2023 Updated Spent Fuel Management Plan ML22335A4632022-12-0101 December 2022 Chronology of Significant Events in Operator Licensing Since the Three Mile Island Accident (1979) TMI-22-008, 2021 Aircraft Movement Data Annual Report for TMI-12022-02-28028 February 2022 2021 Aircraft Movement Data Annual Report for TMI-1 ML21085A6922021-03-15015 March 2021 Plan for Management of Debris Material ML21056A0052021-02-25025 February 2021 2020 Aircraft Movement Data Annual Report ML18107A2152018-04-10010 April 2018 Biennial 10 CFR 50.59 and Commitment Revision Reports for 2016 and 2017 ML17289A0532017-10-15015 October 2017 Case Study Overview ML17165A4092017-06-14014 June 2017 T1R22 Refuel Outage MRP-227-A Reactor Internals Scope Deferral Review RS-16-104, Mitigating Strategies Flood Hazard Assessment Submittal2016-06-29029 June 2016 Mitigating Strategies Flood Hazard Assessment Submittal ML15306A5032015-12-17017 December 2015 Closure Evaluation for Report Pursuant to 10 CFR 50.46 Requirements Related to Thermal Conductivity Degradation ML15223A2152015-08-14014 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the NTTF Review of Insights TMI-15-076, Submittal of TMI White Paper-TMI Bwst Cleanup Path Issue2015-06-22022 June 2015 Submittal of TMI White Paper-TMI Bwst Cleanup Path Issue ML15043A1442015-02-13013 February 2015 Review of Steam Generator Tube Inspection Report for Fall 2013 Outage ML14297A4112014-12-19019 December 2014 Letter and Non-Proprietary Safety Evaluation of Reactor Vessel Internals Inspection Plan RS-14-301, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.2014-12-17017 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. ML14163A0242014-06-10010 June 2014 Response to Request for Additional Information - Review of the Cycle 20 Core Operating Limits Report TMI-14-053, Biennial 10 CFR 50.59 and Commitment Revision Report for 2012 and 20132014-04-16016 April 2014 Biennial 10 CFR 50.59 and Commitment Revision Report for 2012 and 2013 TMI-13-041, Post-Shutdown Decommissioning Activities Report Submittal2013-06-28028 June 2013 Post-Shutdown Decommissioning Activities Report Submittal TMI-12-148, Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-022013-05-16016 May 2013 Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02 IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML12178A2152012-08-0202 August 2012 Closeout of Bulletin 2011-01 Migrating Strategies. E910-11-007, Gpu Nuclear, TMI 2 Defueling Completion Report2011-04-11011 April 2011 Gpu Nuclear, TMI 2 Defueling Completion Report ML1023505272010-08-18018 August 2010 Buried Piping - Inspecting Something You Can'T See TMI-10-029, Biennial 10 CFR 50.59 and Commitment Revision Reports for 2008 and 20092010-04-15015 April 2010 Biennial 10 CFR 50.59 and Commitment Revision Reports for 2008 and 2009 ML0828804502008-10-14014 October 2008 2008 PA Fishing Summary - Summary of Fishing Regulations and Laws ML0824101022008-06-12012 June 2008 Report of Tornadoes in Dauphin County, PA Between 01/01/1950 and 05/31/2008, NCDC ML0815801742008-05-30030 May 2008 License Renewal Environmental Impact Statement ML0824100852008-05-0101 May 2008 Comprehensive Plan for the Water Resources of the Susquehanna River Basin, Draft ML0819807102008-04-0303 April 2008 C2-WHC 2005 - Site Assessment and Wildlife Management Opportunities Report for Exelon Corporation'S Three Mile Island Generating Station. October ML0830502322008-03-11011 March 2008 Pjm 2007 State of the Market Report ML0816106632008-02-14014 February 2008 Biennial 10 CFR 50.59 and Pdms SAR Report for Years 2006 & 2007 ML0612100392006-04-19019 April 2006 Biennial 10 CFR 50.59 and Commitment Revision Report for 2004 and 2005 ML0505301682005-02-17017 February 2005 Background Discussion Material for February 24-25, 2005 NRC Meeting Relating to Replacement for BAW-2374, Revision 1, Evaluation of OTSG Thermal Loads During Hot Leg Loca. ML0309006042003-03-19019 March 2003 Additional Information Regarding Notice of Proposed Amendments to Trust Agreement to Implement Assignment of Decommissioning Trust Funds for Amergen Energy Company, LLC ML0303506252003-01-23023 January 2003 Request for NRC Written Consent to Proposed Amendments to Trust Agreement to Implement Assignment of Decommissioning Trust Funds for Amergen Energy Company, LLC ML0231803602002-11-0404 November 2002 (TMI-1) Emergency Notification System Warning Sirens ML0224802942002-08-28028 August 2002 Fitness-for-Duty Program Performance Data (FFD) for the Period - January 2002 Through June 2002 ML0224901882002-08-27027 August 2002 Fire Hazards Analysis Report (Fhar), Rev 20, Appendix R Evaluation Report, Cables & Components in Fire Area/Zone, Volume II, Attachment 3-7 ML0224901792002-08-27027 August 2002 Fire Hazards Analysis Report (Fhar), Rev 20, Appendix R Evaluation Report, Component Availability for a Fire in Fire Area/Zone, Volume II, Attachments 3-51 - 3-61 2023-03-21
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Buried Pipmg -Inspeeting Something You Can't See By Jeremy Bowen, NRR/DIRS/IRIB Buried piping is subject to significant degradation from various corrosion mechanisms.
Several critical piping systems contain sections of buried piping. As piping ages, coatings deteriorate, and exposed pipe corrodes, piping failure, such as leaks, and possibly rupture, may occur and adversely impact plant operations.
Recent Events.4' June 2009. Elevated levels of tritium were found at Dresden during routine sampling of onsite V V %4-monitoring locations.
The suspected source is an Example of a leaking pipe (non-nuci active leak in underground piping associated with the condensate storage tank (CST). In 2004 and 2006, other underground piping associated with the CST leaked and was replaced (PNO-llI-09-004).
May 2009. While performing the procedure for groundwater monitoring at a well I near the diesel generator building at Hatch, the sampling technician noted a strong diesel/fuel oil odor in the groundwater.
Also, the groundwater had a reddish tint, indicative of the red dye used to identify off-road diesel (EN45055).
Apr. 2009. Oyster Creek reported a leaking condensate pump resulting in a potential tritium release (EN44993).
Feb. 2009. Indian Point declared its CST inoperable due to a leak in the buried return line piping (NRC's response to a U.S. Congressman's inquiry and New York Times Article)l Jul. 2008. At Tricastin Industrial Complex in France, rupture of a buried pipe containing uranium liquid discharges occurred at a fuel manufacturing plant (OpE COMM).Feb. 20081 NRC conducted a special inspection of the degraded essential service ASME code requirements for buried pipinp_: water piping at Byron (IR 2007009).Mar. 2006. Byron reported elevated tritium IWA-5240 VISUAL EXAMINATION IWA-5244 BURIED COMPONENTS levels near buried piping (EN42457). (a) For buried components surrounded by an annulus, Dec_2005.
Braidwood reported elevated the VT-2 visual examination shall consist of an -tritium levels near buried piping (EN42184).
examination for evidence of leakage at each end Oct. 2005. Catawba reported an oil spill due of the annulus and at low point drains.to a break in a buried pipe (EN42042). (b) For buried components where a VT-2 visual examination cannot be performed, the May 2004. Surry declared the auxiliary examination requirement is satisfied by the feedwater system inoperable due to an following:
underground leak (EN 40771). (1) The system pressure test for buried What are Some Current Practices?
For buried service water pipe, the licensee typically relies on a quarterly pressure-drop test or system flow test (see italics in box at right) to meet the code requirement.
With flows ranging from 5000 to 10000 gpm in header piping, a very large leak is required to components that are isolable by means of valves shall consist of a test that determines the rate of pressure loss.Alternatively, the test may determine the) change inflow between the ends of the buried components.
The acceptable rate of pressure loss or flow shall beestablished by the Owner.(2) The system pressure test for nonisolable buried components shall consist of a test to confirm tht flow& during operation is not impaired.06-04ENAU9Nt Fg ERNAL UýSON1 see a significant change. A gross-pipe leakage failure would more likely be discovered by water welling up from leaking buried pipe, vice the Code test.Most licensees are voluntarily implementing non-destructive examination (NDE) as part of their raw water program. Specifically, they use torsional guided wave (ultrasonic testing) techniques.
Many sites also have a cathodic protection system or another protection and detection system for buried pipe. Most carbon steel piping and tanks have a protective coating applied during installation and are further protected by a cathodic system. Degradation of the coatings would result in additional current from the cathodic protection system. Assessment of the coating and cathodic systems is conducted on an annual basis. Non-carbon steel pipes may also be coated, but they usually do not have a cathodic protection system. Periodic inspections are performed when components are excavated for maintenance or any other reason. For plants receiving a renewal license, it is expected that an opportunistic inspection of buried pipe will occur within 10 years prior to the period of extended operation and again in the 10 years after starting extended operation; otherwise, -a-deliberate buried pipe inspection is usually required to be performed.
How Can an NRC Inspector Review a Buried Piping Issue?Most buried piping inspection samples are typically selected as a followup to an actual piping failure, a known degradation, or a problem identified during a review of a condition report. Only after a licensee has a failure in buried safety related piping can they be cited against 10 CFR Part 50, Appendix B, criteria V or IX, for having an inadequate inspection program. If the failure is large enough to create a functional failure, they could also be cited against the maintenance rule (10 CFR 50.65). This current stance of the inspection program is due to the relatively low safety significance associated with most buried piping. However, if an inspector decides to pursue the issue, here are some options: " Observe a licensee's periodic flow or pressure test of underground pipes, the video or results of a video or camera inspection of underground piping, results of a sound detection system used to detect leaks in underground piping, or the periodic maintenance conducted on a cathodic protection system (or similar system) used to protect underground piping and detect any potential leaks. These reviews can be captured under IP 71111.19 or IP 71111.22.* If a licensee excavates underground piping for the purpose of repair and replacement, use this opportunity for direct visual inspection of the piping. It can be reviewed under IP 71111.17 or IP 71111.19 (to cover the post maintenace system pressure test)." When'a licensee implements corrective actions due to suspected underground piping leaks (as potentially identified by tritium issues, tank inventory loss, chemical loss, excessive running of pumps on fire protection piping or other "keep pressure" systems, a sink hole, etc.), review the licensee's actions under IP 71152 or IP 71111.15." Review a licensee's activities associated with buried piping during an inservice inspection as one of the sample requirements in IP 71111.08, which requires a review of two or three types of NDE activities.
JFOINTE AL QY 4 A.
FPWRNE .,LýOýLY* Use IP 71002 during a license renewal inspection, which reviews passive, long lived structures, systems and components, inculding piping.References" Generic Letter 89-08, "Erosion/Corrosion-Induced Pipe Wall Thinning"" Generic Letter 89-13, "Service Water System Problems Affecting Safety-Related Equipment"" Generic Letter 9005, "Guidance for PerformingTemporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping"* IP 49001, "Inspection of Erosion-Corrosion/Flow-Accelerated-Corrosion Monitoring Programs"* IMC 9900, STSOPD, "Operability Determinations and Functionality Assessments for Resolution of Degraded or Non-Conforming Conditions Adverse to Quality or Safety" (Section C. 10)" NUREG -1801, "Generic Aging Lessons Learned (GALL) Report"* NUREG/CR-6876, "Risk-Informed Assessment of Degraded Buried Piping Systems in Nuclear Power"" Information Notice 2007-06, "Potential Common Cause Failures in Essential Service Water Systems"" Information Notice 2006-13, "Groundwater Contamination due to Undetected Leakage of Radioactive Water"* SER 7-06, "Degradation of Essential Service Water Piping"* Buried Pipe Design, Moser, A.P., McGraw Hill, 2 nd Edition, 2001." Previous ROP inspection findings related to underground piping issues Never forget why we do what we do and to the best of our ability!_RI ERNALU NLY 5 S 2 SBO DGs Out at Same Time: Ineffective Risk Management by Jim McGhee, Senior Resident Inspector, Quad Cities Nuclear Power Station, RIII Background.
On August 12, 2008, the Quad Cities' staff began planned maintenance to install a new governor on the Unit 1 Station Blackout (SBO) diesel generator (DG). This modification made the Unit 1 SBO DG inoperable and unavailable.
The resident inspector performed a maintenance risk sample for the work day in accordance with IP 71111.13, "Maintenance Risk Assessments and Emergency Work Control." This activity was selected for configuration verification due to recent changes to the licenseerisk evaluation software that credited both of the SBO DGs for loss of electrical power events and other risk significant equipment that was out of service at the time the diesel work was being performed.
The problem. On August 13, while performing a.walkdown of the redundant Unit 2 SBO DG, the resident inspector saw that the engine governor sight glass had no Sigt glss" visible oil. The inspector immediately reported the condition to the work control center, and operators verified that the oil level was not visible. The oil had leaked out through a loose fitting at the bottom of the governor oil reservoir and collected into a well formed by engine supports beneath the governor; oil leakage was not readily J visible from the floor. The fitting was found to be only finger-tight.
The Unit 2 SBO DG was declared inoperable and made unavailable at 11:10 a.m. Using their Probable Risk Assessment model, the plant staff determined on-line risk to have changed from Green to Yellow. Quad Cities' risk management actions for this configuration required protection of high pressure steam driven injection sources (high pressure coolant injection and reactor core isolation cooling systems).
Mechanical maintenance staff then tightened the fitting and refilled the governor oil sump (approximately 16, oz. of oil in a 47 oz. sump)_The Unit 2 SBO DG was made available at 1:00 p.m., and the licensee returned to a Green-risk condition.
In addition, the licensee initiated an extent of condition inspection for the safety-related diesels.* Oil levels on all safety-related diesel governors were found to be acceptable.
Investigation.
The SBO diesel modification installed a new governor to replace the existing obsolete governor that did not have an oil level sight glass. Followup investigation revealed that this modification had recently been completed on the Unit 2 SBO DG and technicians did not follow work instructions to correctly tighten the fitting, resulting in a slow leak. Further investigation revealed that, as part of this modification, a change was initiated to operator rounds to check the governor oil level; but the procedure was scheduled to be completed on August 29, 2008-three months after the physical modification was completed.
No interim equipment checks were put in place, and operators had apparently not checked the oil level sight glass on 4 the SBO DG governor since the modification was completed.
A check of the operator rounds for FRIN TE 6