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Category:Report
MONTHYEARML24269A0472024-10-0404 October 2024 Enclosure 2, Oyster Creek Nuclear Generating Station, License Amendment Request, License Termination Plan, Pending Request for Additional Information ML24214A0612024-08-0101 August 2024 Enclosure 15: ENG-OCS-014 Revision: 0, Basement Fill Model: Probabilistic Analysis for Embedded Pipes Scenario Oyster Creek Station, January 2024 ML24214A0372024-08-0101 August 2024 License Amendment Request to Revise Renewed Facility Operating License to Add License Condition 2.C.(18) to Include License Termination Plan Requirements ML24214A0692024-08-0101 August 2024 Enclosure 18: Technical Basis Document No. 24-01-12-2888 Revision 1, Dose Contribution from Insignificant Radionuclides in the Oyster Creek Site-Specific Suite of Radiological Nuclides, February 14, 2024 ML24214A0702024-08-0101 August 2024 Enclosure 19: Technical Basis Document, Instrument Efficiency Determination for Use in Minimum Detectable Concentration Calculations in Support of the Final Status Surveys at OCNGS Revision 0, February 14, 2024 ML24214A0782024-08-0101 August 2024 Enclosure 22: Tsd 24-055, Basement Fill Model: Probabilistic Analysis for Instantaneous Release Scenario Assuming Industrial Use Exposure Pathways, Revision 0 ML24214A0792024-07-0808 July 2024 Enclosure 23: Tsd 24-063, Basement Fill Model: Calculation of Dcglw/F Values Assuming Industrial Use Scenario Exposure Pathways, Revision 0 ML24214A0482024-03-31031 March 2024 Enclosure 6: Oyster Creek Nuclear Generating Station Below Grade Structures Radiological Characterization Report Revision 1, March 2024 ML24214A0492024-03-0606 March 2024 Enclosure 7: ENG-OCS-002 Revision 1, RESRAD-Build Input Parameter Sensitivity Analysis - Ocs, March 6, 2024 ML24214A0642024-03-0606 March 2024 Enclosure 16: ENG-OCS-015 Revision: 1, Basement Fill Model: Calculation of Embedded Pipe Dcgl Values Oyster Creek Station, March 6, 2024 ML24214A0602024-03-0606 March 2024 Enclosure 14: ENG-OCS-013 Revision: 1, Basement Fill Model: Calculation of Dcglw/F Values Assuming Industrial Use Scenario Exposure Pathways Oyster Creek Station, March 6, 2024 ML24214A0652024-02-20020 February 2024 Enclosure 17: ENG-OCS-016 Revision: 0, Calculation of Buried Pipe Dcgl Values Oyster Creek Station, February 20, 2024 ML24214A0722024-02-14014 February 2024 Enclosure 20, Oyster Creek 100 Year Land Use Outlook - Categorization and Justification, Ghd, February 9, 2024 ML24214A0582023-11-0101 November 2023 Enclosure 13: ENG-OCS-012 Revision: 0, Basement Fill Model Probabilistic Analysis for Instantaneous Release Scenario Assuming Industrial Use Exposure Pathways Oyster Creek, November 1, 2023 ML23286A1552023-10-13013 October 2023 Defueled Safety Analysis Report (DSAR) ML24214A0542023-07-26026 July 2023 Enclosure 11: ENG-OCS-008 Revision: 0, Derived Concentration Guideline Levels Values for Soil – Industrial Use Scenario Oyster Creek, July 26, 2023 ML24214A0532023-07-25025 July 2023 Enclosure 10: ENG-OCS-007 Revision 0, RESRAD-Onsite Probabilistic Analysis - Industrial Use Scenario Oyster Creek Station, July 25, 2023 ML24214A0442023-04-24024 April 2023 Enclosure 5: Oyster Creek Generating Station Radiological Characterization Report Revision 1, April 24, 2023 ML23025A0112023-01-24024 January 2023 LLRW Late Shipment Investigation Report Per 10 CFR 20, Appendix G ML24214A0752022-09-0808 September 2022 Enclosure 21: Oyster Creek Hydrogeologic Investigation Report, September 8, 2022 ML24214A0572022-08-0404 August 2022 Enclosure 12, ENG-OCS-009 Revision: 0, Area Factors for Soil – Industrial Use Scenario, August 4, 2022 ML22130A6882022-05-10010 May 2022 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G ML24214A0522022-04-14014 April 2022 Enclosure 9: ENG-OCS-006 Revision: 1, Area Factors for Use with Oyster Creek Dcgl Values for Buildings/Structures, April 14, 2022 ML24214A0512022-04-12012 April 2022 Enclosure 8: ENG-OCS-004 Revision 0, Resrad Building Surface Dcgl Values Oyster Creek, April 12, 2022 ML24214A0432022-01-17017 January 2022 Enclosure 4: Radionuclide Selection for Dcgl Development Oyster Creek Station Site Characterization Project, Revision 1, January 17, 2022 ML24214A0392021-11-30030 November 2021 Enclosure 3: Oyster Creek Station, Historical Site Assessment (Hsa) Revision 2, November 2021 ML21036A1692021-01-29029 January 2021 ISFSI Only Security Plan, Training Qualification Plan, Safeguards Contingency Plan Supplemental Information ML20153A2282020-05-29029 May 2020 Biological Opinion for Oyster Creek Shutdown and Decommissioning ML19214A0452019-08-0202 August 2019 NRC to NMFS, Revised Proposed Action for Oyster Creek Endangered Species Act Section 7 Consultation ML19029B3332019-01-29029 January 2019 Security Inspection Plan for Oyster Creek Station - 2019 RA-18-084, Secondary Containment Capability Test2018-09-14014 September 2018 Secondary Containment Capability Test ML18033B7442018-02-21021 February 2018 Staff Assessment of the Response to 10 CFR 50.54(F) Information Request Flood-Causing Mechanism Reevaluation RA-17-032, Submittal of Biennial 10 CFR 50.59 and 1 O CFR 72.48 Change Summary Reports - January 1, 2015 Through December 31, 20162017-05-16016 May 2017 Submittal of Biennial 10 CFR 50.59 and 1 O CFR 72.48 Change Summary Reports - January 1, 2015 Through December 31, 2016 ML15350A3532016-02-17017 February 2016 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 Near Term Task Force... RA-15-042, Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Reports - January 1, 2013 Through December 31, 20142015-05-26026 May 2015 Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Reports - January 1, 2013 Through December 31, 2014 ML15093A2842015-02-23023 February 2015 Enclosure 2: Flood Hazard Reevaluation Report for Oyster Creek Nuclear Generating Station, Rev. 1 RA-14-078, Secondary Containment Capability Test2014-10-24024 October 2014 Secondary Containment Capability Test 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 RA-14-068, Sea Turtle Incidental Take Report 2014-32014-08-0101 August 2014 Sea Turtle Incidental Take Report 2014-3 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14065A2322014-06-16016 June 2014 Staff Assessment of Response to Enclosure 4 of the March 12, 2012, 10 CFR 50.54(F) Information Request - Flooding Walkdowns ML14030A5132014-02-19019 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14038A1112014-02-11011 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Oyster Creek Nuclear Generating Station, TAC No.: MF0824 NEI 99-04, Oyster Creek Nuclear Generating Station, Commitment Change Summary Report - 20122013-12-23023 December 2013 Oyster Creek Nuclear Generating Station, Commitment Change Summary Report - 2012 RA-13-127, Commitment Change Summary Report - 20122013-12-23023 December 2013 Commitment Change Summary Report - 2012 RA-13-088, Sea Turtle Incidental Take Report 2013-52013-09-0909 September 2013 Sea Turtle Incidental Take Report 2013-5 RA-13-074, Sea Turtle Incidental Take Reports 2013-1 and 2013-22013-08-0909 August 2013 Sea Turtle Incidental Take Reports 2013-1 and 2013-2 ML15093A2832013-07-0303 July 2013 Enclosure 1: Local Intense Precipitation Evaluation Report for Oyster Creek, Rev. 6 RS-12-177, E Plan for Future Seismic Walkdown of Inaccessible Equipment2013-04-26026 April 2013 E Plan for Future Seismic Walkdown of Inaccessible Equipment ML13120A1862013-04-0909 April 2013 Enclosure 1, 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 for the Oyster Creek Generating Station Correspondence No. RS- 2024-08-01
[Table view] Category:Miscellaneous
MONTHYEARML23025A0112023-01-24024 January 2023 LLRW Late Shipment Investigation Report Per 10 CFR 20, Appendix G ML19029B3332019-01-29029 January 2019 Security Inspection Plan for Oyster Creek Station - 2019 ML18033B7442018-02-21021 February 2018 Staff Assessment of the Response to 10 CFR 50.54(F) Information Request Flood-Causing Mechanism Reevaluation RA-17-032, Submittal of Biennial 10 CFR 50.59 and 1 O CFR 72.48 Change Summary Reports - January 1, 2015 Through December 31, 20162017-05-16016 May 2017 Submittal of Biennial 10 CFR 50.59 and 1 O CFR 72.48 Change Summary Reports - January 1, 2015 Through December 31, 2016 ML15350A3532016-02-17017 February 2016 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 Near Term Task Force... RA-15-042, Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Reports - January 1, 2013 Through December 31, 20142015-05-26026 May 2015 Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Reports - January 1, 2013 Through December 31, 2014 RA-14-068, Sea Turtle Incidental Take Report 2014-32014-08-0101 August 2014 Sea Turtle Incidental Take Report 2014-3 ML14065A2322014-06-16016 June 2014 Staff Assessment of Response to Enclosure 4 of the March 12, 2012, 10 CFR 50.54(F) Information Request - Flooding Walkdowns NEI 99-04, Oyster Creek Nuclear Generating Station, Commitment Change Summary Report - 20122013-12-23023 December 2013 Oyster Creek Nuclear Generating Station, Commitment Change Summary Report - 2012 RA-13-127, Commitment Change Summary Report - 20122013-12-23023 December 2013 Commitment Change Summary Report - 2012 RA-13-088, Sea Turtle Incidental Take Report 2013-52013-09-0909 September 2013 Sea Turtle Incidental Take Report 2013-5 RA-13-074, Sea Turtle Incidental Take Reports 2013-1 and 2013-22013-08-0909 August 2013 Sea Turtle Incidental Take Reports 2013-1 and 2013-2 ML13098A2092013-04-0505 April 2013 2.206 Petition by New Jersey Environmental Federation (Et.Al.) for Oyster Creek Nuclear Generating Station Exelon Generation Company, LLC 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 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 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 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 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 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 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. ML12166A5042012-07-0505 July 2012 Operating Station Review of Committment Submittal for License Renewal Regarding Thermal Aging Irradiation Embrittlement of Cast Austenitic Stainless Steel ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants RA-11-031, Oyster Creek - Submittal of Commitment Change Summary Report - 20102011-08-12012 August 2011 Oyster Creek - Submittal of Commitment Change Summary Report - 2010 NEI 99-04, Oyster Creek - Submittal of Commitment Change Summary Report - 20102011-08-12012 August 2011 Oyster Creek - Submittal of Commitment Change Summary Report - 2010 RA-11-005, Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Reports - January 1, 2009 Though December 31, 20102011-06-24024 June 2011 Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Reports - January 1, 2009 Though December 31, 2010 RA-10-023, Submittal of Commitment Change Summary Report - 20092010-08-0606 August 2010 Submittal of Commitment Change Summary Report - 2009 NEI 99-04, Oyster Creek, Submittal of Commitment Change Summary Report - 20092010-08-0606 August 2010 Oyster Creek, Submittal of Commitment Change Summary Report - 2009 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1007402512009-08-0707 August 2009 AR 00916938 Report ML0934208122009-06-29029 June 2009 Root Cause Evaluation Report: Tritium Identified in Emergency Service Water (ESW) Vault ML1020203712009-06-25025 June 2009 Assignment Report #00907846 ML1007402602009-06-24024 June 2009 Issue - Statement of Confirmation ML1007402612009-06-24024 June 2009 AR 00934636 Report ML1020203682009-06-23023 June 2009 Assignment Report #009128267 ML1007402592009-06-21021 June 2009 Stable Standard-Fixed Target Hot Lab ML1007402192009-06-14014 June 2009 AR 00931098 Report ML1007402562009-06-0505 June 2009 AR 00928211 Report ML1020203672009-06-0404 June 2009 Assignment Report #00928211 ML1020203662009-06-0303 June 2009 Assignment Report #00927310 ML1007402572009-06-0101 June 2009 AR 00926251 Report ML1020203652009-05-26026 May 2009 Assignment Report #00907846 ML1007402162009-05-22022 May 2009 AR 00922841 Report ML1007402552009-05-22022 May 2009 AR 00922841 Report ML1020203302009-05-14014 May 2009 Assignment Report #00919392 2023-01-24
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Full Action Request Report Page 3 of 11 Assign #: 10 AR #: 00907846 Aff Fac: Oyster Creek Assign Type: NER *Status: COMPLETE Priority: Assigned To: NRSTY Due Date: 06/05/2009 Schedule Ref: Prim Grp: A5351NESPR Orig Due Date: 05/19/2009 Unit Condition: Sec Grp:
Assignment Details SubjectlDescription: Review For NER and submit to Reg Assurance.
Assignment Completion In Progress Nuclear Event Report (NER) Template Notes:
The purpose of an NER is to share information and Lessons Learned within Exelon Nuclear in a timely manner. Refer to LS-AA-115-1004, "Processing of NERs and NNOEs", for additional guidance.
General Guidance:
Your audience for this report is Exelon Nuclear personnel and executives.
? Keep sentences short, to the point, and do not include unnecessary detail.
? Define all acronyms the first time they are used.
? Do not use plant, system, or component designators, use noun names.
? Do not copy investigative reports without removing excess information.
? This is NOT a "20 minute, cut & paste from the IR" assignment. This is a MRC directed assignment that should clearly communicate the issue.
If you need additional Guidance, contact your Site OPEX Coordinator.
After you have filled in the information below AND documented Department Head (or designee) concurrence, Close your Action Tracking assignment AND Notify your Site OPEX Coordinator.
The Red Italic .wording is guidance on how to complete each topic, leave the Red Italic wording as a reference for those approving this document.
It will assist them in understanding what is expected and what content information you were working to satisfy. The Site OPEX Coordinator will remove the Red Italic wording. Items in BLACK are part of the standard template.
A complete, searchable folder of all NERs ever issued is available in Outlook.The path is: Outlook Public Folders/ All Public Folders/ Exelon Nuclear/ Cantera/ NON/LLIN/. In the main folder (NON/LLIN), there are individual sub-folders for each year since 1995. The current year NERs are in the main folder, "NON/LLIN."
NOTE: The message format below also meets INPO NNOE format requirements.
Nuclear Event Report (NER) Report
Subject:
Tritium Identified in Emergency Service Water (ESW) Vault
? The Subject is a brief description of the event. It will appear with" K*k%
the NER number assignedby Site/Fleet OPEX Coordinator to your message.
http://eamgenco.ceco.com/cap/servlet/ReportFullARServlet62500 6/25/2009
Full Action Request Report Page 4 of 11 It briefly describes the problem being documented;
? If this NER provides additional information on an event documented in a previously issued NER(s), the title should end with the phrase,
"(Supplement #_)."
? Do not include acronyms, system/component identification numbers, or utility or plant name in the Subject line.
Abstract:
Elevated tritium concentrations above State of New Jersey reporting levels were identified at Oyster Creek during preparation for work inside the ESW vault. The threshold for reporting groundwater tritium levels to the New Jersey Department of Environmental Protection (DEP) is 2,000 picocuries per liter (pCi/I) -based on a verbal agreement with New Jersey Department of Environmental Protection. The root cause of these leaks are attributed to the corrosion mechanism known as anodic dissolution resulting from poor application of coating that left the buried pipes susceptible to corrosion.
? In the Abstract, provide a brief summary of the event or condition being. documented to tell the reader why the following information is of interest. The abstract should include what went wrong, the consequences, and causes as appropriate. If possible, limit the abstract to four lines.
? For example, "With ACME Nuclear Power Station at 100 percent power, a reactor recirculation pump trip and automatic scram occurred during relay testing. Following the plant trip, some safety-related reactor vessel water level indications were inaccurate. The cause of the loss of bus was procedure error."
Title:
Tritium Identified in Oyster Creek Emergency Service Water (ESW) Vault
? The Title line can be the same as the "Subject Line", and is included
..beneath relquired. the As Abstract to allow for additional details to be added, if a minimum, it should match the Subject Line.
Event Date:
April 15, 2009
? For events where a problem resulted in an undesired condition in the plant, the event'date should be the date the undesired condition occurred (not the date when the originating mistake was made):
? For situations where a problem did not resultin an unintended condition, but the problem itself is being reported because of the potential for it to have caused undesired conditions, the event date should be the date the problem was created.
? For situations where an undesired condition (previously created) was discovered on a date later than when the event occurred, the event date should be the date of discovery.
Station Name/ Unit Name:
Oyster Creek Generating Station/ Unit 1 State the station name and affected unit(s).
Significance:
The urgency to identify the source of the leak led to excavation of several piping lines during a forced outage that lasted roughly 8 days.
Significant financial and personnel resources were required to restore the integrity of the piping. In the event the soil needs to be remediated, a significant cost will be incurred by the company.
A brief, general description of the event's nuclear safety significance, or impact on plant production and/or industrial safety.
Lessons Learned:
This message is submitted to communicate an onsite release of tritium at the Oyster Creek Generating Station due to leaks developing in buried pipe.
hittp://eamgenco.ceco.cori/cap/servlet/ReportFullARServlet6/529 6/25/2009-
Full Action Request Report Page 5 of 11 All Exelon sites should consider taking the following actions to prevent the occurrence of a similar situation.
- 1) Review Buried Pipe program information to ensure proper identification and classification (risk and consequence) of program related piping
- 2) Verify tritium concentrations have been determined for piping systems in the Buried Pipe program
- 3) Develop a strategic plan for inspecting/replacing direct buried pipe to mitigate the potential for the release of tritiated water to the ground or offsite This is a preliminary report, a,supplemental report will be issued upon completion of the root cause investigation.
? Provide the reason for submitting this message. If the reason for submitting the message was to communicate lessons learned to others, simply state that the following lessons were learned from this event, and list them.
? Actions other Nuclear sites should consider taking to prevent the occurrence of a similar event should be stated. For example, "PWR Stations should consider reviewing program X to determine if similar' weaknesses exist."
? For instances in which no action is expected until further investigation is completed, you should state, "This is a preliminary report, a supplemental report will~be issued upon completion of the root cause investigation."
Applicability:
Corporate and Site Buried Pipe Program and Program Owners Briefly describe the programs, processes or groups to which the message applies.
Description:
In preparation for work inside the ESW vault, water found inside the vault was pumped into drums and sampled for gamma emitters, tritium, and pH.
There were no gamma emitters identified, pH was 7.62, and tritium was measured at 102,000 pCi/l. The threshold for reporting groundwater tritium levels to the New Jersey Department of Environmental Protection (DEP),is 2,000 picocuries per liter (pCi/I) based on a verbal agreement with New Jersey Department of Environmental Protection based on the site's lab's LLD. The Environmental Protection Agency's reportable quantity per 40 CFR Part 302 is 100 Ci. The release of tritiated water was caused by leaks in the 8-inch and 10-inch carbon steel Condensate Transfer System lines, SS-4 and CS-24 respectively. The root cause of these leaks are attributed to the corrosion mechanism known as anodic dissolution resulting from poor application of coating that left the buried pipes susceptible to corrosion.
In the Description, provide necessary information to describe what happened in sufficient detail to be of use to an interested reader at another site. Unnecessary wording should be excluded. The sequence of events and consequences should be included as appropriate. If a follow-up report is intended, this report should state that. This is where the story is told.
Consequences:
The leaks in the 8-inch and 10-inch Condensate Transfer lines resulted in the release of tritium to the ground and elevated contamination levels in the area of the leak.
Briefly describe the consequences that resulted as a result of the event occurring.
Causes:
The Root Cause of the degraded 8-inch and 10-inch Condensate Transfer System piping is "anodic dissolution" resulting from disbondment of the coating and susceptible material (Root Cause 1). Improperly applied ittp://eamgenco.ceco.com/cap/servlet/ReportFullARServlet 6/25/2009
Full Action Request Report Page 6 of 11.
coatings and lack of coatings in some areas of the pipe contributed to coating disbondment and the resultant localized corrosion (Contributing Cause #1). The change management processes prior to implementing the Exelon Buried Pipe Program did not support effectively managing design changes and related projects during site ownership and management changes (Contributing Cause.#2). Methodologies used by the buried pipe program do not, in all instances, locate defects, and cannot assess entire continuous)
-full lengths of pipe (Contributing Cause #3).
Briefly present immediate causes, root causes, and contributing causes when these are known. DO NOT-repeat the "What" of the issue, state the "Why.' This may require some research. If the cause of the problem cannot be determined at this time, simply state, "Unknown" or "Under investigation."
Corrective Actions:
Corrective Actions to Prevent Recurrence (CAPR) were created to address this event.
(CAPR 1) Implement a strategic plan that includes moving direct buried Condensate Transfer System piping either above ground or in monitored trenches.
(CA) Revise the program basis document, TR 116, based on the results from the Focus Area Assessment.
(CA) Institutionalize guidance to document As-Left conditions in work order closure documentation following excavations.
(CA) Revise the program basis document (i.e., TR-116)to correct plant design details, risks, consequences, and recommend inspection frequencies and methods.
(CA) Incorporate Buried Pipe Program Owner sign offs/inspections into the work orders to ensure the desired results through maintenance are being achieved.
(CA) Update design documents to as-built conditions.
. ..(CA) Update the Oyster.Creek Buried Pipe Database following reviews Briefly describe the site's corrective actions. Distinguish between those planned and those already taken.
Previous Industry OE:
? There are 23 documented significant underground pipe leaks' in Appendix 1 of the Oyster Creek Underground Piping Program Description and Status, Topical Report 116, Rev.3. Leaks are documented from 1980 to present.
? OE 10250 Perry. Underground Drisco Pipe Failure. 07/01/1999
? OE 16189 Brunswick. Underground Fuel Oil Line Leak. 04/03/2003
? OE 22409 Braidwood Station Identified Low levels of Elevated Tritium in the groundwater on and offsite. 04/19/2006
? Operating Experience Digest (OED 2007-09) External Degradation of Buried Piping. 4/2007
? OE 27146 Quad Cities. Underground Pipe Leak due to Possible Crevice Corrosion. 5/28/2008
? OE 27897 Davis-Besse. Three-Inch Buried Pipe Degradation Results in Leak of Tritium into Ground. 10/22/2008
? OE 28335 Indian Point. Leaking Underground Condensate Return Line Pipe. 02/15/2009 Provide a short list of related industry Operating Experience (OE) based on a search of the'INPO OE database. Contact the Site OPEX Coordinator, if required. This list assists in determining the relative significance and prevalence of the event and allows one to review other industry operating' experience to identify lasting corrective actions to prevent repeat events.
Equipment Information:
NSSS/A-E: General Electric Burns & Roe Reactor Type: BWR.
Affected System: Condensate Transfer System http://eamgenco.ceco.com/cap/servlet/ReportFullARServlet 6/25/2009
Full Action Request Report Page 7 of 11 Component Manufacturer: N/A Component Model Number: N/A Component Part Number: N/A Information
Contact:
Name: Thomas G. Roddey
Title:
Engineering Programs Manager Telephone: (609) 971-4178 E-mail: thomas.Roddey@exeloncorp.com Corrective Action Program Documents:
Issue Report #907846 List the applicable Exelon Issue Report (IR) number(s).
Attachments (Pictures, Root Cause, and so forth):
N/A Attach applicable documents or media that may be of value to the reader and help communicate additional details related to the event. (
After you have filled in the information above AND documented Department Head (or designee) concurrence, Close your Action Tracking assignment AND Notify your Station OPEX Coordinator.
Remember, if you need additional guidance; contact your Site OPEX Coordinator.
5/19/2009 9:36 PM The due date for this assignment was revised consistent with extension of th-fdiJd date for the associated Root Cause report in the IR. The Root Cause investigition needs to be completed first to identify applicable information to be included in the NER. The Root Cause report is due for Manager approval on June 5, 2009. Therefore, this assignment is being extended to June 5, 2009, to coincide with completion of the investigation report.
Thomas G. Roddey Completion Notes:
ittp:H/eamgenco.ceco.com/cap/servlet/ReportFullARServlet62/20 6/25/2009