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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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F'01 Action Request Report Page I of 5 O'Go_ Pck 4 Print New Search j Home AR Ndlmber- 00907846 Aft Fac: Oyster Creek AR Type: CR Status: APPROVED Aft Unit: NA Owed To: A5351CAP Due Date: .08/20/2009 Aft System: -- Event Date: 04/15/2009 CR Level/Class: 3/A Disc Date: 04/15/2009 How H02- Orig Date: 04/15/2009 Discovered:
Action Request Details
Subject:
TRITIUM IDENTIFIED IN ESW VAULT.
Description:
Originator: MATTHEW J NIXON Supv Contacted: Jhansi Kandasamy Condition
Description:
In preparation for work inside the Emergency Service Water vault, water found inside the v*ault 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 102,000 pCi/I. The reporting threshold to the New Jersey DEP for tritium is 2,000 pCi/I.
Immediate actions taken:
The New Jersey DEP was notified of the sample results and a potential release of tritium to the soil. It was also iterated that the water was contained in a concrete vault and being pumped into drums.
A prompt investigation (PINV) was initiated.
Additional samples were obtained for tritium analysis - drum of original water from vault, drum of current water being transferred from vault, and a sample from the vault.
Normandeau Associates were contacted to pick up duplicate samples for analysis by Teledyne Brown Engineering.
Recommended Actions:
Complete PINV. Identify potential sources.
What activities, processes, or procedures were involved?
Sampling of vault water prior to discharge.
Why did the condition happen?
Unkown What are the consequences?
Reported to New Jersey DEP as potential reportable release.
Were any procedural requirements impacted?
N/A Were there any adverse physical conditions?
Unkown List of knowledgeable individuals:
Jhansi Kandasamy Leanne Birkmire Matt Nixon Jay Vouglitios Repeat or similar condition?
No Operable Basis:
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Full Action Request Report Page 2 of 5 N/A Reportable Basis:
OP-AA-106-101 notifications were made to NJ Dept of Env Prot, ENS notifications made to NRC, PINV Reviewed by: HERBERT G TRITT II 04/16/2009 04:18:16 CDT Reviewer Comments:
none SOC Reviewed by: THOMAS S LONSDALE 04/21/2009 09:18:46 CDT SOC Comments:
CONDENSATE TRANSFER WATER SYSTEM-11,CH 04/17/09 SOC: Follow-up Chemistry 4/20/09 TAP - Significance level 3 due to Contamination above normal levels resulting from unplanned events.
4/21/09 RCL: Environmental keyword added. PINV complete. Sig 3 due to contaimination above normal levels resulting from unplanned eventes.
Complex troubleshooting action plan (CTSAP) in progress and asssiged. Risk High - Uncertainty Med, engineering will per a Root Cause Evaluations, Class A. Close to Root Cause assignments made, PINV, CTSAP, and PIMS AR A2222268 pulled through.
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Full Action Request Report Page 3 of 5 Assign #: 01 AR #: 00907846 Aff Fac: OysterCreek Assign Type: TRKG Status: COMPLETE Priority: Assigned To: Due Date: 04/20/2009 Schedule Ref: Prim Grp: ACAPALL Orig Due Date:
Unit Condition: Sec Grp:
Assignment Details Subject/Description: TRITIUM IDENTIFIED IN ESW VAULT
.Assignment Completion In Progress Notes:
Completion Notes:
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Full Action Request Report Page 4 of 5.
Assign #: 02 AR #: 00907846 Aft Fac: Oyster Creek Assign Type: PINV Status: COMPLETE Priority: Assigned To: U00OPO3 Due Date: 04/20/2009 Schedule Ref: Prim Grp: A5332CHEM Orig Due Date: 04/20/2009 Unit Condition: Sec Grp:
Assignment Details Subject/Description: Perform PINV following Management approval, submit to NDO Mailbox and NRC Resident.
Assignment Completion In Progress Notes:
ATTACHMENT 2 Event / Issues Report Format Equipment Issue
- 1. State the problem that is being reported and provide the CR/IR number:
Tritium levels greater than 2,000 pCi/I identified in water pumped out of a concrete vault containing Emergency Service Water (ESW) cables, which were being replaced. The IR# is 907846.
- 2. Brief Description of Equipment and Event / Issue Outside vaults and pipe chases are sampled for gamma emitters, tritium and pH prior to discharge to the ground. The cable work scheduled for the
. . workweek-required entrance into the vault. The manhole was opened ahd water was discovered. The water was pumped into 55-gallon drums and sampled. There were no gamma emitters identified, pH was 7.62 and tritium was 102,000 pCi/I.
The Minimum Detectable Activity (MDA) for on-site tritium analysis is 2,000 pCi/I. This is the Lower Limit of Detection (LLD) listed in the Oyster Creek Offsite Dose Calculation Manual (ODCM) and is the value used, as the reporting threshold for notification to the New Jersey Department of Environmental Protection (NJDEP) for release of tritium.
Since water was observed entering the vault, it was conservatively decided that water could be exiting thevault. Based on the tritium levels in the vault, it was determined that a notification be reported to the NJDEP hotline, due to a prior agreement made with the state. This notification.
was made six minutes after the sample analysis results were received.
There are a total of 31 conduits that enter or exit the vault.
- 3. Pertinent Equipment History Information This vault was inspected on September 29th as part of the License Renewal inspections and Water was tested for Tritium with less than detectable levels.
- 4. Any PCM, PM, Last Worked, OPEX (internal or external), etc issues As part of the License Renewal program, this vault is inspected every 90 days.
- 5. Extent of Condition PMs exist to perform inspections of underground manholes and if water is found, then sampled. The previous records show that there were no detectable levels of Tritium in manholes inspected in September of 2009.
Additional reviews are in progress.
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Full Action Request Report Page 5 of 5
- 6. Current: Status (including risks /concerns)
Continuing to pump rainwater from the vault into 55-gallon drums.
Additional samples obtained from the ESW vault, a sample from the original water pumped from the vault, and a sample from the rainwater being pumped out at the time of sampling. Sample results are expected to be available at 1000, 4/16/09.
Normandeau Associates have been' contacted to pick up duplicate samples for shi'pping to Teledyne Brown Engineering for analysis.
Samples obtained between March 10 and March 12, 2009, as part of the Radiological Groundwater Protection Program (RGPP),. were all less than the LLD of 200 pCi/l.
- 7. Follow-up Actions Planned Evaluate all inputs into and from the ESW vault for potential solurces of tritium.
Inspect other vaults in the vicinity and sample for tritium as warranted.
Have our contractor (Normandeau Associates) collect water samples from the following locations:
? Monitoring wells in the general vicinity of the cable vault - W-3, W-4, W-5, W-6 and MW-15K-1A. These wells were sampled during the March 10-12, 2009 period. The results of tritium analyses on those samples were all < 200 pCi/L
? Lysimeter in the vicinity of the cable vault - CST-9. This lysimeter was sampled on March 11, 2009 and the tritium concentration was < 200 pCi/L.
? 1Lysimeter on the southwest corner of the Condensate Storage Tank -
CST-2. This lysimeter was last sampled in August of 2006 when the tritium concentration was found to be < 200 pCi/L.
? Surface water sample from the main condenser discharge. This is not a routine sampling point.
The samples will be shipped to Teledyne Brown Engineering to be analyzed for tritium, strontium-90 and gamma emitting radionuclides utilizing the LLDs specified for the Radiological Groundwater Protection Program.
- 8. Any Assistance Needed Issues management team assembled for communications and issue resolution.
Completion Notes:
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