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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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AR. - Assignment Report Page 1 of 2 rGoBack Print I New Search Home AR 00934636 Report Aft Fac: Oyster Creek AR Type: CR Status: APPROVED Aff Unit: NA Owed To: A5332CAP Due Date: 07/24/2009 Aff System: Event Date: 06/22/2009 CR Level/Class: '4/D Disc Date: 06/22/2009 How H03A Orig Date: 06/24/2009 Discovered:
WR/PIMS AR: Component #:
Action Request Details
Subject:
NRC COMMENTS ON TRITIUM MASS FLUX ANALYSIS OF H-3 GROUNDWATE
Description:
Originator: CALVIN C TAYLOR Supv Contacted: Jhansi Kandasamy Condition
Description:
NRC inspector stated that he believes that we are underestimating the plume in the Conhansey aquifer by up to a factor of 10 and therefore believes our release could be as much as 10 times the 66 Currie value we stated in the CRA mass flux report. The NRC inspector stated that there was a potential direct path to the Cohansey through the Cape May with a smaller leak rate and also a potential direct and preferential path to the intake because of last years ESW excavation creating a loose fill and penetrating the clay layer between the Cape May and Cohansey. In addition, the NRC inspector has an issue with Exelons decision to characterize the intake canal sample that indicated an elevated level of tritium as invalid (IR 931098).
The station maintains a position that it would have required the leak to have gone undetected for greater than one year in order to reach 66 Curries of H-3. Any leak of this magnitude would have been detected during sampling for the License Renewal inspection of the ESW cable vault in October 2008. In addition, exposure of the exterior of the piping to this leakage would have resulted in significantly more corrosion than what was found. The following data support this conclusion:
800,000 gallons of 6 million pCi/L tritiated water equals 18 Curries of H-3.
Releasing 66 Ci of H-3 requires 3 million gallons of 6 million pCi/L tritiated water.
In 2008, the station had a demineralized water through-put of 4.4 million gallons.
During the period January 1 April 26, 2009, there was a 1.25 million gallon demineralizer through-put.
The above through-puts do not include documented usage of 175,000 gallons for the new Demineralized Water Storage Tank, 100,000 gallons for the Isolation Condenser bleed and feed, steam leaks, aux boiler operation, and other known losses/uses.
The ESW cable vault was pumped late last year October and no tritium was detected. . In addition, a cable replacement was performed in 2006 from the ESW cable vault to and through the turbine building penetration.
Engineering observation that the corrosion on the exterior of the pipe appeared to be the result of being exposed to the leak environment for http://eamgenco.ceco.com/cap/servlet/ReportARServlet 6/25/2009
I AR - Assignment Report Page 2 of 2 less than a year.
Immediate actions taken:
None required.
Recommended Actions:
Provide positions on elevated intake sample result and on bounding value for release volume.
Operable Basis:
N/A Reportable Basis:
N/A Reviewed by: HERBERT G TRITT II 06/24/2009 11:39:16 CDT Reviewer Comments:
none SOC Reviewed by: CALVIN C TAYLOR 06/24/2009 17:35:35 CDT SOC Comments:
CCT 6-24-09: In addition to the above concerns, the inspector also noted that he had previously expressed his concern regarding lack of monitoring in the Cohansey aquifer in the direct path from the CST area to the intake structure and discharge canal. He also stated that he did not have suffucient information to rule out a potential flow bath between the gap between the concrete intake and discharge tunnel structures. Recommend WGE to Chemistry to create actions to address inspector concerns. In addition, recommend an engineering evaluation to formalize bounding value for release.
Assignments Assign #: 01 Assigned To: Status: AWAIT/C Aff Fac: Oyster Creek Prim Grp: ACAPALL Due Date: 06/29/2009 Assign Type: TRKG Sec Grp: Orig Due Date: pp/pp/pppp Priority:
Schedule Ref:
Unit Condition:
Subject/Description: NRC COMMENTS ON TRITIUM MASS FLUX ANALYSIS OF H-3 GROUNDWATE http://eamgenco.ceco.com/cap/servlet/ReportARServlet 6/25/2009
Full Action Request Report Page 3 of 4 Assign #: 02 AR #: 00756041 Aff Fac: Oyster Creek Assign Type: ACIT, Status: COMPLETE Priority: Assigned To: U777JOV Due Date: 07/31/2008 Schedule Ref: Prim Grp: A5332CHEM Orig Due Date: 05/29/2008 Unit Condition: Sec Grp:
Assignment Details Subject/Description: Determine whether a new groundwater monitoring well (for H-3) should be placed in the area by the intake where excavation activities have been taking place.
Assignment Completion In Progress Notes: 05/28/08 LC - Due date extended to 07/31/08 duie to personnel changes in REMP specialist position.
07/28/08 IJV -
Response to ACIT 00756041-02 Assignment Request: Determine whether a new groundwater monitoring well (for H-3) should be placed in the area by the intake where excavation activities have been taking place.
Response: It is not feasible or necessary to install a new groundwater monitoring well at the condenser intake because the geologic formations of concern were removed during the original construction of the intake and discharge canals and associated intake and discharge structures. In addition, the existing groundwater monitoring system adequately monitors on-site groundwater for the presence of any radionuclides attributable to station operation.
The construction of the cooling water intake and discharge canals, and the associated cooling water intake and discharge structures, involved excavations 40-50 feet in depth. As a result, the uppermost Cape May formation was completely removed in these areas. The upper portion of the Cohansey Formation was also removed during those construction activities in the vicinity of the cooling water intake and discharge. These formations were replaced with large concrete and steel components that comprise the intake and discharge structures, and backfill around those structures.
Based upon our knowledge of geology and groundwater at the Oyster Creek Station (Woodward-Clyde Consultants 1983, 1984), the aquifers most vulnerable to contamination are the Cape May and Cohansey aquifers. As a result, groundwater monitoring wells at Oyster Creek are typically screened at depths of approximately 20 feet below grade in the Cape May Aquifer, or approximately 50 feet below grade in the Cohansey Aquifer.
Given the fact that these formations are not present at the cooling water intake structure, it is not possible to install groundwater monitoring wells in that area.
Measurements of groundwater flow at .the Oyster Creek Station (Woodward-Clyde Consultants 1983, 1984; Conestoga-Rovers 2006) demonstrate that the direction of groundwater flow in both the Cape May and Cohansey aquifers is generally from east to west, towards the intake and discharge canals. Groundwater from both aquifers ultimately flows into the intake or discharge canals. The existing monitoring well network includes 4 Cape May wells (W-20, W-3, MW-15K-1A, and W-5) and 3 Cohansey wells (W-2, W-4, and W-6) located at the westernmost edge of the formations, prior to discharging into the intake or discharge canal. These wells are optimally located to monitor the groundwater flowing from the most likely sources of contamination (Turbine Building, Reactor Building, Radwaste facilities, storage tanks) towards the intake and discharge canals.
http://eamgenco.ceco.com/cap/servlet/ReportFullARServlet 6/25/2009
Full, Action Request Report Page 4 of 4 Refer/ences Conestoga-Rovers & Associates. 2006. Hydrogeologic Investigation Report -
Fleetwide Assessment - Oyster Creek Generating Station - Forked River, New Jersey. Prepared for Exelon Generation Company, LLC.
Woodward-Clyde Consultants. August 1983. Phase I Report, Recommended Groundwater Monitoring System.
Woodward-Clyde Consultants. March 1984. Phase II Report, Groundwater Monitoring System.
In conclusion;, a new groundwater monitoring well will not be installed in the intake area. Close to comments above.
Completion Notes: See in progress notes http://eamgenco.ceco.com/cap/servlet/ReportFullARServlet 6/25/2009