|
|
Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:AmerenVE Callaway Plant PO Box 620 Fulton, MO 65251 August 2, 2006 Mr. Stuart A. Richards, Deputy Director Division of Inspection and Regional Support Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SAmerenl UE | | {{#Wiki_filter:AmerenVE PO Box 620 Callaway Plant Fulton, MO 65251 August 2, 2006 Mr. Stuart A. Richards, Deputy Director Division of Inspection and Regional Support Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 |
|
| |
|
| ==Dear Mr. Richards:== | | ==Dear Mr. Richards:== |
| ULNRC-05319 DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.GROUNDWATER PROTECTION | | ULNRC-05319 SAmerenl UE DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO. |
| -DATA COLLECTION QUESTIONNAIRE The nuclear industry, in conjunction with the Nuclear Energy Institute, has developed a questionnaire to facilitate the collection of groundwater data at commercial nuclear reactor sites. The objective of the questionnaire is to compile baseline information about the current status of site programs for monitoring and protecting groundwater and to share that information with NRC. The completed questionnaire for Callaway Plant is enclosed.This submittal contains no new regulatory commitments.
| | GROUNDWATER PROTECTION - |
| | DATA COLLECTION QUESTIONNAIRE The nuclear industry, in conjunction with the Nuclear Energy Institute, has developed a questionnaire to facilitate the collection of groundwater data at commercial nuclear reactor sites. The objective of the questionnaire is to compile baseline information about the current status of site programs for monitoring and protecting groundwater and to share that information with NRC. The completed questionnaire for Callaway Plant is enclosed. |
| | This submittal contains no new regulatory commitments. |
| Please contact Dave Shafer, Superintendent Licensing at 314-554-3104 or me at 573-676-8659 if you have questions about the enclosed information. | | Please contact Dave Shafer, Superintendent Licensing at 314-554-3104 or me at 573-676-8659 if you have questions about the enclosed information. |
| Sincerely, Mr , D. guo Manager, Regulatory Affairs DES/jdg Enclosure a subsidiary ofAmeren Corporation ULNRC-05319 August 2, 2006 Page 2 cc: U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Mr. Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop O-7D1 Washington, DC 20555-2738 Missouri Public Service Commission Governor Office Building 200 Madison Street PO Box 360 Jefferson City, MO 65102-0360 Mr. Floyd Gilzow Deputy Director for Policy Missouri Department of Natural Resources PO Box 176 Jefferson City, MO 65102 Mr. Ralph Andersen Nuclear Energy Institute 1776 1 Street N.W., Suite 400 Washington, DC 20006-3708 ULNRC-05319 August 2, 2006 Page 3 bcc: C. D. Naslund A. C. Heflin K. D. Young G. A. Hughes D. E. Shafer (470)S. L. Gallaghcr (100)L. M. Belsky (NSRB)K. A. Mills P. M. Bell A 160.0761 Certrec Corporation 4200 South Hulen, Suite 630 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards andlpublic disclosed). | | Sincerely, Mr D. , guo Manager, Regulatory Affairs DES/jdg Enclosure a subsidiary ofAmeren Corporation |
| | |
| | ULNRC-05319 August 2, 2006 Page 2 cc: U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Mr. Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies) |
| | Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop O-7D1 Washington, DC 20555-2738 Missouri Public Service Commission Governor Office Building 200 Madison Street PO Box 360 Jefferson City, MO 65102-0360 Mr. Floyd Gilzow Deputy Director for Policy Missouri Department of Natural Resources PO Box 176 Jefferson City, MO 65102 Mr. Ralph Andersen Nuclear Energy Institute 1776 1 Street N.W., Suite 400 Washington, DC 20006-3708 |
| | |
| | ULNRC-05319 August 2, 2006 Page 3 bcc: C. D. Naslund A. C. Heflin K. D. Young G. A. Hughes D. E. Shafer (470) |
| | S. L. Gallaghcr (100) |
| | L. M. Belsky (NSRB) |
| | K. A. Mills P. M. Bell A 160.0761 Certrec Corporation 4200 South Hulen, Suite 630 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards andlpublic disclosed). |
| Send the following without attachments: | | Send the following without attachments: |
| Ms. Diane M. Hooper Supervisor, Licensing WCNOC P.O. Box 411 Burlington, KS 66839 Mr. Scott Bauer Regulatory Affairs Palo Verde NGS P.O. Box 52034, Mail Station 7636 Phoenix, AZ 85072-2034 Mr. Scott Head Supervisor, Licensing South Texas Project NOC Mail Code N5014 P.O. Box 289 Wadsworth, TX 77483 Mr. Dennis Buschbaum TXU Power Comanche Peak SES P.O. Box 1002 Glen Rose, TX 76043 Mr. Stan Ketelsen Manager, Regulatory Services Pacific Gas & Electric Mail Stop 104/5/536 P.O. Box 56 Avila Beach, CA 93424 Mr. John O'Neill Pillsbury Winthrop Shaw Pittman LLP 2300 N. Street N.W.Washington, DC 20037 Enclosure ULNRC-05319 Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire Plant: Callaway Plant 1. Briefly describe the program and/or methods used for detection of leakage or spills from plant systems, structures, and components that have a potential for an inadvertent release of radioactivity from plant operations into groundwater. | | Ms. Diane M. Hooper Mr. Dennis Buschbaum Supervisor, Licensing TXU Power WCNOC Comanche Peak SES P.O. Box 411 P.O. Box 1002 Burlington, KS 66839 Glen Rose, TX 76043 Mr. Scott Bauer Mr. Stan Ketelsen Regulatory Affairs Manager, Regulatory Services Palo Verde NGS Pacific Gas & Electric P.O. Box 52034, Mail Stop 104/5/536 Mail Station 7636 P.O. Box 56 Phoenix, AZ 85072-2034 Avila Beach, CA 93424 Mr. Scott Head Mr. John O'Neill Supervisor, Licensing Pillsbury Winthrop Shaw Pittman LLP South Texas Project NOC 2300 N. Street N.W. |
| Answer: There are 3 shallow groundwater monitoring wells and a groundwater sump located alongside the spent fuel storage building which are sampled quarterly and analyzed for tritium and principal gamma emitters. | | Mail Code N5014 Washington, DC 20037 P.O. Box 289 Wadsworth, TX 77483 |
| These wells are used to ensure there is no leakage from the spent fucl storage pool. There are no monitoring wells, programs, or methods for detection of leakage or spills from plant systems, structures, or components. | | |
| | Enclosure ULNRC-05319 Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire Plant: Callaway Plant |
| | : 1. Briefly describe the program and/or methods used for detection of leakage or spills from plant systems, structures, and components that have a potential for an inadvertent release of radioactivity from plant operations into groundwater. |
| | Answer: There are 3 shallow groundwater monitoring wells and a groundwater sump located alongside the spent fuel storage building which are sampled quarterly and analyzed for tritium and principal gamma emitters. These wells are used to ensure there is no leakage from the spent fucl storage pool. There are no monitoring wells, programs, or methods for detection of leakage or spills from plant systems, structures, or components. |
| : 2. Briefly describe the program and/or methods for monitoring onsite groundwater for the presence of radioactivity released from plant operations. | | : 2. Briefly describe the program and/or methods for monitoring onsite groundwater for the presence of radioactivity released from plant operations. |
| Answer: There are 3 shallow groundwater monitoring wells and a groundwater sump located alongside the spent fuel storage building and three onsite deep wells which are sampled quarterly and analyzed for tritium and principal gamma emitters. | | Answer: There are 3 shallow groundwater monitoring wells and a groundwater sump located alongside the spent fuel storage building and three onsite deep wells which are sampled quarterly and analyzed for tritium and principal gamma emitters. There are no other monitoring wells, programs, or methods for monitoring onsite groundwater for the presence of radioactivity released from plant operations. |
| There are no other monitoring wells, programs, or methods for monitoring onsite groundwater for the presence of radioactivity released from plant operations. | | : 3. If applicable, briefly summarize any occurrences of inadvertent releases of radioactive liquids that had the potential to reach groundwater and have been documented in accordance with 10 CFR 50.75(g). |
| : 3. If applicable, briefly summarize any occurrences of inadvertent releases of radioactive liquids that had the potential to reach groundwater and have been documented in accordance with 10 CFR 50.75(g).Answer: (a) There have been six breaks in the discharge pipeline; however, until recently, only three instances were documented in the corrective action system as a 50.75(g) event. Action 32 of the Callaway Groundwater Protection Initiative (GPI) action plan (CAR 200602748) will document the three undocumented breaks in the plant corrective action system as 50.75(g)events.(b) The shallow groundwater underneath the plant is contaminated with low levels of tritium, and is documented in the plant corrective action system as a 50.75(g) event. The contamination is due to a backflow eddy which carries the plant effluent discharge upriver to the plant intake. This has resulted in low levels of 3 H contamination in the plant raw water systems. Underground leaks in the raw water systems have resulted in low levels of 3H groundwater contamination.(c) The air release valves (ARV's) on the discharge pipeline operate with a small amount of blow- by which has resulted in contamination of the French drain in the manholes and low level tritium contamination of the groundwater in the vicinity of the manholes. | | Answer: |
| Extensive discrete depth soil sampling and sampling of the free water around the manholes has been performed by an independent firm and the results are being analyzed by a registered geologist and a registered professional geotechnical engineer. | | (a) There have been six breaks in the discharge pipeline; however, until recently, only three instances were documented in the corrective action system as a 50.75(g) event. Action 32 of the Callaway Groundwater Protection Initiative (GPI) action plan (CAR 200602748) will document the three undocumented breaks in the plant corrective action system as 50.75(g) events. |
| Drinking water from neighbors with adjoining property has been analyzed and there was no detectable 3 H or other radioactivity of plant origin. Bins were placed under the ARV's to catch the bypass water to prevent it from reaching the French drains. Work is continuing to fully characterize the extent of the contamination from the ARV's. This work is being tracked by Action 22 of the GPI action I Enclosure ULNRC-05319 Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire plan. CAR 200604709 is tracking the development of a permanent solution to this issue.This event is documented in the plant corrective action system as a 50.75(g) event.Pursuant to the NEI Groundwater Protection Initiative, AmerenUE has recently provided a voluntary notification to the Missouri Department of Natural Resources and the USNRC Region 4 Office for each of the above events. The Missouri DNR and the USNRC Region 4 Office have been and will continue to be updated as new information becomes available. | | (b) The shallow groundwater underneath the plant is contaminated with low levels of tritium, and is documented in the plant corrective action system as a 50.75(g) event. The contamination is due to a backflow eddy which carries the plant effluent discharge upriver to the plant intake. This has resulted in low levels of 3H contamination in the plant raw water systems. Underground leaks in the raw water systems have resulted in low levels of 3H groundwater contamination. |
| | (c) The air release valves (ARV's) on the discharge pipeline operate with a small amount of blow- by which has resulted in contamination of the French drain in the manholes and low level tritium contamination of the groundwater in the vicinity of the manholes. Extensive discrete depth soil sampling and sampling of the free water around the manholes has been performed by an independent firm and the results are being analyzed by a registered geologist and a registered professional geotechnical engineer. Drinking water from neighbors with adjoining property has been analyzed and there was no detectable 3H or other radioactivity of plant origin. Bins were placed under the ARV's to catch the bypass water to prevent it from reaching the French drains. Work is continuing to fully characterize the extent of the contamination from the ARV's. This work is being tracked by Action 22 of the GPI action I |
| | |
| | Enclosure ULNRC-05319 Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire plan. CAR 200604709 is tracking the development of a permanent solution to this issue. |
| | This event is documented in the plant corrective action system as a 50.75(g) event. |
| | Pursuant to the NEI Groundwater Protection Initiative, AmerenUE has recently provided a voluntary notification to the Missouri Department of Natural Resources and the USNRC Region 4 Office for each of the above events. The Missouri DNR and the USNRC Region 4 Office have been and will continue to be updated as new information becomes available. |
| These events have also been discussed informally with local county officials. | | These events have also been discussed informally with local county officials. |
| : 4. If applicable, briefly summarize the circumstances associated with any onsite or offsite groundwater monitoring result indicating a concentration in groundwater of radioactivity released from plant operations that exceeds the maximum contaminant level (MCL) established by the USEPA for drinking water.Answer: There have been no offsite groundwater monitoring samples that exceed the USEPA MCL or the reporting values provided by the USNRC Branch Technical Position.One onsite sample of groundwater taken in the area of manhole 6B shows a 3 H concentration of 25,863 pCi/L. Efforts are continuing under Action 22 of the Callaway GPI action plan to determine the extent of the contamination of the area around the manholes with ARV's.5. Briefly describe any remediation efforts undertaken or planned to reduce or eliminate levels of radioactivity resulting from plant operations in soil or groundwater onsite or offsite.Answer: There have been no remediation efforts undertaken to date. Efforts are still underway to characterize the plant site and determine the extent of any identified contamination. | | : 4. If applicable, briefly summarize the circumstances associated with any onsite or offsite groundwater monitoring result indicating a concentration in groundwater of radioactivity released from plant operations that exceeds the maximum contaminant level (MCL) established by the USEPA for drinking water. |
| Remediation will be considered as part of the characterization efforts.2}} | | Answer: There have been no offsite groundwater monitoring samples that exceed the USEPA MCL or the reporting values provided by the USNRC Branch Technical Position. |
| | One onsite sample of groundwater taken in the area of manhole 6B shows a 3H concentration of 25,863 pCi/L. Efforts are continuing under Action 22 of the Callaway GPI action plan to determine the extent of the contamination of the area around the manholes with ARV's. |
| | : 5. Briefly describe any remediation efforts undertaken or planned to reduce or eliminate levels of radioactivity resulting from plant operations in soil or groundwater onsite or offsite. |
| | Answer: There have been no remediation efforts undertaken to date. Efforts are still underway to characterize the plant site and determine the extent of any identified contamination. Remediation will be considered as part of the characterization efforts. |
| | 2}} |
|
---|
Category:Letter type:ULNRC
MONTHYEARULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 ULNRC-06847, Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)2023-12-21021 December 2023 Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01) ULNRC-06849, License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds2023-12-20020 December 2023 License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds ULNRC-06844, Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification2023-12-0707 December 2023 Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ULNRC-06824, Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A2023-08-17017 August 2023 Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A ULNRC-06830, Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak2023-08-15015 August 2023 Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak ULNRC-06223, Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004)2023-07-25025 July 2023 Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004) ULNRC-06799, Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications2023-07-13013 July 2023 Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications ULNRC-06821, Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301)2023-06-21021 June 2023 Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301) ULNRC-06822, Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a2023-06-14014 June 2023 Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a ULNRC-06815, Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a2023-06-0505 June 2023 Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a ULNRC-06818, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate .2023-06-0505 June 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate . ULNRC-06816, Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015)2023-05-0909 May 2023 Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06812, Submittal of 2022 Annual Radiological Environmental Operating Report2023-04-27027 April 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ULNRC-06806, Submittal of Radiological Emergency Response Plan, Revision 552023-04-12012 April 2023 Submittal of Radiological Emergency Response Plan, Revision 55 ULNRC-06807, Submittal of Single Positive Test Forms2023-04-0303 April 2023 Submittal of Single Positive Test Forms ULNRC-06798, Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan2023-03-30030 March 2023 Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan ULNRC-06801, CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions2023-03-30030 March 2023 CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions ULNRC-06804, Submittal of Nuclear Property Insurance Reporting2023-03-29029 March 2023 Submittal of Nuclear Property Insurance Reporting ULNRC-06751, Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control2023-03-29029 March 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control ULNRC-06803, Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection2023-03-29029 March 2023 Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection ULNRC-06805, Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days2023-03-21021 March 2023 Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days ULNRC-06802, Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument2023-03-0909 March 2023 Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument ULNRC-06795, Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms2023-01-24024 January 2023 Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms ULNRC-06794, Submittal of Fitness for Duty Program Data for 20222023-01-24024 January 2023 Submittal of Fitness for Duty Program Data for 2022 ULNRC-06787, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-12-0808 December 2022 Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06781, License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2022-12-0101 December 2022 License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ULNRC-06780, Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-0072022-11-30030 November 2022 Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-007 ULNRC-06772, 10 CFR 50.59 and 10 CFR 72.48 Summary Report2022-11-23023 November 2022 10 CFR 50.59 and 10 CFR 72.48 Summary Report ULNRC-06777, Operating Quality Assurance Manual (Oqam) Revision 362022-11-16016 November 2022 Operating Quality Assurance Manual (Oqam) Revision 36 ULNRC-06779, ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves2022-11-14014 November 2022 ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves ULNRC-06765, License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Testing Frequencies (LDCN 2020-0004)2022-11-0303 November 2022 License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Testing Frequencies (LDCN 2020-0004) ULNRC-06773, Results of Steam Generator Tube In-Service Inspection2022-11-0101 November 2022 Results of Steam Generator Tube In-Service Inspection ULNRC-06775, Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days2022-10-27027 October 2022 Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days ULNRC-06771, Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013)2022-10-25025 October 2022 Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013) ULNRC-06770, Cycle 25 Commitment Change Summary Report2022-10-19019 October 2022 Cycle 25 Commitment Change Summary Report ULNRC-06766, Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014)2022-09-0808 September 2022 Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014) ULNRC-06767, Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies2022-09-0606 September 2022 Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies ULNRC-06764, Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-09-0101 September 2022 Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06763, Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013)2022-09-0101 September 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013) ULNRC-06762, Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 252022-08-25025 August 2022 Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 25 ULNRC-06758, Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002)2022-08-0404 August 2022 Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002) ULNRC-06755, Response to Requests for Additional Information for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals2022-07-13013 July 2022 Response to Requests for Additional Information for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals ULNRC-06754, Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications2022-07-0505 July 2022 Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications ULNRC-06739, Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007)2022-06-30030 June 2022 Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007) ULNRC-06752, Evacuation Time Estimates Report2022-06-27027 June 2022 Evacuation Time Estimates Report ULNRC-06753, Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis2022-06-23023 June 2022 Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis ULNRC-06750, Submittal of Cycle 26 Core Operating Limits Report (COLR)2022-06-13013 June 2022 Submittal of Cycle 26 Core Operating Limits Report (COLR) ULNRC-06735, Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014).2022-05-27027 May 2022 Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014). 2024-01-29
[Table view] Category:Report
MONTHYEARML23354A2462023-12-20020 December 2023 Cracking Assessment for Framatome RSG Channel Head Assembly ML23215A1992023-08-31031 August 2023 ANP-4012NP, Callaway, Unit 1, Rod Ejection Accident Analysis Revision 2, August 2023 ML23299A1982023-06-16016 June 2023 Enclosure 2: Callaway RR Tech Report Containment Post-Tensioning System Inservice Inspection Technical Report Basis for Proposed Extension of Examination Interval, Revision 0 ML23156A6712023-06-0505 June 2023 Description and Justification for Changes ML23150A1832023-05-30030 May 2023 EIP-ZZ-00240 Addendum E, Revision 027, Health Physics Coordinator (Hpc) Checklist Administrative Correction ML23150A1842023-05-18018 May 2023 EIP-ZZ-00240 Addendum E, Revision 027, Health Physics Coordinator (Hpc) Checklist ML23150A1892023-05-18018 May 2023 EIP-ZZ-00245 Addendum H, Revision 004, Security Coordinator Checklist for the Alternate Tsc/Osa Assembly Area ML23131A3882023-04-26026 April 2023 EIP-ZZ-PRO2O Minor Revision 54, Activation and Operation of the Joint Information Center - Procedure Review Form and 50.54(q) Screening Form ML23110A0712023-04-0606 April 2023 Procedure Review Form (PRF) for EIP-ZZ-A0066, Revision 28, RERP Training Program ML23068A0992023-03-0909 March 2023 Special Report 2023-01 PAM Report ML23052A0492023-02-14014 February 2023 Enclosure 7 - Holtec International Report HI-2230125, Revision 0, Supplemental Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station, Revision 0, Dated February 14, 2023 ML22349A6272022-12-15015 December 2022 Enclosure 3 - 2022 Proxy Statement of Ameren Corporation ML22349A6322022-12-15015 December 2022 Enclosure 8 - 10-K Filed 02/23/2022 ML22349A6342022-12-15015 December 2022 Enclosure 9 - 10-Q Filed 03/31/2022 ML22349A6352022-12-15015 December 2022 Enclosure 10 - 10-Q Filed 06/30/2022 ML22349A6362022-12-15015 December 2022 Enclosure 11 - 10-Q Filed 09/30/2022 ML22349A6402022-12-15015 December 2022 Enclosure 14 - Schedule 14C Information for Union Electric Company March 2022 ML22327A2242022-11-23023 November 2022 Enclosure 1: Callaway Plant - Report Period: 10 CFR 50.59 and 10 CFR 72.48 Summary Report June 16, 2021 to November 23, 2022 ML22335A5012022-11-16016 November 2022 Enclosure 3: ANP-4012NP, Revision 1, Callaway Rod Ejection Accident Analysis ML22318A1902022-11-14014 November 2022 Enclosure 2 - Pressurized Water Reactor Owners Group Letter, OG-22-187, Subject: PWR Owners Group Mode 4 LOCA Analysis for Westinghouse NSSS Plants ML22299A2352022-10-21021 October 2022 HI-2220020, Revision 2, Non Proprietary Version of Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station ML22285A1252022-10-12012 October 2022 Attachment 8 to Enclosure 1: ANP-3969NP, Callaway Non-LOCA Summary Report, Revision 2, Dated October 2022 ML22285A1222022-10-12012 October 2022 Attachment 5 to Enclosure 1: ANP-3947NP, Callaway Unit 1 License Amendment Request Inputs for Use of Framatome Fuel, Revision 3, Dated October 2022 ML22285A1232022-10-12012 October 2022 Attachment 6 to Enclosure 1: ANP-3944NP, Callaway Realistic Large Break LOCA Analysis with Gaia Fuel Design, Revision 1, Dated October 2022 ML22285A1242022-10-12012 October 2022 Attachment 7 to Enclosure 1: ANP-3943NP, Callaway Small Break LOCA Analysis with Gaia Fuel Design, Revision 1, Dated October 2022 ML22181B1362022-06-30030 June 2022 Attachment 6 - Replacement for Attachment 6, Description and Assessment Specific to TSTF-439, of ULNRC-06688 ML22181B1402022-06-30030 June 2022 Enclosure 1 - Replacement for Enclosure 1, List of Revised Required Actions to Corresponding PRA Functions, of ULNRC-06688 ML22181B1412022-06-30030 June 2022 Enclosure 4 - Replacement for Enclosure 4, Information Supporting Justification of Excluding Sources of Risk Not Addressed by the PRA Models, of ULNRC-06688 ML22153A1822022-06-0202 June 2022 Attachment 6 - Non-Proprietary Version of Rlbloca Summary Report ML22153A1832022-06-0202 June 2022 Attachment 7 - Non-Proprietary Version of SBLOCA Summary Report ML22153A1852022-06-0202 June 2022 Attachment 8 - Non-Proprietary Version of Non-LOCA Summary Report ULNRC-06715, Enclosure 3: Attachment a to the NPDES Permit Modification Application2022-03-0101 March 2022 Enclosure 3: Attachment a to the NPDES Permit Modification Application ML22027A8092022-01-27027 January 2022 Enclosure 4: Callaway, Unit 1, Acronyms and Definitions ML22027A8082022-01-27027 January 2022 Enclosure 3: Callaway, Unit 1, Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 ML22027A8062022-01-27027 January 2022 Enclosure 1: Request for Exemptions for Risk-Informed Approach to Resolution for Generic Letter 2004-02 ML21356B5072021-12-22022 December 2021 Enclosure 1: Mark-up of Operating License (OL) ML21356B5082021-12-22022 December 2021 Enclosure 2: Clean Copy of Affected OL Pages (Reflecting Proposed Change) ML21343A0952021-12-0909 December 2021 Attachment 1: Description and Assessment ML21335A1602021-12-0101 December 2021 Special Report 2021-02: Accident Monitoring Instrumentation Non-Functional for Greater than 7 Days ML21280A3802021-10-0707 October 2021 Cumulative Summary of Changes to Enclosure 2, License Amendment Request, and Enclosure 3, Callaway Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02, of ULNRC-06526 ML21280A3812021-10-0707 October 2021 License Amendment Request for Risk-Informed Approach to Resolution of Generic Letter 2004-02 ML21272A1702021-09-28028 September 2021 Enclosure 2 - Full Scope Implementation of Alternative Source Term Evaluation of Proposed Changes (Redacted) ML21237A1372021-08-23023 August 2021 Enclosure 1: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - Baseline Weld Input ML21237A1382021-08-23023 August 2021 Enclosure 2: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Critical Breaks) ULNRC-06683, Enclosure 3: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Non-Isolable Breaks)2021-08-23023 August 2021 Enclosure 3: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Non-Isolable Breaks) ULNRC-06526, Methodology for a Risk-Informed Approach to Address Generic Letter 2004-022021-07-22022 July 2021 Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 ULNRC-06660, Cycle 24 Commitment Change Summary Report2021-06-22022 June 2021 Cycle 24 Commitment Change Summary Report ML21173A3412021-06-22022 June 2021 CFR 50.59 and 10 CFR 72.48 Summary Report - May 16, 2019 to June 15, 2021 ML21090A2502021-03-31031 March 2021 Attachment 1 - Changes to the Westinghouse ECCS Evaluation Model and PCT Penalty Assessments ML21090A1882021-03-31031 March 2021 Enclosure 3 - Callaway Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 2023-08-31
[Table view] Category:Miscellaneous
MONTHYEARML23156A6712023-06-0505 June 2023 Description and Justification for Changes ML23131A3882023-04-26026 April 2023 EIP-ZZ-PRO2O Minor Revision 54, Activation and Operation of the Joint Information Center - Procedure Review Form and 50.54(q) Screening Form ML23068A0992023-03-0909 March 2023 Special Report 2023-01 PAM Report ULNRC-06715, Enclosure 3: Attachment a to the NPDES Permit Modification Application2022-03-0101 March 2022 Enclosure 3: Attachment a to the NPDES Permit Modification Application ML22027A8062022-01-27027 January 2022 Enclosure 1: Request for Exemptions for Risk-Informed Approach to Resolution for Generic Letter 2004-02 ML22027A8092022-01-27027 January 2022 Enclosure 4: Callaway, Unit 1, Acronyms and Definitions ML21356B5072021-12-22022 December 2021 Enclosure 1: Mark-up of Operating License (OL) ML21356B5082021-12-22022 December 2021 Enclosure 2: Clean Copy of Affected OL Pages (Reflecting Proposed Change) ML21343A0952021-12-0909 December 2021 Attachment 1: Description and Assessment ML21335A1602021-12-0101 December 2021 Special Report 2021-02: Accident Monitoring Instrumentation Non-Functional for Greater than 7 Days ML21280A3802021-10-0707 October 2021 Cumulative Summary of Changes to Enclosure 2, License Amendment Request, and Enclosure 3, Callaway Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02, of ULNRC-06526 ML21280A3812021-10-0707 October 2021 License Amendment Request for Risk-Informed Approach to Resolution of Generic Letter 2004-02 ML21173A3412021-06-22022 June 2021 CFR 50.59 and 10 CFR 72.48 Summary Report - May 16, 2019 to June 15, 2021 ULNRC-06437, Cycle 22 Commitment Change Summary Report2018-06-0707 June 2018 Cycle 22 Commitment Change Summary Report ULNRC-06349, Callaway, Unit 1 - Enclosure 2 to ULNRC-06349 - Minimum Decommissioning Cost - Per 10 CFR 50.75 Formula Process2017-03-30030 March 2017 Callaway, Unit 1 - Enclosure 2 to ULNRC-06349 - Minimum Decommissioning Cost - Per 10 CFR 50.75 Formula Process ML17097A5582017-03-30030 March 2017 Enclosure 2 to ULNRC-06349 - Minimum Decommissioning Cost - Per 10 CFR 50.75 Formula Process ML16160A0952016-06-0808 June 2016 ASP ANALYSIS-REJECT- Callaway Unit 1 Auxiliary Feedwater Control Valves in Motor Driven Pump Train Inoperable due to Faulty Electric positioner Cards (LER 483-2015-003 and 483-2015-004) ULNRC-06292, Transmittal of 10 CFR50.46 Annual Report ECCS Evaluation Model Revisions2016-03-30030 March 2016 Transmittal of 10 CFR50.46 Annual Report ECCS Evaluation Model Revisions ULNRC-06199, Nuclear Property Insurance Reporting2015-03-18018 March 2015 Nuclear Property Insurance Reporting ULNRC-06173, Submits Owner'S Activity Reports (OAR-1 Forms) for Cycle 20 and Refuel 202015-02-19019 February 2015 Submits Owner'S Activity Reports (OAR-1 Forms) for Cycle 20 and Refuel 20 ML14310A8362015-02-0909 February 2015 NRC Staff Evaluation of Final Rule for Continued Storage of Spent Nuclear Fuel for the License Renewal Environmental Review for Callaway, Unit 1 ULNRC-06168, Enclosure 10 - Articles of Incorporation Ameren Corporation Restated 10/17/19952014-12-18018 December 2014 Enclosure 10 - Articles of Incorporation Ameren Corporation Restated 10/17/1995 ULNRC-06168, Enclosure 7 - 10-Q Filed Period 6/30/2014 Ameren2014-12-18018 December 2014 Enclosure 7 - 10-Q Filed Period 6/30/2014 Ameren ULNRC-06168, Enclosure 16 - Articles of Incorporation - Union Electric Company Restated 04/12/19942014-12-18018 December 2014 Enclosure 16 - Articles of Incorporation - Union Electric Company Restated 04/12/1994 ULNRC-06168, Enclosure 5 - 10-K Filed Period 12/31/2013 - Ameren2014-12-18018 December 2014 Enclosure 5 - 10-K Filed Period 12/31/2013 - Ameren ULNRC-06168, Enclosure 8 - 10-Q Filed Period 9/30/2014 Ameren2014-12-18018 December 2014 Enclosure 8 - 10-Q Filed Period 9/30/2014 Ameren ULNRC-06168, Enclosure 9 - Articles of Incorporation Ameren Corporation Dated 08/07/19952014-12-18018 December 2014 Enclosure 9 - Articles of Incorporation Ameren Corporation Dated 08/07/1995 ULNRC-06168, Enclosure 14 - Defc 14c Filed Period 3/11/2014 - Union Electric2014-12-18018 December 2014 Enclosure 14 - Defc 14c Filed Period 3/11/2014 - Union Electric ULNRC-06168, Enclosure 6 - 10-Q Filed Period 3/31/2014 - Ameren2014-12-18018 December 2014 Enclosure 6 - 10-Q Filed Period 3/31/2014 - Ameren ULNRC-06168, Enclosure 11 - Ameren Corporation By-Laws Effective 12/14/20122014-12-18018 December 2014 Enclosure 11 - Ameren Corporation By-Laws Effective 12/14/2012 ULNRC-06168, Enclosure 15 - Articles of Incorporation - Missouri Electric Light and Power Company Dated 11/20/19222014-12-18018 December 2014 Enclosure 15 - Articles of Incorporation - Missouri Electric Light and Power Company Dated 11/20/1922 ULNRC-06168, Enclosure 4 - 2013 Annual Report (Includes 2013 Form 10-K) - Ameren2014-12-18018 December 2014 Enclosure 4 - 2013 Annual Report (Includes 2013 Form 10-K) - Ameren ULNRC-06168, Enclosure 17 - By-Laws of Union Electric Company as Amended to 12/10/20102014-12-18018 December 2014 Enclosure 17 - By-Laws of Union Electric Company as Amended to 12/10/2010 ML14352A4292014-12-18018 December 2014 Enclosure 15 - Articles of Incorporation - Missouri Electric Light and Power Company Dated 11/20/1922 ML14352A4302014-12-18018 December 2014 Enclosure 17 - By-Laws of Union Electric Company as Amended to 12/10/2010 ML14352A4472014-12-18018 December 2014 Enclosure 3 - 2014 Proxy Statement of Ameren Corporation - Ameren ML14352A4322014-12-18018 December 2014 Enclosure 16 - Articles of Incorporation - Union Electric Company Restated 04/12/1994 ML14352A4332014-12-18018 December 2014 Enclosure 4 - 2013 Annual Report (Includes 2013 Form 10-K) - Ameren ML14352A4342014-12-18018 December 2014 Enclosure 11 - Ameren Corporation By-Laws Effective 12/14/2012 ML14352A4352014-12-18018 December 2014 Enclosure 6 - 10-Q Filed Period 3/31/2014 - Ameren ML14352A4362014-12-18018 December 2014 Enclosure 14 - Defc 14c Filed Period 3/11/2014 - Union Electric ML14352A4382014-12-18018 December 2014 Enclosure 9 - Articles of Incorporation Ameren Corporation Dated 08/07/1995 ML14352A4392014-12-18018 December 2014 Enclosure 8 - 10-Q Filed Period 9/30/2014 Ameren ML14352A4402014-12-18018 December 2014 Enclosure 5 - 10-K Filed Period 12/31/2013 - Ameren ML14352A4412014-12-18018 December 2014 Enclosure 7 - 10-Q Filed Period 6/30/2014 Ameren ML14352A4432014-12-18018 December 2014 Enclosure 10 - Articles of Incorporation Ameren Corporation Restated 10/17/1995 ULNRC-06157, Special Report 2014-04: Inoperability of a Seismic Instrument for Greater than 30 Days2014-11-14014 November 2014 Special Report 2014-04: Inoperability of a Seismic Instrument for Greater than 30 Days ML14290A5322014-10-29029 October 2014 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood -Causing Mechanism Reevaluation ULNRC-06139, Special Report 2014-01 - PAM Report Inoperability of a Post Accident Monitoring (PAM) Instrument2014-09-0202 September 2014 Special Report 2014-01 - PAM Report Inoperability of a Post Accident Monitoring (PAM) Instrument RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 2023-06-05
[Table view] |
Text
AmerenVE PO Box 620 Callaway Plant Fulton, MO 65251 August 2, 2006 Mr. Stuart A. Richards, Deputy Director Division of Inspection and Regional Support Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Mr. Richards:
ULNRC-05319 SAmerenl UE DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.
GROUNDWATER PROTECTION -
DATA COLLECTION QUESTIONNAIRE The nuclear industry, in conjunction with the Nuclear Energy Institute, has developed a questionnaire to facilitate the collection of groundwater data at commercial nuclear reactor sites. The objective of the questionnaire is to compile baseline information about the current status of site programs for monitoring and protecting groundwater and to share that information with NRC. The completed questionnaire for Callaway Plant is enclosed.
This submittal contains no new regulatory commitments.
Please contact Dave Shafer, Superintendent Licensing at 314-554-3104 or me at 573-676-8659 if you have questions about the enclosed information.
Sincerely, Mr D. , guo Manager, Regulatory Affairs DES/jdg Enclosure a subsidiary ofAmeren Corporation
ULNRC-05319 August 2, 2006 Page 2 cc: U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Mr. Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)
Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop O-7D1 Washington, DC 20555-2738 Missouri Public Service Commission Governor Office Building 200 Madison Street PO Box 360 Jefferson City, MO 65102-0360 Mr. Floyd Gilzow Deputy Director for Policy Missouri Department of Natural Resources PO Box 176 Jefferson City, MO 65102 Mr. Ralph Andersen Nuclear Energy Institute 1776 1 Street N.W., Suite 400 Washington, DC 20006-3708
ULNRC-05319 August 2, 2006 Page 3 bcc: C. D. Naslund A. C. Heflin K. D. Young G. A. Hughes D. E. Shafer (470)
S. L. Gallaghcr (100)
L. M. Belsky (NSRB)
K. A. Mills P. M. Bell A 160.0761 Certrec Corporation 4200 South Hulen, Suite 630 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards andlpublic disclosed).
Send the following without attachments:
Ms. Diane M. Hooper Mr. Dennis Buschbaum Supervisor, Licensing TXU Power WCNOC Comanche Peak SES P.O. Box 411 P.O. Box 1002 Burlington, KS 66839 Glen Rose, TX 76043 Mr. Scott Bauer Mr. Stan Ketelsen Regulatory Affairs Manager, Regulatory Services Palo Verde NGS Pacific Gas & Electric P.O. Box 52034, Mail Stop 104/5/536 Mail Station 7636 P.O. Box 56 Phoenix, AZ 85072-2034 Avila Beach, CA 93424 Mr. Scott Head Mr. John O'Neill Supervisor, Licensing Pillsbury Winthrop Shaw Pittman LLP South Texas Project NOC 2300 N. Street N.W.
Mail Code N5014 Washington, DC 20037 P.O. Box 289 Wadsworth, TX 77483
Enclosure ULNRC-05319 Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire Plant: Callaway Plant
- 1. Briefly describe the program and/or methods used for detection of leakage or spills from plant systems, structures, and components that have a potential for an inadvertent release of radioactivity from plant operations into groundwater.
Answer: There are 3 shallow groundwater monitoring wells and a groundwater sump located alongside the spent fuel storage building which are sampled quarterly and analyzed for tritium and principal gamma emitters. These wells are used to ensure there is no leakage from the spent fucl storage pool. There are no monitoring wells, programs, or methods for detection of leakage or spills from plant systems, structures, or components.
- 2. Briefly describe the program and/or methods for monitoring onsite groundwater for the presence of radioactivity released from plant operations.
Answer: There are 3 shallow groundwater monitoring wells and a groundwater sump located alongside the spent fuel storage building and three onsite deep wells which are sampled quarterly and analyzed for tritium and principal gamma emitters. There are no other monitoring wells, programs, or methods for monitoring onsite groundwater for the presence of radioactivity released from plant operations.
- 3. If applicable, briefly summarize any occurrences of inadvertent releases of radioactive liquids that had the potential to reach groundwater and have been documented in accordance with 10 CFR 50.75(g).
Answer:
(a) There have been six breaks in the discharge pipeline; however, until recently, only three instances were documented in the corrective action system as a 50.75(g) event. Action 32 of the Callaway Groundwater Protection Initiative (GPI) action plan (CAR 200602748) will document the three undocumented breaks in the plant corrective action system as 50.75(g) events.
(b) The shallow groundwater underneath the plant is contaminated with low levels of tritium, and is documented in the plant corrective action system as a 50.75(g) event. The contamination is due to a backflow eddy which carries the plant effluent discharge upriver to the plant intake. This has resulted in low levels of 3H contamination in the plant raw water systems. Underground leaks in the raw water systems have resulted in low levels of 3H groundwater contamination.
(c) The air release valves (ARV's) on the discharge pipeline operate with a small amount of blow- by which has resulted in contamination of the French drain in the manholes and low level tritium contamination of the groundwater in the vicinity of the manholes. Extensive discrete depth soil sampling and sampling of the free water around the manholes has been performed by an independent firm and the results are being analyzed by a registered geologist and a registered professional geotechnical engineer. Drinking water from neighbors with adjoining property has been analyzed and there was no detectable 3H or other radioactivity of plant origin. Bins were placed under the ARV's to catch the bypass water to prevent it from reaching the French drains. Work is continuing to fully characterize the extent of the contamination from the ARV's. This work is being tracked by Action 22 of the GPI action I
Enclosure ULNRC-05319 Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire plan. CAR 200604709 is tracking the development of a permanent solution to this issue.
This event is documented in the plant corrective action system as a 50.75(g) event.
Pursuant to the NEI Groundwater Protection Initiative, AmerenUE has recently provided a voluntary notification to the Missouri Department of Natural Resources and the USNRC Region 4 Office for each of the above events. The Missouri DNR and the USNRC Region 4 Office have been and will continue to be updated as new information becomes available.
These events have also been discussed informally with local county officials.
- 4. If applicable, briefly summarize the circumstances associated with any onsite or offsite groundwater monitoring result indicating a concentration in groundwater of radioactivity released from plant operations that exceeds the maximum contaminant level (MCL) established by the USEPA for drinking water.
Answer: There have been no offsite groundwater monitoring samples that exceed the USEPA MCL or the reporting values provided by the USNRC Branch Technical Position.
One onsite sample of groundwater taken in the area of manhole 6B shows a 3H concentration of 25,863 pCi/L. Efforts are continuing under Action 22 of the Callaway GPI action plan to determine the extent of the contamination of the area around the manholes with ARV's.
- 5. Briefly describe any remediation efforts undertaken or planned to reduce or eliminate levels of radioactivity resulting from plant operations in soil or groundwater onsite or offsite.
Answer: There have been no remediation efforts undertaken to date. Efforts are still underway to characterize the plant site and determine the extent of any identified contamination. Remediation will be considered as part of the characterization efforts.
2