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| | issue date = 10/12/2009 | | | issue date = 10/12/2009 |
| | title = Required 30-Day Offsite Dose Calculation Manual Report for the Monticello Nuclear Generating Plant | | | title = Required 30-Day Offsite Dose Calculation Manual Report for the Monticello Nuclear Generating Plant |
| | author name = O'Connor T J | | | author name = O'Connor T |
| | author affiliation = Northern States Power Co | | | author affiliation = Northern States Power Co |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:XCceI Energy" October 12, 2009 L-MT-09-096 MNGP TS 5.5.1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 Renewed License No.: DPR-22 Required 30-Day Offsite Dose Calculation Manual Report for the Monticello Nuclear Generating Plant Pursuant to and in accordance with the requirements of Monticello Technical Specification 5.5.1, the Northern States Power Company, a Minnesota corporation (NSPM) is providing the NRC with a 30-day special report as required by the NEI Enhanced Groundwater Protection Initiative. | | {{#Wiki_filter:XCceI Energy" October 12, 2009 L-MT-09-096 MNGP TS 5.5.1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 Renewed License No.: DPR-22 Required 30-Day Offsite Dose Calculation Manual Report for the Monticello Nuclear Generating Plant Pursuant to and in accordance with the requirements of Monticello Technical Specification 5.5.1, the Northern States Power Company, a Minnesota corporation (NSPM) is providing the NRC with a 30-day special report as required by the NEI Enhanced Groundwater Protection Initiative. |
| Summary of Commitm 7 nts: This *1ter nAes npl/ew commitments or changes any existing commitments. | | Summary of Commitm7 nts: |
| Site -c 6 President, Monticello Nuclear Generating Plant No ryemn States Power Company -Minnesota Enclosure 1 cc: Regional Administrator Region Ill, USNRC Project Manager, Monticello, USNRC Sr. Resident Inspector, Monticello, USNRC ADO q 2807 West County Road 75 | | This *1ter nAes npl/ew commitments or changes any existing commitments. |
| * Monticello, Minnesota 55362-9637 Telephone: | | Site -c 6 President, Monticello Nuclear Generating Plant No ryemn States Power Company - Minnesota cc: Regional Administrator Region Ill, USNRC Project Manager, Monticello, USNRC Sr. Resident Inspector, Monticello, USNRC ADO q 2807 West County Road 75 |
| 763.295.5151 9 Fax: 763.295.1454 N PL, /ý' | | * Monticello, Minnesota 55362-9637 Telephone: 763.295.5151 9 Fax: 763.295.1454 N /ý' |
| | PL, |
| | |
| i This communication is being submitted as part of the NEI Enhanced Ground Water Protection Initiative. | | i This communication is being submitted as part of the NEI Enhanced Ground Water Protection Initiative. |
| MNGP has been investigating a leak of radioactive water for the last several weeks, after testing showed elevated levels of tritium in water leaking into the reactor building.A site troubleshooting team was established, and three new monitoring wells to help develop source/plume characterization were installed. | | MNGP has been investigating a leak of radioactive water for the last several weeks, after testing showed elevated levels of tritium in water leaking into the reactor building. |
| Samples taken on September 8, 2009 from the two new monitoring wells MW-1 0 and MW-1 1 drilled near the condensate storage tanks on plant property showed tritium levels of 1165 picocuries/liter and 290 picocuries/liter respectively. | | A site troubleshooting team was established, and three new monitoring wells to help develop source/plume characterization were installed. Samples taken on September 8, 2009 from the two new monitoring wells MW-1 0 and MW-1 1 drilled near the condensate storage tanks on plant property showed tritium levels of 1165 picocuries/liter and 290 picocuries/liter respectively. A sample taken on September 11, 2009 from the third new well MW-09, near the Reactor Building, showed tritium levels of 21,727 picocuries/liter which is above the Environmental Protection Agency drinking water standard for tritium of 20,000 picocuries/liter. |
| A sample taken on September 11, 2009 from the third new well MW-09, near the Reactor Building, showed tritium levels of 21,727 picocuries/liter which is above the Environmental Protection Agency drinking water standard for tritium of 20,000 picocuries/liter. | |
| A subsequent sample taken from MW-09 on September 14, 2009 showed a level of 5,826 picocuries/liter. | | A subsequent sample taken from MW-09 on September 14, 2009 showed a level of 5,826 picocuries/liter. |
| The station will continue to investigate including the installation of temporary monitoring wells to aid in the identification of the plume and source of tritium.There have not been any significant levels of tritium detected in any of the other permanent plant monitoring wells.An estimate of potential or bounding annual dose to a member of the public would be approximately 1.01 mrem. This assumes that an individual consumes 730 liters (ODCM) and gets 64 millirem per millicurie of tritium ingested (NCRP Report 30) of water containing 21,727 picocuries/liter over the course of a year.No detectable tritium was found in any onsite or offsite drinking water wells monitored by the REMP Program.This issue poses no immediate safety concerns for plant employees or the general public.}} | | The station will continue to investigate including the installation of temporary monitoring wells to aid in the identification of the plume and source of tritium. |
| | There have not been any significant levels of tritium detected in any of the other permanent plant monitoring wells. |
| | An estimate of potential or bounding annual dose to a member of the public would be approximately 1.01 mrem. This assumes that an individual consumes 730 liters (ODCM) and gets 64 millirem per millicurie of tritium ingested (NCRP Report 30) of water containing 21,727 picocuries/liter over the course of a year. |
| | No detectable tritium was found in any onsite or offsite drinking water wells monitored by the REMP Program. |
| | This issue poses no immediate safety concerns for plant employees or the general public.}} |
|
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Category:Letter type:L
MONTHYEARL-MT-24-028, Response to RCI for RR-017 ISI Impracticality2024-08-28028 August 2024 Response to RCI for RR-017 ISI Impracticality L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations L-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) L-MT-24-017, Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-01602024-06-0404 June 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-0160 L-MT-24-015, Response to Request for Additional Information - Alternative Request VR-09 for OMN-172024-05-16016 May 2024 Response to Request for Additional Information - Alternative Request VR-09 for OMN-17 L-MT-24-013, 2023 Annual Radiological Environmental Operating Report2024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report L-MT-24-016, 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2024-05-0808 May 2024 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-24-012, Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component2024-04-25025 April 2024 Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component L-MT-24-002, Submittal of Revision 41 to the Updated Safety Analysis Report2024-04-17017 April 2024 Submittal of Revision 41 to the Updated Safety Analysis Report L-MT-24-004, Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP)2024-04-17017 April 2024 Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP) L-MT-24-006, Subsequent License Renewal Application Annual Update 1 and Supplement 92024-02-29029 February 2024 Subsequent License Renewal Application Annual Update 1 and Supplement 9 L-MT-24-007, Response to NRC Request for Additional Information on Proposed Inservice Inspection Alternative RR-002 for the Sixth Ten-Year ISI Interval2024-02-15015 February 2024 Response to NRC Request for Additional Information on Proposed Inservice Inspection Alternative RR-002 for the Sixth Ten-Year ISI Interval L-MT-24-001, 10 CFR 50.55a Request RR-017 - Inservice Inspection (ISI) Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval2024-01-30030 January 2024 10 CFR 50.55a Request RR-017 - Inservice Inspection (ISI) Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-053, Condition Prohibited by Technical Specifications Due to Inoperable Main Steam Line Low Pressure Isolation Switch2023-12-0404 December 2023 Condition Prohibited by Technical Specifications Due to Inoperable Main Steam Line Low Pressure Isolation Switch L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023 Subsequent License Renewal Application Supplement 2 L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023 Submittal of 2022 Annual Radioactive Effluent Release Report L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023 Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32 L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2023-04-18018 April 2023 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023 Subsequent License Renewal Application Supplement 1 L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023 Core Operating Limits Report (COLR) for Cycle 31, Revision 3 L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 22023-03-17017 March 2023 Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2 L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)2023-02-0707 February 2023 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003) L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program2023-01-23023 January 2023 CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023 Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088) L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022 Industry Groundwater Protection Initiative Special Report L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative2022-12-15015 December 2022 L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462022-12-13013 December 2022 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022 Update to the Monticello Technical Specification Bases L-MT-22-047, Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-11-10010 November 2022 Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval L-MT-22-045, Letter Submitting Post-Exam Package2022-11-0404 November 2022 Letter Submitting Post-Exam Package 2024-08-28
[Table view] |
Text
XCceI Energy" October 12, 2009 L-MT-09-096 MNGP TS 5.5.1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 Renewed License No.: DPR-22 Required 30-Day Offsite Dose Calculation Manual Report for the Monticello Nuclear Generating Plant Pursuant to and in accordance with the requirements of Monticello Technical Specification 5.5.1, the Northern States Power Company, a Minnesota corporation (NSPM) is providing the NRC with a 30-day special report as required by the NEI Enhanced Groundwater Protection Initiative.
Summary of Commitm7 nts:
This *1ter nAes npl/ew commitments or changes any existing commitments.
Site -c 6 President, Monticello Nuclear Generating Plant No ryemn States Power Company - Minnesota cc: Regional Administrator Region Ill, USNRC Project Manager, Monticello, USNRC Sr. Resident Inspector, Monticello, USNRC ADO q 2807 West County Road 75
- Monticello, Minnesota 55362-9637 Telephone: 763.295.5151 9 Fax: 763.295.1454 N /ý'
PL,
i This communication is being submitted as part of the NEI Enhanced Ground Water Protection Initiative.
MNGP has been investigating a leak of radioactive water for the last several weeks, after testing showed elevated levels of tritium in water leaking into the reactor building.
A site troubleshooting team was established, and three new monitoring wells to help develop source/plume characterization were installed. Samples taken on September 8, 2009 from the two new monitoring wells MW-1 0 and MW-1 1 drilled near the condensate storage tanks on plant property showed tritium levels of 1165 picocuries/liter and 290 picocuries/liter respectively. A sample taken on September 11, 2009 from the third new well MW-09, near the Reactor Building, showed tritium levels of 21,727 picocuries/liter which is above the Environmental Protection Agency drinking water standard for tritium of 20,000 picocuries/liter.
A subsequent sample taken from MW-09 on September 14, 2009 showed a level of 5,826 picocuries/liter.
The station will continue to investigate including the installation of temporary monitoring wells to aid in the identification of the plume and source of tritium.
There have not been any significant levels of tritium detected in any of the other permanent plant monitoring wells.
An estimate of potential or bounding annual dose to a member of the public would be approximately 1.01 mrem. This assumes that an individual consumes 730 liters (ODCM) and gets 64 millirem per millicurie of tritium ingested (NCRP Report 30) of water containing 21,727 picocuries/liter over the course of a year.
No detectable tritium was found in any onsite or offsite drinking water wells monitored by the REMP Program.
This issue poses no immediate safety concerns for plant employees or the general public.