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Category:Letter
MONTHYEARML24298A0552024-10-30030 October 2024 Response to Alternative RR-10, Auxiliary Feedwater Valve Testing IR 05000282/20244032024-10-25025 October 2024 – Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403 05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-10-22022 October 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies L-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML24277A1012024-10-0303 October 2024 Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software ML24221A3622024-09-27027 September 2024 Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3 ML24241A1682024-09-23023 September 2024 Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation 05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies IR 05000282/20243012024-09-13013 September 2024 NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301 IR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter IR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24158A5912024-06-0606 June 2024 CFR 50.46 LOCA Annual Report L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections 05000306/LER-2024-001-01, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-05-31031 May 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML24262A1992024-05-29029 May 2024 L-PI-24-018 PINGP 75 Day Letter L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24128A2572024-05-16016 May 2024 ISFSI A13 Acceptance Letter IR 05000282/20240012024-05-15015 May 2024 Integrated Inspection Report 05000282/2024001 and 05000306/2024001 ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent Report ML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML24128A0882024-04-30030 April 2024 Submittal of Updated Safety Analysis Report (Usar), Revision 38 ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance 05000306/LER-2024-001, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-04-29029 April 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 ML24100A8042024-04-24024 April 2024 – Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing ML24114A0882024-04-23023 April 2024 Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP) ML24113A1182024-04-12012 April 2024 NRC Letter Re NRC Office of Investigations Report No. 3-2023-004 ML24100A1212024-04-0909 April 2024 Submittal of Revised Pressure and Temperature Limits Report L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction Report ML24089A2402024-03-29029 March 2024 Guarantee of Payment of Deferred Premiums ML24060A1232024-03-27027 March 2024 To Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds 05000282/LER-2023-001-01, Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables2024-03-21021 March 2024 Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables ML24262A1512024-03-15015 March 2024 L-PI-24-011 150 Day Letter 2024 PINGP ILT NRC Exam ML24010A0582024-03-0505 March 2024 Amendment No. 12 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) 2024-09-27
[Table view] Category:Emergency Preparedness-Emergency Plan and Post Exercise Evaluation (FEMA Evaluation)
MONTHYEARML18302A1272018-10-0505 October 2018 Final After-Action Report/Improvement Plan for the Radiological Emergency Preparedness Program, July 17-18, 2018 ML16223A7682016-07-28028 July 2016 Enclosed Is the Final After Action Report/Improvement Plan for the June 28, 2016, Prairie Island Nuclear Generating Plant Radiological Emergency Preparedness Full Participation Plume Exposure Pathway Exercise ML13301A0812013-10-15015 October 2013 After Action Report/Improvement Plan ML1036100432010-12-13013 December 2010 FEMA, Submittal of Final Report for the August 24, 2010 Radiological Emergency Preparedness (REP) Full Participation Plume Exercise for the Prairie Island Nuclear Generating Plant ML1035501302010-12-13013 December 2010 FEMA, Submittal of Final Report for the August 24, 2010, Radiological Emergency Preparedness (REP) Full Participation Plume Exposure Pathway Exercise for the Prairie Island Nuclear Generating Plant (PINGP) ML0436402632004-09-30030 September 2004 FEMA Final Exercise Report - Prairie Island Nuclear Generating Plant, Report Dated September 30, 2004 ML0428005662004-09-30030 September 2004 FEMA 2 - Final Report for the Radiological Emergency Preparedness (REP) Plume Exercise Conducted on June 16, 2004, for the Prairie Island Nuclear Generating Plant ML0226708272002-08-14014 August 2002 Final Report for Radiological Emergency Preparedness Plume Pathway Exercise Conducted on May 15, 2002 for Prairie Island Nuclear Generating Plant ML0102301442001-01-0808 January 2001 Ltr 1/8/01 FEMA Re Prairie Island 9/13/00 Exercise 2018-10-05
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U.S. Department of Homeland Security Region V 536 South Clark Street, Floor 6 Chicago, IL 60605 DEC 13 2010 Mr. Mark Satorius Regional Administrator U. S. Nuclear Regulatory Commission Region I11 2443 Warrenville Road Lisle, Illinois 60542-435 1
Dear Mr. Satorius:
Enclosed is one copy of the Final Report for the August 24,201 0, Radiological Emergency Preparedness (REP) Full Participation Plume Exposure Pathway Exercise for the Prairie Island Nuclear Generating Plant (PINGP). The State of Minnesota, Dakota and Goodhue Counties, the State of Wisconsin and Pierce County, and the utility owner/operator, Exelon Nuclear, participated in this exercise.
No Deficiencies were identified for the State of Minnesota or for Dakota and Goodhue Counties during this exercise.
No Areas Requiring Corrective Action (ARCAs) were identified for the State 01 Minnesota or the Counties of Goodhue and Dakota during this exercise.
There was one Planning Issue identified for the State of Minnesota and one Planning Issue identified for Dakota County. One ARCA for the State of Minnesota fiom a prior exercise was successfully re-demonstrated.
The ARCA that was resolved for the State of Minnesota was identified under Criterion 5.b.l - OROs provide accurate emergency information and instructions to the public. The Planning Issue for the State of Minnesota was identified under Equipment and Supplies to Support Operations, Criterion 1 .e. 1 - Equipment, Maps, displays, dosimetry, potassium iodide (KI), and other supplies are sufficient to support emergency operations, whereby the Emergency Medical Crew were provided a 0-200mR Direct-Reading Dosimeter (DRD). This DRD is not able to read turn-back values of 1 R or total exposure limits of 3 R in accordance with current State of Minnesota Plans and Procedures. The Planning Issue for Dakota County was identified under Equipment and Supplies to Support Operations, Criterion 1 .e. 1 - Equipment, Maps, displays, dosimetry, potassium iodide (KI), and other supplies are sufficient to support emergency operations, whereby the Radiological Officer had 26 (Model 622,O-20 R) DRDs, 13 of which were expired requiring recertification in 2008.
Satorius Page # 2 There were also three DRDs that had stickers marked " not checked by the RO upon delivery, or prior to being Workers. on them. The inventory of DRDs was for distribution to Emergency No Deficiencies were identified for the State of Wisconl There was one ARCA identified for the State of Wiscon exercise that was successfully re-demonstrated. There v of Wisconsin. One ARCA was not demonstrated from 2 09- 1 c 1 -A-0 1) will be demonstrated during the Point Bel accordance with the extent-of-play agreement.
No ARC this exercise.
The ARCA that was resolved for the State of Wisconsin provide accurate emergency information and instruction The ARCA for the State of Wisconsin was identified un Control, Criterion 3 .a. 1 - The Offsite Response Organiza procedures and managed radiological exposure to emerg and procedures, whereby emergency workers were not t they know what their correct exposure limits were when The Planning Issue for the State of Wisconsin was ident making process involving consideration of appropriate f make protective action decisions for the general public ( KI, if OR0 policy), whereby various State of Wisconsin Pierce County with protective action recommendations 1 A detailed discussion of these issues can be found in Par Based on the results of the August 24,2010, exercise, th plans and preparedness for the States of Minnesota and
' site-specific to the PINGP, can be implemented and are , appropriate measures can be taken offsite to protect the 1 a radiological emergency at the site. Therefore, the Title 44 CFR, Part 350, approval of the 0: and preparedness for the States of Minnesota and Wisco December 4, 198 I, remains in effect. n or for Pierce County during this exercise. n. There was one ARCA from a previous LS one Planning Issue identified for the State xevious exercise. This ARCA (number 33- h REP Exercise in October 20 10, in LS were identified for Pierce County during vas identified under Criterion 5.b. 1 - OROs to the public. :r Implementation of Emergency Worker ons (ORO) issue appropriate dosimetry and ncy workers in accordance with the plans iefed of their correct exposure limits nor did hey were interviewed.
ied under Criterion 2.b.2 - A decision-
- tors and necessary coordination is used to icluding the recommendation for the use of &iff used inaccurate procedures to provide ised on their "home rule" status. IV of the Final Report.
offsite radiological emergency response 'isconsin and affected local jurisdictions, lequate to provide reasonable assurance that
- alth and safety of the public in the event of site radiological emergency response plans sin site-specific to the PINGP, granted on I Satorius Page ## 3 Copies of this report have been provided to the DHSFI Commission Headquarters Document Control Desk an( If you have any questions, please contact William E. K Committee, DHSiFEMA, Region V, at (3 12) 408-5575 Sir & Re Enclosure (1) viA National Office, Nuclear Regulatory the States of Minnesota and Wisconsin. .g, Chairman, Regional Assistance erely, rew Velasquez ional Administrator