|
---|
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 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 ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24262A1992024-05-29029 May 2024 L-PI-24-018 PINGP 75 Day Letter ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 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 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 ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance 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 ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction 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) 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] |
Text
Protecting, maintaining and improving the health ofall Minnesotans October 27, 2014 Allan Barker, Regional State Liaison Officer US Nuclear Regulatory Commission 2443 Warrenville Road Lisle, IL 60532-4352
Dear Mr. Barker:
Subject:
Request to Accompany Nuclear Regulatory Commission (NRC) Inspectors at Minnesota Nuclear Power Plants The Minnesota Department of Health (MDH) requests authorization for a staff member to accompany an NRC Region Ill inspector at Prairie Island Nuclear Generating Power Plant during a health physics inspection.
Based upon the inspection schedule I received, we are requesting Tyler Kruse to accompany inspections ofthe Health Physics Outage inspection November 3-6, 2014; specifically November 4, 2014.
MDH acknowledges that Tyler Kruse, assigned to the Radioactive Materials Unit, must be escorted while at the plant. Attached are signed copies of the Protocol Agreement for State Observation of NRC Inspections.
If you have any questions concerning this matter, please contact Tyler Kruse at (651) 201-4518, or me at (651) 201-4522.
Sincerely, Sherrie Flaherty, MHP, DC, Supervisor Minnesota Department of Health Radioactive Materials Unit PO Box 64975 St. Paul, MN 55164-0975 Attachments cc: James Lynch, Regional State Agreement Officer Aggie Leitheiser, State Liaison Officer RECEIVED OCT 31 2014 General Information: 651-201-5000
- www.health.state.mn.us An equal opportunity employer
Protocol Agreement for State Observation of NRC Inspections NRC Protocol:
- The Regional State Liaison Officer (RSLO} will normally be the lead individual responsible for tracking requests for State observation, assuring consistency regarding these requests, and for advising the Regional Administrator on the dispositions of these requests. The appropriate technical representative or Division Director will communicate with the State on specific issues concerning the inspection(s).
- Requests for observations of Headquarters-based inspections will also be coordinated through the RSLO. Headquarters-based inspections should be referred through the RSLO to a technical representative designated by the Region.
- NRC will process written requests to the Regional Administrator through the State Liaison Officer (SLO). Requests should identify the type of inspection activity and facility the State wishes to observe.
- Limits on scope and duration of the observation period may be imposed if, in the view of the Regional Administrator, they compromise the efficiency or effectiveness of the inspection. Regions should use their discretion as to which, if any, inspections will be excluded from observations.
- State will be informed they must not release information concerning the time and purpose of unannounced inspections.
- The Region will make it clear to the licensee that the State views are not necessarily endorsed by NRC. The Region will also make it clear that only NRC has regulatory authority for inspection findings and enforcement actions regarding radiological health and safety.
State Protocol:
- A State will make advance arrangements with the licensee for site access training and badging (subject to fitness for duty requirements}, prior to the actual inspection.
- Normally, no more than one individual will be allowed to observe an NRC inspection.
- The State will be responsible for determining the technical and professional competence of its representative who accompanies NRC inspectors.
- An observer's communication with the licensee will be through the appropriate NRC team member, usually the senior resident inspector or the team leader.
- When informed of an unannounced inspection, a State must not release information concerning its time and purpose.
- An observer will remain in the company of NRC personnel throughout the course of the inspection.
- State observation may be terminated by the NRC if the observer's conduct interferes with a fair and orderly inspection.
- An observer will not be provided with proprietary or safeguards information.
Observers will not remove any material from the site without NRC or licensee approval.
- The State observer, in accompanying the NRC inspectors, does so at his or her own risk. NRC will not be responsible for injuries or exposures to harmful substances which may occur to the accompanying individual during the inspection and will assume no liability for any incidents associated with the accompaniment.
- The State observer will be expected to adhere to the same conduct as NRC inspectors during an inspection accompaniment.
- If the State observer notices any apparent non-conformance with safety or regulatory requirements during the inspections, he/she will make those observations promptly known to the NRC team leader or lead inspector. Likewise, when overall conclusions or views of the State observer are substantially different from those of the NRC inspectors, the State will advise the team leader or lead inspector and forward those views, in writing, to the NRC Region. This will allow NRC to take any necessary regulatory actions.
- Under no circumstances should State communications regarding these inspections be released to the public or the licensee before they are reviewed by the NRC and the inspection report is issued. State communications may be made publicly available, similar to NRC inspection reports, after they have been transmitted to and reviewed by NRC.
Adjacent State Protocol:
- An adjacent State is a State within the plume exposure pathway emergency planning zone (EPZ) (within approximately a 10-mile radius) of an NRC-licensed facility located in another State. A host State is a State in which an NRC-licensed facility is located. An adjacent State may request permission to observe NRC inspections at an NRC-licensed facility in a host State.
- The adjacent State SLO must communicate his/her request for observation to the Regional Administrator for the region in which the facility is located.
- The adjacent State SLO must also communicate his/her request to the host State SLO so that each State is aware of the other's intentions.
- If a host State and an adjacent State request observation of the same inspection, the Regional Administrator will make the final determination on the number of State observers who may attend the inspection. If there is a need to limit the number of observers, the Regional Administrator will routinely give preference to the host State observers.
- Adjacent State observers will abide by the same protocol in all aspects of the inspection as host States under this agreement.
10 I
&~I12A) I=(
Date