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Category:Emergency Preparedness-Emergency Plan Implementing Procedures
MONTHYEARML21139A3112021-05-19019 May 2021 Independent Spent Fuel Storage Installation (ISFSI) - Revised Emergency Plan (E-Plan), Emergency Plan Implementing Procedures (EPIP) and Rec/Rpss Handbook ML21139A3122021-05-19019 May 2021 Independent Spent Fuel Storage Installation (ISFSI) - Summary of Changes - 10 CFR 50.54(q)(5) ML19246A3512019-09-0303 September 2019 Independent Spent Fuel Storage Installation, and Monticello - Offsite Nuclear Emergency Plan Revision ML19014A0392019-01-14014 January 2019 Independent Spent Fuel Storage Installation, and Monticello, Offsite Nuclear Emergency Plan Revision L-PI-18-016, Enclosure 1, Form 1576 Emergency Action Level (EAL) Matrix, Revision 10 and Emergency Action Level Technical Bases, Revision 132018-04-17017 April 2018 Enclosure 1, Form 1576 Emergency Action Level (EAL) Matrix, Revision 10 and Emergency Action Level Technical Bases, Revision 13 ML17138A2562017-03-30030 March 2017 Revised Emergency Plan Implementing Procedures ML17138A2552017-03-30030 March 2017 Submittal of Revised Emergency Plan and Emergency Plan Implementing Procedures L-PI-15-108, Revised Emergency Plan Implementing Procedures (Epips), Including Revision 22 to F3-12, Revision 15 to F3-21, Revision 27 to F3-9, Revision 13 to F3-23-1CU-I, and Revision 14 to F3-23-2C U-22016-01-11011 January 2016 Revised Emergency Plan Implementing Procedures (Epips), Including Revision 22 to F3-12, Revision 15 to F3-21, Revision 27 to F3-9, Revision 13 to F3-23-1CU-I, and Revision 14 to F3-23-2C U-2 ML12320A0042012-11-0606 November 2012 Radiological Emergency Preparedness (Rep), Full Participation Plume Exposure Pathway Exercise L-PI-04-053, Emergency Plan Implementing Procedures (EPIP)2004-04-21021 April 2004 Emergency Plan Implementing Procedures (EPIP) ML0412504762004-04-20020 April 2004 Revisions to Controlled Documents, Emergency Plan Implementing Procedures ML0409204462004-03-25025 March 2004 Prairie, Revision 34 to Emergency Plan Implementing Procedure F3-2 L-PI-04-028, Revised Emergency Plan Implementing Procedures2004-03-11011 March 2004 Revised Emergency Plan Implementing Procedures L-PI-04-022, Revised EPIP Table of Contents, Revision 19 to F3-9, Emergency Evacuation, and Revision 0 to F3-17.2, Long Term Core Cooling.2004-02-20020 February 2004 Revised EPIP Table of Contents, Revision 19 to F3-9, Emergency Evacuation, and Revision 0 to F3-17.2, Long Term Core Cooling. L-PI-03-117, Revised EPIP Table of Contents and Revision 20 to F3-1, Onsite Emergency Organization, and Revision 20 to F3-10, Personnel Accountability.2003-12-17017 December 2003 Revised EPIP Table of Contents and Revision 20 to F3-1, Onsite Emergency Organization, and Revision 20 to F3-10, Personnel Accountability. L-PI-03-108, Revised EPIPs Table of Contents, Rev. 23 to F3-2, Classification of Emergencies, and Rev. 23 to F3-15, Responsibilities of the Radiation Survey Teams During a Radioactive Airborne Release.2003-11-21021 November 2003 Revised EPIPs Table of Contents, Rev. 23 to F3-2, Classification of Emergencies, and Rev. 23 to F3-15, Responsibilities of the Radiation Survey Teams During a Radioactive Airborne Release. L-PI-03-092, Revised Emergency Plan Implementing Procedures2003-10-0101 October 2003 Revised Emergency Plan Implementing Procedures L-PI-03-041, Emergency Plan Implementing Procedures2003-04-14014 April 2003 Emergency Plan Implementing Procedures L-PI-03-033, Emergency Plan Implementing Procedures2003-03-13013 March 2003 Emergency Plan Implementing Procedures L-PI-03-018, Emergency Plan Implementing Procedures2003-02-27027 February 2003 Emergency Plan Implementing Procedures L-PI-03-014, Emergency Plan Implementing Procedures2003-02-18018 February 2003 Emergency Plan Implementing Procedures ML0236105592002-12-19019 December 2002 Emergency Plan Implementing Procedures, Including Rev 18 to F3-9, Emergency Evacuation, Rev 20 to F3-8, Recommendations for Offsite Protective Actions & Rev 21 to F3-5, Emergency Notifications. ML0229605502002-10-16016 October 2002 Emergency Response Plan Implementing Procedure F3-13.5, Rev 5, Alternate Meteorological Data. ML0229605452002-10-14014 October 2002 Emergency Response Plan Implementing Procedures for Prairie Island Nuclear Generating Plant ML0228305292002-09-26026 September 2002 Offsite Nuclear Emergency Plan Implementing Procedures ML0228000952002-09-23023 September 2002 Emergency Plan Implementing Procedures TOC, F3-2, Rev 30, Classification of Emergencies, F3-31, Rev 6, Response to Security Related Threats & F3-23.1, Rev 12, Emergency Hotcell Procedure ML0228000312002-09-23023 September 2002 Emergency Plan Implementing Procedures TOC, & F3-2, Rev.30, Classification of Emergencies ML0224001802002-08-21021 August 2002 DAEC Emergency Planning Department Procedure Entire EAL Basis Document (Table of Contents Rev) (Copy 91) ML0222803542002-08-0808 August 2002 DAEC Emergency Planning Department Procedure Transmittal Acknowledgment Memo ML0221902822002-07-29029 July 2002 Revised Epips, Including Revised TOC, Rev. 7 to F3-19, Rev. 7 to 3-26.2, Rev. 10 to F3-18 & Temporary Change F3-2 ML0214404292002-05-0606 May 2002 Emergency Plan Implementing Procedures - F3 ML0211905362002-04-17017 April 2002 Emergency Plan Implementing Procedures - F3 ML0211902012002-04-17017 April 2002 Transmittal of Prairie Island Nuclear Generating Plant EOF Emergency Plan Implementing Procedures TOC & F8-9 (Revision 7) ML0214003472002-02-0404 February 2002 Emergency Plan Implementing Procedures - F3 2021-05-19
[Table view] Category:Letter
MONTHYEARIR 05000282/20240032024-11-13013 November 2024 Integrated Inspection Report 05000282/2024003, 05000306/2024003 & 07200010/2024001 ML24310A1682024-11-0505 November 2024 Core Operating Limits Report (COLR) for Cycle 34, Revision 0 ML24298A0552024-10-30030 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 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 2024-09-27
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Committed to Nuclear Ex ce Mano K. Nazar Site Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Dr. East a Welch MN 55089 October 14, 2002 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 Docket Nos. 50-306 License Nos. DPR-60 Prairie Island Emergency Plan Implementing Procedures - F3 Emergency Response Plan Implementing Procedures Furnished with this letter is the Prairie Island Nuclear Generating Plant Emergency Plan Implementing Procedures Temporary Change Addition. This addition includes the following procedures:
INDEXES:
REVISIONS:
DELETIONS:
TEMPORARY CHANGE ADDITIONS:
2002 1580 F3-2 Classification of Emergencies INSTRUCTIONS:
Please post changes in your copy of the Prairie Island Nuclear Generating Plant Emergency Plan Implementing Procedures. Procedures, which have been superseded or deleted, should be destroyed.
Please sign and return the acknowledgment of this update to Bruce Loesch, Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089. If you have any questions, please contact Mel Agen at 651-388-1121 Extension 4240.
Mano K. Nazar Site Vice Presid t Prairie Island Nlear Generating Plant 40+5
c: USNRC - Steve Orth, Region m (2 copies)
NRC Resident Inspector (w/o attachment)
M Agen (w/o attachment)
Records Management (Doc Control Copy) (w/o attachment)
NL File (w/o attachment)
Mfst Num: 2002 - 0792 Date : 10/08/02 FROM : Bruce Loesch/Mary Gadient Loc : Prairie Island TO : UNDERWOOD, BETTY J Copy Num: 515 Holder : US NRC DOC CONTROL DESK SUBJECT : Revisions to CONTROLLED DOCUMENTS Procedure # Rev Title Temporary Change Additions:
2002 1580 F3-2 CLASSIFICATIONS OF EMERGENCIES UPDATING INSTRUCTIONS material in your Prairie Island Controlled Manual or File. Remove Place this revised or cancelled material and recycle it. Sign and date this letter in the space provided below within ten working days and return to Bruce Prairie Island Nuclear Plant, 1717 Wakonade Drive E.,
Loesch or Mary Gadient, Welch, MN 55089.
any Contact Bruce Loesch (ext 4664) or Mary Gadient (ext 4478) if you have questions.
Received the material stated above and complied with the updating instructions Date
PINGP 1300, Rev. 5 TCN #
- Retention: 6 years Effective Date:
Document Type: 1.190 Expiration Date:
TEMPORARY CHANGE NOTICE Page 1 of (5AWI 1.5.10)
CHANGE REQUEST Procedure#: , " Rev: ge) Project ID #:
WO #:
Title:
C/lac5.5_1 X, CaXI45 0 ~ ýL4ae Description of Change: CiEALdtl1_6 Af.
(e.g. page #, step #, te)a eiXe 1144Us7Se, 16-e~ stvd summary/reason) As/ e54e 2a4-0i C-11fl%/ e. all INITIAL REVIEWS %,/
A. Is this a change in intent? Yes El No JEL If No, go to II B
- 1. OC Review Initial/Date (if procedure is OC reviewed/critical WO)"
- 2. Procedure Approver (Work Supv for WO):
B. 10 CFR 50.59 Review
- 1. Is this change or procedure exempt from 10CFR 50.59 screening per 5AWI 3.3.5, App. A or B? Yes J< No [I If Yes, go to II.C
- 2. Complete 50 59 screening per 5AWI 3.3.5/PINGP 1229. Screening/Evaluation #
C. Does this change affect Special Reviews? Yes El No [' If Yes, document Special Review(s) in CHAMPS D. Does this change affect plant operation or Tech Specs? Yes El No [ If Yes and work is in progress, SS notified by __ (initial)
E. Do controlled copies need to be updated? Yes [ No El If Yes, attach marked-up procedure pages to white copy F. All master/working copies updated? Yes El NA [
G. Is training on temporary change needed? Yes
- No El If Yes, PINGP 1268 or PINGP 1224 (Ops Only) issued M. REVIEW AND APPROVAL Reviewer: Date: / "'- -o.Z Apvr(Unit Management Staff)
Approvers Date: *. O 2 ,"-
"O' (Unit Management S f; SRO for OC reviewed procedures/cntical WO)
Forward white copy to Procedure Control IV. POST REVIEWS (required for OC reviewed procedures/critical WO, leave blank if reviewed/approved in II.A)
OC Review Initial/Date: Procedure Approver. Date:
V. TEMPORARY CHANGE DELETION (leave blank if controlled copies not updated, refer to IME)
A. Reviewer. Date:
(Unit Management Staff)
B. Approver: Date: ________
(Unit Management Staff; SRO for OC reviewed procedures/critical WO)
White Copy - Procedure Control Yellow Copy - Attach to procedure Form 175645 (4-02)
Z .6 2 Condition 11: Fires F pr (EAL Ref Manual 11A)
FIRE: is combustion characterized by heat and light (flame). Sources ofI smoke such as slipping drive belts or overheated electrical equipment do not constitute fires. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.
Notification of fire or fire detection alarm in the Control RoomI Notification of Unusual Event Fire confirmed within the Reactor Bldg.,
Auxiliary Bldg., Turbine Bldg., Service Bldg., Rad Waste Bldg., Plant Screen House, D5/D6 Bldg., Cooling Tower Equip.
House, Transformers, or on the surface of a loaded spent fuel cask in the ISFSI Area Fire not extinguished within 10-minutes of I > 10 minutes alarm or notification I F