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Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML22047A0572022-02-16016 February 2022
Supplement to License Transfer Application Related to Decommissioning Quality Assurance Program
ML21131A1412021-05-10010 May 2021
Application for Order Approving Transfer of Control of KPS License and Conforming License Amendments
ML19130A1952019-05-0808 May 2019
Letter - FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition
ML16323A1932016-11-16016 November 2016
Resubmittal of Request for Approval of Security Plan
ML16216A1872016-07-28028 July 2016
License Amendment Request 263; Load Drop Analysis for Spent Fuel Cask Handling Operations
ML15261A2382015-09-14014 September 2015
License Amendment Request 259, ISFSI-Only Emergency Plan and Emergency Action Level Scheme
ML15261A2362015-09-14014 September 2015
License Amendment Request 260, Proposed Changed to License and Technical Specifications to Reflect Permanent Removal of Spent Fuel from Spent Fuel Pool
ML14029A0642014-01-16016 January 2014
Evaluation ETE-NAF-20130072, Revision 0, Kewaunee Spent Fuel Pool Zirconium Fire Parameter Comparison
ML14029A0672014-01-16016 January 2014
Sargent & Lundy Calculation 2013-11284, Revision 0 - Maximum Cladding and Fuel Temperature Analysis for Uncovered Spent Fuel Pool
ML14029A0662014-01-16016 January 2014
Calculation RA-0050, Revision 0 - Kewaunee Resin Cask Drop Dose Consequence Analysis
ML14029A0652014-01-16016 January 2014
Calculation RA-0049, Revision 1, Addendum a - Kewaunee Emergency Action Levels for Post - Cessation of Power Operations
ML14029A0632014-01-16016 January 2014
Kewaunee,Calculation 2013-07050, Revision 2 - Maximum Cladding Temperature Analysis for an Uncovered Spent Fuel Pool with No Air Cooling
ML14029A0622014-01-16016 January 2014
Calculation RA-0044, Revision 1 - Dose Rate at the KPS Site Boundary Following a Complete Draindown of the Spent Fuel Pool
ML14029A0612014-01-16016 January 2014
Enclosure 4 to 13-495A - Supporting Evaluations and Calculations
ML14029A0592014-01-16016 January 2014
Enclosure 3 to 13-495A - Permanently Defueled Emergency Action Level Basis Document
ML14029A0572014-01-16016 January 2014
Enclosure 2 to 13-495A - Permanently Defueled Emergency Action Level Scheme
ML14029A0562014-01-16016 January 2014
Enclosure 1 to 13-495A - Permanently Defueled Emergency Plan
ML14029A0552014-01-16016 January 2014
Attachment 2 to 13-495A - Comparison Matrix for Permanently Defueled Eals, Based Upon Nuclear Energy Institute (NEI) 99-01, Methodology for Development of Emergency Action Levels, Revision 6
ML14029A0542014-01-16016 January 2014
Attachment 1 to 13-495A - Discussion of Change, Technical Analysis, Significant Hazards Determination, and Environmental Considerations
ML14029A0532014-01-16016 January 2014
License Amendment Request 257, Permanently Defueled Emergency Plan and Emergency Action Level Scheme
NEI 99-01, Kewaunee, Attachment 2 to 13-495A - Comparison Matrix for Permanently Defueled Eals, Based Upon Nuclear Energy Institute (NEI) 99-01, Methodology for Development of Emergency Action Levels, Revision 62014-01-16016 January 2014
Kewaunee, Attachment 2 to 13-495A - Comparison Matrix for Permanently Defueled Eals, Based Upon Nuclear Energy Institute (NEI) 99-01, Methodology for Development of Emergency Action Levels, Revision 6
ML13156A0372013-05-29029 May 2013
License Amendment Request 256, Permanently Defueled License and Technical Specifications
ML12248A1492012-08-29029 August 2012
Submittal of Revision to Locked Rotor Radiological Accident Analysis: License Amendment Request 244, Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications
ML12219A0702012-07-30030 July 2012
License Amendment Request 254: Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process
ML11222A1232011-07-25025 July 2011
License Amendment Request 244: Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications
ML11137A0282011-05-0909 May 2011
License Amendment Request 252, Operation of Service Water Flow to Component Cooling Heat Exchangers
ML1022904202010-08-0909 August 2010
License Amendment Request 244: Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications
ML1013803992010-05-12012 May 2010
License Amendment Request 249: Conversion to Improved Technical Specifications (TAC No. ME02467) - Request to Change Proposed Service Water and Main Steam Isolation Valve Specifications
ML1011101232010-04-13013 April 2010
License Amendment Request 246: Revision to Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection Limitations
ML0933602472009-11-20020 November 2009
Request for Approval of Cyber Security Plan
ML0924403712009-08-24024 August 2009
License Amendment Request 249, Conversion to Improved Technical Specifications
ML0912710592009-06-0101 June 2009
License Amendment No. 206, Containment Purge and Vent Isolation Valves Surveillance Requirement
ML0902602992009-01-23023 January 2009
License Amendment Request 247: Emergency Diesel Generator Fuel Oil Technical Specification Changes
ML0825507002008-09-11011 September 2008
License Amendment Request 242: Extension of the One-time Fifteen Year Containment Integrated Leak Rate Test Interval
ML0823211982008-08-18018 August 2008
Application to Use Weighting Factors for External Exposure
ML0823200832008-08-14014 August 2008
License Amendment Request 229, Change Technical Specifications to Require Testing Containment Purge and Vent Isolation Valves When the Reactor Is Above Cold Shutdown
ML0823410392008-08-12012 August 2008
Applicants Environmental Report, Operating License Renewal Stage
ML0819902662008-07-16016 July 2008
License Amendment Request 238: Increase in Technical Specification Minimum Injection Accumulator Boron Concentration
ML0819303172008-07-0707 July 2008
License Amendment Request 239 for Review and Approval of Seismic Analysis Methodology for Auxiliary Building Crane
ML0810604762008-04-14014 April 2008
License Amendment Request- 224, Steam Line Isolation Function Applicability
ML0809504692008-04-0404 April 2008
License Amendment Request 237: Removal of Shield Building and Auxiliary Building Special Ventilation Train Filter Heater Requirements
ML0809500962008-04-0303 April 2008
Response to NRC Request for Additional Information License Amendment Request 210. Technical Specification Modifications Regarding Control Room Envelope Habitability
ML0806305402008-03-28028 March 2008
Issuance of License Amendment 196 Nuclear Core Design and Safety Analysis Methods
ML0731707052007-11-0909 November 2007
License Amendment Request 227 Relocation of Spent Fuel Pool Crane Technical Specification to Technical Requirements Manual
ML0731804992007-11-0909 November 2007
License Amendment Request 234 - Request for Review and Approval of Methodology Change Regarding Auxiliary Building Crane Upgrade
ML0727605722007-10-0202 October 2007
License Amendment Request - 232 Operability Testing of Emergency Diesel Generators
ML0726802782007-09-24024 September 2007
License Amendment Request 228 Incorporation of Dominion Nuclear Analysis and Fuel Topical Report DOM-NAF-5 Into Technical Specifications
ML0726201442007-09-14014 September 2007
License Amendment Request 210 - Technical Specification Modifications Regarding Control Room Envelope Habitability
ML0718600752007-07-0202 July 2007
License Amendment Request - 223, Deletion of License Condition 2.C (5), Fuel Burnup
ML0717002572007-06-12012 June 2007
License Amendment Request - 217 Revision to Reactor Trip Permissive Setpoints
2022-02-16
[Table view] |
Text
Serial No. 13-495A ENCLOSURE 2 LICENSE AMENDMENT REQUEST 257:
PERMANENTLY DEFUELED EMERGENCY PLAN AND EMERGENCY ACTION LEVEL SCHEME PERMANENTLY DEFUELED EMERGENCY ACTION LEVEL SCHEME KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
None E-HUl.1 Damage to a loaded cask CONFINEMENT BOUNDARY as indicated by a radiation reading greater than two times the ISFSI Technical Specification allowable levels.
'D-AAI.1 Reading on ANY effluent radiation monitor that is greater than the reading PD-AUI.1 Reading on ANY effluent radiation monitor that is greater than the reading shown shown for 15 minutes or longer: for 60 minutes or longer.
Auxiliary Building Action Value Auxiliary Buildina Action Value R-1 3 Aux Bldg Vent Exhaust 4.OE+06 cpm R-1 3 Aux Bldg Vent Exhaust 4.OE+05 cpm R-14 Aux Bldg Vent Exhaust 4.OE+06 cpm R-14 Aux Bldg Vent Exhaust 4.OE+05 cpm Liauid Radwaste Liuuid Radwaste R-18 Waste Disposal System Liquid 50 x Discharge Permit Limit R-18 Waste Disposal System Liquid 2 x Discharge Permit Limit R-20 Aux Bldg SW Return 5.OE+04cpm R-20 Aux Bldg SW Return 2.OE+03 cpm
'D-AAI.2 Confirmed sample analysis for a gaseous release indicates a PD-AU1.2 Confirmed sample analysis for a gaseous release indicates a concentration concentration greater than 5.4E-02 pCi/cc for 15 minutes or longer. greater than 5.4E-03 pCi/cc for 60 minutes or longer D-AA1.3 Confirmed analysis for a liquid effluent sample indicates a concentration or PD-AUI.3 Confirmed analysis for a liquid effluent sample indicates a concentration or release rate greater than 50 times the ODCM limits for 15 minutes or release rate greater than 2 times the ODCM limits for 60 minutes or longer.
longer.
PD-AA2.1 UNPLANNED dose rate greater than 15 mrem/hr in ANY of the following areas requiring continuous occupancy to maintain control of radioactive PD-AU2.1 a. UNPLANNED water level drop in the spent fuel pool as indicated by material or operation of systems needed to maintain spent fuel integrity: EITHER of the following:
- Spent Fuel Pool low water level alarm setpoint (3 ft. 4 in. below floor)
R-1 Control Room Area - Visual observation AND
- b. UNPLANNED rise in area radiation levels as indicated by EITHER of the PD-AA2.2 Survey results that indicate an UNPLANNED rise of 100 mrem/hr over following radiation monitors.
NORMAL LEVELS that impedes access to ANY of the following areas . R-5 Fuel Handling Area ALERT Alarm needed to maintain control of radioactive material or operation of systems
- R-10 New Fuel Pit Area ALERT Alarm needed to maintain spent fuel integrity.
PD-AU2.2 Area radiation monitor reading or survey result indicates an UNPLANNED rise of Spent Fuel Pool Pump Area (survey) 25 mrem/hr over NORMAL LEVELS.
None PD-SUI.1 UNPLANNED spent fuel pool temperature rise to greater than 150=F.
HOSTILE ACTION within the VBS boundary or airborne attack threat within 30 Confirmed SECURITY CONDITION or threat minutes.
PD-HAI.1 A HOSTILE ACTION is occurring or has occurred within the VBS boundary PD--UI.1 A SECURITY CONDITION that does not involve a HOSTILE ACTION as as reported by Security Supervision, reported by Security Supervision.
Hazards PD-HA1.2 A validated notification from NRC of an aircraft attack threat within 30 PD-HU1.2 Notification of a credible security threat directed at the site.
minutes of the site.
PD-HU1.3 A validated notification from the NRC providing information of an aircraft threat.
Hazardous event affecting SAFETY SYSTEM equipment necessary for spent fuel None cooling.
PD-HU2.1 a. The occurrence of ANY of the following hazardous events:
" Seismic event (earthquake)
" Internal or external flooding event
" Low lake level
" High winds or tomado strike
" FIRE
" EXPLOSION
" Other events with similar hazard characteristics as determined by the Shift Manager AND
- b. The event has damaged a SAFETY SYSTEM needed for spent fuel cooling.
AND
- c. The damaged SAFETY SYSTEM cannot, or potentially cannot, perform its design function based on EITHER:
" Indications of degraded performance
" VISIBLE DAMAGE Other conditions exist which In the judgment of the Emergency Director POther conditions exist which In the judgment of the Emergency Director warrant warrant declaration of an Alet. Ideclaration of a UE.
PD-HA3.1 Other conditions exist which in the judgment of the Emergency Director IPD-HU3.1 Other conditions exist which in the judgment of the Emergency Director warrant I____ warrant declaration of an Alert. jdeclaration of a UE.
