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MONTHYEARML0302204092003-01-13013 January 2003 License Amendment Request 193, Measurement Uncertainty Recapture Power Uprate Project stage: Request ML0303701282003-02-0606 February 2003 Withholding from Public Disclosure, Proprietary Document Entitled, Kewaunee Power Uprate Engineering Report Sections 5.7 & 5.8, MB7225 Project stage: Other ML0307005032003-02-27027 February 2003 Supplement to License Amendment Request 193, Measurement Uncertainty Recapture Power Uprate Project stage: Supplement ML0307801742003-03-0606 March 2003 Correction to LAR 193 Attachment 8, WCAP 15592, Rev 1 Project stage: Other ML0306605592003-03-0707 March 2003 RAI, Proposed Amendment Request to Implement Measurement Uncertainty Recapture Power Uprate Project stage: RAI ML0308406842003-03-14014 March 2003 Responses to Request for Additional Information Regarding License Amendment Request 193, Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML0307306922003-03-28028 March 2003 Withholding from Public Disclosure, WCAP-15591, Revision 1, MB7225 Project stage: Other ML0310105852003-04-11011 April 2003 RAI, Proposed Measurement Uncertainty Recapture Power Uprate Project stage: RAI ML0312703672003-04-30030 April 2003 Responses to Requests for Additional Information Regarding License Amendment Request 193, Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML0315007242003-05-22022 May 2003 License Amendment Request 195, Application for Stretch Power Uprate Project stage: Request ML0314700022003-05-23023 May 2003 RAI, Request for Withholding Information from Public Disclosure Project stage: RAI ML0314706882003-05-27027 May 2003 Memorandum, Phone Call Held on May 22, 2003, Regarding Measurement Uncertainty Recapture Power Uprate Project stage: Other ML0314801782003-05-27027 May 2003 Request for Withholding Information from Public Disclosure, TAC No. MB7225 Project stage: Withholding Request Acceptance ML0315406732003-06-0303 June 2003 Letter, Review of Draft Safety Evaluation for Measurement Uncertainty Recapture Power Uprate. TAC No MB7225 Project stage: Draft Approval ML0316812802003-06-0909 June 2003 Review of Draft Safety Evaluation for Measurement Uncertainty Recapture Power Uprate - NMC Response Project stage: Draft Other ML0319501222003-06-30030 June 2003 Resolution of Hold Request for License Amendment Request 193, Measurement Uncertainty Recapture Power Uprate for Kewaunee Project stage: Request ML0315307342003-07-0808 July 2003 Issuance of License Amendment 168, Revising the Knpp Operating License and TSs to Increase the Licensed Rated Power by 1.4 Percent Project stage: Approval ML0319103212003-07-0808 July 2003 Tech Spec Pages for License Amendment 168, Revising the Knpp Operating License and TSs to Increase the Licensed Rated Power by 1.4 Percent Project stage: Approval ML0320304582003-07-24024 July 2003 Correction to Issuance of Amendment 168 Project stage: Approval ML0321004012003-07-24024 July 2003 Correction Technical Specification Pages to Issuance of Amendment 168 Project stage: Approval 2003-04-30
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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
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NMCla Committed to NuclearExcellence* Kewaunee Nuclear Power Plant Operated by Nuclear Management Company, LLC NRC-03-018 10 CFR 50.90 February 27, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 KEWAUNEE NUCLEAR POWER PLANT DOCKET 50-305 LICENSE No. DPR-43 SUPPLEMENT TO LICENSE AMENDMENT REQUEST 193, MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE FOR KEWAUNEE NUCLEAR POWER PLANT
References:
- 1) Letter NRC-03-004 from Thomas Coutu to Document Control Desk, "License Amendment Request 193, Measurement Uncertainty Recapture power Uprate for Kewaunee Nuclear Power Plant," dated January 13, 2003 (TAC No. MB7225).
- 2) Letter NRC-81-26 from E.R. Mathews (WPSC) to A. Schwencer (NRC), "Proposed Amendment No. 45," dated February 20, 1981.
- 3) Letter from S.A. Varga (NRC) to E.R. Mathews (WPSC), regarding issuance of Amendment No. 35, dated July 24, 1981.
In accordance with the requirements of 10 CFR 50.90, Nuclear Management Company, LLC (NMC) submitted license amendment request (LAR) 193 (reference 1) for a measurement uncertainty recapture (MUR) power uprate of 1.4 percent. The MUR power uprate would change the operating license and the associated plant Technical Specifications (TS) for the Kewaunee Nuclear Power Plant (KNPP) to reflect an increase in the rated power from 1650 MWt to 1673 MWt.
The reference I submittal followed Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2002-03, "Guidance on the Content of Measurement Uncertainty Recapture Power Uprate Applications." In response to Section VII.5.A of the RIS guidance, the NMC provided a discussion of the 10 CFR 51.22 criteria for categorical exclusion for environmental review. This discussion was provided in reference 1, Attachment 2, pages 58 and 59. This discussion included information regarding effluent releases governed by the Wisconsin Department of Natural Resources (WDNR) including the Wisconsin Pollutant Discharge Elimination System (WPDES) permit and a WDNR Order, the latter containing limits on circulating water discharge flow rate and temperature.
N490 Highway 42 a Kewaunee, Wisconsin 54216-9510 _A OC)
Telephone: 920.388.2560
Docket 50-305 NRC-03-018 February 27, 2003 Page 2 Following the reference I submittal, intake icing problems caused the NMC to thoroughly investigate the WDNR Order temperature limits. Research into this WDNR Order determined that the limits in the original WDNR Order (dated September 13, 1976) were no longer in effect.
From references 2 and 3 it can be concluded that the WDNR Order was no longer in effect following the issuance of the September 28, 1979 WPDES permit. The Environmental Services Department at Wisconsin Public Service Corporation (WPSC), the owner of the KNPP, confirmed that the current WPDES permit is the controlling document and that this permit does not contain any limitations on circulating water discharge flow rate or temperature. The research into the WDNR Order limits has been captured in the site corrective action program.
Based on the above discussion, Attachment 2,Section VII.5.A of the MUR power uprate submittal (reference 1) requires revision. The NMC has determined the most straightforward approach is to revise the affected pages of Attachment 2 in reference 1. The revised pages are numbered 58a and 59a and are included as an attachment to this letter. Revision bars in the right hand margin denote the affected text of these pages. Pages 58a and 59a replace the original pages 58 and 59 of reference 1, Attachment 2, in their entirety.
The fact that the WDNR Order was superceded does not affect the ultimate conclusion of the environmental review provided for the MUR power uprate. The MUR power uprate does not involve a significant change in the types of or significant increase in the amounts of any effluents that may be released offsite or a significant increase in individual or cumulative occupational radiation exposure. Therefore, the proposed change continues to meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), an environmental assessment of the proposed change is not required.
This supplement does not change the Operating License or Technical Specifications for the KNPP. This supplement also does not change the no significant hazards determination originally submitted in reference 1. No additional commitments have been made as a part of this supplement.
In accordance with 10 CFR 50.91, a copy of this application, with the attachment, is being provided to the designated Wisconsin Official.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on February 27, 2003.
~ 6U4-A Thomas Coutu Site Vice-President, Kewaunee Plant LMG Attachment Revised Pages for License Amendment Request 193, Measurement Uncertainty Recapture Power Uprate for Kewaunee Nuclear Power Plant cc- US NRC, Region III US NRC Senior Resident Inspector Electric Division, PSCW
A'TACHMENT 1 NUCLEAR MANAGEMENT COMPANY, LLC KEWAUNEE NUCLEAR PLANT DOCKET 50-305 February 27, 2003 Letter from Thomas Coutu (NMC)
To Document Control Desk (NRC)
Supplement to License Amendment Request 193 Revised Pages for LicenseAmendment Request 193, Measurement Uncertainty Recapture Power Uprate for Kewaunee Nuclear Power Plant
Docket 50-305 NRC-03-01 8 February 27, 2003 Attachment, Page 58a
- 5. A discussion- of the 10 CFR 51.22 criteria for tategorical exclusion for environmental review Including:
A. A discussion of the effect of the power uprate on the types or amounts of any effluents that may be released offsite and whether or not this effect Is bounded by the rmal environmental statement and previous Environmental Assessments for the plant.
A review considering the operating license, the current Wisconsin Pollutant Discharge Elimination System (WPDES) permit, and the information contained in the Final Environmental Statement (FES) was performed. Effluents from the plant that could change as a result of the MUR power uprate are thermal discharges to Lake Michigan and radiological effluents. Although increases in discharge amounts associated with the proposed power uprate are possible, they will remain within acceptable limits. Annual radiological discharges will continue to be a small percentage of the allowable limits and the FES estimates.
The effluents are described below.
Wisconsin Pollutant Discharge Elimination System (WPDES) permit, WI-00001571-06-0, addresses chemical and contamination limits and reporting requirements of KNPP. There are no thermal limits in the WPDES Permit.
Chemical and contamination limits are defined on a volumetric basis. There will be no diluting effects based on the power uprate. Therefore, the chemical and contamination limits are not affected. An evaluation of a 7.4 percent power uprate showed no changes in the current circulating water (CW) flow rate. The evaluation also determined the total temperature rise across the condenser to be 16.7°F. This results in an increase in CW outlet temperature of approximately 1.5*F for a 7.4 percent power uprate. This temperature rise is expected to be much smaller for the 1.4 percent MUR power uprate. Therefore, the WPDES permit does not require modification as a result of the 7.4 percent uprate. The 1.4 percent MUR power uprate is expected to have much less of an impact on the thermal discharge and is bounded by the 7.4 percent evaluation. Therefore, the WPDES permit does not require modification for the 1.4 percent MUR power uprate either.
Docket 50-305 NRC-03-01 8 February 27, 2003 Attachment, Page 59a Normal annual'radiological effluents were evaluated for an uprate to 1772 MWt.
These effluents were described in Section 111.3 of this attachment. Based on the evaluations performed for an uprated power of 1772 MWt, the liquid and gaseous radwaste system design will be capable of maintaining normal operational offsite releases and doses within the requirements of 10 CFR 20 and 10 CFR 50, Appendix I. Additionally, effluent increases are assumed to be proportional to the increase in power. Therefore, effluents from the MUR power uprate (1673 MWt) are bounded by this evaluation. Solid waste volume generation is expected to increase slightly. However, all solid waste is controlled within several state and federal regulatory limits through the KNPP Solid Radioactive Waste Process Control Program (reference VII.1).
B. A discussion of the effect of the power uprate on individual or cumulative occupational radiation exposure.
Normal operation radiation levels were originally evaluated at a core power level of 1721 MWt. Therefore, the original evaluation bounds the power level of the MUR power uprate (i.e., 1673 MWt). Therefore, there will be no changes in radiation zoning in the plant. Additionally, individual worker exposures will be maintained within the acceptable limits of the site ALARA program that controls access to radiation areas.
Environmental Review Conclusions Thermal effluents may change slightly following the MUR power uprate. These changes have been evaluated at an uprated power of 1772 MWt. However, the KNPP WPDES permit does not contain thermal limits. The current WPDES permit remains valid for the 1.4 percent MUR power uprate. Radiological effluents were evaluated at an increased core power of 1772 MWt. All releases and doses will remain within regulatory limits. Radiation exposure was also reviewed. Original normal dose evaluations were based on a 1721 MWt core power level. Therefore, radiation exposure shielding design does not change.
Additionally, the site ALARA program will continue to monitor and control personnel exposure such that the regulatory limits are not exceeded.
Based on the above, the proposed change does not involve a significant change in the types of or significant increase in the amounts of any effluents that may be released offsite or a significant increase in individual or cumulative occupational radiation exposure. Therefore, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22 (b), an environmental assessment of the proposed change is not required.