Letter Sequence Approval |
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MONTHYEARML0309300582003-03-31031 March 2003
Decommissioning Funding Status Reports
Project stage: Request
ML0316102672003-06-0909 June 2003
RAI, Proposed Amendment Request Regarding the Application for Stretch Power Uprate
Project stage: RAI
ML0907202342003-09-16016 September 2003
Advisory Committee on Reactor Safety Review of Stretch Power Uprate Amendment
Project stage: Approval
ML0320902152003-09-16016 September 2003
Advisory Committee on Reactor Safety Review of Stretch Power Uprate Amendment
Project stage: Approval
ML0327507002003-10-0707 October 2003
RAI, Amendment Request Regarding Application for Stretch Power Uprate
Project stage: RAI
ML0406201432003-10-0909 October 2003
Advisory Committee on Reactor Safety Review of Stretch Power Uprate Amendment
Project stage: Approval
ML0332300162003-12-10010 December 2003
Review of License Amendment Request 195, Stretch Power Uprate
Project stage: Approval
ML0331000602003-12-16016 December 2003
Environmental Assessment, Stretch Power Uprate
Project stage: Other
ML0334503782004-01-0707 January 2004
Request for Withholding Information from Public Disclosure, WCAP-15821-P, MB9031
Project stage: Withholding Request Acceptance
ML0401606962004-01-26026 January 2004
Review of License Amendment Request No. 195, Stretch Power Uprate
Project stage: Approval
ML0404204182004-01-30030 January 2004
Responses to NRC Clarification Questions on Responses to Requests for Additional Information Regarding License Amendment Request 195, Stretch Power Uprate
Project stage: Response to RAI
ML0404906872004-02-0909 February 2004
Responses to NRC Clarification Questions on Responses to RAIs Regarding License Amendment Request 195, Stretch Power Uprate
Project stage: Response to RAI
ML0406503782004-02-20020 February 2004
Responses to NRC RAI Regarding License Amendment Request 195, Stretch Power Uprate
Project stage: Response to RAI
ML0404306332004-02-27027 February 2004
License Amendment No. 172, Authorizing an Increase in the Licensed Reactor Core Power Level of 6.0 Percent from 1673 Megawatts Thermal to 1772 Megawatts Thermal
Project stage: Acceptance Review
ML0413405112004-03-23023 March 2004
Corrective Action Program No. 020538 - Enclosure 2
Project stage: Request
ML0409302272004-05-13013 May 2004
Letter, Clarification to Issuance of Amendment 172, Stretch Power Uprate
Project stage: Approval
ML0416600042004-06-16016 June 2004
Correction to Issuance of Amendment No. 172, Stretch Power Uprate (Tac No. MB9031)
Project stage: Approval
ML0616403402006-03-20020 March 2006
Redacted Version of the Update to the Chapter 13 of the Safety Analysis Report of the Kansas State University Triga Research Reactor
Project stage: Request
ML0610102642006-03-30030 March 2006
Kansas State Univ - Update to Chapter 11, Appendix a of the Proposed Safety Analysis Report for the K-State Triga Mark II Nuclear Research Reactor
Project stage: Request
ML0612801932006-07-0505 July 2006
Letter to Mr. P. Michael Whaley from Brian Thomas Determination of Acceptability and Sufficiency for Docketing & Opportunity for a Hearing the Application from Ksu for Renewal of the Facility License for Ksu Nuclear Reactor Facility
Project stage: Other
2004-01-07
[Table View] |
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Category:Letter
MONTHYEARML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
ML24136A1952024-05-14014 May 2024
2023 Annual Radiological Environmental Operating Report
ML24130A0022024-05-0909 May 2024
Summary of Facility Changes, Tests and Experiments and Commitment Changes
IR 05000305/20240012024-05-0202 May 2024
NRC Inspection Report No. 05000305/2024001
ML24121A2472024-04-29029 April 2024
and Three Mile Island, Unit 2 - 2023 Occupational Radiation Exposure Annual Report
ML24101A0422024-04-22022 April 2024
Solutions Inc. – Exemption from Select Requirements of 10 CFR Part 73 ((Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML24106A0492024-04-15015 April 2024
2023 Annual Radioactive Effluent Release Report
ML24080A0702024-03-20020 March 2024
Decommissioning Trust Fund Annual Report
ML24079A0162024-03-19019 March 2024
Annual Property Insurance Status Report
ML24073A2312024-03-13013 March 2024
and Three Mile Island Nuclear Station, Unit 2 - Management Change
ML24061A0202024-02-15015 February 2024
(Ksp) ISFSI, Submittal of Security Plan, Training and Qualification Plan and Safeguards Contingency Plan, Revision 6
ML23339A1332024-01-26026 January 2024
Exemption from the Req of 10 CFR Part 50.82(a)(8)(i)(A) to Use the Kewaunee Decommissioning Trust Fund for the Management of Site Restoration Activities
IR 05000305/20230022023-12-27027 December 2023
NRC Inspection Report 05000305/2023002 (Drss); 07200064/2023001 (Drss)
ML23332A1922023-11-28028 November 2023
Solutions, Inc., Request for Exemptions from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23278A1002023-10-0505 October 2023
Response to Request for Additional Information (RAI) Application for Kewaunee Solutions (Ks) Site Restoration Activities
ML23222A1522023-08-29029 August 2023
Letter RAI KPS Exemption Site Restoration Final Repaired
IR 05000305/20230012023-08-17017 August 2023
NRC Inspection Report No. 05000305/2023001-Kewaunee Power Station
ML23171B0822023-07-0505 July 2023
Letter - Kewaunee Power Station - Issuance of Exemption from Certain Requirements from 10 CFR Part 20, Appendix G, Section Iii.E
ML23132A0012023-05-11011 May 2023
2022 Annual Radiological Environmental Operating Report
ML23116A2182023-04-26026 April 2023
2022 Annual Radioactive Effluent Release Report
ML23089A3042023-03-30030 March 2023
Decommissioning Fund Status Report
ML23093A0312023-03-29029 March 2023
Solutions, Inc., Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 50.75(h)(1)(iv) for Site Restoration Activities
ML23088A2752023-03-29029 March 2023
Solutions, Inc., Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E
ML23087A0402023-03-27027 March 2023
Annual Property Insurance Status Report
ML23087A0292023-03-27027 March 2023
2022 Annual Report of Occupational Radiation Exposure
ML22361A1022023-02-24024 February 2023
Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities
ML23024A0122023-01-26026 January 2023
Letter to Energysolutions Transmitting Threshold Determination for Merger/Restructuring
IR 05000305/20220022023-01-0303 January 2023
NRC Inspection Report Nos. 05000305/2022002(DRSS) Kewaunee Power Station
ML22292A2302022-11-25025 November 2022
U.S. Nuclear Regulatory Commissions Analysis of Dominion Energy Kewaunees Decommissioning Funding Status Report for Kewaunee Power Station, Docket No. 50-305
ML22290A0052022-10-13013 October 2022
Resubmittal of Kewaunee Power Station Independent Spent Fuel Storage Installation (ISFSI) Only Emergency Plan (Ioep) and IOEP- Emergency Action Level (EAL) Basis Document, Revision 0KS
ML24061A0182022-08-25025 August 2022
(Ksp) ISFSI Submittal of Security Pla11, Training and Qualification Plan and Safeguards Contingency Plan Revision 5
ML22241A0302022-08-25025 August 2022
(Ksp) ISFSI Submittal of Security Plan, Training and Qualification Plan and Safeguards Contingency Plan, Revision 5
IR 05000305/20220012022-08-0101 August 2022
NRC Inspection Report Nos. 05000305/2022001(DNMS) - Kewaunee Power Station
ML22215A1512022-07-27027 July 2022
Executed Financial Assurance Instruments for the Kewaunee License Transfer License No. DPR-43 (Docket Nos. 50-305, 72-64)
ML22209A1252022-07-26026 July 2022
Amendment No. 11 to Indemnity Agreement No. B-53 for Kewaunee Power Station (KPS) - Signed by Kewaunee Solutions, Inc
ML22175A1132022-06-30030 June 2022
Solutions, Inc. - Letter for Review and Acceptance of the Energysolutions, LLC Decommissioning Quality Assurance Program with Enclosure
ML22160A5262022-06-28028 June 2022
Letter - KPS - Issuance of Conforming License Amendment Regarding Indirect Transfer of License from DEK, Inc. to Kewaunee Solutions, Inc
ML22160A5272022-06-28028 June 2022
Enclosure 1 - Amendment No. 221 to Renewed Facility Operating License No. DPR-43
ML22160A5282022-06-28028 June 2022
Enclosure 2 - Amendment No. 11 to Indemnity Agreement B-53
ML22188A0812022-06-23023 June 2022
ISFSI, Virgil C. Summer Nuclear Station, Unit 1 & ISFSI, North Anna Power Station, Units 1 & 2 & ISFSI, Surry Power Station, Units 1 & 2 & ISFSI - Submission of Revision 32 of the Quality Assurance Topical Report
ML22172A2452022-06-22022 June 2022
Notification of Planned Closing Date and Required Regulatory Approvals for the Kewaunee License Transfer Transaction
ML22175A0662022-06-17017 June 2022
Designation of Additional Reviewing Official for ISFSI and 10 CFR Part 37 Program Security Background Investigations
ML22166A3392022-06-13013 June 2022
Notification of Nuclear Insurance
ML22138A2552022-05-10010 May 2022
Submittal of 2021 Annual Radiological Environmental Operating Report
ML22158A2112022-05-10010 May 2022
Summary of Facility Changes, Tests and Experiments and Summary of Commitment Changes
ML22091A1892022-04-0101 April 2022
Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report
ML22108A0352022-04-0101 April 2022
License Transfer to Kewaunee Solutions, Inc
ML22089A2432022-03-30030 March 2022
Decommissioning Funding Status Report, Financial Test and Independent Public Accountants' Letter of Attestation
ML22076A0652022-03-15015 March 2022
Energy Solutions and Dominion Energy Kewaunee - Supplement to License Transfer Application Related to Use of Existing Dominion Energy Quality Assurance Program
ML22060A1912022-02-25025 February 2022
Response to Request for Additional Information Related to Submittal for Approval of the Kewaunee Solutions Decommissioning Quality Assurance Program (Dqap), Revision O for Kewaunee Power Station (KPS)
2024-06-03
[Table view] |
Text
May 13, 2004 Mr. Thomas Coutu Site Vice President Kewaunee Nuclear Power Plant Nuclear Management Company, LLC N490 State Highway 42 Kewaunee, WI 54216
SUBJECT:
KEWAUNEE NUCLEAR POWER PLANT - CLARIFICATION TO ISSUANCE OF AMENDMENT NO. 172, STRETCH POWER UPRATE (TAC NO. MB9031)
Dear Mr. Coutu:
On February 27, 2004, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No.
172 to Facility Operating License No. DPR-43 for the Kewaunee Nuclear Power Plant (KNPP).
Amendment No. 172 approved the KNPP 6.0-percent stretch power uprate and revised the Operating License and Technical Specifications (ADAMS Accession No. ML040430633).
One clarification is warranted on the safety evaluation (SE) for Amendment No. 172.
In Section 3.8.2.1.2.1, Long-Term [Loss-of-Coolant-Accident] LOCA Mass and Energy Release, one clarification is warranted on page 88 of the SE. Enclosure 1 contains the clarification to the SE. Please remove page 88 and replace with pages 88 and 88a between the first and second paragraphs in Section 3.8.2.1.2.1. This clarification does not affect the NRC staffs conclusion of Section 3.8.2.1.2.1.
If there are any comments or questions concerning this letter, please contact me at (301) 415-1446.
Sincerely,
/RA/
John G. Lamb, Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-305
Enclosures:
- 1. Insertion to SE page 88
- 2. KNPP Corrective Action Program No. 020538 cc: See next page
ML040430633).
One clarification is warranted on the safety evaluation (SE) for Amendment No. 172.
In Section 3.8.2.1.2.1, Long-Term [Loss-of-Coolant-Accident] LOCA Mass and Energy Release, one clarification is warranted on page 88 of the SE. Enclosure 1 contains the clarification to the SE. Please remove page 88 and replace with pages 88 and 88a between the first and second paragraphs in Section 3.8.2.1.2.1. This clarification does not affect the NRC staffs conclusion of Section 3.8.2.1.2.1.
If there are any comments or questions concerning this letter, please contact me at (301) 415-1446.
Sincerely,
/RA/
John G. Lamb, Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-305
Enclosures:
- 1. Insertion to SE page 88
- 2. KNPP Corrective Action Program No. 020538 cc: See next page DISTRIBUTION:
PUBLIC PDIII-1 R/F LRaghavan JLamb THarris OGC ACRS TBoyce PLouden, RIII GHill (2)
ADAMS Accession Number: ML040930227 (Letter)
ADAMS Accession Number: ML041340511 (Enclosure 2)
OFFICE PDIII-1/PM PDIII-1/LA SPLB/SC* OGC* PDIII-1/SC NAME JLamb THarris HWalker for RHoefling LRaghavan RDennig DATE 04/ 07/04 04/07/04 04/07/04 04/27/04 04/ 29/04 Kewaunee Nuclear Power Plant cc:
John Paul Cowan Jonathan Rogoff Executive Vice President & Vice President, Counsel & Secretary Chief Nuclear Officer Nuclear Management Company, LLC Nuclear Management Company, LLC 700 First Street 700 First Street Hudson, WI 54016 Hudson, MI 54016 Larry L. Weyers James McCarthy Chairman, President and CEO Plant Manager Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant 600 North Adams Street N490 Highway 42 Greey Bay, WI 54307-9002 Kewaunee, WI 54216-9511 David Zellner Gerry Riste Chairman - Town of Carlton Manager, Regulatory Affairs N2164 County B Kewaunee Nuclear Power Plant Kewaunee, WI 54216 N490 Highway 42 Kewaunee, WI 54216-9511 Mr. Jeffery Kitsembel Electric Division David Molzahn Public Service Commission of Wisconsin Nuclear Asset Manager PO Box 7854 Wisconsin Public Service Corporation Madison, WI 53707-7854 600 N. Adams Street Green Bay, WI 54307-9002 Thomas Webb Nuclear Asset Manager Wisconsin Public Service Corporation 600 N. Adams Street Green Bay, WI 54307-9002 Resident Inspectors Office U. S. Nuclear Regulatory Commission N490 Hwy 42 Kewaunee, WI 54216-9510 Regional Administrator Region III U. S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351
3.8.2.1.2 Loss-of-Coolant Accident Containment Analyses The licensee divides the analysis of the response of the containment to a LOCA into a short-term response and a long-term response. The short-term analyses are also called subcompartment analyses. SRP Section 6.2.1.2 defines a subcompartment as any fully or partially enclosed volume within the primary containment that houses high-energy piping and would limit the flow of fluid to the main containment volume in the event of a rupture of the high-energy piping within the volume. These analyses are performed in order to demonstrate that the walls of subcompartments within the containment will maintain their structural integrity when exposed to the large pressure difference which arises due to rapid pressurization of the fully or partially enclosed volume. The analyses are typically analyzed for a very short time period; the KNPP calculations are done for a time period of 3 seconds following the postulated piping break. The long-term analyses are termed containment integrity analyses and must demonstrate that the design temperature and pressure limits of the containment are not exceeded.
Both the short-term and the long-term containment analyses consist of a calculation of the amount of mass and energy resulting from the pipe break entering the enclosure (subcompartment or containment) and the response of the enclosure to this release of mass and energy.
Due to the 6.0-percent stretch power uprate, the mass and energy release rates and the effect on the containment must be re-evaluated.
3.8.2.1.2.1 Long-Term LOCA Mass and Energy Release The licensee has calculated the long-term LOCA mass and energy releases to containment using the NRC-approved Westinghouse March 1979 model1. Although the licensee has revised the long-term LOCA analyses in accordance with the findings of the NRCs review of the GOTHIC 7.0 containment computer code (see Section 3.8.2.1.1 of this SER input), the mass and energy calculations reported in WCAP 16040-P remain unaffected.
WCAP-10325-P-A, "Westinghouse LOCA Mass and Energy Release Model for Containment Design-March 1979 Version," is not directly applicable to pressurized-water reactors (PWRs) with upper plenum injection such as Kewaunee Nuclear Power Plant (KNPP).
However, the licensee previously determined, under the provisions of Title 10 Code of Federal Regulations Section 50.59 (10 CFR 50.59), that the application of WCAP-10325-P-A, was acceptable without prior NRC review and approval. WCAP-10325-P-A is referenced in Revision 17 to the KNPP Updated Safety Analysis Report. The NRC staff has previously approved the use of WCAP-10325-P-A for another Westinghouse-designed two-loop upper plenum injection plant.
During the implementation of the power uprate amendment, the licensee revisited this question in the KNPP Corrective Action Process (CAP) 020538 (see Enclosure 2) in response to questions raised at another Nuclear Management Company, LLC site. The licensee concluded that there was no non-conforming condition.
ENCLOSURE 1 1
WCAP-10325-P-A (Proprietary), WCAP 10326-A (Non-Proprietary), Westinghouse LOCA Mass and Energy Release Model for Containment Design-March 1979 Version, May 1983.
- 88a -
CAP020538 further provides a technical basis for the use of WCAP 10325-P-A. Both the cold-leg injection design and the upper plenum injection design reflood from the bottom of the core. Since there is a greater amount of condensation in the upper plenum injection design, the mass and energy released to the containment will be less than the cold-leg injection design.
The NRC staff therefore agrees with the licensees conclusion that the application of WCAP 10325-P-A is conservative and acceptable for the KNPP containment mass and energy release calculations.
The calculations considered two break locations: the hot-leg and the cold-leg pump suction.
WCAP 16040-P states that the double ended hot-leg (DEHL) break has been shown to result in the highest mass and energy release rates during blowdown. This break also results in the fastest reflood rate which increases the rate of release of energy to the containment. However, for the DEHL break, the energy transferred from the steam generators is minimal which results in a reduction in the energy released after blowdown in comparison with the cold-leg break or the pump suction break. The pump suction break includes a relatively high core flooding rate with the transfer of significant heat from the steam generators. Thus, both break locations, the hot-leg and the pump suction, must be considered.
The calculations also consider cases of maximum and minimum safeguards. These are defined in WCAP 16040-P. The minimum safeguards case is the result of an assumed failure of one EDG which results in the loss of one train of safeguards equipment. The maximum
