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MONTHYEARML11236A1342011-07-31031 July 2011 Westinghouse WCAP-17400-NP, Rev. 0, Prairie Island, Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis, Enclosure 4 Project stage: Request L-2011-409, Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification Regarding Fuel Loading Curve and Areal Density Criteria for Metamic Inserts2011-10-14014 October 2011 Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification Regarding Fuel Loading Curve and Areal Density Criteria for Metamic Inserts Project stage: Request ML1125602172011-10-25025 October 2011 Request for Withholding of Proprietary Information from Public Disclosure Project stage: Withholding Request Acceptance ML1206203892012-03-20020 March 2012 Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes Project stage: RAI L-2012-132, Extended Power Uprate License Amendment Request - Supplement to Proposed Technical Specification Changes Related to Spent Fuel Storage Requirements and Core Operating Limits Report (COLR) References2012-03-31031 March 2012 Extended Power Uprate License Amendment Request - Supplement to Proposed Technical Specification Changes Related to Spent Fuel Storage Requirements and Core Operating Limits Report (COLR) References Project stage: Supplement L-PI-12-038, Westinghouse, Affidavit - CE-12-3 16, Revision 1, Westingliouse Suggested Responses to the Requests for Additional Information Presented in ML120620389.2012-05-0303 May 2012 Westinghouse, Affidavit - CE-12-3 16, Revision 1, Westingliouse Suggested Responses to the Requests for Additional Information Presented in ML120620389. Project stage: Other ML12139A1982012-05-16016 May 2012 Response to Requests for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes (TAC Nos. ME6984 and ME69851) Project stage: Response to RAI ML12215A2522012-08-0707 August 2012 Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes Project stage: RAI L-PI-12-066, Enclosure 2 to L-PI-12-066 - Westinghouse Affidavit, Application for Withholding Proprietary Information from Public Disclosure2012-08-27027 August 2012 Enclosure 2 to L-PI-12-066 - Westinghouse Affidavit, Application for Withholding Proprietary Information from Public Disclosure Project stage: Request ML12249A0692012-09-0404 September 2012 Response to Requests for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes Project stage: Response to RAI ML13011A3162013-01-22022 January 2013 Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes Project stage: RAI L-PI-13-002, Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes2013-02-0808 February 2013 Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes Project stage: Response to RAI ML13197A3972013-06-25025 June 2013 NRR E-mail Capture - Prairie Island Ngp - Sfpc LAR Draft RAI Project stage: Draft Other L-PI-13-067, Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes2013-07-17017 July 2013 Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes Project stage: Response to RAI ML13241A3832013-08-29029 August 2013 Issuance of Amendments Spent Fuel Pool Criticality Changes Project stage: Approval 2012-08-27
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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] Category:Proprietary Information Review
MONTHYEARML23020A9172023-01-26026 January 2023 Request for Withholding Information from Public Disclosure License Amendment Request to Revise Technical Specification Section 5.6.6, RCS PTLR ML19262D4332019-09-23023 September 2019 Request for Withholding Information from Public Disclosure ML17313B1902017-11-13013 November 2017 Request for Withholding Information from Public Disclosure (CAC Nos. MF7121 and MF7122; EPID L-2015-LLA-0002) ML16160A0772016-06-24024 June 2016 Request for Withholding Information from Public Disclosure ML1125602172011-10-25025 October 2011 Request for Withholding of Proprietary Information from Public Disclosure ML1011802112010-05-0606 May 2010 Request for Withholding Information from Public Disclosure for Prairie Island Nuclear Generating Plant, Units 1 and 2 ML1011708332010-05-0606 May 2010 Request for Withholding Information from Public Disclosure for Prairie Island Nuclear Generating Plant, Units 1 and 2 ML1011708142010-05-0606 May 2010 Request for Withholding Information from Public Disclosure for Prairie Island Nuclear Generation Plant, Units 1 and 2 ML0907102152009-03-25025 March 2009 Request for Withholding Information from Public Disclosure for Prairie Island Nuclear Generating Plant, Units 1 and 2 ML0521602472005-08-11011 August 2005 Westinghouse Electric Company Request for Withholding Information from Public Disclosure ML0430106032004-11-0101 November 2004 Westinghouse Electric Co, Withholding from Public Disclosure, WCAP-16219-P, Development and Qualifications of a Gothic Containment Evaluation Model for the Prairie Island Nuclear Generating Plants, Revision 0, April 2004 ML0424407632004-09-0101 September 2004 Withholding from Public Disclosure, Exhibit G of Letter (Selective Scope Implementation of Alternative Source Term for Fuel Handling Accident Applied to Containment Technical Specifications Dated January 20, 2004) ML0413801722004-05-20020 May 2004 Nuclear Management Company, LLC - Request for Withhodling Information from Public Disclosure and Closed Meeting with NRC to Discuss Refueling Plans by Nuclear Management Company ML0413101222004-04-30030 April 2004 Request for Closed Meeting with USNRC to Discuss NMC Refueling Plans ML0409902062004-04-14014 April 2004 4/16/04, Prairie, Units 1 & 2, Withholding from Public Disclosure, CAW-03-1752 ML0409902512004-04-13013 April 2004 Withholding from Public Disclosure, CAW-04-1779, MB8128 & MB8129 ML0315400162003-06-0202 June 2003 Request for Withholding Information from Public Disclosure 2023-01-26
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 October 25, 2011 Mr. Mark A. Schimmel Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 REQUEST FOR WITHHOLDING OF PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE (TAC NOS. ME6984 AND ME6985)
Dear Mr. Schimmel:
By letter dated August 19, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112360231), Northern States Power Company, a Minnesota Corporation (NSPM) submitted a request to amend the renewed operating licenses for the Prairie Island Nuclear Generating Plant, Units 1 and 2. NSPM proposes to revise Technical Specification (TS) 3.7.17, "Spent Fuel Pool Storage," and TS 4.3.1, "Fuel Storage Criticality."
Additionally, NSPM proposes to change the current licensing basis to change the regulatory basis for spent fuel pool criticality analysis from Title 10 of the Code of Federal Regulations (10 CFR), Section 70.24, to 10 CFR 50.68(b), and to change the evaluation methodology used for spent fuel pool criticality analysis to align with NRC Draft Interim Staff Guidance DSS-ISG 2010-01.
The submittal includes a Westinghouse Report, WCAP-17400-NP, Revision 0, entitled "Prairie Island Units 1 and 2 Spent Fuel Pool Criticality Analysis," dated July 2011. This Westinghouse report was included in the submittal as Enclosure 6 and deSignated as proprietary. of the submittal is a non-proprietary version of Enclosure 6. This non-proprietary version of the Westinghouse report has been placed in the NRC's Public Document Room and entered into the Agencywide Documents Access and Management System Public Electronic Reading Room under ADAMS Accession No. ML11236A134.
An affidavit dated July 18, 2011, executed by Mr. J. A. Gresham of Westinghouse Electric Company Nuclear Services, requests that the above identified document be withheld from public disclosure pursuant to 10 CFR Section 2.390. The affidavit states that Enclosure 6 should be considered exempt from mandatory public disclosure for the following reasons:
The information reveals the distinguishing aspects of a methodology which was developed by Westinghouse and public disclosure of this information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar calculations and licensing defense services for commercial power reactors without commensurate expenses.
M. A. Schimmel -2 The development of the technology described in part by the information is the result of applying many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money. To duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.
The NRC staff has reviewed Mr. Gresham's affidavit in accordance with the requirements of 10 CFR 2.390, and on the basis of its statements, we have determined that the submitted information sought to be withheld contains proprietary commercial information and should be withheld from public disclosure. Therefore, the above identified document, which is marked as proprietary, will be withheld from public disclosure pursuant to 10 CFR 2.390(b)(5) and Section 103(b) of the Atomic Energy Act of 1954, as amended.
Withholding from public inspection shall not affect the right, if any, of persons properly and directly concerned to inspect the documents. If the need arises, we may send copies of this information to our consultants working in this area. We will, of course, ensure that the consultants have signed the appropriate agreements for handling proprietary information.
If the basis for withholding this information from public inspection should change in the future such that the information could then be made available for public inspection, you should promptly notify the NRC. You also should understand that the NRC may have cause to review this determination in the future, for example, if the scope of a Freedom of Information Act request includes your information. In all review situations, if the NRC makes a determination adverse to the above, you will be notified in advance of any public disclosure.
If you have any questions regarding this matter, I may be reached at 301-415-3049.
Sincerely,
~-----
Ter A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-282 and 50-306 cc: Mr. J. A. Gresham, Manager Westinghouse Electric Company LLC Nuclear Services, Suite 428 1000 Westinghouse Drive Cranberry Township, PA 16066 Additional Distribution via ListServ
M. A. Schimmel -2 October 25, 2011 The development of the technology described in part by the information is the result of applying many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money. To duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.
The NRC staff has reviewed Mr. Gresham's affidavit in accordance with the requirements of 10 CFR 2.390, and on the basis of its statements, we have determined that the submitted information sought to be withheld contains proprietary commercial information and should be withheld from public disclosure. Therefore, the above identified document, which is marked as proprietary, will be withheld from public disclosure pursuant to 10 CFR 2.390{b){5) and Section 103(b) of the Atomic Energy Act of 1954, as amended.
Withholding from public inspection shall not affect the right, if any, of persons properly and directly concerned to inspect the documents. If the need arises, we may send copies of this information to our consultants working in this area. We will, of course, ensure that the consultants have signed the appropriate agreements for handling proprietary information.
If the basis for withholding this information from public inspection should change in the future such that the information could then be made available for public inspection, you should promptly notify the NRC. You also should understand that the NRC may have cause to review this determination in the future, for example, if the scope of a Freedom of Information Act request includes your information. In all review situations, if the NRC makes a determination adverse to the above, you will be notified in advance of any public disclosure.
If you have any questions regarding this matter, I may be reached at 301-415-3049.
Sincerely, IRA!
Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-282 and 50-306 cc: Mr. J. A. Gresham, Manager Westinghouse Electric Company LLC Nuclear Services, Suite 428 1000 Westinghouse Drive Cranberry Township, PA 16066 Additional Distribution via ListServ DISTRIBUTION PUBLIC LPL3-1 r/f RidsNrrDorlLpl3-1 Resource RidsNrrPMPrairielsland Resource RidsNrrLABTully Resource RidsOgcRp Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDssSrxb Resource RidsNrrDorlDpr Resource RidsRgn3MailCenter Resource ADAMS Accession No' .. ML112560217 W,FICE LPL3-1/PM LPL3-1/LA SRXB/BC LPL3-1/BC AME TBeltz BTuily TUlses RPascarelli II DATE 91 19/11 9 119/11 10111/11 10/25/11 OFFICIAL RECORD COpy