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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
MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 ML23311A3572023-11-0707 November 2023 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0 ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT ML23181A0192023-06-30030 June 2023 Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 ML23150A1722023-05-30030 May 2023 Preparation and Scheduling of Operator Licensing Examinations 2024-02-01
[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