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MONTHYEARML1101002912011-01-0505 January 2011 Cooper - License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves Project stage: Request ML1104202012011-02-11011 February 2011 Acceptance Review Email, License Amendment Request, Revise Technical Specification 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection Project stage: Acceptance Review ML1114307042011-06-0303 June 2011 Request for Additional Information, License Amendment Request, Revise Technical Specification 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection Project stage: RAI ML1118100852011-06-30030 June 2011 Notice of Meeting with Nebraska Public Power District to Discuss Cooper'S Request to Revise TS 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection Project stage: Meeting ML1121401792011-07-11011 July 2011 Licensee Slides from Conference Call with Nebraska Public Power District Project stage: Other ML1121700812011-08-18018 August 2011 7/12/11 - Summary of Teleconference with Nebraska Public Power District to Discuss Cooper'S Request to Revise TS 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs) at Cooper Nuclear Station Project stage: Meeting NLS2011086, Supplement to License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves2011-10-0606 October 2011 Supplement to License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves Project stage: Supplement NLS2011088, Response to Nuclear Regulatory Commission Request for Additional Information for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves2011-10-18018 October 2011 Response to Nuclear Regulatory Commission Request for Additional Information for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves Project stage: Request ML1104808522011-11-0101 November 2011 Request for Withholding Information from Public Disclosure, 2/18/11 Affidavit Executed by J. Harrison, GE Hitachi Nuclear Energy, NEDC-33543P, Revision 0 Project stage: Withholding Request Acceptance ML1136302582012-01-31031 January 2012 Issuance of Amendment No. 240, Revise Technical Specification 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection Project stage: Approval 2011-02-11
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Category:Letter
MONTHYEARIR 05000298/20240032024-11-0505 November 2024 Integrated Inspection Report 05000298/2024003 ML24250A2052024-10-0808 October 2024 Issuance of Amendment No. 278 Regarding Revision to Technical Specification Table 3.3.2.1-1 and Transfer of Minimum Critical Power Ratio Values to Core Operating Limit Report ML24227A0822024-09-0303 September 2024 Summary of Regulatory Audit in Support of License Amendment Request to Modify the High Pressure Coolant Injection Low Flow Value IR 05000298/20240052024-08-22022 August 2024 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2024005) IR 05000298/20240022024-07-25025 July 2024 Integrated Inspection Report 05000298/2024002 ML24183A1722024-07-17017 July 2024 Issuance of Amendment No. 277 to Adopt TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil ML24197A1462024-07-15015 July 2024 NRC Region IV Ltr to Cooper Nuclear Station Re FEMA Level 1 Finding ML24134A1782024-07-0303 July 2024 Issuance of Amendment No. 276 Revision to Technical Specification 3.8.3, Diesel Fuel Oil, Lube Oil and Starting Air, to Allow for Cleaning, Inspection and Any Needed Repairs During Refuel Outage 33 ML24197A0682024-06-24024 June 2024 FEMA Ltr to Missouri State Emergency Management Agency - Level 1 Finding, 24 June 2024 ML24192A0112024-06-13013 June 2024 2024-06-Post Exam Comments 05000298/LER-2023-002-01, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications2024-06-0606 June 2024 Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications IR 05000298/20244012024-06-0404 June 2024 Security Baseline Inspection Report 05000298/2024401 ML24151A1082024-05-30030 May 2024 NRC Initial Operator Licensing Examination Approval 05000298/2024301 ML24137A0942024-05-17017 May 2024 Regulatory Audit Plan in Support of License Amendment Request to Modify Allowable Value Regarding Technical Specification for High Pressure Coolant Injection Pump Discharge Low Flow 05000298/LER-2024-005, High Pressure Coolant Injection Pressure Switch Installation Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited B Technical2024-05-13013 May 2024 High Pressure Coolant Injection Pressure Switch Installation Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited B Technical. 05000298/LER-2024-004, Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications2024-05-0909 May 2024 Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications IR 05000298/20240012024-05-0303 May 2024 Integrated Inspection Report 05000298/2024001 ML24129A0952024-04-25025 April 2024 Preparation and Scheduling of Operator Licensing Examinations IR 05000298/20240102024-04-24024 April 2024 Comprehensive Engineering Team Inspection Report 05000298/2024010 05000298/LER-2024-003, High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications2024-04-22022 April 2024 High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications ML24096A1202024-04-0505 April 2024 Issuance of Amendment No. 275 Revision to Technical Specification 3.3.1.1 (Emergency Circumstances) ML24093A2282024-04-0202 April 2024 Notice of Enforcement Discretion for Cooper Nuclear Station IR 05000298/20240902024-04-0101 April 2024 – Notice of Violation, NRC Inspection Report 05000298/2024090 05000298/LER-2024-001, Inoperable Turbine Stop Valve Limit Switch Causes Condition Prohibited by Technical Specifications2024-03-0404 March 2024 Inoperable Turbine Stop Valve Limit Switch Causes Condition Prohibited by Technical Specifications 05000298/LER-2024-002, Technical Specifications Prohibited Condition for Inoperable Service Water Booster Pump2024-03-0404 March 2024 Technical Specifications Prohibited Condition for Inoperable Service Water Booster Pump IR 05000298/20230062024-02-28028 February 2024 Annual Assessment Letter for Cooper Nuclear Station - Report 05000298/2023006 IR 05000298/20230042024-02-12012 February 2024 Integrated Inspection Report 05000298/2023004 ML24033A3092024-02-12012 February 2024 Summary of Regulatory Audit Regarding the Relief Request RC3-02 Regarding Drywell Head Bolting IR 05000298/20230122024-02-12012 February 2024 NRC Inspection Report 05000298/2023012 ML23334A2012024-01-0303 January 2024 Issuance of Amendment No. 274 Revision to Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements 05000298/LER-2023-002, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications2023-12-20020 December 2023 Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23311A1122023-11-0909 November 2023 Project Manager Assignment IR 05000298/20230032023-11-0202 November 2023 Integrated Inspection Report 05000298/2023003 IR 05000298/20234012023-11-0101 November 2023 Cyber Security Report 05000298/2023401 Public ML23264A8052023-10-11011 October 2023 Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23233A1882023-09-0505 September 2023 Regulatory Audit Plan in Support of Relief Request RC3-02 Regarding Drywell Head Bolting IR 05000298/20243012023-09-0101 September 2023 Notification of NRC Initial Operator Licensing Examination 05000298/2024301 IR 05000298/20230052023-08-21021 August 2023 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2023005)- Mid Cycle Letter IR 05000298/20230022023-08-0808 August 2023 Integrated Inspection Report 05000298/2023002 IR 05000298/20234022023-08-0303 August 2023 NRC Security Inspection Report 05000298/2023402 ML23214A2742023-08-0303 August 2023 Nuclear Station - Notification of Inspection (NRC Inspection Report 05000298/2023004) and Request for Information IR 05000298/20234202023-08-0101 August 2023 Security Baseline Inspection Report 05000298/2023420 05000298/LER-2022-002-01, Manual Core Spray Injection to Restore Skimmer Surge Tank Level2023-06-29029 June 2023 Manual Core Spray Injection to Restore Skimmer Surge Tank Level ML23173A0862023-06-26026 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000298/2023401 IR 05000298/20230102023-05-17017 May 2023 Biennial Problem Identification and Resolution Inspection Report 05000298/2023010 05000298/LER-2022-004-01, 1 for Cooper Nuclear Station, Manual Reactor Scram and Group I Isolation Due to Main Turbine Bypass Valve Failing Open2023-05-11011 May 2023 1 for Cooper Nuclear Station, Manual Reactor Scram and Group I Isolation Due to Main Turbine Bypass Valve Failing Open 05000298/LER-2023-001, Valve Test Failures Result in Condition Prohibited by Technical Specifications2023-05-0808 May 2023 Valve Test Failures Result in Condition Prohibited by Technical Specifications IR 05000298/20234032023-05-0404 May 2023 Security Baseline Inspection Report 05000298/2023403 ML23129A2822023-04-20020 April 2023 Submittal of Revision 31 to Updated Safety Analysis Report 2024-09-03
[Table view] Category:Proprietary Information Review
MONTHYEARML18190A4842018-07-30030 July 2018 Request for Withholding Information from Public Disclosure - 4/23/18 Affidavit Executed by Brian R. Moore, Global Nuclear Fuel - Americas, LLC Related to Safety Limit Minimum Critical Power Ratio Amendment Request ML16126A5362016-06-0606 June 2016 Request for Withholding Information from Public Disclosure ML16088A0932016-04-0101 April 2016 Request for Withholding Information from Public Disclosure ML15257A2502015-09-28028 September 2015 Request for Withholding Information from Public Disclosure - 6/18/15 Affidavit Executed by L. Trosman, Global Nuclear Fuel - Americas, LLC Core Operating Limits Report, Cycles 28 and 29 ML15230A2452015-08-25025 August 2015 Request for Withholding Information from Public Disclosure - 7/1/15 Affidavit Executed by N. Wilmshurst, Electric Power Research Institute Related to Pressure and Temperature Limits Report for 32 EFPY ML14139A2602014-06-0909 June 2014 Request for Withholding from Public Disclosure, 10/4/2011 Affidavit Executed by E. Schrulll, GE-Hitachi Nuclear Energy Americas LLC, NEDC-33674P, Revision 0 ML14139A2522014-06-0909 June 2014 Request for Withholding from Public Disclosure, 6/18/2013 Affidavit Executed by L. Dolan, GE-Hitachi Nuclear Energy Americas LLC, Enclosure 1 of GEH Letter 7491-317703-HP1-1 ML12291A8132012-11-15015 November 2012 Request for Withholding Information from Public Disclosure - 5/11/2007 Affidavit Executed by Thomas Smed, Studsvik Scandpower Gardel BWR-Cooper Nuclear Station Power Distribution Uncertainties ML12289A0712012-11-15015 November 2012 Request for Withholding Information from Public Disclosure - 9/13/12 Affidavit Executed by L. Trosman, Global Nuclear Fuel - Americas LLC VSP-NPP-HP1-12-087 - Response to RAIs ML12285A1412012-11-15015 November 2012 Request for Withholding Information from Public Disclosure - 4/25/12 Affidavit Executed by L. Trosman, Global Nuclear Fuel - Americas LLC GNF-A Report No. S-0000-0140-2518-R0-P ML1104808522011-11-0101 November 2011 Request for Withholding Information from Public Disclosure, 2/18/11 Affidavit Executed by J. Harrison, GE Hitachi Nuclear Energy, NEDC-33543P, Revision 0 ML0909202862009-04-29029 April 2009 Request for Withholding Information from Public Disclosure ML0823106142008-08-27027 August 2008 Request for Withholding Information from Public Disclosure ML0726700042007-10-0909 October 2007 Request for Withholding Information from Public Disclosure ML0726700022007-10-0909 October 2007 Request for Withholding Information from Public Disclosure ML0704502422007-02-27027 February 2007 Withholding from Public Disclosure, Table 4-1 of Hi (Holtec International)-2043224, MD3349 ML0704003662007-02-27027 February 2007 Request for Withholding Information from Public Disclosure - Global Nuclear Fuel - Americas, LLC 1/24/07 Affidavit ML0235402512002-12-20020 December 2002 Withholding Information from Public Disclosure, TAC No. MB6816 ML0220606232002-08-13013 August 2002 Withholding from Public Disclosure, Proprietary Reports GE-NE-E1200144-04, GE-NE-T2300786-00-09, and GE-NE-T23-00786-00-01, Net Positive Suction Head 2018-07-30
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 1, 2011 Mr. Brian J. O'Grady Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321
SUBJECT:
REQUEST FOR WITHHOLDING INFORMATION FROM PUBLIC DISCLOSURE FOR COOPER NUCLEAR STATION (TAC NO. ME5287)
Dear Mr. O'Grady:
By letter dated January 5, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110100291), Nebraska Public Power District (the licensee) submitted an affidavit dated February 18, 2010, executed by James F. Harrison, GE-Hitachi Nuclear Energy Americas LLC (GEH), requesting that the information contained in the following document be withheld from public disclosure pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 2, Section 2.390:
NEDC-33543P, "Nebraska Public Power District, Cooper Nuclear Station, Safety Relief Valve Capacity and Setpoint Evaluation," Revision 0, dated February 2010.
A nonproprietary copy of this document, designated as NEDO-33543, has been placed in the Nuclear Regulatory Commission's (NRC's) Public Document Room and added to the ADAMS Public Electronic Reading Room under ADAMS Accession No. ML110100292.
The affidavit stated that the submitted information should be considered exempt from mandatory public disclosure for the following reasons:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GEH's competitors without license from GEH constitutes a competitive economic advantage over other companies.
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.
We have reviewed your application and the material in accordance with the requirements of 10 CFR 2.390 and, on the basis of the statements in the affidavit, have determined that the submitted information sought to be withheld contains proprietary commercial information and should be withheld from public disclosure.
B. O'Grady -2 Therefore, NEDC-33543P, "Nebraska Public Power District, Cooper Nuclear Station, Safety Relief Valve Capacity and Setpoint Evaluation," Revision 0, 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, please contact me at 301-415-1377 or via e-mail at Iynnea.wilkins@nrc.gov.
Sincerely, Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298 cc: James F. Harrison Vice President, Fuel Licensing, Regulatory Affairs GE-Hitachi Nuclear Energy Americas LLC P.O. Box 780, MIC A-55 Wilmington, NC 28401 Additional Distribution via Listserv
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