Pages that link to "Clemens R"
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The following pages link to Clemens R:
Displayed 46 items.
- ML11188A074 (← links)
- LIC-09-0043, Response to Request for Additional Information Concerning License Amendment Request (LAR) 09-01, Steam Generator Blowdown Isolation Operability and Testing Requirements (← links)
- LIC-09-0020, Response to NRC Regulatory Issue Summary 2006-21 (← links)
- LIC-09-0028, Omaha Public Power District - 30-Day Report of a Significant Change/Error in the Loss of Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46 (← links)
- LIC-08-0076, Transmittal of Affidavit to Withhold Proprietary Information Enclosed in NRC Trip Report Regarding Fort Calhoun Station Sump Strainer Head Loss Testing During February 18-19, 2008 (← links)
- LIC-08-0053, Announcement of New Licensing Manager at Fort Calhoun Station (← links)
- LIC-08-0039, Omaha Public Power District Transmittal of 2007 Annual Financial Report (← links)
- LIC-08-0021, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (← links)
- LIC-08-0012, Clarification of Fort Calhoun Station Technical Specification 2.7(2)j (← links)
- LIC-09-0083, Response to Request for Additional Information Regarding Steam Generator Tube Inservice Inspections During 2008 Refueling Outage (← links)
- LIC-09-0046, Extended Power Uprate (EPU) Input Deck for Nuclear Regulation (NRR) Confirmatory Analyses (← links)
- LIC-09-0036, License Amendment Request 09-03,Revision to Technical Specifications Sections 2.0.1 & 2.7 for Inoperable System, Subsystem or Component Due to Inoperable Power Source & Deletion of Diesel Generator Surveillance Requirements 3.7(1)e (← links)
- LIC-09-0034, Revision to License Amendment Request (LAR) 08-03, Clarify Technical Specification 2.7(2) Regarding Preferred Offsite Power Source, Transformer Allowed Outage Time (AOT) (← links)
- LIC-09-0021, Clarification of B.5.b Commitments (← links)
- LIC-09-0026, Annual Report for 2008 Loss (Loca)/Emergency Core Cooling Pursuant to 10 CFR 50.46 of Coolant Accident System (ECCS) Models (← links)
- LIC-09-0025, Extended Power Uprate Data for Nuclear Reactor Regulation (NRR) Confirmatory Analyses (← links)
- LIC-09-0004, License Amendment Request (LAR) 09-01, Steam Generator Blowdown Isolation Operability and Testing Requirements (← links)
- LIC-09-0008, License Amendment Request for Adoption of TSTF-511, Rev 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. (← links)
- LIC-08-0120, Steam Generator Eddy Current Test Report - 2008 Refueling Outage (← links)
- LIC-08-0098, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Change of Commitment for Close-out Letter Submittal (← links)
- LIC-08-0078, License Amendment Request, Administrative Revisions to Fort Calhoun Station, Unit No. 1, Technical Specifications (← links)
- LIC-08-0066, Request for Relief Pertaining to Liquid Penetrant Acceptance Criteria for Replacement Safety Injection and Refueling Water Tank (SIRWT) Outlet Header Level Control Valve (← links)
- LIC-08-0048, Submittal of Annual Report for 2007 Loss of Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46 (← links)
- LIC-08-0034, Response to Second Round Request for Additional Information Regarding Containment Analysis for Fort Calhoun Station Water Management License Request Amendment Request (← links)
- LIC-07-0082, License Amendment Request (LAR) Permanent Use of Sodium Tetraborate as the Containment Building Sump Buffering Agent. (← links)
- LIC-09-0088, Request for Use of an Alternate Depth Sizing Qualification (← links)
- LIC-08-0112, Retraction of License Amendment Request (Lar), Revision to Technical Specification (TS) 2.5(1)A, Auxiliary Feedwater (AFW) System (← links)
- LIC-07-0037, Special Report on the Containment Tendon Prestressing System, Free Water Found in Dome Tendon D230P (← links)
- LIC-08-0109, Response to Request for Additional Information Concerning Exemption from Requirements of 10 CFR 50, Appendix R, Section Iii.G.B. for Fire Area 31 (← links)
- LIC-08-0102, Refueling Outage Inservice Inspection Results and NIS-1 and NIS-2 Forms (← links)
- LIC-08-0067, Response to Request for Additional Information Relief Request for Valve Replacement and Supplemental Information (← links)
- LIC-08-0040, Response to Request for Additional Information License Amendment Request Modification of Containment Spray Actuation Logic (MD6204) (← links)
- LIC-08-0006, Request for Exemption from Requirements of 10 CFR 50, Appendix R, Section III.G.1.b. for Fire Area 31 (← links)
- ET 11-0010, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, Core Operating Limits Report for Large Break Loss-of-Coolant Accident Analysis Methodology (← links)
- ET 11-0008, (WCGS) - Results of the Seventeenth Steam Generator Tube Inservice Inspection (← links)
- ML033030498 (← links)
- ML032970135 (← links)
- ML032960189 (← links)
- LIC-03-0105, Day Response to NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. (← links)
- LIC-03-0097, Omaha Public Power District (OPPD) Revised Response to NRC Generic Letter 96-05: Periodic Verification of Design Basis Capability of Safety Related Motor Operated Valves (← links)
- LIC-03-0110, Unit No.1 TS Updated for NRC Comments on Pending Amendment Request on Pressure-Temperature Limits Report (← links)
- ML032160582 (← links)
- ML031890327 (← links)
- LIC-03-0086, May 2003 Monthly Operating Report for Fort Calhoun Unit 1 (← links)
- LIC-03-0070, Answer, Response and Request for Clarification in Response to Commission Order Requiring Compliance with Revised Design Basis Threat for Operating Power Reactors (← links)
- LIC-03-0074, Answer, Response and Request for Clarification in Response to Commission Order for Compensatory Measures Related to Training Enhancements on Tactical and Firearms Proficiency and Physical Fitness Applicable to Armed Nuclear Power Plant S (← links)