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Issue date | Title | |
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ML18093A919 | 8 March 2018 | Revision 31 to Updated Safety Analysis Report, Chapter 18, Response to NUREG-0737 Clarification of TMI Action Plan Requirements. Redacted |
ML19092A077 | 11 March 2019 | Revision 32 to Updated Safety Analysis Report, Chapter 7, Instrumentation and Controls |
ML19092A092 | 11 March 2019 | Revision 32 to Updated Safety Analysis Report, Chapter 18, Response to NUREG-0737 Clarification of TMI Action Plan Requirements |
ML19332F184 | 30 November 1989 | Application for Amend to License NPF-42,revising Tech Specs 3.4.1.4.2,3.5.4,4.9.8.1 & 4.9.8.2 Re RHR Flow & Safety Injection Pump Availability |
ML20008G259 | 30 June 1981 | Forwards Response to NUREG-0737, Clarification of TMI Action Plan Requirements. Response Will Be Issued as Chapter 18 of FSAR & Will Be Incorporated in Fsar,Revision 5,currently Scheduled for Jul 1981 Publication |
ML20010J013 | 24 September 1981 | Forwards Response to NRC 810901 Request for Addl Info Re NUREG-0737,Item II.F.2,instrumentation for Detection of Inadequate Core Cooling.Info Will Be Incorporated in Future Revision to FSAR |
ML20058N556 | 17 December 1993 | Transmits Changes to Data Point Library Resulting from Change in Power Rating for Plant,Software Mods That Affected Transmitted Data Points & Editorial Corrections,Per 10CFR50,App E,VI.3.a (ERDS) |
ML20069B568 | 24 May 1994 | Proposed Tech Specs,Incorporating Improvements in Scope & Content Endorsed by NRC in Final Policy Statement on TS Improvements for Nuclear Power Reactors,58FR39132,dtd 930722 |
ML20073L515 | 15 April 1983 | Forwards Response to Generic Ltr 82-33,Suppl 1 to NUREG-0737 Re Requirements for Emergency Response Capability.Due to Const & Licensing Status at Time TMI Requirements Were Issued,Requirements Were Addressed in Chapter 18 of FSARs |
ML20082D944 | 6 April 1995 | Proposed Tech Specs Re Incorporation in Scope & Content Endorsed by NRC for License NPF-42 |
ML20084C203 | 10 April 1984 | Rev 0 to Procedure EDP-ZZ-00005, Assessing Core Damage |
ML20086M585 | 13 December 1991 | Forwards Data Point Library & Critical Safety Function Parameters Data Points,Revised to Better Provide Info Requested in NUREG-1394,Rev 1, Emergency Response Data Sys (ERDS) Implementation |
ML20092H314 | 16 May 1984 | Rev 1 to Engineering Departmental Procedure EDP-ZZ-00005, Assessing Core Damage |
ML20126E388 | 3 June 1985 | Transcript of Commission 850603 Meeting in Washington,Dc Re Discussion/Possible Vote on Full Power OL for Facility. Pp 1-46 |
ML20137T603 | 27 November 1985 | Startup Rept for Cycle 1 |
ML20153G730 | 23 September 1998 | Special Rept 98-003:on 980814,station Entered TS 3.3.3.6, Action Statment a Due to Inoperability of RVLIS B Train. Cause Has Not Yet Been Identified.Work Order 98-202813-000 Has Been Generated |
ML20195E759 | 10 November 1998 | WCNOC Proposed PASS Function Reduction |
ML20196K732 | 26 March 1999 | Proposed Tech Specs Converting to Improved Tech Specs |
ML20203C958 | 2 February 1999 | Forwards Rev to 830804 Response to GL 81-07, Control of Heavy Loads. Util Revised RB Analyses Section of Rept to Clarify Control of Movement of Heavy Loads Over Two RHR Loops During Shutdown & Refueling Conditions |
ML20207J202 | 5 March 1999 | Proposed Tech Specs Re Conversion to ITS Section 1,0,3.1, 3.2,3.3,3.4,3.6,3.7,3.8,3.9,4.0 & 5.0 |
ML20207L040 | 5 March 1999 | Suppl 1 to 970515 Application for Amend to License NPF-42 Incorporating Changes to WCGS TSs & Adding License Conditions to Address Surveillance Requirements.Suppl Submits Mods Submitted to NRC During Review Process |
ML20215E377 | 15 December 1986 | Provides Status of License Condition 2.C.(7),Attachment 3, Item (3) Re Reg Guide 1.97 Instrumentation.Listed Instruments Installed & Maintained Per Plant Procedures |
ML20217F748 | 14 October 1999 | Informs That Based on Approval of Core Assessment Damage Guidance in WCAP-14696,rev 1 for Westinghouse Nuclear Power Plants,Licensee May Use WCAP-14696,rev 1 at Wolf Creek Generating Station |
ML20249B577 | 16 June 1998 | Refers to WCNOC 970515 Proposed License Amend to Convert Current TS for Unit 1 to Improved Sts.Licensee Should Responds to Encl RAI within 30 Days of Ltr Date |
ML20290A575 | 23 July 2020 | Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, Chapter 7, Instrumentation and Controls |
ML20290A586 | 23 July 2020 | Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, Chapter 18, Response to NUREG-0737, Clarification of TMI Action Plan Requirements |
ML21053A117 | 8 April 2021 | 1 - Issuance of Amendment No. 227 TS Change Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Based on TSTF-425 |
ML21168A106 | 7 June 2021 | 4 to Updated Safety Analysis Report, Chapter 18, Response to NUREG-0737 Clarification of TMI Action Plan Requirements |
ML21168A116 | 7 June 2021 | 4 to Updated Safety Analysis Report, Chapter 7, Instrumentation and Controls |
ML22067A030 | 8 March 2022 | Changes to Technical Specification Bases - Revisions 86, 87, 88, 89, and 90 |
ML22151A142 | 18 May 2022 | 5 to Updated Safety Analysis Report, Chapter 18, Response to NUREG-0737 Clarification of TMI Action Plan Requirements - Part 1 of 2 |
ML22151A153 | 18 May 2022 | 5 to Updated Safety Analysis Report, Chapter 7, Instrumentation and Controls |
ML23135A173 | 8 May 2023 | 6 to Updated Safety Analysis Report, Chapter 7, Instrumentation and Controls |
ML23135A184 | 8 May 2023 | 6 to Updated Safety Analysis Report, Chapter 18, Response to NUREG-0737 Clarification of TMI Action Plan Requirements - Part 1 of 2 |
ML24114A127 | 15 April 2024 | Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 18, Response to NUREG-0737 Clarification of TMI Action Plan Requirements |
ML24114A138 | 15 April 2024 | Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 7, Instrumentation and Controls |
NEI 99-01, Wolf Creek Generating Station Proposed Revised EAL Technical Basis Document | 12 September 2016 | Wolf Creek Generating Station Proposed Revised EAL Technical Basis Document |
NEI 99-01, Wolf Creek Nuclear Operating Corporation Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors | 30 September 2016 | Wolf Creek Nuclear Operating Corporation Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors |
NRC Generic Letter 1985-02 | 17 April 1985 | NRC Generic Letter 1985-002: Staff Recommended Actions Stemming from NRC Integrated Program for the Resolution of Unresolved Safety Issues Regarding Steam Generator Tube Integrity |
NRC Generic Letter 1985-05 | 31 January 1985 | NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events |
NRC Generic Letter 1985-07 | 2 May 1985 | NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications |
NRC Generic Letter 1985-08 | 23 May 1985 | NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format |
NRC Generic Letter 1992-04 | 19 August 1992 | NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F) |
NRC Generic Letter 1998-02 | 28 May 1998 | NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition |
NRC-84-0046, Forwards Requested Changes to Final Draft Tech Specs.List of Tech Specs Discussed W/Description of Status & Action Required Also Encl | 20 March 1984 | Forwards Requested Changes to Final Draft Tech Specs.List of Tech Specs Discussed W/Description of Status & Action Required Also Encl |
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 18.0 - Response to NUREG-0737 Clarification of TMI Action Plan Requirements | 31 May 2016 | Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 18.0 - Response to NUREG-0737 Clarification of TMI Action Plan Requirements |
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and Controls | 31 May 2016 | Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and Controls |
WO 02-0004, Revision to Technical Specifications Re Suspension of Positive Reactivity Additions | 21 February 2002 | Revision to Technical Specifications Re Suspension of Positive Reactivity Additions |
WO 02-0062, Changes to Wolf Creek Radiological Emergency Response Plan, Implementing Procedures and Form | 19 December 2002 | Changes to Wolf Creek Radiological Emergency Response Plan, Implementing Procedures and Form |
WO 03-0024, Special Report 2003-001 for Wolf Creek Re Unavailability of Post Accident Monitoring Equipment | 15 April 2003 | Special Report 2003-001 for Wolf Creek Re Unavailability of Post Accident Monitoring Equipment |