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| Issue date | Title | From | To | |
|---|---|---|---|---|
| NRC Generic Letter 1988-06 | 22 March 1988 | NRC Generic Letter 1988-006: Removal of Organization Charts from Technical Specification Administrative Control Requirements | Miraglia F Office of Nuclear Reactor Regulation | |
| NRC Generic Letter 1989-04 | 3 April 1989 | NRC Generic Letter 1989-004: Guidance on Developing Acceptable Inservice Testing Programs | Varga S Office of Nuclear Reactor Regulation | |
| ML20244A835 | 7 April 1989 | Discusses Inservice Testing Program Review,Per Generic Ltr 89-04.NRC Will Discontinue Review of Rev 3 to Inservice Testing Program | Office of Nuclear Reactor Regulation Swenson W | Fay C WEC Energy Group |
| ML20246F689 | 5 July 1989 | Requests Extension of Deadline for Response to Generic Ltr 89-04 Until 901003 in Order to Submit New 120-month Insp Program.Use of O&M Stds Also Requested | Fay C WEC Energy Group | Office of Nuclear Reactor Regulation Office of Information Resources Management Swenson W |
| ML20248H791 | 3 October 1989 | Forwards Response to Generic Ltr 89-04, Guidance on Inservice Testing Programs. Accident Required Flows Known But Implementing Procedures Need to Be Changed to Ensure Full Flow Through Valves Achieved | Fay C WEC Energy Group | Office of Information Resources Management |
| ML20064B365 | 2 October 1990 | Advises That Mods to RHR & Safety Injection Sys Being Rescheduled for Spring of 1992,per Response to NRC Bulletin 88-004 & Generic Ltr 89-04 Re Min Flow Testing Capabilities for Rhr,Safety Injection & Containment Spray Pumps | Fay C WEC Energy Group | Office of Information Resources Management |
| ML20058E765 | 29 October 1990 | Submits follow-up Response to Generic Ltr 89-04,per | Fay C WEC Energy Group | Office of Information Resources Management |
| ML20066B670 | 18 December 1990 | Rev 0 to Pumps & Valve Inservice Testing Program | WEC Energy Group | |
| ML20066B665 | 21 December 1990 | Forwards Rev 0 to Pump & Valve Inservice Testing Program. Program Satisfies Direction of Generic Ltr 89-04 | Fay C WEC Energy Group | Office of Information Resources Management |
| ML20066K355 | 16 January 1991 | Advises That Response to Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs Complete, Per 891003,900302 & 0628 Ltrs | Fay C WEC Energy Group | Office of Information Resources Management |
| ML20070F504 | 1 March 1991 | Application for Amends to Licenses DPR-24 & DPR-27, Consisting of TS Change Request 143,revising Specs 15.4.8.1 & 15.4.8.1.b to Require Auxiliary Feedwater Pump to Be Started Quarterly | Fay C WEC Energy Group | Office of Information Resources Management |
| ML20024G768 | 22 April 1991 | Lists Difficulties Encountered in Implementing Procedures for Some Sys & Components Added to 1990 Pump & Valve Inservice Test Program,Per Generic Ltr 89-04 | Fay C WEC Energy Group | Office of Information Resources Management |
| ML20079B785 | 28 May 1991 | Pump & Valve Inservice Testing Program Point Beach Nuclear Plant | WEC Energy Group | |
| ML031140549 | 7 November 1991 | Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability | Partlow J Office of Nuclear Reactor Regulation | |
| ML20094M555 | 24 March 1992 | Forwards Requests for Relief from Inservice Insp Program for Pumps & Valves,Per Generic Ltr 89-04.Immediate Implementation of Request Planned Since Util Lacks Installed Method to Precisely Control Flow for Affected Sys | WEC Energy Group Zach J | Office of Information Resources Management |
| ML20097A828 | 6 April 1992 | Technical Evaluation Rept Pump & Valve Inservice Testing Program Point Beach Nuclear Power Plant,Units 1 & 2 Wepc, Per 10CFR50.55a(g) | Brookhaven National Laboratory Dibiasio A Grove E Lofaro R | Office of Nuclear Reactor Regulation |
| ML20113H711 | 30 July 1992 | Addresses IST Program Relief Requests Denied in SER Re IST Program,Third 10-yr Interval.Response to All Items in Anomalies & Actions Items Section of TER Will Be Provided by 930417 | WEC Energy Group Link B | Office of Information Resources Management |
| ML19339H249 | 31 July 1992 | Responds to NRC 920528 Ltr Re Unresolved Items in Insp Repts 50-266/92-08 & 50-301/92-08.Corrective Actions:Ist Program Background Document Will Be Revised to Incorporate Acceptance Criteria for 1992,per Generic Ltr 87-06 | WEC Energy Group Link B | Office of Information Resources Management |
| ML20104B585 | 9 September 1992 | Revises 920731 Response to Unresolved Item Re Position Indication Verification of RHR HX Bypass valve,RHR-00626. Util Will Incorporate Position Indication Verification of RHR-00626 Into IST Program,Per Discussions W/J Smith (NRC) | WEC Energy Group Link B | Office of Information Resources Management |
| Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System | 16 February 1993 | Undetected Modification of Flow Characteristics in High Pressure Safety Injection System | Grimes B Office of Nuclear Reactor Regulation | |
| ML20012G545 | 2 March 1993 | Updates 920730 Response to NRC 920417 Ltr,Transmitting SER & TER of Inservice Testing Program for Pumps & Valves.Listed Relief Requests Re Boric Acid Transfer Pumps & Check Valves Withdrawn | WEC Energy Group Link B | Office of Information Resources Management |
| ML20062J499 | 28 October 1993 | Safety Evaluation Granting IST Relief Requests Per 10CFR50.55a(a)(3)(ii) & 10CFR50.55a(f)(4)(iv) | Office of Nuclear Reactor Regulation | |
| ML20059D206 | 28 December 1993 | Discusses Technique to Be Utilized to Demonstrate That Check Valve 1SI-00876B Has Been Full Stroke Exercised,In Response to NRC Transmitting SER Re Several Outstanding Relief Requests for Ist.Relief Request VRR-4 Encl | WEC Energy Group Link B | Office of Information Resources Management |
| L-96-001, Forwards Request for Time Relief from Previously Approved Relief Request VRR-4 | 18 January 1996 | Forwards Request for Time Relief from Previously Approved Relief Request VRR-4 | WEC Energy Group Maxfield G | Office of Information Resources Management |
| NRC Generic Letter 1996-05 | 18 September 1996 | NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves | Martin T Office of Nuclear Reactor Regulation | |
| ML20134D401 | 12 December 1996 | Instrument Uncertainty Associated W/Flow Instrumentation Used for IT-11 SFP Cooling Pump Inservice Test | WEC Energy Group | |
| ML20137P830 | 12 March 1997 | Post-Maint Testing | WEC Energy Group | |
| ML20198L467 | 2 January 1998 | SER Approving Request for Relief VRR-4B to Inservice Testing Program Wisconsin Electric Power Co,Point Beach Nuclear Plant,Units 1 & 2 | NRC (Affiliation Not Assigned) | |
| ML20154C056 | 30 September 1998 | Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval | WEC Energy Group | |
| NPL-99-0230, Submits Clarification of Which Portions of OMa-1988 Parts 6 & 10 Are Being Utilized at Pbnp for IST Program Implementation & Cold SD & RO Justifications,Per 990218 Telcon with NRC | 19 April 1999 | Submits Clarification of Which Portions of OMa-1988 Parts 6 & 10 Are Being Utilized at Pbnp for IST Program Implementation & Cold SD & RO Justifications,Per 990218 Telcon with NRC | Reddemann M WEC Energy Group | Office of Information Resources Management |
| ML20196J425 | 30 June 1999 | Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 | NRC (Affiliation Not Assigned) | |
| ML030730752 | 5 February 2002 | RCE 01-0169, Increased CDF in AFW PRA Model Due to Procedural Inadequacies Related to Loss of Instrument Air, Report Date: February 5, 2002 | Nuclear Management Co Schroeder J Wood R Peterson L Mende R Krause C Flessner R Staskal T Hettick D | Office of Nuclear Reactor Regulation |
| NRC 2002-0016, ASME Section XI Inservice Testing Program Fourth Interval Relief Requests VRR-1 and PRR-1 | 13 February 2002 | ASME Section XI Inservice Testing Program Fourth Interval Relief Requests VRR-1 and PRR-1 | Nuclear Management Co Webb T | Office of Nuclear Reactor Regulation Document Control Desk |
| ML030760376 | 15 May 2002 | NMC Internal Correspondence, Root Cause Evaluation 01-069, Revision 1 | Nuclear Management Co Hettick D | Nuclear Management Co Warner M Office of Nuclear Reactor Regulation |
| ML030760550 | 7 June 2002 | DBD-01, Auxiliary Feedwater System Design Basis Document, Revision 2, Section 3.4.1 - Attachment B, Page B-2 | Westinghouse Electric Corp | Office of Nuclear Reactor Regulation |
| IR 05000301/2002002 | 24 July 2002 | IR 05000301-02-002, on 03/31/2002 - 06/29/2002, Crystal River Unit 3, Resident Integrated Inspection Report | NRC/RGN-II/DRP/RPB2 West L | Florida Power Corp Young D |
| ML030770538 | 19 September 2002 | DBD-101, Rev. 3, Auxiliary Feedwater System Design Basis Document, Section 3.7 - Attachment B | We Energies | Office of Nuclear Reactor Regulation |
| ML030870888 | 26 November 2002 | Fax from T. C. Kendall, Wisconsin Electric Company, to Ken O'Brien, USNRC, Re Mss Meetings 92-09, 92-11, 92-12 Excerpts, & Excerpts from Revision 0 of AFW Design Basis Document Addressing Recirculation AOV & AFW Recirculation Flow Control O | Nuclear Management Co Kendall T | NRC Region 3 O'Brien K |
| ML030140548 | 30 January 2003 | Relief, Fourth Ten-Year Inservice Testing Interval Relief Request | Raghavan L NRC/NRR/DLPM/LPD3 | Nuclear Management Co Cayia F |
| ML030870344 | 6 February 2003 | Compilation of AFW Corrective Actions, Taken in Response to Potential Common Mode Failure Due to a Loss of Station Air and Operator Actions, Volume 1 of 4 (Provided by Licensee in Response to a Question from Ken O'Brien, Usnrc), State Chang | Nuclear Management Co Kreil J | Office of Nuclear Reactor Regulation |
| ML030870087 | 6 February 2003 | Summary of the Quality Assurance Classification of the Auxiliary Feedwater System Recirculation Line and Components and Associated Attachments Developed by T. C. Kendall, Wisconsin Electric Company in Response to a Request from Ken O'Brien, | Wisconsin Electric Kendall T Braenne R | Office of Nuclear Reactor Regulation |
| ML040860161 | 1 April 2004 | Request for Relief VRR 03-01 on a One Time Basis for Performing Inservice Testing of Relief Valve 1RH-861C | Raghavan L NRC/NRR/DLPM/LPD3 | Vanmiddlesworth G Nuclear Management Co |
| NRC 2022-0032, Sixth 10-Year Interval Inservice Testing (1ST) Program Plan | 30 September 2022 | Sixth 10-Year Interval Inservice Testing (1ST) Program Plan | Point Beach Strand D | Office of Nuclear Reactor Regulation Document Control Desk |