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Issue date | Title | |
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IR 05000412/1999301 | 20 April 1999 | NRC Operator Licensing Exam Rept 50-412/99-301(including Completed & Graded Tests) for Tests Administered on 990322- 25.All Applicants Passed All Portions of Exams |
IR 05000412/2005017 | 29 May 1985 | Insp Rept 50-416/85-14 on 850412-0517.No Violation or Deviation Noted.Major Areas Inspected:Operational Safety Verification,Maint Observation,Surveillance Observation, Startup Testing,Independent Insp & ROs |
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units | 23 March 1990 | Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units |
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown | 25 February 1992 | Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown |
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels | 10 August 1993 | Thermal Stratification of Water in BWR Reactor Vessels |
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 | 15 July 1994 | Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 |
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel |
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown | 18 June 1996 | Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown |
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power | 22 October 1996 | Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power |
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown | 11 December 1996 | Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown |
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown | 5 December 1997 | Recent Events Involving Reactor Coolant System Inventory Control During Shutdown |
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick | 5 May 1999 | Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick |
L-02-108, Emergency Preparedness Plan and Implementing Procedures (Volumes 1, 2 & 3) | 16 November 2002 | Emergency Preparedness Plan and Implementing Procedures (Volumes 1, 2 & 3) |
L-04-039, Emergency Response Data System (ERDS) | 22 April 2004 | Emergency Response Data System (ERDS) |
L-04-122, A5.735A, Rev 27, Emergency Preparedness Plan. | 23 September 2004 | A5.735A, Rev 27, Emergency Preparedness Plan. |
L-05-022, License Amendment Request Nos. 314 and 187 Re Radiation & Accident Monitoring Technical Specification Requirements | 22 February 2005 | License Amendment Request Nos. 314 and 187 Re Radiation & Accident Monitoring Technical Specification Requirements |
L-06-151, Emergency Response Data System | 23 October 2006 | Emergency Response Data System |
L-07-017, License Amendment Requests Nos. 334 and 205 | 9 February 2007 | License Amendment Requests Nos. 334 and 205 |
L-07-053, Submittal of Changes to Data Point Libraries for the Emergency Response Data System | 28 March 2007 | Submittal of Changes to Data Point Libraries for the Emergency Response Data System |
L-09-168, Emergency Response Data System Data Point Library Update | 25 June 2009 | Emergency Response Data System Data Point Library Update |
L-11-320, Request NRC Approval of Proposed Emergency Preparedness Plan Using Nuclear Energy Institute 99-01 Revision 5 Methodology | 21 December 2011 | Request NRC Approval of Proposed Emergency Preparedness Plan Using Nuclear Energy Institute 99-01 Revision 5 Methodology |
L-12-326, Response to a Request for Additional Information on a Proposed Emergency Preparedness Plan Revision | 28 September 2012 | Response to a Request for Additional Information on a Proposed Emergency Preparedness Plan Revision |
L-17-104, Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan | 20 May 2017 | Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan |
L-20-295, Emergency Plan Amendment Request | 14 June 2021 | Emergency Plan Amendment Request |
L-21-238, License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident | 31 August 2022 | License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident |
ML020150612 | 7 January 2002 | Part 1 of 2, Beaver Valley Units 1 & 2, Emergency Preparedness Implementing Procedures |
ML031150585 | 29 January 1985 | Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations |
ML040710474 | 2 March 2004 | Emergency Preparedness Plan |
ML042610147 | 5 March 2004 | Condition Report 03-08460, Fire Protection Safe Shutdown Analysis of high-low Pressure Interface |
ML052720291 | 5 November 2009 | Current Facility Operating License No. DPR-66, Technical Specifications, Revised 03/02/2018 |
ML060940416 | 3 March 2006 | ITS Conversion SE - BVPS Doc Table L |
ML070390024 | 21 February 2007 | BVPS Doc Table L |
ML070390284 | 21 February 2007 | Improved Technical Specifications |
ML082380437 | 18 August 2008 | Emergency Preparedness Plan, Consisting of Rev. 26 to Section 4, Emergency Conditions. |
ML092950305 | 5 November 2009 | Technical Specifications, Appendices a, B, and C |
ML16277A113 | 28 September 2016 | Beaver Valley Power Station, Unit Nos. 1 and 2, Request for Licensing Action to Revise the Emergency Plan |
ML20003G119 | 15 April 1981 | Forwards Evaluation Rept of Inadequate Core Cooling Instrument Sys Conformance to NUREG-0737 Item II.F.2,per 801231 Ltr.Evaluation of Core Exit Thermocouples to Be Submitted by 810701 |
ML20062L616 | 25 May 1982 | Responds to NRC Re Violations Noted in IE Insp Rept 50-334/82-05 & 820304 Confirmatory Action Ltr 82-06. Corrective Actions:Eds Nuclear,Inc Audit Verified Compliance of NUREG-0737-related Design Mods |
ML20073G291 | 23 March 1983 | Rept of Facility Changes,Tests & Experiments,1982 |
ML20093G620 | 16 July 1984 | Forwards Addl Info on NUREG-0737,Item II.B.3 Re post- Accident Sampling Sys,In Response to 840420 Request.Core Damage Assessment Procedure,Utilizing Westinghouse Owners Group post-accident Core Damage Assessment Methodology,Encl |
ML20116A309 | 18 July 1996 | Forwards Bvps,Unit 1 Emergency Response Data Sys Input IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394, Rev 1,Section 3.6, Administrative Implementation Requirements |
ML20116N925 | 16 November 1992 | Forwards Input for Beaver Valley Power Station ERDS Data Point Library |
ML20132H255 | 18 September 1985 | 1985 Annual Emergency Preparedness Exercise on 850918-20 |
ML20137K874 | 3 April 1997 | Provides Data Point Library Changes IAW 10CFR50,App E, Section VI.3.a & NUREG-1394,Rev 1,Section 3.6 |
ML20160A079 | 20 May 2020 | Technical Specification Bases Update Status, Revision 37 (Part 1 of 2) |
ML20203C355 | 11 April 1986 | Forwards Response to Questions Re Open Issue 3 Concerning Inadequate Core Cooling & Revised Description of Instrumentation for Detection of Inadequate Core Cooling,Per NRC 860303 Request |