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 Issue dateTitle
IR 05000412/199930120 April 1999NRC 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 05000412/200501729 May 1985Insp 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 Units23 March 1990Unanticipated 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 Draindown25 February 1992Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 115 July 1994Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power22 October 1996Problems 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 Shutdown11 December 1996Undetected 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 Shutdown5 December 1997Recent 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, & FitzPatrick5 May 1999Unanticipated 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 2002Emergency Preparedness Plan and Implementing Procedures (Volumes 1, 2 & 3)
L-04-039, Emergency Response Data System (ERDS)22 April 2004Emergency Response Data System (ERDS)
L-04-122, A5.735A, Rev 27, Emergency Preparedness Plan.23 September 2004A5.735A, Rev 27, Emergency Preparedness Plan.
L-05-022, License Amendment Request Nos. 314 and 187 Re Radiation & Accident Monitoring Technical Specification Requirements22 February 2005License Amendment Request Nos. 314 and 187 Re Radiation & Accident Monitoring Technical Specification Requirements
L-06-151, Emergency Response Data System23 October 2006Emergency Response Data System
L-07-017, License Amendment Requests Nos. 334 and 2059 February 2007License Amendment Requests Nos. 334 and 205
L-07-053, Submittal of Changes to Data Point Libraries for the Emergency Response Data System28 March 2007Submittal of Changes to Data Point Libraries for the Emergency Response Data System
L-09-168, Emergency Response Data System Data Point Library Update25 June 2009Emergency 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 Methodology21 December 2011Request 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 Revision28 September 2012Response 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 Plan20 May 2017Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan
L-20-295, Emergency Plan Amendment Request14 June 2021Emergency 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 Accident31 August 2022License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident
ML0201506127 January 2002Part 1 of 2, Beaver Valley Units 1 & 2, Emergency Preparedness Implementing Procedures
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML0407104742 March 2004Emergency Preparedness Plan
ML0426101475 March 2004Condition Report 03-08460, Fire Protection Safe Shutdown Analysis of high-low Pressure Interface
ML0527202915 November 2009Current Facility Operating License No. DPR-66, Technical Specifications, Revised 03/02/2018
ML0609404163 March 2006ITS Conversion SE - BVPS Doc Table L
ML07039002421 February 2007BVPS Doc Table L
ML07039028421 February 2007Improved Technical Specifications
ML08238043718 August 2008Emergency Preparedness Plan, Consisting of Rev. 26 to Section 4, Emergency Conditions.
ML0929503055 November 2009Technical Specifications, Appendices a, B, and C
ML16277A11328 September 2016Beaver Valley Power Station, Unit Nos. 1 and 2, Request for Licensing Action to Revise the Emergency Plan
ML20003G11915 April 1981Forwards 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
ML20062L61625 May 1982Responds 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
ML20073G29123 March 1983Rept of Facility Changes,Tests & Experiments,1982
ML20093G62016 July 1984Forwards 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
ML20116A30918 July 1996Forwards 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
ML20116N92516 November 1992Forwards Input for Beaver Valley Power Station ERDS Data Point Library
ML20132H25518 September 19851985 Annual Emergency Preparedness Exercise on 850918-20
ML20137K8743 April 1997Provides Data Point Library Changes IAW 10CFR50,App E, Section VI.3.a & NUREG-1394,Rev 1,Section 3.6
ML20160A07920 May 2020Technical Specification Bases Update Status, Revision 37 (Part 1 of 2)
ML20203C35511 April 1986Forwards 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