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05000336/LER-1994-003, Application for Amend to License DPR-65,incorporating Addl Requirements Into TS Re non-QA Equipment Utilized to Achieve Feedwater Isolation in Response to MSLB Inside Containment, Per Commitment Made in LER 94-003-00 & Listed I6 May 1994Application for Amend to License DPR-65,incorporating Addl Requirements Into TS Re non-QA Equipment Utilized to Achieve Feedwater Isolation in Response to MSLB Inside Containment, Per Commitment Made in LER 94-003-00 & Listed Insp Repts
05000423/FIN-2014005-02Failure to Manage Risk of RSST Testing
A05437, Responds to 851212 Request for Addl Info to Confirm That Adverse Impact of Completing Degraded Grid Protection Mods Outweighs Intended Improvements.Description of Probabilistic Assessment Results & Design Analysis Encl13 January 1986Responds to 851212 Request for Addl Info to Confirm That Adverse Impact of Completing Degraded Grid Protection Mods Outweighs Intended Improvements.Description of Probabilistic Assessment Results & Design Analysis Encl
A07899, Provides Addl Info Re Undervoltage Detection Mods & Related License Amend Request,Per NRC 890320 Request.Actual Wiring Drawings Represent True Indication of Separation & Redundancy & Design Single Failure Proof25 April 1989Provides Addl Info Re Undervoltage Detection Mods & Related License Amend Request,Per NRC 890320 Request.Actual Wiring Drawings Represent True Indication of Separation & Redundancy & Design Single Failure Proof
B10909, Forwards Remaining Responses & Corresponding FSAR Changes to 640 Series Questions Not Forwarded by Util . Responses Will Be Formally Submitted Along W/Amend 5 by 83110127 September 1983Forwards Remaining Responses & Corresponding FSAR Changes to 640 Series Questions Not Forwarded by Util . Responses Will Be Formally Submitted Along W/Amend 5 by 831101
B11026, Forwards Responses to 840106 Request for Addl Info Re Probabilistic Safety Study.Info Suppls Util 831109 & 840110 Responses.Min Safety Injection Flow Sufficient to Maintain Vessel Mixture Level Core6 February 1984Forwards Responses to 840106 Request for Addl Info Re Probabilistic Safety Study.Info Suppls Util 831109 & 840110 Responses.Min Safety Injection Flow Sufficient to Maintain Vessel Mixture Level Core
B11111, Forwards Response to Draft SER Open Items19 April 1984Forwards Response to Draft SER Open Items
B11138, Forwards Revised Responses to Draft Instrumentation & Control Sys Branch SER Open Items 1,6 & 21,per NRC 840313 Meeting.Responses to Draft SER Open Items 3,7 & 19 Also Encl.Responses Will Be Incorporated in Future FSAR Amend4 May 1984Forwards Revised Responses to Draft Instrumentation & Control Sys Branch SER Open Items 1,6 & 21,per NRC 840313 Meeting.Responses to Draft SER Open Items 3,7 & 19 Also Encl.Responses Will Be Incorporated in Future FSAR Amend
B11185, Forwards Current Status of Procedures & Sys Review Branch Draft SER Open Items & Revised Responses for Open Items PSRB-13,15 & 1815 May 1984Forwards Current Status of Procedures & Sys Review Branch Draft SER Open Items & Revised Responses for Open Items PSRB-13,15 & 18
B11335, Forwards Procedures Re Degraded Grid Voltage,Including Change 2,Rev 4 to OP2347B, Normal Station Svc Transformer 15G-2S & Change 2,Rev 5 to OP 2347A, Reserve Station Svc Transformer 15G-22S4 December 1984Forwards Procedures Re Degraded Grid Voltage,Including Change 2,Rev 4 to OP2347B, Normal Station Svc Transformer 15G-2S & Change 2,Rev 5 to OP 2347A, Reserve Station Svc Transformer 15G-22S
B11497, Forwards Revs to FSAR Sections 8.2 & 8.3 Re Offsite Power Sys & Emergency Switchgear Bus Protection,Respectively, Closing SER (NUREG-1031),Confirmatory Items 44,45,46 & 50 Per J Knox Request1 April 1985Forwards Revs to FSAR Sections 8.2 & 8.3 Re Offsite Power Sys & Emergency Switchgear Bus Protection,Respectively, Closing SER (NUREG-1031),Confirmatory Items 44,45,46 & 50 Per J Knox Request
B11633, Forwards Summaries of Projects Evaluated for Public Safety Impacts & Proprietary Millstone Nuclear Power Station Unit 1 Integrated Safety Assessment Program Public Safety Impact Model. Proprietary Rept Withheld (Ref 10CFR2.790)7 August 1985Forwards Summaries of Projects Evaluated for Public Safety Impacts & Proprietary Millstone Nuclear Power Station Unit 1 Integrated Safety Assessment Program Public Safety Impact Model. Proprietary Rept Withheld (Ref 10CFR2.790)
B11747, Forwards Review of Integrated Safety Assessment Program Topic 1.25, Degraded Grid Voltage Procedures, Resulting from Review of SEP Topics VIII-1.A & VII-3 Per 850517 Commitment9 October 1985Forwards Review of Integrated Safety Assessment Program Topic 1.25, Degraded Grid Voltage Procedures, Resulting from Review of SEP Topics VIII-1.A & VII-3 Per 850517 Commitment
B11930, Discusses Effects of Hurricane Gloria,Including Preparations for Storm & Loss of Offsite Power Events at Millstone Units 1 & 2 on 850927.Advance Notification Associated W/Severe Weather Events Permits Advance Precautionary Actions31 December 1985Discusses Effects of Hurricane Gloria,Including Preparations for Storm & Loss of Offsite Power Events at Millstone Units 1 & 2 on 850927.Advance Notification Associated W/Severe Weather Events Permits Advance Precautionary Actions
B12280, Forwards Pages 3-6,3-15,3-18 & 3-25 Omitted from Section 3 & Isap Topics 1.02,1.16.1,2.06 & 2.07 Omitted from App C of 860731 Isap Final Rept1 October 1986Forwards Pages 3-6,3-15,3-18 & 3-25 Omitted from Section 3 & Isap Topics 1.02,1.16.1,2.06 & 2.07 Omitted from App C of 860731 Isap Final Rept
B12995, Forwards Revised Isap Rept,Including Update on Isap Topic Reviews,Evaluation of New Topics,Integrated Implementation Schedule,List of Existing Topics & long-term Plan for Resolution of Topic 1.06,per 870804 Comments on NUREG-11849 November 1988Forwards Revised Isap Rept,Including Update on Isap Topic Reviews,Evaluation of New Topics,Integrated Implementation Schedule,List of Existing Topics & long-term Plan for Resolution of Topic 1.06,per 870804 Comments on NUREG-1184
B13099, Forwards Rev 2 to Probabilistic Safety Study Update.Advises That Study Update Will Be Integral Part of Util Response to Generic Ltr 88-20.W/three Oversize Figures Encl10 February 1989Forwards Rev 2 to Probabilistic Safety Study Update.Advises That Study Update Will Be Integral Part of Util Response to Generic Ltr 88-20.W/three Oversize Figures Encl
B13175, Forwards Update Re Implementation Status of Improvement Actions Discussed in Util 880527 Response to SALP Board 880329 Recommendations & Addl Info Pertinent to SALP Repts 50-245/86-99 & 50-336/86-9915 June 1989Forwards Update Re Implementation Status of Improvement Actions Discussed in Util 880527 Response to SALP Board 880329 Recommendations & Addl Info Pertinent to SALP Repts 50-245/86-99 & 50-336/86-99
B13180, Responds to NRC Station Blackout Rule Re Plant Capability for Maintaining Core Cooling & Containment Integrity17 April 1989Responds to NRC Station Blackout Rule Re Plant Capability for Maintaining Core Cooling & Containment Integrity
B14267, Application for Amend to License DPR-65,revising TS Table 3.3-3, ESFAS Instrumentation, Item 6.b, Refueling Water Storage Tank-Low, as Result of Sump Recirculation Actuation Signal Logic Design Mods Being Implemented28 October 1992Application for Amend to License DPR-65,revising TS Table 3.3-3, ESFAS Instrumentation, Item 6.b, Refueling Water Storage Tank-Low, as Result of Sump Recirculation Actuation Signal Logic Design Mods Being Implemented
B15380, Application for Amend to License DPR-65,extending AOT When One Offsite Circuit Inoperable from Current 72 H to Seven Days6 October 1995Application for Amend to License DPR-65,extending AOT When One Offsite Circuit Inoperable from Current 72 H to Seven Days
B15403, Forwards Addl Info Re 951006 Proposed Rev to Ts,Extending cycle-specific Ac Sources AOT & Revised Ts,As Identified by NRC in 951012 Telcon23 October 1995Forwards Addl Info Re 951006 Proposed Rev to Ts,Extending cycle-specific Ac Sources AOT & Revised Ts,As Identified by NRC in 951012 Telcon
B15776, Forwards Response to RAI Re 24-month Fuel cycle-electrical Power Systems Surveillance Extensions23 July 1996Forwards Response to RAI Re 24-month Fuel cycle-electrical Power Systems Surveillance Extensions
B15910, Forwards Response to RAI Re Alternate AC Power Source Requirements18 October 1996Forwards Response to RAI Re Alternate AC Power Source Requirements
ENS 44238Loss of Offsite Power
IR 05000236/198801611 August 1988Insp Rept 50-236/88-16 on 880614-0729.No Unsafe Conditions Identified.Major Areas Inspected:Surveillance,Maint. Emergency Preparedness,Physical Security,Nrc Bulletins & Info Notices & Previous Identified Items
IR 05000245/19850243 December 1985Insp Repts 50-245/85-24 & 50-336/85-30 on 850904-1028. Violation Noted:Failure to Make Repts to NRC Per 10CFR50.72 & 10CFR50.73 During Hurricane Gloria
IR 05000245/19850996 May 1985SALP Repts 50-245/85-99 & 50-336/85-99 for Sept 1983 - Feb 1985
IR 05000245/198600911 July 1986Insp Repts 50-245/86-09 & 50-336/86-09 on 860520-0707.No Unacceptable Conditions Noted.Major Areas Inspected:Plant Operations,Surveillance & Maint,Main Turbine & Static O-ring Differential Pressure Switches
IR 05000245/198602213 February 1987Insp Repts 50-245/86-22 & 50-336/86-23 on 861104-870105.No Violation or Deviation Noted.Major Areas Inspected:Plant Operations,Outage Activities,Surveillance Testing,Periodic Repts & Maint
IR 05000245/19870306 January 1988Insp Repts 50-245/87-30 & 50-336/87-25 on 871027-1130. Violations Noted.Major Areas Inspected:Physical Security, Operations,Svc Water Sys Operability,Vital Dc Switchgear Ventilation,Surveillance & LERs
IR 05000245/198901428 July 1989Insp Rept 50-245/89-14 on 890616-0717.No Unsafe Conditions Noted.Major Areas Inspected:Plant Operations,Physical Security,Control Room Exercise Equipment & NRC Temporary Instruction 2513/93
IR 05000245/199720229 August 1997Insp Repts 50-245/97-202,50-336/97-202 & 50-423/97-202 on 970529-0721.Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support,Including Emergency Preparedness Issues & Fire Protection Activities
IR 05000245/199720321 November 1997Insp Repts 50-245/97-203,50-336/97-203 & 50-423/97-203 on 970722-1001.Violations Noted.Major Areas Inspected:Maint, Engineering,Plant Support & Conduct of Operations
IR 05000245/199720825 February 1998Insp Repts 50-245/97-208,50-336/97-208 & 50-423/97-208 on 971201-31.Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support
IR 05000245/199820719 June 1998Insp Repts 50-245/98-207,50-336/98-207 & 50-423/98-207 on 980301-0427.Violations Noted.Major Areas Inspected:Maint, Operations,Engineering & Plant Support
IR 05000245/199821618 November 1998Insp Repts 50-245/98-216,50-336/98-216 & 50-423/98-216 on 980818-1005.Violations Noted.Major Areas Inspected: Operations,Maintenance,Engineering & Plant Support
IR 05000245/2008004
IR 05000245/201200516 January 2013IR 05000336-12-005 and 05000423-12-005; Millstone Power Station - NRC Integrated Inspection Report (10-01-12 - 12-31-12)
IR 05000245/201300211 April 2013IR 05000336-13-002, 05000423-13-002; 01/01/2013 - 03/31/2013: Millstone Power Station Units 2 and 3; Problem Identification and Resolution
IR 05000245/20130048 November 2013Millstone Power Station-NRC Integrated Inspection Report 05000336/2013004 And 05000423/2013004 and Notice of Violation and Independent Spent Fuel Storage Installation Report No. 07200047/2013001
IR 05000245/201300510 February 2014IR 05000336-13-005, 05000423-13-005; 10/01/2013 - 12/31/2013; Millstone Power Station Units 2 and 3; Operability Determinations and Functional Assessments and Other Activities
IR 05000245/201401128 August 2014IR 05000336/2014011, 05000423/2014011; 6/2/14 to 7/15/14; Millstone Power Station, Units 2/3; Electrical System Response; Event Diagnosis and Operator Performance; Special Inspection to review the 5/25/14, Dual-Unit Reactor Trip, Loss of Off-site Power
IR 05000245/201500712 June 2015IR 05000336/2015007, 05000423/2015007; on 3/30/2015 to 5/01/2015; Millstone Power Station, Units 2 and 3; Component Design Bases Inspection
IR 05000245/201600225 July 2016Millstone Power Station - Integrated Inspection Report 05000336/2016002 and 05000423/2016002, 04/01/2016 - 06/30/2016
IR 05000245/20160084 January 2017Errata for Millstone Power Station - NRC Triennial Fire Protection Inspection Report 05000336/2016007 and 05000423/2016007 Amended to 05000336/2016008 and 05000423/2016008
IR 05000336/198700913 April 1987Insp Rept 50-336/87-09 on 870316-19.No Violations or Deviations Noted.Major Areas Inspected:Maint Organization, Program & Activities,Measuring & Test Equipment Program, Trouble Reporting Sys & Insulation Degradation
IR 05000336/198800225 February 1988Insp Rept 50-336/88-02 on 880101-0208.No Violations Noted. Major Areas Inspected:Previously Identified Items,Plant Operations,Surveillance,Radiation Protection,Physical Security,Ie Bulletin Followup & Outage Activities
IR 05000336/19982035 November 1998Insp Rept 50-336/98-203 on 980824-0904.No Violations Noted. Major Areas Inspected:Effectiveness of Configuration Mgt Plan
IR 05000336/199900310 May 1999Insp Rept 50-336/99-03 on 990322-26.No Violations Noted. Major Areas Inspected:Review of Actions Taken by Util to Resolve Significant Issues List Item 21,fire Protection
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