Semantic search

Jump to navigation Jump to search
 Issue dateTitle
05000245/LER-1979-036, Forwards LER 79-036/03L-018 January 1980Forwards LER 79-036/03L-0
A04790, Requests Extension to 860104 for Haddam Neck Re Environ Qualification of Electrical Equipment,Per Generic Ltr 85-15, 10CFR50.49(g) & Integrated Safety Assessment Program.Further Evaluation Proposed for Millstone.Fee Paid30 September 1985Requests Extension to 860104 for Haddam Neck Re Environ Qualification of Electrical Equipment,Per Generic Ltr 85-15, 10CFR50.49(g) & Integrated Safety Assessment Program.Further Evaluation Proposed for Millstone.Fee Paid
A05104, Discusses plant-specific Analysis & Impact on Compliance w/10CFR50.49 Re Environ Qualification of Electrical Equipment.Addl Info Re GE Drywell Temp Analysis & Tables of Drywell Airspace & Wall Temps Encl.Open Item Resolved31 December 1985Discusses plant-specific Analysis & Impact on Compliance w/10CFR50.49 Re Environ Qualification of Electrical Equipment.Addl Info Re GE Drywell Temp Analysis & Tables of Drywell Airspace & Wall Temps Encl.Open Item Resolved
A05610, Responds to Generic Ltr 86-04 Re Policy Statement on Engineering Expertise on Shift.Comparison of INPO Shift Technical Advisor Guidelines W/Established Bachelors Degree Programs in Engineering Encl13 June 1986Responds to Generic Ltr 86-04 Re Policy Statement on Engineering Expertise on Shift.Comparison of INPO Shift Technical Advisor Guidelines W/Established Bachelors Degree Programs in Engineering Encl
A08949, Responds to Comments Identified in Insp Rept 50-423/90-80 Re EOP at Millstone Unit 34 October 1990Responds to Comments Identified in Insp Rept 50-423/90-80 Re EOP at Millstone Unit 3
B11537, Responds to 850402 Request for Addl Info Re Integrated Safety Assessment Program (Isap) Review.Description of All Plant Betterment Projects & Engineering Studies to Be Included in Isap Review Encl17 May 1985Responds to 850402 Request for Addl Info Re Integrated Safety Assessment Program (Isap) Review.Description of All Plant Betterment Projects & Engineering Studies to Be Included in Isap Review Encl
B11637, Forwards Addl Info Re App R Exemption Requests,Per 850627 Request.Measure of Protection Used to Ensure Switchboard Wire Associated W/Msiv Solenoid Valves Will Not Be Susceptible to Hot Shorts Discussed7 August 1985Forwards Addl Info Re App R Exemption Requests,Per 850627 Request.Measure of Protection Used to Ensure Switchboard Wire Associated W/Msiv Solenoid Valves Will Not Be Susceptible to Hot Shorts Discussed
B11665, Forwards Reviews of Planned Integrated Safety Assessment Program,Topics 2.03,2.20,2.25 & 2.27,including Process Computer Replacement,Drywell Temp Monitoring Sys & Spare Recirculation Pump Motor,Per 850731 Request6 September 1985Forwards Reviews of Planned Integrated Safety Assessment Program,Topics 2.03,2.20,2.25 & 2.27,including Process Computer Replacement,Drywell Temp Monitoring Sys & Spare Recirculation Pump Motor,Per 850731 Request
B11695, Forwards Review of Integrated Safety Assessment Program Topic 1.29, Response to Generic Ltr 81-34, Re Evaluation of Facility Scram Discharge Vol Design Against Guidelines in NUREG-0803.Further Analyses or Mods Unnecessary13 September 1985Forwards Review of Integrated Safety Assessment Program Topic 1.29, Response to Generic Ltr 81-34, Re Evaluation of Facility Scram Discharge Vol Design Against Guidelines in NUREG-0803.Further Analyses or Mods Unnecessary
B11731, Forwards Addl Info Re Draft Tech Specs,Per 850906 Meeting. Encls Include Responses to Specific Tech Spec & SER Items19 September 1985Forwards Addl Info Re Draft Tech Specs,Per 850906 Meeting. Encls Include Responses to Specific Tech Spec & SER Items
B11736, Forwards Addl Responses to Questions Raised Re Proof & Review Tech Specs.Marked-up Tech Specs Encl20 September 1985Forwards Addl Responses to Questions Raised Re Proof & Review Tech Specs.Marked-up Tech Specs Encl
B11794, Submits for Review,Integrated Safety Assessment Program Topics 1.16.1, MP1/MP2 Backfeed, 1.16.2, Modify CRD Pumps, 1.16.3, Alternative Cooling for Shutdown Equipment, & 1.16.4, Power Cold Shutdown Equipment16 October 1985Submits for Review,Integrated Safety Assessment Program Topics 1.16.1, MP1/MP2 Backfeed, 1.16.2, Modify CRD Pumps, 1.16.3, Alternative Cooling for Shutdown Equipment, & 1.16.4, Power Cold Shutdown Equipment
B11795, Forwards Reviews of Integrated Safety Assessment Program, Topic 1.06, Seismic Qualification of Safety-Related Piping & Topic 1.13, BWR Vessel Water Level Instrumentation, Per 850517 Commitment11 October 1985Forwards Reviews of Integrated Safety Assessment Program, Topic 1.06, Seismic Qualification of Safety-Related Piping & Topic 1.13, BWR Vessel Water Level Instrumentation, Per 850517 Commitment
B11805, Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A23 October 1985Forwards Reviews of Integrated Safety Assessment Program Topics 1.43 Re Water hammer,1.44 Re Asymmetric Blowdown Loads on Reactor Sys & 1.48 Re Safety Factor for Penetration X-10A
B12000, Proposed Tech Spec Revs,Expanding Storage Capacity of Spent Fuel Pool by Storing Consolidated Spent Fuel in Fuel Storage Racks31 May 1986Proposed Tech Spec Revs,Expanding Storage Capacity of Spent Fuel Pool by Storing Consolidated Spent Fuel in Fuel Storage Racks
B12024, :Response to Info Requested Re Station Blackout, Technical Review31 March 1986
Response to Info Requested Re Station Blackout, Technical Review
B12965, Drywell Insulation Study31 July 1988Drywell Insulation Study
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
B13747, Proposed Tech Specs Section 3.3.3.6 Re Accident Monitoring instrumentation--reactor Vessel Monitoring27 July 1992Proposed Tech Specs Section 3.3.3.6 Re Accident Monitoring instrumentation--reactor Vessel Monitoring
B14323, Forwards Dpl for Millstone Unit 1,2,3 & Haddam Neck Plant. Dpl Lists Data Points That Will Be Transmitted for Erds. Update to ERDS Will Incorporate Changes Identified During Sys Testing Performed W/Nrc Contractor6 January 1993Forwards Dpl for Millstone Unit 1,2,3 & Haddam Neck Plant. Dpl Lists Data Points That Will Be Transmitted for Erds. Update to ERDS Will Incorporate Changes Identified During Sys Testing Performed W/Nrc Contractor
B14846, Proposed Tech Specs Re GL 93-05 & Various Administrative Changes marked-up Pages2 June 1994Proposed Tech Specs Re GL 93-05 & Various Administrative Changes marked-up Pages
B17758, Informs NRC Staff That Changes to Unit 2 ERDS Data Point Library Were Implemented on 990325.Changes Resulted from Changes Made to Unit 2 Safety Parameter Display Sys22 April 1999Informs NRC Staff That Changes to Unit 2 ERDS Data Point Library Were Implemented on 990325.Changes Resulted from Changes Made to Unit 2 Safety Parameter Display Sys
DD-97-21, Partial Director'S Decision DD-97-21 Denying Request for Immediate Suspension or Revocation of Licenses & Granting Request for Investigation of Possible Matl Misrepresentations,In Response to 961125 & 1223 Petitions12 September 1997Partial Director'S Decision DD-97-21 Denying Request for Immediate Suspension or Revocation of Licenses & Granting Request for Investigation of Possible Matl Misrepresentations,In Response to 961125 & 1223 Petitions
IA-85-771, Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities3 January 1986Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities
IR 05000245/19850264 April 1986Insp Repts 50-245/85-26 & 50-336/85-32 on 851029-1230.No Violation Noted.Major Areas Inspected:Plant Operations, Equipment Alignment & Readiness,Radiation Protection, Physical Security & Fire Protection
IR 05000245/198701821 September 1987Safety Insp Rept 50-245/87-18 on 870731-0807.No Violations or Deviations Noted.Major Areas Inspected:Test Witnessing, Preliminary Results Evaluation of Containment Integrated Leak Rate Test & Tours of Facility
IR 05000245/19870278 December 1987Insp Repts 50-245/87-27 & 50-336/87-23 on 870926-1026.No Violation Noted.Major Areas Inspected:Physical Security, Plant Operations,Surveillance & Maint Activities,Fuel Receipt & IE Bulletin 87-00l Followup
IR 05000245/198801617 March 1989Exam Rept 50-245/88-16OL on 881107-10.Exam Results:All Reactor Operator Candidates Passed Exams.Six Senior Reactor Operator (SRO) Candidates Passed Written Exam & Operating Test.One SRO Candidate Failed Written Exam
IR 05000245/19880992 October 1989SALP Repts 50-245/88-99 & 50-336/88-99 for 880101-890615
IR 05000336/198701117 July 1987Insp Rept 50-336/87-11 on 870519-0629.No Violation Noted. Major Areas Inspected:Daily Operations,Backshift & Weekend Operations,App R Electrical Mod & Control Board Enchancement
IR 05000336/200400629 July 2004IR 05000336-04-006, IR 05000423-04-006, on 04/01/2004 - 06/30/2004; Millstone Power Station, Unit 2 and Unit 3; Surveillance Testing, Other Activities
IR 05000336/202000212 August 2020Integrated Inspection Report 05000336/2020002 and 05000423/2020002
IR 05000423/198900811 July 1989Insp Rept 50-423/89-08 on 890515-0612.No Violations Noted. Major Areas Inspected:Plant Operations,Unresolved Item 50-423/87-12-01,previous Insp Findings,Plant Incident Repts, in-core Thimble Degradation & 10CFR50.59 Safety Evalautions
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
ML01344033811 January 2002Issuance of Amendment 263 Changes to TS Definitions for Core Alteration & Refueling Operations (Tac No. MB1779)
ML02052022520 February 2002Issuance of Amendment, Fuel Handling Accidents Inside Containment and Ventilation Systems (Tac No. MA9364)
Retrieved from "https://kanterella.com/Special:Ask"