Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20207D8781998-12-0808 December 1998
Rev 1 to EMF-98-015, Millstone Unit 2 Loss of Normal FW Flow Transient with Reduced Auxiliary FW Flow
ML20217J0691997-08-31031 August 1997
Non-proprietary Rev 5 to WCAP-10992, Westinghouse Setpoint Methodology for Protection Systems,Mnps,Unit 3,24-Month Fuel Cycle Evaluation
ML20148P1771997-02-28028 February 1997
Rev 0 to Millstone Unit 2 Uncontrolled CEA Bank Withdrawal from Subcritical/Startup Analysis
ML20086S3221995-06-30030 June 1995
Rev 4 to WCAP-10992, W Setpoint Methodology for Protection Systems,Millstone Nuclear Power Station Unit 3 24 Month Fuel Cycle Evaluation
ML20080T8361995-01-0303 January 1995
Physics Methodology for PWR Reload Design, Addendum 4
ML20086H4721991-11-30030 November 1991
Analysis of Capsule W-104 Northeast Nuclear Energy Co Millstone Nuclear Power Station,Unit 2 - Reactor Vessel Matl Surveillance Program
ML20095L4291991-10-31031 October 1991
Nonproprietary Margin to Overfill Analysis for SGTR for Millstone Nuclear Power Station Unit 3 Three-Loop Operation
ML20095L4171991-08-31031 August 1991
Nonproprietary Margin to Overfill Analysis for Stgr for Millstone Nuclear Power Station Unit 3 Four-Loop Operation
ML20058F8961990-08-31031 August 1990
Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for Millstone 3 Nuclear Power Station
ML20058F1081990-04-30030 April 1990
RHR Autoclosure Interlock Removal at Millstone Unit 3
ML20195E4851988-10-25025 October 1988
Milllstone Unit 2 Plant Transient Analysis Rept Analysis of Chapter 15 Events
ML20154N5621988-09-30030 September 1988
Plant Transient Analysis Rept,Analysis of Chapter 15 Events
ML20155D4281988-09-30030 September 1988
Safety Evaluation Supporting More Negative End-of-Life Moderator Temp Coefficient Tech Spec for Millstone Unit 3
ML20034B4941988-02-29029 February 1988
Rev 0 to Final Rept Criticality Safety Analysis Millstone-2 New Fuel Storage Vault & Transfer Carriage W/5 % Enriched 14x14 Fuel Assemblies
ML20149G5621988-01-31031 January 1988
Nonproprietary Evaluation of Margin to Steam Generator Overfill for Millstone Unit 3
ML20236Q4031987-10-30030 October 1987
Addendum 2 to Physics Methodology for PWR Reload Design
ML20238F0331987-06-30030 June 1987
Nonproprietary Resistance Temp Detector Bypass Elimination Licensing Rept for Millstone Unit 3
ML20196J4341986-11-30030 November 1986
Boric Acid Concentration Reduction Effort,Technical Bases & Operational Analysis
ML20210A6051986-09-0505 September 1986
Addendum a to Vol II of Nusco 140-2, Nusco Thermal Hydraulic Model Qualification
ML20235J4861986-07-31031 July 1986
Summary Rept,Fire Protection Qualification Testing of Silicon Dioxide Mineral Insulated Cable
ML20137S5931985-11-30030 November 1985
Westinghouse Setpoint Methodology for Protection Sys, Millstone Nuclear Power Station Unit 3. W/Six Oversize Tables
ML20205N4491985-11-30030 November 1985
Nonproprietary Westinghouse Setpoint Methodology for Protection Sys,Millstone Nuclear Power Station Unit 3. W/ Revised Cover Page.Two Oversize Figures Encl
ML20133B2721985-10-0101 October 1985
ASEA-Atom BWR Control Blades for Us Bwrs
ML20099L0361984-09-30030 September 1984
Evaluation of Acceptability of Reactor Vessel Head Lift Rig,Reactor Vessel Internals Lift Rig,Load Cell & Load Cell Linkage to Requirements of NUREG-0612
ML20098B0251984-06-30030 June 1984
Nonproprietary Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Millstone Unit 3
ML20077N9741983-07-31031 July 1983
Steam Generator Sleeving Rept
ML20074A1061983-03-31031 March 1983
Shape Annealing Factor Component of Axial Shape Index Uncertainty
ML20079G5361982-04-30030 April 1982
Post-Irradiation Evaluation of Reactor Vessel Surveillance Capsule W-97
ML20052E2311982-01-28028 January 1982
Point 1 Isolation Condenser & Shutdown Cooling Sys Piping Cracks
ML20039F8631981-12-31031 December 1981
Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCA W/Loss of Feedwater for Millstone 2 Reactor Vessel
ML20037D4741981-06-29029 June 1981
Mark I Plant Containment Mod Status Summary
B12413, Point Nuclear Power Station,Unit 1 Single-Loop Operation1980-12-31031 December 1980
Point Nuclear Power Station,Unit 1 Single-Loop Operation
ML19337A8221980-07-31031 July 1980
LOCA Analysis Rept for Millstone Unit 1 Nuclear Power Station
ML19320A7551980-06-30030 June 1980
RCS Asymmetric Loads Evaluation Program, Final Rept, Vol 2
ML19320A7621980-06-30030 June 1980
RCS Asymmetric Loads Evaluation Program, Final Rept,Vol 3
ML19320A7721980-06-30030 June 1980
RCS Asymmetric Loads Evaluation Program, App E,Eccs Analysis Approach W/Reduced Area Coolant Channels in Peripheral Assemblies.Final Rept
ML19320A7671980-06-30030 June 1980
RCS Asymmetric Loads Evaluation Program, Final Rept,App a, Numerical Results, Evaluation of C-E Fuel.Nonproprietary Version.App B,Palisades Fuel Analysis,Encl
ML19249B9741979-08-29029 August 1979
Response Time Qualification of Resistance Thermometers in Nuclear Power Plant Safety Sys.
ML20002A1081979-05-0202 May 1979
Sleeved CEA Guide Tube Eddy Current Test Results.
ML20037A2291979-05-0202 May 1979
Response to NRC Question 2.2 on Cycle 3 Safety Analysis, Nonproprietary Version
ML19291A3021979-03-0909 March 1979
QA Program Rept,Revision 3A
ML20062G3871978-12-14014 December 1978
Sleeved Guide Tube Inspec Prog, CEN-104(N)-NP.Describes Inspec Prog to Show Performance Re Wear.Edited to Delete Info W/Held from Pub Disclosure IAW 10CFR2.790
1998-12-08
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999
Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program
05000336/LER-1999-012, :on 990917,unrecoverable CEA Misalignment Entry Into TS 3.0.3 Was Noted.Caused by Grounded Coil Wire for Lower Gripper Assembly.Leads Leading to Lower Gripper Coil Were Insulated1999-10-15015 October 1999
- on 990917,unrecoverable CEA Misalignment Entry Into TS 3.0.3 Was Noted.Caused by Grounded Coil Wire for Lower Gripper Assembly.Leads Leading to Lower Gripper Coil Were Insulated
ML20217C8721999-10-0606 October 1999
Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only
B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With
B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With
B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With
ML20216J4341999-09-24024 September 1999
Mnps Unit 3 ISI Summary Rept,Cycle 6
05000336/LER-1999-011, :on 990823,thermal Reactor Power Limit Was Exceeded.Caused by Lack of Conservatism in Procedures & Alarm Setpoints Used to Limit Reactor Power.Revised Operating Procedures1999-09-20020 September 1999
- on 990823,thermal Reactor Power Limit Was Exceeded.Caused by Lack of Conservatism in Procedures & Alarm Setpoints Used to Limit Reactor Power.Revised Operating Procedures
ML20212A7381999-09-10010 September 1999
Safety Evaluation Supporting Amend 174 to License NPF-49
05000245/LER-1999-001-02, :on 990810,discovered That Stack Flow Monitor Four H LCO Action Statement Had Not Been Met.Caused by Personnel Error.Frequency of LCO Action Was Increased & Personnel Involved Received Coaching.With1999-09-0808 September 1999
- on 990810,discovered That Stack Flow Monitor Four H LCO Action Statement Had Not Been Met.Caused by Personnel Error.Frequency of LCO Action Was Increased & Personnel Involved Received Coaching.With
05000336/LER-1999-010, :on 990804,noted Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve.Caused by Inadequate man-machine Interface. Planning Personnel Will Be Briefed on QC Program Indicators1999-09-0202 September 1999
- on 990804,noted Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve.Caused by Inadequate man-machine Interface. Planning Personnel Will Be Briefed on QC Program Indicators
ML20211N8401999-09-0202 September 1999
Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10
B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With
B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With
B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With
ML20216F5141999-08-31031 August 1999
Rept on Status of Public Petitions Under 10CFR2.206
ML20211G9631999-08-30030 August 1999
SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves
ML20210U0881999-08-13013 August 1999
Safety Evaluation Supporting Amends 239 & 173 to Licenses DPR-65 & NPF-49,respectively
ML20210Q1401999-08-12012 August 1999
Safety Evaluation Supporting Amend 238 to License DPR-65
B17858, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With1999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With
ML20211A6561999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2
B17856, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With1999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With
ML20210J0311999-07-21021 July 1999
Rev 20,Change 10 to QAP 1.0, Organization
ML20210E5931999-07-19019 July 1999
Revised Page 16 of 21,to App F of Northeast Util QA Program Plan
ML20210A0411999-07-15015 July 1999
Rev 20,change 10 to Northeast Util QA Program Tr
ML20210C5911999-07-15015 July 1999
Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes
ML20209G3061999-07-13013 July 1999
Safety Evaluation Supporting Amend 237 to License DPR-65
B17814, Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start1999-07-12012 July 1999
Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start
ML20209D6581999-07-0202 July 1999
Safety Evaluation Supporting Amend 172 to License NPF-49
ML20209D1881999-07-0101 July 1999
Rev 20,change 9 to Northeast Util QA Program Tr
B17830, Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With1999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With
ML20196J1821999-06-30030 June 1999
Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr
ML20209J0541999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Millstone Unit 2
B17833, Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With1999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With
ML20196A8451999-06-30030 June 1999
Post Shutdown Decommissioning Activities Rept
ML20196K1791999-06-30030 June 1999
Addendum 6 to Millstone Unit 2 Annual Rept,
ML20211A6751999-06-30030 June 1999
Revised Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level & Operating Data Rept
ML20196J2191999-06-30030 June 1999
SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46
ML20196H1621999-06-29029 June 1999
Safety Evaluation Supporting Amend 236 to License DPR-65
05000423/LER-1999-007-01, :on 990518,discharge Filter Associated with Crss Cubicle Sump Pump 3DAS-8A,was Determined to Be Contaminated.Caused by Back Leakage from Contaminated Drains Feeding Into ECCS Pump.Lines Modified.With1999-06-17017 June 1999
- on 990518,discharge Filter Associated with Crss Cubicle Sump Pump 3DAS-8A,was Determined to Be Contaminated.Caused by Back Leakage from Contaminated Drains Feeding Into ECCS Pump.Lines Modified.With
05000423/LER-1999-006-01, :on 990516,both Reactor Plant Aerated Drains SR Air Driven Sump Pumps Failed During TRM Surveillance.Caused by Inadequate Preventive Maint Program Design.Surveillance Procedure Sp 3635B.2 Will Be Conducted Monthly1999-06-15015 June 1999
- on 990516,both Reactor Plant Aerated Drains SR Air Driven Sump Pumps Failed During TRM Surveillance.Caused by Inadequate Preventive Maint Program Design.Surveillance Procedure Sp 3635B.2 Will Be Conducted Monthly
05000423/LER-1999-004-01, :on 990516,ESFA of Numerous Plant Components on Restoration of a Train Sequencer Occurred.Caused by Inadequate Procedure Direction.Issued Brief to Operations Describing Inadvertent Sequencer LOP Event.With1999-06-14014 June 1999
- on 990516,ESFA of Numerous Plant Components on Restoration of a Train Sequencer Occurred.Caused by Inadequate Procedure Direction.Issued Brief to Operations Describing Inadvertent Sequencer LOP Event.With
ML20195H1011999-06-11011 June 1999
Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR
05000423/LER-1999-005-01, :on 990510,failure to Perform Surveillance on RCS Pressurizer Heater Penetration Breakers Was Noted.Caused by Lack of Mgt Support.Required Surveillance of Identified Ten Breakers Was Completed1999-06-0808 June 1999
- on 990510,failure to Perform Surveillance on RCS Pressurizer Heater Penetration Breakers Was Noted.Caused by Lack of Mgt Support.Required Surveillance of Identified Ten Breakers Was Completed
05000423/LER-1999-003-01, :on 990505,identified That 18 Month EDG Surveillance Test for LOP with ESF Start Did Not Initiate Test.Caused by Inadequate Understanding of Regulatory Guidance. a & B EDG Returned to Status.With1999-06-0404 June 1999
- on 990505,identified That 18 Month EDG Surveillance Test for LOP with ESF Start Did Not Initiate Test.Caused by Inadequate Understanding of Regulatory Guidance. a & B EDG Returned to Status.With
ML20207G6411999-06-0303 June 1999
Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively
ML20209J0661999-05-31031 May 1999
Revised Monthly Operating Rept for May 1999 for Millstone Unit 2
ML20211B7351999-05-31031 May 1999
Cycle 7 Colr
B17808, Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With1999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With
B17804, Monthly Operating Rept for May 1999 for Mnps,Unit 2.With1999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Mnps,Unit 2.With
1999-09-08
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