ML20154F702
ML20154F702 | |
Person / Time | |
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Site: | Millstone |
Issue date: | 02/03/1986 |
From: | Romberg W NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
References | |
MP-8685, NUDOCS 8603070509 | |
Download: ML20154F702 (2) | |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARB17814, 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
[Table view]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 B17603, Special Rept:On 981212, Start of B-EDG Was Attempted from CR Following Completion of Heat Exchanger Insps.Caused by Trapped Air Pocket within Cw Loop.Performed OPs as Required in Order to re-vent Sys1998-12-29029 December 1998 Special Rept:On 981212, Start of B-EDG Was Attempted from CR Following Completion of Heat Exchanger Insps.Caused by Trapped Air Pocket within Cw Loop.Performed OPs as Required in Order to re-vent Sys B17436, Special Rept:On 980809,at 1427 H with Plant in Mode 1,loose Parts Dectection Sys (Lpm) Was Declared Inoperable.Caused by Power Supply Unit to Signal Conditioning Unit for Lpm. Replaced Power Supply Units1998-09-0909 September 1998 Special Rept:On 980809,at 1427 H with Plant in Mode 1,loose Parts Dectection Sys (Lpm) Was Declared Inoperable.Caused by Power Supply Unit to Signal Conditioning Unit for Lpm. Replaced Power Supply Units B17017, Special Rept:On 980130,declared Meteorological Tower (Met) Delta - T Instrumentation Due to Discovery of Met Instrument Uncertainty Values Found Out of Compliance.Will Modify Meteorological Instrumentation Installed at Plant1998-02-13013 February 1998 Special Rept:On 980130,declared Meteorological Tower (Met) Delta - T Instrumentation Due to Discovery of Met Instrument Uncertainty Values Found Out of Compliance.Will Modify Meteorological Instrumentation Installed at Plant B16546, Special Rept:On 970615,Train B EDG Failed.Event Review Team Was Formed to Investigate & Evaluate Potential Cause of Oscillations1997-07-14014 July 1997 Special Rept:On 970615,Train B EDG Failed.Event Review Team Was Formed to Investigate & Evaluate Potential Cause of Oscillations B16141, Special Rept:On 961224,delayed Submittal of License Amend Request for Section 6.0, Administrative Controls, Occurred.Caused by Inadequate Communication.On 970122 Issued Expectations for Implementing Future Organizational Changes1997-01-22022 January 1997 Special Rept:On 961224,delayed Submittal of License Amend Request for Section 6.0, Administrative Controls, Occurred.Caused by Inadequate Communication.On 970122 Issued Expectations for Implementing Future Organizational Changes B15777, Special Rept:On 960528,Train B Emergency Diesel Generator Failed.Caused by Low Lube Oil Pressure.Instituted Procedural Changes Re Low Lube Oil Pressure During Strainer Swaps1996-06-27027 June 1996 Special Rept:On 960528,Train B Emergency Diesel Generator Failed.Caused by Low Lube Oil Pressure.Instituted Procedural Changes Re Low Lube Oil Pressure During Strainer Swaps ML20094M5581995-11-20020 November 1995 Special Rept:On 950825,valves in Rc Module of PASS Sys Did Not Cycle & Sys Flow Was Obtained.Caused by Particulates Inherent to Effluent Stream Adhering to Vertical Sides of Valve Body.Investigated Residual Problems ML20094K7461995-11-0909 November 1995 Special Rept Identifying That Fire Alarm Sys for Intake Structure Out of Svc for Greater than 14 Days Due to Troubleshooting Maint Required to Locate & Repair Intermittent Alarms.Sys Returned to Svc on 951013 ML20086M6621995-07-19019 July 1995 Special Rept Re Fire Alarm Panel C26E Being Out of Svc for Greater than 14 Days Due to Shooting Maint Required to Locate & Repair Intermittent Electrical Ground.Electrical Ground Cleared & Associated Work Completed ML20086C1461995-06-30030 June 1995 Special Rept Re Fire Suppression Sys for Auxiliary Bldg General Area at Elevation 14'6 Inoperable for Greater than 14 Days Due to Plant Mod Not Administratively Complete.Fire Watch Established ML20084D9721995-05-26026 May 1995 Special Rept:On 950414,plant Shutdown for Refueling Outage & on 950416 Seismic Monitoring Sys Was Declared Inoperable for Automated Work Order Action ML20082K5281995-04-11011 April 1995 Special Rept:On 950316,loose Part Monitoring Sys (Lpm) Channel 5,SG a Lower Failed.Cause of Lpm Channel 5 Failure Isolated to in-containment Cabling/Accelerometer.Cable & Accelerometer Replacement Planned for Next Refueling Outage ML20080B7811994-12-0101 December 1994 Special Rept Re Halon Fire Suppression Sys for Both DC Switchgear Rooms Out of Svc for Greater than 14 Days.Caused by Temporary Ventilation Configuration Requiring Area Doors to Remain Open.Normal Ventilation Methods Reestablished ML20077A4251994-11-15015 November 1994 Special Rept:On 941024,LPMS Declared Inoperable Due to Failure of Lpms Channel 8.Cause of Lpms Channel 8 Failure Isolated to in-containment Cabling/Accelerometer.Cable & Accelerometer Replacement Planned for Next Refueling Outage ML20070M3491994-04-14014 April 1994 Special Rept:On 940318,train B EDG Failed to Start.Caused by Blown Fuse.Replacement Fuse Installed & EDG Surveillance Test Successfully Completed ML20057E8641993-09-0404 September 1993 Special Rept:On 930821,identified Flaws Greater than or Equal to Plugging Limit in 7 Tubes During EC Testing Due to Degradation.Removed Tubes from Svc ML20128E8061992-12-0101 December 1992 Updated Special Rept:On 920204,loose Parts Monitoring Sys Declared Inoperable Due to Receipt of Low Level Alarms on All Channels.On 920902,Channel 12 Went Into Alarm Due to Spurious Low Level Vibration Alarms.Channel to Be Restored ML20113J1151992-07-31031 July 1992 Updated Special Rept MP-91-1080:on 910816,passive Triaxial (Recording) Peak Accelerograph Removed from Svc Due to Inconsistency of Magnetic Trace Data.Amended Surveillance Program Assures Exisitng Accelerographs Meet Design Intent B14192, Special Rept:On 920601,Millstone Unit 2 Entered TS 3.3.3.3 When Seismic Monitoring Sys Removed from Service to Support SG Replacement Outage.Operations Personnel Instructed on Appropriate Actions Re Response to Monitor Alarm1992-07-0909 July 1992 Special Rept:On 920601,Millstone Unit 2 Entered TS 3.3.3.3 When Seismic Monitoring Sys Removed from Service to Support SG Replacement Outage.Operations Personnel Instructed on Appropriate Actions Re Response to Monitor Alarm ML20097G0681992-06-10010 June 1992 Special Rept:On 920204,LPM Was Declared Inoperable Per Plant TS Based on Low Level Alarms on All Channels.Disks Will Be Analyzed for Degradation or Failure on Monthly Frequency HL-2155, Special Rept 2-92-001:on 920311,discovered That Required Surveillance on Water Curtain Isolation Valve Missed Due to Less than Adequate Procedure & Personnel Error.Procedure 42SV-FPX-035-1S Revised & Surveillance Performed on 9203111992-04-0606 April 1992 Special Rept 2-92-001:on 920311,discovered That Required Surveillance on Water Curtain Isolation Valve Missed Due to Less than Adequate Procedure & Personnel Error.Procedure 42SV-FPX-035-1S Revised & Surveillance Performed on 920311 ML20091B9701992-03-27027 March 1992 Special Rept:On 920301,atmospheric Pressure & 88 Degree F RWST Level Switch Failed in lo-lo Level Condition.Caused by microbiological-induced Corrosion of Viton Diaphragm.Switch Replaced & Sensing Lines Chemically Sampled ML20090L2821992-03-13013 March 1992 Special Rept:On 920204,loose Parts Monitoring Sys Was Declared Inoperable.Cause Is Unknown.Sys Vendor Has Been Contacted for Assistance in Resolving These Issues ML20087A3761991-12-31031 December 1991 Updated Special Rept:On 910816,triaxial Peak Accelerograph Inoperable for More than 30 Days & Vendor Stated Tolerance Could Not Be Verified.Accelerograph Will Be Replaced W/Model Which Complies W/Reg Guide 1.12 ML20086D0491991-11-18018 November 1991 Special Rept:On 911011,discovered That Surveillance Procedure for Four Element Seismic Monitoring Sys Performed Incorrectly & Instrumentation Declared Inoperable.Recalibr of Instruments Planned During Present Reactor Shutdown ML20079D9681991-09-25025 September 1991 Special Rept:On 910816,discovered That Surveillance Acceptance Criteria Tolerance Not Repeatable on Passive Triaxial Peak Accelerograph.Caused by Faulty Vendor Stated Tolerances.Replacement of Accelerographs Under Review ML20082P5901991-09-0303 September 1991 Informational Rept:On 910726,discovered That Main Control Board Annunicator Sys Inoperable.Caused by Failure of -12 volt-dc Modules in Annunicator Power Supply Assemblies PS1A & PS1B.Power Supply Replaced & Spare Unit Installed ML20077N4821991-08-0505 August 1991 Special Rept:On 910626,loose Parts Monitor Channel Malfunctioned & Declared Inoperable for More than 30 Days. Caused by Degradation of Channel Monitoring Signal.Channel Repaired & micro-dot Cable Connector Replaced ML20091C3411991-07-29029 July 1991 Special Rept:On 910714,stack high-range Radiation Monitor Declared Inoperable Due to Intermitten Failures Caused by Fluctuations in Output of Power Supply.Guidance Provided Re Resetting Monitor to Operating Status B13840, RO Re Potential Failure of LPSI Sys Piping.Evaluation Involving Estimate of LPSI Piping Stress Upstream of LPSI Injection MOVs Performed.Reverse Flow Testing of LPSI Injection Check Valves Will Be Conducted by 1992 Outage1991-07-18018 July 1991 RO Re Potential Failure of LPSI Sys Piping.Evaluation Involving Estimate of LPSI Piping Stress Upstream of LPSI Injection MOVs Performed.Reverse Flow Testing of LPSI Injection Check Valves Will Be Conducted by 1992 Outage ML20059C0421990-08-23023 August 1990 Special Rept:On 900519,loose Parts Monitor Channel 1 Malfunctioned.On 900606,reactor Trip Occurred Due to Bad Cable.On 900722,loose Parts Monitor Channel 3 Declared Inoperable.Channels 1 & 3 Will Be Repaired Next Outage ML20055D0241990-06-22022 June 1990 Special Rept:On 890716,2 of 12 Loose Parts Monitor Channels Declared Inoperable When Alarms Received Due to Malfunction of Equipment in Containment Bldg.On 900519,loose Parts Channel Alarmed Continuously.Channels Turned Off ML20248H2811989-10-0202 October 1989 Special Rept:On 890902,area Temp Found Greater than 120 F for Duration Greater than 8 H.Caused by Personnel Error Due to Shift Personnel Failure to Adequately Track Temp Excursion.Revised Thermal Life Calculations Performed ML20246H5381989-08-25025 August 1989 Special Rept:On 890716,2 of 12 Loose Parts Monitor Channels Declared Inoperable Due to Continuous Alarming.Caused by Malfunctions in Loose Parts Monitoring Equipment Located Inside Containment Bldg.Channels Turned Off ML20247H4471989-07-21021 July 1989 Special Rept:On 890621,fire Occurred in Containment at Polar Crane Auxiliary Hoist Speed Control Resistor Bank Cabinet Located in Cat Walk.Caused by Melting of Plastic Parts of Temporary Area Fan.Fire Brigade Activated ML20244E5151989-06-13013 June 1989 Special Rept:On 890529,end-of-Cycle 2 ECT Insp of Steam Generator Tubes & Number of Tubes Plugged in Each Steam Generator Completed.Encl Table 1 Summarizes Results.Complete Results Will Be Submitted within 1 Yr ML20246N2171989-05-11011 May 1989 Special Rept:On 890411,unknown RCS Leakrate of Greater than 1 Gpm Discovered.Caused by Sudden Increase in Letdown Piping Pressure & Temp Due to Water Flashing to Steam.Vent Pipe Cut Below Cracked Connection & New Vent Valve Installed ML20246G3931989-05-0303 May 1989 Special Rept:On 890425,analysis of Gas Sample Drawn from post-accident Sampling Sys Indicated Reactor Coolant Gases Not Being Removed from Liquid Sample of Rcs.Liquid Loop to Gas Loop Reinspected & Surveillance Frequency Increased ML20206C0931988-11-0909 November 1988 Special Rept:On 880712,14,18,0827 & 1010,temp Inside Pressurizer Cubicle Exceeded Tech Spec Limit of 120 Degrees. No Temp Excursions Inside Pressurizer Cubicle in Excess of New Tech Spec Temp Limit of 130 F Between 880719 & 1003 ML20155G3101988-10-0606 October 1988 Special Rept:On 880906,Train a Emergency Diesel Generator Output Breaker Tripped During Attempt to Place Load on Engine.Caused by Unit Relay de-energizing While Generator Operated Parallel W/Site Power.Investigation Continuing ML20154D5851988-09-0606 September 1988 Special Rept:On 880804,noted Insufficient Documentation to Substantiate Compliance W/Reg Guide 1.106.Caused by Personnel Error.Engineering Calculation Performed to Verify Trip Setpoint of Thermal Overload Protection Devices ML20207B4491988-07-19019 July 1988 Special Rept:On 880620,area Temp Inside RCS Pressurizer Cubicle Greater than 120 F.No Abnormal Trends Which Would Associate Cause of Temp Excursion to Leakage in Area.Revised Thermal Life Calculations Performed on Environ Equipment ML20154J4191988-05-13013 May 1988 Special Rept:On 880413,containment Area Indicated Area Temp Inside RCS Pressurizer Cubicle Greater than 120 F.Caused by Packing Leak from Isolation Valve & Slight Leakage Past Safety Valve.Maint Performed on Valves ML20151A6121988-04-0404 April 1988 Special Rept:On 880304,valve Found Improperly Locked During NRC Insp Tour.Caused by Personnel Error.Valve Lineup Performed & Required to Be Locked,Checked & Confirmed to Be Locked ML20237F9041987-08-27027 August 1987 Ro:On 870814,oil Spill Occurred at Plant.Caused by Hydrogen Seal Oil Vacuum Tank Malfunction.Boom Installed to Prevent Oil Film from Spreading ML20237K4271987-08-14014 August 1987 Special Rept:Five Channels of Fire Detection Instruments for Reactor Coolant Pump B Area Listed in Tech Spec Table 3.3-10 Out of Svc.Caused by Heat Detector Failure.Heat Detector Will Be Replaced at Next Available Shutdown B12593, Special Rept:On 870612,during Installation of 10CFR50,App R Automatic Halon Fire Suppression Sys in Control Room,Control Room Smoke Detectors Rendered Inoperable.Caused by Removal of Ceiling to Facilitate Installation1987-07-10010 July 1987 Special Rept:On 870612,during Installation of 10CFR50,App R Automatic Halon Fire Suppression Sys in Control Room,Control Room Smoke Detectors Rendered Inoperable.Caused by Removal of Ceiling to Facilitate Installation ML20154F7021986-02-0303 February 1986 Special Rept:Positive Moderator Temp Coefficient Measured Above Tech Spec Limits.Rod Withdrawal & Boron Concentration Limits Established to Prevent Moderator Temp Coefficient from Becoming Positive ML20137P6201986-01-24024 January 1986 Special Rept:On 860115,only One Containment Area high-range Radiation Monitoring Channel Operable in Mode 3.Caused by Voltage Test Failure of Mineral Insulated Cable.Cables Removed & Reworked & Alternate Procedures Devised 1999-07-12 Category:TEXT-SAFETY REPORT MONTHYEARML20217P5391999-10-25025 October 1999
[Table view]Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only 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 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 ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 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 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 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 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 ML20211A6561999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2 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 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 ML20210C5911999-07-15015 July 1999 Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes ML20210A0411999-07-15015 July 1999 Rev 20,change 10 to Northeast Util QA Program Tr 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 ML20209D1881999-07-0101 July 1999 Rev 20,change 9 to Northeast Util QA Program Tr 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 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 ML20196A8451999-06-30030 June 1999 Post Shutdown Decommissioning Activities Rept ML20209J0541999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Unit 2 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 ML20196K1791999-06-30030 June 1999 Addendum 6 to Millstone Unit 2 Annual Rept, ML20196J1821999-06-30030 June 1999 Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr 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 ML20195H1011999-06-11011 June 1999 Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20211A6631999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level,Operating Data Rept & Unit Shutdowns & Power Reductions 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 ML20211B7351999-05-31031 May 1999 Cycle 7 Colr 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 B17807, Monthly Operating Rept for May 1999 for Mnps,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 1.With ML20209J0661999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206J8351999-05-0707 May 1999 Rev 20,Change 7 to QAP-1.0, Northeast Utls QA Program (Nuqap) Tr ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 B17782, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With ML20205R3531999-04-30030 April 1999 Addendum 4 to Annual Rept, B17775, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With ML20205K6141999-04-30030 April 1999 Non-proprietary Version of Rev 2 to Holtec Rept HI-971843, Licensing Rept for Reclassification of Discharge in Millstone Unit 3 Spent Fuel Pool ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 B17777, Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with ML20205Q5891999-04-0909 April 1999 Rev 20,change 6 to QAP-1.0,Northeast Utils QA Program TR ML20205R8751999-04-0909 April 1999 Provides Commission with Staff Assessment of Issues Related to Restart of Millstone Unit 2 & Staff Recommendations Re Restart Authorization for Millstone Unit 2 ML20206T3991999-03-31031 March 1999 First Quarter 1999 Performance Rept, Dtd May 1999 B17747, Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With 1999-09-30 |
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d February 3, 1986 MP-8685 Dr. Thomas Murley U. S. Nuclear Regulatory Commission Regional Administrator Region 1 631 Park Avenue King of Prussia, PA 19406
Reference:
Facility Operating License No. NPF 49, Docket No. 50-423
Dear Dr. Murley:
Positive Moderator Temperature Coef ficient This Special Report is being submitted within ten days pursuant to plant Technical Specification 3.1.1.3, Action a.3 and 6.9.2. Plant Technical Specification 3.1.1.3 required a Moderator Temperature Coefficient less positive than 0 Ok/k/0F for the All rods withdrawn beginning of cycle life (BOL), hot zero THERMAL POWER condition.
During the performance of startup physics testing a Positive Tempera ture Coefficient was measured for the Millstone Unit 3 Nuclear Power Plant. Measured values are as follows:
RCS ITC MTC Control Rod Position Boron Concentration
-1.03 + 0.92 All SHUTDOWN Banks Out 1570 All Control Banks Out
-2.5 .55 Control Bank D Fully Inserted 1502 ppm All other Control and Shutdown Banks Fully Withdrawn
-6.07 -4.12 Control Banks C and D Fully inserted 1383 ppm A!! other Control and Shutdown Banks Fully Withdrawn To prevent the Moderator Temperature Coefficient from becoming positive, Rod Withdrawal Limits and Boron Concentration Limits have been established.
These limits were established in accordance with the fuel vendors recommendations and include a 1 pcm/0F conservatism. It is estimated that the average core burnup at which time the Moderator Temperature Coefficient will be negative for the All rods out Xenon free condition is $570 MWD /MTU.
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r The licensee contact for this Special Report is David McDaniel and may be reached at (203) 444-4339.
Yours truly, NORTHEAST NUCLEAR ENERGY COMPANY
/ u (Jfy "n Wayne D. Rombe
- Station Superintendent Millstone Nuclear Power Station WDR/DM:sc I
,