ML20235P313
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| ML20235P313 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/09/1987 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 87-370, NUDOCS 8707200441 | |
| Download: ML20235P313 (1) | |
Similar Documents at North Anna | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20217N9281999-10-20020 October 1999
[Table view]Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20151X8011998-09-10010 September 1998 Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section ML20247K9281998-05-15015 May 1998 Special Rept:On 980428,letdown PCV Exhibited Slow Response When C RCP Was Started.Cause to Be Determined.Review of Operating Procedure Will Be Performed to Determine If Enhancements Are Necessary ML20217H9611998-04-0707 April 1998 Special Rept:On 980216,groundwater Level at Piezometer P-22, Again Noted to Be Above Max Water Level by 0.41 Feet.Design Package for Installation of Addl Standpipe Piezometers at Toe of Slope Southeast Section,Developed ML20210U8541997-09-16016 September 1997 Special Rept:On 970623,groundwater Level at Piezometer P-22 Was Noted to Be Above Maximum Water Level by 0.31 Feet. Addl Standpipe Piezometers Will Be Installed at Toe of Slope of Dike Along Southeast Section to Provide Further Info ML20141E7651997-05-13013 May 1997 Special Rept:On 970430,groundwater Level at Piezometer P-22 Again Noted to Be Above Max Water Level by 0.86 Feet. Piezometers Along Southeast Portion of Dike Being Monitored on Increased Frequency for Yr to Determine Water Levels ML20134H6581997-02-0404 February 1997 Special Rept:On 970115,groundwater Level at Piezometer P-22 Noted Above Maximum Water Level by 0.51 Feet.Cause Indeterminate.Will Continue to Monitor Piezometers on Quarterly Basis & Will Install Addl Piezometers ML20133B5711996-12-0303 December 1996 Special Rept:On 960709,filter Shipment Exceeded Specific Activity Criteria for LSA Packages Defined in Revised Coc. Caused by Personnel Error.Revised Procedures to Minimize Referencing out-of-date Cocs ML20116N3191996-08-16016 August 1996 Special Rept:On 960714,hourly Fire Watch Established & Fire Barrier Blocks Removed in Preparation of Planned Charging Pump Mods.Blocks re-installed Following Completion of Mod on 960724 ML20095C6991995-12-0707 December 1995 Special Rept:On 951107,spillway EDG Failed to Start During Performance of Monthly Periodic Test.Corrective Maint Work Order Immediately Initiated to trouble-shoot & Repair Spillway EDG ML20085M3851995-06-22022 June 1995 Special Rept:On 950528,RCS Was Filled to Solid Water Conditions During start-up Activities Following Recent Refueling Outage ML20083M5541995-05-0909 May 1995 Special Rept:On 950329,gap Seals Between Top of 12 Inch Concrete Block Wall & Assoc Steel I Beams Above Block Wall Were Discovered Filled W/Everlastic Column Boxboard Engineering Review Intiated ML20077S3991995-01-17017 January 1995 Special Rept:On 940901,determined That Fire Damper Visual Insps Not Performed as Required Due to Fire Protection SRs Being Originally Misinterpreted.Requirements for Visual Insps Incorporated Into Periodic Test Procedures ML20069K8831994-05-24024 May 1994 Special Rept:On 940427,motor Driven Fire Pump Out of Svc for More than Seven Days.Fire Pump 1-FP-P11 Was Returned to Svc on 940510 ML20065E7011994-04-0606 April 1994 Special Rept:On 940307,fuel Oil Pump House High Pressure Carbon Dioxide Sys & Control Room Halon Sys Did Not Perform as Required.Control Room Halon Sys Tested Satisfactorily & Declared Operable ML20058K4941993-12-0303 December 1993 Special Rept:On 931109,EDG Failed to Auto Start During Performance of Main Dam Auxiliary Power Diesel Periodic Test 1-PT-1 Due to Low Out of Spec Readings on Four 6 Volt Batteries.Batteries Replaced & Subj Test Completed ML20126D2961992-12-22022 December 1992 Special Rept:On 921124,7-day SR of Updated FSAR Exceeded to Implement Work Activities on Quench Spray Pump House.On 921203,gaps Discovered in Fire Barrier Foam Matl Around Pipes.Fire Watch Established Until Mods Completed on 921214 ML20126A1031992-12-14014 December 1992 Special Rept:On 921130,motor-driven Fire Pump Removed from Svc to Facilitate Maint Activities on Circulating Water Pump A.On 921202,diesel-driven Fire Pump 1-FP-P-2 Declared Inoperable.Caused by Failure of Control Circuit Relay ML20128A1531992-11-25025 November 1992 Update to 921112 RO Re Improperly Set EDG 2H & 2J.EDGs Reset to Max Position within 18 Minutes.Testing Verified That Max Fuel Available within Load Limiters.Item Not Reportable & 4 H Rept Made to NRC on 921112 Retracked ML20127K8231992-11-18018 November 1992 Special Rept:On 921015,motor-driven Fire Pump 1FP-P-1 Tagged Out & Removed from Svc for More than 7 Days to Permit Maint Activities.Fire Pump Returned to Svc on 921031 & Cross Tie to Fire Loop Will Be Opened When Fire Pump Out of Svc ML20116D1091992-11-0202 November 1992 Special Rept 92-702:on 921005,determined That Fire Damper 2-FP-FDMP-1011 Had Only Partially Closed During Performance of Halon Sys Pressure Switch Testing.Caused by Carpeting Obstructing Cable Link.Carpeting Removed ML20118C0141992-10-0202 October 1992 Special Rept:On 920902,fire Barrier Silicone Foam Found to Be in Nonfunctional Condition on SW Lines.Caused by Voids in Silicone Foam Between All Four SW Pipes.Fire Watch Assigned, Per Administrative Requirements ML20114D8581992-09-0202 September 1992 Special Rept:On 920721,discovered That Fire Damper Not Installed as Specified in Station Drawing.Deviation Rept 92-1579 Submitted Upon Discovery & Hourly Fire Watch Implemented ML20096E0371992-05-14014 May 1992 Special Rept:On 920414,overpressure Protection Sys Actuated When Pressurizer PORV Opened.Caused by Unplanned Increase in RCS Pressure.Operations Personnel Coached on Importance of Properly Controlling Plant Parameters ML20095B2501992-04-14014 April 1992 Special Rept:On 920319,total Settlement of Corner of Fuel Oil Pumphouse (Survey Point 246),as Defined by Survey, Exceeded 75% Allowable Value of .030 Feet.Per Technical Rept CE-0019,structural Integrity Has Not Been Compromised ML20091A9361992-03-24024 March 1992 Special Rept:On 920310,failure of Underground Fire Protection Header Piping Experienced,Rendering Fire Suppession Sys Water Sys Inoperable.Leak Isolated & Motor Driven Fire Protection Pump Returned to Svc on 920317 ML20086A0481991-11-12012 November 1991 Special Rept:On 911029,differential Settlement Between Containment & Main Steam Valve House Exceeded 75% of Allowable Value of 0.030 Ft.Ts Change Request Submitted on 911002 to Delete Monitoring Survey Points 131 & 124 ML20084U8411991-04-18018 April 1991 Special Rept:On 910318,determined That Triaxial Response Spectrum Recorders of Seismic Monitoring Sys Did Not Meet TS 3.3.3.3 Required Measurement Range of 1-20 Hz.License Amend Will Be Submitted to Reflect Correct Ranges ML20084U6871991-04-16016 April 1991 Special Rept:On 901031,discovered Failure of Inst for Resource Mgt,Inc Security Screening Program.No Apparent Significant Degradation of Security Program Exists ML20065M8561990-12-0606 December 1990 Special Rept:On 901102,differential Settlement Between Unit Containment & Main Steam Valve House Exceeded TS Value. Caused by Stresses Placed on Piping.Tech Spec Change Request Submitted to Delete Monitoring Requirement ML20055D3061990-06-29029 June 1990 Ro:On 900530,differential Settlement Between Containment & Main Steam Valve House Exceeded 75% of Allowable Value of 0.030 Ft.Caused by Stresses Placed on Main Steam,Feedwater, Svc Water & Condenser Air Ejector Piping.Rept Reviewed ML20248C5321989-07-28028 July 1989 Special Rept:On 890601,discovered Differential Settlement Between Unit 2 Containment & Main Steam Valve House Exceeding Limit.Caused by Apparent Upward Movement of Point 131 on Unit 2 Containment.Procedure 1-PT-112 Revised ML20246A9291989-06-30030 June 1989 Advises That 30 Day Rept Re 890608 Inoperable Safeguards Area Ventilation Sys Not Required Since First Damper in Series Operable.Safeguards Area Ventilation Sys Operable During Incident ML20246C3131989-06-27027 June 1989 Special Rept:On 890528,min Number of Operable Smoke Detectors on Containment Recirculation Air Sys Not Restored to Operable Status within 14 Days.On 890602,detectors Returned to Operable Status.Engineering Evaluation Underway ML20245J5151989-04-28028 April 1989 Ro:On 890309,differential Settlement Between Svc Bldg & Unit 2 Main Steam Valve House Indicated That 110% of Current Allowable Differential Settlement Occurred.Differential Settlement Result of Inaccuracies in Survey Rod Utilized ML20248J8521989-04-0707 April 1989 Special Rept:On 890302,projected Doses Due to Radioactive Liquid Effluents Discharged to Unrestricted Areas Exceeded 0.06 Mrem Total Body in 31 Day Period.Caused by Calculation Error.Radiological Effluent Tech Specs to Be Computerized ML20236B9431989-03-17017 March 1989 Special Rept:On 890216,diesel Driven Fire Pump Out of Svc Greater than 7 Days,Per Tech Spec 3.7.14.1.Foreign Object Caused Damage to Pump Impeller,Number 3 Wear Rings & Lateral Rings.Repairs to Pumps Being Performed on Priority Basis ML20235M7631989-02-20020 February 1989 Special Rept:On 890206,Kaman Vent Stack B Radiation Monitor RI-VG-180 Inoperable for Greater than 72 H.Monitor Inoperable Due to High Radiation Levels.Sticking Check Source Repaired ML20155J2301988-10-20020 October 1988 Special Rept:On 880910,containment Mat Triaxial Response Spectrum Recorder Inoperable for More than 30 Days.Repairs to Alarm Circuit of Recorder Will Be Performed During Unit 1 1989 Refueling Outage ML20245D8881988-09-29029 September 1988 Ro:On 880915,Kaman Process Vent Radiation Monitor RI-GW-178 Exceeded Action Statement of Tech Spec 3.3.3.1.Smear Results Indicated That Check Source Had Started to Leach.Probably Caused by Condensation.Evaluation Being Performed ML20153E9651988-08-29029 August 1988 Ro:On 880813,Kaman Vent Stack a Radiation Monitor RI-VG-179 Declared Inoperable.Caused by Central Processing Unit Board Malfunction.New Board Ordered & Expected to Be Received on 881009 ML20207G5701988-08-17017 August 1988 Ro:On 880803,Kaman Process Vent Radiation Monitor RI-GW-178 Exceeded Action Statement 35 of Tech Specs 3.3.3.1.Caused by Technical Problems Encountered During Calibr of RI-GW-178. RI-GW-178 Returned to Svc & Action Statement Cleared ML20151R1341988-08-0505 August 1988 Ro:On 880607,differential Settlement Between Svc Bldg & Main Steam Valve House Exceeded 75% of Allowable Value.Effect of Four Buried Svc Water Header Lines Running Between Two Structures of Primary Concern.Tech Spec Change Requested ML20237G7591987-08-14014 August 1987 Special Rept:On 870601,differential Settlement Between Svc Bldg & Main Steam Valve House Exceeded 75% Allowable Value of 0.03 Ft.Tech Spec Change Request Being Considered to Increase Allowable Value to 0.047 Ft.Engineering Rept Encl ML20235P3131987-07-0909 July 1987 Special Rept:During Startup Physics Testing,Positive Moderator Temp Coefficient of +1.24 Pcm/F Measured. Conservative Calculations Demonstrate That Moderator Temp Coefficient Will Be Negative at 70% Reactor Power ML20205H4201986-08-0808 August 1986 Ro:On 860805,automatic Level Controller for Bearing Cooling Water Tower Malfunctioned,Releasing Approx 1,500 Gallons Water to Discharge Canal.Controller Placed in Manual Position ML20091Q4021984-06-0707 June 1984 Special Rept SP-N1-84-02:on 840512,specific Activity of RCS Exceeded Tech Spec Dose Equivalent I-131 Limit of 1.0 Uci/G.Caused by Minor Fuel Element Defects.Primary Coolant Sampled & Analyzed ML20080H3891984-02-0101 February 1984 Special Rept SP-N1-84-01:on 840109,following Unit Rampdown, I-131 Dose Equivalent Specific Activity Exceeded 1.0 Mci/G. Caused by Minor Fuel Element Defects in Reactor Core. Reactor Power Change Rates Administratively Limited ML20080H9811984-02-0101 February 1984 RO SP-N1-84-01:on 840109,I-131 Dose Equivalent Specific Activity Exceeded Tech Spec Limit.Caused by Minor Fuel Element Defects in Reactor Core.Primary Coolant Sampled & Analyzed at Accelerated Frequency ML20126C5311980-03-17017 March 1980 RO 80-035/01T-0:insps at Foreign Plant Revealed Stress Corrosion Cracking in Westinghouse Control Rod Guide Tube Support Pin,Solution heat-treated at 1825 F.Ultrasonic Insps Will Be Done 1999-10-20 Category:TEXT-SAFETY REPORT MONTHYEARML20217N9281999-10-20020 October 1999
[Table view]Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su ML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20210S1411999-07-31031 July 1999 Monthly Operating Repts for July 1999 for North Anna Power Station.With ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML20209E5641999-06-30030 June 1999 Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With ML20195G1901999-05-31031 May 1999 Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206Q6671999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20205K3041999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With ML20207K5921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With ML20207E1731999-02-18018 February 1999 Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year ML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML20199C8781998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20198J5561998-12-0303 December 1998 ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps ML20197G8551998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for North Anna Power Station,Units 1 & 2.With ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20195D0571998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for North Anna Power Station,Units 1 & 2.With ML20154L0691998-10-14014 October 1998 COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy ML20155J6911998-10-0909 October 1998 Staff Response to Tasking Memorandum & Stakeholder Concerns ML20154H4001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for North Anna Power Station,Units 1 & 2.With ML20151X8011998-09-10010 September 1998 Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section ML20151W4711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for North Anna Power Station Units 1 & 2.With ML20237A4341998-07-31031 July 1998 Monthly Operating Repts for July 1998 for North Anna Power Station,Units 1 & 2 ML20236V1251998-07-14014 July 1998 ISI Summary Rept for Naps,Unit 2,1998 Refueling Outage Owners Rept of Isis ML20236K5531998-07-0707 July 1998 SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment ML20236M3381998-06-30030 June 1998 Monthly Operating Repts for June 1998 for North Anna Power Station,Units 1 & 2 ML20248M1011998-05-31031 May 1998 Monthly Operating Repts for May 1998 for North Anna Power Station,Units 1 & 2 ML20248C8831998-05-29029 May 1998 SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program ML20247K9281998-05-15015 May 1998 Special Rept:On 980428,letdown PCV Exhibited Slow Response When C RCP Was Started.Cause to Be Determined.Review of Operating Procedure Will Be Performed to Determine If Enhancements Are Necessary ML20216A8971998-05-0606 May 1998 Rev 0 to Cycle 13 Pattern Ud COLR for North Anna Unit 2 ML20247F4441998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for North Anna Power Station,Units 1 & 2 ML20217B5321998-04-20020 April 1998 Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs ML20217H9611998-04-0707 April 1998 Special Rept:On 980216,groundwater Level at Piezometer P-22, Again Noted to Be Above Max Water Level by 0.41 Feet.Design Package for Installation of Addl Standpipe Piezometers at Toe of Slope Southeast Section,Developed ML20216B1891998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for North Anna Power Station,Units 1 & 2 ML20216E8801998-03-0606 March 1998 Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii) ML20216E2561998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for North Anna Power Station,Units 1 & 2 ML20199J6431998-02-0202 February 1998 Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218 ML20202D5811998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for North Anna Power Station,Units 1 & 2 ML20198S7571998-01-15015 January 1998 Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping ML20198P1351997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for North Anna Power Station,Units 1 & 2 1999-09-08 |
Text
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Tech. Spec. 6.9.2.h VInOINIA ELucTnic AND Pownn Comwxy HIcnwonn,VinoINIA 20261 W,1,. STEWAMT Vaca Passanswv w o cm o '""^*"" July 9, 1987 United States Nuclear Regulatory Commission Serial No.87-370 Attention: Document Control Desk N0/NSP Washington, D.C. 20555 Docket No. 50-338 License No. NPF-4 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 SPECIAL REPORT - POSITIVE MODERATOR TEMPERATURE COEFFICIENT During Startup Physics Testing for Unit 1. Cycle 7, a positive moderator temperature coefficient of +1.24 pcm/ F was measured. Conservative calculations demonstrate that the moderator temperature coefficient will be negative at 70% reactor power. Therefore, control rod withdrawal limits are not necessary since these values are within the Technical Specification limits of section 3.1.1.4.a. This report is submitted in accordance with Technical Specification 6.9.2.h.
Very trul' yours, 4 \
g-
~.
\gKdN W. L. S wart cc: U. S. Nuclear Regulatory Commission 101 Marietta Street, N.W.
Suite 2900 Atlanta, CA 30323 Mr. J. L. Caldwell NEC Senior Resident Inspector North Anna Power Station i
8707200441 8'70709 PDR ADOCK0500:l]I3 f
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