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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20043A9761990-05-18018 May 1990 Special Rept:On 900418,diesel Generator 1B Tripped on Overspeed During Start Attempts 688 & 689.Possibly Caused by Test Lead Hookup or Inductive Voltage Spike Preventing Field Flash.Diodes Installed Across Coils in All Five Relays ML19332E8171989-11-29029 November 1989 Special Rept:On 891030,diesl Generator 1A Declared Inoperable.Caused by Discovery of Large Fuel Oil Leak from Valve 1FD-83 Vent Hole.New Valve Diaphragm Installed in Valve.On 891106,valve Found Leaking Again & Replaced ML19325F3421989-11-13013 November 1989 Revised Special Rept:On 890914,pressurizer Level Indication in Standby Shutdown Facility Failed Low.Caused by Faulty Pressure Sensing Element.Rept Written to Replace Pressure Transmitters ML19324C1641989-11-0202 November 1989 Revised Special Rept:On 890914,operations Determined That Pressurizer Level Indication in Standby Shutdown Facility Failed Low.Caused by Faulty Pressure Sensing Element.Faulty Transmitter Taken to Vendor for Repair.Transmitter Replaced ML19327B6271989-10-23023 October 1989 Special Rept:On 890909,determined That Pressurizer Level Indication in Standby Shutdown Facility Failed Low.Caused by Faulty Pressure Sensing Element.Faulty Transmitters Taken to Vendor for Repair.Barton Transmitter Installed ML19327A9861989-10-10010 October 1989 Ro:On 890922,loss of Power to Sirens Occurred Due to Power Lines Downed by Hurricane Hugo.Ler Will Be Submitted Re Event ML20023C6441983-05-0606 May 1983 Advises That All Info Re RO 369/83-18 on 830407 on Snubber Operability Unavailable.Complete Rept Will Be Submitted by 830520 ML20028A4661982-11-11011 November 1982 RO 369/82-74:rept Due on 821112 Will Be Issued by 821130 Due to Incomplete Investigation of Containment Air Lock Failure ML20052B9031982-04-20020 April 1982 RO 369/82-07:on 820111,811224 & 0914,safety Injection Sys Activated.Caused by Excessive Feedwater Pumped Into Steam Generators on 810914,by Operator Error on 811224 & by Cold Weather on 820111 ML20052A2561982-04-19019 April 1982 RO 369/82-25:on 820318,RCS Tech Spec Limit Violated. Thirty-day Rept,Due on 820416,cannot Be Completed on Time. Rept Will Be Submitted by 820430 ML20052A5641982-04-0808 April 1982 RO 369/82-24:on 820302,Tech Spec Requiring Two Operable RHR Loops & One Operating RHR Loop Violated.Cause Under Investigation.Next Rept Will Be Provided by 820419 ML20052A5931982-03-15015 March 1982 Advises That Updated Rept Re RO-369/81-194 Will Be Provided by 820331 ML20049J5621982-02-26026 February 1982 Ro:Notifying of Postponement of Submittal of RO-369/82-15 Re Cavitation of Centrifugal Charging Pumps.Investigation Not Completed.Rept Will Be Submitted by 820308 ML20049J5171982-02-26026 February 1982 Advises That Update of RO 81-194/03L-0 Is Not Complete.Rept to Be Submitted by 820310 ML20040F0871982-01-26026 January 1982 RO 369/81-161:cable for High Range Radiation Monitor Received,But Installation Delayed Because Environ Qualification Not Complete.Testing to Be Completed by 820315 & Installation by June 1982 ML20040F0931982-01-20020 January 1982 RO 369/82-01:on 820106,Region 2 Notified That Criteria Re Nonseismic Pipe Interaction W/Nuclear safety-related Equipment Found to Have Been Violated.Investigation Delayed Due to Severe Weather.Rept to Be Submitted by 820203 ML20039C4541981-12-18018 December 1981 Special Rept Re Fire Barrier Penetrations in Violation of Tech Spec Requirement That All Fire Barrier Penetrations Shall Be Functional.Fire Dampers Will Be Installed in Four Ducts W/Sealing Around Duct Penetrations ML20011A9071981-10-27027 October 1981 RO 81-277:on 811001,discovered That Shear Plates for Lower Support of Containment Spray Heat Exchanger Were Never Installed.Caused by Installation Problems.Shear Plates Installed ML20038C8111981-08-25025 August 1981 Ro:During Zero Power Physics Testing,All Rods Withdrawn & Isothermal Temp Coefficient Measured - 0.56 Pcm/F.Operating Limits Will Be Established Until Poisons Have Been Built Up to Preclude Positive Mtc ML20010C7021981-08-11011 August 1981 RO 369/81-99:on 810611,Tech Spec 3.3.3.8 Re Radioactive Liquid Effluent Monitoring Instrumentation Channels,Was Thought to Have Been Violated.Investigation Determined Incident Not to Be Reportable as RO ML20009C6321981-07-10010 July 1981 Advises That RO-369/81-99,re 810610 Excessive Alarm/Trip Setpoints for Radioactive Liquid Effluent Monitoring Instrumentation Channels,Will Be Submitted by 810810 ML20009F6031981-04-0909 April 1981 Ro:On 810409,after Period of Routine Operation,Discovered Diesel Generator Could Enter Intake of Ventilation Sys for Technical Support Sys.Design Changes Initiated to Relocate Intake & Install Monitors 1990-05-18
[Table view] Category:LER)
MONTHYEARML20043A9761990-05-18018 May 1990 Special Rept:On 900418,diesel Generator 1B Tripped on Overspeed During Start Attempts 688 & 689.Possibly Caused by Test Lead Hookup or Inductive Voltage Spike Preventing Field Flash.Diodes Installed Across Coils in All Five Relays ML19332E8171989-11-29029 November 1989 Special Rept:On 891030,diesl Generator 1A Declared Inoperable.Caused by Discovery of Large Fuel Oil Leak from Valve 1FD-83 Vent Hole.New Valve Diaphragm Installed in Valve.On 891106,valve Found Leaking Again & Replaced ML19325F3421989-11-13013 November 1989 Revised Special Rept:On 890914,pressurizer Level Indication in Standby Shutdown Facility Failed Low.Caused by Faulty Pressure Sensing Element.Rept Written to Replace Pressure Transmitters ML19324C1641989-11-0202 November 1989 Revised Special Rept:On 890914,operations Determined That Pressurizer Level Indication in Standby Shutdown Facility Failed Low.Caused by Faulty Pressure Sensing Element.Faulty Transmitter Taken to Vendor for Repair.Transmitter Replaced ML19327B6271989-10-23023 October 1989 Special Rept:On 890909,determined That Pressurizer Level Indication in Standby Shutdown Facility Failed Low.Caused by Faulty Pressure Sensing Element.Faulty Transmitters Taken to Vendor for Repair.Barton Transmitter Installed ML19327A9861989-10-10010 October 1989 Ro:On 890922,loss of Power to Sirens Occurred Due to Power Lines Downed by Hurricane Hugo.Ler Will Be Submitted Re Event ML20023C6441983-05-0606 May 1983 Advises That All Info Re RO 369/83-18 on 830407 on Snubber Operability Unavailable.Complete Rept Will Be Submitted by 830520 ML20028A4661982-11-11011 November 1982 RO 369/82-74:rept Due on 821112 Will Be Issued by 821130 Due to Incomplete Investigation of Containment Air Lock Failure ML20052B9031982-04-20020 April 1982 RO 369/82-07:on 820111,811224 & 0914,safety Injection Sys Activated.Caused by Excessive Feedwater Pumped Into Steam Generators on 810914,by Operator Error on 811224 & by Cold Weather on 820111 ML20052A2561982-04-19019 April 1982 RO 369/82-25:on 820318,RCS Tech Spec Limit Violated. Thirty-day Rept,Due on 820416,cannot Be Completed on Time. Rept Will Be Submitted by 820430 ML20052A5641982-04-0808 April 1982 RO 369/82-24:on 820302,Tech Spec Requiring Two Operable RHR Loops & One Operating RHR Loop Violated.Cause Under Investigation.Next Rept Will Be Provided by 820419 ML20052A5931982-03-15015 March 1982 Advises That Updated Rept Re RO-369/81-194 Will Be Provided by 820331 ML20049J5621982-02-26026 February 1982 Ro:Notifying of Postponement of Submittal of RO-369/82-15 Re Cavitation of Centrifugal Charging Pumps.Investigation Not Completed.Rept Will Be Submitted by 820308 ML20049J5171982-02-26026 February 1982 Advises That Update of RO 81-194/03L-0 Is Not Complete.Rept to Be Submitted by 820310 ML20040F0871982-01-26026 January 1982 RO 369/81-161:cable for High Range Radiation Monitor Received,But Installation Delayed Because Environ Qualification Not Complete.Testing to Be Completed by 820315 & Installation by June 1982 ML20040F0931982-01-20020 January 1982 RO 369/82-01:on 820106,Region 2 Notified That Criteria Re Nonseismic Pipe Interaction W/Nuclear safety-related Equipment Found to Have Been Violated.Investigation Delayed Due to Severe Weather.Rept to Be Submitted by 820203 ML20039C4541981-12-18018 December 1981 Special Rept Re Fire Barrier Penetrations in Violation of Tech Spec Requirement That All Fire Barrier Penetrations Shall Be Functional.Fire Dampers Will Be Installed in Four Ducts W/Sealing Around Duct Penetrations ML20011A9071981-10-27027 October 1981 RO 81-277:on 811001,discovered That Shear Plates for Lower Support of Containment Spray Heat Exchanger Were Never Installed.Caused by Installation Problems.Shear Plates Installed ML20038C8111981-08-25025 August 1981 Ro:During Zero Power Physics Testing,All Rods Withdrawn & Isothermal Temp Coefficient Measured - 0.56 Pcm/F.Operating Limits Will Be Established Until Poisons Have Been Built Up to Preclude Positive Mtc ML20010C7021981-08-11011 August 1981 RO 369/81-99:on 810611,Tech Spec 3.3.3.8 Re Radioactive Liquid Effluent Monitoring Instrumentation Channels,Was Thought to Have Been Violated.Investigation Determined Incident Not to Be Reportable as RO ML20009C6321981-07-10010 July 1981 Advises That RO-369/81-99,re 810610 Excessive Alarm/Trip Setpoints for Radioactive Liquid Effluent Monitoring Instrumentation Channels,Will Be Submitted by 810810 ML20009F6031981-04-0909 April 1981 Ro:On 810409,after Period of Routine Operation,Discovered Diesel Generator Could Enter Intake of Ventilation Sys for Technical Support Sys.Design Changes Initiated to Relocate Intake & Install Monitors 1990-05-18
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G7951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20216E8851999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H1731999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20195K3691999-05-31031 May 1999 Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20195K3761999-04-30030 April 1999 Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206R0891999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML20206R0931999-03-31031 March 1999 Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P8991999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205C4171999-03-25025 March 1999 Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed ML20207K2051999-03-0505 March 1999 Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed ML20204C8911999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P9021999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20204C8961999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for McGuire Nuclear Station,Units 1 & 2 ML20199E0301998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for McGuire Nuclear Station,Units 1 & 2 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20198A4481998-12-11011 December 1998 Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted ML20198D7561998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 ML20199E0491998-11-30030 November 1998 Revised Monthly Operating Rept for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 Re Personnel Exposure ML20199E9651998-11-24024 November 1998 Rev 1 to ATI-98-012-T005, DPC Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility ML20196D4171998-11-24024 November 1998 Special Rept 98-02:on 981112,failure to Implement Fire Watches in Rooms Containing Inoperable Fire Barrier Penetrations,Was Determined.Repair of Affected Fire Barriers in Progress ML20196G0581998-11-0606 November 1998 Rev 17 to COLR Cycle 13 for McGuire Unit 1 ML20196G0761998-11-0606 November 1998 Rev 15 to COLR Cycle 12 for McGuire Unit 2 ML20198D7771998-10-31031 October 1998 Revised Monthly Operating Rept for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E5961998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154L6251998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E6021998-09-30030 September 1998 Revised Monthly Operating Rept for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154B4131998-09-22022 September 1998 Rev 0 to ISI Rept for McGuire Nuclear Unit 1 Twelfth Refueling Outage ML20151W3521998-09-0808 September 1998 Special Rept 98-01:on 980819,maint Could Not Be Performed on FPS Due to Isolation Boundary Leakage.Caused by Inadequate Info Provided in Fire Impairment Plan.Isolated Portion of FPS Was Returned to Svc ML20154L6321998-08-31031 August 1998 Rev 1 to MOR for Aug 1998 for McGuire Nuclear Station,Unit 1 ML20153B3741998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236U1601998-07-31031 July 1998 Non-proprietary DPC-NE-2009, DPC W Fuel Transition Rept ML20237B2381998-07-31031 July 1998 Monthly Operating Repts for July 1998 for McGuire Nuclear Station,Units 1 & 2 ML20153B3931998-07-31031 July 1998 Revised Monthly Operating Repts for Jul 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236P0451998-07-0808 July 1998 Part 21 Rept Re non-conformance & Potential Defect in Component of Nordberg Model FS1316HSC Standby Dg.Caused by Outer Spring Valves Mfg from Matl That Did Not Meet Specifications.Will Furnish Written Rept within 60 Days 1999-09-30
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DUKE POWER GOMPANY l P.O. DOX 33889 '
1
' I CHAR Arrw N.O. 98948 ,
. >mALm.w ouza -, j..- .)
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< i i : October 23, 1989 :
l f
, . U.S. Nuclear Regulatory Comission -
-> Document Control Desk '
Washington, DC 20555 x '
Subject:
McGuire Nuclear Station, Units 1 and 2 i Docket Nos. 50-369 and 50-370 i Standby Shutdown Facility Special Report :
. l
[ ' Gentlemen:
Pursuant to FSAR Selected Licensee Comitment 16.9-7, Standby Shutdown Facility (SSF).. find attached a tpecial report concerning the inoperability of the SSF :
Pressurizer Level Indication.
If you have any questions, please contact S.E. LeRoy at (704) 373-6233.
Very truly yours,- !
h .
lal E.' Tucker' !
SEL/467 l l ,
Attachment
' xc Mr. S.D. Ebneter, Administrator Mr. P.K. Van Doorn ,
U.S. Nuclear Regulatory Comission NRC Senior Resident Inspector l
- i. Region II McGuire Nuclear Station i 101 Marietta St. , NW, Suite 2900 ?
' Atlanta, Georgia 30323 l'
Mr. 'D.S. Hood, Project Manager INPO Records Center Office of Nuclear Reactor Regulation Su'.te 1500 ,
l- ,
- U.S. Nuclear Regulatory Comission n 00 Circle 75 Parkway ,
t Washington, DC 20555 Atlanta, Georgia 30339
?
l-
, f I I' '8911030014 891023 9
'[DR- ADOCK Ogg6,9 _ _ _ __
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f ;
I. ;< U.S. Nuc1 car Regulatory Commission ;
Document Control Desk i Docket Nos. 50-369 and 50-370 j October 23, 1989 t
Attachment '
- Duke Power Company ,
McGuire Nuclear Station l Standby Shutdown Facility Special Report I
! l t ,
On September 9, 1989 at 0430, Operations determined that the Pressurizer Level Indication in the Standby Shutdown Facility (SSF) had failed low. A work request was written at 1500 to investigate and repair the level indication. All ;
l' L components in the' loop were verified correct with the exception of level L transmitter INCLT5151. Additionally, the remote amp could not be verified correct l due to a problem in the wiring harness. The problem was believed to be faulty pressure sensing element. The spare trans,.iitters located in the warehouse could not be calibrated, and no other replacement transmitter could be located. The '
i seventh day of inoperability occurred on September 21, 1989 at 0430.
Level transmitter 1NCLT5151 is a Foxboro Model E13DM split architecture .!
differential pressure transmitter. Split architecture refers to the separate !
pressure sensing and amplifier component. The pressure sensing element is located
- in the Annt.lus, and the remote amplifier is located in the switchgear room located ,
on the 750 ft. elevation of the Auxiliary Building. The Foxboro E13DM is obsolete '
and no longer available from the Foxboro company. Three Foxboro E13DMs located in our warehouse could not be calibrated. Due to the split architecture of these !
transmitters, there was great difficulty determining which element of the !
transmitter was at fault.- This problem was compounded by problems in the remote !
amp wiring harness. .
The. faulty transmitters were taken to the vendor for repairs however, none of the transmitters would operate satisfacterily. A stat'on problem report was written to replace the Foxboro E13DM with another type transmitter. McGuire Exempt i Variation Notice No. 2055 was written to replace the Foxboro E13Dm with a Barton Model 764 pressure transmitter. The Barton transmitter was installed per work
- request no. 96999 on October 11, 1989. Operations declared the SSF Pressurizer Level Indication operable the same day.
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