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| {{#Wiki_filter:ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)DOCKET 05000528 05000529 | | {{#Wiki_filter:ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| | ACCESSION NBR:9406210193 DOC.DATE: 94/06/09 NOTARIZED: NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 AUTH. NAME AUTHOR AFFILIATION LEVINE,J.M. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Special Rept 1-SR-94-001:on 940511,plant ventilation sys hxgh range effluent monitors in Units 1&2 inoperable for periods greater than 72 h.Caused by high voltage failure alarm.Design change package installed. | | Special Rept 1-SR-94-001:on 940511,plant ventilation sys hxgh range effluent monitors in Units 1 & 2 inoperable for periods greater than 72 h.Caused by high voltage failure alarm. Design change package installed. |
| DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.ACCESSION NBR:9406210193 DOC.DATE: 94/06/09 NOTARIZED: | | DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL SIZE: |
| NO FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi AUTH.NAME AUTHOR AFFILIATION LEVINE,J.M.
| | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| Arizona Public Service Co.(formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)NOTES:STANDARDIZED PLANT Standardized plant.05000528 05000529 RECIPIENT ID CODE/NAME PDIV-3 PD TRAN,L INTERNAL: ACRS AEOD/ROAB/DS P NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DSSA/SPLB NRR/PMAS/IRCB-E RES/DSIR/EIB EXTERNAL: EG&G BRYCE,J.H NRC PDR NSIC POORE,W.COPIES LTTR ENCL 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 RECIPIENT ID CODE/NAME HOLIAN, B AEOD/DS P/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRSS/PRPB NR-SSA SRXB EG F LE 02 N ILE 01 L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1.1 1'1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
| | NOTES:STANDARDIZED PLANT 05000528 Standardized plant. 05000529 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDIV-3 PD 1 1 HOLIAN, B 1 1 TRAN,L 1 1 INTERNAL: ACRS 1 1 AEOD/DS P/TPAB 1 '. 1 AEOD/ROAB/DS P 2 2 NRR/DE/EELB 1 NRR/DE/EMEB 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRSS/PRPB 2 2 NRR/DSSA/SPLB 1 1 NR - SSA SRXB 1 1 NRR/PMAS/IRCB-E 1 1 EG F LE 02 1 1 RES/DSIR/EIB 1 1 N ILE 01 1 1 EXTERNAL: EG&G BRYCE,J.H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS: |
| PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LIPID FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 28 Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O.BOX 52034~PHOENIX, ARIZONA 85072-2034 JAMES M.LEVINE VICE PRESIOB4T NUCLEAR PRODUCTION 102-03002-JML/BAG/P JC June 9, 1994 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, D.C.20555 | | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LIPID FOR DOCUMENTS YOU DON'T NEED! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 28 |
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| | Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O. BOX 52034 ~ PHOENIX, ARIZONA85072-2034 JAMES M. LEVINE 102-03002-JML/BAG/P JC VICE PRESIOB4T NUCLEAR PRODUCTION June 9, 1994 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, D. C. 20555 |
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| ==Dear Sirs:== | | ==Dear Sirs:== |
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| ==Subject:== | | ==Subject:== |
| Palo Verde Nuclear Generating Station (PVNGS)Units 1 and 2 Docket No.STN 50-528 (License No.NPF-41)Docket No.STN 50-529 (License No.NPF-51)Special Report 1-SR-94-001 File: 94-020-404 Enclosed please find Special Report 1-SR-94-001 prepared and submitted pursuant to the requirements of the PVNGS Qffsite Dose Calculation Manual and Technical Specification 6.9.2.This report discusses the Plant Ventilation System High Range Effluent Monitors (RU-144)in Units 1 and 2 being inoperable for a period greater than 72 hours.If you have any questions, please contact Burton A.Grabo, Supervisor, Nuclear Regulatory Affairs, at (602)393-6492.Sincerely, JML/BAG/P JC Enclosure cc: L.J.Caltan K.E.Perkins K.E.Johnston (all w/enclosure) | | Palo Verde Nuclear Generating Station (PVNGS) |
| A 9406210193 94060'TI PDR ADat:K OS00OS2a S PDR t/~g3 PALO VERDE NUCLEAR GENERATING STATlON UNITS 1 AND 2 PLANT VENTILATlON SYSTEM HlGH RANGE EFFLUENT MONITOR RU-144 INOPERABLE Docket No.STN 50-528 (License No.NPF-41)Docket No.STN 50-529 (License No.NPF-51)Special Report 1-SR-94-001 Initial Conditions On May 11, 1994, Units 1 and 2 were in Mode 1 (POWER OPERATION) operating at approximately 86 percent power.Descri tion of Event This special report is being submitted pursuant to the requirements of the PVNGS Offsite Dose Calculation Manual (ODCM)and Technical Specification 6.9.2 to report an event (three occurrences) in which the Plant Ventilation System High Range Effluent Monitors in Units 1 and 2 were inoperable for periods greater than 72 hours.The 72-hour periods for returning the monitors to service were exceeded in Unit 1 at approximately 0952 MST on May 23, 1993, and at approximately 0745 MST on March 18, 1994.In Unit 2, the 72-hour period for returning the monitor to service was exceeded at approximately 0945 MST on April 23, 1993.Back round Radiation monitors RU-143 (Plant Ventilation System Low Range Effluent Monitor)and RU-144 work as a pair.RU-143 is normally in service and continuously monitors plant ventilation exhaust.RU-144 is automatically started when RU-143 reaches a predetermined setpoint.RU-144 is provided for tracking radioactive effluents during postulated accident scenarios.
| | Units 1 and 2 Docket No. STN 50-528 (License No. NPF-41) |
| Prior to 1993, the low range monitor was required to be operable for the high range monitor to be considered operable.Therefore, if the low range monitor was inoperable, the high range monitor was also inoperable, and ODCM, Table 2.1, Action 42, which requires initiation of the Preplanned Alternate Sampling Program, was applicable. | | Docket No. STN 50-529 (License No. NPF-51) |
| During the first quarter of 1993, Design Change Package (DCP)13PJ-SQ-066 was installed for the Plant Ventilation System effluent monitoring pairs in Units 1 and 2.The DCP allowed the high range monitor to be operable when the low range monitor was out-of-service by placing the high range monitor in a mode designated as Handover Disable.lf only the low range monitor was out-of-service, the high range monitor could be placed in the handover disable mode, remain operable, and ODCM, Table 2.1, Action 42 would not apply. | | Special Report 1-SR-94-001 File: 94-020-404 Enclosed please find Special Report 1-SR-94-001 prepared and submitted pursuant to the requirements of the PVNGS Qffsite Dose Calculation Manual and Technical Specification 6.9.2. This report discusses the Plant Ventilation System High Range Effluent Monitors (RU-144) in Units 1 and 2 being inoperable for a period greater than 72 hours. |
| Cause of Event On May 11, 1994, plant personnel performing troubleshooting under an approved work document identified that a high voltage failure alarm and a detector failure alarm would not annunciate when the high range monitor was in handover disable mode.Errors that prevented the alarms from annunciating in the handover disable mode were found in the vendor-revised software code.The software errors were associated with the changes made by the DCP in the section of code which controls monitor and channel handover.For the monitor to be considered operable in accordance with the ODCM, control room alarm annunciation must be demonstrated to occur if the instrument indicates a downscale failure (detector failure).Therefore, the high range monitor was not operable, even in the handover disable mode, when the low range monitor was inoperable. | | If you have any questions, please contact Burton A. Grabo, Supervisor, Nuclear Regulatory Affairs, at (602) 393-6492. |
| Undetected errors in the vendor-revised software code associated with the DCP were the cause of the condition. | | Sincerely, JML/BAG/PJC Enclosure cc: L. J. Caltan (all w/enclosure) |
| The PVNGS software test plan in the DCP required testing only for those conditions and functions that were known to have changed.The detector failure and high voltage failure alarms were not expected to have changed.Corrective Action The APS investigation determined that the Plant Ventilation high range monitor in Unit 3 and the Fuel Building Ventilation high range monitors (RU-1 46)in all three units were also affected by the software errors;however, the only periods of inoperability that exceeded the 72-hour limit for returning the monitors to service are discussed below.A review of low range monitor inoperability from the time the DCP was installed until the present was performed to determine if there were periods of inoperability in excess of 72 hours.Three occurrences of a low range monitor being'inoperable for periods greater than 72 hours while the high range monitor was believed to be operable in the handover disable mode were identified. | | K. E. Perkins K. E. Johnston A |
| These periods of inoperability were: Unit 2 RU-143/144 0945 MST, 04/20/93 to 1520 MST, 05/05/93 366 Hours Unit 1 RU-143/144 0952 MST, 05/20/93 to 1243 MST, 05/25/93 123 Hours Unit 1 RU-143/144 0745 MST, 03/15/94 to 1230 MST, 03/19/94 101 Hours Although the monitors could not be considered operable during these periods, they were operating normally and were functional with the exception of annunciation capability for a detector failure.Based upon the satisfactory completion of the monthly source checks, there were no detector failures during the periods of high range monitor inoperability. | | 9406210193 94060'TI t PDR ADat:K OS00OS2a S PDR |
| A Quality Assurance audit in mid-1993 identified deficiencies in the control of plant process software including procurement of contract software and control of vendor problem reporting. | | /~g3 |
| Extensive corrective actions are being developed to resolve concerns associated with the design, installation, and configuration of process software.Such problems as errors in vendor-provided software are being addressed within the overall context of the corrective action plan.Resolution is being tracked by an open Quality l' | | |
| Assurance corrective action document.To resolve the specific software problems identified in this report, Setpoint Change Request (SPCR)S13J-SQ-015 has been developed to correct the software errors in the affected monitors.The SPCR contains an extensive Design Validation Test that will test all of the software features, not just those that have been modified, to demonstrate that the software will perform as designed in all modes of operation. | | PALO VERDE NUCLEAR GENERATING STATlON UNITS 1 AND 2 PLANT VENTILATlONSYSTEM HlGH RANGE EFFLUENT MONITOR RU-144 INOPERABLE Docket No. STN 50-528 (License No. NPF-41) |
| The corrected software will be installed and tested by July 29, 1994.Once the Design Validation Test has been used to verify SPCR S13J-SQ-01 5 and has been established as a thorough software test for the monitors, it will be used as the design retest whenever significant modifications are made to the source codes.In the interim, the affected monitors are operable.Administrative controls which prohibit using the high range monitors in the handover disable mode have been implemented.}} | | Docket No. STN 50-529 (License No. NPF-51) |
| | Special Report 1-SR-94-001 Initial Conditions On May 11, 1994, Units 1 and 2 were in Mode 1 (POWER OPERATION) operating at approximately 86 percent power. |
| | Descri tion of Event This special report is being submitted pursuant to the requirements of the PVNGS Offsite Dose Calculation Manual (ODCM) and Technical Specification 6.9.2 to report an event (three occurrences) in which the Plant Ventilation System High Range Effluent Monitors in Units 1 and 2 were inoperable for periods greater than 72 hours. The 72-hour periods for returning the monitors to service were exceeded in Unit 1 at approximately 0952 MST on May 23, 1993, and at approximately 0745 MST on March 18, 1994. In Unit 2, the 72-hour period for returning the monitor to service was exceeded at approximately 0945 MST on April 23, 1993. |
| | Back round Radiation monitors RU-143 (Plant Ventilation System Low Range Effluent Monitor) and RU-144 work as a pair. RU-143 is normally in service and continuously monitors plant ventilation exhaust. RU-144 is automatically started when RU-143 reaches a predetermined setpoint. RU-144 is provided for tracking radioactive effluents during postulated accident scenarios. Prior to 1993, the low range monitor was required to be operable for the high range monitor to be considered operable. Therefore, if the low range monitor was inoperable, the high range monitor was also inoperable, and ODCM, Table 2.1, Action 42, which requires initiation of the Preplanned Alternate Sampling Program, was applicable. |
| | During the first quarter of 1993, Design Change Package (DCP) 13PJ-SQ-066 was installed for the Plant Ventilation System effluent monitoring pairs in Units 1 and 2. The DCP allowed the high range monitor to be operable when the low range monitor was out-of-service by placing the high range monitor in a mode designated as Handover Disable. |
| | lf only the low range monitor was out-of-service, the high range monitor could be placed in the handover disable mode, remain operable, and ODCM, Table 2.1, Action 42 would not apply. |
| | |
| | Cause of Event On May 11, 1994, plant personnel performing troubleshooting under an approved work document identified that a high voltage failure alarm and a detector failure alarm would not annunciate when the high range monitor was in handover disable mode. Errors that prevented the alarms from annunciating in the handover disable mode were found in the vendor-revised software code. The software errors were associated with the changes made by the DCP in the section of code which controls monitor and channel handover. |
| | For the monitor to be considered operable in accordance with the ODCM, control room alarm annunciation must be demonstrated to occur if the instrument indicates a downscale failure (detector failure). Therefore, the high range monitor was not operable, even in the handover disable mode, when the low range monitor was inoperable. |
| | Undetected errors in the vendor-revised software code associated with the DCP were the cause of the condition. The PVNGS software test plan in the DCP required testing only for those conditions and functions that were known to have changed. The detector failure and high voltage failure alarms were not expected to have changed. |
| | Corrective Action The APS investigation determined that the Plant Ventilation high range monitor in Unit 3 and the Fuel Building Ventilation high range monitors (RU-1 46) in all three units were also affected by the software errors; however, the only periods of inoperability that exceeded the 72-hour limit for returning the monitors to service are discussed below. |
| | A review of low range monitor inoperability from the time the DCP was installed until the present was performed to determine if there were periods of inoperability in excess of 72 hours. Three occurrences of a low range monitor being'inoperable for periods greater than 72 hours while the high range monitor was believed to be operable in the handover disable mode were identified. These periods of inoperability were: |
| | Unit 2 RU-143/144 0945 MST, 04/20/93 to 1520 MST, 05/05/93 366 Hours Unit 1 RU-143/144 0952 MST, 05/20/93 to 1243 MST, 05/25/93 123 Hours Unit 1 RU-143/144 0745 MST, 03/15/94 to 1230 MST, 03/19/94 101 Hours Although the monitors could not be considered operable during these periods, they were operating normally and were functional with the exception of annunciation capability for a detector failure. Based upon the satisfactory completion of the monthly source checks, there were no detector failures during the periods of high range monitor inoperability. |
| | A Quality Assurance audit in mid-1993 identified deficiencies in the control of plant process software including procurement of contract software and control of vendor problem reporting. Extensive corrective actions are being developed to resolve concerns associated with the design, installation, and configuration of process software. Such problems as errors in vendor-provided software are being addressed within the overall context of the corrective action plan. Resolution is being tracked by an open Quality |
| | |
| | l' Assurance corrective action document. |
| | To resolve the specific software problems identified in this report, Setpoint Change Request (SPCR) S13J-SQ-015 has been developed to correct the software errors in the affected monitors. The SPCR contains an extensive Design Validation Test that will test all of the software features, not just those that have been modified, to demonstrate that the software will perform as designed in all modes of operation. The corrected software will be installed and tested by July 29, 1994. Once the Design Validation Test has been used to verify SPCR S13J-SQ-01 5 and has been established as a thorough software test for the monitors, it will be used as the design retest whenever significant modifications are made to the source codes. In the interim, the affected monitors are operable. |
| | Administrative controls which prohibit using the high range monitors in the handover disable mode have been implemented.}} |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML17313A9921999-06-21021 June 1999
Special Rept:On 990525,RMS mini-computer Was Removed from Service to Implement Yr 2000 Mod & Was OOS Longer than 72 H Allowed.Caused by Planned Y2K Mods.Preplanned Alternate Sampling Program Was Initiated
ML17313A9911999-06-18018 June 1999
Special Rept:On 990510,loose-part Detection Sys Channel 2 Was Declared Inoperable.Caused by Malfunction of Mineral Cable Connector to Accelerometer.Licensee Will Implement Modifications Which Will Enhance loose-part Detection Sys
ML17313A5401998-08-13013 August 1998
Special Rept:On 980715,declared PASS Inoperable.Caused by Failure of Offgas Flush/Purge Control Handswitch HS0101. Handswitch Replaced & Post Maintenance Retesting Was Initiated
ML17313A1271997-11-26026 November 1997
Special Rept 2-SR-97-002:on 971103,loose-part Detection Sys Channel 2 Declared Inoperable.Caused by Malfunction of Coaxial Cable Connector to accelerometer.Loose-part Detection Sys Channel Will Be Reworked
ML17312A6871996-04-0505 April 1996
Rev 1 to Special Rept 2-SR-96-001,on 960404,alert Declared Due to Fire in Voltage Regulator for CR & Remote Shutdown Panel Essential Lighting,Clarifying Status of Power to UPS 2EQDNN02.Further Investigations Into Event Being Performed
ML17312A6611996-04-0404 April 1996
Special Rept 2-SR-96-001:on 960404,fault Occurred in Voltage Regulator for CR & Remote Shutdown Panel Essential Lighting, Resulting in Fire in 100 Ft Elevation of Cb B Battery Equipment Room & Requiring Declaration of Alert,Per EPIP-04
ML17312A5771996-03-0101 March 1996
Special Rept 1-SR-96-01 on:960225,unit 1 Turbine Tripped Followed by Reactor Power Cutback.Caused by Lightning Strike.Unit 1 Will Not Be Connected to Grid Until Repairs Can Be Made to C Neutral Bushing of Transformer
ML17311A8971995-05-25025 May 1995
Special Rept:On 950416,loose-part Detection Sys Channel 1 Declared Inoperable.Caused by Malfunction of Coaxial Cable Connector to Transducer.Channel Will Be Reworked & Returned to Svc During First Available Outage of Sufficient Duration
ML17310B3621994-06-0909 June 1994
Special Rept 1-SR-94-001:on 940511,plant Ventilation Sys High Range Effluent Monitors in Units 1 & 2 Inoperable for Periods Greater than 72 H.Caused by High Voltage Failure Alarm.Design Change Package Installed
ML17310B3071994-05-20020 May 1994
Special Rept 2-SR-94-002:on 940518,NOUE Declared Due to Fire Which Burned in Excess of 10 Minutes within Protected Area. Fire Extinguished W/Portable Fire Extinguisher.Investigation Initiated to Determine Cause of Fire & Develop C/As
ML17310A9951994-01-13013 January 1994
Suppl 2 to Special Rept 3-SR-92-006:on 921217,PASS Declared Inoperable for Greater than Seven Days Following Failure to Meet Pressurized Sample Portion of Acceptance Criteria for Monthly Functional Sr.Pass Declared Operable on 921226
ML17310A9941994-01-13013 January 1994
Suppl 2 to Special Rept 2-SR-92-004:on 921222,PASS Declared Inoperable for Greater than Seven Days Due to Failure of Containment Air Flow Indicator & Indication of Water Leakage at PASS RCS Sample Septum.Pass Declared Operable on 930105
ML17310A8951994-01-0303 January 1994
Special rept:1-SR-93-008:on 940103,fuel Bldg Ventilation Sys High Range Radiation Monitor Inoperable for Period Greater than 72 Hours.Caused by Difficulties in Installing Mod 1-FJ-SQ-060
ML17310A8701993-12-25025 December 1993
Special Rept 1-SR-93-006:on 931224,30 Day Period for Returning loose-part Detection Sys (Lpds) to Operable Status Exceeded.Inoperable Lpds Channel Scheduled to Be Reworked & Returned to Svc During Next Outage of Sufficient Duration
ML17310A8671993-12-15015 December 1993
Special Rept 1-SR-93-007:on 931215,30 Day Period for Returning Accelerometer to Operable Condition Exceeded. Accelerometer Will Be Replaced During Next Outage of Sufficient Duration
ML17310A7581993-10-30030 October 1993
Special Rept 1-SR-93-004:on 931008,high Range RM RU-146 Made Inoperable for Period of Greater than 72 H as Result of Scheduled Electrical Bus Outage.Maint on Associated Bus Completed on 931015 & RU-146 Returned to Service
ML17310A7001993-10-0909 October 1993
Special Rept 2-SR-93-003:on 931002,thirty Day Period for Returning loose-part Detection Sys Channel 8 to Operable Status Exceeded.Subj Channel Scheduled to Be Reworked & Returned to Svc During Next Outage
ML17310A6301993-09-13013 September 1993
Special Rept 3-SR-93-003:on 930806,loose-part Detection Sys (Lpds) Declared Inoperable & Exceeded 30 Day Period for Being Returned to Svc on 930905.LPDS Channel 5 Scheduled to Be Reworked & Returned to Svc During Next Outage
ML17310A5401993-08-11011 August 1993
Special Rept 1-SR-93-003:on 930806,NOUE Declared When Unit 1 CR Received Verification That Meteorological Instrumentation Unavailable Due to Loss of Power to Meteorological Tower. Caused by Severe Weather.Instrumentation Repaired
ML17310A4961993-08-0202 August 1993
Special Rept 2-SR-93-002:on 930722,Unit 2 in Mode 5,Cold Shutdown During Refueling Outage When ISI of Both SGs Completed.Insp Resulted in Plugging of 74 Tubes in SG 1 & 175 Tubes in SG 2
ML17310A4401993-07-12012 July 1993
Special Rept 1-SR-93-002:on 930526,period for Returning Min Number of Explosive Gas Monitoring Channels to Operable Condition Exceeded.After All Four Cells Rebuilt,Calibr Completed on 930602 & Subj Analyzer Returned to Svc
ML17306B4231993-04-24024 April 1993
Suppl 1 to Special Repts 2-SR-92-004 & 3-SR-92-006:on 921222 Unit 2 PASS Declared Inoperable Due to Failure of Containment Air Flow Indicator.On 921217,Unit 3 PASS Declared Inoperable.Equipment Replaced & Sample Obtained
ML17306B3371993-03-15015 March 1993
Special Rept 2-SR-93-001:on 930314,control Room Personnel Manually Tripped Reactor Due to Rapid Decrease in Pressurizer Heaters.Personnel Commenced Controlled Plant Cooldown.Unit Remains Shut Down for Further Investigation
ML17306B2901993-02-22022 February 1993
Special Rept 1-SR-92-005,suppl 1,provided Per Emergency Plan Implementing Procedure EPIP-03, Notification of Unusual Event Implementing Actions, Occurring on 920822 Re Loss of Power at Meteorological Tower
ML17306B2781993-02-0909 February 1993
Special Rept 3-SR-93-001:on 930204,reactor Trip Occurred & Main Feedwater Pump a Experienced Rapidly Decreasing Pump Speed.Valid Actuation of SI Actuation Sys & Containment Isolation Actuation Sys Also Occurred.Evaluation Underway
ML17306B2721993-01-27027 January 1993
Special Rept 3-SR-004-03:on 920817,PASS Inoperable for More than 7 Days.On 920902,discovered That PASS Unable to Draw Vacuum on Gaseous Sample Bomb.Vent Line Reworked & Procedure Revised
ML17306B2551993-01-24024 January 1993
Special Rept 2-SR-92-004:on 921222,PASS Declared Inoperable for Period Greater than 7 Days Due to Failure of Containment Air Flow Indicator & Indication of Water Leakage at PASS Rcs.Pass Returned to Operable Status on 930105
ML17306B2561993-01-24024 January 1993
Special Rept 1-SR-92-007:on 921227,CB Atmosphere RM Inoperable for Period Greater than 72 H Due to High Flow Conditions.Temporary Mod Installed on Subj RM to Remove Monitor from Dedicated Rms Grounding Sys
ML17306B2541993-01-22022 January 1993
Special Rept 3-SR-92-006:on 921217,PASS Declared Inoperable Following Failure to Meet Pressurized Sample Portion of Acceptance Criteria for Monthly Functional Sr.Pass Returned to Operable Status Following Satisfactory Repairs & Testing
ML17306B1911992-12-21021 December 1992
Special Rept 3-SR-92-004-01:on 920201 PASS Declared Inoperable for Period Greater than Seven Days.Caused by Tubing Being Rerouted.Pass Reworked & Operability Restored on 920905
ML17306B1841992-12-14014 December 1992
Special Rept:On 920810,PASS Declared Inoperable Due to Tubing Being Rerouted.Chemistry Sys Status Procedure 74DP-9ZZ04 Revised to Direct Chemistry Personnel to Ensure That Functional Test Is performed.W/921214 Ltr
ML17306B1291992-11-17017 November 1992
Special Rept 2-SR-92-003:on 921113,reactor Trip Occurred While Motor Generator Set a Out of Svc for Scheduled Maint & Set B Inadvertently Deenergized,Resulting in Loss of Power. State & Local Agencies Notified & Sys Reset
ML17306B0931992-10-30030 October 1992
Suppl 1 to Special Rept 3-SR-92-004:on 920817,seven-day Period for Returning PASS to Service exceeded.30DP-9WP04 Revised to Retest for PASS & Gaseous Radwaste to Be Completed by 921120
ML17306A9951992-09-18018 September 1992
Special Rept 3-SR-92-004:seven-day Period for Returning PASS to Svc Exceeded on 920817.On 920902,discovered That PASS Unable to Draw Vacuum on Gaseous Sample Bomb.Possibly Caused by Maint on 920810.PASS Reworked & Operability Restored
ML17306A9651992-09-16016 September 1992
Special Rept 3-SR-92-003:on 920903,discovered That PASS Unable to Draw Vacuum on Gaseous Sample Bomb & Declared Inoperable for More than 7 Days.Cause Under Investigation. Sys Returned to Operable Status on 920905
ML17306A9401992-08-28028 August 1992
Special Rept 1-SR-92-005:on 920822,discovered That Info Could Not Be Dispatched from Meterological Tower During Routine Surveillance of Daily Midnight Logs.Tower Declared Operable on 920823 Following Power Restoration
ML17306A8101992-06-27027 June 1992
Special Rept 1-SR-92-004:on 920620,loose Part Detection Sys Inoperable for More than 30 Days.Caused by Hardware Problems Associated W/Installation of Loose Part Detection Sys Mods.New Computer Processor Board Installed
ML17306A7971992-06-18018 June 1992
Special Rept 3-SR-92-003:on 920520,RMs RU-145 & 146 Declared Inoperable & Removed from Svc.Caused by Personnel Errors in Documenting Clearance for Retest of RU-146.Shift Supervisor Disciplined & Technician Verified That Pumps Were Energized
ML17306A7961992-06-18018 June 1992
Special Rept 1-SR-92-003:on 920514,unit 1 Entered Mode 3 & PASS Declare Inoperable & Failed Surveillance Test.Caused by Leaking Relief Valve & Malfunctioning Pressure Transducer. Relief Valve & Pressure Transducer Replaced
ML17306A7101992-05-0606 May 1992
Special Rept:On 920504,Control Room Received Alarms on All Seven Control Boards.Plan Computer Returned to Svc & Was Declared operable.W/920506 Ltr
ML17306A6811992-04-18018 April 1992
Special Rept SR-92-002:on 920411,insp of SGs Resulted in Plugging of 23 Tubes in SG 1 & 18 Tubes in SG 2.Complete Results of SG Tube ISI Will Be Submitted by 930411
ML17306A4521992-02-0707 February 1992
Special Rept:On 920101,PASS Declared Inoperable When Chemistry Personnel Could Not Obtain a Containment Air Sample.Caused by Malfunctioning Flow Sensor.Pass Expected to Be Returned to an Operable status.W/920207 Ltr
ML17306A3901992-01-0707 January 1992
Special Rept 1-SR-92-001:on 920102,determined That Leak Existed in Pressurizer Steam Space Instrument Nozzle Mfg from Inconnel 600.Caused by Nonvisible Intergranular Crack.Addl Investigation Underway
ML17306A2981991-12-0505 December 1991
Special Rept 2-SR-91-002:on 911107,fuel Bldg Ventilation Sys high-range Radioactive Gaseous Effluent Monitor Inoperable for More than 72 H.Caused by Power Supply Deenergized for Scheduled Maint.Monitor Returned to Svc on 911114
ML17306A2791991-11-20020 November 1991
Special Rept 3-SR-91-007:on 911115,mobile Crane Came in Contact W/Energized 13.8 Kv Power Line Resulting in Arcing of Crane Outrigger Pads to Ground & Burning of Asphalt Area in Contact W/Pads.Investigation Re Event Being Performed
ML17306A2221991-10-10010 October 1991
Special Rept 1-SR-91-001-01:on 910111,fuel Bldg Ventilation Sys High Range Radioactive Gaseous Effluent Monitor Declared Inoperable for Period Greater than 72 H in Order to Perform Scheduled 18-month Surveillance Testing & Maint
ML17306A2211991-10-10010 October 1991
Special Rept 2-SR-89-007-03:on 891002,fuel Bldg Ventilation Sys High Range Gaseous Effluent Monitor Declared Inoperable for More than 72 H.Caused by Low Flow Limit Switch Being Out of Adjustment.Microprocessor Operated Manual Mode
ML17306A2201991-10-10010 October 1991
Special Rept 2-SR-90-005-01:on 900716,plant Vent Sys High Range Effluent Monitor Inoperable for More than 72 H.Caused by Requirement to Perform Scheduled 18-month Surveillance Testing.Monitor Returned to Svc on 900729
ML17306A2181991-10-10010 October 1991
Special Rept 2-SR-90-004-01:on 910613,fuel Bldg Ventilation Sys high-range Radioactive Gaseous Effluent Monitor Inoperable for More than 72 H.Caused by Need to Perform 18 Month Surveillance Testing.Monitor Returned to Svc
ML17305B7441991-09-18018 September 1991
Special Rept 1-SR-91-002,on 910914:steam Generator Econimizer Valve SGN-FV-1112 Fully Opened Causing Level in Steam Generator 1 to Rapidly Increase.Caused by Malfunction of Lower Gripper High Voltage on Slipped Part Length CEA
1999-06-21
[Table view]
Category:LER)
MONTHYEARML17313A9921999-06-21021 June 1999
Special Rept:On 990525,RMS mini-computer Was Removed from Service to Implement Yr 2000 Mod & Was OOS Longer than 72 H Allowed.Caused by Planned Y2K Mods.Preplanned Alternate Sampling Program Was Initiated
ML17313A9911999-06-18018 June 1999
Special Rept:On 990510,loose-part Detection Sys Channel 2 Was Declared Inoperable.Caused by Malfunction of Mineral Cable Connector to Accelerometer.Licensee Will Implement Modifications Which Will Enhance loose-part Detection Sys
ML17313A5401998-08-13013 August 1998
Special Rept:On 980715,declared PASS Inoperable.Caused by Failure of Offgas Flush/Purge Control Handswitch HS0101. Handswitch Replaced & Post Maintenance Retesting Was Initiated
ML17313A1271997-11-26026 November 1997
Special Rept 2-SR-97-002:on 971103,loose-part Detection Sys Channel 2 Declared Inoperable.Caused by Malfunction of Coaxial Cable Connector to accelerometer.Loose-part Detection Sys Channel Will Be Reworked
ML17312A6871996-04-0505 April 1996
Rev 1 to Special Rept 2-SR-96-001,on 960404,alert Declared Due to Fire in Voltage Regulator for CR & Remote Shutdown Panel Essential Lighting,Clarifying Status of Power to UPS 2EQDNN02.Further Investigations Into Event Being Performed
ML17312A6611996-04-0404 April 1996
Special Rept 2-SR-96-001:on 960404,fault Occurred in Voltage Regulator for CR & Remote Shutdown Panel Essential Lighting, Resulting in Fire in 100 Ft Elevation of Cb B Battery Equipment Room & Requiring Declaration of Alert,Per EPIP-04
ML17312A5771996-03-0101 March 1996
Special Rept 1-SR-96-01 on:960225,unit 1 Turbine Tripped Followed by Reactor Power Cutback.Caused by Lightning Strike.Unit 1 Will Not Be Connected to Grid Until Repairs Can Be Made to C Neutral Bushing of Transformer
ML17311A8971995-05-25025 May 1995
Special Rept:On 950416,loose-part Detection Sys Channel 1 Declared Inoperable.Caused by Malfunction of Coaxial Cable Connector to Transducer.Channel Will Be Reworked & Returned to Svc During First Available Outage of Sufficient Duration
ML17310B3621994-06-0909 June 1994
Special Rept 1-SR-94-001:on 940511,plant Ventilation Sys High Range Effluent Monitors in Units 1 & 2 Inoperable for Periods Greater than 72 H.Caused by High Voltage Failure Alarm.Design Change Package Installed
ML17310B3071994-05-20020 May 1994
Special Rept 2-SR-94-002:on 940518,NOUE Declared Due to Fire Which Burned in Excess of 10 Minutes within Protected Area. Fire Extinguished W/Portable Fire Extinguisher.Investigation Initiated to Determine Cause of Fire & Develop C/As
ML17310A9951994-01-13013 January 1994
Suppl 2 to Special Rept 3-SR-92-006:on 921217,PASS Declared Inoperable for Greater than Seven Days Following Failure to Meet Pressurized Sample Portion of Acceptance Criteria for Monthly Functional Sr.Pass Declared Operable on 921226
ML17310A9941994-01-13013 January 1994
Suppl 2 to Special Rept 2-SR-92-004:on 921222,PASS Declared Inoperable for Greater than Seven Days Due to Failure of Containment Air Flow Indicator & Indication of Water Leakage at PASS RCS Sample Septum.Pass Declared Operable on 930105
ML17310A8951994-01-0303 January 1994
Special rept:1-SR-93-008:on 940103,fuel Bldg Ventilation Sys High Range Radiation Monitor Inoperable for Period Greater than 72 Hours.Caused by Difficulties in Installing Mod 1-FJ-SQ-060
ML17310A8701993-12-25025 December 1993
Special Rept 1-SR-93-006:on 931224,30 Day Period for Returning loose-part Detection Sys (Lpds) to Operable Status Exceeded.Inoperable Lpds Channel Scheduled to Be Reworked & Returned to Svc During Next Outage of Sufficient Duration
ML17310A8671993-12-15015 December 1993
Special Rept 1-SR-93-007:on 931215,30 Day Period for Returning Accelerometer to Operable Condition Exceeded. Accelerometer Will Be Replaced During Next Outage of Sufficient Duration
ML17310A7581993-10-30030 October 1993
Special Rept 1-SR-93-004:on 931008,high Range RM RU-146 Made Inoperable for Period of Greater than 72 H as Result of Scheduled Electrical Bus Outage.Maint on Associated Bus Completed on 931015 & RU-146 Returned to Service
ML17310A7001993-10-0909 October 1993
Special Rept 2-SR-93-003:on 931002,thirty Day Period for Returning loose-part Detection Sys Channel 8 to Operable Status Exceeded.Subj Channel Scheduled to Be Reworked & Returned to Svc During Next Outage
ML17310A6301993-09-13013 September 1993
Special Rept 3-SR-93-003:on 930806,loose-part Detection Sys (Lpds) Declared Inoperable & Exceeded 30 Day Period for Being Returned to Svc on 930905.LPDS Channel 5 Scheduled to Be Reworked & Returned to Svc During Next Outage
ML17310A5401993-08-11011 August 1993
Special Rept 1-SR-93-003:on 930806,NOUE Declared When Unit 1 CR Received Verification That Meteorological Instrumentation Unavailable Due to Loss of Power to Meteorological Tower. Caused by Severe Weather.Instrumentation Repaired
ML17310A4961993-08-0202 August 1993
Special Rept 2-SR-93-002:on 930722,Unit 2 in Mode 5,Cold Shutdown During Refueling Outage When ISI of Both SGs Completed.Insp Resulted in Plugging of 74 Tubes in SG 1 & 175 Tubes in SG 2
ML17310A4401993-07-12012 July 1993
Special Rept 1-SR-93-002:on 930526,period for Returning Min Number of Explosive Gas Monitoring Channels to Operable Condition Exceeded.After All Four Cells Rebuilt,Calibr Completed on 930602 & Subj Analyzer Returned to Svc
ML17306B4231993-04-24024 April 1993
Suppl 1 to Special Repts 2-SR-92-004 & 3-SR-92-006:on 921222 Unit 2 PASS Declared Inoperable Due to Failure of Containment Air Flow Indicator.On 921217,Unit 3 PASS Declared Inoperable.Equipment Replaced & Sample Obtained
ML17306B3371993-03-15015 March 1993
Special Rept 2-SR-93-001:on 930314,control Room Personnel Manually Tripped Reactor Due to Rapid Decrease in Pressurizer Heaters.Personnel Commenced Controlled Plant Cooldown.Unit Remains Shut Down for Further Investigation
ML17306B2901993-02-22022 February 1993
Special Rept 1-SR-92-005,suppl 1,provided Per Emergency Plan Implementing Procedure EPIP-03, Notification of Unusual Event Implementing Actions, Occurring on 920822 Re Loss of Power at Meteorological Tower
ML17306B2781993-02-0909 February 1993
Special Rept 3-SR-93-001:on 930204,reactor Trip Occurred & Main Feedwater Pump a Experienced Rapidly Decreasing Pump Speed.Valid Actuation of SI Actuation Sys & Containment Isolation Actuation Sys Also Occurred.Evaluation Underway
ML17306B2721993-01-27027 January 1993
Special Rept 3-SR-004-03:on 920817,PASS Inoperable for More than 7 Days.On 920902,discovered That PASS Unable to Draw Vacuum on Gaseous Sample Bomb.Vent Line Reworked & Procedure Revised
ML17306B2551993-01-24024 January 1993
Special Rept 2-SR-92-004:on 921222,PASS Declared Inoperable for Period Greater than 7 Days Due to Failure of Containment Air Flow Indicator & Indication of Water Leakage at PASS Rcs.Pass Returned to Operable Status on 930105
ML17306B2561993-01-24024 January 1993
Special Rept 1-SR-92-007:on 921227,CB Atmosphere RM Inoperable for Period Greater than 72 H Due to High Flow Conditions.Temporary Mod Installed on Subj RM to Remove Monitor from Dedicated Rms Grounding Sys
ML17306B2541993-01-22022 January 1993
Special Rept 3-SR-92-006:on 921217,PASS Declared Inoperable Following Failure to Meet Pressurized Sample Portion of Acceptance Criteria for Monthly Functional Sr.Pass Returned to Operable Status Following Satisfactory Repairs & Testing
ML17306B1911992-12-21021 December 1992
Special Rept 3-SR-92-004-01:on 920201 PASS Declared Inoperable for Period Greater than Seven Days.Caused by Tubing Being Rerouted.Pass Reworked & Operability Restored on 920905
ML17306B1841992-12-14014 December 1992
Special Rept:On 920810,PASS Declared Inoperable Due to Tubing Being Rerouted.Chemistry Sys Status Procedure 74DP-9ZZ04 Revised to Direct Chemistry Personnel to Ensure That Functional Test Is performed.W/921214 Ltr
ML17306B1291992-11-17017 November 1992
Special Rept 2-SR-92-003:on 921113,reactor Trip Occurred While Motor Generator Set a Out of Svc for Scheduled Maint & Set B Inadvertently Deenergized,Resulting in Loss of Power. State & Local Agencies Notified & Sys Reset
ML17306B0931992-10-30030 October 1992
Suppl 1 to Special Rept 3-SR-92-004:on 920817,seven-day Period for Returning PASS to Service exceeded.30DP-9WP04 Revised to Retest for PASS & Gaseous Radwaste to Be Completed by 921120
ML17306A9951992-09-18018 September 1992
Special Rept 3-SR-92-004:seven-day Period for Returning PASS to Svc Exceeded on 920817.On 920902,discovered That PASS Unable to Draw Vacuum on Gaseous Sample Bomb.Possibly Caused by Maint on 920810.PASS Reworked & Operability Restored
ML17306A9651992-09-16016 September 1992
Special Rept 3-SR-92-003:on 920903,discovered That PASS Unable to Draw Vacuum on Gaseous Sample Bomb & Declared Inoperable for More than 7 Days.Cause Under Investigation. Sys Returned to Operable Status on 920905
ML17306A9401992-08-28028 August 1992
Special Rept 1-SR-92-005:on 920822,discovered That Info Could Not Be Dispatched from Meterological Tower During Routine Surveillance of Daily Midnight Logs.Tower Declared Operable on 920823 Following Power Restoration
ML17306A8101992-06-27027 June 1992
Special Rept 1-SR-92-004:on 920620,loose Part Detection Sys Inoperable for More than 30 Days.Caused by Hardware Problems Associated W/Installation of Loose Part Detection Sys Mods.New Computer Processor Board Installed
ML17306A7971992-06-18018 June 1992
Special Rept 3-SR-92-003:on 920520,RMs RU-145 & 146 Declared Inoperable & Removed from Svc.Caused by Personnel Errors in Documenting Clearance for Retest of RU-146.Shift Supervisor Disciplined & Technician Verified That Pumps Were Energized
ML17306A7961992-06-18018 June 1992
Special Rept 1-SR-92-003:on 920514,unit 1 Entered Mode 3 & PASS Declare Inoperable & Failed Surveillance Test.Caused by Leaking Relief Valve & Malfunctioning Pressure Transducer. Relief Valve & Pressure Transducer Replaced
ML17306A7101992-05-0606 May 1992
Special Rept:On 920504,Control Room Received Alarms on All Seven Control Boards.Plan Computer Returned to Svc & Was Declared operable.W/920506 Ltr
ML17306A6811992-04-18018 April 1992
Special Rept SR-92-002:on 920411,insp of SGs Resulted in Plugging of 23 Tubes in SG 1 & 18 Tubes in SG 2.Complete Results of SG Tube ISI Will Be Submitted by 930411
ML17306A4521992-02-0707 February 1992
Special Rept:On 920101,PASS Declared Inoperable When Chemistry Personnel Could Not Obtain a Containment Air Sample.Caused by Malfunctioning Flow Sensor.Pass Expected to Be Returned to an Operable status.W/920207 Ltr
ML17306A3901992-01-0707 January 1992
Special Rept 1-SR-92-001:on 920102,determined That Leak Existed in Pressurizer Steam Space Instrument Nozzle Mfg from Inconnel 600.Caused by Nonvisible Intergranular Crack.Addl Investigation Underway
ML17306A2981991-12-0505 December 1991
Special Rept 2-SR-91-002:on 911107,fuel Bldg Ventilation Sys high-range Radioactive Gaseous Effluent Monitor Inoperable for More than 72 H.Caused by Power Supply Deenergized for Scheduled Maint.Monitor Returned to Svc on 911114
ML17306A2791991-11-20020 November 1991
Special Rept 3-SR-91-007:on 911115,mobile Crane Came in Contact W/Energized 13.8 Kv Power Line Resulting in Arcing of Crane Outrigger Pads to Ground & Burning of Asphalt Area in Contact W/Pads.Investigation Re Event Being Performed
ML17306A2221991-10-10010 October 1991
Special Rept 1-SR-91-001-01:on 910111,fuel Bldg Ventilation Sys High Range Radioactive Gaseous Effluent Monitor Declared Inoperable for Period Greater than 72 H in Order to Perform Scheduled 18-month Surveillance Testing & Maint
ML17306A2211991-10-10010 October 1991
Special Rept 2-SR-89-007-03:on 891002,fuel Bldg Ventilation Sys High Range Gaseous Effluent Monitor Declared Inoperable for More than 72 H.Caused by Low Flow Limit Switch Being Out of Adjustment.Microprocessor Operated Manual Mode
ML17306A2201991-10-10010 October 1991
Special Rept 2-SR-90-005-01:on 900716,plant Vent Sys High Range Effluent Monitor Inoperable for More than 72 H.Caused by Requirement to Perform Scheduled 18-month Surveillance Testing.Monitor Returned to Svc on 900729
ML17306A2181991-10-10010 October 1991
Special Rept 2-SR-90-004-01:on 910613,fuel Bldg Ventilation Sys high-range Radioactive Gaseous Effluent Monitor Inoperable for More than 72 H.Caused by Need to Perform 18 Month Surveillance Testing.Monitor Returned to Svc
ML17305B7441991-09-18018 September 1991
Special Rept 1-SR-91-002,on 910914:steam Generator Econimizer Valve SGN-FV-1112 Fully Opened Causing Level in Steam Generator 1 to Rapidly Increase.Caused by Malfunction of Lower Gripper High Voltage on Slipped Part Length CEA
1999-06-21
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17300B3811999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Pvngs,Units 1,2 & 3.With 991007 Ltr
ML17300B3271999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Pvngs,Units 1,2 & 3
ML17313B0751999-08-27027 August 1999
LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr
ML17313B0611999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Pvngs,Units 1,2 & 3.With 990810 Ltr
ML17313B0191999-07-16016 July 1999
LER 99-005-00:on 990618,RT on Low DNBR Was Noted.Caused by Hardware Induced Calculation Error.Cr Operator Was Taken to Place Reactor in Stable Condition IAW Appropriate Operating Procedure
ML17300B3151999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Pvngs,Units 1,2 & 3.With 990714 Ltr
ML17313A9921999-06-21021 June 1999
Special Rept:On 990525,RMS mini-computer Was Removed from Service to Implement Yr 2000 Mod & Was OOS Longer than 72 H Allowed.Caused by Planned Y2K Mods.Preplanned Alternate Sampling Program Was Initiated
ML17313A9911999-06-18018 June 1999
Special Rept:On 990510,loose-part Detection Sys Channel 2 Was Declared Inoperable.Caused by Malfunction of Mineral Cable Connector to Accelerometer.Licensee Will Implement Modifications Which Will Enhance loose-part Detection Sys
ML17313A9731999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Pvngs,Units 1,2 & 3.With 990608 Ltr
ML17313A9281999-05-0707 May 1999
LER 99-004-00:on 990408,PSV Lift Pressures Were Outside of TS Limits.Caused by Lift Pressure Setpoint Drift.Psvs Have Been Tested,Disassembled,Inspected,Reassembled & Certified at Wyle Labs
ML17313A9201999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Pvngs,Units 1,2 & 3.With 990512 Ltr
ML17313A8951999-04-14014 April 1999
LER 99-003-00:on 990317,required Surveillance Requirement Not Completed Due to Deficient Procedure,Was Determined. Caused by Cognitive Personnel Error.St Procedures Revised to Require Chiller to Be Operating & Oil Temperature Checked
ML17313A8921999-04-13013 April 1999
LER 98-003-01:on 980902,discovered That MSSV as-found Lift Pressures Were Outside TS Limits.Caused by Bonding of Valve Disc to Nozzle Seat.Affected Valves Were Adjusted,Retested & Returned to Svc
ML17313A8891999-04-0909 April 1999
LER 99-001-00:on 990310,RT on High Pressurizer Pressure Was Noted.Caused by Loss of Heat Removal.Cr Supervisor Was Removed from Shift Duties for Diagnostics Skills Training. with 990409 Ltr
ML17300B3071999-03-31031 March 1999
Seismic Portion of Submittal-Only Screening Review of Palo Verde Nuclear Generating Station Units Ipeee.
ML17313A8801999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Pvngs,Units 1,2 & 3.With 990412 Ltr
ML20207M9231999-03-12012 March 1999
Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results
ML20207H7471999-03-10010 March 1999
1999 Emergency Preparedness Exercise 99-E-AEV-03003
ML17313A8361999-03-0101 March 1999
LER 99-001-00:on 990103,TS Violation for Power Dependent Insertion Limit Alarm Being Inoperable.Caused by Personnel Error.Revised Procedure to Clarify How Computer Point Is to Be Returned to Scan Mode.With 990302 Ltr
ML17313A8501999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Palo Verde Nuclear Generating Station.With 990311 Ltr
ML17313A7791999-02-0505 February 1999
Safety Evaluation Accepting Licensee Rev to Emergency Plan That Would Result in Two Less Radiation Protection Positions Immediatelu Available During Emergencies
ML17313A8061999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for Pvngs,Units 1,2 & 3.With 990218 Ltr
ML17313A7701999-01-15015 January 1999
LER 96-008-00:on 960507,inadequate Procedure Results in Nuclear Power Channels Not Calibrated During Power Ascension Tests Occurred.Caused by Deficient Procedure.Procedure Revised
ML17313A7381998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.With 990113 Ltr
ML20206H2101998-12-31031 December 1998
SCE 1998 Annual Rept
ML17313A7031998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Pvngs,Unit 1,2 & 3. with 981209 Ltr
ML17313A6701998-11-0404 November 1998
Rev 2 to PVNGS Unit 2 Colr.
ML17313A6741998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Pvngs,Units 1,2 & 3.With 981109 Ltr
ML17313A6611998-10-24024 October 1998
LER 98-008-00:on 980729,EQ of Electrical Connectors Were Not Adequately Demonstrated.Caused Because Test Was Conducted with Only Single Lv Connector & Without Fully Ranged Inputs. Revised EQ Requirements
ML17313A6561998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for PVNGS Units 1,2 & 3.With 981007 Ltr
ML17313A5961998-09-14014 September 1998
LER 98-002-00:on 980814,B Train H Recombiner Was Noted Inoperable Due to cross-wired Power Receptacle.Cause of Event Is Under investigation.Cross-wired Power Supply Receptacle for B Train H Recombiner Was re-wired
ML17313A5761998-09-0808 September 1998
LER 98-003-01:on 980113,discovered That One Channel of RWT Level Sys Had Failed High.Caused by Water Intrusion Into Electrical Termination Pull Box.Weep Holes Were Drilled Into Bottoms of Pull Boxes Nearest Level Transmitters
ML17313A5591998-08-28028 August 1998
LER 98-001-00:on 980730,entered TS 3.0.3 Due to Safety Injection Flow Instruments Being Removed from Svc.Caused by Personnel Error.Transmitters Were Unisolated & Returned to svc.W/980828 Ltr
ML20151S0941998-08-21021 August 1998
Rev 6 to COLR for PVNGS Unit 3
ML20151S0861998-08-21021 August 1998
Rev 4 to COLR for PVNGS Unit 1
ML20151S0901998-08-21021 August 1998
Rev 1 to COLR for PVNGS Unit 2
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
ML17313A5401998-08-13013 August 1998
Special Rept:On 980715,declared PASS Inoperable.Caused by Failure of Offgas Flush/Purge Control Handswitch HS0101. Handswitch Replaced & Post Maintenance Retesting Was Initiated
ML17313A5301998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Pvgns,Units 1,2 & 3.W/980812 Ltr
ML17313A5201998-07-30030 July 1998
LER 98-004-00:on 980630,personnel Discovered That Pressure Safety Valve Had Not Received Periodic Set Pressure Test for ASME Class 1 Pressure Safety Valve.Caused by Personnel Error.Pressure Safety Valve reviewed.W/980730 Ltr
ML17313A5791998-07-0707 July 1998
to PVNGS SG Tube ISI Results for Seventh Refueling Outage Mar & Apr 1998.
ML17313A5001998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.W/980710 Ltr
ML17313A4671998-06-19019 June 1998
LER 98-007-00:on 980520,CR Personnel Observed Flow & Pressure Perturbations on Chemical & Vol Control Sys Letdown Sys.Caused by Cyclic Fatigue Due to Dynamic Pressure Transients.Unit Letdown Piping Replaced
ML17313A4521998-06-19019 June 1998
Rev 5 to COLR for Pvngs,Unit 3.
ML17313A4501998-06-19019 June 1998
Rev 4 to COLR for Pvngs,Unit 3.
ML17313A4131998-06-0505 June 1998
LER 98-006-00:on 980507,determined That Plant Was Outside Design Basis Due to SI Discharge Check Valve Reverse Flow. Check Valve Was Disassembled,Examined & Reassembled, Whereupon Valve Met Acceptance Criteria
ML17313A4211998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Pvngs,Units 1,2 & 3.W/980609 Ltr
ML17313A3951998-05-26026 May 1998
LER 98-005-00:on 980428,noted That Required Response Time Testing Had Not Been Performed.Caused by Personnel Error. Coached I&C Personnel Responsible for Reviewing Work Authorization Documentation
ML17313A3691998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for PVNGS.W/980412 Ltr
ML17313A3251998-04-0101 April 1998
LER 98-004-00:on 980304,safety Valves as-found Pressures Out of Tolerance.Cause of Event Is Under Investigation.Three Mssv'S & Psv Will Be Replaced W/Refurbished & Recertified Valves During Refueling Outage U1R7
1999-09-30
[Table view] |
Text
ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9406210193 DOC.DATE: 94/06/09 NOTARIZED: NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 AUTH. NAME AUTHOR AFFILIATION LEVINE,J.M. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Special Rept 1-SR-94-001:on 940511,plant ventilation sys hxgh range effluent monitors in Units 1 & 2 inoperable for periods greater than 72 h.Caused by high voltage failure alarm. Design change package installed.
DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:STANDARDIZED PLANT 05000528 Standardized plant. 05000529 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDIV-3 PD 1 1 HOLIAN, B 1 1 TRAN,L 1 1 INTERNAL: ACRS 1 1 AEOD/DS P/TPAB 1 '. 1 AEOD/ROAB/DS P 2 2 NRR/DE/EELB 1 NRR/DE/EMEB 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRSS/PRPB 2 2 NRR/DSSA/SPLB 1 1 NR - SSA SRXB 1 1 NRR/PMAS/IRCB-E 1 1 EG F LE 02 1 1 RES/DSIR/EIB 1 1 N ILE 01 1 1 EXTERNAL: EG&G BRYCE,J.H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS:
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Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O. BOX 52034 ~ PHOENIX, ARIZONA85072-2034 JAMES M. LEVINE 102-03002-JML/BAG/P JC VICE PRESIOB4T NUCLEAR PRODUCTION June 9, 1994 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, D. C. 20555
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1 and 2 Docket No. STN 50-528 (License No. NPF-41)
Docket No. STN 50-529 (License No. NPF-51)
Special Report 1-SR-94-001 File: 94-020-404 Enclosed please find Special Report 1-SR-94-001 prepared and submitted pursuant to the requirements of the PVNGS Qffsite Dose Calculation Manual and Technical Specification 6.9.2. This report discusses the Plant Ventilation System High Range Effluent Monitors (RU-144) in Units 1 and 2 being inoperable for a period greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If you have any questions, please contact Burton A. Grabo, Supervisor, Nuclear Regulatory Affairs, at (602) 393-6492.
Sincerely, JML/BAG/PJC Enclosure cc: L. J. Caltan (all w/enclosure)
K. E. Perkins K. E. Johnston A
9406210193 94060'TI t PDR ADat:K OS00OS2a S PDR
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PALO VERDE NUCLEAR GENERATING STATlON UNITS 1 AND 2 PLANT VENTILATlONSYSTEM HlGH RANGE EFFLUENT MONITOR RU-144 INOPERABLE Docket No. STN 50-528 (License No. NPF-41)
Docket No. STN 50-529 (License No. NPF-51)
Special Report 1-SR-94-001 Initial Conditions On May 11, 1994, Units 1 and 2 were in Mode 1 (POWER OPERATION) operating at approximately 86 percent power.
Descri tion of Event This special report is being submitted pursuant to the requirements of the PVNGS Offsite Dose Calculation Manual (ODCM) and Technical Specification 6.9.2 to report an event (three occurrences) in which the Plant Ventilation System High Range Effluent Monitors in Units 1 and 2 were inoperable for periods greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The 72-hour periods for returning the monitors to service were exceeded in Unit 1 at approximately 0952 MST on May 23, 1993, and at approximately 0745 MST on March 18, 1994. In Unit 2, the 72-hour period for returning the monitor to service was exceeded at approximately 0945 MST on April 23, 1993.
Back round Radiation monitors RU-143 (Plant Ventilation System Low Range Effluent Monitor) and RU-144 work as a pair. RU-143 is normally in service and continuously monitors plant ventilation exhaust. RU-144 is automatically started when RU-143 reaches a predetermined setpoint. RU-144 is provided for tracking radioactive effluents during postulated accident scenarios. Prior to 1993, the low range monitor was required to be operable for the high range monitor to be considered operable. Therefore, if the low range monitor was inoperable, the high range monitor was also inoperable, and ODCM, Table 2.1, Action 42, which requires initiation of the Preplanned Alternate Sampling Program, was applicable.
During the first quarter of 1993, Design Change Package (DCP) 13PJ-SQ-066 was installed for the Plant Ventilation System effluent monitoring pairs in Units 1 and 2. The DCP allowed the high range monitor to be operable when the low range monitor was out-of-service by placing the high range monitor in a mode designated as Handover Disable.
lf only the low range monitor was out-of-service, the high range monitor could be placed in the handover disable mode, remain operable, and ODCM, Table 2.1, Action 42 would not apply.
Cause of Event On May 11, 1994, plant personnel performing troubleshooting under an approved work document identified that a high voltage failure alarm and a detector failure alarm would not annunciate when the high range monitor was in handover disable mode. Errors that prevented the alarms from annunciating in the handover disable mode were found in the vendor-revised software code. The software errors were associated with the changes made by the DCP in the section of code which controls monitor and channel handover.
For the monitor to be considered operable in accordance with the ODCM, control room alarm annunciation must be demonstrated to occur if the instrument indicates a downscale failure (detector failure). Therefore, the high range monitor was not operable, even in the handover disable mode, when the low range monitor was inoperable.
Undetected errors in the vendor-revised software code associated with the DCP were the cause of the condition. The PVNGS software test plan in the DCP required testing only for those conditions and functions that were known to have changed. The detector failure and high voltage failure alarms were not expected to have changed.
Corrective Action The APS investigation determined that the Plant Ventilation high range monitor in Unit 3 and the Fuel Building Ventilation high range monitors (RU-1 46) in all three units were also affected by the software errors; however, the only periods of inoperability that exceeded the 72-hour limit for returning the monitors to service are discussed below.
A review of low range monitor inoperability from the time the DCP was installed until the present was performed to determine if there were periods of inoperability in excess of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Three occurrences of a low range monitor being'inoperable for periods greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> while the high range monitor was believed to be operable in the handover disable mode were identified. These periods of inoperability were:
Unit 2 RU-143/144 0945 MST, 04/20/93 to 1520 MST, 05/05/93 366 Hours Unit 1 RU-143/144 0952 MST, 05/20/93 to 1243 MST, 05/25/93 123 Hours Unit 1 RU-143/144 0745 MST, 03/15/94 to 1230 MST, 03/19/94 101 Hours Although the monitors could not be considered operable during these periods, they were operating normally and were functional with the exception of annunciation capability for a detector failure. Based upon the satisfactory completion of the monthly source checks, there were no detector failures during the periods of high range monitor inoperability.
A Quality Assurance audit in mid-1993 identified deficiencies in the control of plant process software including procurement of contract software and control of vendor problem reporting. Extensive corrective actions are being developed to resolve concerns associated with the design, installation, and configuration of process software. Such problems as errors in vendor-provided software are being addressed within the overall context of the corrective action plan. Resolution is being tracked by an open Quality
l' Assurance corrective action document.
To resolve the specific software problems identified in this report, Setpoint Change Request (SPCR) S13J-SQ-015 has been developed to correct the software errors in the affected monitors. The SPCR contains an extensive Design Validation Test that will test all of the software features, not just those that have been modified, to demonstrate that the software will perform as designed in all modes of operation. The corrected software will be installed and tested by July 29, 1994. Once the Design Validation Test has been used to verify SPCR S13J-SQ-01 5 and has been established as a thorough software test for the monitors, it will be used as the design retest whenever significant modifications are made to the source codes. In the interim, the affected monitors are operable.
Administrative controls which prohibit using the high range monitors in the handover disable mode have been implemented.
