ML20153D981
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| ML20153D981 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/14/1986 |
| From: | Bynum J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| ANPP-01530-JRB, ANPP-1530-JRB, NUDOCS 8602240330 | |
| Download: ML20153D981 (1) | |
Similar Documents at Palo Verde | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20079L8741991-10-31031 October 1991
[Table view]Special Rept 1-SR-91-003:on 910927,reactor Trip Occurred, Resulting in Opening of Turbine Control Valve & Causing Primary Sys Temp to Decrease Below 1,837 Psia.Caused by Valid Low Pressurizer Pressure.Isolation Sys Reset ML20155J6451988-10-20020 October 1988 Special Rept 3-SR-88-006:on 881009,condenser Evacuation Sys high-range Effluent Monitor Inoperable for Greater than 72 H.Monitor Inoperable Due to Erratic Indication Caused by Loose &/Or Dirty Detector Connection.Connection Cleaned ML20236G6331987-10-23023 October 1987 Suppls Special Rept 2-SR-86-029.On 870801,containment Bldg Atmosphere Radiation Monitor Declared Inoperable.Caused by Faulty Diaphragm in Discharge Solenoid Valve.Valve Rebuilt & Returned to Operable Status ML20205N9551987-03-19019 March 1987 Special Rept 2-SR-87-009:on 870314,smoke Found Issuing from Heater Drain Pump B Motor.Caused by Mechanical Seal Malfunction.Motor Breaker & Space Heater Breaker Racked Out. Fire Extinguished W/Portable Co Extinguisher ML20205G5261987-03-16016 March 1987 Special Rept 2-SR-87-002:on 870222,high-range Noble Gas Activity Monitor RU-144 Inoperable for Greater than 72 H. Caused by Maint Due to Chattering Contacts in Low Voltage Power Supply.Low Voltage Power Supply Replaced ML20205E5781987-03-13013 March 1987 Special Rept Suppl 2-SR-87-003-01:on 870208,fire at Emergency Diesel Generator a Identified.Caused by Incorrect Implementation of Procedures for Fuel Injection Tubes, Resulting in Tube Disengagement.Fire Extinguished ML20207R1161987-02-25025 February 1987 Special Rept 1-SR-87-009:on 870217,tubes in Steam Generators 1 & 2 Plugged,Resulting from Inservice Insp of Both.Mgt Decision to Inspect Unit 2 Found 30 Tubes Plugged in Steam Generator 1 & 21 Tubes in 2 ML20207Q9931987-02-23023 February 1987 Special Rept 1-SR-87-005:on 870108,radiation Monitoring Units RU-145 & 146 Il Found Inoperable Due to Closed Inlet Valve HCV01.Valve Opened Immediately & Similar Valves Verified to Be in Correct Position.Procedure Revised ML20212D3521987-02-13013 February 1987 Special Rept 2-SR-87-001:on 870123,preplanned Alternate Sampling Program Initiated to Monitor Plant Ventilation Sys After Radiation Monitor Inoperable for 72 H.Cause Under Investigation.Monitor RU-144 Returned to Svc on 870124 ML20211N8121987-02-11011 February 1987 Special Rept 2-SR-87-003:on 870208,fire Discovered at Emergency Diesel Generator A.Caused by Loose Fuel Oil Line Due to Separated Fitting That Supplies Cylinder 5.Next Rept Expected by 870309 ML20211E6261987-01-21021 January 1987 Special Rept 2-SR-86-039:on 861224,containment Bldg Atmosphere Radiation Monitor RU-1 Declared Inoperable.Cause Unknown.Work Order Issued & Troubleshooting Commenced ML20211R0111986-12-0303 December 1986 Special Rept 2-SR-86-037:on 861104,containment Bldg Atmosphere Monitor RU-1 Declared Inoperable Due to Generation of Filter Step Alarms.Caused by Loose Capacitor. Connector Resoldered & Channel Declared Operable on 861110 ML20214V7031986-11-19019 November 1986 Suppl to Special Rept 1-SR-86-069:on 860611,qualified Safety Parameter Display Sys Operated W/One Channel Less than Required & Subsequently Exceeded Tech Spec Action Statement. Actual Cause Not Determined.Addl Troubleshooting Required ML20214P8761986-11-19019 November 1986 Special Rept 2-SR-86-036:on 861031,containment Bldg Atmosphere Monitor RU-1 Declared Inoperable Due to Cracked Drive Belt on Monitor Pump.Caused by Normal Component Aging. Belt Replaced ML20214P9951986-11-18018 November 1986 Special Rept 1-SR-86-097:on 861020,fuel Bldg Ventilation Sys high-range Monitor RU-146 Inoperable.Caused by Failure of low-range Monitor RU-145 Due to Microprocessor Lockup. Monitors Expected to Be Returned to Svc by End of Nov ML20214P2741986-11-13013 November 1986 Special Rept 1-SR-86-093:on 860830 & 1015,containment Bldg Area Radiation Monitor RU-149 Declared Inoperable.Caused by Cognitive Personnel Errors.Appropriate Personnel Counseled on Proper Preparation of Tech Spec Condition Records ML20214P2101986-11-0606 November 1986 Special Rept 2-SR-86-033:on 861011,while Unit in Mode 1,fuel Bldg Ventilation Sys High Range Monitor Inoperable for More than 72 H.Caused by Failure of Channel 2 Detector Due to Normal Component Aging of Integral Tubing.Detector Replaced ML20213G6961986-10-31031 October 1986 Special Rept 2-SR-86-032:on 861002,containment Bldg Atmosphere Particulate Channel RU-1 Declared Inoperable After Finding Low Particulate Readings Compared to Grab Sample Results.Caused by Inadequately Sealed Gasket ML20211J7551986-10-30030 October 1986 Special Rept 2-SR-86-031:on 861001,72 H Action Statement Exceeded for Operability of Noble Gas Activity Monitor RU-142.Monitor Declared Inoperable on 860929.Caused by burned-out Led Diode.Monitor Reworked & Returned to Svc ML20215N3991986-10-22022 October 1986 Special Rept 2-SR-86-030:on 860924,containment Bldg Atmosphere Particulate Channel Declared Inoperable.Computer Experienced Spurious Memory Losses.Surveillance Test Performed & Channel Returned to Svc ML20215K7621986-10-13013 October 1986 Special Rept 1-SR-86-089:on 860911 & 14,fuel Bldg Ventilation Sys high-range Monitor Ru-146 Declared Inoperable for More than 72 H.Caused by Inoperable Monitor Ru-145 on 860911 Due to Spurious Indications ML20211C8541986-10-0909 October 1986 Special Rept 1-SR-86-085:on 861006,safety Injection Actuation Signal & Assumed Safety Injection Flow Into RCS Initiated.Caused by Unstable Feedwater Control Sys Operation.Evaluation in Progress ML20203N2571986-09-10010 September 1986 Suppl 2 to Special Rept 1-SR-85-018:on 850925,condenser Evacuation Sys high-range Monitor RU-142 Inoperable for More than 72 H Due to Failure in low-range Monitor RU-141.New Isolated Grounding Sys Will Be Installed After 860601 ML20203N3651986-09-0707 September 1986 Suppl 1 to Special Rept 2-SR-86-008:on 860331,condenser Evacuation Sys high-range Monitor RU-142 Inoperable for More than 72 H Due to Failure of low-range Monitor RU-141. Caused by Moisture Trapped in Process/Sample Flow Media ML20214P0141986-09-0404 September 1986 Special Rept 2-SR-86-028:on 860809,action Statement for Operability of Main Steam Line Effluent Monitor RU-139 A/B Exceeded.Caused by Communication Problem W/Radiation Monitor Minicomputer.Cause Undetermined Due to Random Malfunction ML20214N9371986-09-0303 September 1986 Special Rept 2-SR-86-029:on 860801,containment Bldg Atmosphere Radiation Monitor RU-1 Declared Inoperable. Possibly Caused by Defective Suction Pump & Faulty Diaphragm.Pump Replaced & Valve Rebuilt ML20206N8111986-08-0808 August 1986 Special Rept 1-SR-86-053:on 860806,startup Transformer NAN-X03 Tripped,Resulting in Loss of Power to Four Unit 1 & Five Unit 2 Buses.Cause Unknown.Esf Actuation Signals Reset & Diesel Generators Unloaded & Shut Down ML20205G0071986-08-0606 August 1986 Special Rept 2-SR-86-018:on 860705,reactor Vessel Water Level Sys Inoperable for More than 7 Days.Caused by Connection of Channel B Heated Junction Thermocouples in Reverse Order.Connection Corrected ML20214J9261986-07-26026 July 1986 RO 2-SR-86-021:on 860626,radiation Monitoring Unit Declared Inoperable on 860623 Not Restored to Operable Status within 72 H.Possibly Caused by Anomaly in Power Supply Voltage. Monitor Reset ML20206R3891986-07-0707 July 1986 Special Rept 1-SR-86-021:on 860513 & 0616,Units 1 & 2, Respectively,Experienced Excessive Alarms on Steam Generator Sensors.Caused by Improper Alarm Setpoint Calibr.Work Request Generated to Check Setpoints During Shutdown ML20202D6901986-07-0303 July 1986 Special Rept 1-SR-86-069:on 860611,five Inoperable Heated Junction Thermocouple Sensors Not Returned to Svc within 7 Days.Cause of Inoperable Sensors Not Determined.Addl Troubleshooting Required ML20206R7581986-06-23023 June 1986 Special Rept 1-SR-86-068:on 860613,30-day Action Statement for Operability of Seismic Monitoring Sys Exceeded.Caused by Defective Switch Card Discovered During Seismic Monitoring Calibr Test.Switch Card Repaired ML20199B3151986-06-0303 June 1986 Special Rept 1-SR-86-049:on 860505,during Deenergization of Train B Balance of Plant/Esfas for Module Replacement Power Loss to Shutdown Cooling Loop & Battery Chargers Occurred. Caused by Inadvertent Grounding of Wire.Power Restored ML20198S5041986-05-30030 May 1986 Special Rept 2-SR-86-015:on 860525,reactor Trip Initiated by Reactor Protection Sys as Result of Low Level Condition in Steam Generator 1.Subsequent Depressurization of Steam Generators Resulted in ESF Initiation ML20210V2201986-05-27027 May 1986 Special Rept 1-SR-86-042:on 860428,nonvalid Emergency Diesel Generator Tripped During Troubleshooting.Caused by Improper Temporary Clamp Reducing Cable Length.Clamp Removed ML20198P9981986-05-21021 May 1986 Special Rept 2-SR-86-014:on 860421,discovered That Unit Potentially Exceeded Time Limits for Action Statement 3 of Tech Spec 3.3.1.Tech Spec 3.0.3 Exited 15 Minutes After Entry & Event Terminated ML20198Q3261986-05-19019 May 1986 Special Rept 1-SR-86-033:on 860417,during Surveillance Testing,Emergency Diesel Generator Train a Tripped on Overspeed Condition.Caused by Deflection of Air Intake Overspeed Butterfly Valve Disk to Fully Open Position ML20203Q0251986-04-25025 April 1986 Special Rept 2-SR-86-008:on 860331,72 H Action Statement for Operability of Condenser Evacuation Sys high-range Radiation Monitor RU-142 Exceeded.Caused by Moisture Trapped in Process/Sample Flow Media.Moisture Trap Installed ML20210L1301986-04-18018 April 1986 Supplemental Special Rept 1-SR-85-035:on 851224,containment high-range Radiation Monitor RU-149 Declared Inoperable Due to Spurious High & Alert Radiation Alarms.Caused by Low Resistance in Radiation Monitoring Unit Cable ML20210K7161986-04-18018 April 1986 Special Rept 1-SR-86-016:on 860402,diesel Generator a Tripped on Overspeed & Declared Inoperable.Caused by Misaligned Overspeed Combustion Air Indication Switch.Slots Cut Into Switch Mounting Bracket & Switch Aligned ML20210K6941986-04-16016 April 1986 Supplemental Special Rept 1-SR-85-032:on 851128,72 H Action Statement for Operability of Containment high-range Monitor RU-148 Exceeded.Caused by Intermittent Low Resistance in Detector Cable Inside Containment.Cable to Be Replaced ML20141F2611986-04-0404 April 1986 Special Rept 1-SR-86-011:on 860306,diesel Generator a Failed to Start within 10 as Required by Tech Spec 4.8.1.1.2.a. Caused by Seized Diesel Generator Governor Output Shaft. Governor Replaced ML20210G5501986-03-17017 March 1986 Supplemental Special Rept 1-SR-85-018:on 850925,condenser Evacuation Sys high-range Monitor (RU-142) Inoperable for More than 72 H.Caused by low-range Monitor Being Declared Inoperable Due to Loss of Stored Data ML20154Q8551986-02-25025 February 1986 Special Rept 1-SR-86-007:on 860203,during Performance of Surveillance Test 41ST-1DG02,diesel Generator B Overspeed Trip Occurred.Caused by Fiber Optic Optical Transistor Failure.Fiber Optic Printed Circuit Board Replaced ML20137Y4061986-02-24024 February 1986 Special Rept (2-SR-86-005):on 860125,Tech Spec Action Statement for Operability of Vent high-range Radiation Monitor RU-144 Exceeded.Caused by Energizing Reactor Coolant Pump W/Grounding Straps Still Attached.Procedure Revised ML20137Y4551986-02-21021 February 1986 Special Rept (1-SR-86-003):on 860122,72 H Action Statement for Operability of Vent high-range Radiation Monitor RU-144 Exceeded.Caused by Time Spent Troubleshooting on Monitor RU-143 ML20137Z2281986-02-21021 February 1986 Special Rept 1-SR-86-005:on 860122,condensor Evacuation Sys high-range Monitor Inoperable for More than 72 H.Caused by Spurious Indication of High Radiation.Investigation Continuing ML20153D9811986-02-14014 February 1986 Ro:On 860211,post-accident Sampling Sys Declared Inoperable Due to Confirmatory Testing of Pump Components.Preplanned Alternate Sampling Program Will Be Submitted ML20137V1481986-02-10010 February 1986 Special Rept 1-SR-86-006:on 860203,safety Injection Actuation,Containment Isolation Actuation & Main Steam Isolation Signals Occurred Due to Reactor Trip.Caused by Low Level in Steam Generator 2.Plant Parameters Stabilized ML20137W0541986-01-23023 January 1986 Special Rept 1-SR-85-035:on 851227,72 H Action Statement for Operability of Containment high-range Radiation Monitor (RU-149) Exceeded.Monitor Declared Inoperable on 851224 Due to Spurious Detector Failure Alarms 1991-10-31 Category:TEXT-SAFETY REPORT MONTHYEARML17300B3811999-09-30030 September 1999
[Table view]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 |
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RECOVED NRC Arizona Nuclear Power Project, P.O. BOX $2034 e PHOENIX. ARIZONA 85072-2034 4 February 14, 1986 ANPP-01530-JRB-94.04 Mr. G. P. Yuhas Chief Facilities Radiological Protection Section Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3 Docket Nos, STN 50-528 (License No. NPF-41)/529/530 Preplanned Alternate Sampling Program File: 85-019-026; 85-056-026 Per our conversations with you on 2-14-86 concerning the Post Accident Sampling System and the Preplanned Alternate Sampling Program the following is submitted for your approval.
The containment atmosphere sampling portion of the Post Accident Sampling System (PASS) has been declared inoperable due to confirmatory testing of pump components. Pursuant to Technical Specification 3.3.3.1, PASS was declared inoperable on Tuesday, February 11. at 1010.
Currently no approved preplanned alternate sampling program (PASP) is in place for use at ANPP. PASP is currently being readied for formal submittal to Region V.
For the majority of accident scenarios, ANPP proposes to utilize grab sampling for the determination of containment atmosphere activity and hydrogen levels. In the event that dose rates preclude grab san.pling, RU-148 and RU-149 and the containment post-loca hydrogen monitors will be utilized for core damage assesment.
We are currently in an operability action statement on RU-148 and RU-149. As an alternative ANPP proposes the use of RE-37, RE-38, RE-158B and RE-158C in accordance with the preolanned alternate program invoked by technical specification 3.3.3.1 and implemented by EPIP-14A.
We request your approval to proceed as proposed.
Very truly yours, 8602240330 860215 PDR ADOCK 05000528 h S J. R. Bynum Plant Manager, VNGS
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