ML20132E182
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| ML20132E182 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/25/1985 |
| From: | Lempges T NIAGARA MOHAWK POWER CORP. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NMP-12535, NUDOCS 8507170645 | |
| Download: ML20132E182 (1) | |
Similar Documents at Nine Mile Point | |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20216J9251999-09-30030 September 1999
[Table view]Suppl to Special Rept:On 990621,11 Containment Hydrogen Monitoring Sys Chart Recorder Was Indicating Below Normal Operating Range.Caused by Excessive Wear on Valve Body & Discs of Bypass Pump.Sample Pump Replaced ML20212F7301999-09-21021 September 1999 Special Rept:On 990907,CR Operators Declared 12 Containment Hydrogen Monitoring Sys Inoperable for Planned Maint.Cause of Low Flow Condition Was Determined to Be Foreign Matl. Replaced Sample Pump Valve Discs ML20212B9081999-09-14014 September 1999 Special Rept:On 990901, 12 Containment Hydrogen Monitoring Sys Was Declared Inoperable for Planned Maint.Caused by Planned Maint Being Performed as Corrective Action.Check Valves with O Rings Were Replaced ML20209D0291999-07-0202 July 1999 Special Rept:On 990621,operator Identified That Number 11 Hydrogen Monitoring Sys (Hms) Chart Recorder Was Indicating Below Normal Operating Range.Cause Indeterminate.Licensee Will Complete Troubleshooting of Subject Hms by 990709 ML20207G2671999-03-0101 March 1999 Special Rept:On 990315,Nine Mile Point,Unit 1 Declared Number 12 Containment Hydrogen Monitoring Sys Inoperable. Caused by Degraded Encapsulated Reed Switch within Flow Switch FS-201.2-1495.Technicians Replaced Flow Switch ML20206P2391998-12-31031 December 1998 Special Rept:On 981222,operators Removed non-TS Channel 12 Drywell Pressure Recorder & Associated TS Pressure Indicator from Svc.Caused by Intermittent Measuring Cable Connection in non-TS Recorder Circuitry.Replaced Cable ML20206P2421998-12-30030 December 1998 Special Rept:On 981219,number 12 Hydrogen Monitoring Sys (Hms) Was Declared Inoperable When Operators Closed Valve 201.2-601.Caused by Indeterminate Failure of Valve 201.2-71. Supplemental Rept Will Be Submitted After Valve Is Repaired ML20198M3571998-12-23023 December 1998 Special Rept:On 981210,operators Declared Number 11 Inoperable,Due to Failure of CR Chart Recorder.Caused by Inverter Board in Power Supply Circuitry of Recorder Due to Component Aging.Maint Personnel Replaced Failed Inverter ML20078A9311994-08-31031 August 1994 Special Rept:On 940818,inoperability of Containment Hydrogen Monitoring Unit 11 Occurred.Caused by Failure of K4 Relay in Auto Calibr Unit.Sticking Relay Released & Exercised ML20211P6331986-11-24024 November 1986 Special Rept:On 861110,diesel Fire Pump Taken Out of Svc to Troubleshoot Lube Oil Pressure Switch.Sys Cross Tied to Unit 2 Fire Suppression Sys as Back Up.On 861026 & 28,occurrence Repts Written for Inoperable Fire Door & Pump,Respectively ML20211F4441986-10-17017 October 1986 Special Rept:On 860903 & 04,some Fire Barrier Penetrations Declared Nonfunctional & Fire Door D-107 Rubbing Against Side Jamb.Measures to Maintain Compliance W/Tech Spec Section 3.6.10.1 Implemented ML20205B3171986-07-18018 July 1986 Special Rept:On 860606,Fire Door 137 Breached to Perform Mod to Door.On 860612,fire Detection Sys DA4116W Removed from Svc to Support Welding Activities in Area.Door & Sys Returned to Svc on 860624 & 26,respectively ML20206F8311986-06-0505 June 1986 Special Rept:On 860423,29,0502,05,06,09 & 14 Certain Fire Barrier,Detection & Suppression Sys Out of Svc for More than 14 Days Until Work Associated W/Refueling Outage Completed. Continuous Fire Watches Established ML20211E2471986-05-19019 May 1986 Special Rept:On 860407,09,11,12,14,15,17,18 & 22,certain Fire Barrier,Detection & Suppression Sys out-of-svc for More than 14 Days Until Work Associated W/Refueling Outage Completed.Protective Measures Will Be Continued ML20198J7671986-05-0909 May 1986 Ro:On 860329,fire Detection Sys in East End of Turbine Bldg Taken Out of Svc to Support Welding Activities for Piping Mods.Fire Watch Patrol Will Continue Until Sys Operable ML20197D3151986-04-30030 April 1986 Special Rept:On 860317,26,28,31 & 0402,certain Fire Barrier, Detection & Suppression Sys Out of Svc for More than 14 Days Until Work Associated W/Refueling Outage Completed.Fire Watch Patrols Initiated ML20137Q0091985-12-13013 December 1985 Suppl to Special Rept:On 851119,Beckman Instruments,Inc Channel 11 hydrogen-oxygen Monitoring Unit Declared Inoperable.Caused by Excess Condensation Due to Insufficient Suction of Worn Sample Pump.Pump Replaced ML20139A2941985-11-22022 November 1985 Special Rept:On 851109,Channel 11 hydrogen-oxygen Monitoring Unit (Beckman Instruments,Inc) Declared Inoperable Due to Loss of Sample Flow.Caused by Reboiler Subject to Excessive Condensation.Next Rept by 851213 ML20138A0201985-11-13013 November 1985 Special Rept:On 851031,while out-of-svc for Trouble Shooting,Channel 11 Containment high-range Radiation Monitor Tripped Upscale.Caused by Spurious Electrical Spike Induced by Welding Activities.Trip Setpoint Readjusted ML20138E1231985-11-0505 November 1985 Special Rept:On 851022,ground Fault Inadvertently Induced on Station Battery Board 11.Caused by Removal of Electric Fire Pump Svc to Perform Mod.Fault Cleared & Fire Pumps Returned to Svc ML20137V0101985-09-0909 September 1985 Special Rept:On 850808,fire Barrier Penetrations I-849 & I-2310 Declared Inoperable Due to Maint Mods on Floor Drains.Fire Watch Patrols Performed Hourly Insps Until Completion of Mods on 850830 ML20132E1821985-06-25025 June 1985 Special Rept:On 850611,number of Operable Channels in Svc Less than Required by Tech Specs.Caused by Removal of Primary Containment hydrogen-oxygen Monitor to Replace Faulty Stepper Switch.Sys Returned to Operable Status ML20127B2941985-06-0505 June 1985 Special Rept:On 850508,ventilation Duct Fire Penetration in Reactor Bldg Track Bay Wall Found Unequipped W/Fire Damper, Per Tech Spec 3.6.10.1.Hourly Fire Watch Patrols Established.Reevaluating Fire Design ML20116M1131985-04-15015 April 1985 Special Rept:On 850314,ventilation Duct Fire Penetrations Discovered Not Equipped W/Fire Dampers & Declared Inoperable.Fire Watches Established.Penetrations Will Be Included in Review of Fire Hazards Analysis ML20114D5121985-01-23023 January 1985 Nonroutine Environ Operating Rept:On 841226,data Indicated Sensitivity Spec Not Met for Radiological Analysis of Environ Fish Samples,Per Reg Guide 4.8 & NUREG-0473.Caused by Short half-lives of Radionuclides ML20098G5601984-09-21021 September 1984 Nonroutine Environ Operating Rept, Re Fish Samples Showing Radionuclides W/Sensitivity of Greater than 80 pCi/kg-dry When Analyzed by Gamma Spectral Analysis ML20090E6511984-06-29029 June 1984 Nonroutine Radiological Environ Operating Rept:On 840423, Shoreline Sediment Samples Showed Concentrations of Cs-137 & Sr-90 in Excess of 10 Times Applicable Control Sample.Caused by Past Liquid Effluent Discharges at Site ML20090L0841984-05-14014 May 1984 Ro:On 840414,accuracy of Temp Difference Between Nominal Meteorological Tower Elevations of 27 & 200 Ft Found Inconsistent.Caused by Electronic Drift of 200-ft Elevation Delta Temp Translator Card.Card Recalibr 05000220/LER-1983-044, Special Rept of Actions Taken to Assess Current Status of Fire Barrier Penetrations & to Assure Future Integrity of Barriers Following Improper Sealing of One Penetration Reported in LER 83-441984-04-24024 April 1984 Special Rept of Actions Taken to Assess Current Status of Fire Barrier Penetrations & to Assure Future Integrity of Barriers Following Improper Sealing of One Penetration Reported in LER 83-44 ML20083F5151983-12-0707 December 1983 Nonroutine Rept:One Aug 1983 Cladophora (Algae) Sample Showed Co-60 Concentration Slightly Greater than 10 Times Control Result.Caused by Liquid Effluents at Site.No Corrective Actions Required ML20078K6321983-09-26026 September 1983 Updated RO 83-23:on 830809,circuit Breaker for Core Spray Pump Suction Valve 81-21 Taken Out of Svc for Preventive Maint While Leaving Valve in Open Position.Event Did Not Violate Tech Spec 3.3.4.b as Previously Reported ML20072R1541983-03-16016 March 1983 Telecopy Message of RO 83-05:on 830315,cleanup Sludge Tank Vent Overflowed Into Reactor Bldg Exhaust Ventilation Sys Causing Emergency Ventilation Sys to Initiate. Decontamination of Exhaust Ductwork in Progress ML20148G9911978-10-20020 October 1978 RO 78-35:on 781028 During Routine Surveillance Test All 8 Main Stream High Flow Transmitters Were Set Less Conservatively than Req Due to Test Pressure Gauge Out of Calibr ML20084B5191976-10-14014 October 1976 RO 76-28:during Mgt Review of Existing Plant Design, Containment Spray Pump Control Switch Found to Preclude Sister Pump from Automatic Starting,If Control Switch in Lockout.Cause Not Stated.Operating Procedure OP-19 Revised ML20090E1671974-10-31031 October 1974 Ro:On 741001,during Containment Spray Raw Water Pump Testing,Flow Measurement Was Not Adequate to Determine Specified Performance.Caused by Design Error.Flowthrough Pumps Will Be Adjusted ML20090D3321973-09-0707 September 1973 Ro:On 730829,four Fuel Bundle Segments Were Operating Slightly in Excess of Allowable Average Planar Linear Heat Generation Rate.Adjustments Made in Power Distribution to Obtain Optimum Power Distribution & Output from Reactor ML20090D3901973-09-0707 September 1973 Ro:On 730626,stack Gas Monitor Sample Pump Tripped & Could Not Be Restarted.Caused by Bound Motor.Leakage Detected in Reservoir Jar.Sample Pump Piped Up.Third Sampling Pump Will Be Used as Spare ML20090D3361973-08-30030 August 1973 Ro:On 730829,fuel Bundle Segments Found Operating Slightly in Excess of Allowable Average Planar Linear Heat Generation Rate.Core Thermal Power Reduced Using Reactor Recirculation Flow ML20090D4001973-08-0101 August 1973 Ro:On 730708,reactor Scram Causing Increased Reactor Pressure & High Neutron Flux Scram Occurred.Caused by Isolation of Main Steam Line 12 Due to Closing of Outside Isolation Valve.Relief Valves Operated to Relieve Pressure ML20090D3861973-07-0606 July 1973 Ro:On 730630,during Routine Surveillance Testing,Core Spray Differential Pressure Instruments Read 8.3 Psid or 3.3 Psid Above Instrument Check List.Caused by Instrument Drift. Calibr Cycle Will Be Increased to Every 2 Wks ML20090D3881973-07-0303 July 1973 Ro:On 730629,two Turbine Anticipatory Trip Bypass Switches Found to Actuate at 5 & 6 Psi Above Instrument Checklist Value of 360 Psig.Caused by Instrument Drift.Barksdale 02-13 a & B Calibr Setting Lower than 360 Psig ML20090D3921973-06-21021 June 1973 Ro:On 730612,electromatic Relief Valve Failed to Close Properly Following Manual Actuation from Control Room. Caused by Sticking Valve Due to Scoured Valve Rings & Leaking Union on Pilot Tube Extension.New Rings Installed ML20090D3961973-06-12012 June 1973 Telecopy Message of Ro:On 730612,electromatic Relief Valve Failed to Close Following Manual Actuation from Control Room.Bypass Steam Dropped to 16%.Written Rept to Follow by 730622 ML20090D4051973-06-0606 June 1973 Ro:On 730418,three Main Steam Isolation Valves Failed to Meet Leakage Criteria.Cause Not Stated.Leakage Repaired ML20090D4871973-01-17017 January 1973 Ro:On 721229,turbine Trip & Anticipatory Reactor Scram Initiated When Operator Opened Cabinet Door Carrying Protective Fuses for Generator Monitoring Relays.Caused by Open Pilot Valve for Electromatic Relief Valve D ML20090D4361972-11-29029 November 1972 Ro:On 721119,unit Inadvertently Tripped During Testing of Turbine Thrust Bearing Wear Detector.Turbine Trip Caused Reactor Scram W/Inadvertent Opening of Safety Valve & Pressurization of Drywell.Caused by Operator Error ML20090D5331972-11-0303 November 1972 Ro:On 720809,main Fuel Grapple Failed Over Spent Fuel Storage Pool.Caused by Failed Grapple Cable & Sheared Lower Support Pins.Thrust Bearing Lacked Lubrication.Repair of Grapple Head Will Occur When Acceptable Method Approved ML20090D4491972-11-0303 November 1972 Ro:On 720919,unidentifiable Leakage Into Drywell Equipment Drain Tank 11 Increased.Caused by Faulty Pump Seals.Seals Repaired & Recirculation Sys Isolation Valves Repacked ML20090D4291972-10-0606 October 1972 Ro:On 720925 & 26,standby Liquid Control Pump Discovered Inoperable.Caused by racked-out Circuit Breaker.Operating Procedures Changed ML20083Q0311972-08-16016 August 1972 Ro:Problem W/Electromatic Relief Valve Discovered During Annual Insp Outage.Info Re Leakage Detailed in . Weld Sealed Instead of Stitch Welded.Valve Fully Operable 1999-09-30 Category:TEXT-SAFETY REPORT MONTHYEARML20217G2161999-10-15015 October 1999
[Table view]Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217K4631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Nine Mile Point, Unit 1.With ML20216J9251999-09-30030 September 1999 Suppl to Special Rept:On 990621,11 Containment Hydrogen Monitoring Sys Chart Recorder Was Indicating Below Normal Operating Range.Caused by Excessive Wear on Valve Body & Discs of Bypass Pump.Sample Pump Replaced ML20212F7301999-09-21021 September 1999 Special Rept:On 990907,CR Operators Declared 12 Containment Hydrogen Monitoring Sys Inoperable for Planned Maint.Cause of Low Flow Condition Was Determined to Be Foreign Matl. Replaced Sample Pump Valve Discs ML20212B9081999-09-14014 September 1999 Special Rept:On 990901, 12 Containment Hydrogen Monitoring Sys Was Declared Inoperable for Planned Maint.Caused by Planned Maint Being Performed as Corrective Action.Check Valves with O Rings Were Replaced ML20212C4601999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Nine Mile Point Nuclear Station,Unit 1.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 ML20210U4591999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Nine Mile Point, Unit 1.With ML20209D0291999-07-0202 July 1999 Special Rept:On 990621,operator Identified That Number 11 Hydrogen Monitoring Sys (Hms) Chart Recorder Was Indicating Below Normal Operating Range.Cause Indeterminate.Licensee Will Complete Troubleshooting of Subject Hms by 990709 ML20210B9081999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Nine Mile Point Unit 1.With ML20209F8811999-06-0808 June 1999 Rev 1 to NMP Unit 1 COLR for Cycle 14 ML20207G2261999-06-0707 June 1999 SER Accepting Proposed Mod to Each of Four Core Shroud Stabilizers for Implementation During Current 1999 Refueling Outage at Plant,Unit 1 ML20196E2111999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Nmp,Unit 1.With ML20207B0241999-05-18018 May 1999 Safety Evaluation of Topical Rept TR-107285, BWR Vessel & Intervals Project,Bwr Top Guide Insp & Flaw Evaluation Guidelines (BWRVIP-26), Dtd December 1996.Rept Acceptable ML20206U5351999-05-17017 May 1999 SER Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant, Units 1 & 2 ML20196L2301999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Nmp,Unit 1.With ML20205L0541999-04-0101 April 1999 Nonproprietary Replacement Pages to HI-91738,consisting of Section 5.0, Thermal-Hydraulic Analysis ML20205S5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for NMP Unit 1.With 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 ML20207G2671999-03-0101 March 1999 Special Rept:On 990315,Nine Mile Point,Unit 1 Declared Number 12 Containment Hydrogen Monitoring Sys Inoperable. Caused by Degraded Encapsulated Reed Switch within Flow Switch FS-201.2-1495.Technicians Replaced Flow Switch ML20204C9971999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Nine Mile Point,Unit 1.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML17059C5501999-01-31031 January 1999 Rev 0 to MPR-1966(NP), NMP Unit 1 Core Shroud Vertical Weld Repair Design Rept. ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20199K9331998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20210R8441998-12-31031 December 1998 1998 Annual Rept for Energy East ML20206P2391998-12-31031 December 1998 Special Rept:On 981222,operators Removed non-TS Channel 12 Drywell Pressure Recorder & Associated TS Pressure Indicator from Svc.Caused by Intermittent Measuring Cable Connection in non-TS Recorder Circuitry.Replaced Cable ML20206P2421998-12-30030 December 1998 Special Rept:On 981219,number 12 Hydrogen Monitoring Sys (Hms) Was Declared Inoperable When Operators Closed Valve 201.2-601.Caused by Indeterminate Failure of Valve 201.2-71. Supplemental Rept Will Be Submitted After Valve Is Repaired ML20198M3571998-12-23023 December 1998 Special Rept:On 981210,operators Declared Number 11 Inoperable,Due to Failure of CR Chart Recorder.Caused by Inverter Board in Power Supply Circuitry of Recorder Due to Component Aging.Maint Personnel Replaced Failed Inverter ML20198D9361998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Nine Mile Point,Unit 1.With ML20155E2001998-11-0202 November 1998 Safety Evaluation Approving NMP 980227 Request for Extension of Reinspection Interval for Core Shroud Vertical Welds at NMP1 from 10,600 Hours to 14,500 Hours of Hot Operation ML20195J4141998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20154D8401998-10-0505 October 1998 Safety Evaluation Accepting Proposed Changes Related to PT Limits in Plant,Unit 1 TSs ML20154P1821998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20153B2001998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Nmpns,Unit 1.With ML20237C6351998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20236T5911998-07-20020 July 1998 LER 98-S01-00:on 980618,security Force Member Left Nine Mile Point,Unit 2 Vehicle Gate Unattended Without Ensuring,Gate Alarm Had Been Reactivated.Caused by Inadequate Work Practice.Vehicle Gate Alarm Was Activated ML18040A3491998-07-0202 July 1998 LER 98-017-00:on 980602,control Room Ventilation Sys Was Declared Inoperable.Caused by Original Design Deficiency. Mod Designed,Tested & Implemented Prior to Startup from RF06 to Correct Design deficiency.W/980702 Ltr ML20236Q1701998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Nine Mile Point Nuclear Station,Unit 1 ML17059C1011998-06-24024 June 1998 LER 98-014-00:on 980525,noted Differences Between Actual Valve Weights & Weights Shown on Engineering Drawings.Caused by Vendor Failing to Provide Accurate Valve Weights.Revised Valve Drawings & Associated Calculation,Per 10CFR21 ML20151P1751998-06-16016 June 1998 Rev 0 to SIR-98-067, Evaluation of NMP Unit 2 Feedwater Nozzle-to-Safe End Weld Butter Indication (Weld 2RPV-KB20, N4D) ML18040A3451998-06-0404 June 1998 LER 98-004-01:on 980302,TS Required LSFT of Level 8 Trip of Main Turbine Was Missed.Caused by Knowledge Deficiency of EHC Sys.Revised Applicable LSFT Procedures Prior to Refueling Outage 6.W/980604 Ltr ML20249B4971998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20198B4991998-05-15015 May 1998 Non-proprietary Replacement Pages for Attachment F to Which Proposed to Change TS 5.5, Storage of Unirradiated & Sf ML20247R1141998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20217B0621998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Nine Mile Point Nuclear Station,Unit 1 ML17059C1681998-03-19019 March 1998 Revised Niagara Mohawk Powerchoice Settlement Document for NMPC PSC Case Numbers 94-E-0098 & 94-E-0099, Vols 1 & 2 ML20217F4341998-03-19019 March 1998 SER Related to Proposed Restructuring New York State Electric & Gas Corp,Nine Mile Point Nuclear Station,Unit 2 ML17059B9051998-02-28028 February 1998 NMP Unit 1 Boat Samples Analyses Part Iii:Tension Tests, RDD:98:55863-004-000:01 1999-09-30 |
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- - -* NMP-12535 NIAGARA MOHAWK POWER CORPORATION NI AG ARA MOHAWK 300 ERIE BOULEVARD. WEST SYRACUSE. N. Y.13 202 June 25, 1985
_Dr.' Thomas E. Murley Regional Administrator United States Nuclear Regulatory Connission Region I 631 Park Avenue King of Prussia, PA 19406 Re: Docket No. 50-220-SPECIAL REPORT-
Dear Dr. Murley:
This Special Report .is being submitted in accordance with Technical Specification 3.6.11 (Table 3.6.11-2 action 4a) which states, "With the number of operable channels less than the total number of channels shown in Table 3.6.11-1, prepare and submit a Special Report to the Commission within 14 days following the event outlining the actions taken, 'the cause
. of the inoperability and the plans and schedrie for restoring the system to operable status."
On June 11,1985 the #11 Primary Containment flydrogen-Oxygen Monitor was removed from service by Operations so that a faulty stepper switch could be' replaced. This left the number of operable channels remaining in service less than that required by Technical Specifications Table 3.6.11-1. The monitor was returned to an operable state by operations on June 12, 1985. On June 18,1985 the #12 Primary Containment flydrogen-Oxygen Monitor was removed' from service by Operations so that an un-soldered connection and dirty contacts could be repaired. This left the number of operable channels remaining in service less than that required by Technical Specifications Tabic 3.6.11-1. The system was returned to an operable state by Operations on the same day it was removed (6/18/85) .
Very truly yours,.
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5000220 PDR Thomas E. Lempges Vice President Nuclear Generation TEL/lo j cc: Document Control Desk Resident Inspector g
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