ML20084E134
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| ML20084E134 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/26/1974 |
| From: | Platt C ROCHESTER GAS & ELECTRIC CORP. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20084E131 | List: |
| References | |
| AO-50-244-74-17, NUDOCS 8304140352 | |
| Download: ML20084E134 (1) | |
Similar Documents at Ginna | |
|---|---|
Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20084A5111975-08-15015 August 1975
[Table view]AO 75-13:on 750815,approx 12,000 Gallons of Refueling Water Storage Tank Water Ran Into Sump B Causing Containment Basement Floor to Be Flooded & Sump a to Flood.Caused by Personnel Error ML20084A7251975-07-25025 July 1975 AO 75-12:on 750725,during Monthly Surveillance Procedure PT-9,undervoltage & Underfrequency Protection,Primary Undervoltage Device 273/11B Armature Did Not Drop Down to Assume de-energized Position.Caused by Scale Accumulation ML20084A8111975-04-11011 April 1975 AO 75-09:on 750410,control Rod Cap K-7 Inspected Due to Leak Indication & Pinhole Leak Discovered.Cap to Be Replaced ML20084A8301975-04-0909 April 1975 AP 75-08:on 750326,post-accident Charcoal Filter Sys a & B Tested for Filter Efficiency.Filter Bank a Tested Efficiency at 99.4% for Molecular Iodine Removal ML20084A8511975-03-24024 March 1975 AO 75-07:eddy Current Testing Program Indicated That 10 a & 12 B Steam Generator Hot Leg Tubes Had Wall Thinning of 50% or Greater.Cause Not Stated ML20084A8791975-02-26026 February 1975 AO 50-244/75-5:on 750218,safety Injection Pump 1C Failed to Start Manually from Bus 16.Cause Not Stated.Safety Injection Pump 1C Will Be Started Weekly Until 1975 Refueling Shutdown Scheduled for 750315 ML20084A9031975-02-21021 February 1975 AO 50-244/75-04:on 750213,during Performance of PT-20,MSIV Solenoid Trip Test,One Air Supply Solenoid Valve Failed to Operate When Tested.Caused by Flat Spot or Burr on Latching Pin.Linkage Adjusted ML20084A8881975-02-18018 February 1975 AO 75-05:on 750218,safety Injection Pump 1C Failed to Start from Bus 16 When Manually Activated.Cause Not Stated.Pump Will Be Started Once/Wk from Bus 16 Until PORC Changes Testing Frequency ML20084A9251975-02-14014 February 1975 AOs 50-244/75-02 & 50-244/75-03:on 750205 & 06,safety Injection Pump 1C Failed to Start Manually from Bus 16. Caused by Spring Being Slightly Depressed.Westinghouse to Be Notified ML20084A9141975-02-13013 February 1975 AO 75-04:on 750213,during Performance of PT-20 MSIV Solenoid Trip Test,One Air Supply Solenoid Valve on MSIV 1H Failed to Operate When Tested.Cause Not Stated.Linkage Adjusted.Test to Be Repeated Before 750315 Outage ML20084A9521975-02-0606 February 1975 AO 75-03:while Conducting Retest of Safety Injection Pump 1C on Bus 16,pump Failed to Start Manually First Time.Holding Coil of Lockout Relay & Breaker to Have Thorough Insp ML20084A9411975-02-0505 February 1975 AO 75-02:while Conducting PT-2.1 & Following Satisfactory Test of Safety Injection Pumps 1A & B,Safety Injection Pump 1C Failed to Start Manually on Bus 16.Pumps Started from Bus 14.Thorough Insp of Breaker Recommended ML20084B0091975-01-17017 January 1975 AO 50-244/75-1:on 750108,turbine Governor Valve & Associated Trip & Throttle Valve Tripped to Closed Position Approx 15 After Steam Supply Quick Start Valves Opened.Caused by Degraded Lube Oil Supply Pressure Due to Instrument Drift ML20084B0211975-01-0909 January 1975 AO 75-1:on 750108,steam Driven Auxiliary Feedwater Pump Tripped Out After Running for Approx 15 S.Low Lube Oil Pressure Trip Setpoint Adjusted ML20084E0841974-12-20020 December 1974 AO 50-244/74-21:on 741211,boric Acid Tank Level Channel LC 171 Dropped to Zero Level Indication.Caused by Failure of LC 171 Power Supply Module.Module Replaced ML20084E0961974-12-18018 December 1974 AO 50-244/74-20:on 741209,deficiency Found in Monthly Surveillance Test Procedure PT-16 Re Auxiliary Feedwater Flow.Caused by Incorrect Ref Pressure Value.Test Procedure PT-16 Revised Based on New Data from Flow Balance ML20084E1031974-12-13013 December 1974 AO 50-244/74-19:on 741204,during Surveillance Test PT-9, Undervoltage Relay 274/11B Failed to Operate.Caused by Scale Accumulation on Armature Plunger Opposite Upper Guide Bearing.Plunger Polished ML20084E0891974-12-11011 December 1974 AO 50-244/74-21:on 741211,boric Acid Tank Level Transmitter LT-171 Dropped to Zero Level Indication.Cause Not Stated ML20084E0991974-12-10010 December 1974 AO 50-244/74-20:on 741209,deficiency Discovered in PT-16 Flow Check Procedure of Auxiliary Feedwater Pump.Procedure Revised ML20084E1111974-12-0505 December 1974 AO 50-244/74-19:on 741204,during Monthly Surveillance Test PT-9,undervoltage Relay 274/11B Failed.Caused by Scale Accumulation on Armature Plunger Opposite Upper Guide Bearing.Plunger Polished ML20084E1201974-11-12012 November 1974 AO 50-244/74-18:on 741111,excessive Leakage Rate Indicated from Containment Side Purge Exhaust Valve.Caused by Crimp in Rubber Valve Seat.Crimp Smoothed Out ML20084E1291974-10-0404 October 1974 AO 50-244/74-17:on 740925,discrepancies Found in Level Alarm Setpoints on Accumulations.Caused by Erroneous Calculations Supplied by Westinghouse.Tech Spec Change Request Filed ML20084E1381974-09-30030 September 1974 AO 50-244/74-16:on 740918,results of Water Sample Analysis Showed Boron Concentration in a Accumulator Below Tech Spec Limit.Caused by Leakage of Primary Coolant Into B Loop Accumulator.Closer Surveillance of Accumulator Maintained ML20084E1341974-09-26026 September 1974 AO 50-244/74-17:on 740925,possible Discrepancy Found in Vol of Borated Water in Accumulators.Cause Under Investigation. Correct Vol to Be Established When Final Accurate Figures Available ML20084E1421974-09-19019 September 1974 AO 50-244/74-16:on 740918,results of Water Sample Analysis Showed Boron Concentration in a Accumulator Below Tech Spec Limit.Recommendations Made for Closer Surveillance of Boron Concentration in Accumulators ML20084E1451974-08-23023 August 1974 AO 50-244/74-15:on 740815,steam Generator a Blowdown Isolation Valve Was Only Closing 80%.Caused by Piece of Carbon Steel Resting on Top of Valve Seat Ring.Valve Stem & Plug Assembly Replaced ML20084E1491974-08-16016 August 1974 AO 50-244/74-15:on 740815,1A Steam Generator Blowdown Isolation Valve Failed to Close Properly.Further Insp of Valve Operator Recommended ML20084E1521974-08-15015 August 1974 AO 50-244/74-14:on 740807,safety Injection Pump 1C Failed to Start Manually on Bus 16.Cause Not Determined.Westinghouse Specialist to Examine Breaker.Possible Replacement of Lockout & Tripper Bar Assembly Recommended ML20084E1581974-08-0707 August 1974 AO 50-244/74-14:on 740807,safety Injection Pump 1C Failed to Start Manually on Bus 16.Thorough Insp Recommended ML20084E1661974-07-16016 July 1974 AO 50-244/74-13:on 740702,leak Discovered in Socket Weld of 3/4-inch Vent Pipe to Weldolet on Charging Pump Discharge Filter Bypass Line.Caused by Improper Weldolet Surface Preparation.New Valve & Nipple Installation Recommended ML20084E1741974-07-16016 July 1974 AO 50-244/74-12:on 740629,leak Discovered in Socket Weld of 3/4-inch Vent Pipe to Vent Valve on Charging Pump Discharge Filter Bypass Line.Caused by Corrosion Mechanism.New Valve Installation Recommended ML20084E1861974-07-0808 July 1974 AO 50-244/74-11:on 740626,main Steam Line Isolation Valve a Failed to Close.Caused by Excessive Heat to Coils & Plungers.Plungers Adjusted ML20084E1691974-07-0303 July 1974 AO 50-244/74-13:on 740702,leak Found in Weld Connecting 3/4-inch Vent Valve Nipple to Weldolet on Charging Pump Filter Bypass Line.Repairs During Cold Shutdown Recommended ML20084E1801974-07-0202 July 1974 AO 50-244/74-12:on 740629,leak Found in Weld Connecting 3/4-inch Vent Valve to Nipple on Charging Pump Discharge Filter.Valve Replaced ML20084E1921974-06-26026 June 1974 AO 50-244/74-11:on 740626,main Steam Line Isolation Valve a Failed to Close.Valves Adjusted ML20084E1951974-06-21021 June 1974 AO 50-244/74-10:on 740613,valve 991,outlet from Primary Sys Flow Indicator FI-903 to Channel Drain Tank Reported Open. Caused by Improperly Verified Valve Alignment.Valve 991 Locked Closed ML20084E1991974-06-14014 June 1974 AO 50-244/74-10:on 740613,valve 991 of Sample Sys Flow Indicator FI-903 Found Open & Chemical Tank Overflowing. Valve Closed & Tank Pumped Down to Normal Level ML20084E2061974-06-10010 June 1974 AO 50-244/74-09:on 740530,during Surveillance Test, Underfrequency Relay 811/11A Found Inoperable.Cause Undetermined.Testing Frequency of Relays Increased ML20084E2081974-05-30030 May 1974 AO 50-244/74-09:on 740530,during Surveillance Test PT-9, One Underfrequency Relay on Bus 11A Failed to Transmit Signal of Simulated Fault Condition.Relay Replaced ML20084E2141974-05-21021 May 1974 AO 50-244/74-08:on 740511,increase in Gas Radiation Level of Auxiliary Bldg Exhaust at Vent Noticed.Caused by Dripping in General Location of a Mixed Bed Demineralizer Outlet Piping.Leak Isolated ML20084E2201974-05-14014 May 1974 AO 50-244/74-08:on 740511,liquid Leak in Outlet Piping from a Mixed Bed Demineralizer in Auxiliary Bldg Released Gases to Bldg Atmosphere.Leak Isolated ML20084E2311974-05-0303 May 1974 AO 50-244/74-07:on 740426,during Surveillance Test, Underfrequency Relay 811/11A Found Inoperable.Caused by Opening of Electrolytic Capacitor.Printed Circuit Board Replaced ML20084E2431974-05-0202 May 1974 AO 50-244/74-06: on 740422,RHR Pump Suction Valve 851B Failed to Open.Caused by Valve Being Too Tightly Sealed in Closed Position.Operating Procedures for Heatup Changed ML20084E2391974-04-26026 April 1974 AO 50-244/74-07:on 740426,during Surveillance Test PT-9,one Underfrequency Relay on 11A Bus Failed to Transmit Signal to Logic Racks When Fault Condition Simulated.Relay Replaced ML20084E2501974-04-23023 April 1974 AO 50-244/74-06:on 740422,RHR Valve 851B Failed to Open. Valve Manually Opened.Procedure Review Recommended ML20084H0301974-04-16016 April 1974 AO 50-244/74-04:on 740406,during Surveillance Test PT 2.1, Safety Injection Pump 1C Failed to Start Manually When Connected to Bus 16.Caused by Trip Bar Switch Prematurely Closing.Lockout Coil Assembly & Trip Bar Switch Adjusted ML20084H0341974-04-0808 April 1974 AO 50-244/74-04:on 740406,during Periodic Test PT-2,1,safety Injection Pump 1C Failed to Start Manually on Bus 16.Caused by Failure of Capacitor in Control Circuit & Malfunction of Tripper Bar Switch.Switch Adjusted ML20084E2731974-02-22022 February 1974 AO 50-244/74-03:on 740214,containment Purge & Exhaust Dampers Failed to Maintain Leakage Rates within Specified Levels.Caused by Paint & Dirt Debris on Disc Edges of Purge Valves.Edges Cleaned ML20084E2931974-02-19019 February 1974 Ao:On 740101,abnormal Degradation Discovered in Steam Generator a Tubes Designed to Contain Radioactive Matls Resulting from Fission Process.Cause Undetermined.Tube Sheets Cleaned Using High Pressure Water Lance Method ML20084E2811974-02-15015 February 1974 AO 50-244/74-03:on 740214,containment Purge & Exhaust Dampers Failed to Maintain Leakage Rates within Specified Levels.Repairs to Dampers Will Be Completed 1975-08-15 Category:TEXT-SAFETY REPORT MONTHYEARML17265A7601999-10-0505 October 1999
[Table view]Part 21 Rept Re W2 Switch Supplied by W Drawn from Stock, Did Not Operate Properly After Being Installed on 990409. Switch Returned to W on 990514 for Evaluation & Root Cause Analysis ML17265A7621999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Re Ginna Npp.With 991008 Ltr ML17265A7531999-09-23023 September 1999 Part 21 Rept Re Corrective Action & Closeout of 10CFR21 Rept of Noncompliance Re Unacceptable Part for 30-4 Connector. Unacceptable Parts Removed from Stock & Scrapped ML17265A7541999-09-22022 September 1999 LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr ML17265A7471999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Re Ginna Npp.With 990909 Ltr ML17265A7431999-08-24024 August 1999 LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed ML17265A7341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Re Ginna Npp.With 990806 Ltr ML17265A7291999-07-29029 July 1999 Interim Part 21 Rept Re safety-related DB-25 Breaker Mechanism Procured from W Did Not Pas Degradatin Checks When Drawn from Stock to Be Installed Into BUS15/03A.Holes Did Not line-up & Tripper Pan Bent ML17265A7181999-07-23023 July 1999 LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians ML17265A7081999-07-22022 July 1999 LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored ML17265A7131999-07-22022 July 1999 Special Rept:On 990407,radiation Monitor RM-14A Was Declared Inoperable.Caused by Failed Communication Link from TSC to Plant Process Computer Sys.Communication Link Was re-established & RM-14A Was Declaed Operable on 990521 ML17265A7031999-07-19019 July 1999 LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr ML17265A7211999-07-19019 July 1999 ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp. ML17265A7021999-07-15015 July 1999 LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr ML17265A7661999-06-30030 June 1999 1999 Rept of Facility Changes,Tests & Experiments Conducted Without Prior NRC Approval for Jan 1998 Through June 1999, Per 10CFR50.59.With 991020 Ltr ML17265A7011999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Re Ginna Npp.With 990712 Ltr ML17265A6851999-06-21021 June 1999 LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr ML17265A6761999-06-16016 June 1999 Part 21 Rept Re Defects & noncompliances,10CFR21(d)(3)(ii), Which Requires Written Notification to NRC on Identification of Defect or Failure to Comply. Relays Were Returned to Eaton for Evaluation & Root Cause Analysis ML17265A6661999-06-0202 June 1999 LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With 990602 Ltr ML17265A6681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Re Ginna Nuclear Power Plant.With 990608 Ltr ML17265A6651999-05-27027 May 1999 Interim Rept Re W2 Control Switch,Procured from W,Did Not Operate Satisfactorily When Drawn from Stock to Be Installed in Main Control Board for 1C2 Safety Injection Pump. Estimated That Evaluation Will Be Completed by 991001 ML17309A6541999-05-27027 May 1999 LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr ML17265A6631999-05-24024 May 1999 LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved ML17265A6601999-05-21021 May 1999 LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr ML17265A6591999-05-17017 May 1999 Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested ML17265A6441999-05-13013 May 1999 LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr ML17265A6431999-05-12012 May 1999 LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed ML17265A6381999-05-0707 May 1999 Part 21 Rept Re Replacement Turbocharger Exhaust Turbine Side Drain Port Not Functioning as Design Intended.Caused by Manufacturing Deficiency.Turbocharger Was Reaasembled & Reinstalled on B EDG ML17265A6391999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Re Ginna Nuclear Power Plant.With 990510 Ltr ML17265A6361999-04-23023 April 1999 Part 21 Rept Re Power Supply That Did Not Work Properly When Drawn from Stock & Installed in -25 Vdc Slot.Power Supply Will Be Sent to Vendor to Perform Failure Mode Assessment.Evaluation Will Be Completed by 991001 ML17265A6301999-04-18018 April 1999 Rev 1 to Cycle 28 COLR for Re Ginna Npp. ML17265A6251999-04-15015 April 1999 Special Rept:On 990309,halon Systems Were Removed from Svc & Fire Door F502 Was Blocked Open.Caused by Mods Being Made to CR Emergency Air Treatment Sys.Continuous Fire Watch Was Established with Backup Fire Suppression Equipment ML17265A6551999-04-0909 April 1999 Initial Part 21 Rept Re Mfg Deficiency in Replacement Turbocharger for B EDG Supplied by Coltec Industries. Deficiency Consisted of Missing Drain Port in Intermediate Casing.Required Oil Drain Port Machined Open ML17265A6291999-03-31031 March 1999 Rev 0 to Cycle 28 COLR for Re Ginna Npp. ML17265A6241999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ginna Station.With 990409 Ltr ML17265A6141999-03-31031 March 1999 LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr ML17265A6131999-03-29029 March 1999 LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr ML17265A6061999-03-24024 March 1999 LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp ML17265A5661999-03-0101 March 1999 Rev 26 to QA Program for Station Operation. ML17265A5961999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With 990310 Ltr ML17265A5371999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With 990205 Ltr ML17265A5951998-12-31031 December 1998 Rg&E 1998 Annual Rept. ML17265A5001998-12-21021 December 1998 Rev 26 to QA Program for Station Operation. ML17265A4951998-12-21021 December 1998 LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr ML17265A4931998-12-17017 December 1998 LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery ML17265A4761998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Re Ginna Nuclear Power Plant.With 981210 Ltr ML17265A4691998-11-25025 November 1998 LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR ML17265A4531998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Re Ginna Nuclear Power Plant.With 981110 Ltr ML17265A4271998-10-0505 October 1998 LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr ML17265A4291998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Re Ginna Nuclear Power Plant.With 981009 Ltr 1999-09-30 |
Text
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ROC.4 ESTER GAS AND E: .'RIC CORPORATION e 69 EAST AVEN . ROCHESTER, H.Y.1W9 v e s s e. m , w
,, anta toet ne 540 2 7 D?
Cinna Statica -
September 26, 1974 _
Mr. James P. O'Reilly, Director Directorate of Regulatory Operations Region 1 U. S. Atomic Energy Co:Inis s ion 631 Park Avenue King of Prussia, Pennsylvania 19406 h
Subject:
Abnomal Occurrence 74-17: Violation of a limiting condition for operation as established in the Tech-nical Specifications by operating with the eccu=ulators low level below the 1008 cubic feet as established in _
Technical Specification 3.3.1.lb Dear Hr. O'Reilly.
This is to confire cy phone call to Mr. John Hannon yesterday to report Abnomal Occurreate 74-17 at Cirna Station.
After W siinghouse alerted us to the possibility that we might have a dis-crepancy in the volume of borated water in the accumulators at Ginna Statice, 7 an irrediate investigation was started.
7 At this tire, it appears that the ar.ount of borated water in the accumulatm e ha.* been between approxicately 970 cubic feet and 995 cubic feet, rather than the 1005 cubic feet and 1030 cubic feet as specified in the Ginna Station Technical Specifictstions.
Further investigations are continuing and the correct volure of borated watet will be established in each accumulator as soon as final accurate figures are available.
Your office will be kept infomcd as to the progr$ss of our investigations. -
Very truly yours, _
tdA!!.# ? ~
Charles E. Platt Superintendent CEP:fah i sr- Mr. J. P. O' Leary, AFL Hr. G. J.'Swarthout, RG6E ,
Mr. L. D. k'hite, Jr., PG&E -'
s
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