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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML19343C2181975-12-23023 December 1975 AO 50-219/75-33:on 751212,during 6-month Load Test on Station a batteries,125 Volt Dc Distribution Ctr de-energized.Caused by Personnel Error in Following Procedure.Distribution Ctr re-energized ML20090C9991975-12-12012 December 1975 AO 75-33:on 751212,125-volt Dc Distribution Ctr of Station a Battery Inadvertently de-energized.Caused by Failure to Establish Proper Breaker Lineup Preparation for Conducting Battery Load Test.Procedure changed.W/751219 Memo ML19343C2191975-12-11011 December 1975 AO 50-219/75-32:on 751203,during Testing,Emergency Diesel Generator 1 Failed to Start When Simulated Loss of Power Condition Applied to Fast Start Logic Circuit.Caused by Failure of Relay to Operate Due to Varnish on Armature ML20126E8281975-12-0303 December 1975 AO 50-219/75-31:on 751124,during Operability Test of Torus to Drywell Vacuum Breakers,Alarm Sys 2 Failed to Annunciate in Control Room When V-26-4 Opened.Caused by Failure of Relay Due to Contacts Being Detective.Relay Replaced ML20090D0071975-11-25025 November 1975 AO 75-31:on 751124,drywell Vacuum Breaker Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-4 Opened. Caused by Component Failure.Corrective Action Under Investigation ML20090D0161975-11-0707 November 1975 AO 75-30:on 751106,low Reactor Pressure Core Spray Valve Permissive Pressure Switches Re 17 a & C Tripped at Pressure Less than Min Required Value.Caused by Switch Repeatability.Pressure Switches Recalibr ML20090D0601975-11-0606 November 1975 AO 75-29:on 751027,torus Drywell Vacuum Breakers Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-8 Opened. Caused by Sticking Microswitch ML20090D0761975-10-28028 October 1975 AO 75-29:on 751027,torus to Drywell Vacuum Breaker Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-8 Opened.Caused by Component Failure.Corrective Action Under Investigation ML20090D0941975-10-24024 October 1975 AO 75-28:on 751015,standby Gas Treatment Sys 1 Inoperable. Caused by Air Solenoid Valve Coil Failure.Defective Solenoid Coil Replaced ML20090D1141975-10-17017 October 1975 AO 75-27:on 751008,low Reactor Pressure Core Spray Valve Permissive Pressure Switches RE17B & D Tripped at Pressure Less than Min Required Value.Caused by Switch Repeatability. Pressure Switches Recalibr ML20090D1041975-10-16016 October 1975 AO 75-28:on 751015,standby Gas Treatment Sys 1 Inoperable. Caused by Air Solenoid Valve Coil Failure.Defective Solenoid Coil replaced.W/751016 ML20090D1341975-10-0808 October 1975 AO 75-27:on 751008,low Reactor Pressure Core Spray Valve Permissive Pressure Switches RE17B & D Tripped at Pressures Less than Min Required Value.Caused by Switch Repeatability. Pressure Switches Recalibr ML20090D1501975-09-23023 September 1975 AO 75-26:on 750923,emergency Svc Water Pump 52C Failed to Start Automatically During Routine Surveillance Test of Containment Spray Sys Ii.Caused by Failure of Contact Switch in Time Delay Relay 16 K4B.Relay Replaced ML20090D2071975-09-0808 September 1975 AO 75-24:on 750829,electromatic Relief Valve Pressure Switches 1A83C & 1A83D Tripped at Pressures in Excess of Max Allowable Value.Caused by Instrument Setpoint Repeatability. Switches Reset ML19291C2641975-09-0808 September 1975 AO 73-19:when Closing Signal Was Applied to Breaker S1A,loss of Power Occurred at 4160-volt Ac Bus 1A Causing Trip of Various Pumps.Caused by Incorrect Setting of Current Transformer Ratio Matching Taps.Taps Set Properly ML20090D1941975-09-0808 September 1975 AO 75-25:on 750829,stack Gas Sample Sys Failed to Monitor Stack Releases Continuously While Reactor Was in Unisolated Condition.Caused by Malfunctioning Pump Lubricator.Thermal Overload Protection Reset ML20090D2151975-09-0202 September 1975 AO 75-24:on 750829,electromatic Relief Valve Pressure Switches 1A83C & 1A83D Tripped at Pressures in Excess of Max Allowable Value.Caused by Instrument Setpoint Repeatability. Switches Reset ML20090D2011975-09-0202 September 1975 AO 75-25:on 750829,stack Gas Sample Sys Failed to Monitor Stack Releases Continuously While Reactor Was in Unisolated Condition.Caused by Malfunctioning Pump Lubricator.Thermal Overload Protection Reset ML20090D2241975-08-21021 August 1975 AO 75-23:on 750817-20,stack Effluent for Iodine & Particulates Not Monitored.Caused by Personnel Error.Filter Installed in Operating Stack Gas Sampling Train ML20090D2261975-08-11011 August 1975 Preliminary AO-50-219/75-22:on 750810,stack Gas Sample Line Low Flow Alarm Received.Caused by Stack Gas Sample Pump a Not Running.Thermal Overload Protection Reset ML20090D2471975-08-0404 August 1975 Preliminary AO-50-219/75-21:on 750801,during Routine Surveillance on B Isolation Condensor Sys,Steam Line Valve V-14-32 Failed to Close on Simulation of Steam Line High Flow.Caused by Low Torque Switch Setting.Torque Increased ML20090D2521975-07-17017 July 1975 AO 50-219/75-19:on 750708,during Monthly Surveillance Test on Reactor High Pressure Scram Sensors,Re 03A,B,C & D, A,B & D Tripped Above Normal Trip Points.Caused by Switch Repeatability.Sensors Recalibr ML20090D2561975-07-0909 July 1975 Preliminary AO 50-219/75-19:on 750708,during Monthly Surveillance Test on Reactor High Pressure Scram Sensors,Re 03A,B,C & D,A,B & D Tripped Above Normal Trip Points.Caused by Switch Repeatability.Sensors Recalibr ML20084E1151975-07-0101 July 1975 RO 50-219/75-18:on 750623,two 8-1/2 Inch Handhole Covers in Standby Gas Treatment Filter Train Not in Place.Cause Unknown.Handhole Covers Repositioned & Secured ML20090D2741975-06-27027 June 1975 AO 50-219/75-17:on 750619,during Surveillance Test,Core Spray Sys Parallel Isolation Valve V-20-15 Failed to Demonstrate Operability.Caused by Broken Tab on B Phase of Valve Motor Breaker Stab.Stab Replaced ML20090D2661975-06-24024 June 1975 Preliminary AO 50-219/75-18:on 750623,handhole Covers in Standby Gas Treatment Filter Train 1-1 Not in Place.Cause Under Investigation.Covers Repositioned & Secured ML20090D2781975-06-24024 June 1975 AO 50-219/75-16:on 750614,electromatic Relief Valve Pressure Switches 1A83P & E Tripped at Pressures Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Switches Reset ML20090D2731975-06-19019 June 1975 Preliminary AO 50-219/75-17:on 750619,during Surveillance Test,Core Spray Sys Parallel Isolation Valve V-20-15 Failed to Demonstrate Operability.Caused by Broken Tab on B Phase of Valve Motor Breaker Stab.Stab Replaced ML20090D2901975-06-16016 June 1975 Preliminary AO 50-219/75-16:on 750614,electromatic Relief Valve Pressure Switches 1A83B & E Tripped at Pressure Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Switches Reset ML20090D6561975-06-0606 June 1975 AO-50-219/75-14:on 750529,during Surveillance Test of Containment Spray Pump Operability,Essential Svc Water Pump 1-2 Failed to Develop Sufficient Discharge Pressure.Caused by Dirt in Check Valve V-3-68.Valve Cleaned & Repaired ML20090D2971975-06-0606 June 1975 AO 50-219/75-15:on 750530,calculations of TIP Traces Indicated Total Peaking Factor in One Core Location in Excess of Value of Pf Given in Tech Specs.Caused by Lack of Operating Experience W/New Core Loading ML20090D2981975-06-0202 June 1975 Preliminary AO 50-219/75-15:on 750530,calculations of TIP Traces Indicated Total Peaking Factor in One Core Location in Excess of Value of Pf Given in Tech Specs.Caused by Lack of Operating Experience W/New Core Loading ML20090D6581975-05-30030 May 1975 Preliminary AO-50-219/75-14:on 750529,during Surveillance Test of Containment Spray Pump Operability,Essential Svc Water Pump 1-2 Failed to Develop Sufficient Discharge Pressure.Caused by Dirt in Check Valve V-3-68.Valve Cleaned ML20090D6611975-05-14014 May 1975 AO-50-219/75-13:on 750507,during Surveillance Test,Time Delay Relay 6Kll Failed to de-energize within 15 After Pressure Sensor RE-15C Tripped.Caused by Component Failure.Relay 6Kll Replaced ML20090D6641975-05-0707 May 1975 Preliminary AO-50-219/75-13:on 750507,during Surveillance Test,Time Delay Relay 6Kll Failed to de-energize within 15 After Pressure Sensor RE-15C Tripped.Caused by Component Failure.Relay 6Kll Replaced ML20090D6531975-05-0606 May 1975 AO-50-219/75-12:on 750426,low Reactor Pressure Core Spray Valve Permissive Pressure Switches Re 17B & C Found to Trip at Pressure Less than Tech Spec Value.Caused by Switch Repeatablilty.Switches Recalibr ML20090D6701975-04-28028 April 1975 Preliminary AO-50-219/75-12:on 750426,low Reactor Pressure Core Spray Valve Permissive Pressure Switches Re 178 & C Found to Trip at Pressure Less than Tech Spec Value.Caused by Switch Repeatability.Switches Recalibr ML20090D6751975-04-18018 April 1975 AO-50-219/75-11:on 750410,leakage of Main Line Drain & Bypass Line Exceeded Tech Spec Rate.Caused by Failure of Packing on Valve V-1-110.Valve to Be Repacked ML20090D7001975-04-14014 April 1975 AO-50-219/75-10:on 750404,reactor Bldg to Torus Vacuum Breaker Valves V-26-16 & 18 Leak Rates Exceeded Tech Spec Limits.Caused by Component Failure.Valves Adjusted &/Or Repaired ML20090D6811975-04-11011 April 1975 Preliminary AO-50-219/75-11:on 750410,leakage of Main Line Drain & Bypass Line Exceeded Tech Spec Rate.Caused by Failure of Packing on Valve V-1-110.Valve to Be Repacked ML20090D7131975-04-0808 April 1975 AO-50-219/75-09:on 750329,breaker 1C Tripped Resulting in Fault on Bus 1C.Caused by Fault on Cable 86-25.Cables Replaced ML20090D7061975-04-0707 April 1975 Preliminary AO-50-219/75-10:on 750404,reactor Bldg to Torus Vacuum Breaker Valves V-26-16 & 18 Leak Rates Exceeded Tech Spec Limits.Caused by Component Failure. Valves Adjusted &/Or Repaired ML20090D7271975-04-0303 April 1975 AO-50-219/75-08:on 750325,power Operation Continued W/ Average Linear Heat Generation Rate of Fuel Assemblies in Excess of Max Linear Heat Generation Rate.Caused by Failure to Properly Monitor Reactor Core.Rate Reduced ML20090D7211975-03-31031 March 1975 Preliminary AO-50-219/75-09:on 750329,breaker 1C Tripped Due to Fault on Bus 1C.Caused by Fault on Cable 86-25.Cables Replaced ML20090D7651975-03-27027 March 1975 AO-50-219/75-07:on 750319,during Standby Gas Treatment Sys (SGTS) Test,Dehumidifying Heater EHC-1-5 in SGTS 1 Failed to Energize.Caused by Plugged Orifice in Air Supply to Controller.New Type of Differential Relay Installed ML20090D7361975-03-26026 March 1975 Preliminary AO-50-219/75-08:on 750325,power Operation Continued W/Average Linear Heat Generation Rate of Fuel Assemblies in Excess of Max Linear Heat Generation Rate. Caused by Improper Reactor Core Monitoring.Rate Reduced ML20090D7761975-03-20020 March 1975 Preliminary AO-50-219/75-07:on 750319,during Stanby Gas Treatment Sys (SGTS) Test,Dehumidifying Heater EHC-1-5 in SGTS 1 Failed to Energize.Caused by Plugged Orifice in Air Supply to Controller.New Type of Relay Installed ML20090D7801975-03-19019 March 1975 AO-50-219/75-06:on 750310,stack Gas Sample Sys Failed to Continuously Monitor Stack Releases While Reactor in Unisolated Condition.Caused by Circuit Design.Request to Modify Circuit for Stack Gas Sample Pumps Submitted ML20090D7901975-03-13013 March 1975 AO-50-219/75-05:on 750306,during Monthly Surveillance Test, Containment Spray Pump 51A Failed to Start When Subjected to Simulated Signals.Caused by Breaker Trip Bar Failing to Reset After Previous Breaker Trip.Trip Bar Bushings Cleaned ML20090D7811975-03-11011 March 1975 Preliminary AO-50-219/75-06:on 750310,stack Gas Sample Sys Failed to Monitor Stack Releases While Reactor in Unisolated Condition.Caused by faulty-circuit Design 1975-09-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4451999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Oyster Creek Nuclear Generating Station.With ML20211P6731999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Oyster Creek Nuclear Generating Station.With ML20211A7051999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Oyster Creek Nuclear Station.With ML20209G0631999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Oyster Creek Nuclear Generating Station.With ML20212H5491999-06-18018 June 1999 Non-proprietary Rev 4 to HI-981983, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool ML20195E7961999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Oyster Creek Nuclear Generating Station.With ML20206N7431999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Oyster Creek Nuclear Generating Station.With ML20205P5401999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Oyster Creek Nuclear Generating Station.With ML20204C8201999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Oyster Creek Nuclear Generating Station.With ML20199E4671998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Oyster Creek Nuclear Generating Station.With ML20195E8321998-12-31031 December 1998 10CFR50.59(b) Rept of Changes to Oyster Creek Sys & Procedures, for Period of June 1997 to Dec 1998.With ML20198D2091998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Oyster Creek Nuclear Generating Station.With ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20195C4271998-11-0606 November 1998 Safety Evaluation Supporting Proposed Ocnpp Mod to Install Core Support Plate Wedges to Structurally Replace Lateral Resistance Provided by Rim Hold Down Bolts for One Operating Cycle ML20155J3021998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Oyster Creek Nuclear Generating Station.With ML20154R4981998-10-20020 October 1998 Core Spray Sys Insp Program - 17R ML20154L3051998-10-14014 October 1998 Safety Evaluation Accepting Licensee Request to Defer Insp of 79 Welds from One Fuel Cycle at 17R Outage ML20154Q3371998-09-30030 September 1998 Rev 8 to Oyster Creek Cycle 17,COLR ML20154L5571998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Oyster Creek Nuclear Generating Station.With ML20151V6311998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Oyster Creek Nuclear Generating Station.With ML20237D5691998-08-31031 August 1998 Rev 0 to MPR-1957, Design Submittal for Oyster Creek Core Plate Wedge Modification ML20237D5711998-08-18018 August 1998 Rev 0 to SE-000222-002, Core Plate Wedge Installation ML20237B0131998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Oyster Creek Nuclear Generating Station ML20236R0511998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Oyster Creek Nuclear Generating Station ML20249B2981998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Oyster Creek Nuclear Station 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 ML20247F1891998-05-0505 May 1998 Risk Evaluation of Post-LOCA Containment Overpressure Request ML20247G0581998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Oyster Creek Nuclear Generating Station ML20216K0341998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Oyster Creek Nuclear Generating Station ML20151Y4651998-03-31031 March 1998 Non-proprietary Version of Rev 1 to GENE-E21-00143, ECCS Suction Strainer Hydraulic Sizing Rept ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216J0841998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Oyster Creek Nuclear Generating Station ML20203B2781998-02-16016 February 1998 10CFR50.59(b) Rept of Changes to Oyster Creek Systems & Procedures ML20203A3801998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Oyster Creek Nuclear Generation Station ML20198P1791997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Oyster Creek Nuclear Station ML20217C7591997-12-31031 December 1997 1997 Annual Environmental Operating Rept for Oyster Creek Nuclear Generating Station ML20197E9131997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Oyster Creek Nuclear Station ML20199E4561997-11-13013 November 1997 Safety Evaluation Accepting Ampacity Derating Analysis in Response to NRC RAI Re GL-92-08, Thermo-Lag 330-1 Fire Barriers, for Plant ML20199D4381997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Oyster Creek Nuclear Station ML20202E8511997-10-21021 October 1997 Rev 0 to Scenario 47, Gpu Nuclear Oyster Creek Nuclear Generating Station Emergency Preparedness (Nrc/Fema Evaluated) 1997 Biennial Exercise. Pages 49 & 59 of Incoming Submittal Were Not Included ML20211M9481997-10-0303 October 1997 Supplemental Part 21 Rept Re Condition Effected Emergency Svc Water Pumps Supplied by Bw/Ip Intl Inc to Gpu Nuclear, Oyster Creek Nuclear Generation Station.No Other Nuclear Generating Stations Effected by Notification ML20198J7361997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Oyster Creek Nuclear Generating Station ML20211B7461997-09-24024 September 1997 Part 21 Rept Re Failure of Emergency Service Water Pump Due to Threaded Flange Attaching Column to Top Series Case Failure.Caused by Dissimilar Metals.Pumps in High Ion Svc Will Be Upgraded to 316 Stainless Steel Matl ML20210V0181997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Oyster Creek Nuclear Generating Station ML20210L2961997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Oyster Creek Nuclear Station ML20149F9961997-07-18018 July 1997 Safety Evaluation Re Gpu Nuclear Operational Quality Assurance Plan,Rev 10 for Three Mile Island Nuclear Generating Station,Unit 1 & Oyster Creek Nuclear Generating Station ML20196H0111997-07-11011 July 1997 Special Rept 97-001:on 970620,removed High Range Radioactive Noble Gas Effluent Monitor (Stack Ragems) from Service to Allow Secondary Calibr IAW Master Surveillance Schedule. Completed Calibr on 970628 & Returned Stack Ragems to Svc ML20210L3081997-06-30030 June 1997 Corrected Page to MOR for June 1997 for Oyster Creek Nuclear Generating Station ML20141H2051997-06-30030 June 1997 Monthly Operating Rept for June 1997 for Oyster Creek Nuclear Station 1999-09-30
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Dear Mr. Giambusso:
. Subj ect: Oyster Creek Station Docket No. 50-219 Power Failure The purpose of this letter is to report a violation of the Technical Specifications, paragraph 3.7.A.2., in that although both startup transformers were energized to carry power to the station 4160V AC buses, neither transformer could be considered operable due to an improper setting on the C phase differ-ential monitoring relays. Further, during the event, neither diesel generator was able to restart after having once been initiated in the " fast start" mode and been secured when power was again lost to the 4160V AC buses.
These situations are considered to be abnormal occurrences as defined in the Technical Specifications, paragraph 1.15.D. (failure of one or more compo-nents or an engineered safety feature that causes the feature to be incapable of performing its intended function) and 1.15.G. (observed inadequacies in the imple-mentation of procedural controls such that the inadequacy causes the existence or development of an unsafe condition in connection with the operation of the plant).
Notification of this event, as required by the Technical Specifications, paragraph 6.6.2.a. , was made to AEC Region I, Directorate of Regulatory Operations, by telephone on September 8,1973, and further elaborated upon personally with Mr. B. Greenman from AEC Region I, Directorate of Regulatory Operations on Septem-ber 11, 1973 during his visit to the site. Further, the problem with the start-up transformers was telecopied to AEC Region I on September 10, 1973, and the difficulty experienced with the diesel generators was telecopied on September 13, 1973. .
A plant shutdown had progressed to the point where, with electrical
- output at approximately 90 MWe, a transfer of station loads from the auxiliary transformer to the startup transformers was attempted. When a closing signal was applied to the SIA breaker, a loss of power occurred on the 1A 4160V AC bus which, among other things, caused two circulating water pumps, three reactor recirculation pumps, and the operating condensate and feedwater pumps to trip. Diesel generator 8/O3040 % 3
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Mr. Giambusso Septeder 18, 1973 1
No. I was initiated in the " fast start" mode, reenergizing the IC 4160V AC bus, restoring power to the requisite safeguard systems should they have been re-quired. An attempt was made to start the B and C condensate pumps, but before either pump could be started, the reactor scrammed due to low water level. In reconstructing the subsequent events, the following seems pertinent:
- 1. Following the scram, the IB 4160V AC bus was energized properly from the SB transformer.
- 2. The " lockout" relay, 86SA, was reset manually, the SIA breaker was closed, diesel generator No. I was synchronized with " system",
and the IC breaker was closed.
- 3. Diesel generator No. I was secured. At this time, the " trouble" alarm was annunciated in the control room and an electrician was dispatched to determine the cause.
- 4. An attempt was made to start the A condensate pump, but the in-rush current apparently tripped S1A breaker. Diesel generator No. I was not initiated in the " fast start" mode due to the engine
" lockout" relay whi< h has previously been actuated (the cause from the " trouble" alarm) .
- 5. An attempt was made to start the B or C condensate pumps, but the in-rush current apparently tripped the S1B breaker. Diesel generator No. 2 was initiated in the " fast start" mode reenergizing the ID 4160V AC bus. For the period of time taken for diesel generator No. 2 to come up to speed, buildup voltage and reenergize the bus (less than 15 seconds), the station was without AC power.
- 6. Both the SA and SB transformer " lockout" relays were reset manually and both SIA and SIB breakers were closed.
- 7. Diesel generator No. I was initiated in the " fast start" mode when the electrician reset the engine " lockout" relay.
- 8. Diesel generator No. 2 was synchronized with " system", the ID breaker closed, and the diesel generator was secured. Upon securing the unit, the " trouble" alarm was annunciated (apparently due to the engine " lockout" relay being activated) . The electrician was advised of the situation.
- 9. Again, an attempt was made to start the B or C condensate pumps with the same results as befbre. Ilowever, diesel generator No. 2 failed to start.
i 10. The electrician reset the engine " lockout" relay for diesel generator No. 2 and the unit was initiated in the " fast start" mode.
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O' L, Mr. Giambusso September 18, 1973
- 11. With two CRD pumps running, the control rod drive system hydraulic control station bypass valve was . opened to assist in the recovery of reactor water level. The minimum level reached, as recorded by the feedwater control system level recorder, was 9' above the core, l' 10" above the actuation point for initiating the core spray system and isolating the reactor.
- 12. The MSIV's were closed by the operator and the isolation condensers were manually initiated to eliminate the water inventory loss from the vessel and to provide for decay heat removal.
The problem experienced with the startup transformer breakers SIA and SIB was traced to an incorrect setting of the current transformer ratio matching taps for the C phase differential relay on both units. In attempting to either carry a sizeable load and/or start a large load, a differential fault current based upon the improper tap setting was sensed, tripping the bus supply breakers.
! Relay nomenclature is as follows:
Manufacturer: General Electric Model No.: 12BDD15&11A 5 amps, 60 cycles, 125-250 DC Control Volts i-The problem experienced with the diesel generators was identified to be as a result of relay contact actuation which is inherent in the design of the circuit (see Figure 1). When the unit is initiated in the " fast start" mode, power to the engine fault circuit ia cut off. With the unit at speed, the OAD relay is energized closing contacts in the engine " lockout" circuit. Under normal conditions, i
the bearing oil pressure switch would be closed, enabling the MBR relay to be i energized, opening a contact in the engine " lockout" circuit. However, that relay could not be energized due to the opened " fast start" relay contacts and consequently the bearing oil pressure contacts remained closed. When the unit was secured, j the " fast start" relay was deenergized, closing the " fast start" relay contacts.
Before the MBR relay could be energized and its respective contacts opened in the engine " lockout" circuit, the " lockout" relay was actuated which prevented a
; subsequent start. The engines would remain locked out until the relays could be manually reset locally, as was the case.
P The current transformer ratio matching taps were set up properly and station loads were returned to normal. This action was completed by 8:30 a.m.
The ' company Relay Department was contacted and load checks were conducted on each !
' of the transformer phase differential relays. All checks were satisfactory. As regards to the diesel generator problem, during the loss of power conditions, the
" lockout" relays were reset allowing the units to restart. A " fast start" test -
of diesel generator No. I was subsequently conducted while monitoring the engine :
fault relay circuitry, turning up the problem as previously discussed. General Motors.has been contacted with regards to a modification which could be made to the circuit to circumvent the problem.
. The designed redundancy for the station vital power supplies (i.e. ,
off-site power and diesel generators) was not present and, in fact, had not been ,
present since July 30, 1973, when a test of the startup transformer phase differ- i 2
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i l Mr. Giambusso September 18, 1973 ential relays had been conducted. Under a bona-fide loss of power condition, both diesel generators would have performed their intended function and, in fact, did since both units t Ltuated to energize their respective buses upon initially sensing undervoltage. Ilowever, had a problem arisen, which required a subsequent " fast start" immediately after the units had been secured from a " fast start", such as occurred here, no AC power would have been available to power any necessary safe-guards equipment until the engine " lockout" relays could be reset.
To prevent a reoccurrence of this tyTe event, the following actions are being taken:
- 1. Prepare procedures, in conjunction with the Relay Department, for all Relay Department work in the Oyster Creek plant. All work in the future will be coordinated with the shift foreman.
- 2. Prepare a design change to the diesel generator logic circuits to prevent lockout following shutdown of the diesel. General Motors will be contacted for recommendations.
- 3. Review and revise Procedure No. 511 " Loss of Feedwater System" as required.
We are enclosing forty copics of this report.
Very truly yours, 7
Donald A. Ross l Manager, Nuclear Generating Stations es Enclosures cc: Mr. J. P. O'Reilly, Director Directorate of Regulatory Operations, Region I
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