RO 82-1:on 820417,only One Dilution Pump Placed in Svc During Reactor Startup W/Ambient Water Temp Less than 60 F. Caused by Procedural Inadequacy.Procedure Revised to Require Two Pumps to Be in Operation During Startup| ML20053C920 |
| Person / Time |
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| Site: |
Oyster Creek |
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| Issue date: |
05/20/1982 |
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| From: |
GENERAL PUBLIC UTILITIES CORP. |
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| To: |
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| Shared Package |
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| ML20053C918 |
List: |
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| References |
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| RO-82-1, NUDOCS 8206030165 |
| Download: ML20053C920 (2) |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20196H0111997-07-11011 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
ML20129A3401996-10-15015 October 1996
Special Rept 96-001,rev 1:on 960806,stack Ragems High Range Monitor Was Removed from Svc & Not Restored to Svc in Seven Days.Caused by Malfunction of Interlock on Source. Interlock Components Replaced
ML20117K5931996-09-0505 September 1996
Special Rept SR 96-001:on 960806,declared Stack Ragems High Range Monitor Inoperable.Caused by Difficulties Requiring Component Replacement.Developed Course of Action for Returning Stack Ragems Instrument
ML20116B7521992-10-27027 October 1992
Special Rept 92-08:on 920929,Turbine Building High Radiation Noble Gas Monitor Declared Inoperable for Greater than Seven Days.Alternate Testing Performed Throughout Period of Inoperability
ML20115G6461992-10-22022 October 1992
Special Rept 92-07:on 921015,determined That Stem & Disc Separated on Discharge Valve V-9-004 for Diesel Fire Pump P-9-102A.On 921021,fire Pumps Isolated.Redundant Fire Pump Secured & Valves Replaced
ML20105A5121992-09-10010 September 1992
Special Rept 92-06:on 920807,fire Diesel Pump 1 Declared Inoperable for More than 7 Days to Perform Preventive Maint.On 920811,diesel Engine Overheated.Solenoid Valve Replaced & New Cooling Water Strainers Installed
ML20104B6081992-09-10010 September 1992
Special Rept 92-05:on 920727,condenser Bay Sprinkler Sys 2 Removed from Svc After Spurious Actuation of Sprinkler Head. Hourly Fire Watch Established While Sys Out of Svc.Sprinkler Head Replaced & Sys Returned to Svc on 920814
ML20114C5191992-08-26026 August 1992
Special Rept 92-03:on 920705,electromatic Relief Valve C Inadvertently Opened While Testing Pressure Switch of Valve A.Caused by Personnel Error.Training Session Will Be Held & Engineering Work Request Submitted Re Switch Terminal Point
ML20114A9701992-08-17017 August 1992
Special Rept 92-04:on 920724,fire Diesel Pump 2 Removed from Svc to Replace Battery Cables & Solenoid Valve.Correct 24 Volt Dc Coil Obtained from Mfg & Pump Returned to Svc on 920806
ML20096D4711992-05-0101 May 1992
Special Rept 92-02:on 920327,fire Diesel Pump 1 Out of Svc for More than 7 Days to Replace Pump Due to Marginal Discharge Pressure.Caused by Valve Seating Problem.Pump Replacement Expected to Be Completed by 920504
ML20100R7411992-04-10010 April 1992
Special Rept 92-01:on 920227,CO2 Fire Suppression Sys for 4,160-volt Switchgear Inoperable for More than 14 Days When Leaking Valve Stem Repaired on 920226.Possibly Caused by Moisture Intrusion.Corroded Components Replaced
ML20087B8431992-01-0303 January 1992
Special Rept 91-09:on 911115,fire Diesel Pump 1-2 Failed to Meet Required Acceptance Criteria During Functional Test. Caused by Cloth Rag Becoming Lodged Inside Pump.Fire Diesel Pump 1-2 Rebuilt & Reinstalled on 911208
ML20076E2641991-08-13013 August 1991
Special Rept 91-08:on 910717,coolant Found Leaking from Cap on Heat Exchanger of Engine of Fire Diesel Pump 1-1.Caused by Wearing on HX Neck,Resulting in HX Failing to Hold Normal Pressure.Engine Secured & Work Request Initiated
ML20076E3001991-08-12012 August 1991
Special Rept 91-07:on 910709,nonfunctional Fire Barrier Doors Between Fire Zones OB-FA-6 & TZ-FZ-11B Not Restored to Operable Status within 7 Days.Caused by Ventilation Flow Preventing Door from Closing.Fire Patrol Established
ML20077K2271991-07-31031 July 1991
Special Rept 91-06 Re Nonfunctional Fire Barrier Door Not Repaired within 7 Days as Required by Tech Spec 3.12.E. Caused by Broken Door Closure Mechanism.Hourly Fire Watch Initiated.Door Mechanism Repaired on 910704
ML20082E1411991-07-23023 July 1991
Special Rept:On 910702,non-functional Fire Barrier Door Not Repaired within Seven Days as Required by Tech Specs. Caused by Faulty Door Closing Mechanisms.Util Evaluating Alternate Door Closing Mechanisms
ML20073C9381991-04-18018 April 1991
Special Rept 91-04:on 910309,fire Detection Sys on Elevations 75' & 95' of Reactor Bldg Made Inoperable to Facilitate Maint Activities.Fire Watch Patrol Has Been Established to Compensate for Detection Sys
ML20070T5341991-03-28028 March 1991
Special Rept:On 910222,inoperable Fire Hose Station 33 Not Restored to Operable Status within 14 Days as Required by Tech Specs.Caused by Maint to Angle Valve.Valve Reopened on 910312,restoring Hose Station 33 to Operability
ML20070M5181991-03-14014 March 1991
Special Rept 91-02:on 901117,discovered That Fire Barrier Door Between 480-volt Switchgear Rooms a & B Nonfunctional Since 901110 & Not Repaired within 7 Days.Caused by Faulty Door Latching Mechanism.Fire Watch Established
ML20058A7441990-10-16016 October 1990
Special Rept 90-04:on 900921,nonfunctional Fire Barrier Door Not Repaired within 7 Days.Fire Watch Established
ML20245E7541989-06-0909 June 1989
Special Rept 89-02:on 890526,declared Fire Pump/Diesels 1-1 & 1-2 Inoperable.Caused by Loss of Fire Suppression Water. Pressure Switch & Associated Recorder for 1-2 Diesel Recalibrated Along W/Pump Discharge Pressure Gauge
ML20247J2081989-05-22022 May 1989
Special Rept 89-01:on 890422,nonfunctional Fire Barrier Not Repaired within 7 Days as Required by Tech Spec 3.12.E. Fire Watch Established.Nonfunctional Fire Barrier Seal Plannned to Be Restored to Operable Status by 890523
ML20237C6711987-12-11011 December 1987
Special Rept 87-08:on 871112,fire Diesel Pump 1-2 Not Restored to Functional Status within 7 Days.Caused by Constraints Imposed by Increased outage-related Maint Activities.Fire Diesel Pump Restored to Functional Status
ML20236S5201987-11-19019 November 1987
Special Rept 87-07:on 871020,nonfunctional Thermo Lag Fire Barrier Not Restored to Functional Status within 7 Days Per Tech Spec 3.12.E.Caused by Constraints Imposed by Increased Maint Activities.Fire Watch Established
ML20236L3711987-10-29029 October 1987
Special Rept 87-06:on 870928-30,fire Barrier Penetration Seals Identified as Not Meeting Acceptance Criteria.Cause Not Stated.Fire Watch Established Immediately.Fire Barrier Seals Will Be Restored to Functional Status by 871030
ML20235B4411987-09-22022 September 1987
Ro:On 870811,spill of Reactor Bldg Closed Cooling Water Occurred.Caused by Failure to Follow Instructions on Switching & Tagging Request Form Re Valve Backseating. Procedures Will Be Revised & Training Provided
ML20235G2151987-09-20020 September 1987
Ro:On 870911,w/reactor in Cold Shutdown Mode,Tech Spec Safety Limit 2.1.E Exceeded.Caused by Operator Error. Operators Received Training on Safety Limit,Applicable Procedures & Relevant Control Room Indications
ML20214H9801987-05-0707 May 1987
Ro:On 870424,operator Personnel Blocked Open Two Torus to Drywell Vacuum Breaker Valves at Time When Primary Containment Integrity Was Required.Caused by Cognitive Personnel Error.Procedures Revised
ML20215H3621987-04-0909 April 1987
Special Rept 87-02:on 870214,turbine Trip & Reactor Scram Occurred.Caused by Loose Wire Causing Loss of Feedwater Flow Signal.Following Reduction in Reactor Pressure All Electromatic Relief Valves Reseated Properly
ML20206E3931987-04-0101 April 1987
Special Rept 87-01:on 870302,inoperable Fire Suppression Water Deluge Sys Not Restored to Functional Status within 14 Days from Time of Discovery.Caused by Long Lead Time for Procurement of Replacement Parts
ML20209H2501987-01-23023 January 1987
Special Rept 86-017:on 861228,nonfunctional Fire Barrier Not Returned to Functional Status within 7 Days from Discovery.Hourly Fire Watch Established.Repairs Completed & Penetration Seal Restored to Functional Status on 870112
ML20207J2981986-12-17017 December 1986
Special Rept 86-16:on 861121,fire Barrier Door Between Monitor & Control Area Stairwell & Hallway Outside Cable Spreading Room Found Nonfunctional.Hourly Fire Watch Patrol Established.Door to Be Restored as Functional on 861222
ML20207J2821986-12-16016 December 1986
Special Rept 86-15:on 861110,penetrations Through Floor of 4160 Volt Switchgear 1D Vault & Floor of Motor Generator Set Room Found Degraded.As of 861117,penetrations Not Restored to Functional Condition.Hourly Fire Watch Patrol Initiated
ML20197B1471986-10-0909 October 1986
Special Rept 86-14:on 860922 & 27,nonfunctional Fire Barrier Penetration Seals Not Restored to Functional Status within 7 Days.Hourly Fire Watch Patrol Established within 1 H. Restoration Expected by 861130
ML20212D6251986-07-10010 July 1986
Special Rept 86-03:on 860616,two Hangers Supporting Ofc Bldg Fire Water Supply Riser Found to Need Repair.Riser Consequently Isolated,Rendering Sprinkler Sys 4 & 12 & Deluge Sys 4 Inoperable.Hangers Repaired & Sys Restored
ML20137U7031986-01-20020 January 1986
Fire Protection Special Rept 85-03:on 851216,insp of 14 Fire Dampers Identified Design or Installation Deficiencies Resulting in Dampers Being Determined Inoperable.Caused by Nonconforming as-found Fire Damper Configuration
ML20117C7451985-04-25025 April 1985
Special Rept 85-02:on 850225,electromatic Relief Valves NR-108B,NR-108C & NR-108D Failed to Fully Reseat After Initial Actuation,Per Tech Spec 6.9.3.f.Caused by Valve Design Deficiency.Design Change Considered
ML20102B8671985-02-21021 February 1985
Special Rept 85-01:on 850207,leakage Observed Around post-indication Valve V-9-13.Fire Suppression Water Sys Isolated on 850211 to Facilitate Valve Repair.Caused by Crack in Valve Body.Valve Replaced
ML20092N6351984-06-15015 June 1984
Special Rept 84-01:on 840606,post-indicating Valve V-9-12 Branching Off 14-inch Fire Water Main Damaged by Maint Vehicle,Resulting in Loss of Fire Suppression Water Sys. Caused by Lack of Protection Against Physical Damage
ML20083C6451983-12-0808 December 1983
RO 83-02T:on 831119,w/fire Pump 1-1 Out of Svc,Fire Pump 1-2 Failed to Start on Low Sys Pressure.Caused by Impeller Wear Rings Out of Tolerance on High End of Clearance Limits. Overspeed Trip Reset
ML20082R6551983-11-21021 November 1983
RO 83-02:on 831119,fire Pump 1-2 Failed to Start on Low Sys Pressure During Demand for Fire Water to Fill Isolated Portion of Underground Fire Suppression Pool.Caused Suspected to Be Faulty Overspeed Trip Switch.Switch Tested
ML20082L1491983-11-18018 November 1983
Followup RO 83-01:on 831103,fire Suppression Water Sys Declared Inoperable After Pump 1-1 Failed Testing.Mod Underway to Install New Pressure Relief Valves on Both Fire Pumps
ML20082B7921983-11-0404 November 1983
RO 83-01:on 831103,fire Suppression Water Sys Declared Inoperable Due to Smoke Emitting from Under Fire Pump 1-2 Pumphead During post-maint Inservice Test & Failed Design Rated Curve for Pump 1-1.Caused by Misadjusted Impeller
ML20082L5721983-09-15015 September 1983
Advises That Followup to RO 83-17 Re Diesel Generator Fast Start Surveillance Will Be Forwarded by 830921
ML20073A7071983-03-23023 March 1983
RO 83-4:on 830211,during Controlled Reactor Shutdown,One Dilution Pump Remained in Svc When Intake Canal Water Below Tech Spec Limit.Caused by Personnel Error.Procedures Will Be Revised to Provide More Explicit Directions
ML20071B0911983-02-14014 February 1983
RO 83-1-1:on 830113,dilution Pump 1-2 Removed from Svc. Caused by Insufficient Seal Water flow.Long-term Corrective Action Includes Program Designed to Improve Pump Reliability
ML20071B0951983-02-14014 February 1983
RO 83-2-1:on 830118,dilution Pump 1-1 Removed from Svc Due to Steam Around Flax Packing Gland.Caused by Wearing in of New packing.Long-term Corrective Actions Include Upgrading Dilution Pump Seal
ML20071B1021983-02-14014 February 1983
RO 83-3-1:on 830123,dilution Pumps 1-2 & 1-3 Tripped Off. Caused by Failed Electrical Terminations (Stress Cones). Terminations Replaced
ML20070P8361983-01-11011 January 1983
RO 82-8-2:on 821205,dilution Pump 1-3 Tripped,Leaving Dilution Pump 1-2 in Operation.Seal Water Pump Failed & Ambient Water Temp Fell Below Tech Spec Limit.Cause Unknown. Total Dilution Pump Refurbishment Program Initiated
ML20064E7271982-12-21021 December 1982
RO 82-7:on 821201,dilution Pump 1-3 Removed from Svc.Caused by Mud & Debris Clogging Grates,Blocking Water Flow to Dilution Pump.Mud & Debris Removed.Total Dilution Pump Refurbishment Program Planned
1997-07-11
[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
[Table view] |
Text
r-OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 j Nonroutine Environmental Operating Report No. 50-219 82-1 Report Date May 20,1982 Occurrence Date April 17,1982 Identification of Occurrence Exceeding a limiting condition as defined in the Environmental Technical Specifications, paragraph 2.1.4.3, when an insufficient number of dilution pumps were in operation as specified in paragraph 2.1.4.2. Less than two dilution pumps were operating for greater than 15 minutes, and the ambient water temperature was less than 600F.
This event is considered to be a Nonroutine Environmental Operating Report as defined in the Technical Specifications, Appendix "B", Paragraph 5.6.2.
Conditions Prior to Occurrence Increasing Power Dilution Pump Flow 2.60 E5 GPM Circulating Water Pump Flow 4.60 E5 GPM Dilution Pump 1-1 out of service for maintenance.
Prior to the occurrence, the ambient water temperature in the intake canal was 5 7. 50F. The condenser discharge water temperature was 63.0 F and the U.S.
Route 9 Discharge bridge temperature was 60.50F.
De scription of Occurrence i
At 0656 hours0.00759 days <br />0.182 hours <br />0.00108 weeks <br />2.49608e-4 months <br /> on April 17, 1982, the reactor scrammed. Prior to the reactor scram, dilution pumps 1-2 and 1-3 were operating. Reactor start up occurred at 2145 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.161725e-4 months <br /> on April 17, 1982, with only one dilution pump (#1-2) operating. A second dilution pump (#1-3) was not placed in service until 0825 hours0.00955 days <br />0.229 hours <br />0.00136 weeks <br />3.139125e-4 months <br /> on April 18, 1982.
i 8206030165 820520 PDR ADOCK 05000219 S PDR
Nonroutine Environmental Operating Report No. 50-219 82-1 Page 2 Apparent Cause of Occurrence Procedural inadequacy. Procedure 201.1 entitled " Approach to Critical" specifies that dilution pump (s) be put in service during reactor start up.
Ho wever, it gives no guidelines regarding the necessity of having two dilution pumps in operation when ambient water temperature is less than 600F or water temperature exceeds 870F at the U.S. Route 9 Bridge at Oyster Creek Analysis of Occurrence The continuous operation of the dilution pumps is required to maintain water temperatures within the specified limiting conditions. The objective of operating the dilution pumps in the prescribed manner is to minimize the occurrence of adverse biological effects in Oyster Creek and contiguous waters. Since the operation of an insufficient number of dilution pumps was of limited duration, there were no harmful marine biological effects observed.
Corrective Ac tion 4
Immediate corrective action involved putting dilution pump 1-3 in operation.
In addition, Procedure 201.1 ( Approach to Critical) has been revised such that it specifies that two dilution pumps shall be put into service prior to reactor start up when water temperature at the U.S. Route 9 Bridge exceeds 870F or ambient water temperature is less than 600F.
Long term corrective action also involves a total dilution pump improvement program designed to improve the reliability and operability of the pumps per a submittal to the Nuclear Regulatory Commission on July 1,1981. This improvement program includes upgrading of the dilution pump seal water and
, lubricating oil cooling water systems, pipe line strainers, pipe and heat tracing and overhaul of the dilution pumps. Material orders have been placed for the necessary parts, with delivery dates in advance of the start of the next refueling outage. In addition, a monitoring system will be installed that will specifically identify the cause of pump trips in order to effectively plan maintenance.
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