ML20084E930
From kanterella
Jump to navigation
Jump to search
| ML20084E930 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/07/1972 |
| From: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8304180674 | |
| Download: ML20084E930 (1) | |
Similar Documents at Oyster Creek | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20196H0111997-07-11011 July 1997
[Table view]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 Category:TEXT-SAFETY REPORT MONTHYEARML20217K4451999-09-30030 September 1999
[Table view]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 |
Text
r o
j / '
c
- v _
Jersey Central Power & Light Company M ADISoN AVENUE AT PUNCH BOWL RO AD e MoRRISToWN. N. J. 07960 e 539-611 I April 7, 1972 b, .
-9 Dr. Peter A. Morris, Director >
dpg2 Division of Reactor Licensing United States Atomic Energy Commission
-i
- 8g [A N l Wshington, D. C. 20545 JN 4 w}\ . wg
Dear Dr. Morris:
9s, @
Subject:
Oyster Creek Station Docket No. 50-219 Diesel Fire Pump Starting Failure The purpose of this letter is to report to you the failure of Diesel Fire Pump 1-2 to start during a surveillance test on l
March 21, 1972. &
1:
m This surveillance test consists of starting each pump from t the control room and again by lovering the fire pump discharge header . u, pressure. The pump started on the signal from the control room but /
did not start on the drop in header pressure. The operator in attendance observed that the diesel cranked very slowly. Each fire
( /'
pump is started by a starting motor driven electrically by a 24-volt DC battery. Each pump is equipped with two, 24-volt DC batteries either of which may be used for starting. Each battery is composed of two heavy-duty 12-volt batteries connected in series. The Shift Foreman on duty went to the fire pump location and by selecting the alternate battery for 1-2 pump, started the diesel although it cranked very slouly, it was determined later that each of the batteries serving the failed pump has one bad cell. The 12-volt batteries which had the baTcell were replaced with new batteries.
In the future, closer attention will be given to possible l
battery deterioration.
I Il 7 We are enclosing twenty-five copies of this report.
AN f Very truly yours,
! n. -
{l) . .. i
[f$l( 8304180674 720407 PDR ADOCK 05000219 v l' hIvan R. Finfr/..f'f(.l#'
ock,,Jr.
glI S PDR N nager, Nudicar Generating Stations IRF/ph ( [
Enclosures [
.j y,
cc: Mr. J . P. O'Reilly, Direc tor Division of Compliance, Region I bO COPY SENT REGION / A,
_
Retrieved from "https://kanterella.com/w/index.php?title=ML20084E930&oldid=2743739"