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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000278/LER-1993-0061993-09-0303 September 1993 LER 93-006-00:on 930814,LPCI Sys Became Inoperable When Triple Low Water Level Signal Simulated on Unit 2.RWL Instrumentation LT-72B Valved Out of Svc & Equalized Allowing Indicated Water Level to increase.W/930903 Ltr 05000278/LER-1993-0051993-09-0303 September 1993 LER 93-005-00:on 930809,HPCI Sys Declared Inoperable Due to Defective Flow Controller.Flow Controller Removed,All Potentiometers & Boards Cleaned,Flow Controller Reinstalled & Necessary Testing & Tuning performed.W/930903 Ltr 05000278/LER-1993-0041993-08-30030 August 1993 LER 93-004-00:on 930730,simulated Low Steam Flow Signal to Recombiner Initiated Isolation Signal to Off Gas Recombiner, Causing Main Condenser Vacuum to Begin Decreasing.Special Procedure SP-1438 revised.W/930830 Ltr 05000277/LER-1990-0141990-07-19019 July 1990 LER 90-014-00:on 900620,RWCU Isolation Occurred During Pressurization of Sys Following Isolation Valve Maint.Caused by Design Weakness.Design of Instrumentation Reviewed & Procedural Controls enhanced.W/900719 Ltr 05000278/LER-1990-0071990-07-18018 July 1990 LER 90-007-00:on 900620,RWCU Isolated While Pressurizing Sys Following Isolation Valve Insp.Caused by Design Weakness. Design of Instrumentation Reviewed & Procedural Controls enhanced.W/900719 Ltr 05000277/LER-1990-0131990-06-27027 June 1990 LER 90-013-00:on 900530,failure to Perform Tech Spec Surveillance Tests Since 891130 Discovered.Caused by Incorrect Std Practice.Tests Revised to Clarify Testing Requirements of Tech Spec 4.14.C.1.c.W/900627 Ltr 05000277/LER-1989-006, Corrected LER 89-006-00:on 890209 & 25,determined That Tubing to Containment Isolation Valve Installed W/Inadequate Support & Containment Atmosphere Control & Dilution Sys Not Per Applicable Installation Criteria.Controls Estab1989-05-0909 May 1989 Corrected LER 89-006-00:on 890209 & 25,determined That Tubing to Containment Isolation Valve Installed W/Inadequate Support & Containment Atmosphere Control & Dilution Sys Not Per Applicable Installation Criteria.Controls Established 05000277/LER-1989-007, Corrected LER 89-007-00:on 890411,green Discoloration Discovered in Grease on Stabs of Control Fuses in Switchgear.Root Cause of Event Under Investigation.Stabs Lubricated W/Different Type of Approved Grease1989-05-0909 May 1989 Corrected LER 89-007-00:on 890411,green Discoloration Discovered in Grease on Stabs of Control Fuses in Switchgear.Root Cause of Event Under Investigation.Stabs Lubricated W/Different Type of Approved Grease 05000277/LER-1987-016, Corrected LER 87-016-00:on 870820,isolations Occurred When Four of Eight 4 Kv Emergency Transformers Momentarily de-energized.Caused by Inadequate Concern for Potential Electrical Hazard by Maint Craft Supervision1987-09-28028 September 1987 Corrected LER 87-016-00:on 870820,isolations Occurred When Four of Eight 4 Kv Emergency Transformers Momentarily de-energized.Caused by Inadequate Concern for Potential Electrical Hazard by Maint Craft Supervision 05000277/LER-1984-008, Revised LER 84-008-01:on 840427,standby Gas Treatment Sys Solenoid Valve SV-00009 Failed to Operate Properly, Preventing Fan a Inlet & Outlet Dampers from Opening.Cause of Solenoid Failure Under Investigation1984-07-24024 July 1984 Revised LER 84-008-01:on 840427,standby Gas Treatment Sys Solenoid Valve SV-00009 Failed to Operate Properly, Preventing Fan a Inlet & Outlet Dampers from Opening.Cause of Solenoid Failure Under Investigation 05000278/LER-1984-001, Revised LER 84-001-02:on 840106,turbine Exhaust Rupture Diaphragm Alarm Annunicated Following Startup of HPCI Turbine.Caused by Rupture of Inner Rupture Disc.Inner Rupture Disc Replaced1984-06-0101 June 1984 Revised LER 84-001-02:on 840106,turbine Exhaust Rupture Diaphragm Alarm Annunicated Following Startup of HPCI Turbine.Caused by Rupture of Inner Rupture Disc.Inner Rupture Disc Replaced 05000277/LER-1984-003, Revised LER 84-003-01:on 840131,heatup Rate Exceeded Tech Spec Limits.Caused by Personnel Error.Operator Disciplined. Memo Issued to All Licensed Operators Re Tech Spec Rate1984-05-0303 May 1984 Revised LER 84-003-01:on 840131,heatup Rate Exceeded Tech Spec Limits.Caused by Personnel Error.Operator Disciplined. Memo Issued to All Licensed Operators Re Tech Spec Rate 05000278/LER-1983-018, Updated LER 83-018/03X-1:on 831117,control Rods 34-35 & 34-7 34-27 Exceeded Allowable Scram Insertion Time of 7 S.Caused by Failure of Scram Solenoid Valve in Both Hydraulic Control Units.Solenoids Replaced1984-02-10010 February 1984 Updated LER 83-018/03X-1:on 831117,control Rods 34-35 & 34-7 34-27 Exceeded Allowable Scram Insertion Time of 7 S.Caused by Failure of Scram Solenoid Valve in Both Hydraulic Control Units.Solenoids replaced.W/840210 Ltr 05000278/LER-1983-008, Followup LER 83-008/01X-1:on 830214,during Refueling Outage, Surveillance Testing Indicated Combined Leakage for Listed Valves Exceeded Limits or Failed to Meet Requirements.Caused by Seat Surface Degradation1983-09-13013 September 1983 Followup LER 83-008/01X-1:on 830214,during Refueling Outage, Surveillance Testing Indicated Combined Leakage for Listed Valves Exceeded Limits or Failed to Meet Requirements.Caused by Seat Surface Degradation 05000278/LER-1982-022, Revised LER 82-022/01X-1:on 821025-1102,RHR HX 3D Leaked Slightly Radioactive Water Into Intake Structure.Caused by Expansion Bellows Leak Between Inner Floating Head & Drain. HX Repaired1983-01-11011 January 1983 Revised LER 82-022/01X-1:on 821025-1102,RHR HX 3D Leaked Slightly Radioactive Water Into Intake Structure.Caused by Expansion Bellows Leak Between Inner Floating Head & Drain. HX Repaired 05000277/LER-1982-030, Telecopy Message of LER 82-030/01P:on 820917,contaminated Water Released from Recombiner Bldg Into Storm Drain Sys. Caused by Spurious Actuation of Fire Protection Sprinkler Sys in B Filter Train of Exhaust Ventilation Sys1982-09-21021 September 1982 Telecopy Message of LER 82-030/01P:on 820917,contaminated Water Released from Recombiner Bldg Into Storm Drain Sys. Caused by Spurious Actuation of Fire Protection Sprinkler Sys in B Filter Train of Exhaust Ventilation Sys 05000278/LER-1982-0111982-07-13013 July 1982 LER 82-011/03L-0:on 820620,fuse on Positive Leg to Transmitter Circuit Board Blew Causing Downscale Failure of Drywell 0-70 Psig Pressure Recorder.Caused by Intentional Ground Installed on Positive of Transmitter.Fuse Replaced 05000278/LER-1982-0101982-07-13013 July 1982 LER 82-010/03L-0:on 820618,downscale Failure of Drywell 0-70 Psig Pressure Recorder Occurred.Caused by Blown 0.3 Ampere Fuse Installed on Positive Side of Power Supply to Transmitter Circuit Board.Fuse Replaced 05000277/LER-1982-0161982-07-13013 July 1982 LER 82-016/01P:on 820709,equalizing Valve on Main Steam Line a High Flow Transmitter (Dpis 116B) Found Open.Cause Under Investigation.Valving of Instrument Performance Verified 05000277/LER-1982-0131982-07-0808 July 1982 LER 82-013/03L-0:on 820608,while Filling Diesel Generator Carbon Dioxide Fire Suppression Sys Storage Tank,Tank Pressure Dropped Below Tech Spec Limit.Caused by Venting Tank Vapor Space to Atmosphere Instead of Delivery Truck 05000277/LER-1982-0151982-07-0606 July 1982 LER 82-015/1P:on 820703,main Steam Line Flow Transmitter D & 1 of 4 Main Steam Line High Flow Transmitters Found W/Open Equalizing Valves.Cause Under Investigation.Valving of Instruments Verified 05000278/LER-1982-0091982-06-28028 June 1982 LER 82-009/03L-0:on 820530,operator Lost Valve Indication Position on HPCI Sys.Caused by Blown Fuse in Instrument Panel Due to Shortened Solenoid Coil in Turbine Exhaust Drain Valve.Fuse Replaced & Valves Stroked 05000278/LER-1982-0071982-06-21021 June 1982 LER 82-007/03L-0:on 820519,during Operability Testing,Hpci Steam Inlet valve,MO-14,blew Fuses When Stroked & Turbine Stop valve,HO-5513,failed to Close in Response to Remote Trip Signal.Steam Inlet Valve Repacked & Switch Replaced 05000278/LER-1982-0051982-06-14014 June 1982 LER 82-005/03L-0:on 820514,during Normal Operation,Reactor Operator Heard Relay in Primary Containment Isolation Sys Energize.Caused by Defective Component in Rosemount Model 510DU Slave Trip Unit.Instrument Replaced 05000277/LER-1982-0121982-06-11011 June 1982 LER 82-012/03L-0:on 820517,pressure Drop Across Combined HEPA Filters & Charcoal Absorber Banks in Control Room Emergency Ventilation Sys Exceeded Tech Spec Limits.Caused by Pin on Connecting Linkage of Damper OBV-30 Falling Out 05000277/LER-1982-010, Sanitized Version of LER 82-010/01X-0:on 820413,Eberline Instrument Corp Reported 9.175 Rem Exposure to TLD Badge. Caused by Deliberate Tampering W/Badge Found Near Radiation Source.Individual Denied Access to Site1982-05-13013 May 1982 Sanitized Version of LER 82-010/01X-0:on 820413,Eberline Instrument Corp Reported 9.175 Rem Exposure to TLD Badge. Caused by Deliberate Tampering W/Badge Found Near Radiation Source.Individual Denied Access to Site 05000277/LER-1982-008, Revised LER 82-008/01X-1:on 820328,auxiliary Boiler Operated on Diesel Fuel 2 Instead of Fuel Oil 6,decreasing Diesel Fuel Inventory Below Tech Spec Limit of 104,000 Gallons. Caused by Failure to Monitor Fuel Tank Inventory1982-04-15015 April 1982 Revised LER 82-008/01X-1:on 820328,auxiliary Boiler Operated on Diesel Fuel 2 Instead of Fuel Oil 6,decreasing Diesel Fuel Inventory Below Tech Spec Limit of 104,000 Gallons. Caused by Failure to Monitor Fuel Tank Inventory 05000277/LER-1982-0061982-04-12012 April 1982 LER 82-006/03L-0:on 820313,during Surveillance Testing of Fire Protection Sys,Diesel Fire Pump Tripped Off on Overspeed Condition.Caused by Defective Overspeed Control Switch.Defective Switch Replaced ML20064J1791978-12-20020 December 1978 /03L-0 on 781127:D Reactor Bldg Area Exhaust Radiat Monitor Indicated Downscale & Was Determined to Be Inoperable.Caused by Defective Zener Diode in Amplifier of GE sensor-converter Unit,Model 194X927011 ML20062E8681978-12-0606 December 1978 /03L-0 on 781117:output Demand Signal from RCIC Flow Controller (Inst HCS213-115) Read Down Scale.Caused by Open Circuit in Controller Demand Current Loop ML20062E8741978-12-0404 December 1978 /03L-0 on 781102:during Third Refueling Outage, Failed to Remove Neutron Flux Samples from Reactor Vessel. Caused by Administrative Oversight.Eval of Sample Removal Prog Is in Progress ML20064F1111978-11-20020 November 1978 /01T-0 on 781106:while at Pwr Feedwater Control Sys Failure Resulted in Reactor Low Level Transient & Scram HPCI Initiated But Delivered Unstable Flow & Soon Tripped on Overspeed.Cause Was HPCI Governor Being Out of Calibr ML20062D6351978-11-20020 November 1978 /03L-0 on 781021:during Startup,Excessive Oper of HPCI Gland Seal Condensate Pump Was Noted.Check Valve 2-23-131 Was Leaking Which Let Condensate Return to Gland Seal Condenser.Valves Were Blocked to Facilitate Repair ML20062C9961978-11-0808 November 1978 /03L-0 on 781019:during start-up,inboard Main Steam Line Drain Isolation Valve MO-2-74 Would Not Close in Response to Hand Switch in Control Room,Due to Defective Limitorque SMB-000 Torque Switch on the Valve ML20062C5471978-11-0101 November 1978 /01T-0 on 781019:unit 3 Containment Oxygen Concentration Had Increased to 0.1% Above 4 Percent Limit of Tech Spec 3.7.A.5.Caused by Open Air back-up Valves in Inoperable Instru Nitrogen Compressor ML20062C5381978-10-24024 October 1978 /01T-0 on 781010:2 4KV Emergency Bus Sequential Loading Relays Found Outside Tech Spec Limits.Caused by Error in Determining Setpoint & Calibr Span of Relays.Relays Recalib & Testing Procedures Revised ML20062A3801978-10-0404 October 1978 /03L-0 on 780904:backflow of Radioactive Liquid from Radwaste Demineralizers to Svc Air Sys Discovered on 780904 & 780921.Caused by Leaking Process Valves & Associated Check Vlaves Due to Dirt Deposits ML20147B2321978-09-29029 September 1978 /03l-0 on 780830:E-3 Diesel Start Time to Reach Rated Voltage & Frequency Did Not Meet Surveillance Test Requirement,Probably Caused by Leaking Check Valve in the Hydraulic Sys Assoc W/The Air Booster Relay ML20064B7541978-09-26026 September 1978 /03L-0 on 780901:failure of Auxiliary Oil Pump to Start Due to a Ground in Motor.Motor,Baldor Type 1040D, 7 1/2 H.P.,25OV.D.C. Was Replaced & HPCI Sys Tested Satisfactorily W/In 36 Hours.Ads Timers Not W/In Tech Specs ML20064B7521978-09-26026 September 1978 /03L-0 on 780904:during Surveillance Test Unit 3 Dmain Steam Radiat Monitor Failed to Cause a Half Scram Due to Defective Transistor.Transitor Was Replaced & Monitor Returned to Svc in 6 Hours ML20064B7501978-09-26026 September 1978 /03L-0 on 780901:while Testing ADS Subsys,Timers on Both Loops Were Found Outside the 115-125 Second Limit of Tech Specs Due to Setpoint Drift of Time Delay Relays. Timers Were Calibrated,Retested & Returned to Svc 05000000/LER-1977-005, Updated LER 77-005/1T:on 770114,failure of High Pressure Svc Water/Emergency Svc Water & Emergency Cooling Water Pumps to Meet FSAR Seismic Requirements Noted.Caused by Change in Calculation Techniques1977-01-28028 January 1977 Updated LER 77-005/1T:on 770114,failure of High Pressure Svc Water/Emergency Svc Water & Emergency Cooling Water Pumps to Meet FSAR Seismic Requirements Noted.Caused by Change in Calculation Techniques ML20086F3031976-10-0101 October 1976 LER 76/065/03L:on 760921,isolation Valve AO-5235 Failed to Respond to Manual Close Signal.Caused by Stuck Plunger. Plunger Freed & Valve Operated Properly 05000277/LER-1976-015, Telecopy LER 76-015/01P:allowable Gross Activity Gaseous Release Rate Exceeded Tech Spec.Caused by Xenon Gases Released During Filter Demineralizer Backwash.No Immediate Corrective Action Possible1976-03-0505 March 1976 Telecopy LER 76-015/01P:allowable Gross Activity Gaseous Release Rate Exceeded Tech Spec.Caused by Xenon Gases Released During Filter Demineralizer Backwash.No Immediate Corrective Action Possible 05000277/LER-1976-012, Telecopy LER 76-012/01P:on 760225,allowable Gross Activity Gaseous Release Rate Exceeded Tech Spec.Caused by Xenon Gases Released During Filter Demineralizer Backwash.No Immediate Corrective Action Possible1976-02-25025 February 1976 Telecopy LER 76-012/01P:on 760225,allowable Gross Activity Gaseous Release Rate Exceeded Tech Spec.Caused by Xenon Gases Released During Filter Demineralizer Backwash.No Immediate Corrective Action Possible 05000277/LER-1976-011, Telecopy LER 76-011/01P:on 760219,allowable Gross Activity Gaseous Release Rate Exceeded Tech Spec.Caused by Xenon Gases Released During Filter Demineralizer Backwash.No Immediate Corrective Action Possible1976-02-19019 February 1976 Telecopy LER 76-011/01P:on 760219,allowable Gross Activity Gaseous Release Rate Exceeded Tech Spec.Caused by Xenon Gases Released During Filter Demineralizer Backwash.No Immediate Corrective Action Possible 1993-09-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20151Y2901998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbaps,Units 2 & 3. with ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 ML20237B9531998-08-10010 August 1998 Specification for ISI Program Third Interval,Not Including Class Mc,Primary Containment for Bpaps Units 2 & 3 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20237A5351998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pbaps,Units 2 & 3 ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) ML20236M3471998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbaps,Units 2 & 3 ML20249C4791998-06-0202 June 1998 Rev 6 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20248F4781998-06-0101 June 1998 Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20248M3001998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pbaps,Units 2 & 3 ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20249C4751998-05-0707 May 1998 Rev 5 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20247G0721998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Pbaps,Units 2 & 3 1999-09-30
[Table view] |
LER-2076-012, Telecopy LER 76-012/01P:on 760225,allowable Gross Activity Gaseous Release Rate Exceeded Tech Spec.Caused by Xenon Gases Released During Filter Demineralizer Backwash.No Immediate Corrective Action Possible |
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f3 (v%iI LADE LPiiI A ELECTRIC COJA N T Peach Botton Atonic Pover Station
)
Delta, Pennsylvania )
1731h February 25, 1976 Mr. Tadei P. O'Reilly, D. rector- }
Of ce of Inspection and En fo rc e=e nt United States Nuclear Redulatory Commission 631 Park Avenue Oj King of Prussia., Penncylvania. 19h 06- [M[ /
SUBJECT:
' REPORTABLE OCCURRENCE . PROMPT N O T I F I C A T.I.O N ,
Confirming R. S. Fleischennn's phone conversstion with Mr. Valt E n u n a c k ,. .R e g i o n. 1 , Uni:t e d S.t at e s Nuclear RegulaItary- '
Co=cicsion.co. Eebruary 25,.. 1976.
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Reference:
Docket Number 050-2.77 '
Unit No. 2 Technical 3'p ec i.fi c at io n R e f e re nc e :. 3.8.C 1 Report No.: 2-76-12/IP Occurrence D a t.e :. F e b r ua ry- 25,. 1974 Identifiention.of Cccurrence:
Exceeded Technical Specifi. cation 3.8.C.1. - Allevable Gross
( Activity-(Gasecus) release rate for.a short period o f ti=e .
Conditions Price to Occurrence:
Unit 2 a t- loo? power and Uni.t 3 at 60%.
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Plast gasecus re1 ease rate about ep 75.of. Technical S p e c.l fi.c ati.o n allowable.
i i
i Descriptien of Occurrence:
At 9: 40 n.c. on 2/25/76 the yni.t 2 roof vent radia. tion-=onitors spil upward.. It was estinat.ed. quickly that -it could have exceeded Technical Specification lini.ts.
Apparent Cause of Occurrence:
At 6:50 a . c .. o n 2/25/76 the 2A RWCU fil t e r decineralizer was I reno ved .from.'s e rvice to be backvashed and.preccated. The back-l vash vac started a t. about 9 : 4 0; a . n:. The vess'el vas left bottled.
This 50 ninuto hold apparently a11oved.some of the Icdine absorbed en the powdex resin to decay to Xenon. When.the RWCU vessel was
) onekusshed, the Xenon 6ases which had builtup in the vessel vere releasci to the bsekvAsh. receiving tank. The backwash receiving tank is vented to the ventilation system through a HEPA filter, which 'alloved tie. gases to be relenced fron the unit i ventilation stack. i Analysis of Occurrence:
The Unit 2 roof vent =cnitor spiked at about 9:hC a.n. ,The peak i instantaneous. release rate was calculated to be 2 3 5x10" uCi/sce. l l
This release- rate in abcut 3 9 ti=ec- the Technical Specification lisi.t. The main st ack and Unit 3 roof vent release rates renuined unchanged during the period that the 2 roof vent release rate was b, i g h.. In less than 10 ninutes the calculated l I
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0401090575 760225 gDRADOCK 050002[
. ,6 Continued on page 2)
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2uaaz wux Reportable Occurrence p.c 2 Prompt !io t i fi ca t i o rr 2-7 6-12 /IP,,
Unit 2 roof vent relesse rate was less than Technical Spec ificat i on. .lici.t s . The total. length o -f tice t hat .the-Unit 2 roof vent- release rate was higher than norcal was less than- 55 minut.esu ,,
Initial analysis.of the particulat.c filtern and iodine cartridges indiented..no s ig n i f i can.t in.c re as e in pa rt i e.ula t e.
or iodine relense. rates. /, n isot;opic analysis was run on.
a gas sacple-obtained at .t.h'er end of the release.. It indicated only.Xel35 and XeL33 It van esticated that the.
activity r e l e a-s e dm due to this-spike was ab ou t. 25 c.u ri e s (based on Oroam Radiat ion Roof. Vent Monitor Readings)..
The release c a l c ul a t i.o n s. for roof vent. releases contain a tt MPC of 3.- 3. !ia . uci /e e for a 10 minute old offgas =ixture per T e c h n i e nl S p e.e-i r i.c at i o n s . Ho we ve r. , in this case the.=ost ,.
liciting MPQLfor the eaj or activity vculd. be: 3N7 aci/ce.
If the. sust li=i.t itn g MPC.of activity.nessured is used.in the-r ele a-s e calcul.at: ion 40 the Technical Specification.relesse l ,
linit; i s. noCS. exceeded;. .,' , , .
! 3ased o n .t h e.n a b o v e g: the shoEb-tere l e n g.t h:.: o.f t h e release'and the fric t t hat: .th er .=aj or =ensurm.d . activi.ty were nob le gases, the *ef f e e t st..from:- t h.is re.leaoe should: :be, very mininn.li.
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l The- re leuse: ve.s shert . tern 'in nat ure ; n.o -incediate etrreetive-action'vas pos:s;ihle . Yurther. invest.igati'on vill be.=nde. L.nr.ra the .s ec h an i nc.. c.f release. The..procedu re. for b ackst.sah. anst.
precoat. of..the reactor v e.t e r e l>c a m.u p: filter decinerali- ers..
{ v.1 I.%. c e revise d' if improve =ents; aru. .found; to .dec re asc. the ,
- 6aseous reletse ratea. ..
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