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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20148S3141997-06-30030 June 1997 Ro:On 970422,Oconee Unit 2 Was Shut Down Due to Leak in Rcs. Leak Was Caused by Crack in Pipe to safe-end Weld Connection at RCS Nozzle for HPI Sys A1 Injection Line.Unit 1 Was Shut Down to Inspect Hpis Injection Lines & Implement Ldst Mods ML20117A5981992-11-23023 November 1992 Special Rept:On 921119,ability of Control Battery Racks to Withstand Seismic Event Could Not Be Confirmed & Batteries Declared Inoperable.Batteries Expected to Be Restored in TS Required Time ML20236T0791987-11-25025 November 1987 Advises LER 269/87-09,re Degradation of More than One Functional Unit of Emergency Power Switching Logic for Units 2 & 3,in Preparation & Will Be Submitted by 871215. Incident Originally Discussed in Special Rept ML20210J6671987-02-0303 February 1987 Special Rept:On 861113-14,1206 & 23,spurious Fire Alarms Annunciated in Control Room.On 870118,unit Shut Down Due to Problems W/Detectors.Cause Undetermined.Technicians Investigating Potential Problem W/Detectors ML20215N4011986-10-20020 October 1986 Special Rept:On 860808,during Shutdown for Maint,Found Unidentified Wires in Environmentally Qualified Limitorque motor-operated Valves.Caused by Mfg Deficiency.Wires Replaced ML20209C1871986-08-13013 August 1986 Special Rept:On 860707,fire Barrier Penetration Nonfunctional.Caused by Design Deficiency Due to Ineffective Communication Between Design Groups.Fire Watch Established. Notice Initiated Requiring Installation of Fire Wall ML20212D2221986-07-29029 July 1986 Special Rept:On 860606,determined That Inadequate Assurance Existed Re Use of Qualified Grease in All Limitorque Operators.Appropriate Programs Not Updated to Reflect Revs. Lubrication Records Reviewed ML20210N5641986-04-14014 April 1986 Special Rept:On 860206,fire Wall Determined to Be Degraded. Caused by Personnel Failure to Recognize That Removing Small Amount of Pyrocrete Would Degrade Fire Wall.Fire Wall Repaired & Declared Fully Functional.Part 21 Related ML20137D6481985-11-22022 November 1985 Ro:On 851119,Keowee Hydro Unit 2 Inoperable Beyond Oconee Tech Spec Limit Due to Burned Out Laminated Copper Connection Between Two Coils.Caused by Cracked Brazement. Connector & Field Coils Will Be Replaced ML20135D7781985-08-21021 August 1985 Ro:On 850722,CRD Dc Breaker CB-1 Failed Trip Time Requirement During Channel C Reactor Protective Sys on-line Test.Cause of Failure Could Not Be Determined.Failed CB-1 Breaker Placed in Tripped Position ML20129G0441985-05-24024 May 1985 Ro:On 850425,batch of Powdex Resin from Powdex Cells 1A & 1D Transferred to Chemical Treatment Pond 2 Instead of Powdex Backwash Tank.Caused by Misalignment of Valve CTP-7.Valve Correctly Positioned ML20108E5341985-02-14014 February 1985 Special Rept:On 850114,CRD Dc Breaker Failed Slow During Channel D Reactor Protective Sys on-line Test.Caused by Sticking Trip Latch Roller Bearings & Excessive Trip Latch Operating Torque.Breaker Front Frame Replaced ML20112D0771984-12-14014 December 1984 Special Rept:On 841109,many Fire Barriers Did Not Meet Surveillance Insp Acceptance Criteria & Declared Inoperable. Caused by Const/Installation Deficiency,Component Failure/ Malfunction & Some Unknown Causes.Firestops Repaired ML20099E0241984-10-24024 October 1984 Special Rept:On 840927,discovered That Contaminated Oil Shipped to Lee Steam Station for Disposal by Incineration. Caused by Misinterpretation of Regulations.Shipments of Contaminated Oil Halted ML20093F1911984-10-0808 October 1984 RO 269/83-16,revising 831107 Commitment Re Completion Date of 850101 to Relocate Hydrogen Purge Unit Connection Near Permanent Hookup Connections on Each Unit for Hydrogen Recombiner ML20093L5061984-10-0505 October 1984 Special Rept:On 840906,batch of Powdex Resin from Powder Cells 2D & 2E Transferred from Plant to Chemical Treatment Pond 1 Instead of to Powdex Backwash Tank.Caused by Misalignment of Valves of Chemical Treatment Ponds 5 & 6 ML20106B4791984-10-0303 October 1984 Special Rept:On 840928,power Circuit Breaker 22 Explosively Short Circuited,Causing Power Circuit Breaker 9 to Open, Isolating 230 Kv Overhead Line from Primary OL Power Source. Breaker Reclosed ML20096A1061984-08-22022 August 1984 Suppl to Rev 1 to RO-287/83-13:containment Isolation Valve 3CS-5 Declared Inoperable Due to Leakage Past Seat. Investigation Into Valve Failure Conducted & Diaphragm Replaced ML20094N8601984-07-27027 July 1984 RO 269/83-20 Re Trip Shaft & Bearing Assembly Portions of CRD Breaker Front Frame Assemblies.Nine of 17 GE Frames Defective.Util Awaiting Schedule for Delivery of New Frames ML20092A4291984-06-0606 June 1984 Special Rept:On 840419,during Fuel Reshuffling for Cycle 8, Fuel Assembly FA 0297 Became Stuck in Fuel Location E-10 During Insertion & Fuel Assembly FA 029Q Damaged.Caused by Inadequate Procedure Change ML20092A3841984-04-30030 April 1984 Updated RO-269/83-20 Submitted on 840111 Re Two CRD Breakers Experiencing Delay During Testing.Ge Will Ship CRD Breaker Front Frame Assemblies on 840514.Installation Will Be Complete on All Three Units by 840731 ML20084G4851984-04-18018 April 1984 Updated RO 269/83-17:seals at Conduit Connections Defective. Scotchcast 9 Epoxy Resin Will Be Utilized to Seal Conduit Connections,Dow Corning RTV 3145 Applied to Conduit Fittings & Conduit/Cable Seals Will Be Upgraded ML20082R7561983-12-0202 December 1983 Ro:On 831015-16,standby Bus 2 Deenergized to Verify Emergency Power Path & CT-3 Startup Transformer Locked Out. Caused by Failure of Two Insulators Causing Short to Ground. Info Supersedes 831101 Rept ML20082H5161983-11-21021 November 1983 Ro:Re Loss of Power on Both Standby Buses W/Both Units Out of Svc.Investigation Incomplete.Necessary Info Will Be Submitted by 831202 ML20082C6081983-11-14014 November 1983 Ro:On 831109,while Units Out of Svc for Planned Maint,Lee 6C Gas Turbine Tripped off-line,deenergizing Standby Buses & Placing Units in Degraded Mode Beyond Tech Spec Limit.Cause Undetermined.Next Rept by 831118 ML20078P9651983-11-0202 November 1983 Ro:On 831028,while Unit Out of Svc,Lee 6C Gas Turbine Tripped & Deenergized Both 4,160-volt Standby Buses.Cause Unknown.Lee 5C Turbine Placed on-line to Sys Grid. Investigation Continuing ML20081K0951983-11-0101 November 1983 Ro:On 831015-16,w/Unit 1 Out of Svc,Standby Bus 2 Deenergized to Allow Operability Verification of Underground Emergency Power Path in Accordance W/Tech Specs.On 831015, CT-3 Underwent Lockout.Caused by Bad Insulators ML20078P8841983-10-31031 October 1983 Ro:On 831026,w/unit Out of Svc for Maint,Lee Steam Station Gas Turbine Tripped,Deenergizing Both Standby Buses.Cause Not Determined.Redundant Buses Available ML20081B2521983-10-17017 October 1983 Ro:On 831012,standby Buses Deenergized to Allow for Operability Performance Testing of Standby Bus Breakers Per Tech Specs.Testing Caused Degraded Mode Beyond Tech Spec Limit ML20078H4121983-10-0404 October 1983 Ro:On 830929,while Energizing 4,160-volt Standby Buses,Lee 6C Gas Turbine Tripped off-line,deenergizing Both Standby Buses & Placing Two Operating Units in Degraded Mode.Cause Undetermined Since Unit Has No Event Recorder ML20080P3271983-09-27027 September 1983 Ro:On 830922,w/both Keowee Hydro Units Out of Svc for Planned Maint,Lee 6C Gas Turbine,Being Used to Energize Buses,Tripped Off Line.Both Standby Buses Deenergized & Units 1 & 3 Placed in Degraded Mode ML20080M0261983-09-16016 September 1983 Updated RO 287/83-07.Investigation Incomplete.Next Rept Expected by 831030 ML20080G2351983-09-0606 September 1983 RO 270/83-09:on 830802,hydraulic Snubber Noted Technically Inoperable for More than 72 H.Investigation Incomplete.Next Rept Will Be Submitted by 830912 ML20076C3291983-08-15015 August 1983 RO 287/83-07:followup to Rept Submitted on 830708. Investigation Incomplete.Supplemental Rept Expected by 830915 ML20072J2031983-06-24024 June 1983 Ro:On 830527,certain Containment Isolation Valves May Have Failed in non-ES Position Due to Loss of Dc Power. Investigation & Rept Will Be Completed & Reviewed by 830708 ML20073Q0121983-04-19019 April 1983 Corrected RO 269/83-07:on 830303,during Insp of Manual Containment Isolation Valves,Valve CF-19 Discovered Open. Caused by Personnel Error.Valve Closed.Core Flood Procedure & Reactor Bldg Manual Checklist Changed ML20069K4141983-04-15015 April 1983 Updated ROs 287/83-04,269/83-05 & 269/83-10:repts Being Reviewed & Will Be Submitted No Later than 830419 ML20072T7011983-03-30030 March 1983 RO-287/83-04 Will Not Be Submitted by 830331 as Planned.Rept Re Open Valve on Emergency Hatch Leak Rate Test Pressurization Line Incomplete.Rept to Be Submitted by 830414 ML20072T6971983-03-30030 March 1983 RO-269/83-10 Will Be Delayed Due to Continuing Investigation of Incident Re Partially Opened Interpersonnel Emergency Door Following Testing.Rept Should Be Submitted No Later than 830415 ML20073C4071983-03-25025 March 1983 Informs That RO-287/83-04 Not Reportable.Results of Seismic Analysis Indicate Letdown Line Was Seismically Operable W/Lead Blankets Attached.Pipe Stress,Support Restraint & Equipment Nozzle Loads within Allowable Limits ML20069E3741983-03-11011 March 1983 Ro:On 830225,reactor Protective Sys Pump Power Monitor Sys Failed to Meet Operability Requirements.Investigation Incomplete at Present Time.Rept Will Be Submitted by 830325 ML20070K5851982-12-23023 December 1982 Ro:On 821213,Region 2 Informed of Two Manual Containment Isolation Valves Discovered Open.Rept Providing Details Delayed Due to Investigation.Rept Will Be Completed & Submitted by 821231 ML20070K7311982-12-23023 December 1982 RO 287/82-14:primary to Secondary Leak Discovered in Steam Generator 3B.Rept Will Not Be Submitted Until 830107 Contrary to Previous Commitment ML20065L7761982-10-14014 October 1982 Ro:On 821014,Unit 2 Core Relief Valves Declared Inoperable Due to Analysis Prompted by B&W Safety Concern.Unit 3 Valves Were Offsite Undergoing Ring Adjustment.Immediate Shutdown of Unit 2 Commenced ML20063N2791982-09-0707 September 1982 Informs That RO-269/82-15 Re Electrically Inoperable Valve CCW-8 Will Be Submitted by 820921.Investigation Incomplete ML20063M0851982-09-0303 September 1982 Advises That RO-269/82-16 Re Separation of safety-related Cables Will Not Be Filed.Review & Evaluation Determined That Separation of Specified Cables Conforms to Established Criteria.No Further Action Required ML20063M1031982-09-0101 September 1982 Ro:On 820818,five Reactor Coolant Pump Closure Studs Determined to Be Degraded in Size Below Acceptable SAR limits.RO-287/82-09 Will Be Completed,Reviewed & Submitted by 820910 ML20062J1721982-08-0505 August 1982 RO 270/82-10:on 820722,util Informed NRC That Upper Surge Tank Indicator Read Below Tech Spec Min Required Water Level.Investigation & Preparation of Rept Incomplete.Final Review & Rept Expected by 820819 ML20071K3471982-07-20020 July 1982 RO 269/82-13:on 820706,emergency Feedwater Pump Declared Inoperable When Required Surveillance Testing Discovered Not Performed.Investigation & Rept Will Be Completed,Reviewed & Submitted by 820803 ML20058D8291982-07-16016 July 1982 RO 270/82-09:on 820616,valve 2FDW-316 Would Not Close Completely After Sampling & Affected Flow Path Declared Inoperable.Investigation & Rept Will Be Completed,Reviewed & Submitted on 820730 1997-06-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20206P1501999-01-0505 January 1999 LER 98-S03-00:on 981207,security Officer Discovered Uncontrolled Safeguards Info Drawing.Caused by Failure to Follow Established Procedures & Policies.Drawing Was Controlled by Site Security.With ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20198E6381998-12-17017 December 1998 LER 98-S02-00:on 981130,security Access Was Revoked Due to Falsification of Criminal Record.Individual Was Escorted from Protected Area & Unescorted Access Was Restricted. with ML20153G4601998-09-30030 September 1998 USI A-46 Seismic Evaluation Rept, Vols 1-2 ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML15261A4681998-09-0404 September 1998 Safety Evaluation Supporting Amends 232,232 & 231 to Licenses DPR-38,DPR-47 & DPR-55,respectively ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20247L9041997-12-31031 December 1997 1997 Annual Rept for Duke Energy Corporation & Saluda River Electric Cooperative,Inc,Financial Statements as of Dec 1997 & 1996 Together W/Auditors Rept ML20198J7651997-10-15015 October 1997 Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units ML20148S3141997-06-30030 June 1997 Ro:On 970422,Oconee Unit 2 Was Shut Down Due to Leak in Rcs. Leak Was Caused by Crack in Pipe to safe-end Weld Connection at RCS Nozzle for HPI Sys A1 Injection Line.Unit 1 Was Shut Down to Inspect Hpis Injection Lines & Implement Ldst Mods ML20148H2501997-06-0505 June 1997 Safety Evaluation Accepting Proposed Restructuring of Util Through Acquisition Of,& Merger W/Panenergy Corp ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20134N7121997-02-20020 February 1997 Safety Evaluation Accepting Relief Request 96-04 for Plant ML20138L2151997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Oconee Nuclear Station,Units 1,2 & 3 ML20138L2281996-12-31031 December 1996 Revised Monthly Operating Repts for Dec 1996 for Oconee Nuclear Station,Units 1,2 & 3 ML20133C1231996-12-23023 December 1996 Informs Commission of Staff Review of Request for License Amends from DPC to Perform Emergency Power Engineered Safeguards Functional Test on Three Oconee Nuclear Units ML20115F2471996-07-0303 July 1996 Part 21 Rept Re Piping (Small Portion of Unmelted Matl Drawn Lengthwise Into Bar During Drawing Process) Defect That Existed in Bar as Received from Mill.Addl Insp Procedure for Raw Matl Instituted ML20107M8931995-10-31031 October 1995 Nonproprietary DPC Fuel Reconstitution Analysis Methodology ML17353A4341995-10-31031 October 1995 Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range. ML17264A1181995-07-31031 July 1995 Response to Part (1) of GL 92-01,Rev 1,Suppl 1. ML20086M0851995-06-29029 June 1995 DPC TR QA Program ML20077R3631994-12-31031 December 1994 Monthly Operating Repts for Dec 1994 for Bfnpp ML20236L5971994-12-29029 December 1994 SER in Response to 940314 TIA 94-012 Requesting NRR Staff to Determine Specific Mod to Keowee Emergency Power Supply Logic Must Be Reviewed by Staff Prior to Implementation of Mod ML20064L2001994-01-31031 January 1994 Final Rept EPRI TR-103591, Burnup Verification Measurements on Spent-Fuel Assemblies at Oconee Nuclear Station ML20062K7481993-12-0101 December 1993 ISI Rept for Unit 2 McGuire 1993 Refueling Outage 8 ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20046C1291993-08-0202 August 1993 LER 93-007-00:on 930701,determined That Unit 1 Ssf Rc Makeup Sys Inoperable in Past Due to Design Deficiency.Operations Procedures Revised to Reflect Newly Calculated Operating Limits for Rc Makeup Pump,Rcps & RCS.W/930802 Ltr ML20056G0131993-07-27027 July 1993 Rev 0 to ISI Rept Unit 2 Oconee 1993 Refueling Outage 13 ML20044G5311993-05-26026 May 1993 Suppl to 921207 Part 21 Rept Re Declutch Sys Anomaly in Certain Types of Valve Actuators Supplied by Limitorque Corp.Limitorque Designed New Declutch Lever Which Will Be Available in First Quarter 1993 ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20117A5981992-11-23023 November 1992 Special Rept:On 921119,ability of Control Battery Racks to Withstand Seismic Event Could Not Be Confirmed & Batteries Declared Inoperable.Batteries Expected to Be Restored in TS Required Time ML20097G0421992-05-31031 May 1992 Analysis of Capsule OCIII-D Duke Power Company Oconee Nuclear Station Unit-3 ML20077D0671991-11-15015 November 1991 Nonproprietary Version of Rev 0 to Boric Acid Corrosion of Oconee Unit 1 Upper Tubesheet ML20067A5241990-12-31031 December 1990 Final Submittal in Response to NRC Bulletin 88-011, 'Pressurizer Surge Line Thermal Stratification.' ML20042F3541990-04-30030 April 1990 Special Rept Re Failure to Prevent Performance Degradation of Reactor Bldg Cooling Units.Caused by Mgt Deficiency & Inadequate Program.Cooling Unit Declared Inoperable & Removed from Svc for Cleaning & Placed Back in Operation ML17348A1621990-03-27027 March 1990 Part 21 Rept Re Matls W/Programmatic Defects Supplied by Dubose Steel,Inc.Customers,Purchase Order,Items & Affected Heat Numbers Listed ML19332D5391989-10-31031 October 1989 Core Thermal-Hydraulic Methodology Using VIPRE-01. ML20042F2321989-08-31031 August 1989 Nonproprietary DCHF-1 Correlation for Predicting Critical Heat Flux in Mixing Vane Grid Fuel Assemblies. ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking ML20245B6061988-08-31031 August 1988 Inadequate NPSH in HPSI Sys in Pwrs, Engineering Evaluation Rept ML20239A6991987-11-30030 November 1987 Addendum 1 to Rev 2 to Integrated Reactor Vessel Matl Surveillance Program (Addendum) ML20236T0791987-11-25025 November 1987 Advises LER 269/87-09,re Degradation of More than One Functional Unit of Emergency Power Switching Logic for Units 2 & 3,in Preparation & Will Be Submitted by 871215. Incident Originally Discussed in Special Rept ML20236Q9491987-10-31031 October 1987 Monthly Operating Repts for Oct 1987 ML20235W9611987-09-30030 September 1987 Monthly Operating Repts for Sept 1987 ML20234B1861987-08-31031 August 1987 Monthly Operating Repts for Aug 1987 ML20237K4761987-07-31031 July 1987 Monthly Operating Repts for Jul 1987 ML20236Y0221987-07-0808 July 1987 Safety Evaluation Clarifying Determination of Acceptability of Test Duration for Performance of Integrated Leak Rate Test at Plant ML20235S6311987-06-30030 June 1987 Monthly Operating Repts for June 1987 1999-01-05
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DUKE POWI:n Goduwxy P.O. nox 11:11t50 CitAltI.oTTE. N.C. 211242 HAI.11. TUCKER Trnrenose
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] [f l April 14, 1986 Dr. J. Nelson' Grace, Regional Administrator U.'S. Nuclear Regulatory Commission - Region II 101 Marietta Street NW, Suite 2900 Atlanta, Georgia 30323 Re ference: Oconee Nuclear Station Docket No. 50-270
Dear Dr. Grace:
Please find attached a special report on non-functional fire barriers.
This report is submitted pursuant to Oconee Nuclear Station Technical Specification 3.17.6 which concerns fire barrier penetrations that cannot be restored to functional status within seven days, and describes an incident which is considered to be of no significance with respect to public health and safety.
Very truly yours, s
J -
/4%
Hal B. Tucker PJN/jgm Attachment xc: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 J.C. Bryant NRC Resident Inspector Oconee Nuclear Station Helen Nicolaras Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 INPO Records Center Suite 1500 1100 circle 75 Parkway Atlanta, Georgia 30339 M&M Nuclear Consultants 1221 Avenue of the Americas New York, New York 10020 8605050147 860414 PDR ADOCK 05000270 (
S PDR tl ZEl}
DUKE POWER COMPANY OCONEE NUCLEAR STATION-SPECIAL REPORT ON NON-FUNCTIONAL FIRE BARRIERS
Introduction:
On January 16, 1986 a small section of pyrocrete was removed from the fire wall which divides the Unit 2 East and West Penetration Rooms. The pyrocrete was removed to identify a hanger that was to be modified. On February 6, 1986, at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, with Unit 2 at 97% full power, this fire wall was determined to be degraded. The degraded condition had existed for 49 days, thus violating Technical Specification 3.17.6 requirements for repair of the fire barrier in 7 days.
The cause of the incident was determined to be personnel error, because the fire wall was degraded, without taking the required compensatory action.
The immediate corrective action was to verify the operability of the fire protection systems and establish an hourly fire watch.
Smoke detector systems located in the East and West Penetration Rooms function as automatic monitoring devices. The rooms are also toured at least tvice each shift. Based on the above, the possibility of a fire occurring and spreading and going undetected are very low. Therefore, the health and. safety of the public were not affected by this incident.
Description of Occurrence:
On February 6, 1986, with Unit 2 at 97% full power, the fire wall located in the Unit 2 West Penetration Room was inspected and determined to be degraded.
Upon investigation of the incident, it was learned that Nuclear Station Modification (NSM) 1714 was issued on June 28, 1985 to modify a hanger.
The NSM package was returned on July 16, 1985 without any work being performed because the hanger was located in a fire wvil.
On September 26, 1985, NSM 1714 was reissued. The package was returned on October 8, 1985 for a similar reason.
On January 16, 1986, NSM 1714 was again reissued. When the hanger could not be identified, a small section of pyrocrete (about 6"x8"x2") was removed, exposing a section of steel. The removal of the pyrocrete was not documented. A procedure is not required to remove or install pyrocrete.
The exposed steel was inspected, and NSM 1714 was returned on January 17, 1986, because hanger drawings did not cor',ctly show the steel that was located.
On March 5, 1986, NSM 1714 was again reissued. Upon inspection of the job, pyrocrete removal was reported to Maintenance Services and Project Services on March 6, 1986 at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />. Shortly after this time, the fire wall was declared degraded. At 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br /> a work request was initiated to repair Penetration 2PE6. The work request should have read, repair fire wall near
Penetration 2PE6. The 7 day Technical Specification 3.17.6 requirement was noted on the work request. The fire detection system for the East and West Penetration Rooms was verified operable at this time.
The required hourly fire watch was started at 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br />.
Due to a misunderstanding between personnel, no work began.
On March 7, 1986, another inspection of the fire wall was made and i discovered a small section had also been removed from the East side. The investigation could not determine when it was removed or by whom. It is believed that it was removed some time after January 16, 1986, because this was the date that the actual work began on the NEM package.
On March 12, 1986, conversation between Construction and Maintenance Supervisors concluded that pyrocrete work had not yet begun. Three days
! were then spent attempting to receive issue of the material, without success.
On March 18, 1986, pyrocrete material was transferred from Catawba Nuclear Station and work on the fire wall was completed on March 19, 1986, at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />.
Cause of Occurrence:
The root cause of the degraded fire wall and failure to comply with Technical Specification 3.17.6 was that a Construction and Maintenance Supervisor failed to recognize that removing a small amount of pyrocrete would degrade the fire wall and did not initiate the proper action needed to ensure compliance with Technical Specifications.
J A contributing cause to this incident is management deficiency, because management issued the NSM hanger package to e number of Craft Supervisors after it was known that a fire wall would U.terfere with the hanger modification, without giving any guidance to the Craft Supervisors or contacting the Fire Barrier Accountable Eagineer. However, this hanger is the first to require modification that involved a fire wall. It is concluded that lack of experience and inattention to the planning phase of 4
the work was the cause of the management deficiency.
[ The' fire wall in Unit 2 West Penetration was qualified as a hour barrier by model testing. When any portion of the wall is removed, it is concluded that the fire wall is degrceed. Two small sections of pyrocrete vece removed, one section from tne West side and one section from the East side.
The two sections that were removed were in different areas of,th.e wall, several feet apart. There was never a complete through hole .Y, the wall.
The wall was not declared not-functional, but degraded. It ieJdifficult to i know to what degree the wall was degraded, but a non-conservative estimate is less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> but greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Construction and Maintenance Supervisor did not know tizat the removal of a small section of pyrocrete from the fire wall would degrade the barrier. He is qualified to install pyrocrete under Coating Specifications 0-155-LI, but not qualified to determine what constitutes fire wall degradation.
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y Corrective Action:
The immediate corrective action was to initiate a work request to repair the fire wall, start hourly fire watch tours, and verify operability of the fire detection systea.
Supplemental corrective actions included:
e Fire wall repaired and declared fully functional on March 21, 1986, at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, e A memo has been written by Maintenance Services to instruct all Station Personnel to contact Maintenance Services before any work in performed on fire barriers, e Appropriate personnel have been counseled regarding proper documentation, and the necessity to ensure that appropriate action is taken to correct deficiencies.
Planned corrective actions are to change procedure MP/0/A/3019/04 to include in prerequisites a requirement fcr the Penetration, Fire Barrier Accountable Engineer to be notified of all work on any penetration, fire wall (i.e., repair, modification, removal, or installation) prior to work.
Also a sign off step for the accountable Engineer and documentation for penetration fire barrier work request numbers. This change will be completed by 5-7-86. All appropriate Construction and Maintenance Supervisors will review the incident report to benefit from lessons learned.
Analysis of Occurrence:
No equipment or syatems were affected by this incident. The possibility of a fire occurring in the Penetr1 tion Rooms is remote. The use of high heat, such as welding or burning on a job in these areas, is restricted and requires a burning permit and fire watch.
Smoke detector systems are located in the East and West Penetration Rooms that function as automatic monitoring devices. Fire fighting equipment is located outside the Penetration Room's door. The Penetration Rooms are toured at least twice each shift. An hourly fire watch patrol was established when the fire wall was identified as degraded. Based on the above, the possibility of a fire occurring and spreading and going undetected are very low. Therefore, the health and safety of the public were not affected by this incident.