ML20214J491
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Letter Sequence Other | |
|---|---|
TAC:62897, (Open) | |
Initiation
Questions
Results
Other: ML20205F935, ML20205G379, ML20205Q105, ML20207R057, ML20210F602, ML20212J543, ML20214J491, ML20214J670, ML20214V904 | |
MONTHYEARML20128H1261985-06-0606 June 1985
[Table View]Summary of 831219 Meeting W/Util & S&W in Bethesda,Md Re Util Equipment Qualification Program.Meeting Agenda & Supporting Documentation Encl Project stage: Meeting ML20205Q1051986-05-23023 May 1986 Forwards Vols 1-1C to Equipment Qualification Rept - Environ Qualification of Class 1E Electrical Equipment. Representative Sample of Equipment Will Be Installed & Available for Insp in Support of NRC Audit Project stage: Other ML20206E6191986-06-16016 June 1986 Notification of 860701 Meeting W/Util in Bethesda,Md to Discuss Technical Issues Re Util 860523 Equipment Qualification Rept,Identified as SER Confirmatory Issue 14, in Preparation for NRC Audit Project stage: Meeting ML20203G4881986-07-28028 July 1986 Summary of 860701 Meeting W/Util,Westinghouse & S&W in Bethesda,Md Re Preparation for Onsite Equipment Qualification Audit.Agenda & Attendee List Encl.Audit Expected to Take Place in Aug 1986 Project stage: Meeting ML20205C3281986-08-0404 August 1986 Forwards Addendum 1 to 2BVM-166, Sqrt & Pump & Valve Operability Review Team (Pvort) Audit Program & Updated Master Equipment List,Per Sqrt/Pvort 860723 Premeeting.List Submitted to Support NRC 860930 Audit Project stage: Meeting ML20210F6021986-09-20020 September 1986 Forwards Rev 1 to Vols 1,1A,1B & 1C to Equipment Qualification Rept - Environ Qualification of Class 1E Electrical Equipment. Review & Schedule of NRC Audit Requested.List of Specs & Status of Util Response Also Encl Project stage: Other ML20215N2011986-10-23023 October 1986 Discusses Results of 860701 Meeting W/Util & Contractor in Preparation for Equipment Qualification Onsite Review.Onsite Review Scheduled for 861117-21.Access for Review Team Members Requested Project stage: Meeting ML20214E5881986-11-19019 November 1986 Notification of 861120 Meeting W/Util in Shippingport,Pa to Discuss Applicant Personnel Findings Made During Equipment Qualification Site Audit Project stage: Meeting ML20214V9041986-12-0303 December 1986 Forwards Updated Environ Qualification Program for Safety- Related Mechanical Equipment in Response to FSAR Questions 270.2 & 270.3 Identified in FSAR Amend 4.Qualification Methodology & Results Discussed Project stage: Other ML20207D4731986-12-19019 December 1986 Forwards Supplemental Info Re Evaluation of Superheated Steam Blowdown on Environ Qualification of Facility Equipment,Per 861125 Telcon.Response Provides Addl Info on Computer Codes Utilized in Superheat Evaluation Project stage: Supplement ML20212J5431987-03-0404 March 1987 Forwards Response to Specific & Generic Comments from Nrc/ NRR Environ Qualification Audit on 861118-20.Info Indicates That Action to Address Specific Comments Completed & Action to Address Generic Comments Prior to Fuel Load Underway Project stage: Other ML20207R0571987-03-0505 March 1987 Forwards Comments for Resolution Re SER Confirmatory Issue 14 Identified During Equipment Qaulification Review Team 861118-20 Audit.Response Requested within 45 Days of Ltr Receipt Project stage: Other ML20205G3791987-03-24024 March 1987 Forwards Responses to NRC Requests for Info Re Environ Qualification Program,Including High Energy Line Break W/ Superheat & Qualification Methodology for Submergence Project stage: Other ML20205F9351987-03-26026 March 1987 Forwards Environ Qualification of Safety-Related Mechanical Equipment, Including Rev 1 to Books 1-3 Re Masonelian air-operated Valves,Rev 4 Re Xomox Plug Valves & Rev 5 Re Pacific Charging Pumps,Per P Tam 870317 Telecopy Project stage: Other ML20214J6701987-05-18018 May 1987 Notifies of Completion of Environ Qualification (EQ) Effort for Facility EQ Packages in Compliance w/10CFR50.49. Potential 10CFR50.55(e) Items Re Improper Sealing of EQ Program Equipment Will Be Submitted within 30 Days Project stage: Other ML20214J4911987-05-25025 May 1987 Interim Significant Deficiency Repts 87-16 & 87-17 Re Conduit Sealing of 50 Class 1E Items.All Physical Work Re Re Environ Qualification Program Complete W/Exception of Four Bisco Seals Project stage: Other 1986-07-28 |
| ML20214J491 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/25/1987 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 2NRC-7-142, 87-16, 87-17, TAC-62897, NUDOCS 8705280069 | |
| Download: ML20214J491 (4) | |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20154E2171998-09-28028 September 1998
[Table view]Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. 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Vendor Will Notify Enertech W/Recommendations That All Items Supplied W/Incorrect Matl Be Removed & Destroyed ML20059E9081993-12-29029 December 1993 Part 21 Rept Re Decreases in Valve Actuator Motor Starting Torques Resulting from Increasing 3-Phase Actuator Motor Temp.Concludes Valves Capable of Performing Intended safety- Related Function ML20058K6431993-12-10010 December 1993 Part 21 Rept Re Potential for Unacceptable Recirculation Spray Sys Operation for Supporting Long Term Core Cooling Capability.Caused by Disc of motor-operated Valve on Suction of Pump Not Engaged to Motor Operator ML20058H0791993-12-0303 December 1993 Part 21 Rept Re BVPS Unit 2 Suction Valves for Rs Pumps Supplied by Henry Pratt Co,W/Regard to Inadequate Discharge Pressure.Temporary Mod Made to Four Affected Suction Valves Which Will Properly Position & Retain Spline Adapter ML20046B1321993-07-23023 July 1993 Interim Part 21 Rept Re Decreases in MOV Motor Starting Torques Resulting from Increasing Motor Temp.Valves Mfg by Limitorque Corp.Mfg in Process of Revising Recommended Torque Degradation Calculation at Degraded Voltage ML20128H4561993-01-25025 January 1993 Followup Part 21 Rept Re Disintegration of Balston 21554-1 Automatic Drain Float & Air Piping Filter Assemblies Mfg Prior to Nov 1989.Caused by Contaminants in Air Start Sys. Customers Should Order Air Filters Mfg After Nov 1989 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20116D1241992-10-29029 October 1992 Supplemental Part 21 Rept Re Byron Jackson River Water Pump Couplings.Initially Reported on 921101.Caused by Lack of Matl Toughness.Replacement Couplings Were Screened to Insure Adequate Toughness & Purchase Spec Amended ML20101R3691992-07-0707 July 1992 Final Part 21 Rept Re Failure of Byron Jackson River Water Pump Couplings.Initially Reported on 911121.Couplings Failed in Svc Due to Lack of Toughness.Couplings Examined & Suspect Matl Removed from Svc ML20079L8031991-11-0101 November 1991 Part 21 Rept Re 910620 Failure of Coupling in River Water Pump 1A Supplied by Byron Jackson.Caused by Mechanical Failure of Shaft Coupling.Metallurgical Analysis of Suspect Coupling Will Be Performed & Couplings Replaced ML20082P6871991-09-0404 September 1991 Revised Part 21 Rept Re Failure of Crosby Spring Relief Valves During Testing.Valve Prematurely Lifted During Sixth & Seventh Refueling Outages Due to Use of Stainless Instead of Carbon Steel.Springs,W/New Matl,Installed at Facility ML20077L5661991-08-0505 August 1991 Part 21 Rept Re Crosby Spring Relief Valve Failures Experienced During Testing at Facility.Evaluation Conducted to Determine If Safety Hazard Could Exist.Spring Changed to ASTM-A638 Grade 660,correcting Problem at Facility ML20055E8221990-07-0505 July 1990 Part 21 Rept Re Abb 27/59 Relays Deteriorated Due to Thermal Stress.Initially Reported on 900222.Units W/Listed Identification Numbers to Be Inspected & Replaced If Signs of Overheating Present ML20043A8491990-05-11011 May 1990 Part 21 Rept Re Contactors Used on Diesel Generator Immersion Heater Mfg by Cutler-Hammer.All Contactors W/Date Code Before 890522 Suspect.Dimensions Changed to Correct Problem.Formal Rept Will Be Sent Next Wk ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used ML20011F1941990-02-22022 February 1990 Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys 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 ML20236C7981987-10-22022 October 1987 Part 21 Rept Re Defect Concerning Modulating Solenoid Valve Supplied by Target Rock Corp.Valve Has Been Reassembled Using Proper Spiral Pin ML20237H8281987-08-0707 August 1987 Final Potential Significant Deficiency Rept 87-18 Re Failure of Emergency Switchgear & Diesel Generator Room Supply Fans to Start by Actuation of Switches on Alternate Shutdown Panel.Initially Reported on 870803.Control Switch Replaced ML20235M3651987-07-0101 July 1987 Deficiency Rept 87-09 Re Linear Indication on Reactor Vessel Weld.Initially Reported on 870301. Boat Sample Removed by Westinghouse for Vertical Linear Indication.No Addl Repts Anticipated ML20235H1811987-06-17017 June 1987 Final Deficiency Rept 87-16 Re Improper Installation of Bisco LOCA Seals in Conduits Containing Rockbestos Cable. Initially Reported on 870518.Rework on All Seals Completed ML20215C5771987-06-10010 June 1987 Part 21 Rept Re Small Leak in Unit B Cooling Water Header Lower Pipe in Right Bank of Emergency Diesel Generators. Affected Water Header Pipes Replaced W/Upgraded Matl & Unit a Water Header Pipes Visually Inspected for Leakage ML20215A9951987-06-0202 June 1987 Potential Significant Deficiency Rept 87-15 Re Failure of Main Steam Valve Area Supply Fans to Start Automatically. Initially Reported on 870508.Diesel Sequencer Interlock Rewired to Open Dampers.No Addl Repts Anticipated ML20215B0511987-06-0202 June 1987 Significant Deficiency Rept 87-14 Re Lack of Documentation Certifying Modes 5 & 6 N-1 Operation.Initially Reported on 870507.Appropriate Documentation Expected to Be in Place When Full Power License Received.No Addl Repts Required ML20215A3451987-05-29029 May 1987 Final Deficiency Rept 87-10 Re Linear Indications Identified During Preservice Insp of Reactor Vessel Studs.Initially Reported on 870501.Corrective Actions Include Blending/ Grinding of Surface Indications to Remove Distress Marks ML20214U9511987-05-28028 May 1987 Revised Final Deficiency Rept 87-08 Re Containment Isolation Phase B-initiated Timers for Control Room Emergency Pressurization Fans.Initially Reported on 870327.Correct Date for Completion Is 870504 Instead of 870411 ML20216C9341987-05-28028 May 1987 Potential Significant Deficiency Rept 86-14 Re Outside Containment Flood Analysis.Initially Reported on 860917. Outside Flood Analysis Calculation Revised to Elevate Lines Previously Exempted from Analysis ML20214J4911987-05-25025 May 1987 Interim Significant Deficiency Repts 87-16 & 87-17 Re Conduit Sealing of 50 Class 1E Items.All Physical Work Re Re Environ Qualification Program Complete W/Exception of Four Bisco Seals ML20214V0571987-05-21021 May 1987 Final Significant Deficiency Rept 87-07 Re High Head Safety Injection/ Charging Pump Operating Below Min Operating Curve.Initially Reported on 870323.Pump Rotating Assembly Replaced W/Spare Rotating Assembly & Satisfactorily Tested ML20214H4091987-05-14014 May 1987 Final Deficiency Rept 87-13 Re Pressure Locking & Thermal Binding of Westinghouse Gate Valves.Initially Reported on 870415.S&W Review Resulted in Initiation of Advance Change Notice D-0266 to Correct Discs in 10 Valves 1998-09-28 Category:INCOMING CORRESPONDENCE MONTHYEARL-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999
[Table view]Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999 Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct L-99-151, Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program1999-10-0707 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program L-99-149, Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion1999-09-28028 September 1999 Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion L-99-148, Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 9908171999-09-24024 September 1999 Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 990817 ML20212G0601999-09-23023 September 1999 Forwards Answer of Duquesne Light Co to Petition to Waive Time Limits & Suppl Comments of Local 29, Intl Brotherhood of Electrical Workers.Copies of Answer Have Been Served to Parties & Petitioner by e-mail or Facsimile ML20212C5521999-09-21021 September 1999 Forwards for Filing,Answer to Firstenergy Nuclear Operating Co & Pennsylvania Power Co in Opposition to Petition to Waive Time Limits & Suppl Comments of Local 29 Intl Brotherhood of Electrical Workers L-99-144, Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-031999-09-20020 September 1999 Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-03 ML20212B3291999-09-16016 September 1999 Forwards for Filing,Petition to Waive Time Limits in 10CFR2.1305 & Supplemental Comments of Local 29,Intl Brotherhood of Electrical Workers Re Beaver Valley Power Station,Units 1 & 2 L-99-134, Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC1999-09-15015 September 1999 Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC L-99-138, Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)1999-09-0303 September 1999 Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d) L-99-136, Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls1999-09-0202 September 1999 Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods1999-09-0202 September 1999 Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods L-99-137, Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 31999-08-31031 August 1999 Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 3 L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl1999-08-31031 August 1999 Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl L-99-037, Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change L-99-012, Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B L-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999 Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001 L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes L-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999 Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by L-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999 Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999 Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6 L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC L-99-109, Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-62301999-07-0707 July 1999 Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6230 L-99-104, Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl1999-06-29029 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl L-99-093, Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.51999-06-25025 June 1999 Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.5 L-99-102, Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl1999-06-22022 June 1999 Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl L-99-101, Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal1999-06-22022 June 1999 Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages1999-06-17017 June 1999 Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195H4651999-06-16016 June 1999 Forwards for Filing Answer of Firstenergy Corp in Opposition to Petition for Leave to Intervene of Local 29, Intl Brotherhood of Electrical Workers. Copies of Answer Have Been Served Upon Parties & Petitioner by e-mail ML20195J5221999-06-16016 June 1999 Forwards Answer of Duquesne Light Co to Petition to Intervene of Local 29,International Brotherhood of Electrical Workers in Listed Matter.With Certificate of Svc L-99-100, Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-1091999-06-15015 June 1999 Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-109 L-99-095, Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys1999-06-15015 June 1999 Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys L-99-099, Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr1999-06-14014 June 1999 Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr ML20195H3731999-06-0303 June 1999 Forwards Petition to Intervene of Local 29,Intl Brotherhood of Electrical Workers in Matter of Firstenergy Nuclear Operating Co,For Filing L-99-090, Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request1999-06-0202 June 1999 Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request L-99-086, Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 11999-05-28028 May 1999 Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 1 L-99-089, Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b)1999-05-28028 May 1999 Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b) L-99-084, Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon1999-05-27027 May 1999 Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon L-99-082, Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS1999-05-17017 May 1999 Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS L-99-071, Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS1999-05-12012 May 1999 Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS 1999-09-03 Category:TEXT-SAFETY REPORT MONTHYEARL-99-154, Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with1999-09-30030 September 1999
[Table view]Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with L-99-139, LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With1999-09-0202 September 1999 LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With L-99-140, Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with L-99-126, Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With L-99-107, Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with ML20209D9531999-06-27027 June 1999 Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999 L-99-096, Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with L-99-078, Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable1999-05-0303 May 1999 Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable L-99-079, Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With ML20205L0401999-04-0909 April 1999 SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2 L-99-054, Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite1999-04-0505 April 1999 Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite L-99-058, Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with ML20196K7981999-03-25025 March 1999 Rev 4 to COLR, for Cycle 8 L-99-038, Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with ML20203E1181999-02-10010 February 1999 SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description L-99-019, Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced1999-02-0505 February 1999 Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced ML20196F7011999-01-31031 January 1999 BVPS Unit 2 Heatup & Cooldown Limit Curves During Normal Operation at 15 EFPY Using Code Case N-626 ML20203D4811999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Bvps,Units 1 & 2, in Accordance with NRC GL 97-02.With ML20207E6631999-01-28028 January 1999 Rev 0 to EMECH-0713-1, Operational Assessment of SG Tubing at Beaver Valley Unit 1,Cycle 13 ML20210G7041999-01-22022 January 1999 BVPS Unit 1 Facility Changes,Tests & Experiments for 980123-990122 ML20207E5861998-12-31031 December 1998 Annual Rept 1998 for Toledo Edison ML20207E5601998-12-31031 December 1998 Annual Rept 1998 for Pennpower ML20198B9021998-12-31031 December 1998 BVPS Unit 1 Simulator Four Yr Certification Rept for 1995-1998 ML20207E5901998-12-31031 December 1998 Dqe 1998 Annual Rept to Shareholders ML20199C9971998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Bvps,Units 1 & 2. with ML20207E5521998-12-31031 December 1998 Annual Rept 1998 for Ohio Edison ML20207E5761998-12-31031 December 1998 Annual Rept 1998 for Illuminating Co ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199F5341998-12-29029 December 1998 Safety Evaluation Granting Relief Requests 1-TYP-3-B3.140-1, 1-TYP-3-B5.70-1,1-TYP-3-RH-E-1-1,1-TYP-3-B-G-1, 1-TYP-3-APP-I-1,1-TYP-3-UT-1,1-TYP-3-N-509,1-TYP-3-N-521, 1-TYP-3-N-524,1-TYP-3-B3.120-1 & 1-TYP-3-C6.10-1 ML20198K8551998-12-21021 December 1998 SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1 ML20198A1631998-12-0909 December 1998 SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) Request L-98-229, Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with ML20195J3131998-11-12012 November 1998 Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief L-98-210, Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with ML20206G0291998-10-31031 October 1998 BVPS Unit 2 Facility Changes,Tests & Experiments for Period 971101-981031 ML20154R9121998-10-20020 October 1998 Safety Evaluation Accepting Proposed Changes to QA Program Description in Chapter 17.2 of BVPS-2 Ufsar.Proposed Changes Would Modify QA Organization to Allow Warehouse QC Inspectors to Report to Manager of Nuclear Procurement Dept ML20154P7491998-10-19019 October 1998 SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1 ML20198F7611998-10-0606 October 1998 Duquesne Light Co,Beaver Valley Power Station 1998 Emergency Preparedness Ingestion Zone Exercise, Conducted on 981006 ML20154C6711998-10-0101 October 1998 Safety Evaluation Concluding That Revised Model Identified in Dl Submittal Was Appropriate for Analysis of Installed Conduit Ampacity Limits.Determined That There Are No Outstanding Safety Concerns with Respect to Ampacity ML20154D5001998-09-30030 September 1998 Special Rept on Overview of BVPS-1 & BVPS-2 TS Compliance Issues & Corrective Action Taken L-98-197, Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods L-98-188, Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure1998-09-21021 September 1998 Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure L-98-178, Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with ML20155B5871998-08-28028 August 1998 Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed L-98-168, Monthly Operating Repts for July 1998 for Bvps,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Bvps,Units 1 & 2 L-98-157, Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product1998-07-29029 July 1998 Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product L-98-139, Monthly Operating Repts for June 1998 for Bvps,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Bvps,Units 1 & 2 L-98-119, Monthly Operating Repts for Bvps,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for Bvps,Units 1 & 2 1999-09-30 |
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'A Duqu@esne Light (412)393 7546 Beaver Valley No. 2 Unit Project Organization Telecopy 1412) 393-7889 SgGeoBl 8 2NRC-7-142 Shippingport, PA 15077 7
United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Significant Deficiency Reports 87-16 and 87-17
REFERENCE:
2NRC-7-132, dated May 13, 1987 Gentlemen This letter provides information regarding the above Significant Deficiency Reports (SDR's) on conduit sealing of 50 BVPS-2 Class lE items as mentioned in the reference. The attached information indicates that (1) The nineteen (19) RDF RTD's were not affected by these SDR's, (2) The four (4) Reed position indicators on the pressurizer PORV's (2 indicators per PORV) now have an alternate qualified sealing method installed, (3) For the ten (10) Target Rock SOV's inside containment, the installation of qualified seals has been completed. The seals located outside containment are now installed in accordance with the existing installation specification.
The above information and attachment is provided to address recent NRC concern on Significant Deficiency Reports 87-16 and 87-17. As indicated in the reference, a written report on these items will be provided to the NRC.
This completes all physical work associated with the Environmental Qualification Pr] gram with the exception of four (4) Bisco Seals around cable terminations to be located at the reactor vessel head solenoid operated vent valves 2RCS*SOV200A&B and 201A&B. The reactor vessel head must be in place prior to final determination of the conductor length and determining the exact location of the seal. This activity will be completed during Mode 5 and prior to entering Mode 4 - Hot Shutdown at the completion of initial core loading. Reactor remote head venting capability is not needed prior to this time.
8705280069 870525 g/\
PDR ADOCK 05000412 S PDR gp si
o United States Nuclear Regulatory Commission Mr. Harold R. Denton Significant Deficiency Reports 87-16 and 87-17 Page 2 The completion of all documentation associated with the Environmental Qualification Program was certified in our letter 2NRC-7-132 dated May 18, 1987.
Should there be any questions regarding the above, please contact our Mr. K. E. Woessner at 412/393-7739.
DUQUESNE LIGHT COMPANY J. J. Carey Vice President, Nuclear Group KEW/ bib MCE/KEW/SIG/DEF AR/NAR Attachment cc: Mr. P. Tam, NRC Project Manager Mr. J. Beall, NRC Sr. Resident Inspector Dr. T. E. Murley, NRC Region I Administrator INPO Records Center
United States Nuclear Regulatory Connission Mr. Harold R. Denton Significant Deficiency Reports 87-16 and 87-17 i Page 3 ..
COMMONWEALTH OF PENNSYLVANIA )
) SS:
COUNTY OF BEAVER )
On this I [ day of [hleV , /((7 , before me, a Notary Public in and for said Commondalth and County, personally appeared J. J. Carey, who being duly sworn, deposed and said that (1) he is Senior Vice President of Duquesne Light, (2) he is duly aut.horized to execute and file the foregoing Submittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge, flLA.lt2/ kh itMd
/ Notary Public wM S. fAITO'% 144AM MIM j 3ptPPl3GPt8190t0, WR W M COGSISSIOR EIPIES WI' 33 IE y en, FeneWole W d M 2
i e
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_. _ ..____ _ _ _ _ _._________ _ ____ _ _ _ _______.__.__ _ _ ______._ _ _______ _ _ ______ A _ __ _ _ _ _ ____ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _
Attachment This attachment provides a brief description of BVPS-2 equipment items relative to Significant Deficiency Reports 87-16 and 87-17. ,
SDR 87-16 involves installation of BISCO LOCA SEAL (conduit sealant) over braided wires as a deviation from field installation specifications. SDR 87-17 involves installation of conduit seals for PORV position indicators without SQC verification of graphoil tape installation.
The effect of these SDR's on DVPS-2 Equipment is discussed below.
19 RDF RTDS (SDR 87-16) (Inside Containment)
The method of conduit sealing of the RTD's does employ the j pouring of BISCO LOCA SEAL over inline butt splices, covered with Raychem sleeves, not continuous braided wire. This sealing method is in accordance with field installation specification 931 and is acceptable and qualified for BVPS-2 applications.
]
27 Target Rock SOV's (SDR 87-16) (Inside/Outside Containment)
Target Rock SOV's have been installed with BISCO LOCA SEAL (conduit sealant) poured and set over braided wires. This installation is not in strict accordance with field specification 931. Ten affected SOV's inside containment have been reworked and now comply with the specification. Although the "as
- installed" (BISCO over braided wire) is acceptable for SOV's installed outside containment due to low pressure (< l.00 psi) accident conditions, DLC has decided to rework the conduit seals to be in strict accordance with the field installation specification. All rework has now been completed. Only, the four seals associated with the reactor vessel head vent remain to l be installed.
4 Reed Position Indicators (SDR 87-17) (Inside Containment)
The SOC verification of graphoil tape on 4 conduit connections (2 connections each on PORV 2RCS*RV551A and 2RCS*RV551C had not been made as documented by N&D 39292. An alternate qualified seal has been provided and installed per N&D 39292 Rev. A disposition on all 4 of these indicators.
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