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MONTHYEARML20126L2181980-11-0707 November 1980 Environ Qualification of Safety-Related Electrical Equipment to Harsh Environs,Ie Bulletin 79-01B, Technical Evaluation Rept Project stage: Other ML20126L2121981-05-27027 May 1981 Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment.Equipment,Required to Mitigate LOCA Following Accident in Harsh Environ,Found Acceptable Except as Noted in Section 3 Project stage: Approval ML20126L2081981-05-27027 May 1981 Forwards Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment.Evaluation Based on Util 800307,0425,0519,0905 & 810113 Submittals Project stage: Approval ML20140B6461981-09-0909 September 1981 Reiterates 810722 Request for Documents Re Show Cause Petition on Environ Qualification of safety-related Equipment at Facility Project stage: Request ML20197J7541986-05-0606 May 1986 Part 21 Rept 86-01 Re Limitorque Valve operator-motor Lead Insulation Exhibiting Brittlement.Motor Leads for Motor Actuators Will Be Replaced W/Properly Insulated Wire by 860801 Project stage: Other ML20199B4231986-06-0606 June 1986 Interim Part 21 Rept Re Defects Discovered in Limitorque Auxiliary Feedwater Flow Control Valve Motor Lead Insulation.Initially Reported on 860506.Replacements Will Not Be Available Until After 1986 Refueling Outage Project stage: Other 05000344/LER-1986-003, Forwards Clarification of Util Position Re 10CFR50.49 Compliance for 11 ECCS Valves Discussed in Rev 1 to LER 86-003,per 860905 Enforcement Conference & Concerns Raised in Insp Rept 50-344/86-321986-09-11011 September 1986 Forwards Clarification of Util Position Re 10CFR50.49 Compliance for 11 ECCS Valves Discussed in Rev 1 to LER 86-003,per 860905 Enforcement Conference & Concerns Raised in Insp Rept 50-344/86-32 Project stage: Other ML20210A6251986-09-11011 September 1986 Discusses Potential Generic Question Re Failure Potential for safety-related Valves,Per 860827 Meeting W/Util to Discuss QA Audit of Limitorque Procurement of Peerless Motors.Part 21 Related Project stage: Meeting ML20210V1941986-09-25025 September 1986 Informs of Results of RCS Thermal Expansion Monitoring Performed During Wk of 860902.Measurements Acceptable.Data Will Be Taken When RCS Temp Reaches 340 F,In Lieu of Holding Temp at 340 F for Analysis & Evaluation Project stage: Other ML20235Z7871986-10-15015 October 1986 Discusses Insp on 860318-0428 & Two Special Insps on 860513- 0612 & 860804-14 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty Project stage: Other ML20235Z7661987-04-29029 April 1987 Confirms Telcons Establishing 870518-22 as Dates for NRC Equipment Qualification Insp.Items to Be Included in Insp Listed.Encl Withheld Project stage: Other 1986-05-06
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 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 ML20127P1271992-12-11011 December 1992 Part 21 Rept Re Possibility That Addl Steel & Lead of Figure 2 Would Attenuate 80 Kev Photopeak of Xe-133 Resulting in Failure to Detect Concentration of Xe 102 Microcurie/Cc Range.Schematic Encl ML20127P1101992-11-25025 November 1992 Part 21 Rept Re Calibr,Wind Tunnel for Model 8500 Thermo Anemometer Out of Spec.No New Units Sold to Licensees within Past 12 Months.Range of Possible Calibr Errors Out of Spec Is 3% to 20%.Full Rept Will Be Submitted 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 ML20059B9191990-08-21021 August 1990 Part 21 Rept Re Defects in SA-194 Grade 6 Check Valve Bonnet Nuts Supplied to Westinghouse by Copes-Vulcan.On 900316 Discharge Check Valve Bonnet Found Cracked During Routine Maint.All Bonnet Nuts for Subj Valves 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 ML20247Q9241989-05-26026 May 1989 Part 21 Rept 89-01 Re Containment Electrical Penetration Assemblies Supplied by Bunker Ramo.Design or Mfg Const Deficiencies Could Have Created Substantial Safety Hazards. Integrity Checks Conducted to Identify Inadequate Crimps 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 ML20212B5121986-12-19019 December 1986 Part 21 Rept 86-01 Re Peerless-Winsmith Nuclear Grade Dc Motors.Sleeving Sys Will Be Developed & Applied Over Existing Lead Wire.Evaluation of Capability of Sleeved Lead Wire Anticipated by Third Quarter 1987 ML20215G6801986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20205C0371986-07-25025 July 1986 Part 21 Rept Re Stationary Sleeve on Atwood & Morrill Co,Inc MSIV Thrust Bearings Extending Past Rotating Face.Stationary Sleeve Machined to Provide .02 Inch Clearance Below Rotating Face ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires ML20199B4231986-06-0606 June 1986 Interim Part 21 Rept Re Defects Discovered in Limitorque Auxiliary Feedwater Flow Control Valve Motor Lead Insulation.Initially Reported on 860506.Replacements Will Not Be Available Until After 1986 Refueling Outage ML20195D2171986-05-27027 May 1986 Rev 1 to Part 21 Rept Re Dowel Displacement on Connecting Rod Bearings Purchased During Nov 1985 - Apr 1986.Initially Reported on 860421.Rod Bearings Will Be Inspected Dimensionally.Further Info Forthcoming ML20197J7541986-05-0606 May 1986 Part 21 Rept 86-01 Re Limitorque Valve operator-motor Lead Insulation Exhibiting Brittlement.Motor Leads for Motor Actuators Will Be Replaced W/Properly Insulated Wire by 860801 ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20136B3941985-11-0404 November 1985 Deficiency & Part 21 Rept Re Length of Keyway on Low Speed Shaft That Drives Speed Increaser Lube Oil Pump Mfg by Nuttall Gear Corp.Key Replaced W/Longer Key & Keyway Staked to Prevent Movement of Key ML20134Q1741985-08-29029 August 1985 Part 21 Rept Re Potential Maint Issues Associated w/Anker-Holth Snubbers.Owners of Anker-Holth Snubbers Will Be Informed of Problems & Sent Revs to Technical Instruction Manuals to Include Procedures for Seal & Fluid Maint ML17275A8021981-01-0909 January 1981 Part 21 Rept Re Failure to Provide Proper Control Components Intl Valves Supplying 2 Gpm Flow When in Closed Position. Caused by Valve Failure.Affected Licensees Notified & Selection of Alternative Method Underway 1994-01-17
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20210F8701999-07-22022 July 1999 Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar ML20209C6531999-07-0606 July 1999 Rev 8 to Defueled SAR, for Trojan Nuclear Plant ML20206H4501999-05-0505 May 1999 Safety Evaluation Supporting Amend 201 to License NPF-1 ML20206C9351999-04-23023 April 1999 Safety Evaluation Supporting Amend 199 to License NPF-1 ML20206C9751999-04-23023 April 1999 Safety Evaluation Supporting Amend 200 to License NPF-1 ML20207G9881999-03-0303 March 1999 Rev 6 to Trojan Nuclear Plant Decommissioning Plan ML20207J0781999-02-28028 February 1999 Update to Trojan ISFSI Sar ML20202G4511999-02-0202 February 1999 Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar ML20207C6981998-12-31031 December 1998 1998 Annual Rept for Trojan Nuclear Plant. with ML20195J2501998-11-17017 November 1998 Rev 7 to Trojan Nuclear Plant Defueled Sar ML20155E0561998-10-29029 October 1998 SER Approving Two Specific Exemptions Under 10CFR71.8 for Approval of Trojan Reactor Vessel Package for one-time Shipment to Us Ecology Disposal Facility Near Richland,Wa ML20155E0411998-10-27027 October 1998 Amend 7 to Quality-Related List Classification Criteria for Tnp ML20154R4121998-10-0202 October 1998 Requests Commission Approval,By Negative Consent,For Staff to Grant Two Specific Exemptions from Package Test Requirement Specified in 10CFR71 for Trojan Reactor Vessel Package & to Authorize one-time Transport for Disposal ML20237B6121998-08-13013 August 1998 Revised Trojan Reactor Vessel Package Sar ML20151W5471998-08-13013 August 1998 Rev 22 to PGE-8010, Poge Nuclear QA Program for Trojan Nuclear Plant ML20236Y2691998-08-0808 August 1998 Revised Trojan Rv Package Sar ML20249B4081998-06-17017 June 1998 Rev 6 to Trojan Nuclear Plant Defueled Sar ML20203E6291998-02-28028 February 1998 Trojan Nuclear Plant Decommissioning Plan ML20198T1741998-01-0404 January 1998 Rev 5 to Trojan Nuclear Plant Decommissioning Plan ML20248K6891997-12-31031 December 1997 Enron 1997 Annual Rept ML20203J3821997-12-31031 December 1997 Annual Rept of Trojan Nuclear Plant for 1997 ML20248K6931997-12-31031 December 1997 Pacificorp 1997 Annual Rept. Financial Statements & Suppl Data for Years Ended Dec 1996 & 97 Also Encl ML20203B0341997-11-26026 November 1997 Rev 5 to Trojan Nuclear Plant Defueled Sar ML20199F8141997-10-21021 October 1997 Requests Approval of Staff Approach for Resolving Issues Re Waste Classification of Plant Rv ML20216F4291997-07-25025 July 1997 Requests Commission Approval of Staff Approach for Reviewing Request from Poge for one-time Shipment of Decommissioned Rv,Including Irradiated Internals to Disposal Site at Hanford Nuclear Reservation in Richland,Wa ML20141F2311997-06-24024 June 1997 Rev 3 to PGE-1061, Tnp Decommissioning Plan ML20148K3541997-06-0909 June 1997 Safety Evaluation Supporting Amend 198 to License NPF-1 ML20148E8631997-05-31031 May 1997 Amend 6 to PGE-1052, Quality-Related List Classification Criteria for Trojan Nuclear Plant ML20148D2681997-05-23023 May 1997 Safety Evaluation Supporting Amend 197 to License NPF-1 ML20141H3181997-05-19019 May 1997 Safety Evaluation Supporting Amend 196 to License NPF-1 ML20140D9451997-03-31031 March 1997 Tnp First Quarter 1997 Decommissioning Status Rept ML20137K5811997-03-31031 March 1997 SAR for Rv Package ML20136D5591997-03-0606 March 1997 Safety Evaluation Approving Merger Between Util & Enron Corp ML20134B6231997-01-15015 January 1997 Draft Rev 3 of Proposed Change to Trojan Decommissioning Plan ML20217M2381996-12-31031 December 1996 Portland General Corp 1996 Annual Rept ML20217M2471996-12-31031 December 1996 Pacific Power & Light Co (Pacifcorp) 1996 Annual Rept ML20217M2551996-12-31031 December 1996 1996 Enron Annual Rept ML20135C3521996-12-31031 December 1996 Annual Rept of Trojan Nuclear Plant for 1996 ML20132G2831996-12-19019 December 1996 Rev 2 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan ML20132H0011996-12-12012 December 1996 Rev 20 to PGE-8010, Portland General Electric Nuclear QA Program for Trojan Nuclear Plant ML20132B8491996-12-12012 December 1996 Rev 20 to PGE-8010, Trojan Nuclear Plant Nuclear QA Program ML20135B5241996-11-27027 November 1996 Rev 4 to Trojan Nuclear Plant Defueled Sar ML20135B5341996-11-25025 November 1996 Trojan ISFSI Safety Analysis Rept ML20134M3381996-11-20020 November 1996 SER Approving Physical Security Plan for Proposed Trojan ISFSI ML20134K6621996-11-11011 November 1996 Decommissioning Plan,Tnp ML20134F1211996-10-31031 October 1996 Safety Evaluation Supporting Amend 195 to License NPF-1 ML20134F4661996-10-30030 October 1996 Final Survey Rept for ISFSI Site for Trojan Nuclear Plant ML20134P4321996-09-30030 September 1996 Tnp Quarter Decommisioning Status Rept,Third Quarter 1996 ML20137K5321996-09-0505 September 1996 Rev 0 to H Analysis of Residue Protocol ML20137K5091996-06-28028 June 1996 Summary Rept Poge Tnp SFP Project 1999-07-06
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May 6, 1986 Trojan Nuclear Plant Docket 50-344 License NPF-1 Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek CA 94596-5368
Dear Sir:
TROJAN NUCLEAR PLANT 10 CFR 21 Defect Report Valve Operator-Motor Lead Insulation The attached 10 CFR 21 Defect Report identifies a defect which we have evaluated to be reportable in accordance with 10 CFR 21 requirements. The defect results from an apparent deviation in the quality of the motor lead insulation in replacement motor actuators installed at Trojan during the 1985 refueling outage. The supplier of the motor actuators, Limitorque Corporation, has been contacted and has been made aware of the results of our 10 CFR 21 Evaluation.
Please direct any questions you may have regarding the technical issues to Manager, Nuclear Plant Engineering, Mr. R. L. Steele.
Sincerely, w/
Bart D. Withers Vice President Nuclear Attachment c: Director, Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington DC 20555 Mr. Lynn Frank, Director State of Oregon 8605200161 860506 Department of Energy PDR ADOCK 05000344 s PDR l !
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i 10 CFR 21 DEFECT REPORT Portland General Electric Company Report Number: 86-01 121 SW Salmon Street Report Date: May 6, 1986 Portland, Oregon 97204 TROJAN NUCLEAR PLANT Responsible Officer: Mr. B. D. Withers, Vice President Nuclear Date Responsible Office Received Information: May 6, 1986 Basic Component or Activity: Electric Actuator (Valve Operator)
Type: SKB-000; 2 ft-lbs 125 Volts DC, Nominal PGE Purchase Order N-29175 Limitorque Order No. 3M4515 Firm Supplyina Basic Component: Limitorque Corporation PO Box 11318 Lynchburg, Virginia 24506 Description of Defect and Substantial Safety Hazard That Could be Caused:
As reported in Trojan Licensee Event Report No. 50-344/86-01, following a Plant trip on February 8,1986, operation of the "A" train auxiliary feedwater (AFW) flow control valve (CV-3004D1) to the "D" steam genera-tor was interrupted. The power supply fuse to the valve motor operator blew because of a motor lead short circuit. As indicated in LER 86-01, the probable cause of the blown fuse was the breakdown of the internal motor lead insulation resulting in a short circuit path to the grounded case of the valve operator.
During further evaluation and inspection of the AFW flow control valve operators, the motor lead insulation has exhibited a brittle nature.
Movement of the leads during maintenance could cause cracks in the brittle insulation. The weakened insulation would then be subject to failure under the normal vibration and operating environment of the motor actuator.
The Limitorque Corporation was contacted regarding the brittle nature of the insulation. Limitorque provided PCE with a repair procedure (appli-cation of Ray-Chem heat shrink tubing over the existing leads) should additional failures be identified. Further discussions with Limitorque indicate that the brittle condition of the insulation may be a quality control problem with the subcontractor (H. K. Porter) that supplied the motors to Limitorque. Consequently, Limitorque has established a program for the repair of the valve actuators that were supplied to Trojan with the apparent insulation defect. PGE informed Limitorque that an evaluation under 10 CFR 21 would be performed.
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- r Page 2 The results of the 10 CFR 21 evaluation indicate that a substantial safety hazard could exist should the insulation breakdown prevent the closure of an AFW flow control valve. During a feedwater line break accident, the AFW flow to the affected feedwater line must be isolated.
This action assures that sufficient feedwater flow is delivered to the intact feedwater lines and steam generators. The inability of the operator to take action to close the valve within 10 minutes would defeat the safety function of the AFW System to deliver an adequate volume of feedwater to the intact steam generators.
Number and Location of Such Components in Use at the Trojan Nuclear Plant:
The Trojan design (Four-Loop Westinghouse Pressurized Water Reactor) uses a total of eight AFW flow control valves in two redundant and independent safety-related trains. The valves are located in the Main Steam Support Structure between the Turbine Building and the Containment Building.
This is the only application for this particular type of direct current (de), 125-volt, valve motor actuator at Trojan.
Corrective Action:
The motor leads for the motor actuators will be replaced with properly insulated wire as recommended by the Limitorque Corporation. Every effort will be made to complete this work prior to the conclusion of the refueling outage on June 11, 1986. A completion date of August 1, 1986 will be met in any case.
Other Pertinent Information:
The motor actuators with the apparent insulation problem were installed in the Trojan Nuclear Plant in accordance with Plant design change, RDC 84-104. The AFW flow control valve actuators were upgraded in order to meet the environmental qualification requirements for electrical equipment located in the Main Steam Support Structure. The modification was completed during the 1985 refueling outage. ,
l Attached for reference is a copy of the Certified Information Sheet from the Limitorque Corporation which provides specific details regarding the electric actuator.
This report represents both the initial and final written notification to the NRC of the 10 CFR 21 defect.
MHM/kal 0822W.586
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LIMITCREUE CORPORATIUN P.O. Box 11318, Lynchburg, VA 24506 CERTIFIED INFORMATION SHEET - ELECTRIC ACTUATOR Lirnitorque Order No. 3M4515 Customer Name Portland Oregon General Electric Co.
Customer P.O. No. S.O. No.
N-29175 a x 7.. ,. ,
Unit Type & Size SMB-000 Motor 2 Ft.Lbs. Sultable for Volts DC Phase Cycle 125 Volts 1900 RPM Approximate Amps Approximate Amps Approximate Full Load 1.6 Locked Rotor 15.9 H.P. .144 Unit Enclosure Weatherproof Submersible ( ft. Head for hrs.)
Explosionproof Class Group (s) Div. 3 Nuclear Outilne Drawing: 02-403-0245-2 au mns _ ) _ )
Wiring Diagram: 15-476-1340-3 c y -) ; y 20, n . 2 . i ,
Limit Switch Compartment Heater 120 volt 25 watt Motor Heater 120 voit 40 watt CX8000lXGN N100tNXW0%)HE26XX XXX X X X X ooh p Nud X O)#00008tXXXX XX XX XX XX XNtM XX X Mechanical Dial Position Indicator X sNplied supplied Spur or Bevel Gear Attachment shplied supplied Ratio Handwheel Diameter inches (if other than standard) with spinner Position A B supplied (Applies to Electric / Manual Combinations only)
Tagging and Remarks:
Inside Containment, Safety Related, Qualified per Limitorque Qualification Report #B0009 In accordance with the actuator qualification, motor "T" drains must be field installed in place of the two lowest motor drain plugs. Motor "T" drains are tagged and located in the Limit Switch Compartment on shipment from Limitorque.
l (1) Diazo Mylar ENCLOSED:
All drawings and information listed above are certified for construction. Please advise us at once should you require any changes or corrections, as we are proceeding to manufacture in accordance with the above information. _
Limitorque Certification Department Revision By Name ,.c _hh Date FEB 0 5 1985 Date ,_ .,
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