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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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aus r - E PbrtlandGeneralElectricCeny syy David W. Cockf> eld Vice President, Nuclear May 26, 1989 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 Containment Electrical Penetration Assemblies (EPAs)
The attached report is submitted in accordance with Title 10 of.the Code of Federal Regulations, Part 21 (10 CFR 21). A defect has been identified in I
the integrity of wire crimp terminations in individual Containment EPA modules of the soft seal epoxy design. The supplier of the EPAs, Bunker Ramo Corporation, is no longer in business.
Please contact us with any questions or comments regarding this defect.
Sincerely, j
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Attachment e .
gg . c: U.S. Nuclear Regulatory Commission [] j ggrt ATTN: Document Control Desk l Washington DC 20555 - l oo wy, C00 co ;u i Mr. William T. Dixon c3 , i coo State of Oregon 88 Department of Energy h j.
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4 Mr. R. C. Barr ,
k$ NRC Resident Inspector 2 {
OfLLO Trojan Nuclear Plant / i
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4 121 S W Sanon Street Pomana Ore;pn 97204
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, trajen Nuclear PIEnt Document Control De:k s Docket 50-344 Attachment License NPF-1 May 26, 1989 Page 1 of 2 j 10 CFR 21 DEFECT REPORT l,
Portland General Electric Company Report No. : 89-01 121 SW Salmon Street Report Date: May 26, 1989 Portland Oregon 97204 l
TROJAN NUCLEAR PLANT Responsible Officer:
Mr. D. w. Cockfield, Vice President Nuclear Date Responsible Officer Received Information:
May 25, 1989 l Basic Component or Activity: i Electrical Penetration Assembly (EPA)
Manufacturer's Number: 50003326 i PGE Purchase Order: N-00318 Defective Component: Module (Soft Seal Epoxy Design)
Type: Low Voltage ait Instrumentation l 6-Firm Supplying Basic Component: (No longer in business)
Bunker Ramo Corporation i Amphenol Space and Missile Systems (SAMS) Division l 9201 Independence Avenue Chatsworth, California 91311 i
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.i Description of Defect and Substantial Safety Hazard That Could Be Caused: j On April 28, 1989 during EPA module maintenance, seven wire crimp l terminations within an EPA module failed to remain intact under a tensile !
load estimated at five to ten pounds-force. In subsequent testing, )
inadequate crimp terminations have been identified in those modules )
I associated with wire sizes #14 and #16 American wire gauge (AWG).
- 14 AWG wire is used to provide control and indication power for many )
safety-related valves. #16 AWG wire is used to provide signal j information for process instrumentation. If the wires were detached from the module conductors during a seismic event, the capability to prevent ,
or mitigate the consequences of an accident would be seriously degraded.
It is concluded that this design or manufacturer's construction !
deficiency could have created a substantial safety hazard. l I
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,. Krojan Nuclesr Pirnt Docum:nt Control Dsak 1 Docket 50-344 Attachment License NPF-1 May 26, 1989 l Page 2 of 2 l
Number and Location of Such Components in Use at the Trojan Nuclear Plant:
Nine safety-related or accident monitoring-related EPAs with crimp termi-nations of similar design are installed in the Containment Building wall of the Trojan Nuclear Plant. Four of these contain modules with #14 AWG wires. The remaining five contain modules with #16 AWG wires.
Corrective Acticn:
Integrity checks are being conducted by Portland General Electric Company (PCE) to identify inadequate crimp terminations affecting safety-related or accident monitoring-related equipment. The integrity check is a pass / fail test of the terminations with a specified tensile load applied.
Circuits associated with terminations that fail the integrity check are being rewired through terminations which have passed the check. Design drawings are being updated to reflect wiring changes. Testing, repairs, evaluation of associated potential concerns and operability verification of safety-rele.ted or accident monitoring-related EPA modules will be completed prior to startup from the current refueling outage.
One module experienced a large number of termination failures during the integrity check. This module will be replaced and destructively examined to determine the root cause of the failures. The completion date of this action has not been determined. .
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Other Pertinent Information:
Loose crimp termination problems in EPAs supplied by the Bunker Ramo ,
Corporation were previously reported to the Nuclear Regulatory Commission ]'
(NRC) as outlined in NRC Bulletin (NRCB) 82-04, " Deficiencies in Primary Containment Electrical Penetration Assemblies;" however, the actions to be taken by holders of operating licenses were directed to plants having EPAs utilizing a hard seal epoxy module design. Trojan Plant EPAs utilize a soft seal epoxy module design. l l
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