Part 21 Rept Re non-compliance for DG Control Sys.Licensee Revised Component Dedication Rept to Require Removal of Jumper & Require Checking Auxiliary Contact Arm Screws for Tightness.Gpu Only User Affected by NotificationML20134F574 |
Person / Time |
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Site: |
Oyster Creek |
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Issue date: |
11/04/1996 |
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From: |
Galeazzi D, Nuding M AFFILIATION NOT ASSIGNED |
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To: |
Hodge V NRC |
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References |
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REF-PT21-96 NUDOCS 9611060282 |
Download: ML20134F574 (4) |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20211M9481997-10-0303 October 1997 Supplemental Part 21 Rept Re Condition Effected Emergency Svc Water Pumps Supplied by Bw/Ip Intl Inc to Gpu Nuclear, Oyster Creek Nuclear Generation Station.No Other Nuclear Generating Stations Effected by Notification ML20211B7461997-09-24024 September 1997 Part 21 Rept Re Failure of Emergency Service Water Pump Due to Threaded Flange Attaching Column to Top Series Case Failure.Caused by Dissimilar Metals.Pumps in High Ion Svc Will Be Upgraded to 316 Stainless Steel Matl ML20140J1981997-06-12012 June 1997 Part 21 Rept Re Failures of GE Type CR120AD Relays Dedicated for SR Use.Resulting High Current Through Short Circuit Caused Magnet Wire to Fuse & Produced Energetic Arc at Failure ML20140A4761997-05-27027 May 1997 Provides Addl Info to 970429 Part 21 Rept Re Potential safety-related Problem W/Asco HV 266000-007J Scram Solenoid Pilot Valves.Corrective Actions Also Listed ML20140G5551997-04-29029 April 1997 Part 21 Rept Re Potential safety-related Problems W/Asco HV 266000-007J Scram Solenoid Pilot Valves (Sspv).Caused by Hardening of Core Disc in SSPV Pilot Head.Investigation Is Continuing ML20134F5741996-11-0404 November 1996 Part 21 Rept Re non-compliance for DG Control Sys.Licensee Revised Component Dedication Rept to Require Removal of Jumper & Require Checking Auxiliary Contact Arm Screws for Tightness.Gpu Only User Affected by Notification ML20078F6021995-01-30030 January 1995 Part 21 Rept Re Possibilities of Some Nonconforming Diodes May Have Been Used in Safety Related Spare Parts Provided for S4N,D4N,T4N & 2100C ML20056D7071993-07-15015 July 1993 Part 21 Rept Re Reportable defect-75 PSIG Relief Check Valve 1 Npt,Emd 9521844,Kepner 416C-1-75 ML20102B2071992-06-24024 June 1992 Part 21 Rept Re Cracking of Stellite 21 Hardfacing on Guide Nose of Poppets Supplied as Part of MSIV Leakage Improvement Mod.Initially Reported by Clei on 920522. Recommends That Liquid Penetrant Exam Be Performed 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 ML20248G2511989-04-0404 April 1989 Part 21 Rept Re Defect in Two Safety Relief Valves for Core Spray Sys Supplied by Lonergan.Relief Valves Ordered & Received for Installation & Two Valves Lifted Prematurely Removed from Sys & Sent to Offsite Test Facility 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 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 ML20210F4741986-09-16016 September 1986 Part 21 Rept Re Possible Sticking in Closed or Partially Open Position on Dresser 3050 Diaphragm Valves.Initially Reported on 850118.Disc Caps,Including Chamfers on Outside Diameter,Will Be Modified ML20203D0221986-07-14014 July 1986 Part 21 Rept Re Air Monitoring Sys Probes Exhibiting Blue Tip Rather than Normal White Tip & Insensitive to Chlorine. Caused by Improper Handling/Storage.Advisory Bulletin Encl. Item Not Reportable Per Part 21 ML20141D8051986-04-0101 April 1986 Part 21 Rept Re Model 402 Series Level Control Used for safety-related Application Shipped W/O Torque Check. Customers Will Be Notified by 860428 & Requested to Perform Torque Check.List of Plants Using Component Encl ML20210G9921985-08-13013 August 1985 Part 21 Rept Re Failure of Isolated Worm Shaft Gear When Certain Critical Speeds Combined W/Repetitive Transfer of Actuator Clutch Mechanism from Manual (Handwheel) to Motor Drive Mode.Two Possible Solutions Noted ML20126B7941985-06-0707 June 1985 Part 21 Rept Re Procurement of Replacement Parts from Dresser Industries for Electromatic Relief Valves.Caused by Failure of Supplier to Notify Util That Dash 3 Parts Being Supplied for Dash 2 Model.Parts Replaced ML20086U4251984-02-24024 February 1984 Followup Part 21 Rept Re Defective Mechanical Snubber Capstan Springs Supplied by Pacific Scientific.Affected Utils Listed.Purchasers Have Been Notified & Advised to Work Directly W/Pacific Scientific in Disposition 1998-05-21
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4451999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Oyster Creek Nuclear Generating Station.With ML20211P6731999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Oyster Creek Nuclear Generating Station.With ML20211A7051999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Oyster Creek Nuclear Station.With ML20209G0631999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Oyster Creek Nuclear Generating Station.With ML20212H5491999-06-18018 June 1999 Non-proprietary Rev 4 to HI-981983, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool ML20195E7961999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Oyster Creek Nuclear Generating Station.With ML20206N7431999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Oyster Creek Nuclear Generating Station.With ML20205P5401999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Oyster Creek Nuclear Generating Station.With ML20204C8201999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Oyster Creek Nuclear Generating Station.With ML20199E4671998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Oyster Creek Nuclear Generating Station.With ML20195E8321998-12-31031 December 1998 10CFR50.59(b) Rept of Changes to Oyster Creek Sys & Procedures, for Period of June 1997 to Dec 1998.With ML20198D2091998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Oyster Creek Nuclear Generating Station.With ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20195C4271998-11-0606 November 1998 Safety Evaluation Supporting Proposed Ocnpp Mod to Install Core Support Plate Wedges to Structurally Replace Lateral Resistance Provided by Rim Hold Down Bolts for One Operating Cycle ML20155J3021998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Oyster Creek Nuclear Generating Station.With ML20154R4981998-10-20020 October 1998 Core Spray Sys Insp Program - 17R ML20154L3051998-10-14014 October 1998 Safety Evaluation Accepting Licensee Request to Defer Insp of 79 Welds from One Fuel Cycle at 17R Outage ML20154Q3371998-09-30030 September 1998 Rev 8 to Oyster Creek Cycle 17,COLR ML20154L5571998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Oyster Creek Nuclear Generating Station.With ML20151V6311998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Oyster Creek Nuclear Generating Station.With ML20237D5691998-08-31031 August 1998 Rev 0 to MPR-1957, Design Submittal for Oyster Creek Core Plate Wedge Modification ML20237D5711998-08-18018 August 1998 Rev 0 to SE-000222-002, Core Plate Wedge Installation ML20237B0131998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Oyster Creek Nuclear Generating Station ML20236R0511998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Oyster Creek Nuclear Generating Station ML20249B2981998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Oyster Creek Nuclear Station ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20247F1891998-05-0505 May 1998 Risk Evaluation of Post-LOCA Containment Overpressure Request ML20247G0581998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Oyster Creek Nuclear Generating Station ML20216K0341998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Oyster Creek Nuclear Generating Station ML20151Y4651998-03-31031 March 1998 Non-proprietary Version of Rev 1 to GENE-E21-00143, ECCS Suction Strainer Hydraulic Sizing Rept ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216J0841998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Oyster Creek Nuclear Generating Station ML20203B2781998-02-16016 February 1998 10CFR50.59(b) Rept of Changes to Oyster Creek Systems & Procedures ML20203A3801998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Oyster Creek Nuclear Generation Station ML20198P1791997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Oyster Creek Nuclear Station ML20217C7591997-12-31031 December 1997 1997 Annual Environmental Operating Rept for Oyster Creek Nuclear Generating Station ML20197E9131997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Oyster Creek Nuclear Station ML20199E4561997-11-13013 November 1997 Safety Evaluation Accepting Ampacity Derating Analysis in Response to NRC RAI Re GL-92-08, Thermo-Lag 330-1 Fire Barriers, for Plant ML20199D4381997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Oyster Creek Nuclear Station ML20202E8511997-10-21021 October 1997 Rev 0 to Scenario 47, Gpu Nuclear Oyster Creek Nuclear Generating Station Emergency Preparedness (Nrc/Fema Evaluated) 1997 Biennial Exercise. Pages 49 & 59 of Incoming Submittal Were Not Included ML20211M9481997-10-0303 October 1997 Supplemental Part 21 Rept Re Condition Effected Emergency Svc Water Pumps Supplied by Bw/Ip Intl Inc to Gpu Nuclear, Oyster Creek Nuclear Generation Station.No Other Nuclear Generating Stations Effected by Notification ML20198J7361997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Oyster Creek Nuclear Generating Station ML20211B7461997-09-24024 September 1997 Part 21 Rept Re Failure of Emergency Service Water Pump Due to Threaded Flange Attaching Column to Top Series Case Failure.Caused by Dissimilar Metals.Pumps in High Ion Svc Will Be Upgraded to 316 Stainless Steel Matl ML20210V0181997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Oyster Creek Nuclear Generating Station ML20210L2961997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Oyster Creek Nuclear Station ML20149F9961997-07-18018 July 1997 Safety Evaluation Re Gpu Nuclear Operational Quality Assurance Plan,Rev 10 for Three Mile Island Nuclear Generating Station,Unit 1 & Oyster Creek Nuclear Generating Station ML20196H0111997-07-11011 July 1997 Special Rept 97-001:on 970620,removed High Range Radioactive Noble Gas Effluent Monitor (Stack Ragems) from Service to Allow Secondary Calibr IAW Master Surveillance Schedule. Completed Calibr on 970628 & Returned Stack Ragems to Svc ML20210L3081997-06-30030 June 1997 Corrected Page to MOR for June 1997 for Oyster Creek Nuclear Generating Station ML20141H2051997-06-30030 June 1997 Monthly Operating Rept for June 1997 for Oyster Creek Nuclear Station 1999-09-30
[Table view] |
Text
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Fax:9194461134 Nov 4 '96 17:48 P.01 M2 /3 !
- qE$I BNGINE SYSTEMS,INC. jJ=~]
l
! 1220 South Washington St. -
Rocky Mount, NC 27801 %_h,.5 $1. .-
- i Phone
- (919)977-2720
)
1 i Fax: (919)446-1134 f lg - 41996 I i l
TELEFAX j"'
) DATE: November 4,1996 i
COMPANY: Office of Nuclear Reactor Regulation FAXNUMBER: 301/415-1887 l
i ATTENTION: Vern Hodge
REFERENCE:
Report 10CFR21-0074 FROM: MichaelNuding Dear Sir. l Attached is our report 10CFR21-0074 for a 10CFR21 icpereble defect with four excitation contactors (EMD
(;9562575) supplied by ESI to GPU nuclear. GPU is the only user affected by this notification.
Should you have any questions, please let us know. )
Sincerely, Engine Systems,Inc.
. l m..ek, Michael Nuding, a{,\.J, Manager, Quality Assurance 3 9611060 A
yooh19 4
() PDR PDR
~l
Fax:9194461134 Nov 4 '96 17:48 P.02
~
l Report No.10CFR21-0074 NOVEMBER,4,1996
- i a
10CFR21 REPORTING OF DEFECTS l AND NON-COMPLIANCE
! COMPONENT: "EXC" Contactor, EMD #9562575 SYSTEM: EMD MP-45 diesel generator control systems
! CONCLUSION: Defect is Reportable in Accordance with 10CFR21 i
s l
a 5
2 5
PREPARED BY: #,b '
DATE: #M' Donald D. Gpl6azzi Engineering' Manager REVIEWED BY: //A L s / / d/ DATE: /m y / 99 <,
, Michael Nuding
- General Manager, Quality Assurance
._ ._... _ _ . _ _ . ._ _ _ . . __ _ . _ _ _ _ . _ _ _ _ _ . - _ _ . _ _ . ._ ._m. . _ _
i Fax:9194461134 tbv 4 '96 17:49 P.03 l 1 , '
a REPORT NO.10CFR21-0074 l
- PAGE: 10F 2 l i
SUMMARY
l I
i
- Engine Systems, Inc. (ESl) received notification on 10/22/96 from GPU Nuclear about i problems with EMD contactor #9562575. ESI had further discussions with GPU (Mr.
John Rogers) on 11/4/96. The problems reported by GPU are as follows:
l
- 1. A wire jumper was installed between one of the contactor coil terminals and one of
. the contactor auxiliary contact terminals. This jumper is normally supplied with the l contactor from EMD; however, it is not required for the wiring configuration in the j GPU diesel generator control system. If left connected on the contactor when i installed in the GPU control system, a short circuit is created in the DC control i power supply when the contactor is energized (causing the auxiliary contact to close). This condition was present on all four of the contactors supplied by ESI.
l 2. The connection of the stationary contact arm on the auxiliary contact block was loose. This condition was present on two of the four contactoss supplied by ESI.
{
I The contactor is designated "EXC" (excitation contactor) and is energized to provide
! excitation to the generator.
1 I
l COMPONENT
! EMD contactor #9562575.
! CUSTOMERS AFFECTED.
i l GPU Nuclear, Oyster Creek is the only user of this contactor is nuclear safety related i
service. 4 i DEFECT i
i
- 1. A wire jumper was installed between one of the contactor coil terminals and one of
- the contactor auxiliary contact terminals. This jumper is normally supplied with the contactor from EMD; however, it is not required for the wiring configuration in the
- GPU diesel generator control system. If left connected on the contactor when installed in the GPU control system, a short circuit is created in the DC control power supply when the contactor is energized (causing the auxiliary contact to j close). This condition was present on all four of the contactors supplied by ESI.
- 2. The connection of the stationary contact arm on the auxiliary contact block was
- loose. This condition was present on two of the four contactors supplied by ESI.
4 I
REPORT NO.10CFR21-0074
- PAGE: 2 OF 2 I
CORRECTIVE ACTION
- 1. GPU has removed the jumper and tightened the connection screws of the auxiliary contact station arm on all four contactors.
- 2. ESI has revised the component dedication report to require removal of the jumper and to require checking the auxiliary contact arm screws for tightness.
GPU is the only user affected by this notification. All contactors supplied to GPU have been corrected; therefore, no further corrective action is required.
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