|
---|
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
_ . ,_ _ ___ _ .
l l , ,
l e l
j GPU Nuclear, Inc.
( One Upper Pond Road NUCLEAR Persippany, NJ 070541095 Tel201316 7000 June 12, 1997 6730-97-2176 .
U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
10CFR Part 2130-Day Repon i Oyster Creek Nuclear Generating Station Docket No. 50-219 Potential Failure of General Electric Type CR120AD Relays Oyster Creek has experienced failures of the General Electric Type CR120AD relays. The failure mechanism was identified as a manufacturing defect; specifically, part of the stan-end pigtail of the relay coils was off the insulating lead pad and, therefore, lying directly on the outer !
layer of the winding. This configuration placed insulation on the afTected length of magnet wire in a high-electrical-stress condition that led to dielectric breakdown at the failure site, thus effectively short circuiting the coil.
Although our evaluation of all ten potentially defective relays installed at Oyster Creek i concluded that their fail-safe mode does not impact plant safety, this potential defect is being conservatively reported in accordance with 10 CFR Part 21.21, (d) (3)(ii). l Should you have questions regarding this matter, please contact Yosh Nagai of our staff i at (201) 316-7974.
Sincerely, I
$W h li ,
T. G. Broug/hton \
President ,-
YN/ pip ' l((
c: Administrator, Region 1 NRC Resident inspector Oyster Creek NRC Project Manager 9706190261 970612 PDR 8 ADDCK 05000219 PDR ^
. . .- . - - - - ~ _ . - -. - _ - _ .. .= . .
~
l 10 CFR 21 - 30 DAY WRITTEN REPORT CONCERNING POTENTIAL FAILURE OF
. GENERAL ELECTRIC TYPE CR120AD RELAYS
- 1. Name and Address Of The Individual Informing The Commission:
Name: T. G. Broughton President ,
Address: GPU Nuclear, Inc.
One Upper Pond Road l' Parsippany, NJ 07054-1149
- 11. Basic Component Affected: j General Electric Type CR120AD Relays Ill. Firm Supplying Components:
l General Electric Nuclear Energy 175 Curtner Avenue San Jose, California 95125 IV. Nature of the Potential Defect:
On March 26,1996 Oyster Creek Generating Station issued a deviation report which identified an open coil in three CR120AD relays dedicated for safety-related use: one relay failed immediately after the installation when energized, another relay failed within two days during startup test and a third failed some months later during a surveillance test. Following these incidents a coil from one of the failed relays was sent to General Electric (GE) for analysis and the two remaining relays were sent intact to an independent research laboratory (Southwest Research Institute) for failure analysis.
After the analysis, Southwest Research Institute concluded that the principal problem observed in both relay coils was a manufacturing defect: specifically, part of the start-end pigtail of the coil was off the insulating lead pad and, therefore, lying directly on the outer layer of the winding, which was near the finish end of the coil. This configuration placed insulation on the affected length of magnet wire in a high-electrical-stress l condition that led to dielectric breakdown at the failure site, thus efTectively short l circuiting the coil. Resulting high current through the short circuit caused the magnet wire to fuse and produced an energetic arc at the failure site.
e There are ten (10) potentially defective relays installed at Oyster Creek. GPU Nuclear ,
has concluded that their fail-safe mode does not impact plant safety. However, there may be other nuclear facilities with these relays installed or kept in their warehouse without knowing of or about this potential failure.
V. Date on which Potential Defect Was Identified.
1 We determined on May 8,1997 that this potential failure of the GE relay CR120AD '
could have a generic implication and it was reported to NRC Operations Center, by phone, on May 9,1997.
VI. Number and Location of Components.
There are ten (10) potentially defective relays installed at Oyster Creek.
l Vll. Corrective Actions Taken if a premature failure of any of these relays occurs, with an "open" coil as the failure ;
mechanism, we may consider replacing the remaining nine relays. However, replacement I
of the ten relays is not scheduled at this time for the following reasons:
i) The previous failures of the CR120AD relays at Oyster Creek occurred either i immediately upon energization or within a few months of operation. Also, none of I the installed relays have failed since their installation approximately seven months l
l ago.
i ii) The probability of these relays having a potential manufacturing defect is extremely low.
iii) Our evaluation concluded that there is no impact to plant safety due to their fail-l safe mode feature.
l t
l l
i 1
i i i l I
.. ... . . . _ _ . . . . . . - _ . . - _ . . . . - , - - - , _ - _~ . ._ --
80 5 ,
l ,
i f
i l GPU Nuclear, Inc.
i A One Upper Pond Road l NUCLEAR Parsippany, NJ 070541095
[ Tel 201316 7000
! June 12, 1997 '
6730-97-2176 l
U. S. Nuclear Regulatory Commission Attention: Document Control Desk j
, Washington, DC 20555 l
l Gentlemen: .
Subject:
10CFR Part 2130-Day Report l Oyster Creek Nuclear Generating Station i l- Docket No. 50-219 Potential Failure of General Electric Type CR120AD Relays Oyster Creek has experienced failures of the General Electric Type CR120AD relays. The I failure mechanism was identified as a manufacturing defect; specifically, part of the start-end !
pigtail of the relay coils was ofTthe insulating lead pad and, therefore, lying directly on the outer laycr of the winding. This configuration placed insulation on the afTected length of magnet wire :
in a high-electrical-stress condition that led to dielectric breakdown at the failure site, thus ' i effectively short circuiting the coil.
l Although our evaluation of all ten potentially defective relays installed at Oyster Creek concluded that their fail-safe mode does not impact plant safety, this potential defect is being conservatively reported in accordance with 10 CFR Part 21.21,(d)(3)(ii).
- Should you have questions regarding this matter, please contact Yosh Nagai of our staff at (201) 316-7974.
Sincerely, MbMA l i T. G. Broughton President YN/ pip 4
i c: Administrator, Region 1 l NRC Resident inspector Oyster Creek NRC Project Manager
! . __._.l o ,
I -
10 CFR 21 - 30 DAY WRITTEN REPORT CONCERNING POTENTIAL FAILURE OF GENERAL ELECTRIC TYPE CR120AD RELAYS
)
I l l l l
- 1. Name and Address Of The Individual Informing The Commission:
l 1
l l Name: T. G. Broughton l
l President !
< l
- l. i l
Address: GPU Nuclear, Inc.
One Upper Pond Road Parsippany, NJ 07054-1149
- 11. Basic Component Affected: l l
l General Electric Type CR120AD Relays Ill. Firm Supplying Components:
General Electric Nuclear Energy 175 Curtner Avenue !
San Jose, California 95125 '
l IV. Nature of the Potential Defect: l l
On March 26,1996 Oyster Creek Generating Station issued a deviation repon which identified an open coil in three CR120AD relays dedicated for safety-related use: one l relay failed immediately after the installation when energized, another relay failed within l two days during startup test and a third failed some months later during a surveillance test. Following these incidents a coil from one of the failed relays was sent to General
! Electric (GE) for analysis and the two remaining relays were sent intact to an independent I l research laboratory (Southwest Research Institute) for failure analysis.
! After the analysis, Southwest Research Institute concluded that the principal problem observed in both relay coils was a manufacturing defect: specifically, part of the start-end pigtail of the coil was off the insulating lead pad and, therefore, lying directly on the outer layer of the winding, which was near the finish end of the coil. This configuration placed insulation on the affected length of magnet wire in a high-electrical-stress condition that led to dielectric breakdown at the failure site, thus efTectively short 4 circuiting the coil. Resulting high current through the short circuit caused the magnet wire to fuse and produced an energetic arc at the failure site.
1 . ___ _. __
i I
There are ten (10) potentially defective relays installed at Oyster Creek. GPU Nuclear {
has concluded that their fail-safe mode does not impact plant safety. However, there may l l
be other nuclear facilities with these relays installed or kept in their warehouse without l
' knowing of or about this potential failure. I V. Date on which Potential Defect Was Identified.
We determined on May 8,1997 that this potential failure of the GE relay CR120AD could have a generic implication and it was reported to NRC Operations Center, by l
phone, on May 9,1997.
l VI. Number and Location of Compnents.
There are ten (10) potentially defective relays installed at Oyster Creek.
Vll. Corrective Actions Taken
- if a premature failure of any of these relays occurs, with an "open" coil as the failure i i
mechanism, we may consider replacing the remaining nine relays. However, replacement i of the ten relays is not scheduled at this time for the following reasons:
l l i) The previous failures of the CR120AD relays at Oyster Creek occurred either immediately upon energization or within a few months ofoperation. Also, none of the installed relays have failed since their installation approximately seven months I ago. ,
i ii) The probability of these relays having a potential manufacturing defect is l extremely low.
l iii) Our evaluation concluded that there is no impact to plant safety due to their fail-safe mode feature.
l l
I i
a i
k l
y
,