|
---|
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
. . - -_ ._ _ _ _ _ _ - - . _ _ _ _ _ . . _ . _ . _ . _ _ _ . _ _ _ - . _ . _
8:55 : 301 816 5101:c 1/ 4
.y.NT BY:lM/ll' IN1GNATl0NAL-LA: 3 24-37 :- 1EONICAL SYC GRf%
UW/IP internat6onal, Inc.
P n, , o,.m c l g ;;,-
ow ur wei
'r=ri,,
[*; -r
)
w.
n-*
h sw ;
Cor*vuoai ri +.
24 September.1997 i
II.S. Nuclear Regulatory commission Attn: Document Control Desk Washington, D.C. 20555 :
Not:Jication Pursuant to Title 10, CFR. Part 21 Gentlemen: .
Dds letter transtnits a Nottfication ofDefects and Non-cor!fonnance in accordance with the requirements of 10 CFR, Part 21. The attached Notification. CFRN 97 01, reports a corulition which efects Emergemy Service Waterpumps supplied by BW/IP International, Inc.to GPU, oyster Creek Nuclear Generating Station.
This transmittal completes the notification requirements on this issue.
\'ery truly yours,
~ //f :;
u.,j,,",'#Nn.*ema .
Manager, Nuclear Products Operations Attach, l
cc: Part 21 Rvaluation Board Members 1
500G1 135RME,IEE
-9709260006 970924 8 PDR- ADOCK.05000219f" PDR s 8
SD7. flYS/IP IMLRAAll0NAL-LA: 9-24-37 : 8:55 : TEGINICAL SYC GRP- 301 810 5151:s 2/ 4 L i
NOTIFICATION NO. CFRN 97-01 i
DATE: 24 September 1997 NOTIFICATION OF A REPORTABLE ISSUE PURSUANT TO 10 CFR 21 TO: U. S. Nuclear Regulatory Commission i, Attn: Document Control Desk i Washington, D.C. 20555 NAME AND ADDRESS Ol' INDIVIDUAL INFORMING Tile COMMISSION:
Mr. Woody Larie OW/IP Intamational,Inc.
Pump DMston 2300 EastVernon Avenue Vemon, CA 900EB (213) 587-6171 For Technical Information Contact Dr. Kent Huber BW/IP Evaluation No. CFR 97 007 IDENTIFICATION OF THE FACILl1Y, THE ACTIVITY, OR THE DASIC COMPONENT SUPPLIED FOR SUCH FACILITY OR ACTIVITY WITHIN THE UNITED STATES WHICH FAILS TO COMPLY OR CONTAINS A DEFECT:
Facility: GPU Nuclear, Oyster Creek Nuclear Generation Station Bar,ic Component: Emergency Service Water Pump UWAP Model 16(2H 4 stage VIP 1
(DENTIFICATION OF THE FIRM SUPPLYING THE BASIC COMPONENT WHICH FAILS TO COMPLY OR CONTAINS A DEFECT: r BWAP International. Inc.
Pump DMsion:
2300 E.Vernon Avenue L.os Angeles, CA 90058 Page1 L
.,n. , , - , . . - . , , . .
,+- . , . , . , , , . , . . , . , - - , . - , , , . . - , , , _ , . . - , , , , _ , , - - - - , , , , . , , -
$LN1. liY:15%/ll' IN1LDAll0NAL LA: 0-24-97 : 8:50 : lLCilNICAL SVC GRP- 301810 5151:r at i NOTIFICATION NO. CFRN 97-01 ,
NATURE OF THE DEFECT OR FAILURE TO COMPLY AND THE SAFETY HAZARD WHICH IS CREATED OR COULD BE CREATED BY SUCH DEFECT OR FAILURE TO COMPLY:
An Emergency Service Water pump fa; led during a sito Operability Test. Inspection revealed the threaded flange attaching the column to the top series case had failed. Utility attributed failure to dissimilar metals: a cast iron flange was Installed between a stainless steel column pipe and a stainless steel top caso. Utility removed a second pump from service which had similar metallurgy Failure of the pump would preclude its ability to perform its intended safety function.
T THE DATE ON WHICH THE INFORMATION OF SUCH DEFECT OR FAILURE TO COMPLY WAS OBTAINED:
DW/IP International,Inc., was informed of the flange failure on 21 August 1997.
IN THE CASE OF A DASIC COMPONENT W;1lCl4 CONTAINS A DEFECT OR FAILS TO COMPLY, THE NUMDER AND LOCATION OF ALL SUCH COMPONENTS IN USE AT, SUPPLIED FOR, OR DEING SUPPLIED FOR ONE OR !!. ORE FACILITIES OR ACilVillEE SUBJECT TO THE REGULAllONS:
GPU Nuclear, Oyster Crcck Station, purchased ci;ht pumps in which cast iron and stzinless $1001 parts are in contact in a high son opphcation. Two pumps have been scrapped The matenal compatibihtecs of the six pumps that are in operation at GPUN have either been corrected or are in the process of being corrected.
Initial evaluation indcates that this is an isolated incident limited to only this location. Ilowever, a review ts being performed of the installed base of BW/tP pumps to identify the number and locat on of any other pumps in similar nuclear applicctions that may have materialcornpatibchty concerns.
Page 2
,, . - . , ..m, ys __ . ,. ,.
y-.m _
SLNI 1(Y IW/II' IMIRM110ML-LA; 3-21-37 8:50 llCilNICAl SVC GRl'-- 301 816 5151.s 1/ 1 NOTiflCATlON NO. CFRN 97-01 THE CORRECTIVE ACTION WHICH HAS, IS BEING, OR WILL BE TAKEN: THE NAME OF 1HE INDIVIDUAL OR ORGANIZATION RESPONSIBLE FOR THE ACTION: AND THE LENGTH OF TIME THAT HA? UEEN OR WILL DE TAKEN TO COMPLETE THE ACTION:
nW/IP recornmends that utstity upgrado all pumps in high ion services to 316 stainicss steel material and install isolation kits between the stainless steel column flange and the cast iron discharge head. Two pumps from the Oyster Creek station are currently in the UW!lP Service Center for refurbishmont and materials upgrading. GPU has been advised to installisolation kits on two units which are currently in operation.
ANY ADVICE RELATED TO THE DEFECT OR FAILURE TO COMPLY ABOUT THE FACILITY, ACTIVITY, OR DASIC COMPONENT THAT HAS BEEN,IS BEING, OR WILL DE GIVEN TO PURCHASERS:
Pumps were purchased by GPUN in 1986 as commercialitems not subject to 10CFR, Part 50, Appendix B or 10CFR, Part 21, requirements. GPUN subsequently designated the pumps as Safety related equipment.
The dedication process performed by GPUN established the onginal design as the design basis of the cquipment for future safety-related purchases and repairs Pump was installed in a beackish water environment which caused corrosion of the top case flange. Based on inspection observations, BW!lP recommended,in 1993, that GPUN upgrade all pump components to 316 stainless steel. However, orie pump, SIN 651 N-07t.B. was refurbished with GPUN supplied parts, as directed ie the GPUN purchase order to support plant schedules, and returned to the s,ite with a combination of C l.
and stainless steel materials.
In July 1997, the top case f;ange on one of the pumps crperienmd a total fadure inspection showed a second pump alt.o had similar materials of construction both pumps were removed hom sernce rend returned to DW/IP International for iefurbishing.
Page 3 d
T O
SENERAL INFORMATION or OTiiER EVENT NUMBER: 32985 LICENSEE 'DW/IP INTERNATIONAL, INC. NOTIFICATION'DATE: 09/24/97 CITY: LOS ANGELES REGION: 4 NOTIFICATION TIME: 12:00 (ET)
COUNTY: LOS ANGELES STATE: CA EVENT DATE: 09/24/97-LICENSEN: AGREEMENT: Y EVENT TIME: 08:55(PDT)
DOCKET: LAST UPDATE DATE: 09/24/97 NOTIFICATIONS ELMO COLLINS RDO NRC NOTIFIED BY: W. LANE (VIA FAX) VERN HODGE (NRR) FEMA 10 OPS OFFICER: STEVE SANDIN TOM MOSLAK (RIDO)
. EMERGENCY CLASS: NOT APPLICADLE 10 CFR SECTION:
2CCC 23.21 UNSPECIFIED PARAGRAPil EVENT TEXT PART 21 NOTIFICATION THE EMERGENCY SSRVICE WATER PUMP, BW/IP MODEL 16-Gil 4 -STAGE VTP FAILED DURING A SITE OPERADILITY TEST AT T.lE OYSTER CREEK GENERATING STATION. AN INSPECTION REVEALED TilAT THE THREADED FLANGE ATTACllING Tlid COLUMN TO Ti!E TOP SERIES CASE IIAD FAILED. TIIE UTILITY (GPU) ATTRI!30TED Ti!E FAILURE TO DISSIMILAl. METALS; A CAST IRON FLANGE WAS INSTALLED BETWEEN TIIE STAINLESS STEEL COLUri4 PIPE AND A STAINLESS STEEL TOP CASE. BW/IP REVIEWED TIIE UTILITIES UVALUATION AND RECOMMENDED TilAT ALL SUCl! PUMPS IN !!IGH ION SERVICES DE UPGRADED TO 316 STAINLESS STEEL MATERIAL.
-w..__
i