ML18096B242
ML18096B242 | |
Person / Time | |
---|---|
Site: | Salem, Hope Creek, Cooper, Fort Calhoun ![]() |
Issue date: | 02/01/1993 |
From: | Zahuranec E CRAWFORD FITTING CO. |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
REF-PT21-93 NUDOCS 9302100167 | |
Download: ML18096B242 (2) | |
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217A1691999-09-22022 September 1999
[Table view]Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20217M0211999-09-20020 September 1999 Part 21 Rept Re Possible Deviation of NLI Dc Power Supply Over Voltage Protection Circuit Actuation.Caused by Electrical Circuit Conditions Unique to Remote Engine Panel. Travelled to Hope Creek to Witness Startup Sequence of DG ML20211D6491999-08-25025 August 1999 Part 21 Rept Re Nonconformance within LCR-25 safety-related Lead Acid Battery Cells Manufactured by C&D.Analysis of Cells Completed.Analysis of Positive Grid Matl Shows Nonconforming Levels of Calcium within Positive Grid Alloy ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML20202F6861999-01-26026 January 1999 Engine Sys,Inc Part 21 (10CFR21-0078) Rept Re Degradation of Synchrostat Model ESSB-4AT Speed Switches Resulting in Heat Related Damage to Power Supply Card Components.Caused by Incorrect Sized Resistor.Notification Sent to Customers ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20247G6131998-05-13013 May 1998 Part 21 Rept Re Defect Contained in Automatic Switch Co, Solenoid Valves,Purchased Under Purchase Order (Po) 970161. Caused by Presence of Brass Strands.Replaced Defective Valves ML20217A1531998-04-16016 April 1998 Closure to Interim Part 21 Rept Submitted to NRC on 970929. New Date Established for Completion of Level I & 2 Setpoint Project Committed to in .Final Approval of Setpoint Calculations Will Be Completed by 980531 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20217D4141997-09-29029 September 1997 Interim Part 21 Rept Re Errors Noted During Preparation of ITS Surveillance Test Procedures Using GE Calculated Setpoints.Setpoint Calculations Will Be Reviewed,Corrected & Approved to Establish Significance of Errors ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process ML20141C4931997-06-17017 June 1997 Part 21 Rept Re Nonconforming Raw Water Pump Impellers.Raw Water Pump Assembly AC-10D Replaced Due to Normal Wear on Pump Internals,Namely Pump Impellers & Impeller Liners ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum ML20148D1201997-05-23023 May 1997 Part 21 Rept Re Replacement Impellers for Byron Jackson Raw Water Pumps Having Blade Dimensions Out of Tolerance Due to Normal Wear on Pump Internals.Replaced Raw Water Pump Assembly AC-10D ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20137G6261997-03-25025 March 1997 Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause ML18102A3701996-09-0606 September 1996 Part 21 Rept Re Installation of NUS Model OCA 801 Signal Isolator Modules & Model Mth 801 Signal Summator Modules. Replacement Modules Including Spares for Plant,Unit 2 Have Been Inspected by Vendor & Repaired ML18102A3381996-08-21021 August 1996 Part 21 Rept Re Chipping of Latching Mechanism Props Installed in GE 4 Kv magne-blast Circuit Breakers,Type AM-4.16-350-2H.Two Affected Breakers Have Been Returned to Vendor ML18102A5591996-08-0808 August 1996 Part 21 Rept Re Defect in NUS Model OCA801 Signal Isolator Modules.Replacement Modules Installed in Reactor Control & Protection Sys ML20096A4021995-12-28028 December 1995 Interim Part 21 Rept Failure of Scram Discharge Vol Drain Valve 1BFHV-F011.Possible Causes of Failure,Includes Spring mis-adjustment,change in Spring Adjuster Setting & Spring Relaxation.Further Investigation Ongoing ML18101A8771995-08-0404 August 1995 Interim Part 21 Rept Re Potentially Reportable Deficiency in Edward Valve Model 838YT Check Valves Due to Disk Exhibiting Excessive Leakage.Disk from Original Valve Cleaned, Inspected & Installed in Replacement Valve ML18101A8611995-08-0101 August 1995 Interim Part 21 Rept Re Velan Valve Corp Check Valve Failure to Close.Insp of Internals Showed Moderate Wear in Gap Between Valve Disc & Hanger Arm.New Disc Installed & Valve Tested Satisfactorily ML20082S7401995-04-26026 April 1995 Part 21 Rept Re Hinge Arms Associated W/Sixteen Swing Check Valves Mfg by Anchor-Darling Valve Co ML20081L7701995-03-29029 March 1995 Initial Part 21 Rept Re Anchor-Darling Check Valve Hinge Arms.Cs Pump B Discharge Check Valve Failed to Close in Nov 1994 Because Butt Stop on Hinge Arm Not of Sufficient Length.New Butt Stop Hinge Arm,Hinge Pin & Disc Installed ML18038A8971994-09-0707 September 1994 Part 21 Rept Re Defect in Latching Mechanism of Potter & Brumfield Relay on C&D High Voltage Shut Down Alarm Assembly Printed Circuit Boards.Pull Test on Relay Reset Button Incorporated Into Receiving Insp Procedures LIC-94-0164, Part 21 Rept Re Nonconformance in Potentiometers W/ Attachable Switches Mfg by Ohmite & Supplied by Abb C-E. Nonconforming Components Returned to Abb C-E & Abb C-E Issued Info Bulletin 94-02,providing Appropriate Guidance1994-08-24024 August 1994 Part 21 Rept Re Nonconformance in Potentiometers W/ Attachable Switches Mfg by Ohmite & Supplied by Abb C-E. Nonconforming Components Returned to Abb C-E & Abb C-E Issued Info Bulletin 94-02,providing Appropriate Guidance ML18100B2391994-07-27027 July 1994 Part 21 Rept Re Signal Summators PM-505B & 506B Found to Saturate High When Summators Lose Power & Reenergized. Summators Powered from Independent Vital Instrument Buses & Inverters.Design Changes Implemented ML20071J5271994-07-26026 July 1994 Part 21 Rept Re Ohmite Model CU1021 & CU1031 Potentiometers Model CS-1 Switches Supplied by Abb C-E.Verified That Potentiometers/Switches Combinations Not Installed at FCS in Location Which Could Have Adverse Safety Implication ML18100B2271994-07-25025 July 1994 Part 21 Rept Re Cracking in Valve Stem & Plug Connection Pinning Collar Area on PORVs 1PR1 & 1PR2.Caused Attributed to Either IGSCC or Hydrogen Assisted Cracking.Porv Internals Replaced W/Internals Mfg from SS 316 Matl W/Plug Stellited ML18100B2101994-07-14014 July 1994 Deficiency Rept Re PORV Plug & Stem Material Defects. Initially Reported 940714.PORV Internals Were Replaced W/Plug Stellited ML18100B1911994-06-30030 June 1994 Initial Part 21 Rept Re Deficiency in Signal Summators PM-505B & PM-506B Supplied by Westinghouse.Design Changes Implemented & Operators Made Aware of Affects of Power Supply Transient on Summator Operability ML20063M1701994-03-0202 March 1994 Part 21 Rept Clarifying & Supplementing Info Provided by Licensee Re Deficiency in Qualified Life Calculation for Microswitches Mfg by Comsip,Inc. Subj PTW-5300 Dc Indicators Supplied by Comsip,Inc,Mfg by Microswitch Corp ML18100A7681993-12-13013 December 1993 Interim Part 21 Rept Re Discovery That Ge/Alco EDGs High Pressure Injection Tube Studs Did Not Meet Correct Matl non- Std & Not Correct Geometry.All Nonconforming Studs Identified & Replaced ML20046C6591993-08-0505 August 1993 Part 21 Rept:On 930429,deficiency Identified Re Heat Damage to Comsip Series PTW-5300 Dc Powered Microswitches.Initially Reported on 930709.Safety-related Dc Microswitches Will Be Replaced Prior to 931230 ML20128H9931993-02-0909 February 1993 Interim Deficiency Rept Re Defect in Replacement EDG Fuel Oil Pumps Supplied by Colt Industries (Fairbanks Morse Engine Div).Initially Reported on 930111.Plugs & O-rings Repositioned.Vendor Requested to Perform Evaluation ML18096B2421993-02-0101 February 1993 Part 21 Rept Re Possible Matl Defect in Stainless Steel Swagelock Tube Fittings.Initially Reported on 921218.List of Part Numbers,Heat Codes & Addl Affected Customers Encl ML20127K8811993-01-0606 January 1993 Part 21 Rept Re Engine Driven Fuel Oil Pump Being Returned for Proper Configuration Due to Portion of O Ring Missing from Plug 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 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl 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 ML20116L4311992-10-20020 October 1992 Followup to Part 21 Rept from Consolidating Power Supply, Inc Re Purchase & Procurement of 24-inch Flange at Facility Which Failed to Meet ASME Code Class III Requirements.Flange Purchased by Conex Pipe Sys,Inc.Investigation Underway ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20101L0791992-06-29029 June 1992 Final Part 21 Rept Re Defect in Assembly Process for Gh Bettis Containment Atmosphere Control Sys Valve Replacement Actuators.Initially Reported on 920529.Air Filter Installed in Compressor Main Air Line to Prevent Contamination 1999-09-22 Category:TEXT-SAFETY REPORT MONTHYEARML20217F1501999-10-12012 October 1999
[Table view]Special Rept:On 990929,south Plant Vent (SPV) Range Ng Monitor Was Inoperable.Monitor Was Inoperable for More than 72 H.Caused by Electronic Noise Generated from Noise Suppression Circuit.Replaced Circuit ML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20217G7461999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Cooper Nuclear Station LIC-99-0096, Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20212K9781999-09-30030 September 1999 Safety Evaluation Accepting USI A-46 Implementation Program ML18107A5571999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr ML18107A5581999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr ML20217N6531999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Hope Creek Generating Station,Unit 1.With ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20217M0211999-09-20020 September 1999 Part 21 Rept Re Possible Deviation of NLI Dc Power Supply Over Voltage Protection Circuit Actuation.Caused by Electrical Circuit Conditions Unique to Remote Engine Panel. Travelled to Hope Creek to Witness Startup Sequence of DG ML20211N5531999-09-0808 September 1999 Safety Evaluation Supporting Amend 121 to License NPF-57 ML20211J9321999-09-0202 September 1999 Safety Evaluation Concluding That Licensee Proposed Alternatives Provide Acceptable Level of Quality & Safety. Proposed Alternatives Authorized for Remainder of Third ten- Yr ISI Interval for Fort Calhoun Station,Unit 1 LIC-99-0084, Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With ML20212C5001999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cooper Nuclear Station ML18107A5301999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 ML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML20216E6431999-08-26026 August 1999 Rev 19 to TDB-VI, COLR for FCS Unit 1 ML20211D6491999-08-25025 August 1999 Part 21 Rept Re Nonconformance within LCR-25 safety-related Lead Acid Battery Cells Manufactured by C&D.Analysis of Cells Completed.Analysis of Positive Grid Matl Shows Nonconforming Levels of Calcium within Positive Grid Alloy ML20211B3781999-08-13013 August 1999 Special Rept 99-002:on 990730,NPV Radiation Monitoring Sys Was Declared Inoperable.Caused by Voltage Induced in Detector Output by Power Cable to Low Range Sample Pump. Separated Cables & Secured in Place to Prevent Recurrence ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF). ML20210U4721999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Hope Creek Generating Station,Unit 1.With ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr ML18107A4821999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr ML20210R1961999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fcs,Unit 1 ML20210R0381999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Cooper Nuclear Station ML20210J2921999-07-29029 July 1999 Special Rept:On 990406,OG TS & Associated Charcoal Absorbers Were Removed from Svc.Caused by Scheduled Maint on Hpci. Evaluation of Offsite Effluent Release Dose Effects Was Performed to Ensure Plant Remained in Compliance ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML20210G2181999-07-27027 July 1999 Safety Evaluation Supporting Amend 192 to License DPR-40 ML20216D8331999-07-26026 July 1999 Safety Evaluation Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given HCGS Design,Operation & History ML20216D8721999-07-26026 July 1999 Review of Submittal in Response to USNRC GL 88-20,Suppl 4: 'Ipeees,' Fire Submittal Screening Review Technical Evaluation Rept:Hope Creek Rev 1:980518 ML20210F3331999-07-22022 July 1999 Safety Evaluation Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3.Finds That Proposed Alternative for RR-B3 Provides Acceptable Level of Quality & Safety & Authorizes Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20210D9951999-07-22022 July 1999 Safety Evaluation Supporting Amend 191 to License DPR-40 ML20216E6361999-07-21021 July 1999 Rev 18 to TDB-VI, COLR for FCS Unit 1 ML20209H8281999-07-15015 July 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Cooper Nuclear Station ML20211A9981999-07-12012 July 1999 Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF). ML20209E1061999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Cns.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20210C4731999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8901999-06-30030 June 1999 IPEEEs Technical Evaluation Rept High Winds,Floods & Other External Events ML18107A4351999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr LIC-99-0065, Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With ML20210R2081999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Fcs,Unit 1 1999-09-08 |
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CRAWFORD FITTING COMPANY SOLON, OHIO 44139 FRED A. LENNON PHONE (216) 248-4600 CHAIRMAN FAX (216) 349-5970 February 1, 1993 Document Control Desk Off ice of Nuclear Reactor Regulation Nuclear Regulatory Commission Washington, DC 20555
Subject:
Defects Potentially Reportable under 10CFR21
Dear Sir:
Pursuant to our letter of December 18, 1992 on a possible material defect in stainless steel Swagelok tube fittings, we are writing this follow-up to report some additional certifications of the parts to nuclear facilities.
A list of the part numbers, heat codes and the nuclear customers to which these additional fittings have been sold is enclosed. Please note~ this is not the reporting of any new heat codes with a possible defect. These are additional f acil'ities which our search has uncovered on the previously report:ed heats.
All these facilities have already been notified by us of this potential problem.
If you have any questions, please do not hesitate to contact us.
E. y 4- * ~ahuranec Vice "President and General Manager cc: SM
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- SS-400-3 (EON)
PG & E Company 90 Miles N.W. of Avila Beach Avila Beach, CA 93424 P.O. #057250 109 pcs.
SS-600-2-4 (EON)
Nebraska Public Power District Cooper Nuclear Station Brownville, NE 68321 P.O. 353610 10 pcs.
SS-600-2-4 (EON)
Omaha Public Power District
-Ft. Calhoun Station Ft. Calhoun N.E. 68023 P.O. S073817 100 pcs.
SS-600-2-4 (EDK)
PSE & G Co.
Nuclear Department Material Center Artificial Island End of Buttonwood Road Hancocks Bridge, NJ 08038 P.O. 404006 Rel. 039 20 pcs.
SS-600-2-6 (EPY)
Cooper Industries, Inc.
Energy Services Group 150 Lincoln Avenue Grove City, PA 16127 80 pcs.
P.O. #3621 N 1998 10 pcs.
SS-600-2-6 (EPY)
Nebraska Public Power Station Cooper Nuclear Station BroW'nvilJ.. e NE 68321 P.O.* 356167 6 pcs.
SS-600-2-6 (EPY)
PSE & G Nuclear Dept. Material Center Artificial Island End of Buttonwood Road Hancocks Bridge, NJ 08038 P.O. 404005 Rel 008 40 pcs.