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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARLD-99-039, Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified1999-06-30030 June 1999 Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified LD-99-035, Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed1999-06-25025 June 1999 Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed ML20153C1091998-09-18018 September 1998 Part 21 Rept Re Defective Capacity Control Valves.Trentec Personnel Have Been in Contact with Bg&E Personnel Re Condition & Have Requested Potentially Defective Valves 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 ML20217J9811998-04-28028 April 1998 Part 21 Rept Re Incorrect Description of Drift Specification for Model 1154,gauge Pressure Transmitters,Range Code 0 in Manual Man 4514,Dec 1992.Cause Indeterminate.Will Issue & Include Errata Sheets in All Future Shipments to Users ML20217K5191997-10-24024 October 1997 Part 21 Rept Re Five Valves That May Have Defect Related to Possible Crack within Forging Wall at Die Flash Line.Caused by Less than Optimal Forging Temperatures.Newer Temperature Monitoring Devices at Forging Area Heating Ovens Procured ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected ML17309A6211997-09-29029 September 1997 Part 21 Rept Re Final Disposition of Masterflow 713 & Embeco 636 Grout Nonconformance Reported by Master Builders,Inc. Licensee Continuing to Monitor shelf-life of Masterflow 713 & Embeco 636 Grouts Produced at Rancho Cucamonga LD-97-024, Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-0041997-08-14014 August 1997 Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-004 ML20149J8681997-07-22022 July 1997 Part 21 Rept Re Failure of Main Steam Header Radiation Monitors Supplied by Nuclear Research Corp.Caused by Defect in Installed Basic Component.Declared Monitors Inoperable & Implemented Alternate Preplanned Monitoring Method ML20149D3121997-07-14014 July 1997 Part 21 Draft Rept Re 970606 Failure of Main Steam Header Radiation Monitors Supplied by Nuclear Research Corp.Caused by Temperature Compensation.Detectors Declared Inoperable & Removed for Repair LD-97-002, Part 21 Rept Re Piping Line Loss Between SG & MSIV Inlet When MSSVs Area Activated.Recommends That Utils Confirm Proper Adjustment of MSSV Blowdown Settings So as to Preclude Valve Chatter & Related Structural Concerns1997-01-17017 January 1997 Part 21 Rept Re Piping Line Loss Between SG & MSIV Inlet When MSSVs Area Activated.Recommends That Utils Confirm Proper Adjustment of MSSV Blowdown Settings So as to Preclude Valve Chatter & Related Structural Concerns ML20133M2501997-01-15015 January 1997 Part 21 Rept Re Failures of GE Type AMH-4.76-250 Circuit Breakers.Caused by Bent Trip Lever.Replaced Trip Paddles, Support Bracket & Spring Discharge Link 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 ML20134E8171996-10-25025 October 1996 Part 21 Rept Re Bent Manual Trip Paddles in GE Magne Blast 4-kV Circuit Breakers.Investigation Revealed No Gap Between Manual Trip Rod & Manual Trip Lever.Definitive Explanation for Breaker Failures Not Been Confirmed ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl ML20112G9811996-05-29029 May 1996 Part 21 Rept Re Bechtel Job 21464 Calvert Cliffs Nuclear Power Plant DG Project.Plant Start Up Problem Rept 96-06M Addressed Oil Filter O-Rings,filter Element & Filter Holder ML20101L2051996-03-28028 March 1996 Followup to Part 21 Rept Re Failures of gould-shawmut Fuses. Initial Investigation Into Issue Revealed Certain Percentage of Fuses Developed Cracks in Fuse Elements ML20091P4271995-08-24024 August 1995 Final Part 21 Rept Re Regular Locknut Being Installed on Governor Where Thinner Locknut Required at Calvert Cliffs. Applications of Thick Nut P/N 75233A06 on Control Linkages Will Be Reviewed to Insure Applications Correct ML20083L0411995-05-0505 May 1995 Interim Part 21 Rept Re Failures of Gould-Shawmit A25X 10-15 Ampere Fuses Due to Cracking of Fuse Element.Util Not Yet Verified That Mfg Process Described Cause of Failures & Performing Own Metallurgical Analysis on Fuses ML20077M7581995-01-10010 January 1995 Part 21 Rept,Determined That Bechtel Power Corp Analysis of long-term Cooling Phase of LOCA Did Not Model Heat Transfer from RCS Metal Components to RCS Coolant.Util Asked C-E to Provide New Mass & Energy Transfer Data ML20078R2721994-12-14014 December 1994 Part 21 Rept Re Auxiliary Feedwater Pump Turbine Governor Valve Binding.Caused by Galvanic & Crevice Corrosion Between Stem & Stem Packing Components.Licensees Replaced Stem & Packing Gland Matls ML20078Q1641994-12-0909 December 1994 Part 21 Rept Re Result in Slight Increase in post-accident Containment Temp.Licensees Have No Current Operability Concerns Due to Low Ultimate Heat Sink Temps at Present Time ML20080A7681994-11-15015 November 1994 Part 21 Rept Re AFW Pump Turbine Governor Valve Binding Caused by Galvanic & Crevice Corrosion Between Stem & Stem Packaging Components.Turbine Mfg by Terry Steam Turbine Co. Licensee Plans to Periodically Exercise Valve Stems ML20070K8111994-07-20020 July 1994 Interim Part 21 Rept Re OP 38TD8-1/8 CS Injection Pump Erosion Sleeve Cavitation,Reported by Bg&E.Vendor Pursuing Evaluation to Determine Whether Situation Could Potentially Affect All Nuclear Utils Who Operate Subj Sleeve ML20070M6451994-04-26026 April 1994 Part 21 Rept Re anti-rotation Keys for 6-inch MOVs Mfg by Velan.New Keys Machined on-site to Dimensional Requirements of New Drawings Supplied by Vendor Installed & Performed Satisfactorily ML20059H7721994-01-17017 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 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20056E6771993-08-20020 August 1993 Initial Part 21 Rept Re GE AK-25 Circuit Breakers w/RMS-9 Overcurrent Trip Devices.On 930731,three Spurious Trips of Subj Breakers Experienced While in Refueling Shutdown.Addl Info Re Issue Will Be Provided within 30 Days LD-93-019, Part 21 Rept Re Defect in Input to Better Axial Shape Selection Sys (Basss) Computer Code.Caused by Inconsistency Between Basss User Documentation & Code.Initially Determined on 930205.Correct Input Provided1993-02-12012 February 1993 Part 21 Rept Re Defect in Input to Better Axial Shape Selection Sys (Basss) Computer Code.Caused by Inconsistency Between Basss User Documentation & Code.Initially Determined on 930205.Correct Input Provided 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 ML20077N5061991-08-0909 August 1991 Part 21 Rept Re Defective 3/8 inch,3-way Solenoid Valve Model Supplied by Automatic Switch Co.Cv Valves Will Be Specified on Future Purchase Order W/Actual Test Values Requested for Each Valve L-91-002, Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl1991-01-0404 January 1991 Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl ML20059M1751990-09-24024 September 1990 Supplemental Part 21 Rept 1 Re Defect in Coltec Industries, Inc Connecting Rod Assemblies Nuts/Bolts on Model 38TD8-1/8 Emergency Generators.Initially Reported on 851120.Nuts/bolts for Assemblies at Stated Plants Inspected & Replaced ML20056A4151990-08-0303 August 1990 Part 21 Rept Re Thomas & Betts Electrical Terminal Lug Cracking Around Barrel.Initially Reported on 900731.All Thomas & Betts Products Currently Stocked in Warehouses Isolated & Ordered Held in Warehouse ML20012C1051990-03-0707 March 1990 Part 21 Rept Re Several Failures of Fairbanks Morse Engine Div Piston Pins/Bushings on Upper Pistons.Caused by Incorrect Surface Pattern on Piston Pins.Piston Pins Under Listed Purchase Orders to Be Removed & Replaced 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 ML20246M7461989-07-13013 July 1989 Part 21 Rept Re Steam Generator Snubber Nuts Found Not to Meet Mfg Matl Composition Specs.Initially Reported on 890712.All 150 Nuts Will Be Replaced w/A194Gr2H Nuts 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 ML20244D4091989-06-0606 June 1989 Corrected Part 21 Rept Re Responsible Officers for Reporting of Defects & Noncompliance.One of Creel Alternates Listed in Error in .Alternate Should Read as Stated ML20236C2721989-03-15015 March 1989 Part 21 Rept Re Nuclear fuel-potential Loss of Shutdown margin.C-E Issuing Info Bulletin Re Shutdown Margin During Refueling ML20236A9391989-03-0707 March 1989 Part 21 Rept Re Emergency Diesel Generator Fuel Supply Crossover Line Mfg by Fairbanks Morse.Initially Reported on 890303.Fuel Leaking from Line Could Come in Contact W/Hot Engine Parts.Crossover Pipe Will Be Replaced 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 ML20207K7831988-09-29029 September 1988 Part 21 Rept Re Defect in Amphenol SAMS Model 205-0034 Electrical Penetration Assembly.Metallurgical Analysis Revealed That Studs Made of Copper Alloy & Alloy Has Degraded.Equipment Replaced on Unit 1 ML20155C3681988-09-20020 September 1988 Part 21 Rept Re Deviation in Westinghouse Type Ds 206 & 416 Circuit Breakers.Crimp Connections Repaired ML20215G2441987-06-16016 June 1987 Part 21 Rept Re Failure of Load Sequencing Equipment Supplied in Aug 1977 During Scheduled Testing.Caused by Open Electrical Connection on One Crimp Lug.Since 1978,insulated Lugs Used on All Equipment 1999-06-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G6971999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Calvert Cliffs Npp,Units 1 & 2.With ML20216J8731999-09-10010 September 1999 Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant ML20211M4841999-08-31031 August 1999 Replacement Pages 2-48,2-49 & 2-50 to Rev 14 of Defueled Sar ML20212A4441999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ccnpp,Units 1 & 2. with ML17326A2011999-08-23023 August 1999 LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr ML20211D7111999-08-0909 August 1999 Rev 17 to Maine Yankee Defueled Safety Analysis Rept (Dsar) ML20210S6091999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ccnpp,Units 1 & 2. with ML20210N6001999-07-27027 July 1999 ISI Summary Rept for Calvert Cliffs Unit 2. Page 2 of 3 in Encl 1 of Incoming Submittal Not Included ML20210B7941999-07-15015 July 1999 SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs ML20196K4821999-07-0606 July 1999 Safety Evaluation Concluding That Because of Permanently Shutdown & Defueled Status of Myaps Facility,Confirmatory Orders No Longer Necessary for Safe Operation or Maint of Plant LD-99-039, Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified1999-06-30030 June 1999 Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified ML20209F1721999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Calvert Cliffs Npp.With LD-99-035, Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed1999-06-25025 June 1999 Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed ML20196C6981999-06-21021 June 1999 Safety Evaluation Concluding That Use of ASME Section XI Code Including Summer 1983 Addenda as Interim Code for Third 10-year Insp Interval at Calvert Cliffs Units 1 & 2 Until Review of 1998 Code Completed,Would Be Acceptable ML20195K2811999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ccnpp,Units 1 & 2. with ML20206H1611999-05-0505 May 1999 Safety Evaluation Supporting Amend 164 to License DPR-36 ML20206G5731999-05-0303 May 1999 Safety Evaluation Supporting Amend 163 to License DPR-36 ML20206R5871999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ccnpp,Units 1 & 2. with ML20195B3891999-04-30030 April 1999 0 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models ML20205N2951999-04-13013 April 1999 Special Rept:On 990314,fire Detection Sys Was Removed from Svc to Support Mod to Replace SRW Heat Exchangers in Unit 2 SRW Room During Unit 2 Refueling Outage.Contingency Measure 15.3.5.A.1 Will Continue Until Fire Detection Sys Restored ML20210T5211999-04-0101 April 1999 Rev 0 to Ccnpp COLR for Unit 2,Cycle 13 ML20205P5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20205D5261999-03-26026 March 1999 SER Accepting Util Rev 1 to CFH Training & Retraining Program for Maine Yankee.Rev 1 to CFH Training & Retraining Program Consistent with Current Licensing Practice for Facilities Undergoing Decommissioning ML20204H6471999-03-21021 March 1999 SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20204C4631999-03-16016 March 1999 Safety Evaluation Supporting Amend 162 to License DPR-36 ML20207M8321999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Calvert Cliffs Nuclear Power Plant.With ML20203D4311999-02-0505 February 1999 Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons ML20199G4671999-01-20020 January 1999 SER Accepting USI A-46 Implementation for Plant ML20206Q3221999-01-11011 January 1999 Special Rept:On 981226,wide Range Noble Gas Effluent RM Was Removed from Operable Status.Caused by Failure of mid-range Checksource to Properly Reseat.Completed Maint & post-maint Testing & RM Was Returned to Operable Status on 990104 ML20199F4781999-01-0808 January 1999 Safety Evaluation Concluding That Bg&E Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking.Concludes GL 95-07 Actions Were Addressed ML20207L0451999-01-0808 January 1999 Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors ML20198S7591999-01-0707 January 1999 SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M2281998-12-31031 December 1998 1998 Annual Rept for Bg&E. with ML20199E2931998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Calvert Cliffs Npp. with ML20206D7491998-12-31031 December 1998 Co Annual Financial Rept for 1998. with ML20206R9911998-12-0808 December 1998 Rept of Changes,Tests & Experiments (10CFR50.59(b)(2)). with ML20198B2631998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20195H1001998-11-16016 November 1998 Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative ML20155G9591998-11-0303 November 1998 Rev 1 to Post-Shutdown Decommissioning Activities Rept ML20195E5281998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Calvert Cliffs Nuclear Power Station,Units 1 & 2.With ML20196E2211998-10-31031 October 1998 Non-proprietary Rev 03-NP to CEN-633-NP, SG Tube Repair for Combustion Engineering Designed Plant with 3/4 - .048 Wall Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves ML20155D8651998-10-28028 October 1998 Public Version of, Maine Yankee Emergency Preparedness Exercise ML20154Q7191998-10-21021 October 1998 Special Rept:On 980923,unit 1 Wrngm Was Removed from Operable Status.Caused by Failure of Process Flow Transducer.Completed Maint to Remove Process Flow Transducer Input to Wrngm Microprocessor & Completed Formal Evaluation ML20154G3931998-10-0505 October 1998 Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code ML20154M5841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Calvert Cliffs Nuclear Plant,Units 1 & 2.With ML20153C2571998-09-18018 September 1998 Special Rept:On 980830,wide Range Noble Gas Monitor (Wrngm) Channel Was Removed from Operable Status.Caused by Need to Support Performance of Required 18-month Channel Calibr.Will Return Wrngm to Operable Status by 980925 ML20153C1091998-09-18018 September 1998 Part 21 Rept Re Defective Capacity Control Valves.Trentec Personnel Have Been in Contact with Bg&E Personnel Re Condition & Have Requested Potentially Defective Valves ML20151U5441998-09-0404 September 1998 Bg&E ISI Summary Rept for Calvert Cliffs ML20197C8231998-09-0303 September 1998 Safety Evaluation Supporting Request for Exemption from Certain Requirements of 10CFR50.54(q),10CFR50.47(b) & (C) & App E to 10CFR50 Re Emergency Planning ML20151T5281998-09-0101 September 1998 Special Rept:On 980819,declared Rv Water Level Monitor Channel a Inoperable.Caused by Failure of Three Heated Junction Thermocouples (Sensors) in Lower Five Sensors. Channel a & B Rv Water Level Probes Will Be Replaced 1999-09-30
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" ' RosemountNuclearInstruments n-m=me.mn.w no 12001 TocMoogy orive Eden Prairie. MN s5344 Us A
- Tot 1(612)82e-82s2 28 April 1998 m i g,n eze ezoo Re: Notification under 10 CFR Part 21 for Rosemount Model 1154 Alphaline Nuclear Pressure Transmitter, Range Code 0, Drift Specification Pursuant to 10CFR Part 21 Paragraph 21.21(b), Rosemount Nuclear Instruments, Inc. (RNII) is writing to inform you that the drift specification for Model 1154, gage pressure transmitters, range code 0, is not correctly described in Manual MAN 4514, December 1992. Manual MAN 4514, December 1992, page 4-1, Drift is incorrectly stated as 0.2% ofupper range limitfor 30 months. The correct specification is 10.3% ofupper range limitfor 30 months.
The Product Data Sheet for Model 1154, #00813-0100-4514, November 1995, page 4, Drift, shows k0.2% ofupper range limitfor thirty months (*0.3% ofupper range limitfor range 0).
This is the correct drift specification for this model, since 0.2% of upper range limit applies to all range codes other than range code 0.
This notice does not apply to other Model 1154 gage pressure transmitters, nor to any Model 1154 differential or high line differential pressure transmitters. Moreover, it does not apply to any Model 1152,1153 Series B or D transmitters.
The design and qualification of Model 1154 Range Code 0 is based on design and qualification of Rosemount Model 1153 Series D Alphaline Nuclear Pressure Transmitter. In turn, Model 1153 Series D design and qualification references Model 1153GDO, whose qualification is documented in Rosemount Report 78215. The range code 0 sensor module is designed to operate between 0 and 6000 psi. However, the specified upper range limit on model 1154 range code O pressure transmitter is 4000 psig. This means the specified upper range limit on range code 0 is actually " ranged down" from its design limits. There are " range-down" effects associated with operating the transmitter at levels lower than the design limit. More specifically, the transmitter gain must be turned up in order to calibrate the transmitter from 0 to 4000 psig, which amplifies any zero errors. This means that some of the errors in performance, including drift, must be magnified by the " range-down multiplier" of 1.5. The correct drift specification for range code 0 is *0.3% ofupper range limit as properly indicated in Product Data Sheet for Model 1154, #00813-0100-4514, November 1995.
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.h 10CFR21 Notification 27 April 1998 Page 2 of 3 1.0 Name and address of the individual providing the information:
Mr. Jeffrey W. Schmitt Vice President & General Manager Rosemount Nuclear Instruments, Inc.
12001 Technology Drive Eden Prairie, MN 55344 2.0 Identification ofitems supplied:
Model 1154 Alphaline Pressure Transmitter Range Code 0 gage pressure 3.0 Identification of firm supplying the item:
Rosemount Nuclear Instruments, Inc. i 12001 Technology Drive l Eden Prairie, MN 55344 l i
4.0 Nature of the failure and potential safety hazard:
This notification relates to the incorrect statement of drift specification in Manual MAN 4514, December 1992, page 4-1 under Drift for Model 1154 Alphaline Pressure !
Transmitter for Nuclent Service.
RNII does not have sufficient information to determine the safety impact related to plant applications. Licensees must determine the impact on plant operations and plant safety and take action as deemed necessary.
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P 10CFR21 Notiflemtion 27 April 1998 Page 3 of 3 5.0 The corrective action which is taken, the name of the individual or organization responsible for that action and the length of time taken to complete that action:
Until such time as the manual containing the error is fully revised, errata sheets will be
. issued and included in all future shipments of cmrent revision (December 1992) 1154 Manuals, stating the correct drift specification to be *0.2% ofupper range limItfor thirty months (20.3% ofupper range limitfor range 0). Additional errata sheets will be made available for users requesting them to include in 1154 manuals already shipped from RNII.
The above actions will be completed within 6 months of this notification.
No further action related to this issue is expected. Mr. Schmitt is responsible should any further action related to this issue be necessary.
6.0 - Any advice related to the potential failure of the item:
The end user must determine the full scope of this nonconformance as it relates to plant operations and plant safety and take action as deemed necessary.
RosemountNuclear Instruments,Inc. has a strong commitment to the nuclear industry and assures you that we are dedicated to the supply of high quality products and services to our customers. We are sorry for any inconvenience. If there are any questions, or you require additional information related to this issue, please contact Jerry Edwards (612) 828-3951, Mike Dougherty at (612) 828-8250 or Gerard Hanson at (612) 828-3480.
Sincerely, I
ROSEMOUNT NUCLEAR INSTRUMENTS, INC.
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Je rey W. chmitt Vice President & General Manager l
HEIER RISEMINIT u
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Attachment 10CFR Part 21-Notification dated 29 April 1998 Baltimore Gas and Electric P.O. Number Model Number Serial Numher 97002GX 1154GPORC 0509259 97002GX 1154GPORC 0509260 97002GX 1154GPORC 0509266 97002GX 1154GPORC 0510022 14458GX 1154GPORC 0511121 15172 1154GPORC 0514216 l
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Attachment 10CFR Part 21-Notification dated 29 April 1998 Maine Yankee Atomic Power Co. l P.O. Number Model Number Serial Number 96-03801 1154GPORA 0512978 I 96-03801 1154GPORA 0512983 l
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GENERAL INFORMATION or OTHER EVENT NUMBER: 34142 i
LICENSEE: ROSEMOUNT' NUCLEAR INSTRUMENTS NOTIFICATION DATE: 04/28/98 l CITY: EDEN PRAIRIE REGION: 3 NOTIFICATION TIME: 14:15 [ET]
COUNTY: STATE: MN EVENT DATE: 04/28/98 i
LICENSE #: AGREEMENT: N EVENT TIME: 14 :15 [CDT]
l DOCKET: LAST UPDATE DATE: 04/28/98 NOTIFICATIONS HAROLD GRAY RDO l NRC NOTIFIED BY: JEFF SCHMITT VERN HODGE, NRR FAX l HQ OPS OFFICER: JOHN MacKINNON EMERGENCY CLASS: NOT APPLICABLE l 10 CFR SECTION:
CCCC 21.21 UNSPECIFIED PARAGRAPH I
l EVENT TEXT 10CFR PART 21 REPORT - ROSEMOUNT MODEL 1154 ALPHALINE NUCLEAR GAGE PRESSURE TRANSMITTERS, RANGE CODE 0, DRIFT SPECIFICATION VALUE IS SUPPOSED TO BE l 10.03% INSTEAD OF 10.02%.
ROSEMOUNT NUCLEAR INSTRUMENTS, INC (RNII) REPORTED THAT THE DRIFT l SPECIFICATION FOR ROSEMOUNT MODEL 1154, ALPHALINE NUCLEAR GAGE PRESSURE TRANSMITTERS, RANGE CODE 0, IS NOT CORRECTLY DESCRIBED IN MANUAL MAN 4514, l DECEMBER 1992. MANUAL MAN 451,4, DECEMBER 1992, PAGE 4-1, " DRIFT" IS ,
l INCORRECTLY STATED AS iO.2% OF UPPER RANGE LIMIT FOR 30 MONTHS. THE i CORRECT SPECIFICATION IS iO.3% OF UPPER RANGE LIMIT FOR 30 MONTHS.
i THZS 10CFR PART 21 REPORT DOES NOT APPLY TO OTHER MODEL 1154 GAGE PRESSURE TRANSMITTERS, NOR TO ANY MODEL 1154 DIFFERENTIAL OR HIGH LINE DIFFERENTIAL l TRANSMITTERS. MOREOVER, IT DOES NOT APPLY TO ANY MODEL 1152, OR MODEL 1153 l
SERIES B OR D TRANSMITTERS.
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TIOnEn-HUGE UU I ,2003 Tcennoiosy orive Edsn Prairia, MN 55344-3695 USA DATE: April 28,1998 PAGE(S) INCLUDING LEAD SHEET: 6 II6.INIf,3~}hi LT;O3_:,1 - ,, i'32 !~.7.CiTQ[~FNOM_M'.
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1 COMPANY: NRC FAX NUMBER: (612) 828-8280 ATTENTION: Document Control Desk SENDER: Jeff Schmitt l
FAX NUMBER: (301) 816-5151 PHONE NUMBER: (612) 828-3432 l
SUBJECT:
Part 21 Notice I CC: I i
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