Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based CalibrationsML12094A371 |
Person / Time |
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Site: |
Millstone, Hatch, Calvert Cliffs, Dresden, Peach Bottom, Browns Ferry, Salem, Palo Verde, Indian Point, Catawba, Harris, Saint Lucie, Point Beach, Watts Bar, Hope Creek, Grand Gulf, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Summer, Seabrook, Brunswick, Limerick, Turkey Point, Vermont Yankee, Crystal River, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, South Texas, San Onofre, Comanche Peak, Quad Cities, Humboldt Bay, Zion, Bellefonte, FitzPatrick, LaSalle ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
04/02/2012 |
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From: |
Pham D Rosemount Nuclear Instruments |
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To: |
Document Control Desk, Office of Nuclear Reactor Regulation |
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References |
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Download: ML12094A371 (10) |
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Similar Documents at Millstone, Hatch, Calvert Cliffs, Dresden, Peach Bottom, Browns Ferry, Salem, Palo Verde, Indian Point, Catawba, Harris, Saint Lucie, Point Beach, Watts Bar, Hope Creek, Grand Gulf, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Summer, Seabrook, Brunswick, Limerick, Turkey Point, Vermont Yankee, Crystal River, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, South Texas, San Onofre, Comanche Peak, Quad Cities, Humboldt Bay, Zion, Bellefonte, FitzPatrick, LaSalle |
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Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l ML22098A1172022-03-29029 March 2022 Engine Systems, Inc. Report No. 10CFR21-0134, Rev. 0 - 10CFR21 Reporting of Defects and Non-Compliance - (Emo Cylinder Head with Fireface Thickness Below Specification Cylinder Head P/N 40121485) ML22075A2192021-11-29029 November 2021 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0133, Rev. 0 - Swing Check Valve, P/N ESl50359 JAFP-21-0029, Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2021-04-29029 April 2021 Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues ML21096A1142021-04-0606 April 2021 Ametek Solidstate Controls - Updated Interim Notifcation 1CAN012101, Interim Report Concerning an Evaluation of Deviation2021-01-18018 January 2021 Interim Report Concerning an Evaluation of Deviation ML20279A5772020-11-23023 November 2020 U.S. Nuclear Regulatory Commission'S Analysis of Public Service Enterprise Group Nuclear, LLC Decommissioning Plans Update for Salem Generating Station, Hope Creek Generating Station and Peach Bottom Independent Sfsis ML20296A2762020-10-0606 October 2020 Lake Engineering Co. - Third Interim Notification Per 10 CFR Part 21 - Degraded Snubber SF1154 Hydraulic Fluid Batch No. 17BLVS293 DCL-20-047, 10 CFR Part 21 Notification: Inadequate Dedication of Replacement Thermocouples2020-06-16016 June 2020 10 CFR Part 21 Notification: Inadequate Dedication of Replacement Thermocouples ML20049A0752020-02-11011 February 2020 C&D Technologies, Inc. -10 CFR Part 21 Evaluation Regarding Container Failure in KCR-07 Batteries ML20021A0452020-01-0303 January 2020 Lake Engineering Co. - Interim Notification Per 10 CFR Part 21, Degraded Snubber SF1154 Hydraulic Fluid Batch No. 16DLVS852 ML19346H8732019-12-12012 December 2019 Westinghouse Electric Company - Notification of the Potential Existence of Defect Pursuant to 10 CFR Part 21 ML19323C9712019-11-15015 November 2019 Interim 10 CFR 21 Report for Masoneilan Model 8005N Transducer ML19325C0942019-11-0707 November 2019 Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch ZJS1518 Final Report Per 10 CFR Part 21 ML19304B6072019-10-31031 October 2019 Written Defect Notification for GE-Hitachi Stationary Primary Contact Finger Q0114C5382P002 ML19317D0932019-10-25025 October 2019 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10 CFR21-0127, Rev. 0, Emd Fuel Injectors - Seized Plunger and Bushing ML19295D7322019-10-11011 October 2019 Engine Systems, Inc. Report No. 10CFR21-0125, Rev. 1 - Signal Converter Transmitter ML19263A6662019-09-0909 September 2019 Lake Engineering Co. - Third Interim Notification Per 10 CFR Part 21: Degraded Snubber SF1154 Hydraulic Fluid Batch No. ZJS1518 ML19261A1942019-09-0606 September 2019 Final Report (Log # 2019-22-00) (Event# EN 54215) - Non-Destructive Examination (Liquid Penetrant) Performance of Components by an Un-Qualified Employee ML19246A1022019-08-22022 August 2019 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No 10CFR21-0126, Rev 0 - Emd Fuel Injector - Cracked Spray Tip, Pin 5229250 ML19213A0252019-07-26026 July 2019 Ultra Electronics - Update to ML19155A084 10CFR21 Interim Report ML19207A0562019-07-19019 July 2019 Engine Systems, Inc. - Part 21 Report 10CFR21-0125, Rev. 0, for a 10CFR21 Reportable Notification on a Signal Converter Transmitter ML19210D4342019-07-11011 July 2019 Curtiss-Wright SAS - 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 ML19190A0432019-06-28028 June 2019 Discusses Proprietary Information for Curtiss-Wright SAS - 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 - Cw SAS Initial Report No. 10CFR21-48 ML19158A1302019-05-31031 May 2019 Curtiss-Wright Nuclear Division - Notification Report for Potential Part 21 Update ML19155A0842019-05-31031 May 2019 Ultra Electronics - Interim Notification Per 10CFR21 ML19158A1312019-05-31031 May 2019 Paragon Energy Systems LLC -10 CFR Part 21 Report of Defect GS2 Terry Turbine Introl Positioners ML19106A1062019-04-12012 April 2019 Ametek Solidstate Controls - Notification of Potential Defect - 10 CFR Part 21 ML19087A2522019-03-21021 March 2019 Engine Systems, Inc. - 10 CFR 21 Reportable Notification on Excitation Transformers for Vickers Voltage Regulator System ML19080A0592019-03-0808 March 2019 Interim Report of Potential 10CFR Part 21, Eaton A200 Series Starters/Contactors ML19078A0872019-03-0808 March 2019 Curtiss-Wright - Interim Notification Report for Potential Part 21 Update ML19008A0432019-01-0404 January 2019 Third Interim Notification Per 10 CFR Part 21 Degraded Snubber SF1154 Hydraulic Fluid Batch No. 11KLVS146 ML19029A1552018-12-27027 December 2018 10 CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0123, Rev. 1 ML18353A4282018-11-30030 November 2018 Engine Systems, Inc., 10CFR21-0123, Rev. 0, for a 10CFR21 Reportable Condition on Emd Fuel and Soakback Pumps ML18332A1222018-11-15015 November 2018 Curtiss-Wright - Interim Notification Report for Potential Part 21 Update ML18302A2282018-10-19019 October 2018 Itt Enidine - USNRC 10CFR Part 21 Notification ML18270A3352018-09-26026 September 2018 Interim 10 CFR 21 Report for General Electric Hitachi (GEH) Relay Contact Cartridge DJ148C6159P001 ML18263A2812018-09-20020 September 2018 (Waterford 3) - Part 21 Report of Westinghouse 7300 Circuit Card Increased Failure Rate ML18243A5112018-08-28028 August 2018 Curtiss-Wright Nuclear Division - Senasys Selector Switch P/N 910CMC-5240X, Part 21 Notification ML18211A3022018-07-25025 July 2018 Interim Notification Per 10 CFR Part 21, Degraded Snubber SF1154 Hydraulic Fluid Batch No. 11 KLVS146 ML18159A0392018-06-0606 June 2018 National Technical Systems (Nts) - Potential Part 21 on Dedicated Items Not Available for Pmi Testing (NUPIC) ML18150A6892018-05-30030 May 2018 Interim Report of a Deviation or Failure to Comply ML18102A5292018-04-0303 April 2018 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0121, Rev. 0, Refurbished Pressure Regulator Assembly, P/N 1776 506. ML18075A3552018-03-0606 March 2018 10 CFR Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl 10x8x10 and 6x4x6 Bolted Bonnet Gate Valve ML17355A1392017-12-0505 December 2017 Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch 14ELVS145 Final Report Per 10 CFR Part 21 ML17340A3922017-11-28028 November 2017 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0119, Rev. 0 ML17325B0222017-11-17017 November 2017 Fisher Controls International LLC Information Notice (FIN) 2017-05 ULNRC-06393, 10 CFR Part 21 Written Notification Regarding Cameron Barton Model 752B Differential Pressure Transmitters2017-10-31031 October 2017 10 CFR Part 21 Written Notification Regarding Cameron Barton Model 752B Differential Pressure Transmitters ML17286A0242017-10-11011 October 2017 Part 21 on Siemens 5-3AF-GER-350-1200-78 & 5-3AF-GEU-350-1200-78 Circuit Breakers 2024-01-23 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Millstone]] OR [[:Hatch]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Palo Verde]] OR [[:Indian Point]] OR [[:Catawba]] OR [[:Harris]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Summer]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Limerick]] OR [[:Turkey Point]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Comanche Peak]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:Zion]] OR [[:Bellefonte]] OR [[:FitzPatrick]] OR [[:LaSalle]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Millstone]] OR [[:Hatch]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Palo Verde]] OR [[:Indian Point]] OR [[:Catawba]] OR [[:Harris]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Summer]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Limerick]] OR [[:Turkey Point]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Comanche Peak]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:Zion]] OR [[:Bellefonte]] OR [[:FitzPatrick]] OR [[:LaSalle]] </code>. Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML24018A0112024-01-18018 January 2024 CFR 21 Report Emergency Diesel Generator Fuel Oil Piping ML24018A0142024-01-17017 January 2024 Engine Systems, Inc., Report No. 10CFR21-0137, Rev. 1, 56913-EN 56913 ML24010A2132024-01-10010 January 2024 CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers ML24018A0952024-01-0404 January 2024 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0137, Rev. 0 ML24008A0692024-01-0404 January 2024 Part 21 Report No. 10CFR21-0137, Rev. 0 for Reportable Notification for an Emo Cylinder Liner with Bore Deficiency, P/N 9318833 (Component of Power Assembly P/N 40124897), S/N 20M0938 ML24002A7112023-12-28028 December 2023 Interim Part 21 Report of a Deviation or Failure to Comply - Lube Oil Scavenging and Fuel Oil Engine Driven Pump NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24004A2092023-12-12012 December 2023 Flowline, Inc. - Interim Part 21 Report Notification Regarding Supply of 1 Sch. 80 (0.179 Wall) SB466 Uns C71500 Buttweld Long Radius 90 Degree Elbow; Manufacturer: Flowline; Heat No: 27668; 27 Pieces - Heat Code ML23352A2382023-12-0808 December 2023 56882-EN 56882 - Tioga Pipe, Inc Interim Part 21 Report Re Supply of 1 Inch Sch. 80 SB466 Uns C71500 Buttweld Long Radius 90 Degree Elbow ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) NLS2023049, 10 CFR Part 21 Report Regarding HGA Relays2023-09-0606 September 2023 10 CFR Part 21 Report Regarding HGA Relays ML23241A0022023-08-25025 August 2023 Paragon Final Part 21 Report on Defect with Eaton/Cutler Hammer Size 4 and 5 Freedom Series Contactors Modified by Paragon with Special Coils And/Or with RTV to Improve the Securing of Shading Coils RBG-48245, Part 21 Notification of a Failure to Comply Identified During Preinstallation Testing on a Motor Driven Relay2023-08-24024 August 2023 Part 21 Notification of a Failure to Comply Identified During Preinstallation Testing on a Motor Driven Relay ML23221A3702023-08-0303 August 2023 Paragon Energy Solutions, 10CFR Part 21 Initial Notification: P21-08032023-IN, Rev. 0 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23187A4722023-06-30030 June 2023 56603-EN 56603 - Engine Systems, Inc., Report No. 10CFR21-0136, Rev. 0 Re Voltage Regulator Chassis ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 ML23212A9502023-05-24024 May 2023 Engine Systems, Inc., Part 21 Report Re Woodward EGB-35P Governor/Actuator with Foreign Material ML23117A0432023-04-20020 April 2023 Framatome, Inc., Part 21 Notification of Existence of a Defect ML23100A1072023-04-10010 April 2023 Framatome Part 21 Report Re Erroneous Change of State for Circuit Breaker ML23094A1252023-03-31031 March 2023 Talen Part 21 Final Notification P21-03032023-FN R0 Re Defect Identified in Automatic Transfer Switch ML23094A1242023-03-31031 March 2023 EN 56387 Update - Paragon Energy Solutions Final Notification of Defect of Automatic Transfer Switch ML23087A1292023-03-23023 March 2023 Trillium Valves USA - Part 21 Written Notification - Event Number: 56420 ML23082A1122023-03-17017 March 2023 10 CFR Part 21 Report Inconsistent Crimping of Motor Leads to Ring Terminal Connectors and Failure to Comply. Trillium Valves USA Part 21 Evaluation I211003 ML23066A2212023-03-0707 March 2023 Velan, Inc. - Revised Part 21 Notification Re Butterfly Valves Found to Have a Number of Fasteners Loose ML23065A2002023-03-0303 March 2023 EN 56252 Update - Flow Serve - Final Notification of Potential Part 21 on Peerless 56 Frame DC Motors ML23065A1962023-03-0202 March 2023 EN 56387 Paragon - Part 21 Report Re Defect Identified in Automatic Transfer Switch Pn: NLI-ATS480A400X1 ML23060A0412023-03-0101 March 2023 Part 21 Interim Report of a Deviation or Failure to Comply Associated with a Limitorque Actuator ML23038A0192023-02-0606 February 2023 Curtiss-Wright Part 21 Notification for Qualtech Np Supplied Eaton TMR5 Timing Relays ML23030A6642023-01-27027 January 2023 Flowserve, Part 21 Second Interim Notification Report Re Peerless 56 Frame DC Motors ML23025A2532023-01-25025 January 2023 Part 21 Final Report Regarding Siemens Medium Voltage Circuit Breakers ML23024A0292023-01-24024 January 2023 Part 21 Interim Report of a Deviation or Failure to Comply Associated with a Limitorque Actuator ML23011A0622023-01-11011 January 2023 Written Part 21 Notification of a Defect Associated with Imi CCI Supplied Main Steam and Main Feedwater Isolation Valves ML22342B1402022-12-0202 December 2022 56252-EN 56252 - Flowserve - Limitorque - Interim Report Potential Part 21 on Peerless 56 Frame DC Motors ML22341A0322022-11-30030 November 2022 10 CFR Part 21 Notification from Curtiss-Wright Nuclear Division for Qualtech Np Supplied Eaton TRM5 Timing Relays ML22314A0132022-11-0404 November 2022 EN 56209 - Part 21 Report Re Schneider Electric P/N ASP840-000 Modicon Primary/Secondary Power Supply Failures ML22307A0602022-11-0303 November 2022 EN 56200 - Fairbanks Morse Re Basic Component Which Fails to Comply or Contains a Defect ML22307A0192022-11-0101 November 2022 EN 56196 - NRC 10 CFR Part 21 Notification, Nutherm, Written Notification of Potential Defect Found in Nutherm/Sola Hevi-Duty Uninterruptible Power Supply (Ups), S4K2U1000-NM 191 ML22301A1742022-10-28028 October 2022 Global Nuclear Fuel Americas, LLC (GNF) - Part 21 60-Day Interim Report Notification: GNF3 Raised Water Rod (SC-22-04 Rt) ML22303A0042022-08-31031 August 2022 Final Report Notification Pursuant to 10 CFR Part 21.21, Regarding Supply of 6 NPS Sch. 40 Seamless Stainless-Steel Pipe; Manufacturer: Maxim Tubes Company Pvt. Ltd.; Heat No: N200309AW01, SR No: 7; 9 Pcs; 180 Feet Total Procured as Unquali ML22259A1732022-08-26026 August 2022 EN 55960 - Curtiss Wright Part 21 Report Re Potential Defect in Configuration of the Quick Disconnect Connector Cable Assemblies Supplied to McGuire and Catawba Nuclear Power Stations ML22220A2362022-08-0202 August 2022 Leonardo DRS, 16-AAT907B Power Supply 10 CFR Part 21 Notification ML22201A1012022-07-18018 July 2022 Framatome, Inc. - 10 CFR Part 21 Notification of Existence of a Defect and Failure to Comply ML22222A0092022-07-0101 July 2022 EN 55974 - Flowserve, Part 21 Report Re Solenoid Coil Failure of Model 38878-8 Solenoid Valve at Catawba Nuclear Station for Use on FWIV Actuator 2024-01-04 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Millstone]] OR [[:Hatch]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Palo Verde]] OR [[:Indian Point]] OR [[:Catawba]] OR [[:Harris]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Summer]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Limerick]] OR [[:Turkey Point]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Comanche Peak]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:Zion]] OR [[:Bellefonte]] OR [[:FitzPatrick]] OR [[:LaSalle]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Millstone]] OR [[:Hatch]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Palo Verde]] OR [[:Indian Point]] OR [[:Catawba]] OR [[:Harris]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Summer]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Limerick]] OR [[:Turkey Point]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Comanche Peak]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:Zion]] OR [[:Bellefonte]] OR [[:FitzPatrick]] OR [[:LaSalle]] </code>. |
Text
0410212012 U.S. NuclearRegulator), Commission OperationsCenter EventReport Page I Part 21 (PAR) Event# 47693 Rep Org: ROSEMOUNT NUCLEAR Notification Date i Time: 02/23/2012 11:08 (EDT)
Supplier: ROSEMOUNT NUCLEAR Event Date / Time: 02/16/2012 .(CST)
Last Modification: 04/02/2012 Region: 3 Docket #:
City: CHANHASSEN Agreement State: Yes County: License #:
State: MN NRC Notified by: DUYEN PHAM Notifications: MEL GRAY R1DO HQ Ops Officer: VINCE KLCO MIKE ERNSTES R2DO Emergency Class: NON EMERGENCY PATTY PELKE R3DO 10 CFR Section: RICK DEESE R4DO 21.21 UNSPECIFIED PARAGRAPH PART 21 GRP - EMAIL PART 21 REPORT - ROSEMOUNT PRESSURE TRANSMITTERS WITH NONZERO BASED CALIBRATIONS The following information was received by facsimile:
"During the course of qualification testing to replace certain diodes identified for obsolescence, RNII [Rosemount Nuclear Instruments, Inc.] has determined that Model 1154 Series H range code 4-8 pressure transmitters with a significantly elevated or suppressed 4 mA point may not meet the published steam pressure/temperature accuracy specification.
"The out of tolerance condition observed during steam pressure/temperature qualification testing is not related to the replacement diode changes. It is an inherent performance characteristic related to large zero elevation or suppression. The steam pressure/temperature accuracy specification will be revised to account for nonzero based calibrations with a significantly elevated or suppressed 4 mA point.
"This revised specification supersedes the published steam pressure/temperature accuracy specification for all Model 1154 Series H pressure transmitters affected by this notification.
"RNII recommends that users review the application where 1154 Series H range code 4-8 pressure transmitters are used to determine if there are safety considerations related to the revised steam pressure/temperature specification."
Rosemount Nuclear has provided instruments to the following list of domestic U.S. customers: Alabama Power; American Electric Power; Arizona Public Service/Pinnacle West; Bechtel Power; Constellation Energy; Dominion Nuclear Connecticut/Dominion Generation; Duke Energy; ECFS MCS; Edison Material Supply; Electro Mechanics; Entergy; Exelon Generation; Florida Power and Light; FPL Energy; Georgia Power; Northern States Power-
04/02/2012 U.S. Nuclear Regulatory Commission OperationsCenter Event Report e9 Part 21 (PAR) Event# 47693 Minnesota DBA XCEL Energy; Pacific Gas and Electric; Progress Energy Florida; Progress Energy Carolinas; PSEG Nuclear; South Carolina Electric and Gas; Southern California Edison; Southern Nuclear Operating Company; STP Nuclear Operating; Tennessee Valley Authority; TXU/Luminant; Westinghouse Electric.
- UPDATE FROM DUYEN PHAM TO PETE SNYDER ON 4/2/12 AT 1224 EDT ***
"This revision only affects Section 4.0 of the 23 February 2012 notification letter. The pressure values listed in Section 4.0 at 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> have been corrected. No other changes have been made."
Notified R1 DO(Caruso), R2DO(Lesser), R3DO(Dickson), R4DO(Haire) and Part 21 Group via email.
Received at: 04/02/2012 12:24 2012 Apr 02 11,03 AM EPM OUT ROSEMOUNT NUCLEAR 952-949- 1/8 EMERSON.
Process Management ROSEMOUNT" Nuclear 8200 Market Boulevard Chanhassen, MN 55317 USA Facsimile Tel 1 (952) 949-5210 Fax 1 (952) 949-5201 No. of Pages:
Including cover page 8 To: NRC Operations Center Fax Number: (301) 816-5151 Date: Monday, April 2, 2012 From: Duyen Pham, Quality Manager Phone: (952) 949-5363 E-Mail: Duven.PhamfEmerson.com
Subject:
Revision to 23 FEBRUARY 2012 Notification under 10 CFR Part 21 on certain Rosemount Model 1154 Series H Pressure Transmitters with nonzero based calibrations Rosemount Nuclear Instruments, Inc. is submitting the attached revised notification. Please contact me ifyou have any questions.
This revision only affects Section 4.0 of the 23 February 2012 notification letter.
Sincerely, Duyen Pham Quality Manager Rosemount Nuclear Instruments, Inc.
www. RosemountNuciearcm RNII.lnfo(OEmersonProcess.com
2012 Apr 02 11,03 AM EPM OUT ROSEMOUNT NUCLEAR 952-949- 2/8 Rosamount Nuclear Instruments, Inc.
8200 Market Boulevard EW Ol NI IChanhassen, MN 55317 USA Nuclear Tel Fax (962) 1 (952) 949-5201 www.RosemountNuclear.com 2 April 2012 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attn: Document Control Desk Re: Revision to 23 FEBRUARY 2012 Notification under 10 CFR Part 21 on certain Rosemount Model 1164 Series H Pressure Transmitters with nonzero based calibrations Note: This revision only affects Section 4.0 of the 23 February 2012 notification letter.
The, pressure values listed in Section 4.0 at 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> have been corrected.
No other changes have been made.
Following Is the 23 FEBRUARY 2012 notification letter In Its enttrety with the above specific updates incorporated:
Pursuant to 10 CFR Part 21, section 21,21(b), Rosemount Nuclear Instruments, Inc. (RNII) is writing to inform you that certain Model 1154 Series H pressure transmitters may not perform within the published steam pressure/temperature accuracy specification.
Rosemount Nuclear Instruments, Inc. does not have complete information relating to specific plant applications and therefore cannot determine the potential effects of the condition on plant operation.
The potentially affected Model 1154 Series H pressure transmitters were shipped from RNII beginning In 1988. Model 1154 pressure transmitters (versus Model 1154 Series H) are not affected by this notification.
1.0 Name and address of the individual providing the information:
Mr. Marc D. Bumgarner Vice President & General Manager Rosemount Nuclear Instruments, Inc.
8200 Market Boulevard Chanhassen, MN 55317 2.0 Identification of Items supplied:
All Model 1154 Series H range code 4-8 pressure transmitters shipped since the initial release in 1988 are potentially affected. Model 1154 Series H range code 9 pressure transmitters are not affected, nor are Model 1154 (versus Model 1154 Series H) transmitters.
Page I of 7
2012 Apr 02 11,03 AM EPM OUT ROSEMOUNT NUCLEAR 952-949- 3/8 More detailed information can be found In the enclosed appendices.
- Appendix A lists 1154 model code combinations
- Appendix B lists N-options Specials with Specific Steam Pressure/Temperature Accuracy Specifications
- Appendix C lists U.S. domestic customers to which Rosemount Nuclear Instruments, Inc. has shipped one or more 1154 Series H range code 4-8 pressure transmitters 3.0 Identification of Items supplied:
Rosemount Nuclear Instruments, Inc.
8200 Market Boulevard Chanhassen, MN 55317 4.0 Nature of the failure and potential safety hazard:
During the course of qualification testing to replace certain diodes identified for obsolescence, RNII has determined that Model 1154 Series H range code 4-8 pressure transmitters with a significantly elevated or suppressed 4 mA point may not meet the published steam pressure/temperature accuracy specification.
The out of tolerance condition observed during steam pressure/temperature qualification testing is not related to the replacement diode changes. It is an inherent performance characteristic related to large zero elevation or suppression.
The steam pressure/temperature accuracy specification will be revised to account for nonzero based calibrations with a significantly elevated or suppressed 4 mA point.
Currently, the Model 1154 Series H steam pressure/temperature specification establishes an expected accuracy as follows:
Accuracy within +/- (1.0% of upper range limit + 1.0% of span) for range codes 4-8; +/- (2.0% of upper range limit + 0.5% of span) for range code 9 during and after sequential exposure to steam at the following temperatures and pressures, concurrent with chemical spray for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
420°F (215.6CC), 85 psig for 3 minutes 350¶F (176.6' C), 85 psig for 7 minutes 3200 F (160-C), 86 75 psig for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 265'F (129.4-C), 85 24 psig for 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> The Model 1154 Series H steam pressure/temperature accuracy specification will be revised to envelop the observed steam pressure/temperature qualification test data as follows:
Accuracy within +/- (1.0% of upper range limit + 1.0% of span)* for range codes 4-8; +/- (2.0% of upper range limit + 0.5% of span) for range code 9 during and after sequential exposure to steam at the following temperatures and pressures, concurrent with chemical spray for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ROSEMOuNT Nuclear Page 2of 7
2012 Apr 02 11,03 AM EPM OUT ROSEMOUNT NUCLEAR 952-949- 4/8 420°F (215.6-C), 85 psig for 3 minutes 350°F (176.6-C), 85 psig for 7 minutes 320°F (160-C), 8" 75 psig for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2657 (129.4-C), 86 24 psig for 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br />
- For range codes 4-8. if oreisure at the 4mA point (appolied to either the hibh or low side of the transmitter) Is greater than 50% -of the upper range limit, the accuracy sieclficatLon is +/- 2% of upper range limit This revised specification supersedes the published steam pressure/temperature accuracy specification for all Model 1154 Series H pressure transmitters affected by this notification.
The 1154 Series H range code 9 pressure transmitters have a steam pressure/temperature accuracy specification that already envelopes the observed steam pressure/temperature qualification test data and are not affected by this notification.
Model 1154 Series H pressure transmitters ordered with N-option specials which include specific steam pressure/temperature accuracy specifications may also be affected. See Appendix B for details.
On February 16, 2012, it was concluded that a substantial safety hazard may exist.
Rosemount Nuclear Instruments, Inc. does not have sufficient information to determine the potential safety impact in plant applications. As a result, a notification about the potential substantial safety hazard is being made in accordance with 10 CFR Part 21 to customers who purchased affected 1154 Series H pressure transmitters.
6.0 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; (a) Update Model 1154 Series H Qualification Report D8700096 to include the revised steam pressure/temperature specification for pressure transmitters impacted by this notification as noted in Section 4.0.
(b) Update the Model 1154 Series H Product Data Sheet 00813-0100-4631 and Product Manual 00809-0100-4631 to Include the revised steam pressure/temperature specification for pressure transmitters impacted by this notification as noted in Section 4.0.
(a) Update the N0059 Specification Drawing 01154-2704 to include the revised steam pressure/temperature specification for pressure transmitters impacted by this notification as noted in Appendix B.
Completion: March 2012 Mr. Marc Bumgarner, VP&GM of Rosemount Nuclear Instruments, Inc. is responsible for any further action related to this issue.
6.0 Any advice related to the potential failure of the item:
ROSEMOUNT" Nuclear Page 3 of 7
2012 Apr 02 11,03 AM EPM OUT ROSEMOUNT NUCLEAR 952-949- 5/8 RNII recommends that users review the application where 1154 Series H range code 4-8 pressure transmitters are used to determine ifthere are safety considerations related to the revised steam pressure/temperature specification.
Rosemount Nuclear Instruments, Inc. is committed to the nuclear industry and remains dedicated to the supply of high quality products to our customers. If you have any questions, or require additional Information related to this Issue, please contact: Mike Dougherty (208) 865-1112 or Tracy Kaluzniak (952) 949-7159.
Sincerely, Marc D, Bumgarner Vice President & General Manager Rosemount Nuclear Instruments, Inc.
Enc.: Appendix A: Model Code Combinations Appendix B: N-option Specials with Specific Steam Pressure/Temperature Accuracy Specifications Appendix C; List of Customers Nuclear Page 4 of 7
2012 Apr 02 11'03 AM EPM OUT ROSEMOUNT NUCLEAR 952-949- 6/8 Appendix A: Model Code Combinations Potentially affected model codes begin with the following:
Base Model Description 1154DH4... 1154 Series H Differential Pressure 2000 psig Static Pressure Rating 1154DHIS... 1154 Series H Differential Pressure 2000 psig Static Pressure Rating 1154DH6... 1154 Series H Differential Pressure 2000 pslg Static Pressure Rating 1154DH7... 1154 Series H Differential Pressure 2000 psig Static Pressure Rating 1154DH7 ... 1154 Series H Differential Pressure 2000 psig Static Pressure Rating 1154DN8... 1154 Series H Differential Pressure 2000 si Static Pressure Ratin 1154HH4... 1154 Series H Differential Pressure 3000 psig Static Pressure Rating 1154HH6... 1154 Series H Differential Pressure 3000 pslg Static Pressure Rating 1154HH6... 1154 Series H Differential Pressure 3000 psig Static Pressure Rating 1154HH7... 1154 Series H Differential Pressure 3000 psig Static Pressure Rating 1154HH7... 1154 Series H Differential Pressure 3000 psig Static Pressure Rating 1154HH8,.. 1154 Series H Differential Pressure 3000 psig Static Pressure Rating Unaffected model codes begin with the following:
Base Model Notes 1154SH9... 1154 Series H Sealed Reference Pressure 1154DP,.. 1154 Differential Pressure 2000 psig Static Pressure Rating 1154HP... 1154 Differential Pressure 3000 psig Static Pressure Rating 1154GP... 1 1154 Gage Pressure ROSEMOUNT"Nuclear Page 5 of 7
2012 Apr 02 11,03 AM EPM OUT ROSEMOUNT NUCLEAR 952-949- 7/8 Appendix B: N-option Specials with Specific Steam Pressure/Temperature Accuracy Specifications N-option (RNII Description Steam Notes drawing reference) Pressure/Temperature Accuracy Specification N0059 (01154-2704) Defines the use of a Model Is affected by this 11 54DH8RB with a sealed notification.
reference on the low side. The revised steam a(1.5%URL+1 %span) pressure/temperature accuracy specification is
+/-(2% URL + 1% span) when the 4 mA point is greater than 50% of URL.
N0026 (01153-2725) Defines the use of an 1154 Series H range code 4 pressure transmitter calibrated to a maximum working pressure of 210 in. H20.
N0079 (01153-2758) Variant of the N0026 option with a vent/drain valve kit consisting of two threaded SST valve seats and two SST :5.50 inH20 Not affected by this valve stems. notification N0087 (01154-2712) Variant of the N0026 option with the electronic housing rotated 180 degrees.
N0089 (01154-2714) Variant of the N0026 option with the electronic housing rotated 90 degrees in the clockwise direction.
N0080 (01154-2705) Defines the use of a range Not affected by this code 9 module for a calibration :+/-(3%URL+1%span) notification range of 0 - 4000 psi.
N01 10 (01154-2725) Defines the use of a range code 9 module for a calibration E(3%URL+1%span) Not affected by this range of 0 - 4000 psi with notification adjustable damping, Nuclear Page 6 of 7
2012 Apr 02 11,03 AM EPM OUT ROSEMOUNT NUCLEAR 952-949- 8/8 Appendix C: List of Customers Domestic U.S. Customers ALABAMA POWER CO AMERICAN ELECTRIC POWER CO INC ARIZONA PUBLIC SERVICE CO/PINNACLE WEST CAPITAL BECHTEL POWER CORP CONSTELLATION ENERGY GROUP INC DOMINION NUCLEAR CONNETICUT INC/DOMINION GENERATION DUKE ENERGY CORP ECFS MCS EDISON MATERIAL SUPPLY LLC ELECTRO MECHANICS ENTERGY CORP EXELON GENERATION CO LLC FLORIDA POWER AND LIGHT CO FPL ENERGY LLC GEORGIA POWER CO NORTHERN STATES POWER - MINNESOTA DBA XCEL ENERGY PACIFIC GAS AND ELECTRIC COMPANY PROGRESS ENERGY FLORIDA INC PROGRESS ENERGY CAROLINAS INC PSEG NUCLEAR LLC SOUTH CAROLINA ELECTRIC & GAS SOUTHERN CALIFORNIA EDISON CO SOUTHERN NUCLEAR OPERATING COMPANY STP NUCLEAR OPERATING CO TENNESSEE VALLEY AUTHORITY TXU/LUMINANT GENERATION CO LLC WESTINGHOUSE ELECTRIC CO LLC MOS WT Nuclear Page 7 of 7