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| Start date | Reporting criterion | Title | Event description | System | LER | |
|---|---|---|---|---|---|---|
| ENS 53263 | 8 March 2018 05:00:00 | 10 CFR 21.21(d)(3)(i), Failure to Comply or Defect | Part 21 Notification - Defect Regarding Certain Pressure Transmitters and Amplifier Circuit Card Assemblies | The following notification is an excerpt from the received report: Pursuant to 10 CFR Part 21, section 21.21(b), Rosemount Nuclear Instruments, Inc. (RNII) is writing to inform you that a total of eleven (11) Model 1154 and 1154 Series H output range code 4 pressure transmitters whose model code includes special option suffix N0026 or N0087 and five (5) 01154-0153-0002 Amplifier Circuit Card Assemblies may not calibrate at all the published values. Name and address of the individual providing the information: Mr. Gerard Hanson Vice President & General Manager Rosemount Nuclear Instruments, Inc. 8200 Market Blvd Chanhassen, MN 55317 Nature of the failure and potential safety hazard: During evaluation of two returned 01154-0153-0002 Amplifier Circuit Card Assemblies (CCAs), it was observed that a single resistor (R316) on each affected Amplifier CCA had an incorrect resistance value. The N0026 and N0087 special options enable a standard upper range limit (URL) of a transmitter with output range code 4 to be increased from 150 inches water to 210 inches water, in combination with a minimum span of 75 inches water. This R316 resistor allows the transmitter to achieve performance specifications, calibration ranges, and spans as indicated by the special option drawing. In the sub-assembly process, the R316 resistor on a standard Amplifier CCA is replaced to create a new Amplifier CCA part number (01154-0153-0002). The R316 resistor enables the standard lower range limit (LRL) of a transmitter with output range code 4 to be decreased from -150 inches water to -210 inches water (negative pressure values imply pressure applied to the low-pressure side of the transmitter), in combination with a minimum span of 75 inches water. This R316 resistor allows the transmitter to achieve performance specifications, calibration ranges, and spans as indicated by the special option drawing. The new resistor's material traceability information is recorded on the traveler. In final assembly, each transmitter with special option suffix N0026 and N0087 is assembled using one of these 01154-0153-0002 Amplifier CCAs. It then receives a factory calibration check at 135 inches water to 210 inches water and customer specified calibrated range, to ensure conformance to the minimum span and maximum URL specifications, as defined by the special option drawing. Appropriate manufacturing paperwork is used to document and record each Amplifier CCA serial number, as well as each final assembly transmitter. To meet site specific application requirements, transmitters may be field recalibrated to different upper and lower range values and/or spans. Model 1154 and 1154 Series H transmitters with special option suffix N0026 or N0087 and Amplifier CCAs whose R316 resistors were not replaced during the sub-assembly process, will have incorrect resistance values and may not calibrate to all upper and lower range values and/or spans published for the applicable special option. However, if an affected transmitter has been successfully calibrated, having the incorrect resistance value will not adversely affect transmitter performance specifications during normal operation or accident conditions. The manufacturing records for the two returned Amplifier CCAs, part number 01154-0153-0002, were carefully reviewed. The sub-assembly traveler lacked the required material traceability information, indicating that the R318 resistors were not replaced. RNII reviewed all sub-assembly travelers for part number 01154-0153-0002. The issue has been isolated to one lot which included (16) Amplifier CCAs. On March 8, 2018, RNII concluded that a substantial safety hazard may exist. The corrective action which has been taken; the name of the individual or organization responsible for that action; and the length of time taken to complete that action: (a) RNII previously discontinued manufacturing 01154-0153-0002 Amplifier CCAs, there are no Amplifier CCAs currently in production or finished goods. (b) RNII examined all manufacturing paperwork for all 01154-0153-0002 Amplifier CCAs, and other than the single lot of (16) Amplifier CCAs described above, no additional discrepancies were found. Any advice related to the potential failure of the item: The end user is advised to determine the impact of this potential non-conformance on its plant operations and safety and take action as deemed necessary. Affected 01154-0153-0002 Amplifier CCA(s) and transmitter(s) can be returned to RNII for rework. Contact RNII to facilitate the return process. If there are any questions, or you require additional Information related to this issue, please contact: Mike Dougherty (206) 665-1112, Paul Schmeling (952) 949-5359, or Brian VanderWoude (952) 949-5207. Shipped as piece parts (P/N 01154-0153-0002) to Arkansas Nuclear One and Waterford. Shipped as part of transmitter (N0026 and N0087) to Palo Verde, St. Lucie, and Calvert Cliffs. | ||
| ENS 49370 | 20 September 2013 05:00:00 | 10 CFR 21.21(d)(3)(i), Failure to Comply or Defect | Part 21 Issue on Rosemount Model 710Du Trip Units | The following is a summary of the information received from Rosemount Nuclear Instruments, Inc. (RNII) via facsimile: In August 2013, Rosemount conducted normal, transient and accident radiation testing on a sample of Model 710DU Trip Units (master and slave) to verify radiation performance of some commercial grade semiconductor components. The results indicated that post-exposure radiation performance may not meet the criteria established in their previously published Qualification Report D8200037. This affects all transmitters shipped from RNII since June 1983. Per RNII's Model 710 Trip/Calibration System Discontinuance Letter dated September 14, 2011, RNII stopped accepting purchase orders as of December 31, 2012. At this time RNII is no longer accepting orders and no corrective actions are being taken. These transmitters were purchased by: Carolina Power and Light/Duke Energy, Commonwealth Edison Co., Constellation Energy Group, Inc., DTE Energy Services, Inc., Energy Northwest, Entergy Nuclear, LLC, Exelon Generation Co., LLC, Gavial, General Physics Corp., GE Nuclear Energy, Georgia Power Co./Southern Nuclear Operating Co., Harlo Corp., Knolls Atomic Power Lab, Long Island Lighting Co., Mercury Co. of Norwood, Inc., Mississippi Power & Light Co., Nebraska Public Power District, NextEra Energy/FPL Energy, Northern States Power/XCEL Energy, Inc., NuTherm International, Inc., PPL Susquehanna, LLC, Progress Energy Carolinas, LLC/Duke Energy, PSEG Nuclear, LLC, Public Service Electric & Gas, Singer Co., Tennessee Valley Authority, Texas Municipal Power Agency, United Controls and Westinghouse Electric Corporation. 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 | ||
| ENS 47693 | 16 February 2012 06:00:00 | 10 CFR 21.21 | 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-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 * * * The following information was received by facsimile: This revision only affects Section 4.0 of the 23 February 2012 notification letter. The pressure values listed in Section 4.0 at 8 hours and 56 hours have been corrected. No other changes have been made." Notified R1DO(Caruso), R2DO(Lesser), R3DO(Dickson), R4DO(Haire) and Part 21 Group via email. | ||
| ENS 47716 | 16 February 2012 06:00:00 | 10 CFR 21.21 | Part 21 Report - Rosemont Pressure Transmitters Out of Tolerance Condition | The following information was received by facsimile: During the course of qualification testing to replace certain diodes identified for obsolescence, an out of tolerance condition during steam pressure/temperature testing was observed on a test pressure transmitter in the qualification program. Through investigation into the out of tolerance condition, it was determined that the condition was not related to the replacement diode, but rather the result of the magnitude of a resistance change made to the transmitter temperature compensation circuitry during a final factory acceptance test. A brief description of the final acceptance test follows. During pressure transmitter final processing, a test is conducted on Model 1154 Series H pressure transmitters to assess the effects of ambient temperature changes on the 4mA to 20mA analog output. The temperature test is performed on each transmitter to verify the transmitter accuracy performance over normal operating temperatures from 40 F to 200 F. If the transmitter does not meet the acceptance criteria for the test, changes can be made to the compensating resistor values to optimize performance in the normal operating temperature range. If the resistance adjustment is too large, it has been determined that the accuracy of the pressure transmitter relative to the published steam pressure/temperature profile and accuracy specification may be exceeded during a steam pressure/temperature event. The magnitude of output shift during steam pressure/temperature conditions, that is attributable to the resistance changes made in final processing, is predictable based on the specific amount of resistance added or subtracted during the compensation process for each transmitter. Accordingly, RNII (Rosemount Nuclear Instruments, Inc) has reviewed the production records for the potentially affected transmitters and a revised steam pressure/temperature accuracy specification has been established for each shipped pressure transmitter. The revised steam pressure/temperature accuracy specification has been listed by serial number. This revised specification supersedes the published steam pressure/temperature accuracy specification for all Model 1154 Series H pressure transmitters affected by this notification. Also note that for certain calibrations with large zero elevation and suppressions as defined in RNII's Part 21 Notification, dated February 23, 2012, an alternate steam pressure/temperature accuracy specification is also provided for pressure transmitters that are affected by both notifications. All other 1154 Series H published specifications remain unchanged. On February 23, 2012, it was concluded that a substantial safety hazard may exist. RNII 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. The manufacturing rework procedure 01153-3000 has been updated to limit the amount of acceptable resistance that may be added or subtracted during final testing. A revised steam pressure/temperature accuracy specification for each pressure transmitter impacted by this notification has been determined. RNII recommends that users review the application where 1154 Series H pressure transmitters are used to determine if there are safety considerations related to the revised steam pressure/temperature accuracy specification. The United States nuclear sites associated with this Part 21 are: Farley, D.C. Cook, Palo Verde, ANO-1, Calvert Cliffs, Point Beach, Oconee, Catawba, Waterford 3, Braidwood, La Salle, Davis Besse, Crystal River 3, Vogtle, Millstone, Diablo Canyon, Salem, Hope Creek, San Onofre, South Texas, Watts Bar, Comanche Peak, Wolf Creek, St. Lucie, Dominion Energy - Unspecified, and Northeast Nuclear Energy - Unspecified. * * * UPDATE FROM DUYEN PHAM TO PETE SNYDER ON 4/3/12 AT 1531 EDT * * * The following information was received by facsimile: This revision potentially affects the following commercial nuclear power plant sites in the United States: 1. Calvert Cliffs, 2. Millstone, 3. Hope Creek, 4. Salem, 5. Catawba, 6. Crystal River, 7. Farley, 8. Oconee, 9. St. Lucie, 10. Vogtle, 11. Watts bar, 12. Braidwood, 13. Davis Besse, 14. D.C. Cook, 15. LaSalle, 16. Point Beach, 17. Arkansas Nuclear One, 18. Comanche Peak, 19. Diablo Canyon, 20. Palo Verde, 21. San Onofre, 22. South Texas Project, 23. Waterford 3, and 24. Wolf Creek. Note: Notification #1 (EN #47693), dated 23 February 2012 (and revised on 2 April 2012) impacts ALL 1154 Series H pressure transmitters range codes 4 to 8 shipped since 1988. This does NOT impact the 1154SH9 since the 1154SH9 has a wider steam pressure/temperature specification. The revised specification is the same for all affected transmitters. Note: Notification #2 (this report - EN #47716), dated 2 March 2012 (and revised as of today (3 April 2012)) impacts only a subset of 1154 Series H pressure transmitters range codes 4 to 9 shipped from March 1994 to February 2012. This is a smaller affected population and does include the range 9 in the scope. The revised specification for this second issue is serial number dependent and only affects the transmitters listed in Appendix A (of the full part 21 report). Notified R1DO(Caruso), R2DO(McCoy), R3DO(Bloomer), R4DO(Haire), and Part 21 Group via email. | ||
| ENS 46449 | 22 November 2010 06:00:00 | 10 CFR 21.21 | Anolmaly Discovered on Rosemount Model 1152 Differential Pressure Transmitters with Output Code "L" 10-50 Ma Electronics | The following was received via fax: Rosemount Nuclear discovered an anomaly in Model 1152 differential pressure transmitters while troubleshooting a separate, unrelated issue. The anomaly is related to the pressure transmitters response during a overpressure condition. Normally, under a low side overpressure condition, the output will go off-scale and remain off scale for conditions less than 10 mA. Rosemount has discovered that some detectors may go off-scale and then return to on-scale between 10mA and 50 mA, rather than remain off scale under 10mA. This is caused by a change made to operational amplifier components in March 2001. Rosemount recommends all customers evaluate the safety impact of this anomaly on their plants. No field failures have been reported to date. The following sites are affected: Browns Ferry, Brunswick, Cook, Dresden, Duane Arnold, Fermi, Fort Calhoun, Ginna, Hatch, Indian Point, Kewaunee, Millstone, Nine Mile Point, Oyster Creek, Palisades, Pilgrim, Quad Cities, Sequoyah, Vermont Yankee, and Watts Bar. | ||
| ENS 43826 | 15 November 2007 06:00:00 | 10 CFR 21.21 | Part 21 - Potential Insufficient Thread Engagement for Certain Pressure Transmitters | Rosemount Nuclear Instruments, Inc. (RNII) reported that certain Model 1152, 1153 Series B and D, and 1154, and 1154 Series H Pressure Transmitters may have inadequate thread engagement between the electronics housing and sensor module. Transmitters affected by this notification may not confirm to RNII specifications under accident conditions. Supplier testing has determined that no immediate risk exists, however it is RNII's opinion that two threads of engagement may not be sufficient to assure that the product will perform its intended safety function over the qualified life of the transmitter. The following are the potentially affected licensees: Oyster Creek, Calvert Cliffs, Kewaunee, North Anna, Millstone, Surry, Turkey Point, Vogtle, Diablo Canyon, Shearon Harris, South Texas Project, Browns Ferry, and Wolf Creek. | ||
| ENS 43266 | 12 January 2007 05:00:00 | 10 CFR 21.21, Notification of failure to comply or existence of a defect and its evaluation | Part 21 - Rosemount Pressure Transmitter May Not Be Seismically Qualified | During routine operations on the RNII production floor, it was observed that an incorrect torque wrench was being used at mechanical assembly to tighten the Sensor Module Lock Nut. The incorrect tool was calibrated to a value of 12.5 ft-lb, resulting in undertorquing of the lock nut. The incorrect torque wrench was removed from service and replaced with a tool calibrated to the correct torque value of 35 ft-lb. RNII reworked all affected transmitters that had not yet shipped to the correct torque value. Assembly with the incorrect tool could result in certain pressure transmitters having a degraded environmental seal between the sensor module and the electronics housing during or after a seismic event. The five affected models have been delivered to the Byron and Comanche Peak nuclear stations. |