ENS 47716
ENS Event | |
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06:00 Feb 16, 2012 | |
Title | Part 21 Report - Rosemont Pressure Transmitters Out of Tolerance Condition |
Event Description | 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.
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. |
Where | |
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Rosemount Nuclear Chanhassen, Minnesota (NRC Region 3) | |
Organization: | Rosemount Nuclear |
Reporting | |
10 CFR 21.21 | |
Time - Person (Reporting Time:+370.85 h15.452 days <br />2.207 weeks <br />0.508 months <br />) | |
Opened: | Duyen Pham 16:51 Mar 2, 2012 |
NRC Officer: | John Knoke |
Last Updated: | Apr 3, 2012 |
47716 - NRC Website | |
Rosemount Nuclear with 10 CFR 21.21, Notification of failure to comply or existence of a defect and its evaluation | |
WEEKMONTHYEARENS 476932012-02-16T06:00:00016 February 2012 06:00:00
[Table view]10 CFR 21.21, Notification of failure to comply or existence of a defect and its evaluation Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ENS 477162012-02-16T06:00:00016 February 2012 06:00:00 10 CFR 21.21, Notification of failure to comply or existence of a defect and its evaluation Part 21 Report - Rosemont Pressure Transmitters Out of Tolerance Condition ENS 464492010-11-22T06:00:00022 November 2010 06:00:00 10 CFR 21.21, Notification of failure to comply or existence of a defect and its evaluation Anolmaly Discovered on Rosemount Model 1152 Differential Pressure Transmitters with Output Code "L" 10-50 Ma Electronics ENS 438262007-11-15T06:00:00015 November 2007 06:00:00 10 CFR 21.21, Notification of failure to comply or existence of a defect and its evaluation Part 21 - Potential Insufficient Thread Engagement for Certain Pressure Transmitters ENS 432662007-01-12T05:00:00012 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 2012-02-16T06:00:00 | |