ML20080T685
| ML20080T685 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/08/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080J079 | List: |
| References | |
| IEB-90-001, IEB-90-1, NUDOCS 9503140068 | |
| Download: ML20080T685 (2) | |
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UNITED OTATES '
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NUCLEAR REGULATORY COMMISSION ~
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO NRC BULLETIN 90-01. SUPPLEMENT 1 i
LOSS OF FILL-0IL IN TRANSMITTER MANUFACTURED BY ROSEMOUNT ENTERGY OPERATIONS. INC.
RIVER BEND STATION. UNIT I DOCKET NO. 50-458
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INTRODUCTION i
NRC Bulletin 90-01 Supplement 1, was issued by the NRC on December 22, 1992, to inform ~ addressees.of activities taken by the NRC staff and the industry in evaluating Rosemount transmitters and to request licensees to take actions to resolve this issue. The supplement requests utilities to review the information for applicability to their facilities, perform testing on the
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transmitter commensurate with its importance to safety and demonstrated failure rate, and modify as appropriate their actions and enhanced surveillance programs.
The supplement also requested that the licensee provide a response that included a statement as to whether the licensee will take the actions requested, a list of specific actions that the licensee would complete, and the schedule for completing the actions. Additionally, wNn the specific actions committed to in the licensee's response were completed, the licensee was required to provide a statement confirming said completion.
If the i
licensee did not plan to comply with all of the requested actions as delineated in the supplement, a statement was required identifying those requested actions not taken, as well as an evaluation which provided the bases for requested actions not taken.
2.0 DISCUSSION AND EVALUAi10N
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The licensee for the River Bend Station, Unit 1, Entergy Operations, Inc.,
j responded to NRC Bulletin 90-01, Supplement 1, in submittals dated March 11, 1993, and February 15, 1995. The requested actions delineated in Supplement 1 I
asked that licensees review plant records and identify any Rosemount Model
.I 1153 Series B, Model 1153 Series D, and Model 1154 transmitters manufactured before July 11, 1989, that are used or may be used in the future in either safety-related systems or systems installed in accordance with 10 CFR 50.62 (the ATWS rule). Additionally, the licensee was to commit to a specified -
enhanced surveillance monitoring frequency that corresponded to the normal operating pressure of the transmitters identified.
1 ENCLOSURE 1
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Furthermore, the licensee was requested to evaluate their enhanced l
L surveillance monitoring program.
In their March 11, 1993 response, the licensee indicated a committed ~to replace transmitter IE31*PDTN088A.
This transmitter was the only remaining transmitter with a normal operating pressure between 500 79d.1500 psi that had not'been replaced nor reached its psi-month maturity at the time of the initial response. Confirmation of completion of this commitment was received in the correspondence dated February 15, 1995.
A detailed evaluation of the licensee's response is documented in the contractor's Technical Evaluation Report.
3.0 CONCLUSION
The staff has reviewed the licensee's response to NRC Bulletin 90-01, Supplement 1, and concluded that the licensee conforms to the requested actions and has completed the reporting requirements.
Compliance with applicable NRC requirements may be the subject of NRC audits.or inspections in the future.
Principal Contributor:
J. Ganiere Date: March 8, 1995
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