ML17158A455
| ML17158A455 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/23/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17158A454 | List: |
| References | |
| IEB-90-001, IEB-90-1, NUDOCS 9409070242 | |
| Download: ML17158A455 (2) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 ENCLOSURE 1
SAFETY EVALUA7ION BY THE OFFICE OF NUCLEAR REACTOR REGULATION LOSS OF FILL-OIL'INTRANSMITTERS MANUFACTURED BY ROSEMOUNT NRC BULLETIN 90-01 SUPPLEMENT 1
PENNSYLVANIA POWER AND LIGHT COMPANY SUS UEHANNA UNITS 1
AND 2 DOCKET NOS.
50-387 AND 50-388
- 1. 0 INTRODUCTION Nuclear Regulatory Commission (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 action to resolve this issue.,
The Supplement requests utilities to review the information for applicability to their facilities, perform testing on the 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 or not the licensee will take the actions requested, and a list of specific actions that the licensee would complete and the schedule for completing the actions.
Additionally, when 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 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 EVALUATION The licensee for the Susquehanna
- Plant, Pennsylvania Power and Light Company, responded to NRC Bulletin 90-01, Supplement 1, in submittals dated March 4,
- 1993, and Hay 31, 1994.
The Requested Actions delineated in Supplement 1
asked that licensees review plant records and identify any Rosemount Model 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.
Furthermore, the licensee was requested to evaluate their enhanced surveillance monitoring program.
A detailed evaluation of the licensee's response is documented in the enclosed contractor's report.
9O09070am 9<08a3 PDR ADOCK 05000387
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- 3. 0 CONCLUSION We have reviewed the licensee's response to NRC Bulletin 90-01, Supplement 1,
and conclude that the licensee conforms to the Requested Actions of NRC Bulletin 90-01, Supplement 1,
and has completed the reporting requirements.
Compliance with applicable Commission requirements may be the subject of NRC audits or inspections in the future.
Principal Contributor:
D. Spaulding, NRR Date:
August 23, 1994