ML18153B164
| ML18153B164 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 11/23/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18152A346 | List: |
| References | |
| IEB-90-001, IEB-90-1, NUDOCS 9412050336 | |
| Download: ML18153B164 (3) | |
Text
e UNITED STATES e
ENCLOSURE 1 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555--0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION LOSS OF FILL-OIL IN TRANSMITTERS MANUFACTURED BY ROSEMOUNT NUCLEAR REGULATORY COMMISSION (NRC) BULLETIN 90-01, SUPPLEMENT 1 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2, NORTH ANNA POWER STATION UNITS 1 AND 2 DOCKET NOS. 50-280, 50-281, 50-338, 50-339
1.0 INTRODUCTION
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 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, when the specific actions committed to in the licensee's response were completed, the licensee was required to provide a statement confirming said com~letion.
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 Surry Power Station Units 1 and 2, and North Anna Power Station Units 1 and 2, Virginia Electric and Power Company, responded to NRC Bulletin 90-01, Supplement 1 in submittals dated March 16, 1993, October 14, 1993, and July 12, 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.
9412050336 941123 PDR ADOCK 05000280 G
PDR Enclosure l
~I A detailed evaluation of the licensee's response is documented in the enclosed contractor's report.
3.0 CONCLUSION
The staff has reviewed the licensee's response to NRC Bulletin 90-01, Supplement 1, and concludes that the licensee conforms to the Requested Actions of NRC 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 Date: November 23, 1994
ONAL ENGINEER NG LABORATORY Evaluation of Utility Response to Supplement 1 to NRC Bulletin 90-ul; North Anna-1/-2 and Surry-1/-2
~Lockheed Idaho Technologies Company I~EL-9<+:'C]03 October 1994 Alan C. Udy Idaho National Engineering Laboratory Work performed under DOE Contract No. DE-AC07-94lD13223