ML18153C364
| ML18153C364 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/06/1990 |
| From: | Julian C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18152A430 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 50-280-90-22, 50-281-90-22, NUDOCS 9009240233 | |
| Download: ML18153C364 (2) | |
Text
ENCLOSURE 1 NOTICE OF DEVIATION Virginia Electric and Power Company Surry 1 & 2 Docket Nos. 50-280, 50-281 License Nos. DPR-32, DPR-37 During an NRC inspection conducted on July 9-19, 1990 a deviation from a written commitment was identified.
In accordance with the 11General Statement of Policy and Procedure for NRC Enforcement Action 11
, 10 CFR Part 2, Appendix C, (1990),
the deviation is listed below:
Virginia Electric and Power Company responded their compliance to RG 1.97 (NUREG 0737, Supplement 1) in letters dated January 31, 1984; May 10, 1985; June 21, 1985; August 2, 1985; April 21, 1986; and August 12, 1987 (RG 1.97, Revision 3).
RG.1.97, Revision 3, Table 1, Design and Qualification criteria for Instrumentation, lists the twelve criteria and specifically defines the requirements for each criteria.
Criteria 1, Equipment Qualification, states that qualification applies to the complete instrumentation cha~nel from sensor to display. It further states that the seismic portion of qualification should be in accordance with RG 1.100, Seismic Qualification of Electric Equipment for Nuclear Power Plants.
Seismic qualification applies to instrumentation for Category 1 variables.
Criteria 9, Interfaces, states that the transmission of signals for other use should be through isolation devices that are designated as part of the monitoring instrumentation and that meet the provisions of RG 1.97.
Interface requirements apply to instrumentation for Category I and 2 variables.
Contrary to Criteria 1 above, during July 9-19, 1990, unqualified commercial grade indicators and recorders were installed in RG 1.97 instrumentation loops to monitor Category 1 variables.
Contrary to Criteria 9 above, during July 9-19, 1990, instrumentation loops for Category 1 and 2 variables did not have isolations devices between the RG 1.97 displays and the non Class IE plant computer.
Please provide to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and if applicable a copy to the NRC Resident Inspector Surry, in writing within 30 days of the date of this Notice, the reasons for the deviation, the corrective steps which have been taken and the results achieved, 9009240233 90g&Z8~ao PDR ADOCK PNU Q
Virginia Electric and Power Company 2 Surry 1 & 2 Docket Nos. 50-280, 50-281 License Nos. DPR-32, DPR-37 the corrective steps w~ich will be taken to avoid further deviations, and the date when your corrective action will be completed.
Where good cause is shown, consideration will be given to extending the response time.
Dated at Atlanta, Georgia this 6th day of September 1990 FOR THE NUCLEAR REGULATORY COMMISSION Ut~-- /f O
~!0~7.7 Caudle A. Julian, Chief Engineering Branch Division of Reactor Safety