ML20011F015
| ML20011F015 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/07/1990 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20011F013 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 50-334-89-25, 50-412-89-23, NUDOCS 9002230449 | |
| Download: ML20011F015 (2) | |
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APPENDIX A NOTICE OF DEVIATION Duquesne Light Company Docket No.
50-334/50-412 Beaver Valley Power Station, Units 1&2 License No. DPR-66/NPF-73 As a result of the Regulatory Guide (R.G.) 1.97 inspection conducted on December 4-8, 1989, and in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (Enforcement Policy) (1989), the following deviations were identified:
A.
R.G.1.97 revision 3, Table 1, Category 1 Design and Qualification Criteria for Instrumentation, Section 2 (Redundancy) states, in part, that: "No single failure within either the accident monitoring instrumentation, its auxiliary supporting features, or its power sources concurrent with the failures that are a condition or result of a specific accident should prevent the operators from being presented the information necessary for them to determine the.afety status of the plant and to bring the plant to and maintain it it a safe condition following an accident." Section 9 (Interfaces) states, in part, 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 this document."
1.
Contrary to Section 2 above on December 8,1989 it was determined that separate indicators were not provided for the three post-accident instrument channels monitoring the Unit 1 Steam Generator Level-Wide Range variable.
2.
Contrary to Section 9 above, on December 8,1989, it was determined that the installed instrumentation for the Unit 1 Steam Generator Level-Wide Range does nct have an isolation device between the instrument loops and the common strip chart three pen recorder for transmitter channels FW-477, FW-487 and FW-497.
B.
R.G. 1.97 revision 3, Table 1, Category 1 Design and Qualification Criteria for Instrumentation, Section 1 paragraph 4 states, in part, that:
"the seismic portion of qualification should be in accordance with R.G. 1.100, ' Seismic Qualification of Electric Equipment for Nuclear Power Plants.'
Instrumentation should continue to read within the required accuracy, following, but not necessarily during a safe shutdown earthquake."
Contrary to the above, on December 8,1989, it was determined that the Unit 2 recorders for the Steam Generator Level-Narrow Range were not seismically qualified.
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R,G.1.97 revision 3, Table 1, Category 1 Design and Qualification i
Criteria for Instrumentation, Section 8 (Equipment Identification) states, in part, that:
" Types A, B and C instruments designated as Category 1 and 2 should be specifically identified with a common designation on the control' panels so that the operator can easily discern that they are intended for use under accident conditions.
Contrary to the above, on December 8, 1989, it was determined that the Unit 2 Post-Accident Monitoring Recorders were not specifically identified with a common designation.
Pursuant to the provisions of 10 CFR 2.201, Duquesne Light Company is hereby requested to_ submit to this office within thirty days of the date of the letter which transmitted this Notice, a written statement or explanation in reply, including: (1) the corrective steps which have been taken and the results achieved;'(2) corrective steps which will be taken to avoid further deviations; and (3) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending this response time.
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