ML20052H897
| ML20052H897 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/12/1982 |
| From: | Woolever E DUQUESNE LIGHT CO. |
| To: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8205240150 | |
| Download: ML20052H897 (2) | |
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May 12, 1982
- 1521, United States Nuclear Regulatory Comission Region I 631 Park Avenue King of Prussia, PA 19406 ATTENTION:
Mr. R. C. Haynes Administrator SUBJECP:
Beaver Valley Power Station - Unit No. 2 Interim Report - Two RCS Wide-range Pressure Transmitters Docket No. 50-412 Significant Deficiency Report No. 82-02 Gentlemen:
This interim report is in reference to the potential significant
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deficiency in two reactor coolant system (RCS) wide-range pressure trans-mitters reported to the N clear Regulatory Comission by E. F. Kurtz of Duquesne Licht Company on.pril 13, 1982.
Due to the inaccuracy of RCS wide-range pressure measurement in a post-accident environment, Westinghouse is currently evaluating several possible corrective actions taking into account the licensing basis of Beaver Valley Power Station - Unit No.
2.-
Pursuant to the requirements of 10CFR50.55(e), a written interim report is subnitted, and it is presently anticipated that a subsequent report on this matter should be subnitted to you on October 18, 1982.
DUQUESNE LIGHT COMPANY By e-E. JfAoolever Vice President JMM/wjs Attachment cc:
Mr. G. Walton, NRC Resident Inspector (w/ attachment)
Ms. E. Doolittle, Project Manager (w/ attachment) 8205240150 820512 PDR ADOCK 05000412 g
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e 1.
DESCRIPTION OF THE DEFICIENCY, Wide-range reactor coolant system (RCS) pressure measurements serve as the criteria for the termination of safety injection (SI) in a number of post-accident functions. When combining transmitter, signal conditioning, and indicator allowance for error due to cali-bration uncertainty, drift, environmental effects, etc., recent cualification tests in a post-accident hich-energy line break environment have indicated that the wide-range RCS pressure channels exhibit inaccuracies. These inaccuracies rnay cause the pressurizer power operated relieve valves to be lifted prior to the termination of SI in a post-accident operation.
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Arr'tLTtD STRUCIURE(S), SYSTEM (S), COMPONENT (S)
The involved structures are two (2) reactor coolant system wide-range pressure transmitters supplied by the Westinghouse Corporation.
3.
ANALYSIS OF SAFEIY IMPLICATIONS The inaccuracy of RCS wide-range pressure measurement leads to the possibility that the pressurizer power operated relief valves may be lifted prior to the termination of SI.
This could lead to a greater number of valve challences thus increasina the probability of a small loss-of-coolant accident due to the valve failina open. Like-wise, the inaccuracy of this measurement could lead to the termina-tion of SI below the set-point for autcznatic SI.
The potential post-accident inaccuracy of the RCS wide-range pressi.re measurement constitutes a Significant Deficiency for some plants under construction as defined in 10CFR50.55 (e) (1) (ii). This deter-mination was made because the desian does not conform to the criteria and bases stated in the Safety Analysis Rerort or Construction Permit.
In particular, the accuracy functional requirements for Regulatory Guide 1.97, Fevision 1 (including the requirements for safety crade cold shutdown, if so committed), are not demonstrated to be satis-fied by the current instrumentation.
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INALUATION OF POSSIBLE CORREPTIVE ACTION The Westinghouse Owners Group Procedures Subccrrmittee met on April 29 and 30, 1982. As part of this meeting, the SI termination requirements were reviewed. An additional report, including the results of this review, should be subnitted to you or October 18, 1982.
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