ML20079M855
| ML20079M855 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/24/1983 |
| From: | Woolever E DUQUESNE LIGHT CO. |
| To: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, 2NRC-3-010, 2NRC-3-10, 82-02, 82-2, NUDOCS 8303030286 | |
| Download: ML20079M855 (4) | |
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(412)787 - 5141 (412)923 - 1960 Telecopy (412) 787-2629 Nuclear Construction Division Robinson Plaza, BuildinD 2. Suite 210 February 24, 1983 Pittsburgh, PA 15205 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 A'"TENTION:
Mr. R. C. Haynes Administrator
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Two Reactor Coolant System Wide-Range Pressure Transmitters Significant Deficiency No. 82-02 Gentlemen:
Pursuant to the requirements of 10CFR50.55(e), the " Final Report on Potential Deficiency in Two Reactor Coolant System Wide-Range Pressure Transmitters" is attached for your review.
If there are any questions concerning this report, please contact the Beaver Valley Unit 2 Project Office.
DUQUESNE LIGHT COPPANY By
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E. J. Woolever Vice President JMM/wjs Atttchment cc:
Mr. R. DeYoung, Director Office of Inspection and Enforcement (3) (w/a)
NRC Document Control Desk (w/a)
Mr. G. Walton, NRC Resident Inspector (w/a)
Ms. L. Lazo, Project Manager (w/a)
SUBSCRIBEDANDSJORNTOBEFOREMETHIS
- /// DAY OF 7/j/us e,-, 1983.
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Notary Public ANITA ELAINE REITER, NOTARY PUDLIC ROBINSON TOWNSHIP, ALLEGHINY COUNTY MY COMMISSION EXPIRES OCI0BER 20,19y I
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United States Nucle r R:gulttory Commicsion Mr. R. C. Haynes page 2 COMMONWEALTH OF PENNSYLVANIA )
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COUNTY OF ALLEGHENY
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On this,2/f2 day of m
/9 83
, before me, r
a Notary Public in and for said Conunonwealth and County, personally appeared E. J.
Woolever, who being duly sworn, deposed and said that (1) he is Vice President of Duquesne Light, (2) he is duly authorized to exe-cute and file the foregoing Submittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge.
U Notary Public ANITA ELAINE REITER, NOTARY PUBLIC ROBINSON TOWNSHIP, ALLEGHENY COUNTY MY COMMISSION EXPIRES OCTOBER 20,1986 t
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BEAVER VALLEY POWER STATION - UNIT NO. 2 DUQUESNE LIGHT COMPANY Final Report on Potential Deficiency in Two Reactor Coolant System Wide-Range Pressure Transmitters 1.
SUMMARY
Westinghouse Water Reactor Division (WRD) Safety Review Committee found that a Potentially Reportable Significant Deficiency exists for Beaver Valley Power Station - Unit =No.
2 (BVPS-2) because of the potential post-accident inaccuracy of the Reactor Coolant System (RCS) wide-range pressure measurements.
Wide-range RCS pressure measurements are used in a number of post-accident functions.
2.
IMMEDIATE ACTION TAKEN Westinghouse (W) notified Duquesne Light Company (DLC) of the potential problem by telephone on April.13, 1982.
DLC notified E. B. McCabe of the Nuclear Regulatory Commission (NRC) by telephone on April 13, 1982.
Additional details were provided to Region I of fice in Interim Report No. 1, "Two RCS Wide-Range Pressure Transmitters," dated May 12, 1982, and Interim Report No. 2, dated October 18, 1982.
3.
DESCRIPTION OF THE DEFICIENCY Wide-range RCS pressure measurements serve as the criteria for the termination of safety injection (SI) in a number of post-accident func-tions.
When combining transmitter, signal conditioning, and indicator allowance for error due to calibration uncertainty, drift, environ-post-accident, mental effects, etc.,
recent qualification tests in a high-energy line break environment have indicated that the wide-range RCS pressure channels exhibit inaccuracies.
These inaccuracies may cause the pressurizer power-operated relief valves to be lifted prior to the termination of SI in a post-accident operation.
4.
ANALYSIS OF SAFETY 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 challenges, thus increasing the probability of a small loss-of-coolant accident due to the valve failing open.
Likewise, the inaccuracy of this measurement could lead to the termination of SI below the setpoint for automatic SI.
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1 5.
CORRECTIVE ACTION TO REMEDY DEFICIENCIES W has determined that the only way the wide-range pressure transmitters maintain required accuracy in-containment-is if they are environmen-tally protected (temperature and radiation).
If protection cannot-be provided to the transmitters, they should ~ be located out-of-contain-ment.
BVPS-2 has chosen to lo.: ate two wide-range RCS pressure trans-mitters outside the containment structure.
These transmitters wil' connect to the Reactor. Vessel Level. Indication System instrument piping by means of a sealed system in order to satisfy post-accident accuracy requirements.
The two direct sensing' wide-range RCS pressure trans-mitters which remain inside - the ' containment will be used for over-pressure protection.
The two additional transmitters located outside containment will be implemented with the Reactor Vessel Level Indica-tion System installation.
6.
ADDITIONAL REPORTS There'will be no further reports. This is the final report.
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