ML20098F204
| ML20098F204 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/05/1984 |
| From: | Woolever E DUQUESNE LIGHT CO. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 2NRC-4-138, 82-02, 82-2, NUDOCS 8410020458 | |
| Download: ML20098F204 (4) | |
Text
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$VL rp 2NRC-4-138 a
(412) 787 - 5141 Telecopy 2
-6 Nuclear Construction Division August 5, 1984 Flobinson Plaza, Building 2, Suite 210 Pittsburgh, PA 15205 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 ATTENTION:
Dr. Thomas E. Murley Administrator
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Two Reactor Coolant System Wide-Range Pressure Transmitters Significant Deficiency Report No. 82-02, Updated Final Report Gentlemen:
On February 24, 1983, Duquesne Light Company (DLC) s ubmitted the final report on Significant Deficiency No. 82-02, "Two Reactor Coolant System Wide-Range Pressure Transmitters."
This updated final report clarifies the reason for leaving the direct sensing wide range pressure transmitters in containment.
DLC anticipates no further reports on this matter.
DUQUESNE LICHT COMPANY By E. (J. Woolever Vice President RW/wjs Attachment cc:
Mr. R. DeYoung, Director (3) (w/a)
Ms. M. Ley, Project Manager (w/a)
Mr. E. A. Licitra, Project Manager (w/a)
Mr. G. Walton, NRC Resident Inspector (w/a)
NRC Document Control Desk (w/a)
SUBSCRIBED AND SWJ)RN TO BEFORE ME THIS
//// DAY OF pffse 8+t./m 1984.
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A LJ JW Notary Public 8410020458 840805 AN!!A ELA!ilE REITER, ?!OTARY PUBLIC 05000 CGElfJSON TOWN 2 HIP, ALLEGHENY COUNTY MY COMMiGSION EXP!RES OCTOBER 20,1986 l
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1 Unit d Stcton Nuciscr R2gulttcry Cosmiccicn Dr. Thoma3 E. Murlsy Page 2 COMMONWEALTH OF PENNSYLVANIA' )
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COUNTY OF ALLEGHENY
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On this s/f/
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, before me, a
~- Notary Public in and for said Commonwealth and County, personally appeared E. J. Woolever, who being duly sworn, deposed and said that (1) he is Vice President of Duquesne Light, (2) h: is duly authorized to execute 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 bes t of his knowledge.
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Notary Public ANITA ELAINE REITER, NOTARY PUBLIC PGBINSON TOWNSHIP, ALLEGHENY COUNTY MY COMMISSION EXPIRES OCTOBER 20,1986 L
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e BEAVER VALLEY POWER STATION - UNIT NO. 2 DUQUESNE LIGHT WMPANY Updated 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 Beave r Valley Power Station - Unit No. 2 (BVPS-2) because of the potential post-accident inaccuracy of the Reactor Coolant System (RCS) wide-range pres-sure 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 Commis s ion (NRC) by telephone on April 13, 1982.
provided to Region I of fice in interim reports Additional details we re dated May 12, 1982, Oc tobe r 18, 1982, and the final report dated February 24, 1983.
3.
DESCRIPTION OF THE DEFICIENCY Wide-range RCS pressure measurements serve as the criteria for the termi-nation of safety injection (SI) in a number of post-accident funct ions.
When combining transmitter, signal conditioning, and indicator allowance for error due to calibration uncertainty, drift, environmental ef fect s,
etc.,
recent qualification tests in a po s t-ac cident, high-energy line break environment have indicated that the wide-range RCS pressure chan-nels exhibit inaccuracies.
Thede inaccuracies may cause the pressurizer power-operated relief valves to be lif ted 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 possi-bility that the pressurizer powe r-operated relief valves may be lifted prior to the termination of SI.
This could lead to a greater number of valve ch allenge s, thus increasing the probability of a small los s-o f-c.alant accident due to the valve failing open. Likewise, the inaccuracy of this meas urement could lead to the termination of SI below the set-point for automatic SI.
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 environmentally protected (temperature and radiation).
If protection cannot be provided to the transmitters, they should be located out-of-containment.
BVPS-2 L
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has chosen to locate two wide-range RCS pressure transmitters outside the containment otructure.
These transmitters will connect to the Reactor Vessel Level Indication System' instrument piping and will be installed in conjunction with that system.
The two direct sensing wide-range RCS pressure transmitters which remain inside the containment will be used for cold overpressure protection.
6.
ADDITIONAL REPORTS l
This is an update to the final report.
No additional reports are anticipated.
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