ML20098E857
| ML20098E857 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/05/1984 |
| 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 8410020034 | |
| Download: ML20098E857 (5) | |
Text
PLEASE'N01E2 This lottor is bsing raissusd to
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corrcet data of August 5, 1984 to rud S ptemb2r 5, 1984.
DESIGNATED GRIGINAL
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Certi N-2
-st i Tei. coo,h!ls-s15 September 5, 1984 Nues.or construction olvimon Rocinton Pia 28. Building 2. Swit 210 Pittscurgn. P A 152CS 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 Ccapany (DLC) submitted 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 le aving the direct sens ing vide range pres sure transmitters in containment.
DLC anticipates no further raporta on this matter.
DUQUESNE LIGHT COMPANY By E. g. Woo Lever Vice President RW/vjs Attachment Mr. R. DeYoung, Director (3) (w/a) ec:
Hs 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) l l
SUBS,CRIBED AND SWORN TO BEFORE ME THIS
.M/ DAY OF x / w 8.* 1 t-1984.
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hnitcdSectosNucloceR;gulctcryCommissien Dr. Thoma3 E. Murlcy Page 2 COMMONWEALTH OF PENNSYLVANIA )
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COUNTY OF ALLEGHE!rt
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On this df/
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////, be fore me, a Notary Public in and for said Commonwealth and County, personally appeared E. J. Woolever, who being duly sworn, deposed and said that (i) he is Vice President of Duquesne Light, (2) he is duly authorized to execute and file and (3) the statements the foregoing Submittal on behalf of said Company, set fortn in the Submittal are true and correct to the be s t of his knowledge.
f/ s.Y 1-t v i 1l Notary Public ANITA ELAINE REITER, NOTARY PUBLIC CCSINSON TOWNSHIP. ALLEGHENY COUNTY MY COMMIS$10N EXPtRES OCT08EM 20.1986 I
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RW/wjs NR/NRC/SDR8202 Attachment bec: J. J. Carey (w/ attachment)
J. A. Multz C. E. Ewing T. D. Jones -
T. P. Noonan M. M. Siegel R. J. Swiderski L. E. Arch R. Coupland D. G. $sucs D. H. Williano J. Pedro (NUS)
C. R. Bishop R. Wittschen D. Chamberlain (S&W) "
P. RaySircar (6)
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T. J. Lex (4)
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NCD File SDR 82-02 File 4
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Y BEAVER VALI.EY POWER STATION - UNIT NO.,2 DUQUCSNE LICHT COMPANY
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Updated Final Report on Potential Deficiency in Two' Reactor Coolant System Wide-Range Pressure Transmitters i
1.
SUMMARY
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Westinghouse Water Reactor Division (WRD) Safety Review Committee found that a Potentially Reportable Significant Deficiency..a.xis ts for Beaver Valley Power Station - Unit No. 2 (BVFS-2) because of the potential post-accident inaccuracy of the Reactor Coolant Systets (RCS) '. ride-range pres-are used in a sure measurements.
Wide-r ango RCS pressure measurements number of post-accident func t. ions.
2.
IMMEDIATE ACTION TAKEN Westinghouse (W) notified Duquesne Light Cotapany (DLC) of the po tential problem by telephone on April 13, 1982. DLC notified E. B. McCabe of the Nuc lear Regulatory Commission (MRC) by telephone on April 13, 1982.
Additional details were provid ed to. Region I of fice in interim repo rts dated May 12, 1982, Octobe r 18, 1982, and the final report dated February 24, 1983.
4 3.
DESCRIPTION OF THE DEFICIENCY Wide-range RCS pressure casasurements se'tve as the critaria for the taral-nation of safety injection (SI) in a nusber of post-accident functions.
When combining transmitter, sissal conditioning, and indicator allowance for error due to calibration uncertainty, drif t, environmental effects, po st-accident, high-energy line etc.,
recent qualification tests in a break environment have indicated that the wide-range RCS pressure chan-nels exhibit inaccuracies.
These 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 leads to the possi-The inaccuracy of RCS wide-range pressure measurement bility that the pressurizer power-operated relief valves may be lifted prior to the termination of SI.
This could lead to a greater number of a small toe s-o f-valve ch allenge s, thus increasing the probability of coolant accident due to the valve f ailing open.
Likewise, the inaccuracy of this measurement 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 envirornnentally protected (temperature and radiation).
If protection cannnt be provided j
l to the transmitters, they should be located ou t-o f-cont Ainment.
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has chosen to locate two wide-range RCS pressure transmitters outside the These transmitters will connect to the Re act or containment structure.
installed in vessel Level Indication System instrument piping and will be conjunction with that system.
The two direct sens ing wide-range RCS pressure transmitters which remain inside the containment will be used for cold overpressure protection.
6.
ADDITIONAL REPORTS This is an updat e to the !inal report.
No additional repo rt s are anticipated.
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