ML20083K103
| ML20083K103 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/10/1984 |
| From: | Woolever E DUQUESNE LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| 2NRC-4-038, 2NRC-4-38, NUDOCS 8404160066 | |
| Download: ML20083K103 (4) | |
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2NRC-4-038 (412)787 - 5141 Telecopy 2) 8 629 Nuclear Construction DMsion April 10, 1984 Robinson Plaza. Buildmg 2, Suite 210 Pittsburgh, PA 15205 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Mr. George W. Knighton, Chief Licensing Branch 3 Office of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit 2 Docket No. 50-412 Open Item / Question Response Geatlemen:
This letter forwards responses to the issues listed below.
Duque sne Light Company plans to incorporate the res ponses to the FSAR ques tion into FSAR Amendment 6.
The following items are attached:
At tachment 1:
Response to Question 430.119 (Power " Systems Branch) fo rwarded by your letter dated September 19, 1984.
At tachment 2:
Response to Open Item 57 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report.
DUQUESNE LIGHT COMPANY By 7-E. (/. Woolever Vice President KAT/wjs cc: -Mr. H. R. Denton, Director NRR Mr. D. Eisenhut, Director Division of Licensing Mr. G. Walton, NRC Resident Inspector Mr. M. Lacitra, Project Manager 8404160066 840410 PDR ADOCK 05000412 E
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SUBSCRIBED AND S ORN TO BEFORE ME THIS g DAY OF fil_;
, 1984.
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Not ary Public ANITA ELAINE REITER, NOTARY PUBLIC ROBINSON TOWNSHIP, ALLEGHEflY COUNTY dg MY COMMISSION EXPIRES OCTOBER 20,1936
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United States Nuclear Rtgulatory Commission Mr. Gsorge W. Knighton, Chief
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COMMONWEALTH OF PENNSYLVANIA )
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COUNTY OF ALLEGHENY
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, be fo re me,
On this
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day of I
i a Notary Public in ard for said Commonwealth and County, pe rso n ally l
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 execute and file the foregoing Submittal on behalf of said Company, ard (3) the L
s tatement s. set fo rth in the Submittal are true and correct to the best of his knowledge.
t ad lY Notary Public
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ANITA ELAINE REITER,' NOTARY PUBLIC ROBINSON TOWNSHIP, ALLEGHENY COUNTY MY COMMISSION EXP!RES OCTOBER 20,1986 s
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ATTACHMENT 1 Question 430.119 (SRP 9.5.7)
In Sect ions 9.5.7.2 and 9.5.7.5 of the FSAR you di sc u s s the level alarm s as so ci ated with the lube oil system.
You state that "the rocker arm tube oil reservoir level is monito red for high level and the level is maintained by a lever control valve."
No ment ion is made of a reservoir low level alarm.
A failure of the level control valve to maint ain lube oil level in the rocker arm reservoir could result in inadequat e or no lubricat ing oil fo r the rocker arm s, le ad ing to diesel generator unavailability and/or failure.
This is an unac cep t-able condition. Prov ide a low level alarm for the rocker arm lube oil reservoir (SRP 9.5.7, Part III).
Response
A rocker arm tube oil low pres sure al a rm is provided to ale rt the operator of condit ions such as low rocker arm lube oil reservoir level.
The level control valve is a float valve wh ich tend s to be pushed open by inlet oil pr es sur e.
The valve ope ning is further assured by the length of the float rod and weight of the float which provide suf ficient mechanical advant age to fo rce the valve open reliably.
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. f-t ATTACHMENT 2 OPEN ITEM 57 7.3.3.2 Test of Engineered Safeguards P-4 Interlock on Novembe r 7,
1979, Wes tinghouse not ified the Commis sion of an undetect ab le failure that could exist in the engieered safeguards P-4 interlocks.
Test procedures were developed to detect failures that might occur.
The procedures require the use of voltage measurements at the terminal blocks of the reactor trip breaker cabinets.
The staf f raised a concern on the possibility of accidental sho rt ing or grounding of safety sys tem circuits during tes ting of the P-4 interlocks. The applicant is studying this issue. This item is open, subject to staff review of the applicant's pending response.
Response
Beaver Valley Unit 2 plans to tes t the P-4 interlock by using the testing procedure recommended by Westinghouse.
This pr oced ure has been satis factorily used at Beaver Valley Unit 1 for approximately four years.
The experience gained on BVPS-1 has indicated that accidental shorting
- or ' grounding of safety system circuits is not a problem.
The refo re,
the proposed modification to the breakers does not provide substantial
' additional protect ion ditch is required for the public health and safety.
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