ML19345B693
| ML19345B693 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/25/1980 |
| From: | Dunn C DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| TAC-12922, NUDOCS 8012020355 | |
| Download: ML19345B693 (5) | |
Text
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November 25, 1980 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 LWR Primary Coolant System Pressure Isolation Valves Gentlemen:
Attached for your information are results of testing performed at Beaver Valley Power Station on check valves that are installed in the Event V configuration as described in your February 23, 1980 letter and our response dated March 17, 1980.
The valves were tested initially on November 11 - 14, 1980 and were retested on November 18, 1980 following a plant trip and inadvertent safety injection.
In accordance with your February 23, 1980 letter, we are providing three (3) originals and thirty-seven (37) copies of our response.
If you have any questions, please contact my office.
Very truly yours, 02 / LSw-C. N. Dunn Vice President, Operations Attachment cc:
Mr. D. A. Beckman U.S. Nuclear Regulatory Commission Beaver Valley Power Station S33y trg '.. '
Shippingport, PA 15077 7, _,i
.~U,S.
Nuclear Regulatory Commission 0;!,i;g c/o Document Management Branch
{p g Washington, DC 20555 NO C86)
MIN $,@&a@w::,,
8012020 M p
(CORPORATE SEAL)
Attest:
(Mik
/
h Thomas We'lfer,[Jic.
Secretary COMMONWEALTH OF PENNSYLVANIA)
) SS:
COUNTY OF ALLEG1ENY Or. this S6 day of Me d
, 1980, before me, HENRY G. ST0ECKER a Notarp Public in and for said Commonwealth and County, personally appeared C. N. Dunn, 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, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge, information and belief.
N%M RY G. STOECr.ER, Nc4ary Public Pcbu gh A;:egheny County. Pa.
i3v Cceassion hpires february 20,1982 l
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Safety Injection System Cold Leg Check Valve Leakage Test Report Testing of the Safety Injection (SI) System cold leg check valves 31-10, 11, 12, 23, 24 and 25, (refer to attached Figure 1 for valve numbers) was performed to satisfy concerns related to possible leakage of primary coolant system in-line check valves and the postulated failure of the associated checi valve (EVENT V).
Initial testing of the valves was performed on November 10, 11 2nd 14, 1980. No leakage was observed on check valves SI-10, 11 and 12.
Leakage of 0.1 gpm for check valve SI-23, 0.5 gpm for check valve SI-24, and 0.92 gpm for check valve SI-25 was observed.
Testing was also performed on November 18, 1980 after a plant trip and inadvertant safety injection had occurred the previous day. No leakage was observed for any check valve during this second test.
Testing of the check valves was accomplished using the following method.
Three test rigs consisting of a blank flange with a 1/16" hole drilled through the center to which was affixed tubing, valves and a pressure gage as shown in Figure 2, were attached to the system at a low point drain located between each of the three check valve pairs.
Check valves SI-10, 11 and 12 were tested concurrently.
Initial pressure, as indicated at Pressure Indicator PI-SI-900 (Figure 1), was recorded.
Valve T (Figure 2) was opened and pressure upstream of check valves 3
SI-10, Il and 12, as indicated on the test gage (Figure 2), was increased to a minimum of 2000 psig.
Pressure at PI-SI-900 was monitored and the time to reach either 200 psig or a stabilized lesser pressure was deter-mincd.
For both the initial test and the test performed on November 18, 1980, there was t increase in pressure observed at PI-SI-900, and, therefore, it can be concluded that no leakage occurs across the check valve seats of valves SI-10, 11 and 12.
If there had been a pressure increase, the leak rate would be calculated by opening valve SI-46 (Figure
- 1) and determining the time required to drain and collect the amount of water necessary to reduce the pressure to the initial pressure.
Check valves SI-23, 24 and 25 were then individually tested.
The initial pressure as indicated on the test gage was recorded.
The pressure downstream of SI-23 was then reduced to approximately 500 psig by opening valve T (Figure 2).
Valve T was closed and a stop watch started simul-7 2
teneousIy.
The test gage was observed for increasing and/or stabilizing pressure.
Leak rate was determined, if necessary, by opening valve T 2
and collecting water for one minute.
The above method was rereated for check valves SI-24 and 25 using the test rig which had been installed on a drain line on their respective lines.
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FIGURE 1 - LOW HEAD SAFETY INJECTION PUMPS To REACTOR COOLANT SYSTEM COLD LEGS T
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