ML20084H129
| ML20084H129 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/17/1971 |
| From: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20084H127 | List: |
| References | |
| 12223, 1292, NUDOCS 8305020011 | |
| Download: ML20084H129 (2) | |
Text
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forsey Con traI Power & Ligh t Colnpany M A DISoN AVE N U C A T l.W4 CH Do nL Ro AD e MORRIS TOWN. N. J. 079EO e 5 39 611 i e
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.i Dr. Peter A. Morris, Director
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United States Atomic Energy Commincion h
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Dear Dr. fiorris:
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Sub,j ect :
Dyster Creek Station Docket No. 50-219 Main Steam Isolation Valve Testing The purpose of thin letter ic to advice you that the Main Stema Icolation Vnives at our Oycter Creek Station were again Lected for leakage on February 16-17, 1971 rind to report the resulta of thase tects.
An opportunity to test the valvec cceurred because of a ceheduled out. age to incpect the turbine control valves.
The final resulte of these tests indicated the fol]oving leak rates:
N303A -- Lens than 0.1 SCFil UC0hA = 3.6 SCFH NG03B -- Leus than 0.1 GCFH NS0hB = h.3 SCFH These results are within the allowable Technical Specification leak rate of 11.1 Standard Cubic Feet Per Hour (GCFH) at 20 poig.
I!S03A' and hSO3B are the north and couth valves, respcetively, that are located inside the dryvell.
US0hA and UC0hB are the north and routh valvec, respectively, that are located outside the dryvell.
On February 16, 1971, the reactor vencel vac preocurized to 20 puig in order to test the inner valven.
The resulte showed that air una leaking throu.;h N303B and that U303A had no detectable leakage.
Both of the inside valven were then cycled and retested and again U303A had no detectable leakage an_d the meanured leak rate of U303B vac
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approxirnteh 380JCfl!.
The reactor vencel was then vedted, the main steam linec vere flooded with water, and a 20 psig pressure decay test van conducted between the north valve pair in order to determine the Icakar.c through 1:30hA. Aa reported above, this leakage was observed to be 3.6 CCFli, ruring this test, no water leakage was detected past 3
either of the incide valves; and since the reactor vessel water level EAS///
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Dr. Peter A. Morris
~Pa'ge II March 17, 1971 was already raised for the valve testing, a 1000 psig hydrostatic test i
of the primary system was performed as the result of maintenance work done on the electrcmatic relief valves. Again, during this hydrostatic test, no water leakage was detected past the inside main steam isolation valves.
Following a successful hydrostatic test, a pressure decay test was performed between the south pair of isolation valves and the leakage through US0h2 was determined to be h.3 SCFH.
The steam lines above the inside isolation valves were then drained and NS03B was retested, and there was no detectable leakage through this valve with 20 psig air pressure in the reactor vessel.
The results of this testing indicate that the seating surfaces of NS03B, as well as the other valves, have remained in good condition, particularly the inside valves, since no water leakage was detected at 1000 psig water pressure and no air leakage was detected under standard test conditions.
It is evident that NS033 requires a larger seating force than the other valves and close attention vill be paid to the performance of this valve when it is tested again.
In the meantime, we are confident this valve vill perform its safety function since 850 to 1000 psig steam pressure is available to assist in seating the valve upon an isolation signal.
Very truly yours, l}
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'Ivan R. Finfroc 4 Jr.
Manager, Nuclear Generating Stations IRF/pk Mr. R. W. Kirkman, Regional Director cc:
Division of Compliance
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