ML17252A262

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Letter Regarding Dresden Station Feedwater Check Valve Local Leak-Rate Testing - Dresden Unit 3
ML17252A262
Person / Time
Site: Dresden Constellation icon.png
Issue date: 12/14/1976
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS Ltr. #76-871
Download: ML17252A262 (3)


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CommonweaAEdison

  • Dresden Nuclear ~;

Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. #76-871 December 14, 1976 Mr. James G~ Keppler, Regional Director Directorate of Regulatory Operations - Region I I I U. S. Nuclear Regulatory Commission 799 Roosevelt Road G 1 en E 11 yn, I 11 i no is 6013 7

SUBJECT:

Dresden Station Feedwater Check Valve Local Leak-Rate T~sting

REFERENCE:

Letter to J. G. Keppler from B. B. Stephenson dated N.ovember 4, 1976 (Reportable Occurrence report no. 50-249/1976-25)

Because feedwater check valve local leak-rate tests (LLRT's) have repeatedly yielded excessive 11as found" leakage results, a new test method has been develop~d which approximates as closely as possible the primary con-tainment conditions during a Joss-of-coolant accident. (LOCA).

The new test method involves pressurizing the vol~me ~pstream of the feedwater check valve with water to approximately 50 psig, the~ draining the system and performing a LLRT utilizing isolatton valve test procedures.

Current isolation valve test procedures specify a pneumatic pre,ssure decay test as required by the Technical Specifications.

The station ~~ocedur~~*will be revised to reflect the new method of testing the feedwatet check valves *in the 11as found" condition.

Development of this new test method was based on typical pqstulated conditions following a LOCA.

The condition.s selected were the design basis LOCA followed by a loss of**off*site power, two* failures which would result

  • in the lowest differential pressure available to seat the feedw.at.er check

.valves.

For these conditions, reactor and containment press.ure would. be a~p~oximately 50 psig wh~n the feedwater system pressure dropped to zero as the result of the loss of off-site power.

Postulated LOCA's with less than design basis-size breaks would result in longer blowdown rates and potentially higher ~ifferential pressure ~vailable to seat the check valves following the subsequent Joss of off-site power.

Since there would still be water on the valves due to their position in the low point of the 1 ine, the new met~odof seating the valves with water is ~epresentative 6f acciden~ conditions.

JO C.F.R. part 50, appendix J, section I I l.C. 1 specifies that each valve to be tested shall be closed by.normal operation and without any preliminary exercising or adj~stments. Feedwater check valve seating with water is con-side*red a normal operation since the valve is normally seated with water and a differential pressure.

Based.on the r~sults of testing performed during the Dresden Unit-3 1976 refuel in~ outage, it is anticipated that the utilization of the new

  • test method will significantly reduce the incidence of excessive "as found" leakage test results on the feedwater check valves.

(The method used to test the Unit-3 feedwa~er check valves is described in the ref¢r~nced re-portable occur~enc~ iepo~t.)

As stated previously, the Dresden Station LLRT procedure for the feedwater check valves will be revised to include thii new testing method.

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Dirett6r of inspection & Enforc~m~nt Dfrector'of Management Information & Program Contiol Fi le/NRC