ML17199F783

From kanterella
Jump to navigation Jump to search
Advises That No Addl Tech Specs Required for Containment Vent & Purge Valves,Per 860228 Request.Determination Based on Existing Surveillance Activities & SER Transmitted on 860228,affirming Valve Closure Under Accidental Pressure
ML17199F783
Person / Time
Site: Dresden, Quad Cities, 05000000
Issue date: 06/02/1986
From: Wojnarowski J
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
1735K, NUDOCS 8606100080
Download: ML17199F783 (2)


Text

Commonweal.dison One First National

a. Chicago, Illinois Address Reply to: Post Office Box 767 thicago. Illinois 60690 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Conunission Washington, DC 20555 June 2, 1986 Subject; *Dresden Station Units 2 and 3 Quad Cities Station Units 1 and 2 Containment Vent and Purge Valves

.NRC Docket Nos. 50-237/249 '& 50~254/265 Reference*:

Letters fr.om J. *A. Zwo1inski to D. L. Farrar dated February 28, 1986, transmitdng SER for Subject '(.a~ves at Dresden and Quad Cities.

Dear Mr. Denton:

The referenced letters documented NRC concurrence. that the subject vent.and purge valves* are able to close from. the fully open position against containment pressure 'during a LOCA.

The reference also requested we determine whether any additional Technical Specifications.regarding these valves were necessary.

COIDJll~nwealth Edison has reviewed your Safety Evaluation regardirig this issue and our existing Technical Specifications at Dresden and*Quad Cities *and 'determined that no add1tional specifications are required.

The containment vent and purge valves addressed in the reference are routinely leak rate tested in acc.ordance with Appendix J and our current Technical Specifications.

In addition; these valves are currently monitored under our Inservice Testing Program per the criteria in Section XI of the ASME Code.

In view of these*existing surveillance activities and the demonstrated ability to close under accident pressure, *no additional Technical Specification requir~ments are necessary.

If you have any additional questions regarding this matter, please contact this office.

( 8606100000 860602

,, I
  • 1:.. ~DR ADOCK 05000237 :j' I

PDR.

'\\

I

  • I

'J~*.,,

-~

Mr. H. Juene 2, 1986 One signed original and ten (10) copies of this letter are provided for your use.

.,/

lm cc:

R. Gilbert - NRR R. Bevan - NRR Very truly yours, J ~** R. Wojnarowski Nuclear' Licensing Administator NRC Resident Inspector - DIQC 1735K