ML17179B149

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Informs That Unless Util Notifies NRC within 10 Days of Ltr Receipt That NRC Incorrect Re Util Involving Validation of Design Basis of Containment Heat Removal Sys, NRC Would Consider Withdrawn
ML17179B149
Person / Time
Site: Dresden 
Issue date: 10/15/1993
From: Stang J
Office of Nuclear Reactor Regulation
To: Farrar D
COMMONWEALTH EDISON CO.
References
TAC-M86122, NUDOCS 9310220130
Download: ML17179B149 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket No. 50-237 Mr. D. L. Farrar Manager, Nuclear_ Regulatory Services Commonwealth Edison Company Executive Towers West III, Suite 500 1400 OPUS Place Downers Grove, Illinois 60515

Dear Mr. Farrar:

October 15, 1993

SUBJECT:

SYSTEMATIC EVALUATION PROGRAM, TOPIC VI-3, CONTAINMENT PRESSURE AND -

HEAT REMOVAL CAPABILITY (TAC ~O. M86122)

_ On March 18, 199i, you sent a letter to the NRC concerning the validation of the design basis -of the containment heat removal system.

In summary, the letter and its enclosure stated that Commonwealth Edison Company (CECo) has reanalyzed the Systematic Evaluation Program (SEP)*topic concerning the containment heat removal system.

The reason for the reanalysis came about bec~use of the reduced containment cooling service water (CCSW) flow and

_reduced duty of the containment cooling heat exchanger discovered by CECo in early 1992~ Page 2 of the enclosure.to the letter indicated the reanalysis effort was to reconstitute the design basis of the CCSW system based on the above reductions to the CCSW system. _

By letter dated July 12, 1993, the NRC stated that such changes to the design basis of the plant could not be made under 10 CFR 50.5.9, but rather would require an amendment to the_ license in accordance with 10 CFR 50.90 with NRC r~view and approval~

By 1 etter dated September 3, 1993,

  • in response to a Not ice of Vi o 1 at ion concerning the CCSW system, CECo stated it would submit an amendment to the license for Dresden, Units 2 and 3, to change the design basis of the CCSW

~ystem. In conversations between Mr. Piet (CECo) *and Mr. Stang (NRC), it was conveyed that the SEP topic concerning containment heat removal capability would also be* addressed in the amendment r~quest. -

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Mr. D. October )5, 1993 OFC Unless you. notify us that we are incorrect within 10.days of receipt of the this letter, we consider your March 18, 1993, letter withdrawn and TAC No.

M86122 to be complete.

If you have *an.Y. further questions, please cont.act me at '(301) 504-1345.

cc:

  • See next page DISTRIBUTION:.

Docket* Fi 1 Ef NRC & Loca 1. PDRs

PD II I -2 r If

.J. Roe J. Zwolinski.

J. Dyer

. C. Moore J. Stang OGC ACRS ( 10)

B. Clayton Rill **

Sincerely, Original signed by:*

John F. Stang, Project Manager Project Directorate 111-2 Division of Reactor Projects - 111/IV/V

.Office of Nucle~r Reactor Regulation

'PM:PDIII-2 D:PDIII-2 NAME JOVER~

DJ,\\TE 93 93

'.i 93 YES NO COPY YES NO YES NO

Mr. D. L. Farrar

.Commonwea 1th Edi son Company cc:.

Michael I. Miller, Esquire

  • Sidley and Austin One First National Plaza Chicago, Illinois 60690 Mr. G. Spedl Plant Manager Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450-9765 U. S. Nuclear Regulatory Commission
  • Resident Inspectors Office Dresden Station 6500 North Dresden Road -

Morris, Illinois 60450-9766 Chairman Board of Supervisors of Grundy County Grundy County Courthouse Morris, Illinois 60450 Regional Administrator Nuclear Regulatory Commis.sion, Region III 799 Roosevelt Road, Bldg. #4 Glen Ellyn, Illinois 60137 Illinois Department of Nuclear Safety Office*of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Robert Neumann Office of Public Counsel State of Illinois Center 100 W. Randolph Suite 11-300 Chicago, Illinois 60601 Dresden Nuclear Power Station Unit Nos. 2 and 3