ML20207R878

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Advises of Revs to TR Tramm Re Handling of Heavy Loads Resulting from Updates to Previous Commitments & Need to Install High Density Spent Fuel Racks.Tech Spec Change Request Withdrawn
ML20207R878
Person / Time
Site: Byron, Braidwood, 05000000
Issue date: 03/11/1987
From: Ainger K
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
2825K, NUDOCS 8703180245
Download: ML20207R878 (2)


Text

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/ Address Reply t; Post Office Box 767 Chicago, Illinois 60690 - 0767 March 11, 1987 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Control of Heavy Loads NRC Docket Nos. 50-454/455 and 50-456/457 References (a): April 7, 1982 letter from T. R. Tramm to H. R. Denton (b): October 15, 1986 letter from K. A. Ainger to H. R. Denton

Dear Mr. Denton:

This is to advise you of some revisions to information contained in reference (a) regarding the handling of heavy loads at Byron and Braidwood Stations. The revisions have resulted from updates to previous commitments in reference (a) and the need to install high density spent fuel racks.

In response 3.f of reference (a), it is stated that the spent fuel pool bridge crane has two 2-ton hoists which are interlocked to prevent simultaneous motion. This statement was based on a design change proposed in 1981 to add an additional hoist to the spent fuel pool bridge crane. After the bridge crane was installed at Byron, it was found that the existing single hoist was adequate and the design change to add a second hoist was cancelled.

Consequently, only one hoist is installed on the spent fuel pool bridge crane.

In response 3.3 of reference (a) regarding the containment polar crane, it states "the main hook makes a maximum of two head lifts per outage".

Unforeseen circumstances, such as a control rod drive shaft hanging up or reactor head 0-rings becoming damaged, may necessitate an additional lift of the reactor head occasionally during outages. While we do not expect this to occur frequently, we wish to clarify our previous statement to read "the main hook normally makes two head lifts per outage".

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H. R. Denton March 11, 1987 The response to request 4b in reference (a) discusses additional mechanical stops to be installed on the fuel handling building crane when carrying a heavy load within 25 feet of the spent fuel pit. This commitment is being revised so that these additional mechanical stops are required to be installed during the handling of a spent fuel cask in the area of the spent fuel pool. The requirement for the additional mechanical stops during handling of spent fuel casks is in accordance with assumptions in FSAR Chapter 15 accident analysis for a spent fuel cask drop. Any other heavy loads will be carried in the spent fuel pool area in accordance with NUREG-0612 or by using the additional mechanical stops mentioned above.

Reference (b) transmitted a request for a license amendment to temporarily remove mechanical stops required by technical specifications during the installation of high density spent fuel racks. This is to inform you that the license amendment requested by reference (b) is no longer necessary and is hereby withdrawn.

Installation of the high density spent fuel racks will be performed in accordance with the provisions of alternative 3 of Section 5.1.2 of NUREG-0612.

please direct any questions you may have regarding this matter to this office.

Very truly yours, K. A. Ainger Nuclear Licensing Administrator im cc: Regional Administrator - RIII Byron Resident Inspector Braidwood Resident Inspector 2825K