ML20214V988

Supplemental Application for Amend to License NPF-37, Requesting Increase in Storage Capacity of Spent Fuel Racks Rev to 860903 Application Required Due to Change in Mfg Process of High Density Racks

ML20214V988
Person / Time
Site:	Byron
Issue date:	11/24/1986
From:	Ainger K COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20214V991	List: ML20214V988 ML20214V997
References
2420K, NUDOCS 8612100037
Download: ML20214V988 (2)

Text

E

[ z,n_-

> on. Fws Neonel Plaza. CNceOD. Encis AcMress Hoply to: Post Omco Box 767 CNcago,lilinois60000 0767 November 24, 1986 Mr. Harold R. Denton, Director

$b 45+

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC. 20555

Subject:

Byron Station Units 1 and 2 Application for Amendment to Facility Operating License NPF-37, Appendix A, Technical Specifications References (a): September 3, 1986 letter from K.A. Ainger to H.R. Denton (b): November 7, 1986 letter from K.A. Ainger to H.R. Denton

Dear Mr. Denton:

Reference (a) requested a license amendment to increase the storage capacity of the spent fuel racks at Byron Station and reference (b) transmitted a detailed determination of no significant hazards considerations for the proposed amendment.

This letter contains revisions to the technical specification changes requested in reference (a). The revisions are primarily due to a change in

-the manufacturing process of the high density racks. In addition, the revised amendment includes a new Figure 5.6-1 which provides criteria for fuel storage in Region 2 of the high density spent fuel racks. Attachment A of this letter contains the revisions to the proposed amendment.

, This revised amendment has been reviewed and approved by both On-site l and Off-site review in accordance with Commonwealth Edison Company procedures. The determination of no significant hazards considerations transmitted in reference (b) is not affected by this revised amendment.

A surveillance will be conducted to verify the proper location of each fuel assembly in the high density spent fuel racks after each unit's refueling and at intervals of approximately six months thereafter. However, when a unit is scheduled for a refueling which is expected to be completed within nine months of the previous pool inventory, the six month interval may be extended to coincide with the inventory required after the refueling. This requirement is presently included in Byron Station procedure BAP 2000-4.

Chapter 9 of the Byron /Braidwood FSAR will be updated to reflect the design of the high density spent fuel racks after approval of the proposed license amendment. This update will include the surveillance commitment outlined above.

O lli

(_.

Please direct any questions regarding this matter to this office.

One signed original and fifteen (15) copies of this letter and attachment are provided for NRC review.

Very truly yours, K. A. Ainger Nuclear Licensing Administrator

/klj att.

cc: Byron Resident Inspector 2420K a

1 1

- , - , , . , - , _ _ _ . . _ _ _ _ _ , . , - . . . _ , . - - -- _ - _ _