ML17179A709

Informs That Util Intends to Implement Similar Sequencing Strategy Mods at Lasalle,Units 1 & 2,in Ref to Util Transmitting Proposed Revised CR Sequencing Methods for Quad-Cities & Dresden Stations

ML17179A709
Person / Time
Site:	Dresden, Quad Cities, LaSalle
Issue date:	01/27/1993
From:	Piet P OMAHA PUBLIC POWER DISTRICT
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9302030219
Download: ML17179A709 (2)

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C~mmonv.9h Edison 1400 Opus Place Downers Grove, Illinois 60515 January 27, 1993

• Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn:

Document Control Desk

Subject:

Dresden Nuclear Power Station Units 2 and 3 Quad Cities Nuclear Power Station Units 1 and 2 LaSalle County Nuclear Power Station Units 1 and 2.

Revised Control Rod Sequencing Methods NRC Docket Nos. 50-2371249. 50-254/265 and 50-373/37 4

Reference:

(a)

Letter, J.A. Silady to T.E. Murley, "Revised Control Rod Sequencing Methods," July 18;, 1990._*

Dr. Murley:

. (b)

Letter, B.L. Siegel to T.J. Kovach, "Revised Control Rod SequencinQ Methods for the Dresden and Quad Cities Nuclear Power Stations," September 21, 1990.

(c)

Commonwealth Edison Topical Report NFSR-0085, "Benchmark of BWR Nuclear Design Methods';" (as approved by NRC letter from B.L. Siegel to T.J.. Kovach dated February 27, 1992 and as

. ~upplemented).

• The Reference (a) letter transmitted proposed revisions to the control rod *sequencing strategies for Quad Cities and Dresden stations. Refe. ranee (a) detailed the proposed sequence strategy modifications. It was not applied to LaSalle at that time due to the constraints of the Rod Sequence Control System (RSCS). The Reference (b) letter determined that the prop_osed revisions to control rod sequencing strategies were.

acceptable.

In the time frame since Reference (b), Commonwealth Edison (CECo) has received approval to perform the Control Rod Drop Accident (CADA) analysis in-house (Reference

• (c)), and for Technical Specification changes to remove the RSCS blocks at LaSalle have been approved (Amendments #88 and #73 for LaSalle Units 1 and 2, respectively).

Therefore, CECo intends to implement similar sequencing strategy modifications at LaSalle and to expand the application to some control rod groups beyond 50% rod density at all three stations. Any control rod sequencing strategies/techniques to be used at CECo's BWR reactors will be evaluated using the Reference (c) approved methodology to verify that the CADA licensing basis of 280 cal/gm is met for each cycle. These analyses will then be evaluated per 1 OCFR50.59 as part of the reload licensing review for each cycle.

Since no T~chnical Specification or UFS~R changes are required CECo will implement ~hy revisio~s to thf)~~~~.P~r:itrol rod se9uencing strategies

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January ~7. 1993

• following completion of the On-Site Review ofthe 1 OCFRS0.59 safety evaluation incorporating these changes.

. cc:

If yo~ have any questions, please conta9t this.office.

Very truly yours,.

~w~

Peter L. Piet

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• Nuclear Licen*sing Administra~or A.B. Davis, ReQional Administrator'." Riii.*

_ J.F. Stang, ProJ8Ct Manager - NRR C.P. Patel, P_roJect Manager - NRA J.R. Stransky, Project Manager - NRA M.N. Leach, Senior Resident Inspector - Dresden T.* Taylor, Senior Resident Inspector - Quad Cities D.L. Hills, Senior ~esident Inspector - LaSalle

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