ML18040A818

Further Response to IE Bulletin 79-26 Requirements.Util Developed & Verified Analytical Method to Calculate Control Blade Depletion.Based on Analysis,Util Determined That No Control Blades Will Exceed 34% B-10 Depletion

ML18040A818
Person / Time
Site:	Susquehanna
Issue date:	11/21/1986
From:	Keiser H PENNSYLVANIA POWER & LIGHT CO.
To:	Adensam E Office of Nuclear Reactor Regulation
References
IEB-79-26, PLA-2747, NUDOCS 8612010439
Download: ML18040A818 (2)

Text

Pennsylvania Power 8 Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 215 l 770 5151 Harold W. Keiser Vice President-Nuclear Operations 21 5/770-7502 NOV 2 3 1g86 Director of Nuclear Reactor Regulation Attention: Ms. E. Adensam, Project Director BWR Project Directorate No. 3 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION LICENSE CONDITION 2.C.(9) OF FACILITY OPERATING LICENSE NO. NPF-22 PLA-2747 FILE R41-2/R41-1A Docket No. 50-388

Dear Ms. Adensam:

License Condition 2.C.(9) of Facility Operating License No. NPF-22 requires that PP&L comply with items 1, 2 and 3 of IE Bulletin 79-26, Revision 1, and submit a report on item 3 within 30 days of plant start-up following the unit's first refueling outage. PP&L responded to the bulletin in PLA-623 dated February 11, 1981. In response to these requirements, the following information is provided.

1. PP&L has developed and verified an analytical method to calculate control blade depletion. This analysis determines the exposure history which then determines boron-10 depletion averaged over the upper one-fourth of each control blade on a continuing basis. Based on this analysis, PP&L has determined that no control blades will exceed 34% boron-10 depletion averaged over the upper one-fourth of the blade before the end of the second cycle.

2. Individual control blades will be scheduled for replacement prior to exceeding 34% boron-10 depletion averaged over the upper one-fourth of the blade as predicted by the analysis described above.

3. Shutdown margin tests have been satisfactorily conducted pursuant to Technical Specifications Section 4.1.1. Since no control blades have approached the boron-10 depletion limits, special shutdown margin tests 8612010439 861121  ! I PDR ADOCK 05000388 i

.PDR

Page 2 SSES PLA-2747 NOV 21 1S86 File R41-2/R41-1A Ms. E. Adensam are not necessary and shutdown margin procedures need not be modified to account for reactivity loss due to boron-10 depletion.

This completes PPSL's actions for License Condition 2.C.(9).

9l~

H. W. Keiser Vice President-Nuclear Operations cc: M. C. Thadani USNRC L. R. Plisco USNRC