L-87-348, Provides Results of Baseline Blackness Testing Program Performed in Aug 1987 on Spent Fuel Racks Installed in Spent Fuel Pool.No Gaps or Voids Noted in 54 Panels.Next Test Will Be Performed within 3 Yrs

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Provides Results of Baseline Blackness Testing Program Performed in Aug 1987 on Spent Fuel Racks Installed in Spent Fuel Pool.No Gaps or Voids Noted in 54 Panels.Next Test Will Be Performed within 3 Yrs
ML20237H497
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 08/20/1987
From: Woody C
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
L-87-348, NUDOCS 8708250043
Download: ML20237H497 (2)


Text

. P. O. Box 14000, Juno BEACH, FL 33408-0420 39%

AUGUSI 2 0 1987 L-87-348 U. S. Nuclear Regulatory Commission Attn: Document Control Desk l Washington, D.C. 20555 l Gentlemen:

! Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-25l l Surveillance Results from Unit 3 Spent Fuel Pool Your letter dated June 9,1987 requested information concerning the use of Boraflex neutron absorbing material in Turkey Point Units 3 and 4 spent fuel racks. Our . letters, L-87-279 (dated July 10,1987) and L-87-313 (dated July 27, 1987) responded to your letter. In those letters Florida Power & Light (FPL) committed to provide the staff with the results of our baseline blackness testing program. FPL added this testing to the existing surveillance program in response to industry experience coricerning Boraflex usage.

Blackness testing was performed during the first week of August 1987 on the installed spent fuel racks in Turkey Point Unit 3 Spent Fuel Pool. FPL tested eight Region I storage locations (containing a total of 32 full length Boroflex panels) and ten Region 11 storage locations (containing a total of 22 full length Boroflex panels). FPL selected these storage locations because they are representative of those storage locations which have received the highest accumulated dose for Region I and Region 11. Calculations indicate that the accumulated gamma dose would be 7.8 x 109 rods assuming on infinite array of storage cells each containing a spent fuel assembly with an average burnup of 36,000 MWD /MTU stored for one year. No indication of gaps, voids or other spatial distribution anomalies were observed in any of the 54 panels.

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1 l U. S. Nuclear Regulatory Commission i L-87-348

! Page two in addition to indicating the existing condition of the Boroflex panels, this testing will provide baseline data for comparison against the results of future surveillance tests. FPL expects to perform the next test within three years (in conjunction with the five year surveillance intervoi for the Boroflex sample coupons), or sooner, if industry experience indicates a ' shorter surveillance period is warranted. Calculations indicate that the accumulated gamma dose would be 1.2 x 10 10 rods assuming an infinite array of storage cells each containing a spent j fuel assembly with an average burnup of 36,000 MWD /MTU stored for one year.

Should there be further questions, please contact us.

Very truly yours, l

hdh C. O. Wood l Group Vic P sident l

! Nuclear Energy l

COW /RG/gp cc: Dr. J. Nelson Grace, Regional Administrator, Region 11, USNRC Senior Resident inspector, USNRC, Turkey Point Plant i

I l RGI/038/2

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