L-76-196, Letter Submitting Additional Reload Information to Supplement Letters Submitted on 4/21, 5/10, & 5/13/1976 for Turkey Point Unit 4

Letter Submitting Additional Reload Information to Supplement Letters Submitted on 4/21, 5/10, & 5/13/1976 for Turkey Point Unit 4

ML18227D129
Person / Time
Site:	Turkey Point
Issue date:	05/19/1976
From:	Robert E. Uhrig Florida Power & Light Co
To:	Lear G Office of Nuclear Reactor Regulation
References
L-76-196
Download: ML18227D129 (15)

Text

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TO: Mr Lear FIIOM: Florida Pwg '& Light Co DATE OF DOCUMENT Miami, FXa 5-19-76 R E Uhrig OATE AECEIVEO ff I QtLETTEA I INOTOAIZEO P flOP INPUT FOAM NUMOE fl OF COP I ES A E CE I V E 0

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! QCOPY one signed DES C A IP TI ON ENCLOSUAE Ltr re thhir 4-21-76 & 5-10-76 & 5.-13-76 Addi Reload Information..."....

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A.CKNOWLEDGRD PLANT NAtIE k '4 DO NOT REMOVE SA1,'ETY FOR ACTION/INFORMATION ENVXRO 5-25-76 ehf ASSIGNED AD: ASSXGNED AD:

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03I L-76-196 issue u '~as May 19, 1976 Director of Nuclear Reactor Regulation Attn: Mr. George Lear, Chief Operating Reactors Branch 53 Division of Operating Reactors I33 ~II'QQ U. S. Nuclear Regulatory Commission io Washington, D. C. 20555

Dear Mr. Lear:

Re: Turkey Point Unit. 4 Docket No. 50-251 Additional Reload Information Florida Power 6 Light Company is submitting the following information to supplement our letters of April 21, May 10, and May 13, 1976:

1. Method of Analysis:

The general methods and procedures used for the analysis were those given in the Turkey Point FSAR, Section 14.3.2.

The hot rod thermal transient was re-analyzed using the March 15, 1975 version of LOCTA-IV computer code.

Only the 0.4 DECL break was analyzed. This is the worst case for Turkey Point 4 as shown in NRC submittal L 380, July 29, 1975 R. E. Uhrig to A. Giambusso, and in the original ECCS Analysis of March 10, 1975. Table,"

1 and Figures 1-5 presents the results of the analysis.

Region 4 is limiting for the following reasons:

~Re ion 4 Region 4 fuel wae on the periphery of the core during Cycle 2. Some of the fuel rods have very low burnup. Thus, these rods behave essentially as fresh fuel. Region 4 fuel results in a peak clad tem-perature (PCT) of 2156'IF utilizing as-built fuel rod parameters .~, ':==,

The Region 4 PCT will fall below 2150'F by 3000 MWD/MTU core average burnup into Cycle 3.

HELPING BUILD FLOFIIDA

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To: Mr. George Lear May 19, 1976 Re: Turkey Point Unit 4 Page Additional Reload Xnformation Receion 3 All Region 3 fuel received high burnup during Cycle 2. The Westinghouse time dependent fuel densifi-cation, model was used to calculate that fuel temperatures were reduced sufficiently to result in a PCT of less than 2150'F about 6500 MWD/MTU into Cycle 2. (The PCT in Cycle 3 is also less than 2150'F). This fuel is now less limiting than Region 4 because of the greater fuel burnup and the 35 psi lower initial cold prepressurization level.

Both of these factors result in greater clad creepdown for Region 3 which means the stored energy in the Region 3 fuel is lower.

Receion 5 Region. 5 design parameters are the same as Region 4 except for 65 psi lower initial prepressurization level. Thermal analysis of the fuel using as-built Regions 4 and 5 fuel rod parameters resulted in lower fuel temper-atures for Region 5 fuel mainly due to the lower initial prepressurization level. Region 5 fuel would result in a PCT of less than 2150'F.

Yours very truly, obert E. Uhrig Vice President REU/GDW/hlc cc: Jack .R. Newman, Esq.

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TABLE 1 LARGE BREAK 0.4 DECL RESULTS Peak Clad Temp. 'F 2156.

Peak Clad Location Ft. 6.0 Local Zr/H20 Rxn (max)'A 9.27 Local Zr/H20 Location Ft. 5.75 Total ZR/H20 Rxnl < 0.3 Hot Rod Burst Time sec 25. 8 Hot Rod Burst Location Ft. 5. 75 CALCULATION NSSS Power Mwt 102% of 2297 Peak Linear Power kw/ft 1025 of 13.73 Peaking factor (At 2297 NWt) 2.32 Accumulator Water Volume 825 Fuel region + cycle analyzed Cycle Region Unit 4 FLA 3 4 (Limiting Region)

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