ML20043A058

Forwards Cycle 5 Redesign Peaking Factor Limit Rept for Facility.Unit Redesigned During Refueling Outage Due to Removal & Replacement of Several Fuel Assemblies Found to Contain Leaking Fuel Rods

ML20043A058
Person / Time
Site:	Sequoyah
Issue date:	05/11/1990
From:	Wallace E TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9005170276
Download: ML20043A058 (10)

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TENNESSEE VALLEY' AUTHORITY SN 157B Lookout Place May 11, 1990 U.S. Nuclear Regulatory Commission.

ATTN: Document Control Desk, Washington, D.C. 20555 -)

Centlement In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - UNIT 1 CYCLE 5 REDESIGN PEAKING FACTOR LIMIT REPORT Enclosed is a copy of.the subject peaking factor limit report.. This report is

'being;provided in accordance with SQN Technical Specification (TS) 6.9.1.14

" Radial-Peaking Factor Limit Report." The appropriate elevation dependent j W(z) values, when applied to a power distribution-measured under equilibrium  !

conditions,-demonstrate that the-initial conditions assumed in the loss of-coolant accident analysis are met along with the emergency core cooling system

~

acceptance criteria of 10 CFR 50.46.. TVA's Nuclear Fuel organization'has ,

reviewed the enclosed report and found-it acceptable-for use.- j The Unit 1 Cycle 5 core was redesigned during the refueling outage because of i

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the removal and replacement of several. fuel assemblies that were found to contain leaking fuel rods. The need to, redesign the core' reload during'the refueling outage has precluded submittal of the subject report:60 days prior.

to initial criticality (presently-scheduled =for:May.17, 1990) as required by TS 6.9.1.14. :TVA, therefore, requests an. exemption from this requirement.

l Please direct questions concerning this issue to-Bruce S. Schofield at l (615) 843-6172. i 1

Very truly yours, TENNESSEE VALLEY AUTHORITY

. 1 E. r:. allace,- nager j Nuclear Licensing and' Regulatory Affairs Enclosure cc: See page 2

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An Equal Opportunity Employer - J; 001

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- U.S. Nuclear. Regulatory. Commission l cc Ms. S. C. Black,' Assistant Director (Enclosure) for Projects. .

TVA Projects Division i U.S. Nuclear Regulatory Commission '

One White Flint, North 11555 Rockville-Pike Rockville, Maryland 20852 ,

NRC Resident Inspector (Enclosure)

• Sequoyah Nuclear Plant 2600 Igou Ferry Road -

4 Soddy Daisy. Tennessee 37379 -

Mr. .B. A. Wilson, Assistant Director -(Enclosure) I for Inspection-Programs.

TVA Projects Division

'U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 I

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ENCLOSURE- ,

. SEQUOYAH UNIT 1, CYCLE 5 REDESIGN PEAKING FACTOR LIMIT REPORT (L38 900503 803) o i

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Westinghouse Commercial Nuclear Ba 3912 1 7 " Electric Corporation Fuel Division Pittsburgh Psansyty:nia 15230 3912 ~!

gg ry; ,, 4 May 2, 1990

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9CTIV*-G-0049 ifr.'T.A. Keys, Manager i

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4 Fuel Fabrication and Utilization S Tennessee Valley Authority i

1. hjb 1101 Market Street ,

BR 6N 60A i 01attanooga, Tennessee 37401 l

Dear Mr. Keys:

TENNESSEE VALLEY AUDIORITY SEQUOYAH AND WATIS BAR NUCLEAR ICWER PIANTS  !

S_EOUOYAH UNIT 1, CYCLE 5 REDESIGN PEAKING FACIOR LIMIT xt;R>Fd 4 Se Sequoyah Unit 1, Cycle 5 Redesign Peaking Factor Limit Report provides .;

information which permits the exact determination of W(z) versus core height as a function of cycle burnup. 21s report transmits the elevation  :

dependent W(z) values. Rese are to be used as inputs to define the I

' appropriate fitting coefficients for W(z) interpolations as a function of cycle burnup and axial elevation. We W(z) values are appropriate for the Cycle 5 burnup range of 0 to 17000 MO/MIU.

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The W(z) functions for Cycle 5 bur 71ups of 150, 4000,10000,14000 MWD /MIU  :

s, are provided in Figures 1-4 of this letter. Using three point

- interpolation, these W(z) functions can be used to determine W(z) values W .for cycle burnups between 0 and 17000 MO/MIU. For three point interpolation, the W(z) values from the three burnup steps 1 sest to the. l measured burnup should be used. A plot of the limiting FoXPrel T .

points and corresponding envelope is also included for information ,

purposes. 'l Should you have any questions regarding these data,,please do not hesitate to call or write. .

• l very truly yours,-

N. R. Metcalf

, Project Engineer OfFD Projects t NRM:mld 4 cc: I. R. Williamson RECEIVED ,

. Naclar Fuei

.MAY 's 1990

- Nuclear Fael Supply .

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.m .-  : 7l.. 0 ,',P,EAKINC FACTOR LIMIT REPORT FOR SEQUOYAH UNIT 1 CYCLE 5 REDESICN

,, RAOC OPERATION

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slpf e + - This Peaking Factor Limit Report is provided in accordance with j f' Para 6raph 6.9.1.14 of the Sequoyah Unit 1 Technical Specifications.

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'The Sequoyah Unit 1, Cycle 5 elevation dependent W(z) values for RAOC operation at beginning, early middle, late middle, and near end of-life are shown in Figures 1 through ?. respectively. This information is ,

4 sufficient to determine W(z) versus core height for Cycle 5 burnups in lu the range of 0 MVD/MTU to 17000 MWD /MTU'through the use of three point interpolation. W(z) was calculated using the method described in Part'B g; of Reference 1. u The appropriate W(z) function is used to confirm that the heat flux hot channel factor, Fq (z), will be limited to the Technical Specification i values of:

M Fq(z) $ P [K(z)] for P > 0.50 and

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Fq(z) $ 4.64 [K(z)) for P $ 0.50 i

e The appropriate elevation dependent W(z) values, when applied to a power distribution measured under equilibrium conditions, demonstrate that the initial conditions assumed in the LOCA are met, along with the-ECCS acceptance criteria of 10CFR50.46.

(1) WCAP 10217 A, Relaxation of Constant Axial. Offset Control -

Fq Surveillance Technical' Specification -,

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. ' ' '"ste 1.i go77ag CORE HEIGHT (FEE 1) 7ap I.'"s 9.4000 l'l'8 1.1357 9.6000 1.1419 8.8000 1.1425 10.000 1.1428 10.200 1.1477 10.400 1.0000 10.800 1.0000 t

10.800 1.0000 i

FIGURE 1 11'0C0 1'N l 11.200 1.0000

'" U SEQUOYAH UNIT 1 CYCLE 5 l$$- , goon 11.800 1.0000 RAOC

SUMMARY

OF MAX W(2) AT 150 MWD /MTU 12.000 1.0000 TOP AND BOTTOM 15% EXCLUDED AS PER TECH SPEC 4.2.2.2.0

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.. SEQUOYAH UNIT 1 CYCLE 5 11.Soo 1.0000 11.800 1.0000 RAOC

SUMMARY

OF MAX W(2) AT 4000 MWD /MTU 12.000 1.0000 TOP AND BOTTOM 15% EXCLUDED AS PER TECH SPEC 4.2.2.2.G

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10.800 1.0000 l 11.000 1.0000 I FIGURE 3 11,200 1,0000 5

' 11.400 1.0000 SEQUOYAH UNIT 1 CYCLE S 11.soo 1 0000 l-11.s00 1.0000  ;

RAOC

SUMMARY

OF MAX W(Z) AT 10000 MWD /MTU 12.000 1.0000 TOP AND BOTTOM 15% EXCLUDED AS PER TECH SPEC 4.2.2.2.G 1

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8.600 1.2102 0 2 4 6 8 10 8.s00 12 e,o00 1.1,sS5 1, ,,

BOTTOM CORE HEIGHT (FEET) s.200 1.17.0 8 TOP s.40o 1.1814 S.800 1.1917 9.800 1.1999 10.00 1.2038

[. 10.20 1.2060 10.400- 1.0000 t

10.800 1.0000  ;

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"*000 FIGURE 4 '0000 l 11.200 1.0000 l 11.400 1.0000 .

SEQUOYAH UNIT 1 CYCLE 5 11.800 1.0000 l 11.800 1.0000 I RAOC

SUMMARY

OF MAX W(2) AT 14000 MWD /MTU 12.000 1.000o-l TOP AND BOTTOM 15% EXCLUDED AS PER TECH SPEC 4.2.2.2.G 1 i

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CORE HEIGHT (FEET) l' FIGURE 5 SEQUOYAH UNIT 1 CYCI.E 5 MAXIMUM (FO

• P(REL)) VS AXIA'L CORE HEIGHT DURING NORMAL CORE OPERATION 4

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