ML18227D110

Letter Re Description of Cycle 2 Reload Fuel

ML18227D110
Person / Time
Site:	Turkey Point
Issue date:	02/07/1975
From:	Robert E. Uhrig Florida Power & Light Co
To:	Case E Office of Nuclear Reactor Regulation
References
L-75-82
Download: ML18227D110 (17)

Text

NRC DISTR UTIPN FOR PART 50 DOCKET MA IAL (TEMPORARY FORM)

CONTROL Np:

1664 FILE'RpM.

Florida Power 6 Light C

~ DATE pF DpC Miami, Florida Robert E

Uhri 2-7-75 DATE R EC'D 2-14-75 LTR TWX RPT OTHER xxxx Tp:

tfr. Edson G. Case CLASS UNCLASS PROP INFO xxxxx DESCRIPTION:

ORIG 3-signed INPUT CC OTHER Np CYS REC'D 3

ENCLOSURES:

SENT AEC PDR SENT LOCALPDR x~

DOCKET Np:

50-251 Ltr trans the following:

Descri,ption of Cycle 2 Reload Fuel for Turkey Point Unit 4. ~. ~ ~

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Turkey P~i~t y4 FOR ACTION/INFORMATION BUTLER (L)

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P. COLLINS ENISE EG OPR FILE 5 REGION (2)

T.R. WILSON STEE LE TECH REVIEW SCHROEDER MACCARY KNIGHT PAWLICKI SHAO STE LLO HOUSTON NOVAK ROSS IPPOLITO TEDESCO LONG LAINAS BENAROYA VOLLMER INTERNALDISTR IBUTION

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E. COUPE PETERSON HART F I E LD (2)

KLECKER EISENHUT W IGG INTO N LpCALPDR Homestead, Fla

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BOX 013100, MIAMI,FLORIDA 33101

==

FLORIDA POWER 5 LIGHT COMPANY February-7, 1975 L-75-82 Mr. Edson G.

Case, Acting Director Office of Nuclear Reactor Regulation U.

S. Nuclear Regulatory Commission Washington, D.

C.

20555 Dear Mr.- Case; Re:

Turkey Point Plant Unit No.

4 Docket No. 50-251 Descri tion of C cle 2 Reload Fuel Florida Power 6 Light Company herein submits a description of the reload fuel for use in Turkey Point Unit 4 for Cycle 2 operation.

Upon completion of Cycle 1 operation, expected about the later part of March, we plan to replace 52 Region 1 assemblies with Region 4

assemblies.

The fuel design parameters for Turkey Point Unit 4, Cycle 2 are summarized in Table l.

Other physical design aspects of Region 4

fuel assemblies are the same as Region 3, except the initial prepressurization level of Region 4 has been increased by 50 psi.

Two of the Region 4 assemblies are removable rod type assemblies, each of which may have 12 special fuel rods containing advanced process fuel.

The mechanical design of the removable rod assemblies is identical to the design of the removable rod assemblies licensed for Carolina Power 6 Light Company (H.

B. Robinson unit 2) and our Turkey Point Unit 3

~ It is comparable to the design of removable rod assemblies licensed for Uirginia Electric Power (Surry Unit 1),

Commonwealth Edison (Zion Unit 1),

and Wisconsin Michigan Power Company/Wisconsin Electric Power Company (Point Beach Unit 1).

An evaluation (1) of the nuclear, thermal and hydraulic performance of these demonstration assemblies has shown them to be essentially the same as standard Region 4 fuel assemblies and thus, do not result in more limiting reactor conditions than a standard Region 4 assembly in the same location.

3.86l~

HELPING BUILD FLORIDA

II'

0 Mr. Edson G.

Case February 7,

1975 Unit 4 system pressure will be increased from the Cycle 1 system pressure

'of 1900 psia to 2250 psia for Cycle 2.

No clad flattening is predicted to occux during Cycle 2,. based on the Westinghouse revised clad flattening model.

(2), Accordingly, the limiting fuel residence 'time 'for Unit '4 is determined by Region, 3 assemblies, and is 30,000 EFPH.

Table 2,compares the range of core phy'sics parameters addressed in the safety analysis for Cycle 1 with those of Cycle '2.

Table 3

lists 'the available 'shutdown margin in Cycle 2.

The control xod insertion limits for Cycle 2, two loop operation, axe pxovided in Figure 1

~

The insertion limits for Cycle 2, three loop operation, are sho'wn in Figure '2.

The accidents covered in the FSAR have been review'ed fox the proposed Cycle.'2 fuel and we 'conclude that the core reload will not make the,'.consequences of these accidents more 'severe than the accep'table limits prev'iously reported in the 'applicable safety analysis.

We shall be submitting, under separate cover, proposed changes to the Technical Specification to support the Cycle 2,reload,'er uly yours, Robert E. Uhrig Vice Pxesiden't REU.nch

'ttach.'c:

Mr. Jack R.

Newman

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Table 1

Turkey Point Unit 4-Cycle 2

Fuel Assembly Design Parameters

~Re ion Enrichment

(% U-235)

Density

(% theoretical)>>

No. of assemblies 1

2 3,'.

4

1. 85

2. 56 3.11 2.55 1

52 52 52 93.88 92.71 92.14 95.00 Approximate burnup at beginn-'ng of Cycle 2

(MWD/MTU) 12300 15100 10050

>>Regions 1,2, and 3 are as-built values; Region 4 is nominal value;

however, a lower density of 94.5% theoretical was used in thermal evaluations.

Table 2

Turkey Point Unit 4

'Kinetics Characteristics FSAR(')

(2250 sia)

Cy.l. 1 (4)

(1900 sia)

Cycle 2

(2250 sia)

Moderator Temperature Coefficient,

( hp/o F)x10 Doppler Coefficient,

( hp/o F) x 105 Delayed Neutron Fraction, jeff'%)

Prompt Neutron Lifetime

(@sec)-

Shutdown Margin

-3.5 to +0.3+

-3:5 to 0

-1.6 to.1.0 -1.6 to -1.2 0.52 to 0.72 0.52 to 0.70 14

-3.5 to 0

-2.6 to -1.0 0.50 to,0.50 14

>1. 77 "The positive coefficient does not occur at operating conditions.

Table 3

Turkey Point Unit 4 Cycles 1 and 2

END OF CYCLE Shutdown Requirements and Margins Item Control Rod Worth at HZP

(%hp)

All Full Length Rods Inserted 7.71 7.52

~Cele l

~C'.cle 2

All Full Length Rods Inserted Less Worst Stuck Rod (F-14)

(1) Less 10%

6. 47 5.82

6. 40 5.76 Control Rod Re uirements Power Defect (Combined Doppler, Tavg, Void and Redistribution Effects)

3. 07

2. 74 Rod Insertion Allowance (2) Total Requirement

0. 70

0. 70 3.77

'. 3.44 Shutdown Margin ( (1) - (2)

)

(%)

r Required Shutdown Margin

~(%)

2'5

l. 77 2.32 1.,77

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REFERENCES 1.

"Irradiation of Demonstration Assemblies in Turkey Point Unit 4, WCAP-8461, January, 1975.

2.

"Revised Clad Flattening Model"*, WCAP-8381, July, 1974.

3.

"Final Safety Analysis Report',

Turkey Point Units No.

3 and 4.

4.

"Fuel Densification, Turkey Point Plant Units, No.

3 and 4, Low Pressure Analysis", WCAP-8137,

June, 1973.

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