ML20080G186

Revised Pages to Safety Evaluation Submitted w/830701 Cycle 2 Reload Application

ML20080G186
Person / Time
Site:	Sequoyah
Issue date:	09/13/1983
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20080G182	List: ML20080G181 ML20080G186
References
TVA-SQN-TS-47, NUDOCS 8309200120
Download: ML20080G186 (4)

Text

. .

e r* o

1.0 INTRODUCTION

AND

SUMMARY

Sequoyah Unit 2 is in its first cycle of operation. The. unit is

, expected to refuel-and be ready for Cycle 2 startup in November 1983.

This report presents an evaluation for Cycle 2 operation which demonstrates that the core reload will not adversely affect the safety of the plant. Those incidents analyzed and reported in the FSAR(1) which could potentially be affected by fuel reload have been reviewed for the Cycle 2 design described herein. The applicability of the current nuclear design limits was verified for Cycle 2 using the methods described-in Reference 2. The results of new analyses have been

- included, and the justification for the applicability of previous results from the remaining analyses is presented. It has been concluded that the Cycle 2 design does not cause the previously acceptable safety limits for any incident to be exceeded.

. The above operational conclusions are based on the assumption that: (1)

Cycle 1 nominal burnup is 15,100 + 500 MWD /MTV, (2) Cycle 2 burnup is limited to 11,500 MWD /MTU, and (3) there is adherence to plant operating limitations given in the technical specifications and their proposed modifications presented herein. The irapact of this reload has been evaluated and found to be within the safety limit as described in this RSE for Cycle 2.

During the Cycle 1/2 refueling sixty-eight Region 1 fuel assemblies will be replaced by sixty-eight Region 4 assemblies. One of the 68 Region 4 assemblies has nineteen fuel rods of 3.40 w/o U-235. See Table 1 for the number of fuel assemblies in each region, Figure 1 for the Cycle 2 core loading pattern and Figure 1A for the placement of the nineteen 3.4 w/o U-235 fuel rods.

Nominal design parameters for Cycle 2 are 3411 MWt core pow r, 2250 psia core pressure, nominal core inlet temperature of 546.7 F, and core average linear power of 5.43 kw/ft.

s' I

8309200120 830913 PDR ADOCK 05000328 p PDR -

~ -* * *

• CORE LOADING PATTEFil

, , ,. Sequoyah Unit 2. Cycle 2 R P N H L X J H G F E D C B A 4 4 4 2 -

4 4 4 I i 4 4 4 2 4 1 4 2 4 4 4 12 8 8 12 ,

. 4* 4 2 2 4 2 3 4 i 4 2 2 4 4 8 12 12 8 33 ,

4 2 3 3 2 2 2 2 2 3 3 2 4 l

4 4 2 3 .2 3 3 3 3 3 2 3 2 4 4

. 12 . 12 4 2 4 l2 3 2 3 2 3 2 3 2 4 / 4 I 12 l 12 4 4 8

'2 2 3 3 2 3 2 3 3 2 2 4 8

4 90

. 4 4 2 2 3 3 2 3 2 3 3 2 2 4 4 8 8 4 2 4 2 3 2 3 2 3 '2 3 2 4 2 4 ,

12 12 i

~

~~

4 4 2 3 2 3 3 3 3 3 2 3 2 4 4 ,

12 12

• 8 4 2 3 3 2 2 2 2 2 3 3 2 4 3

4 4 2 2 4 2 3 2 4 2 2 4 4 8 )

i 12 y 12 . 8 4 4 4 2 4 1 4 2 4 4 4

• 'I 12 8 8 12 4 4 4 2 4 4 4 1

0 x - Region Numbar Y - Number of Burnable Poison Rods .

" - Secondary Source Rods s

• Assembly contains nineteen fuel rods of 3.40 w/o U-235

-- w ._m,e...n.-.. .--e-.w ww-> y --weeee +c* - -

m-- _mev----w.wve-e---v--

w er--*t w--a3r -mwwre--re-ayg== --wew- =v---wwg ewrve r -w. wwyy