ML20211J150

Proposed Tech Specs,Correcting Page 20 of 970723 TS Amend Request to Relocate RCS Pressure & Temperature Limits from TS to Pressure & Temperature Limit Rept

ML20211J150
Person / Time
Site:	Farley
Issue date:	09/30/1997
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20211J147	List: ML20211J144 ML20211J150
References
NUDOCS 9710080006
Download: ML20211J150 (2)

Text

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t F.NCLOSURE1 Joseph M. Farley Nuclear Plant - Unit 1 Pressure Temperature Limits Report Corrected Page O

9710080006 970930 PDR ADOCK 05000348 p PDR

e

. PRESSURE TEMPERATTJRE LIMITS REPORT Table 5 7 PRESSURIZED THERMAL SHOCK (RTns) VALUES FOR 36 EFPY

• Surface Fluence ARTsw Materiel CF (10 n/cm2, 1 M RTns FF (CF x FF)

E > 1.0 MeV) ('F)

(F) ('F) ('F)

Intermediate Shell Plate B6903 2 91.0 3.97 1.35 123.3 0 34 157 Intermediate Shell Plate B6903 3 82.2 3.97 1.35 111.3 10 34 155 Lower Shell Plate B6919-1 97.8 3.97 1.35 132.5 15 34 182 Lower Snell Plate BC919-1 95.9 3.97 1.35 129.9 15 17 162 Using S/C Data Lower Shell Plate B6919 2 98.2 3.97 1.35 133.0 5 34 172 Intermediate Shell Longitudinal Welds19-894 A & B 118.6 1.23 1.06 125.4 -56 66 135 (Heat # 33 A277)

Intermediate Shell Longitudinal Welds19-894 A & B 75.7 1.23 1.06 80.1 56 44 68 (Heat # 33A277)

Using S/C Data Circumferential Weld 11-894 100.8 3.97 1.35 136.5 56 66 147 (Heat # 6329637)

Lower Shell Longitudinal Welds20-894 A & B 104.0 1.23 1.06 110.0 56 66 120 (Heat # 90099)

NOTES:

I (a) WCAP-14689 '3 1

FARLEY UNIT 1 20 REVISION I

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