ML021010301

Technical Specification Pages for Browns Ferry, Units 2 & 3

ML021010301
Person / Time
Site:	Browns Ferry
Issue date:	03/28/2002
From:	NRC/NRR/DLPM/LPD2
To:	Tennessee Valley Authority
References
TAC MB2753, TAC MB2754
Download: ML021010301 (2)

Text

RCS P/T Limits 3.4.9 1600 -

i i iIi Wi [-1 I 1O1 I

IIII-fITIF III Curve No. 1 1500 I I I I I II II I I I I I I I I 1 2 Minimum temperature for pressure BROWNS FERRY UNIT 2 11 /1 tests such as required by ASME Section Xi.

1400 CURVES 1,2, & 3 APE VAUD FOR 17.2 EFPY OF Curve No. 2 1300 OPERAMION I1 Iyit Minimum temperature for I I I mechanical heatup or cooldown

.°' 1200 following nuclear shutdown.

0.

- - - - - - - - - - - - - - - -;- j/jjj//jji

• Curve No. 3 1100 Minimum temperature for core

---

C-- operation (criticality).

° 1000 I

-j Notes LU Co 900 These curves include sufficient LU

--- I---- margin to provide protection 1 against feedwater nozzle o0 800 degradation. The curves allow for

- - - - - - - - - - - --- shifts in RTNDT of the Reactor vessel beltline materials, in z

accordance with Reg. Guide 1.99,

, 600 Rev. 2, to compensate for radiation embrittlement for 17.2 a:

LU EFPY.

D 3 o 5D00 Co Lu cL 400-

_ . . . . .I I I. I 1 1- 1 1 11 1 1 1 11 I I I I I 300- . 1 *I-IJ 2P'SIG BOLTUP hI /

r 7 200- 82 OF ff _

I I I I.

IIIILEI -IE I IEIIEIIIIIEPE 0 lI I I I 0 100 150 200 250 MINMUM REACORVESSL METALTEUPRA1URE )

Figure 3.4.9-1 Pressure/Temperature Limits BFN-UNIT 2 3.4-29 Amendment No. 2 275

RCS P/T Limits 3.4.9 1600 I-=

1500 2 _- 3 - Curve No. 1 BROWNS FERRY UNIT 3 -- - _ _ Minimum temperature for 1 CURVES 1, 2, & 3 ARE I _- pressure tests such as required by VALID FOR 13.1 EFPY OF ASME Section Xl.

OPERATION 1300 - -'- -Curve No. 2

_ -_ _ _ _ _ _" _ _r-_ I_ - Minimum temperature for 1200mechanical heatup or cooldown 10-- _- - - - following nuclear shutdown.

__Curve No. 3 Minimum temperature for core

a. 1000 _ operation (criticality).

0 sThese 900 - - No-es curves include sufficient margin to provide protection

- 800 _ _ against feedwater nozzle

__ ____ - degradation. The curves allow for 700 ___ shifts in RTNDT of the Reactor Z vessel beltline materials, in

- - - - - - accordance with Reg. Guide 1.99,

• 600 - _ r- - - - - Rev. 2, to compensate for S2- - - - - - - - radiation embrittlement for 13.1 500- -EFPY.

400 50

2) - - - - - - - - - -F - --

°00 - - --- -312P 25G BOLTUP CLO _I 70 OF

_ LL 200 100-I0 ---- - - -------

0 50 100 METAL 150 TEMPERATURE 200 (ff) 250 M INIMUM REACTOR VESSEL Figure 3.4.9-1 Pressure/Temperature Limits BFN-UNIT 3 3.4-29 Amendment No. 247-, 233