ML022260680
| ML022260680 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/13/2002 |
| From: | George Wunder Office of Nuclear Reactor Regulation |
| To: | |
| Wunder G, NRR/DLPM, 415-1494 | |
| References | |
| TAC MB4685 | |
| Download: ML022260680 (3) | |
Text
Figure 3.4.6.1-1 Hydrostatic Pressure and Leak Tests Pressure/Temperature Limits - Curve A 100 All system leakage and hydrostatic pressure tests performed during the service life of the pressure boundary in compliance with ASME Code Section XI 1,200 1,100 o.1,000 g1ooo
" 900 0 I-800 U
700 o
600 15s00 t:
400 2
"U 300 U,
A.
to 100 0
Beilt? e
- Bottom Head
-- Upper Vessel 200 150 250 MINIMUM REACTOR VESSEL METAL TEMPERATURE (-F)
Note:
This figure is valid through Cycle 14 12 Operation in accordance with NRC Safety Evaluation Report supporting Amendment No. 13 9 Amendment No. 4-34, 139 02 top
- r 01DPV f
7 9!
tupl 0
50 HOPE CREEK 3/4.4-23
Figure 3.4.6.1-2 Non-Nuclear Heatup and Cooldown Pressure/Temperature Limits - Curve B 100 150 1,200 1,100 0..
CL 1,000 0
900
- 0.
0 o"
800 S
700 w
o 600 S400
,I w 3500 200 W
I. 100 0.
Beftline
- - - Bottom Head
-Upper Vessel FVTF1 I
I I
200 250 MINIMUM REACTOR VESSEL METAL TEMPERATURE (F)
This figure is valid through Cycle 44 12 Operation with NRC Safety Evaluation Report supporting Amendment No. 139 Amendment No. 4-34, 139 All heatup and cooldowns that are performed when the reactor is not critical at the normal heatup and cooldown rate of lO0 Flhr
^r'eg rs Iadar32EnY oltup 79F 0
50 Note:
4 I I E
I 3/4 4-23a HOPE CREEK
Figure 3.4.6.1-3 Core Critical Heatup and Cooldown PressureiTemperature Limits - Curve C 1,200 1,100 1,000 900 800 700 600 500 400 300 200 100 0
0 All heatup and cooldowns that are I
performed when the reactor Is critical at
--- the normal heatup and cooldown rate of r
Minimum criticality withm normal water level 88"F CL
- 0.
W
- 0.
W 0
IJ1 wJ Co I
z_
Col U)
'U 50 100 150 200 250 Note:
HOPE CREE MINIMUM REACTOR VESSEL METAL TEMPERATURE (OF)
This figure is valid through Cycle 14 12 Operation in accordance with NRC Safety Evaluation Report supporting Amendment No. 139 "K
3/4 4-23b Amendment No. 1--4, 13' 17 9
i I I i I i I I I, ", i i !