ML040750188
| ML040750188 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/10/2004 |
| From: | NRC/NRR/DLPM |
| To: | |
| Jabbour K, NRR/DLPM, 415-1496 | |
| Shared Package | |
| ML040750002 | List: |
| References | |
| TAC MC0807, TAC MC0808 | |
| Download: ML040750188 (6) | |
Text
RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1
NOTES-----------------------
- 1. Only required to be performed during RCS heatup and cooldown operations or RCS inservice leak and hydrostatic testing when the vessel pressure is > 312 psig.
- 2. The limits of Figure 3.4.9-2 may be applied during nonnuclear heatup and ambient loss cooldown associated with inservice leak and hydrostatic testing provided that the heatup and cooldown rates are < 150F/hour.
- 3. The limits of Figures 3.4.9-1 and 3.4.9-2 do not apply when the tension from the reactor head flange bolting studs is removed.
Verify:
30 minutes
- a. RCS pressure and RCS temperature are within the limits specified by Curves No. 1 and No. 2 of Figures 3.4.9-1 and 3.4.9-2; and
- b. RCS heatup and cooldown rates are
< 100F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.
SR 3.4.9.2 Verify RCS pressure and RCS temperature Once within 15 are within the criticality limits specified in minutes prior to Figure 3.4.9-1, Curve No. 3.
control rod withdrawal for the purpose of achieving criticality (continued)
BFN-UNIT 2 3.4-26 Amendment No.-253, 288
RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.9.5
NOTES----------------------
- 1. Only required to be performed when tensioning the reactor vessel head bolting studs.
- 2. The reactor vessel head bolts may be partially tensioned (four sequences of the seating pass) provided the studs and flange materials are > 700F.
Verify reactor vessel flange and head flange temperatures are > 830F.
30 minutes SR 3.4.9.6
NOTE-------------------------
Not required to be performed until 30 minutes after RCS temperature < 850F in MODE 4.
Verify reactor vessel flange and head flange 30 minutes temperatures are > 830F.
NOTE------------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after RCS temperature < 100'F in MODE 4.
Verify reactor vessel flange and head flange 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> temperatures are > 830F.
BFN-UNIT 2 3.4-28 Amendment No. 2537 288
RCS P/T Limits 3.4.9 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 ROWNS FERRY UNIT2 _2_
CURVES 1, 2, AND 3 3
ARE VALID FOR 23 EFPY OF OPERATION BOTTOM HEAD FLANGE-68 0F' REGION 83F F
Curve No.
1 Minimum temperature for bottom head during mechanical heatup or cooldown following nuclear shutdown.
Curve No. 2 Minimum temperature for upper RPV and beltline during mechanical heatup or cooldown following nuclear shutdown.
Curve No. 3 Minimum temperature for core operation (criticality).
Notes These curves include sufficient margin to provide protection against feedwater nozzle degradation.
The curves allow for shifts in RT,= of the Reactor vessel beltline materials, in accordance with Reg.
Guide 1.99, Rev. 2, to compensate for radiation embrittlement for 23 EFPY.
The acceptable area for operation is to the right of the applicable 0 curves.
200 100 0
0 50 100 150 200 MINIMUM REACTOR VESSEL METAFL TEMPERATURE (OF) 25 Figure 3.4.9-1 Pressure/Temperature Limits for Mechanical Heatup, Cooldown following Shutdown, and Reactor Critical Operations BFN-UNIT 2 3.4-29 Amendment No. 257, 275, 288
RCS P/T Limits 3.4.9 1400 1300 1200 1100 H
to P.
rJ4 0
E-4 0I H
E4 n
1000 900 800 700
- 600 500
,400 300
-BROWNS FERRY UNIT 2 i
CURVES 1 AND 2 ARE VALID FOR 23 EFPY OF _
OPERATION T}1 Mail 17ii BOTTOM HEAD FLANGE 68 0F R-EGION 830 F Curve No. 1 Minimum temperature for bottom head during in-service leak or hydrostatic testing.
Curve No. 2 Minimum temperature for upper RPV and beltline during in-service leak or hydrostatic testing.
Notes These curves include sufficient margin to provide protection against feedwater nozzle degradation.
The curves allow for shifts in RT= of the Reactor vessel beltline materials, in accordance with Reg. Guide 1.99, Rev.
2, to compensate for radiation embrittlement for 23 EFPY.
The acceptable area for operation is to the right of the applicable curves.
200 100 0
0 50 100 150 200 MINIMUM REACTOR VESSEL METAL TEMPERATURE (OF)
Figure 3.4.9-2 Pressure/Temperature Limits for Reactor In-Service Leak and Hydrostatic Testing BFN-UNIT 2 3.4-29a Amendment No. 288
RCS P/T Limits 3.4.9 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 1BROWNS FERRY UNIT 2 -jj
--URVES 1, 2, AND 3
_I ARE VALID FOR 30 2
_EFPY OF OPERATION BTTOM HEAD FLANGE F REGION 7
L ui3 F
Curve No. 2 Minimum temperature for upper RPV and beltline during mechanical heatup or cooldown following nuclear shutdown.
Curve No. 3 Minimum temperature for core operation (criticality).
Notes These curves include sufficient margin to provide protection against feedwater nozzle degradation.
The curves allow for shifts in RTm of the Reactor vessel beltline materials, in accordance with Reg. Guide 1.99, Rev.
2, to compensate for radiation embrittlement for 30 EFPY.
The acceptable area for operation is to the right of the applicable curves.
Curve No. 1 Minimum temperature for bottom head during mechanical heatup or cooldown following nuclear shutdown.
200 100 0
0 50 100 150 200 250 300 MINIMUM REACTOR VESSEL METAL TEMPERATURE (OF)
Figure 3.4.9-1 Pressure/Temperature Limits for Mechanical Heatup, Cooldown following Shutdown, and Reactor Critical Operations BFN-UNIT 2 3.4-29b Amendment No. 288
RCS P/T Limits 3.4.9 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 BROWNS FERRY UNIT 2
-CURVES 1 AND 2 ARE VALID FOR 30 EFPY OF OPERATION
- l _ _ _
BOTTOM-HEAD 68OF FLANGE REGION
.x~zz83OF A :.
4n--t Curve No. 1 Minimum temperature for bottom head during in-service leak or hydrostatic testing.
Curve No. 2 Minimum temperature for upper RPV and beltline during in-service leak or hydrostatic testing.
Notes These curves include sufficient margin to provide protection against feedwater nozzle degradation.
The curves allow for shifts in RTm of the Reactor vessel beltline materials, in accordance with Reg. Guide 1.99, Rev.
2, to compensate for radiation embrittlement for 30 EFPY.
The acceptable area for operation is to the right of the applicable curves.
200 100 0
0 50 100 150 200 250 MINIMUM REACTOR VESSEL METAL TEMPERATURE (OF)
Figure 3.4.9-2 PressurelTemperature Limits for Reactor In-Service Leak and Hydrostatic Testing BFN-UNIT 2 3.4-29c Amendment No. 288