ML062080623

Technical Specifications, Uprate of Pressure -Temperature Curves (TAC MC5373) (TS 428)

ML062080623
Person / Time
Site:	Browns Ferry
Issue date:	07/26/2006
From:	NRC/NRR/ADRO/DORL/LPLD
To:
Chernoff M, NRR/DORL, 415-4041
References
TAC MC5373
Download: ML062080623 (7)

Text

(3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive,

.... possess, and use at any lime any byproduct, sou-rce,;and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:

Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3293 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 256, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

For Surveillance Requirements (SRs) that are new in Amendment 234 to Facility Operating License DPR-33, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 234. For SRs that existed prior to Amendment 234, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 234.

Renewed License No. DPR-33 Amendment No. 256

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 < 150 F/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. I and No. 2 of Figures 3.4.9-1 and 3.4.9-2; and

b. RCS heatup and cooldown rates are

< 100°F 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 I 3.4-26 Amendment No. 256

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.5

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 30 minutes temperatures are > 830F.

SR 3.4.9.6 NOTE Not required to be performed until 30 minutes after RCS temperature < 85°F in MODE 4.

Verify reactor vessel flange and head flange 30 minutes temperatures are > 830F.

SR 3.4.9.7 ,NOTE Not required to be performed until 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> after RCS temperature 100°F in MODE 4.

Verify reactor vessel flange and head flange 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> temperatures are > 830 F.

BFN-UNIT 1 3.4-28 Amendment No. 256

Reactor Steam Dome Pressure 3.4.9 1400 -Curve Ho.1- . . ...

2 ~ Minimum temperature for bottom head during 1300- -- - mechanical heatup or cooldown following BRCUNS FE+

CUPRIES 1, f LD_ 3.1 D3NII nuclear shutdown.

1200 ARE V ID FOR 12 EF If O" OP ERA IOD .

Curve No. 2 I . -#- Minimum temperature for upper RPV and beltline

' during mechanical o0 0-"00 * .heatup or cooldown following nuclear F shutdown.

Curve No. 3 80 - Minimum temperature for O :core operation (criticality).

W Cn 70 0 . -

SNotes

> ese curves include 00 sufficient margin to provide protection

• against feedwater 0 500-- [The nozzle degradation.

curves allow for 40- - -shifts in RTr of the 2 40 :Reactor vessel beltline 0 materials, in 3U -: - accordance with Reg.

D 30 .Guide 1.99 Rev. 2 to o0 o compensate for Uj :radiation embrittlement

c. 20 for 12 EFPY.

o BOTTOM FLANGE The acceptable area for 10 68RGIN operation is to the a 03 ii right of the applicable curves.

0 _Z ~

-q --- - i 0 2 5 7 10 12 15 17 20 22 25 27 30 5 D 5 0 5 0 5 0 5 0 5 0 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 I 3.4-29 Amendment No. 256

Reactor Steam Dome Pressure 3.4.9 1400 Curve No. 1 j 2 Minimum temperature for 1300 -bottom head during in-service ISF RRY NIT 1 leak or hydrostatic testing.

1200 S 1.AND 2 1 0LID IOR 1AT Curve No. 2

Minimum RPV and temperature beltline for upper 1100 ,/ during In-service leak or hydrostatic testing.

1000 0o 90 0 . SThese margin curves Include to provide sufficient protection 62 " )against feedwater nozzle 80 - - degradation. The curves allow 0 *for shifts in RTNDT of the Reactor

• vessel beltline materials, In 70 accordance with Reg. Guide 0 1.99 Rev. 2 to compensate for radiation embrittlement for 12

-EFPY.

tJ 60 it 0 0 The acceptable area for 5o operation isto the right of the applicable curves.

0 40 I- 0 30 0

0. 20 *A* : -FLANGE

/ REGION 0

83F 10 0

0 0 25

-4 5 10 0

12 5

15 0

17 5 20 0

MINIMLJM REACTOR VESSEL METAL TEMPERATURE "F Figure 3.4.9-2 Pressure/Temperature Limits for Reactor In-Service Leak and Hydrostatic Testing BFN-UNIT 1 3.4-29a Amendment No. 256

Reactor Steam Dome Pressure 3.4.9 1400 Curve No.- -I-Minimum temperature for 1300 bottom head during mechanical heatup or cooldown following nuclear shutdown.

1200 Curve No. 2 1100 Minimum temperature for upper RPV and beltline during mechanical 1000 heatup or cooldown following nuclear DO NOT USE THIS FIGURE

%turefor This curve applies to operations >12 EFPY.

For current operation, use previous curve, whic"h Is valid up to 12 EFPY. clude lin to

ion

er

ion.

for of the 400 Reactor ves--'ss beltline ILl materials, in accordance with Reg.

300 Guide 1.99 Rev. 2 to U, compensate for 200 i 1 radiation embrittlement for 16 EFPY.

The acceptable area for 100 68F 1 837 operation is to the right of the applicable curves.

0 0 25 50 75 100 125 150 175 200 225 250 275 300 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 1 3.4-29b Amendment No. 256

Reactor Steam Dome Pressure 3.4.9 1400 I I, Curve No. I Minimum temperature fox 1300 1:1 1 21 bottom head during in-service leak or BROI IS FE RY I [IT 1 hydrostatic testing.

1200 ARE VALID FOR : 6 EFPY OF OERAT: ON I Curve No. 2 1100 Minimum temperature for

/ upper RPV and beltline 1000

_ 1-- during in-service leak or hydrostatic testing.

DO NOT USE THIS FIGURE ude I to

)n This curve applies to operations >12 EFPY.

)n for For current operation, use previous curve, which is thp Itline valid up to 12 EFPY. eg.

Lo

.lement 400 telccepcaUle aUrea fox L- operation is to the right of the applicable curves.

300 0U

n. FLANGE 200 BOTTOM HEAD REGIO 681*F 83F 100 0

~~1~ II~ -

0 25 50 75 100 125 150 175 200 MINIMUM REACTOR VESSEL METAL TEMPERATURE "F Figure 3.4.9-2 Pressure/Temperature Limits for Reactor In-Service Leak and Hydrostatic Testing BFN-UNIT I 3.4-29c Amendment No. 256