ML051790230
| ML051790230 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/16/2005 |
| From: | Crouch W Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TVA-BFN-TS-428 | |
| Download: ML051790230 (6) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabarna 35609-2000 June 16, 2005 TVA-BFN-TS-428 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:
In the Matter of
)
Docket No. 50-259 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 1 -
SUPPLEMENT TO TECHNICAL SPECIFICATIONS (TS)
CHANGE 428 -
UPDATE OF PRESSURE-TEMPERATURE (P-T) CURVES This letter supplements proposed Technical Specification (TS) 428, which revises the reactor vessel P-T limit curves.
TVA identified a typographical error on the mark-up and clean TS pages 3.4-29 and 3.4-29a.
The notes on these pages should have referenced 12 Effective Full Power Years (EFPY) instead of 16 EFPY.
Updated pages are enclosed with this submittal.
TVA has determined that the supplemental information provided does not affect the no significant hazards considerations associated with the proposed amendment and TS changes.
The proposed amendment and TS changes still qualify for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c) (9)
Jio0
U.S. Nuclear Regulatory Commission Page 2 June 16, 2005 If you have any questions about this submittal, please contact me at (256) 729-2636.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on June 16, 2005.
Sincerely, William D. Crouch Acting Manager of Licensing and Industry Affairs
References:
- 1.
TVA letter, T.E. Abney to NRC, dated December 6,
- 2004, "Browns Ferry Nuclear Plant (BFN) Unit 1 -
Technical Specifications (TS)
Change TS 428 - Update Of Pressure-Temperature (P-T) Curves."
U.S. Nuclear Regulatory Commission Page 3 June 16, 2005 Enclosure cc (Enclosure):
State Health Officer Alabama Dept. of Public Health RSA Tower -
Administration Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 Margaret Chernoff, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739
ENCLOSURE BROWNS FERRY NUCLEAR PLANT, UNIT 1 TECHNICAL SPECIFICATION CHANGE REQUEST (TS 428)
UPDATE OF PRESSURE-TEMPERATURE (P-T) CURVES
Reactor Steam Dome Pressure 3.4.9 1400 Curve No. 1 1
2 3
Minimum temperature for bottom head during 1300 mechanical heatup or BRC NS FE RY l NII 1:
cooldown following nuclear shutdown.
- CURVSi1,
%ND i-ARE V,ID FOR 12 EFE 0 0O ERA 10 Curve No. 2 1100 Minimum temperature for upper RPV and beltline during mechanical 1000 heatup or cooldown
- following nuclear shutdown.
90
_1 0
W Curve No. 3
- 80.
Minimum temperature for
° 0
core operation (criticality).
i., 70 0_
Notes z
60 These curves include
°o sufficient margin to I
0 I
provide protection 50 against feedwater s
nozzle degradation.
Z 0
The curves allow for shifts in RTND of the n
40 l
Reactor vessel beltline
.J 0
- materials, in
'u accordance with Reg.
=
0 0
Guide 1.99 Rev. 2 to 0
./compensate for W
.radiation embrittlement
- 0. 20 for 12 EFPY.
0 BOTTOM FLANGE The acceptable area for 10 68-F REGION operation is to the 0
_3 right of the applicable curves.
0 2
5 7
10 12 15 17 20 22 25 27 30 5
0 5
0 5
0 5
0 5
0 5
0 MINIMUM REACTOR VESSEL METALTEMPERATURE F Figure 3.4.9-1 Pressure/Temperature Limits for Mechanical Heatup, Cooldown following Shutdown, and Reactor Critical Operations BFN-UNIT 1 3.4-29 Amendment No. 234
Reactor Steam Dome Pressure 3.4.9 1400 1300 1200 1100 1000 U,3 LI.
In 0.o 2
M 0
IU
-J U,
cc:
0 2
cx U,
C,,
cc:
0.
90 0
80 0
70 0
60 0
50 0
40 0
30 0
20 0
BRO NSF RRY NIT 1 CURES 1 AND2 2 ARE LID FOR 12 i EFPY OF OJERAT ON
_/
FLANGE BorroM-REGION HEAD 83'F 68'F To__
_-I-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 RTNDT of the Reactor vessel beltline materials, in accordance with Reg. Guide 1.99 Rev. 2 to compensate for radiation embrittlement for 12 EFPY.
The acceptable area for operation is to the right of the applicable curves.
10 0
0 0
25 50 75 10 0
12 5
15 0
17 5
20 0
MINIMUM REACTOR VESSEL METAL TEMPERATURE eF Figure 3.4.9-2 Pressure/Temperature Limits for Reactor In-Service Leak and Hydrostatic Testing BFN-UNIT 1 3.4-29a Amendment No. 234