ML20035H132
| ML20035H132 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/22/1993 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035H133 | List: |
| References | |
| NUDOCS 9305030187 | |
| Download: ML20035H132 (12) | |
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UNITED STATES
[di
'I j NUCLEAR REGULATORY COMMISSION l
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WASHINGTON. D.C. 20555-0001
.,Y,.*
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 211 License No. DPR-52 The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated August 25, 1992, as supplemented on December 23, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
a 9305030187 930422 PDR ADOCK 05000260 P
^
. 2.
Accordingly, the license is amended by change's to the Technical Specifications as indicated in the attachment to this license amendment i
and paragraph 2.C.(2) of Facility Operating License No. DPR-52 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 211, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical i
Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
.f Frederick J. Heb@ n, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 22,1993 j
}
r DOCKET NO. 50-260 ATTACHMENT 10 LICENSE AMENDMENT NO. 211 FACILITY 0PERATING LICENSE NO. DPR-52 l
i UNIT 2 i
EFFECTIVE PACE LIST P
P INSERT
' REMOVE
]
3.2/4.2-31 3.2/*.2-31 l
3.2/4.2-32 3.2/4.2-32 l
3.2/4.2-54 3.2/4.2-54*
l 3.2/4.2-55 3.2/4.2-55 i
- Denotes overleaf page h
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TABLE 3.2.F Surveillance Instrumentation C tD o *1 P' Z Minimum # of Operable Instrument Type Indication N
Channels Instrument #
Ins t rument and Rance Notes 4
2 LI-3-5BA Reactor Water Level Indicator -155" to (1) (2) (3)
LI-3-5BB
+60" 2
PI-3-74A Reactor Pres ure Indicator 0-1200 psig (1) (2) (3)
PI-3-748 2
XR-64-50 Drywell Pressure Recorder -15 to +65 psig (1) (2) (3) l PI-64-67B Indicator -15 to +65 psig d
2 XR-64-50 Drywell Temperature Recorder, Indicator (1) (2) (3)
TI-64-52AB 0-400'F l
1 XR-64-52 Suppression Chamber Recorder 0-400'F (1) (2) (3)
Air Temperature 1
N/A Control Rod Position 6V Indicating
)
g Lights
)
s 4=
1 N/A Neutron Monitoring SRM, IRM. LPRM
)
(1) (2) (3) (4) 0 to 100% power
)
g b
1 PS-64-67B Drywell Pressure Alarin at 35 psig
)
w
)
1 TS-64-52A &
Drywell Temperature Alarm if teep.
)
PIS-64-58A &
and Pressure and
> 281*F and
)
(1) (2) (3) (4) -
IS-64-67A Timer pressure >2.5 pstg )
7=
after 30 minute
)
M delay
)
3 1
LI-84-2A CAD Tank "A" Level Indicator 0 to 100%
(1) 5 1
LI-84-13A CAO Tank "B" Level Indicator 0 to 1000 (1)
U
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C to TABLE 4.2.F
- 3 M gZ H
HINIMUM TEST AND CAllBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION N
Instrument Channel
{_alibration Frecuency Instrument Check
- 1) Reactor Water Level Once/6 months Each Shift (LI-3-58A&B)
- 2) Reactor Pressure Once/6 months Each Shift (PI-3-74A&B)
- 3) Drywell Pressure Once/6 months Each Shift (PI-64-67B) and XR-64-50
- 4) Drywell Te=verature Once/6 months Each Shift (TI-64-52AB) and XR-64-50
- 5) Suppression Chamber Air Temperature Once/6 months Each Shift g
(XR-64-52)
- 8) Control Rod Position N/A Each Shift
- 9) Neutron Monitoring (2)
Each Shift y
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- 10) Drywell Pressure (PS-64-678)
Once/6 months N/A
- 11) Drywell Pressure (P15-64-5BA)
Once/6 months N/A
- 12) Drywell Temperature (TS-64-52A)
Once/6 months N/A
- 13) Timer (15-64-67A)
Once/6 months N/A
- 14) CAD Tank Level Once/6 months Once/ day
- 15) Containment Atmosphere Monitors Once/6 months Once/ day
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UNITED STATES jf[IQl j NUCLEAR REGULATORY COMMISSION gyg ry wasmcTou. o c 20sss.ooo, s,
1 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 163 License No. DPR-68 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated August 25, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR 7
Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
i 1
F I
f i
i
l
. l 2.
Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendment 1
and paragraph 2.C.(2) of Facility Operating License No. DPR-68 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.168, are hereby incorporated in the license. The l
licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Frederick J. Hebdon, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
i Changes to tne Technical Specifications Date of Issuance: April 22, 1993 i
r
DOCKET NO. 50-296 ATTACHMENT TO LICENSE-AMENDMENT NO. 168 l
FACILITY OPERATING LICENSE NO. OPR-68 UNIT 3 EFFECTIVE PACE LIST REMOVE INSERT 3.2/4.2-30 3.2/4.2-30 3.2/4.2-31 3.2/4.2-31*
- Denotes overleaf page l
i 9
L i
i 5
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i
TABLE 3.2.F Surveillance Instrumentation Minimum # of pZ Operable Instrument Type Indication Channels Instrument #
Instrument and Range Notes u
2 LI-3-46 A Reactor Water Level Indicator - 155" to (1) (2) (3)
LI-3-46 B
+60" 2
PI-3-54' Reactor Pressure Indicator 0-1500 psig (1) (2) (3)
PI-3-61 2
XR-64-50 Drywell Pressure Recorder -15 to +65 psig (1) (2) (3)
PI-64-67 Indicator -15 to +65 psig 2
TI-64-52 Drywell Temperature Recorder, Indicator (1) (2) (3)
XR-64-50 0-400*F l
1 XR-64-52 Suppression Chamber Recorder 0-400*F (1) (2) (3) l Air Temperature 1
N/A Control Rod Position 6V Indicating
)
F Lights
)
w 1
N/A Neutron Monitoring SRM. IRM, LPRM
)
(1) (2) (3) (4)
O to 100% power
)
y 1
PS-64-67 Drywell Pressure Alarm at 35 psig
)
i u
)
0 1
XR-64-50 and Drywell Temperature Alarm if temp.
)
PS-64-58 B and and Pressure and
> 281*F and
)
(1) (2) (3) (4) l 15-64-67 Timer pressure >2.5 psig )
after 30 minute ' )
del ay
)
ya 1
LI-84-2A CAD Tank "A" Level Indicator 0 to 100%
(1) ct 1
LI-84-13A CAD Tank "B" Level Indicator 0 to 100%
(1) 5 I
m m.
m.
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c to TABLE 3.2.F (Cont'd)
DM P' %
Survelliance Instrumentation g
w Minimum # of Operable Instrument Type Indication Channels Instrument #
Instrument and Rance Notes i'
2 H M 94 Drywell and 0.1 - 20%
(1) 2 Torus H M 104 Hydrogen 2
Concentration 2
Pd!-64-137 Drywell to Indicator (1) (2) (3)
Suppression 0 to 2 psid Pd!-64-138 Chamber Differential Pressure 1/ Valve Reller Valve (5)
Tallptpe W
Thermocouple Temperature or y
Acoustic Monitor on Relief Valve Tailpipe g
b 2
LI-64-159A Suppression Indicator, (1) (2) (3)
F' Chamber Vater Recorder 0-240" XR-64-159 Level-Wlde Range 2
PI-64-160A Drywell Pressure Indicator, Recorder)
(1) (2) (3)
XR-64-159 Wide Range 0-300 psig
)
2 TI-64-161 Suppression Pool Indicator, Recorder)
(1) (2) (3) (4) (6)
T R-64-161 Bulk
)
TI-64-162 Temperature 30* - 230* F
)
TR-64-162
)
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