ML20117G712
| ML20117G712 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/30/1996 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20117G709 | List: |
| References | |
| NUDOCS 9609050295 | |
| Download: ML20117G712 (8) | |
Text
1 ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
{
UNITS 1,-l2, AND 3 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE _TS-380 MARKED PAGES l
I.
AFFECTED PAGE LIST 1
Unit 1 Unit 2 Unit 3 3
4 3
l II.
MARKED PAGES
]
1 See attached.
I 9609050295 960830 PDR ADOCK 05000259 P
. - - _ ~
w l
APRIL 16, 1996 4
)
(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 er equipment and instrument calibration or associated with radioactive apparatus
]
or components; g
(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 amended license shall be deemed to contain and is subject to the j
conditions specified in the following Conunission regulations in 4
10 CFR Chapter I:
Part 20, Section 30.34 of Part 30, Section 40.41 i
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 i
the rules, regulations, and orders of the commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below j
(1)
Maximum Power Laval P
l 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, j
as revised through Amendment No. 229 are hereby incorporated in l
z the license. The licenses shall operate the facility in l
accordance with the Technical Specifications.
(3) '
e operation of the facility, the licensee shall, pursuant 1
to the F rel-Mat _er Pollution Control Act Amendments of 1972 (Public Law 92-500), comp 11 applicable thermal water
_m D E LEN C O quality standarda of the State of Al
- - *ha United States.
w (4)
Deleted.
(5)
The facility may be modified by plugging the bypass flow holes j
in the lower core support plate as described in Browns t'erry
{
i Nuclear Plant Units 1 and 2 Safety Analysis Report for flant i
i Modifications to Iliminate Significant In-Core Vibrations (NEDC-21091), October 1975.
The reactor shall not be operated i
with the plugs installed in the lower core support plate bypass flow holes without further authorization by the NRC.
BFN Unit 1 NO. 2 2 0 4
4 APR 01, 1993 (3)
In eration of the facility, the licensee shall, pursuant to the Federa ollution Control Act Amendments of 1972 O g g, (Public Law 92-500), comply wi licable thermal wacer quality standards of the State of Alabama and' & Ur.it d (4)
The licensee is hereby granted an exemption from the requirements of General Design Criterion 4 with respect to high energy pipes outside containment in accordance with the condition set forth in the Technical Specifications, Section 3.6.G.2 which requires completion of those items listed in " Concluding Report on the Effects of Postulated Pipe Failure Outside of Corstainment for the Browns Ferry Nuclear Plant Units 2 and 7" and related to Unit 2 prior to startup of Unit 2 following the first refueling outage.
l (5)
The facility may be modified by plugging the bypass flow holes l
in the lower core support plate as described in Browns Ferry Nuclear Plant Units 1 and 2 Safety Analysis Report for Plant Modifications to Eliminate Significant In-Core Vibrations (NEDC-21091), October 1975.
The reactor shall not be operated with the plugs installed in the lower core support plate bypass flow holes without further authorization by the NRC.
(5) (a)
Deleted (6)
The facility may be modified by drilling bypass flow holes in Type 2 and Type 3 fuel assemblies as described in NEDO-21091,
" Browns Ferry Nuclear Plant, Units 1 & 2 Safety Analysis Report for Plant Modifications to Eliminate Significant In-Core Vibrations; and NEDE-21156, " Supplemental Information for Plant Modification to Eliminate Significant In-Core Vibrations," dated January 1976.
(7)
The facility may be modified as described in " Browns Ferry Nuclear Plant Units 1 and 2 Emergency Core-Cooling Systems Low Pressure Coolant Injection Modifications for Performance Improvement (December 1975)" submitted by application dated December 1, 1975 and supplements dated February 12, 1976, March 24, 1976, March 30, 1976, May 21, 1976, June 11, 1976, and July 21, 1976.
l i
1 h W.207 arN Unit 2
)
. ~
APRIL 16, 1996 (3)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess and use at any time any byproduct, source 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 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 license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter Is 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; and is subject to all (pplicable 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 belows (1)
Mari tmim 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)
Techn4emi snacificatiana The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 204 are hereby incorporated in the l
license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
In ration of the facility, the licensee shall, pu*.suant to the Federal %
Pollution Control Act Amendments of 1972 (Public Law 92-500), comp applicable thermal water ggr ec j
quality standards of the State of Alabama United States. /
~
J
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ANENDMDR 5. 2 0 4 BFN Unit 3
ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY BROWNS PERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-380 REVISED PAGES i
I.
AFFECTED PAGE LIST i
I Unit 1 Unit 2 Unit 3 i
3 4
3 l
l II.
REVISED PAGES l
l See attached.
i f
l I
l l
1
_- ~.
l i
i i
f (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 I
chemical or physical form for sample analysis or equipment and g
instrument calibration or associated with radioactive apparatus j
or components; i
(5)
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but f
not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This amended license shall be deemed to contain and is subject to the l
conditions specified in the following Commission regulations in i
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 I
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 l
l state reactor core power levels not in excess of 3293 megawatts thermal.
(2)
Technical Snecifications The Technical Specifications contained in Appendices A and B, f
I as revised through Amendment No. 229 are hereby incorporated in the license. The licensee shall operate the facility in
.j accordance with the Technical Specifications.
(3)
Deleted.
d i
(4)
- Deleted, j
i l
(5)
The facility may be modified by plugging the bypass flow holes l
in'the lower core support plate as described in Browns Ferry Nuclear Plant Units 1 and 2 Safety Analysis Report for Plant l
l Modifications to Eliminate Significant In-Core Vibrations (NEDC-21091),. October 1975.
The reactor shall not be operated with the plugs installed in the lower core support plate bypass flow holes without further authorization by the NRC.
BFN.
Unit 1
. (3)
Deleted.
d (4)
The licensee is hereby granted an exemption from the requirements of General Design criterion 4 with respect to high energy pipes outside containment in accordance with the condition set forth in the Technical Specifications, Section 3.6.G.2 which requires completion of those items listed in " Concluding Report on the Effects of Postulated Pipe Failure Outside of Containment for the Browns Ferry Nuclear Plant Units 2 and 3" and related to Unit 2 prior to startup of Unit 2 following the first refueling outage.
(5)
The facility may be modified by plugging the bypass flow holes in the lower core support plate as described in Browns Ferry Nuclear Plant Units 1 and 2 Safety Analysis Report for Plant Modifications to Eliminate Significant In-Core Vibrations (NEDC-21091), October 1975.
The reactor shall not be operated with the plugs installed in the lower core support plate bypass flow holes without further authorization by the NRC.
(5) (a)
Deleted (6)
The facility may be modified by drilling bypass flow holes in Type 2 and Type 3 fuel assemblies as described in NEDO-21091,
" Browns Ferry Nuclear Plant, Units 1 & 2 Safety Analysis Report for Plant Modifications to Eliminate Significant In-Core Vibrations; and NEDE-21156, " Supplemental Information for Plant Modification to Eliminate Significant In-Core Vibrations,"
dated January 1976.
(7)
The facility may be modified as described in " Browns Ferry Nuclear Plant Units 1 and 2 Emergency Core Cooling Systems Low Pressure Coolant Injection Modifications for Performance Improvement (December 1975) " submitted by application dated December 1, 1975 and supplements dated February 12, 1976, March 24, 1976, March 30, 1976, May 21, 1976, June 11, 1976, and July 21, 1976.
i BFN Unit 2 l
S
1 I
a s
. 1 (3)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess and use at any time any byproduct, source 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 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 license shall be deemed to contain and is subject to the conditions specified in the following Commission egulations in 10 CFR Chapter I: Part 20, Section 30.?. of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 et Part 50, and Section~70.32 of Part 70; and is subject to all applicable provisiens of the Act and to the rules, regulations, and orders of the Comm!.ssion now or hereafter in effect; and is subject to'the additional conditions specified or incolporated below:
1 (1)
Maximum Power Level I
The licensee is authorized to operate the facility at steady state reactor core power leve s not in excess of 3293 megawatts thermal.
I (2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 204 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Deleted.
d BFN Unit 3