ML20237G068
| ML20237G068 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/26/1987 |
| From: | Zwolinski J NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20237G070 | List: |
| References | |
| TAC-64372, TAC-64373, TAC-64374, NUDOCS 8709020085 | |
| Download: ML20237G068 (15) | |
Text
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'o UNITED STATES
'g NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D. C. 20555
\\...../
l l
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 l
I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 137 License No. DPR-33 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated December 15, 1986, complies with the standards and I
requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission'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 Comission; 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.
l 1
1 prt DO K O P
N
, 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-33 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.137, are hereby incorporated in the license. The 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 60 days from the date of issuance.
FORTHENUCLEARREGULATORYgMMI ION John A.
wolinski, Assistant Director for Pr jects TVA Proj ts Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: August 26, 1987
ATTACHMENT TO LICENSE-AMENDMENT N0._137 FACILITY OPERATING LICENSF NO. DPR-33 DOCKET NO. 50-259 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3.6/4.6-9 3.6/4.6-9 3.6/4.6-10 3.6/4.6-10 i
i l
l l
L________
1 3.6/4.6 PRIMARY SYSTEM BOUNDARY SURVEILLANCE REQUIREMENTS LIMITING CONDITIONS FOR OPERATION 4.6.C.
Coolant Leakage 3.6.C.
Coolant Leakage 1.
Reactor. coolant
- 1. a.
Any time irradiated system leakage shall fuel is in the reactor vessel and be checked by the sump and air sampling reactor coolant system and recorded temperature is above at least once per 212*F, reactor coolant 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
leakage into the primary containment I
from unidentified sources' shall not exceed 5 gps. In addition, the total reactor coolant system leakage into the primary containment shall not exceed 25 spm.
b.
Anytime the reactor is in RUN mode, reactor coolant leakage into the primary containment from unidentified sources shall not increase by more than 2 spm averaged over any 24-hour period in which the reactor is in the RUN mode except as defined in 3.6.C.I.c below, c.
During the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the RUN mode following i
STARTUP, an increase in reactor coolant leakage into the primary containment of >2 spa is acceptable as long as the requirements l
of 3.6.C.1.a are met.
j I
3.6/4.6-9 AMENDMENT NO. 137 BFN Unit 1 s
4
i, s
i I
\\
l-s' 3.6/4.6 PRIMARY SYSTEM BOUNDARY LIMITINGCONDITINNS,FOROPERATION
. SURVEILLANCE REQUIREMENTS
~~i i 4.,6. C Coolant Leakage 3.6.C Coolant Lealage I
i
- 2. With the air sampling 2.
Both the sump rod air sampling system IMOPERABLE, grab
<r systemsshalltrp0PERABLEdurigg reactor power oparation. From' samples shall be obtained and etter the date that one of and renalyzed at least onco I
these systems is made or found every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
to be INOPERABLE'for any reason, reactor power operation is I
permissible only during the succeeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the sump system or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for the air sampling system.
l l
The air snapling system may be removed from service for a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for calibration, function testing, and maintenance without j
providing a temporary j
monitor.
l 3.
If the condition in 1 or 2 above cannot be met, an orderly I
shutdown shall be initiated and the reactor shall be shutdown in the Cold Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l 3.6.D.
Relief Valves 4.6.D.
Relief Valves l
1.
When more than one relief valves 1.
Approximately one-half of I
are known to be f ailed, an all relief valves shall orderly shutdown shall be be bench-checked or initiated and the reactor replaced with a j
depressurized to less than 105 bench-checked valve l
psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, each operating cycle.
-j All 13 valves will have been checked or replaced upon the completion of every second cycle.
2.
Once during each l
operating cycle, each j
relief-valve shall be l
manually opened until l
l thermocouple and I
acoustic monitors i
downstream of the valve indicate steam is flowing from the valve.
l 3.6/4.6-10 I
h!ft1 i
Amendment No. 137 l
e
- pa uoyg'o,7 UNITED STATES
'^
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
%,...../
1 i
1 l
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT ?
)
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.133 License No. DPR-52 i
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated December 15, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR 4
Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 I
conducted in compliance with the'Comission's regulations; i
I D.
The issuance of this amendment will not be inimical to the common i
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 dpplicable requirements have been satisfied.
. )
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-52 is hereby i
amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 133, are hereby incorporated in the license. The 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 60 days from the date of issuance.
FOR THE NUCLEAR REGULATOR COMilSSION
-k
- h,
j John
. Zwolinski, Assistant Director for. Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: August 26, 1987
)
o ATTACHMENT TO LICENSE AMENDMENT N0.133 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3.6/4.6-9 3.6/4.6-9 3.6/4.6-10 3.6/4.6-10 4
- - ----- A
l
~
3.6/4.6 PRIMARY SYSTEN BOUNDARY LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.C.
Coolant Leakage-4.6.C.
Coolant Leakage
- 1. a.
Any time irradiated 1.
Reactor coolant fuel is in tho' system leakage shall reactor vessel and be checked by the reactor coolant sump and air sampling temperature is above system and recorded 212*F, reactor coolant at least once per leakage into the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
primary containment from unidentified sources shall not exceed 5 spa.
In addition, the total reactor coolant system leakage into the primary containment shall not exceed 25 spm.
b.
Anytime the reactor is in RUN mode, reactor coolant l
1eakage into the primary containment from unidentified sources shall not increase by more than 2 gpm averaged over any 24-hour period in which the reactor is in the RUN mode except as defined in 3.6.C.1.c below.
l c.
During the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the RUN mode following i
STARTUP, an increase in i
I reactor coolant leakage into the primary containment of >2 spa is acceptable as long as the requirements of 3.6.C.I.a are met.
l BFN 3.6/4.6-9 AMEN 0 MENT NO. 133
. Unit 2
3.6/4.6 PRIMARY SYSTEM BOUNDARY LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.C Coolant Leakage 4.6.C Coolant Leakage 2.
Both the sump and air sampling
- 2. With the air sampling systems shall be OPERABLE during system INOPERABLE, grab reactor power operation. From samples shall be obtained and after the date that one of and analyzed at least once these systems is made or found every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
to be INOPERABLE for any reason, reactor power operation is permissible only during the succeeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the sump system or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for the air h
sampling system.
The air sampling system may be removed from service for a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for calibration, function testing, and maintenance without providing a temporary monitor.
3.
If the condition in 1 or 2 above cannot be met, an orderly shutdown shall be initiated and the reactor shall be shutdown in the Cold Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.6.D.
Relief Valves 4.6.D.
Relief Valves 1.
When more than one relief valves 1.
Approximately one-half of are known to be failed, an all relief valves shall orderly shutdown shall be be bench-checked or initiated and the reactor replaced with a depressurized to less than 105 bench-checked valve psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
each operating cycle.
All 13 valves will have been checked or replaced upon the completion of every second cycle.
2.
Once during each operating cycle, each relief valve shall be manually opened until thermocouple and acoustic monitors downstream of the valve indicate steam is flowing from the valve.
3.6/4.6-10 AMENDMENT NO. 133 gy
[
o,,
NUCLEAR REGULATORY COMMISSION UNITED STATES y
g WASHINGTON, D. C. 20$55 r,,
- y
- s a
%> +... + /
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No,108 License No. OPR-68 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated December 15, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission'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
' Comission; 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 comon 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.
~
. I I
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment 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.108, are hereby incorporated in the license. The 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 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION O
l
"(
'(>
John
. Zwolinski, Assistant Director for Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications j
Date of Issuance: August 26, 1987 i
l 4
ATTACHMENT TO LICENSE AMENDMENT N0. 108 FACILITY OPERATING LICENSE N0. DPR-68 DOCKET NO. 50-296 Revise the Appendix A Technical Specifications by removing the pages f
identified below and inserting the enclosed pages.. The revised pages l
are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3.6/4.6-9 3.6/4.6-9 3.6/4.6-10 3.6/4.6-10
)
)
9 i
)
l I
1 l
i
i l
J 3.6/4.6 PRIMARY SYSTEN BOUNDARY LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS j
3.6.C.
Coolant Leakage 4.6.C.
Coolant Leakage
- 1. a.
Any time irradiated 1.
Reactor coolant Iuel is in thr4 system leakage shall reactor vessel and be checked by the reactor coolant sump and air sampling temperature is above system and recorded 212*F, reactor coolant at least once per leakage into the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
primary containment from unidentified sources shall not exceed 5 spm. In addition, the total reactor coolant system leakage into the primary containment i
1 shall not exceed 25 spm.
b.
Anytime the reactor is in i
RUN mode, reactor coolant leakage into the primary containment from unidentified sources shall not increase by more than 2 spm averaged over any 24-hour period in which the reactor is in the RUN mode except as defined in 3.6.C.1.c below, c.
During the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the RUN mode following STARTUP, an increase in reactor coolant leakage into the primary containment of >2 spm la acceptable as long as the requirements of 3.6.C.1.a are met.
3.6/4.6-9 AMEN 0 MENT NO. 108 BFN Unit 3
3.6/4.6 PRIMARY SYSTEM BOUNDARY LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.C Coolant Leakage 4.6.C Coolant Leakage 2.
Both the sump and air sampling
- 2. With the air sampling systems shall be OPERABLE during system INOPERABLE, grab reactor power operation.
From samples shall be obtained and after the date that one of and analyzed at least once these systems is made or found every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, to be INOPERABLE for any reason, reactor power operation is permissible only during the succeeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the sump system or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for the air sampling system.
The air sampling system may be removed from service for a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for calibration, function testing, and maintenance without providing a temporary monitor.
3.
If the condition in 1 or 2 above cannot be met, an orderly shutdown shall bo initiated and the reactor shall be shutdown in the Cold Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.6.D.
Relief Valves 4.6.D.
Relief Valves 1.
When more than one relief valves 1.
Approximately one-half of are known to be f ailed, an all relief valves shall orderly shutdown shall be be bench-checked or initiated and the reactor replaced with a depressurized to less than 105 bench-checked valve psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
each operating cycle.
All 13 valves will have been checked or replaced upon the completion of every second cycle.
2.
Once during each operating cycle, each relief valve shall be manually opened until thermocouple and acoustic monitors downstream of the valve indicate steam is flowing from the valve.
BFu 3.6/4.6-10 AMENDMENT NO. 108 Unit 3
,