ML18029A892
| ML18029A892 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/19/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Tennessee Valley Authority |
| Shared Package | |
| ML18029A893 | List: |
| References | |
| DPR-33-A-123, DPR-52-A-118, DPR-68-A-094 NUDOCS 8509300487 | |
| Download: ML18029A892 (18) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
123 License No. DPR-33 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated September 21,
- 1984, as supplemented June 6, 1985, 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.
C.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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.
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:
P
(2)
Technical S ecifications The Technical Specifications contained in Appendices'A and B, as revised through Amendment No.
123, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 90 days from the date of issuance.
FOR THE N CLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Domenic B. Vassallo, Chief Operating Reactors Branch f/2 Division of Licensing Date of Issuance:
September 19, 1985
ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO.
DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:
1.
Remove pages 31 and 35 and replace with revised pages 31 and 35.
2.
The marginal lines on these pages denote the areas being changed.
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIR1DKNTS 3.1 REACTOR PROTECTION SYSTEM 4.1 REACTOR PROTECTION SYSTEM A licabilit A licabilit Applies to the instrumentation and associated devices which initiate a reactor scram.
Applies to the surveillance of the instrumentation and asso-ciated devices which initiate reactor scram.
Ob ective
~Ob ect1ve To assure the operability of the reactor protection system.
To specify the type and frequen-cy of surveillance to be applied to the protection instrumenta-tion.
S ecification S ecification A. When there is fuel in the ves-
- sel, the setpoints, minimum number of trip systems, and minimum number of instrument channels that must be operable for each position of the mode switch shall be as given in Table 3.1.A.
A. Instrumentation systems shall be functionally tested and calibrat-ed as indicated in Tables 4.1.A and 4.1.B respectively.
B. Two RPS power monitoring chan-nels for each inservice RPS MG sets or alternate source shall be operable.
- 1. With one RPS electric power monitoring channel for in-service RPS MG set or alt-ernate 'power supply inoper-able, restore the inoper-able channel to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove the associated RPS MG set or alternate power supply from service.
31 Amendment Nos.
1
, 123
NOTES FOR TABLE 3.1.A 1.
There shall be two operable or tripped trip systems for each function. If the minimum number of operable instrument channels per trip system cannot be met for one trip system, trip the inoperable channe1s or entire trip system within one hour, or, alternatively, take the be1ow listed action for that trip function. If the minimum number of operable instrument channe1s cannot be met by either trip
- system, the appropriate action listed below (refer to right-hand column of Table) shall be taken.
An inoperable channe1 need not be placed in the tripped condition where this would cause the trip funct-ion to occur.
In these
- cases, the inoperable channe1 shall be restored to operable status within two hours, or take the action listed below for that trip function.
A. Initiate insertion of operable rods and complete insertion of all operable rods within four hours.
In refue1ing mode, suspend all operations involving core alterations and fully insert all oper-able control rods within one hour.
B.
Reduce power level to IRM range and place mode switch in the Startup/Hot Standby position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Reduce turbine load and close main steam line isolation valves.
within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D.
Reduce power to less than 30X of rated.
2.
Scram discharge volume high bypass may be used in shutdown or refuel to bypass scram discharge volume scram with control rod block for reactor protection system reset.
3.
Bypassed if reactor pressure is less than 1055 psig and mode switch not in run.
4.
Bypassed when turbine first stage pressure is less than 154 psig.
5.
IRMs are bypassed when APRMs are onscale and the reactor mode switch is in the run position.
6.
The design permits closure of any two lines without a scram being initiated.
~
I 7.
When the reactor ie subcritical and the reactor water temperature is less than 212oP, only the following trip functions need to be operable:
A.
Mode switch in shutdown B.
Manual scram C.
High flux IRM D.
Scram discharge volume high leve1 E.
Not required to be operable when primary containment integrity is not required.
9.
Not required if all main steamlines are isolated.
35 Amendment Nos. Q, 123
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Q UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
License No.
DPR-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated September 21,
- 1984, as supplemented June 6,
- 1985, 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 regulation's 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.
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 amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
118, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Domenic B. Vassallo, Chief Operating Reactors Branch ¹2 Division of Licensing Date of Issuance:
September 19,, 1985
ATTACHMENT TO LICENSE AMENDMENT NO.
118 FACILITY OPERATING LICENSE NO.
DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:
1.
Remove pages 31 and 35 and replace with revised pages 31 and 35.
2.
The marginal lines on these pages denote the areas being changed.
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.1 REACTOR PROTECTION SYSTEM 4.1 REACTOR PROTECTION SYSTEM A licabilit Applies to the instrumentation and associated devices which initiate a reactor scram.
Applies to the surveillance of the instrumentation and asso-ciated devices which initiate reactor scram.
Ob ective Ob ective To assure the operability of the reactor protection system.
To specify the type and frequen-cy of surveillance to be applied to the protection instrumenta-tion.
S ecification S ecification A. When there is fuel in the ves-sel, the setpoints, minimum number of trip systems, and minimum number of instrument channels that must be operable for each position of the mode switch shall be as given in Table 3.1.A.
A. Instrumentation systems shall be functionally tested and calibrat-ed as indicated in Tables 4.1.A and 4.1.B respectively.
31 Amendment Nos.
4, 118
0 NOTES FOR TABLE 3.1.A There shall be two operable or tripped trip systems for each function. If the minimum number of operable instrument channels per trip syst: em cannot be met for one trip system, trip the inoperable channels or entire trip system within one hour, or, alternatively, take the below listed action for that trip function. If the minimum number of opeiable instrument channels cannot be met by either trip
- system, the appropriate action listed below (refer to right-hand column of Table) shall be taken.
An inoperable channel need not be placed in the tripped condition where this would cause the trip funct-ion to occur.
In these
- cases, the inoperable channel shall be restored to operable status within two hours, or take the action listed below for that trip function.
A. Initiate insertion of operable rods and complete insertion of all operable rods within four hours.
In refueling mode, suspend all operations involving core alterations and fully insert all oper-able control rods within one hour.
B.
Reduce power level to IRM range and place mode switch in the Startup/Hot Standby position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Reduce turbine load and close main steam line isolation valves within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D.
Reduce power to less than 30X of rated.
20 Scram discharge volume high bypass may be used in shutdown or refuel to bypass scram discharge volume scram with control rod block for reactor protection system reset.
30 Bypassed if reactor pressure is less than 1055 psig and mode switch not in run.
4 Bypassed when turbine first stage pressure is less than 154 psig.
IRMs are bypassed when APRMs are onscale and the reactor mode switch is in the run position.
6.
The design permits closure of any two lines without a scram being initiated.
7 ~
When the reactor is subcritical and the reactor water temperature is less than 212oP, only the following trip functions need to be operable:
A.
Mode switch in shutdown B.
Manual scram C.
High flux IRM D.
Scram discharge volume high level E.
Not required to be operable when primary containment integrity is not required.
9.
Not required if all main steamlines are isolated.
35 Amendment Nos. Nl, 118
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0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROMNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
94 License No.
DPR-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated September 21,
- 1984, as supplemented June 6, 1985, 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 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.
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 S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No.
94, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Domenic B. Vassallo, Chief Operating Reactors Branch ¹2 Division of Licensing Date of Issuance:
September 19, 1985
ATTACHMENT TO LICENSE AMENDMENT NO.
94 FACILITY OPERATING LICENSE NO.
DPR-68 DOCKET NO. 50-296 Revise Appendix A as follows:
1.
Remove pages 31 and 34 and replace with revised pages 31 and 34.
2.
The marginal lines on these pages denote the areas being changed.
LIMITING CONDITIONS FOR OPERATION 3.1 REACTOR PROTECTION SYSTEM SURVEILLANCE RE UIREMENTS 4.1 REACTOR PROTECTION SYSTEM A licabilit A licabilit Applies to the instrumentation and associated devices which initiate a reactor scram.
Applies to the surveillance of the instrumentation and asso-ciated devices which initiate reactor scram.
~Ob ective To assure the operability of the reactor protection system.
~Ob ective To specify the type and frequen-cy of surveillance to be applied to the protection instrumenta-tion.
S ecification S ecification A. When there is fuel in the ves-sel, the setpoints, minimum number of trip systems, and minimum number of instrument channels that must be operable for each position of the mode switch shall be as given in Table 3.1.A.
A. Instrumentation systems shall be functionally tested and calibrat-ed as indicated in Tables 4.1.A and 4.1eB respectively.
31 Amendment Nos.
94
NOTES FOR TABLE 3.1.A There shall be two operable or tripped trip systems for each function. If the minimum number of operable instrument channels per trip system cannot be met for one trip system, trip the inoperable channels or entire trip system within one hour, or, alternatively, take the below listed action for that trip function. If the minimum number of operable instrument channels cannot be met by either trip
- system, the appropriate action listed below (refer to right-hand column of Table) shall be taken.
An inoperable channel need not be placed in the tripped condition where this would cause the trip funct-ion to occur.
In these
- cases, the inoperable channel shall be restored to operable status within two hours, or take the action listed below for that trip function.
A.
Initiate insertion of operable rods and complete insertion of all operable rods within four hours.
In refueling mode, suspend all operations involving core alterations and fully insert all oper-able control rods within one hour.
B.
Reduce power level to IRM range and place mode switch in the Startup/Hot Standby position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Reduce turbine load and close main steam line isolation valves within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D.
Reduce power to less than 30X of rated.
2 ~
Scram discharge volume high bypass may be used in shutdown or refuel to bypass scram discharge volume scram with control rod block for reactor protection system reset.
3 ~
Deleted 4,
Bypassed when turbine first stage pressure is less than 154 psig.
IRMs are bypassed when APRMs are onscale and the reactor mode switch is in the run position.
6.
The design permits closure of any two lines without a scram being initiated.
7 ~
When the reactor is subcritical and the reactor water temperature is less than 212oF, only the following trip functions need to be operable:
8.
9.
A. Mode switch in shutdown B. Manual Scram C. High flux IRM D. Scram discharge volume high level E.
APRM 15X scram Not required to operable when primary containment integrity is not required.
Not required if all main steamlines are isolated.
10.
Not reauired to be operable when the reactor pressure vessel head is not bolted to the vessel.
The APRM downscale trip function is only active when the reactor mode switch is in run.
34, Amendment Nos. 78,
$g, 75, 94