ML18029A886
| ML18029A886 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/19/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Tennessee Valley Authority |
| Shared Package | |
| ML18029A887 | List: |
| References | |
| DPR-33-A-122, DPR-52-A-117, DPR-68-A-093 NUDOCS 8509300440 | |
| Download: ML18029A886 (17) | |
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.
122 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 June 26, 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-33 is hereby amended to read as follows:
8509300440 850919 PDR nDaCX OSOOOa59, P
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(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
122, 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 the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Domenic B. Vassallo, Chief Operating Reactors Branch P2 Division of Licensing Date of Issuance:
September 19,. 1985
ATTACHMENT TO LICENSE AMENDMENT NO.
122 FACILITY OPERATING LICENSE NO.
DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
4A, 4B 2.
The marginal lines on these pages denote the area being changed.
P.
Seconda Containment Inte rit 1.
Secondary containment integrity means that the reactor building is intact and the following conditions are met:
a) At least one door in each access opening to the turbine building, control bay and out-of-doors is closed.
b) The standby gas treatment system is operable and can maintain 0.25 inches of water negative pressure in those areas where secondary containment integrity is stated to exist.
c) All secondary containment penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by an operable secondary containment automatic isolation system, or 2.
Closed by at least one secondary containment automatic iso-lation valve deactivated in the isolated position.
2.
Reactor zone secondary containment integrity means the unit react-or building is intact and the following conditions are met:
a) At least one door between any opening to the turbine building, control bay and out-of-doors is closed.
b) The standby gas treatment system is operable and can maintain 0.25 inches water negative pressure on the unit zone.
c) All the unit reactor building ventilation system penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by an operable reactor building ventilation system automatic isolation system, or 2.
Closed by at least one reactor building ventilation system automatic isolation valve deactivated in the isolated pos-ition.
If it is desirable for operational considerations, a reactor zone may be isolated from the other reactor zones and the refuel zone by maintaining at least one closed door in each common passageway be-tween zones.* Reactor zone safety related features are not compro-mised by openings between adjacent units or refuel zone, unless it is desired to isolate a given zone.
To effectively control zone isolation, all accesses to the affected zone will be locked or guarded to prevent uncontrol-led"'passage to'he'ffected zones.
4A Amendment Nos.
, 122
3.
Refuel zone secondary containment integrity means the refuel zone is intact and the following conditions are met:
a) At least one door in each access opening to the out-of-doors is closed.
b) The standby gas treatment system is operable and can maintain 0.25 inches water negative pressure on the refuel zone.
c) All refuel zone ventilation system penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by an operable refuel zone ventilation system automatic isolation system, or 2.
Closed by at least one refuel zone ventilation system auto-matic isolation valve deactivated in the isolated position.
If it is desirable for operational considerations, the refuel zone may be isolated from the reactor zones by maintaining all hatches in place between the refuel floor and reactor zones and at least one closed door in each access between the refuel zone and the reactor building.*
Refuel zone safety related features are not compromised by openings between the reactor building unless it is desired to isolate a given zone.
To effectively control zone isolation, all accesses to the affected zone will be locked or guarded to prevent uncontrolled passage to the unaffected zones.
4B
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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. 117 License No.
DPR-52 1.
The Nuclear Regulatory Comaission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 26, 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 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; H
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.
117, 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 the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Domenic B. Vassallo, Chief Operating Reactors Branch 5'2 Division of Licensing Date of Issuance:
September 19,:1985.
ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO.
DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
4A, 48 2.
The marginal lines on these pages denote the area being changed.
Seconda Containment Inte rit 1.
Secondary containment integrity means that the reactor building is intact and the following conditions are met:
a) At least one door in each access opening to the turbine building, control bay and out-of-doors is closed.
b) The standby gas treatment system is operable and can maintain 0.25 inches of water negative pressure in those areas where secondary containment integrity is stated to exist.
c) All secondary containment penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by an operable secondary containment automatic isolation system, or 2.
Closed by at least one secondary containment automatic iso-lation valve deactivated in the isolated position.
2.
Reactor zone secondary containment integrity means the unit react-or building is intact and the following conditions are met:
a) At least one door between any opening to the turbine building, control bay and out-of-doors is closed.
b) The standby gas treatment system is operable and can maintain 0.25 inches water negative pressure on the unit zone.
c) All the unit reactor building ventilation system penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by an operable reactor building ventilation system automatic isolation system, or 2.
Closed by at least one reactor building ventilation system automatic isolation valve deactivated in the isolated pos-ition.
Ifit is desirable for operational considerations, a reactor zone may be isolated from the other reactor zones and the refuel zone by maintaining at least one closed door in each common passageway be-tween zones.* Reactor zone safety related features are not compro-mised by openings between adjacent units or refuel zone, unless it is desired to isolate a given zone.
To effectively control zone isolation, all accesses to the affected zone will be locked or guarded to prevent uncontrol-led passage to the* affected'ones.
4A Amendment Nos.
9, 117
3.
Refuel zone secondary containment integrity means the refuel zone is intact and the following conditions are met:
a) At least one door in each access opening to the out-of-doors is closed.
b) The standby gas treatment system is operable and can maintain 0.25 inches water negative pressure on the refuel zone.
c) All refuel zone ventilation system penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by an operable refuel zone ventilation system automatic isolation system, or 2.
Closed by at least one refuel zone ventilation system auto-matic isolation valve deactivated in the isolated position.
If it is desirable for operational considerations, the refuel zone may be isolated from the reactor zones by maintaining all hatches in place between the refuel floor and reactor zones and at least one closed door in each access between the refuel zone and the reactor building.*
Refuel zone safety related features are not compromised by openings between the reactor building unless it is desired to isolate a given zone.
To effectively control zone isolation, all accesses to the affected zone will be locked or guarded to prevent uncontrolled passage to the unaffected zones.
4s Amendment Nos.
9, 117
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A UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
93 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 June 26, 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 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 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.
93, 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 the date of issuance.
FOR THE NUCLEAR REGULATORY COMt1ISSION
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.
93 FACILITY OPERATING LICENSE NO.
DPR-68 DOCKET NO. 50-296 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
4A, 4B 2.
The marginal lines on these pages denote the area being changed.
P.
Seconda Containment Inte rit 1.
Secondary containment integrity means that the reactor building is intact and the following conditions are met:
a) At least one door in each access opening to the turbine building, control bay and out-of-doors is closed.
b) The standby gas treatment system is operable and can maintain 0.25 inches of water negative pressure in those areas where secondary containment integrity is stated to exist.
c) All secondary containment penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by an operable secondary containment automatic isolation system, or 2.
Closed by at 1east one secondary containment automatic iso-lation valve deactivated in the isolated position.
2.
Reactor zone secondary containment integrity means the unit react-or building is intact and the following conditions are met:
a) At least one door between any opening to the turbine building, control bay and out-of-doors is closed.
b) The standby gas treatment system is operable and can maintain 0.25 inches water negative pressure on the unit zone.
c) All the unit reactor building ventilation system penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by an operable reactor building ventilation system automatic isolation system, or 2.
Closed by at least one reactor building ventilation system automatic isolation valve deactivated in the isolated pos-ition.
Ifit is desirable for operational considerations, a reactor zone may be isolated from the other reactor zones and the refuel zone by maintaining at least one closed door in each common passageway be-tween zones.* Reactor zone safety related features are not compro-mised by openings between ad)acent units or refuel zone, unless it is desired to isolate a given zone.
To effectively control zone iso1ation, all accesses to the affected zone will be locked or guarded to prevent uncontrol-led passage to the'ffected'zones.
4A Amendment Nos.,
93
3.
Refuel zone secondary containment integrity means the refuel zone is intact and the following conditions are met:
a) At least one door in each access opening to the out-of-doors is closed.
b) The standby gas treatment system is operable and can maintain 0.25 inches water negative pressure on the refuel zone.
c) All refuel zone ventilation system penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by an operable refuel zone ventilation system automatic isolation system, or 2.
Closed by at least one refuel zone ventilation system auto-matic isolation valve deactivated in the isolated position.
If it is desirable for operational considerations, the refuel zone may be isolated from the reactor zones by maintaining all hatches in place between the refuel floor and reactor zones and at least one closed door in each access between the refuel zone and the reactor building.*
Refuel zone safety related features are not compromised by openings between the reactor building unless it is desired to isolate a given zone.
To effectively control zone isolation, all accesses to the affected zone will be locked or guarded to prevent uncontrolled passage to the unaffected zones.
4B Amendment Non~,
93