ML18036B080
| ML18036B080 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/19/1992 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18036B081 | List: |
| References | |
| DPR-33-A-188, DPR-52-A-203, DPR-68-A-160, GL-89-014 NUDOCS 9212040364 | |
| Download: ML18036B080 (22) | |
Text
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UNITEDSTATES t NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
188 License No.
DPR-33 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated April 1, 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 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.
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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:
3.
(2) Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 188, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 19, 1992
- '.:,.)
~.J,i....
Frederick J.
Heb on, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
UNIT 1" EFFECTIVE PAGE LIST TECHNICAL SPECIFICATION 311 RENOVE INSERT 1.0-11 1.0-12 1.0-11 1.0-12*
- Denotes overleaf page
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owned, leased, or otherwise controlled by TVA.
s t
ea Any area at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for industrial, commercial, institutional, or recreational purposes.
Dose u va e t
The DOSE EQUIVALENT I-131 shall be the concentration of I-131 (in pCi/gm) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.
The thyroid dose conversion factor used for this calculation shall be those listed in Table III of TID-14844 "Calculation of Distance Factors for Power and Test Reactor Si.tes".
Gaseous Waste reat e
S ste The charcoal adsorber vessels installed on the discharge of the steam jet air effector to provide delay to a unit's offgas activity prior to release.
embe s of t e Public Shall include all individuals who by virtue of their occupational status have no formal association with the plant.
This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions.
This category shall ~o include non-employees such as vending machine servicemen or postmen who, as part of their formal gob function, occasionally enter restricted areas.
LL.
the OPERATIONAL CONDITIONS or other conditions specified for individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements.
Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval. It is not intended that this (extension) provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages.
Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and'OPERABILITY requirements for a limiting condition for operation and associated action statements unless otherwise required by these specifications.
Surveillance Requirements do not have to be performed on inoperable equipment.
BFN Unit 1 1.0-11 Amendment 188
MM.
Surveillance Requirements for ASME Section XI Pump and Valve Program Surveillance Requirements for Inservice Testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:
l.
Inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g),
except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55(g)(6)(i).
2.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these technical specifications:
ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for inservice
'v't'equired frequencies for performing inservice Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 276 days At least'once per 366 days 3.
The provisions of Specification 1.0.LL are applicable to the above required frequencies for performing inservice testing activities.
4.
Performance of the above inservice testing activities shall be in addition to other specified surveillance requirements.
5.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any technical specification.
6.
The inservice inspection program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the staff positions on schedule,
- methods, personnel, and sample expansion included in this generic letter.
BFN Unit 1 1.0-12 ew~mg~. ><<
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t UNITEDSTATES t NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT UNIT 2 AMENDMENT TO FACILITY OPERATING LICENS Amendment No. 203 License No.
DPR-52 The Nuclear Regulatory.Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated April 1,
- 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 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 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:
3.
(2) Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 203, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 19, 1992
- ...,),..,)
<~ '.J.!,
Frederick J.
Hebdon, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
UNIT 2.
EFFECTIVE PAGE LIST TECHNICAL SPECIFICATION 311 RENOVE INSERT 1.0-11 1.0-12 1.0-11 1.0-12*
- Denotes overleaf page
ONS (Cont'd)
GG.
owned; leased, or otherwise controlled by TVA.
e t cted r
Any area at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for industrial, commercial, institutional, or recreational purposes.
os uivalent I-The DOSE EQUIVALENT I-131 shall be the concentration of I-131 (in pCi/gm) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.
The thyroid dose conversion factor used for this calculation shall be those, listed in Table III of TID-14844 "Calculation of Distance Factors for Power and Test Reactor Sites".
Gaseous Wast eat e t S
The charcoal adsorber vessels installed on the discharge of the steam get air e)ector to provide delay to a unit's offgas activity prior to release.
Membe s
o the ub Shall include all individuals who by virtue of their occupational status have no formal association with the plant.
This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions.
Thi.s category shall ~ include non-employees such as vending machine servicemen or postmen who, as part of their formal gob function, occasionally enter restricted areas.
LL.
OPERATIONAL CONDITIONS or other conditions specified for individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements.
Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval. It is not intended that this (extension) provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages.
Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a limiting condition for operation and associated action statements unless otherwise required by these specifications.
Surveillance Requirements do not have to be performed on inoperable equipment.
BFN Unit 2 1.0-11 Amendment 203
t
~~ - Surveillance Requirements for Inservice Testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:
Inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section ZI of the ASME Boiler and Pressure Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g),
except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55(g)(6)(i).
2 ~
Surveillance intervals specified in Section ZI of the ASME Boiler and Pressure Vessel'ode and applicable Addenda for the inservice testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these technical'pecifications:
ASME 'Boiler and Pressure Vessel Code and applicable Addenda terminology for inservice v't Required frequencies for performing inservice v
Meekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually At least once per 7 days At least once per 31 days At least once per 92 days
'At least once per 184 days At least once per 276 days At least once per 366 days 3.
The provisions of Specification 1.0.LL are applicable to the above required frequencies for performing inservice testing activities.
4.
Performance of the above inservice testing, activities shall be in addition to other specified surveillance requirements.
5.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any technical specification.
6.
The inservice inspection program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the staff positions on schedule,
- methods, personnel, and sample expansion included in this generic letter.
BFN Unit 2
- 1. 0-12
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t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
160 License No.
DPR-68 The Nuclear Regulatory Commission (the Commission) has found that:
A.
C
~
The application for amendment by Tennessee Valley Authority (the licensee) dated April 1,
- 1992, complies wi'th 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; 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; 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.
0 Cl
2.
3.
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.
- 160, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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
) ~::.i,.)
Frederick J.
Hebdon, 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:
October 19, i992
l5
UNIT 3 EFFECTIVE PAGE LIST TECHNICAL. SPECIFICATION 311 REMOVE INSERT 1.0-11 1.0-12 1.0-11 1.0-12*
+Denotes overleaf page
1.0 IEHluXMR (
GG.
owned, leased, or otherwise controlled by TVA.
st e
Any area at or beyond the site boundary to vhich access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for industrial, commercial, institutional, or recreational purposes.
os u va ent
The DOSE EQUIVALEHT I-131 shall be the concentration of I-131 (in pCi/gm) vhich alone vould produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.
The thyroid dose conversion factor used for this calculation shall be those listed in Table III of TID-14844 "Calculation of Distance Factors for Power and Test Reactor Sites".
G ou e
me S
t The charcoal adsorber vessels installed on the discharge of the steam jet air ejector to provide delay to a unit's offgas activity prior to release.
e be s o t e ub ic Shall include all individuals vho by virtue of their occupational status have no formal association with the plant.
This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated vith plant functions.
This category shall XLoO include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter restricted areas.
LL.
Ill OPERATIOHAL COHDITIOHS or other conditions. specified for individual limiting conditions for operation unless otherwt,se stated in an individual Surveillance Requirements.
Each Surveillance Requirement shall be performed vithin. the specified surveillance interval vith a maximum allovable extension not to exceed 25 percent of the specified surveillance interval. It is not intended that this (extension) provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages.
Performance of a Surveillance Requirement vithin the specified time interval shall constitute compliance and OPERABILITY requirements for a limiting condition for operation and associated. action statements unless otherwise required by these specifications.
Surveillance Requirements do not have to be performed on inoperable equipment.
BFH Unit 3 1.0-11 Amendment 160
MM.
Surveillance Requirements for ASME Section KI Pump and Valve Program Surveillance Requirements for Inservice Testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:
1.
Inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g),
except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
2.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these technical specifications:
ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for inservice t t Required frequencies for performing inservice Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually At least once per 7 days At least'once per 31 days At least once per 92 days At least once per 184 days At least once per 276 days At least once per 366 days 3.
The provisions of Specification 1.0.LL are applicable to the above required frequencies for performing inservice testing activities.
4.
Performance of the above inservice testing activities shall be in addition to other specified surveillance requirements.
5.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any technical specification.
6.
The inservice inspection program for piping identifed in NRC Generic Letter 88-01 shall be performed in accordance with the staff positions on schedule,
- methods, personnel, and sample expansion included in this generic letter.
BFN Unit 3 1.0-12 AMENDMENTgg. g Q P