ML20247K517
| ML20247K517 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/23/1988 |
| From: | Black S NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20247K486 | List: |
| References | |
| TAC-00101, TAC-00102, TAC-00103, TAC-101, TAC-102, TAC-103, NUDOCS 8909210188 | |
| Download: ML20247K517 (18) | |
Text
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NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555 5
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FEPRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY CPERATING LICENSE Anerdment No.155 License No. DPR-33 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 13, 1988, 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 orovisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities autht.'4 zed 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 w411 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.
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2-2.
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 tperating 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.155, 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 daya, from'the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION d
4 Lex <_.
Suzanne Black, Assistant Director for Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: September 23, 1988 e
. ~.
' ATTACHMENT TO LICENSE AMENDMENT NO.155
, FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 j
Revise the Appendix A Technical Specifications'by removing the pages identified below and insertirg the enclosed pages. The. revised pages are identified by the captioned' amendment number and contain marginal lines indicating.the area of change. Overleaf'pages* are provided to l'
maintain' document completeness.
1 8
PEMOVE INSERT 3.2/4.2-18 3.2/4.2-18 3.2/4.2-19 3.2/4.2-19 3.2/4.2-46 3.2/4.2-46 3.2/4.2-47 3.2/4.2-47 1
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NOTES FO'R TABLE 3.7_,3 Key: 0 = Open
.C = Closed SC =-Stays Closed l
GC = Goes Closed Note: Isolation groupings are as fo-llows:
Group 1: The valves in Group 1 are actuated by any one of the following conditions:
1.
Reactor Vessel Low Water Level'(378")
2.
Main Steamline High Radiation 3.
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Main Steamline Space High Temperature l
L 5.
Main Steamline Low Pressure Group 2: The valves in Group 2 are actuated by any of the following conditions:
1 1.
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2.
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Group 3: The valves in Group 3 are actuated by any of the following conditions:
1.
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2.
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Reactor Water Cleanup System High Drain Temperature Group 4: The valves in Group 4 are actuated by any of the following conditions:
1.
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HPCI Steamline Low Pressure 4
HPCI Turbine Exhaust Diaphragm High Pressure Group 5: The valves in Group 5 are actuated by any of the following condition:
1.
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RCIC Steamline Low Pressure 4
RCIC Turbine Exhaust Diaphragm High Pressure Group 6: The valves in Group 6 are actuated by any of the following conditions:
1.
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2.
High Drywell Pressure 3.
Reactor Building Ventilation High Radiation Amendment No. 155 BFN 3.7/4.7-30 Unit 1
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UNITED STATES t
18
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3 NUCLEAR REGULATORY COMMISSION ~
w AsHINGTON. D. C. 20555
- \\....,.,d TENNESSEE VALLEY AUTHORITY DOCVET NO. 50-260 BROWNS FERRY MUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 151 License No. DPP-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 13, 1988, complies with the standards and requirements of the Atomic Energy Act of 1054, 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 ths 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 anendment will not be inimical to the common defense and security or to the health and safety o' the public; and E.
The issuance of this amendment is in accordance with 10 CFP Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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2-
,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-52 is hereby amended to read as follows:
(2) Technical Specifications The. Technical Specificaticos contained in Appendices A and B, as revised through Amendment No.151, are hereby incorporated in the license. The. licensee shall operate the facility in accordance Lith 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 by -,cc /N4 cA Suzanne Black, Assistant Director for Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: Septenber 23, 1938 l
l l
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1 I-I l
ATTACFMENT TO LICENSE AMENDMENT NO.151
. FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Revise the Appendix A Technical Specifications by remcving 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. Overleaf pages* are provided to maintain document completeness.
REMOVE INSER1 3.2/4.2-18 3.2/4.2-18 3.2/4.2-19 3.2/4.2-19 3.2/4.2-46 3.2/4.2-46 3.2/4.2-47 3.2/4.2-47 3.7/4.7-30 3.7/4.7-30 l
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s; NOTES FOR TABLE 3.7_._A Key:
0 = Open C = Closed SC = Stays Closed GC = Goes Closed Note:
Isolation groupings are as follows:
Group 1: The valves in Group 1 are actuated by any one of the following conditions:
1.
Reactor Vessel Low Water Level (378")
2.
Main Steamline High Radiation 3.
Main Steamline High Flow 4
Main Steamline Space High Temperature 5.
Main Steamline Low Pressure Group 2: The valves in Group 2 are actuated by any of the following conditions:
1.
Reactor Vessel Low Water Level (538")
2.
High Drywell Pressure Group 3: The valves in Group 3 are actuated by any of the following conditions:
1.
Reactor Low Water Level (538")
2.
Reactor Water Cleanup System High Temperature 3.
Reactor Water Cleanup System High Drain Temperature Group 4: The valves in Group 4 are actuated by any of the following conditions:
1.
HPCI.Steamline Space High Temperature 2.
HPCI Steamline High Flow 3.
HPCI Steamline Low Pressure 4
HPCI Turbine Exhaust Diaphragm High Pressure Group 5: The valves in Group 5 are actuated by any of the following condition:
1.
RCIC Steamline Space High Temperature 2.
RCIC Steamline High Flow 3.
RCIC Steamline Low Pressure 4.
RCIC Turbine Exhaust Diaphragm High Pressure l
Group 6: The valves in Group 6 are actuated by any of the following conditions:
1.
Reactor Vessel Low Water Level (538")
2.
High Drywell Pressure 3.
Reactor Building Ventilation Hig' Radiation I
BFN 3.7/4.7-30 Amendment No. 151 I
Unit 2 l
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555 f
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TENNESSEE ~ VALLEY AUTHORITY DOCKET NO. 50-296 BPCWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 126
~
License No. DPR-68 1.
The Nuclear Regulatory Cnmission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 13, 1988, 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 cenformity 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 amerdment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Ccmission'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 L
been satisfied.
_._____.______._.___-___-___________.___._._____.__._.._________m_
u.
2.
Accordingly, the license is amended by changes to the Technical Specifications as. indicated in the attachuent to this literse amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-68 9 hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as-revised through Amendment No.126, are hereby incorporated in the.
license. The licensee shal1~ operate the facility in accordance with the Technical Specifications.
-This license amendment is effective as of its date of. issuance and shall 3.
be implemented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION CIb
(
i vt w Suzanne lack, Assistant Director for Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: September 23, 1983 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 126 FACILITY' OPERATING-LICENSE NO.' DPR.
DOCKET NO. 50-296-Revise the Apperdix A Technical Specifications.by removing the pages identified below and insertine the enclosed pages..The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
PEMOVE INSERT 3.2/4.2-18 3.2/4.2-18 3.2/4.2-19 3.2/4.2-19 3.2/4.2-45 3.2/4.2-45 3.2/4.2-46 3.2/4.2-46 3.7/4.7-29 3.7/4.7-29 3.7/4.7-30 3.7/4.7-30*
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i NOTES'FOR TABLE 3.7.A Key:
0 = Open C = Closed o
SC = Stays Closed GC = Goes Closed
. Note:
IsolationLgroupings are as follows:
Group 1: The valves in Group 1 are actuated by any of the following conditions:
a 1.
Reactor Vessel Low Water Level (378")
2.
Main Steamline High Radiation l
3.
Main Steamline High Flow 4
Main Steamline Space High Temperature 5.
Main Steamline Low Pressure l
Group 2: The valves in Group 2 are actuated by any of the following l
conditions:
1.
Reactor Vessel Low Water Level (538")
2.
High Drywell Pressure Group 3: The valves in Group 3 are actuated by any of the following I
conditions:
)
1.
Reactor Low Water Level (538")
2.
Reactor Water Cleanup System High Temperature
.3.
Reactor Water Cleanup System High Drain Temperature l
Group 4: The valves in Grcup 4 are actuated by any of the following conditions:
1.
HPCI Steamline Space High Temperature 2.
HPCI Steamline High Flow 3.
HPCI Steamline Low Pressure
-4.
HPCI Turbine Exhaust Diaphragm High Pressure Group 5: The valves in Group 5 are actuated by any of the followinc j
conditionst 1.
RCIC Steamline Space High Temperature 2.
RCIC Steamline High Flow l
3.
RCIC Steamline Low Pressure 4.
RCIC Turbine Exhaust Diaphragm High Pressure 1
The valves in Group 6 are actuated by any of the following Group 6:
conditions:
1.
Reactor Vessel Low Water Level (538")
2.
High Drywell Pressure 3.
Reactor Building Ventilation High Radiation 3.7/4.7-29 Amendment 10. 126 BFN Unit 3
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