ML18039A671
| ML18039A671 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/15/1999 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML18039A672 | List: |
| References | |
| NUDOCS 9901250330 | |
| Download: ML18039A671 (16) | |
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UNITED STATES NUCLEAR REGULATORY COlVlMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEYAUTHORITY DOCKET. NO. 50-260 BROWNS FERRY NUCLEAR PLANT UNIT2 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No. 257 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 March 3, 1998,.as supplemented November 13, and December'15, 1998, 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 facilitywilloperate 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 willbe conducted in compliance with the Commission's regulations; D.
The issuance of this amendment willnot 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.
9~0mS0330 W9OXZS PDR ADQCK 05000260
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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-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. 257, 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
+C Cecil O. Thomas, Jr. Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 15, 1999
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ATTACHMENTTO LICENSE AMENDMENTNO. 257 FACILITYOPERATING 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 3.4-29 Insert 3.4-29
0 4
t
RCS P/T Limits 3.4.9 1600 1500 1400 1300 1200
~'100'O 1000 O,0 800 coo 700 E
600
~h 500
.4oo 300 312 PSIG BROWNS FERRY UNIT2 1
2 3
Curve No. 1 Minimum temperature for pressure tests such as required by Section XI.
Curve No. 2 Minimum temperature for mechanical heatup or cooldown following nuclear shutdown.
Curve No. 3 Minimum temperature for.core operation (criticality).
Notes These curves include sufficient
~ margin to provide protection against feedwater nozzle.
degradation.
The curves allow for shifts in RTNor of the Reactor vessel beltline materials, in accordance with Reg. Guide 1.99, Rev. 2, to compensate for radiation embrittlement for 16 EFPY.
200 1000'OLTUP 82'F CURVES 1, 2, & 3 ARE
'ALIDFOR 16 EFPY OF OPERATION 0
50 100 150 200 250 300 350 400 Minimum Reactor Vessel Metal Temperature
('F)
Figure 3.4.9-1 Pressure/Temperature Limits BFN-UNIT2 3.4-29 Amendment No. 257
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 TENNESSEE VALLEYAUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT UNIT3 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No. 217 License No. DPR-68 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated March 3, 1998, as supplemented November 13, and December 15, 1998, 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 facilitywilloperate 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 willbe conducted in compliance with the Commission's regulations; D.
The issuance of this amendment willnot 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.
Acco'rdingly, 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. 217, 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 Cecil O. Thomas, Jr. Director Project Directorate ll-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 15, 1999
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ATTACHMENTTO LICENSE AMENDMENTNO. 217 FACILITYOPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Revise the Appendix ATechnical 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
. 3.4-29 Insert 3.4-29
41 l
RCS P/T Limits 3.4.9 1600 1500 1400
~ 1300 1200 1100 0
I 1000 0'
900 A'-
800 O
700 6oo g
5oo g
400 300 312 P IG BROWNS FERRY UNIT3 1
2 3
Curve No. 1 Minimum temperature for pressure tests such as required by Section Xl.
Curve No. 2 Minimum temperature for mechanical heatup or cooldown following nuclear shutdown.
Curve No. 3 Minimum temperature for core operation (criticality).
Notes These curves include sufficient margin to provide protection against feedwater nozzle degradation.
The curves allow for shifts in RTNDT ofthe Reactor vessel beltline materials, in accordance with-Reg. Guide 1.99, Rev. 2, to compensate for radiation embrittlement for 20 EFPY.
200 100 BOLTUP 70'F CURVES 1, 2, &3 ARE VALIDFOR 20 EFPY OF OPERATION 0
50 100 150 200 250 300 350 400 MIMMUMREACTOR VESSEL MErALTEMPERATURE ('F)
Figure 3.4.9-'1 Pressure/Temperature Limits BFN-UNlT3 3.4-29 Amendment No. 217
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