ML18031A729
| ML18031A729 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/19/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18031A731 | List: |
| References | |
| DPR-33-A-129, DPR-52-A-124, DPR-68-A-100, TAC-60822, TAC-60823, TAC-60824 NUDOCS 8608270387 | |
| Download: ML18031A729 (15) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSlON WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 129 License No.
DPR-33 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Adthority (the licensee) dated February 12, 1986, 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:
8b08270387 'b0819 PDR
- DOCK 05000259:
P,
'DR I
(2)
Technical S ecifications The Technical Specifications contained in Appendices A an B, as revised through Amendment No. 129, are hereby incorporate in the license.
The licensee shall operate the facility in acco dance with the Technical Specifications.
h 3.
This license amendment is effective as of the date of issuance and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMI SION
Attachment:
Changes to the Technical Specifications Daniel R. Muller, Director BWR Project Directorate P2 Division of BWR Licensing Date of Issuance:
August 19, 1986
ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO.
DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:
1.
Remove the following page and replace with identically numbered page.
185 2.
The marginal lines on this page denotes the area being changed.
p"DI~IO'pH pov'~~TZC rU'BVt;ZLLAt'CE;FQUZI<Ett'IJT.
~ c:-.-v"v <<ur:v'"P.'DARY 4
6
'PIERRE S~Sa
~ an~taco.
H.
Seisrttc Qcstr
!n
. Suo".orts and Snubbcrs During all modes of operation, all seismic restraints, snubbersJ and supports shall be operable except as noted in 3.6.H.1.
All safety-related snubbers are listed in Surveillance Instruction BF SI 4.6.H.
1.
lfith one or more seismic restraint,
- support, or snubber inopcrablc on a system that is required to be operablc in the current plant condition, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable seismic restraint(s),
suppor t(s) or snubber(s) to operable status and perform an engineering evaluation on the attached component or declare the attached system inoperable and follow the appropriate Limiting Condition statement for that system.
The surveillance rcqutrc.in s
of paragraoh 4.6.G cre thu only req iremcnts rhat np"':
to atty se1s-ic rc '.r -ni o.
sunpox"t o Ite
'c.l n s.ub Q ~
~
Each safct; -related sn bber sha' perform ntc of thc foov!n; augun ntud !nscrv!tc tns'tcttton BF SI l.
In ruction t:roun't Th>>
~ ~ ~Illhh~r t tt:ty hc catt;-
gorisud into tvo t-..".jor Srcups cased on v".c'tc" the snubocrs arc accessib'c or inaccc"sible durin,", reactor operation.
These ~a]or arouos tray bc furr:tcr subdiv! 'cd into group".
based on dcs'n, cn:!r-onr:ent.
ur o-lter features vh..h -.ay be c::netted o
afreet thai opcrabil!tv of thc
'nubbers virh1n he grot.p
~
aeh group ntav bi:
irspcctcd
'ndencn'cn acct rdance vith 4.6.H.2 threat"!t 4.6.H.9.
2 ~
Visual. Irsncction Schedule and !.ot Si=c The first inservicc visual inspection of nubbcrs not prcv!ously included in these tcchnical specificatiors and vhosc visual inspection has not been perfor"tcd and documented previously, shnll bc pcrforrt d vithln six months for accessible snub-ber" and bciorc resun'lnp.
pover a:rer thc first rcfueli"hi outage 185 Amelldment Nos. 75,N '
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROMNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. l24 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 February 12, 1986, 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 comon 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 an 8,
as revised through Amendment No. 124
, are hereby incorporate iw the license.
The licensee shall operate the facility.in acco dance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Daniel R. Muller, Director BWR Project Directorate b2 Division of BWR Licensing Date of Issuance:
August 19, 1986
ATTACHMENT TO LICENSE AMENDMENT NO.
124 FACILITY OPERATING LICENSE NO.
DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:
1.
Remove the following page and replace with identically numbered page.
185 2.
The marginal lines on this page denotes the area being changed.
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FOR OP..2TXC'.I U!UiEXILANCE I'.F3UXI(E."!F'ITS 5
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~ "w i~ I%(i 5 i ~ l Qe ~ ~
a(
as c'.il ~g
~
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a
~
5eis"llc a'lf bllue i S
~ ~
i.
~
During all modes of operation, all seismic restraints,
- snubbers, and supports hall be operable except as noted in 3.6.H.1., All safety-related snubber s are listed in Surveillance Instruction BF SI 0.6.H.
c eru' ei
~
that np The survcillaoc of par gr D!l 4.
only reruiremen ta anv se s iic GUpport otne 1,
Mith one or more seismic restraint,
- support, or snubber inoperable on a system that 1
is required to be operable in the current plant condition, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable seismic restraint(s)t support(s)l) or snubber(s) to operable status and perform an engineering evaluation on the attached component or declare the attached system inoperable and follow the appropriate Limiting Condition statement for that system.
Qr 5
lo Ins~uc ion n oue".
- ills, Ulhhi,ril.i. ii he cu groups based on l'.c nor thc sllucours arc acccssib c
0 inaccc "sible durin" re ctor ope a
oil ~
These
-.o c
grouos:say bc furtner subi idcd into j; Dup balled on dcsihn, envir-vh ch r ny bc e Dcctu o
affect thc operabili v of the snubbl v thorn t,lc group.
Each group nav ou ins;ected indcpc:l'c; '
occcrdante vith 4.6.!!.2 t'hrr u"h '
- 6. H. 9.
2.
V'u.ll Insnctt ion Sthcd 1 c on" !.vr 5 i c The f'rst inservice vi"ual inspecrion of snubbcrs not previously inclul!Cd in these tcchni=a 1 specif ications anc Uhosc visual inspection has not been performed and docu~unrcd previously, shnl'c pcrforolcd l:ithxn six months for accessible "nub-bers and betorc resuning poMir afrur thc fir t rcfuelinh ourage Amendment No. g i t~4 105
~ gP,R REQIj~
Vp O~
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.
100 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 February 12, 1986, 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 an 8, as revised through Amendment No. 100, are hereby incorporate in the license.
The licensee shall operate the facility in acco dance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Daniel R. Muller, Director BWR Project Directorate
¹2 Division of BWR Licensing Date of Issuance:
August 19, 1986
ATTACHMENT TO LICENSE AMENDMENT..NO. lOO FACILITY OPERATING LICENSE NO.
DPR-68 DOCKET NO. 50-296 Revise Appendix A as follows:
1.
Remove the following page and replace with identically numbered page.
198 2.
The marginal lines on this page denotes the area being changed.
I>'.ITI1'C COVOZTIOWS FOR OPZ "~iTIG:~
SVRVrILLuVCr.: R~aVZRE~r)JTS ee <<vp v c~'4'
><<)r'QA>V S>>i<<~ir Acstrsints.
Supports s
->>bbers During all modes of operation, all eismic restraints,
- snubbers, and supports shall be operable except as rated in 3.6.H. 1: hll safety-related snubbers are listed in Surveillance Instruction BF SI 4 ~ 6.H.
1.
>Jith one or more seismic restraint, suppor t, or snubber inoperable on a system that is required to be operable in the current plant condition, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable seismic restrairt(s),
support(s),
or snubber (s ) to oper able status and per form an engineering evaluation on the attached component or declare the attached system inoperable and follow the appr opriate Limiting Condition statement for that system.
4.6 pa1~~v s.s.
n.
Scisni ucstra
"..=.
and Snub'r The su vcl lance rrnlu of para'o.
~
4 6 ~ C crc he only rcquircm nt" that apo';:
ta any scis;-..ic restrain or support c )'.Cr th a snubbers.
ach sa!c
': <<cia rd au)'Uncn Iu'nsc
<<v < tu In q, ~
~ a>>
These
<<n.:bbct's a.e 1
<<".Cd
~
BF Si '.6.!!.
Tn""ection Groups Tlu ulhhi r l nag hc catr-Sur'.Cd i,nto tvo ~jot Srous oascd or. v..c hi.
snuobcrs arc acccssib'c or inaccc"sible durin reactor operation.
Thusc...ajor Qrouos:."<<ky b>> furtnr. ~
subd ivi'd into j',rol'p based on desi);no cn.'ntlcnt, or other features vhi h nay bc c Dc"tc'o af!ie thc opcrab!.lity o the "nubbe. s vithID the carol.p.
Each rroup !liar b>>
irs;CC cd indcprndcnt' acccrdancc vi h 4.6.8.2 thr:llh 4.6.H.9.
2.
Vise.l)..nsncct ion Schedu! c and !.,!t Si=c Thc !'rst inservicc vi ual in Feet!on of nubbcrs not previously included in these tcchnical spec ' icat ions and vhosc visual inspection ha" not been ocrforncd and docu~>>ntcd previously. si'all bc pcriorc:cd vithin si!'onths for accessible nub-bcts and bciorc resunin'over
- a. icr thc fir t rcfuelinS outage Amendment Nos. 3,$ $.>DO 198