ML20215A885
| ML20215A885 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  (DPR-033, DPR-052, DPR-068) |
| Issue date: | 12/04/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Tennessee Valley Authority |
| Shared Package | |
| ML20215A888 | List: |
| References | |
| DPR-33-A-131, DPR-52-A-127, DPR-68-A-102, TAC 60870, TAC 60871, TAC 60872 NUDOCS 8612110435 | |
| Download: ML20215A885 (12) | |
Text
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UNITED STATES o
8 NUCLEAR REGULATORY COMMISSION o
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l TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.131 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 February 24, 1986, complies with the standards and l
requirementsoftheAtomicEnergyActof1954,asamended(theAct),
and the Comission's rules and regulations set forth in 10 CFR l
Chapter I; f
i.
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; j
r C.
There is reasonable assurance (1) 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; i
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 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:
8612110435 861204 PDR ADOCK 05000259 P
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.131, 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 and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 4, 1986
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I t-I i-ATTACHMENT TO LICENSE AMENDMENT N0.131
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FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised areas are indicated by marginal lines.
Pages 183 L.
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st: avg!!. '.nCI RroJ tR9'T.h*T; y_o,, g._a. q,vm r-- ny:
{i 4.6.c S:ructors! Inte=rt:r, t
3.6.G Structural Integrity 1.
Ince:vice in3pectien c,y f,333
'g Code C1:ss 1, Class 2, : d 1.
The structural integrity of ASME Claca 3 c: ponent:
$ bc s
Code Class 1, 2, and 3 equivalent perfsr=ed i: eccordss:e.ith components shall be maintained in Section ~CI of the 4T.II Lailar accordance with Specification 4.6 G nd Prescura Vessel Ccdo cad r
throughout the life of the plant.
applicable Addasds as required by 10 CT' 50, Section 50.55a(,),
e:ccept where speific.rritten a.
With the structural integrity relief has been gr:sted by r;C of any ASME code Class 1 pursuant to 10 CFR 50, Sac ic equivalent component, which.
50.55a(s)(6)(1).
is part of the primary system, not conforming ta the above requirements, restore the structural integrity of the i.-
affected cot:ponent to within I
its limit or maintain the reactor coolant system in either a cold shutdotm condi-o tion or less than 50 F above the minimum temperature re-2.
quired by KDT considerations, A!ditional inopo:: ions sh:11 he '
performed on certa 1.. cir=u=icren-t until each indication of a taal p1Pc voida ca 11cted to pro-defect has been investigated vide additionsi pr= :c: ten and evaluated.
agasnne F Pa vhip. which could 1
Jama:;c auxiliary and c=r.:: 1 Sfs-b.
With the structural integrity E****
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of any ASME Code Class 2 or 3 3
equivalent component not con-
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forming to the above require-ments, restore the structural
-- ye.g
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g7.,.,9 ;,. 7u-12 integrity of the affected li,
' component to within its limit cv-:;, c7.:-;;,
g or isolate the affected
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KW -31. CTV-Ir, s
component from all operable x79-39, c W-15..
systems.
ErV-Ja, and t W-3:
pain etese cns-6. 0.s-:4 CMS-J2, INS-104 i_
Cns-15, and cms R3:R DS d:A-4, asxa-;,
DSTJG-gA
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- ('23C5-12, :: 3-11, 2 5C3-5, and 3:C5-4 iSJ T
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Amendment No. pp.131 1
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o UMITED STATES
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8 NUCLEAR REGULATORY COMMISS;CN o
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f WASHINGTON, D. C. 20555 i,
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.127 License No. DPR-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
.The application for amendment by Tennessee Valley Authority (the licensee)datedFebruary 24, 1986, 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
- j.
Comission; I
C.
There is reasonable assurance (i) that the activities authorized by
.this amendment can be conducted without endangering the health and
>j 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 1
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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to'this license amendment l-and paragraph 2.C.(2) of Facility Operating License No. DPR-52;is hereby l
amended to read as follows:
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f (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.127, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license at,endment 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 k
Daniel R. Muller, Director
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BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 4,1986 l
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1
ATTACHMENT TO LICENSE AMENDMENT NO.127
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FACILITY OPERATING LICENSE NO. DPR-52 DOCKET N0. 50-260 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised areas are indicated by marginal lines.
Pages 183 i
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- !r_!_.!.;0 C ::3:T:"::S F10?ERATION SURVI:L* ?.!.CZ 'C'J:RY:E?;T
%.6.C S:ructur-1 Inte rity 3.6.G Structural Intecrity 1.
Inscr tica inspec:ica cf JSliI 1.
The structural integrity of ASME Ccdc Class 1, Class 1. and Code Class 1, 2, and 3 equivalent Class 3 c==cenants shall be co:ponents shall be maintained in perfor:cd i$1 accordance vi:h accordance with Specification 4.6.G gee: ion c of the f,,m,,,y, 3 ile;.
throughout the life of the plant.
and Prassure Vessel Code sad applicable Addenda as recuired s.
L'ith the atractural integrity by 10 C7?. 30, See:1en 50.33a(g),
except where specifi: vrittaa of any ASME code Class 1 relief has beca granted by :C0 equivalent component, which pursuan: to 10 C7a 50, secti:n is part of tha primary systen, 30.33a (g) (6) (1).
not conforming to the above requirc 2nts, restore the l
structural in:.cgrit:. of the affected ccmponent to within its Jinit or raintain the reactor coolant sy:: tem in r
cither a co1J ahutdo m condi-o tica er less than 30 F above the mini =un temperature re-quired by NDT considerations, 2.
. Additienc1 1..ance:1:n: zEl de until each indicatica of a perfor==d r,a cer:si. cir=u.derun.
defact has been investigated tial pipe veld.i so li :cd ::
and evn3 ' tat'.d.
pro-vide addi:1 car.1 pr:te::ica egsine.c pipe whip, unich c:uh b.
With the structural 'ntegrity Jama::e am:ili ry and cen:roi ap-of any AS.e. Cerla Class 2 or 3 tens-l equivalenc con?onent not con-forning to the above rec,uire-tents, restera the structural integrity of the affceted I
component to within its limit 7 *
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CW-'
'#2-13
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or isolate the affe n ed C W-12. C W-25,
.-3" cFV-29*
Kn ce=ponent from all operable
- systems, u -- 3 9.
W-L,.
g3,3 3,,,, c;.,;,;;
Main steso CMS-4, xy.3-; t.,
C'.5-2 0,.XMS-104 CMS-15. and CMS 2.
RMR c.;3;;;,., ;3y;.g,.
M rig.- c Care 5: ray 705-407 TCS-l.23 Tscs-4cs Ts:s-:::.
153 Amendment No. 92,98,127 i
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UNITED STATES
?
8 NUCLEAR REGULATORY COMMISSION o
{
U WASHINGTON, D. C. 20666
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i TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296
- i BROWNS FERRY NUCLEAR PLANT, UNIT 3 i!'
i AMENDMENT TO FACILITY OPERATING LICENSE t
Amendment No.102 l[
License No. DPR-68 lf 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
- The application for amendment by Tennessee Valley Authority (the
'l licensee) dated February 24, 1986, complies with the standards and j
requirementsoftheAtomicEnergyActof1954,asamended(theAct),
- o and the Comission's rules and regulations set forth in 10 CFR
?
Chapter I;
- ).
i.-
B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the
- E Commission;
. c
[;
C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and f
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 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 Comission'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:
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[. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.102, 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 and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
./
Y I
Daniel R. Muller, Director BWR Project Directorate #2 i
Division of BWR Licensing
Attachment:
Changes to the Technical j
Specifications Date of Issuance: December 4,1986
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I, ATTACHMENT TO LICENSE AMENDMENT NO.102 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET N0. 50-296 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised areas are indicated by marginal lines.
Pages 196 8
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i:MITI::c cc::DITIt 3 Fca c:'En?.T On rc.rmc::I nEOUInt:c cs EE.i m Y f.Y m e r.tt n,,ny
$ 4.5 PRI!duv sysTnt rot :nany l
C.
- Jtrrett 1
- teerie; 3.6.C Structural Integrity l
r 1.
' se.Mce insps:-i== cf as.c -
1.
The structural integrity of ASE
=
4 Cede Class 1, 2, and 3 couivalent
-Code C1:ss 1, C_scs 2, c d components shall be raintained in l
Class 3 cespsac=ts chcn Sc Performed is ac:crden:= ti:h accordance uith Specification 4.6.G oc n.
of de,*_T 3ciler throughout the life of the olant.
==d 2rt.scura Vessc1 Cad: ::
l ayplicabla sddanda s :ce:greg a.
1:ith the structural.integri::y by 10 CFP.30, See:ica 30.'3;cyg),
f
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of cny AS:2 cod.: Class 1 m apt where spa d" - --- - en I.
equivalent ccaponent, which relic: cas bacn gr:::cd by ;;7.0 -
?
d 1
a part of the prit:arv systen, Fursusu: to 10 CI?. 30, Sc::ica E
not conforming to the above l
30.5:s(3)(6)(1).
I.
requirements, restore the structural integrity of the affected component to within i.
i its limit or maintain the reactor cool:nt system in I
cither a cold shutdown condi-tion or less than 50 F cbove the ninimum temperaturc re-quired by XDT considerations, h
until cach indication of a
}',
dafect has been invcatigated nd evolunted.
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f.2
- ith the.4tructur:1 integrity i
of :ny AS:'E 0;de Clnss 2 or 3 I
equivalent compenant not con-forming to the above require-2.
Additional a
cents, restore the structural l
performed o. certa.in fincpoctions chall be integrity of the affected circumforontial pipe co=ponent to within its limit t: olds as listed to or isolate the affected provide additional compencut fro = all operable Protection egainst PAPD " AMP' *-Qich systc=s.
l could c=cgo
(
cu::ilic.y Lad ccatrol CV3tu.3.
Fcoduster-GMl-9, ::Z -13.
g G.n!- 12 e CBl=:Ge E N-31, G32-29, M
- nt-39, 001-15, um-se, enn on-
- :
t
. Amendnent No. 18.55.55.102 t
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