ML19210D219

Amends 54,49 & 26 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Changing Tech Specs to Increase High Drywell Pressure Trip Level Setting from 2 to 2.5 Psig

ML19210D219
Person / Time
Site:	Browns Ferry
Issue date:	11/09/1979
From:	Ippolito T Office of Nuclear Reactor Regulation
To:
Shared Package
ML19210D220	List: ML19210D219 ML19210D221 ML19210D222
References
NUDOCS 7911260071
Download: ML19210D219 (14)

Text

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UNITED STATES

+

NUCLEAR REGULATORY COMMISSION

[,,y.,)y( ; g WASHINGTON, D. C. 20555 gv...../

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 '

BROWNS FERRY NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 54 License No. DPR-33 1.

The Nuclear Regulatory Comission (the Conmission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated August 27, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Conmission's rules and regulaticns set forth in 10 CFR Chaoter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comissim; 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 anendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

1393 313 7911260 o

/

Accordingly, the license is amended by changes to the Technical 2.

Specifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility License No. OPR-33 is hereby amended to read as follows:

l (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54, 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 its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

< h'Tfiom)a f'Ippolito, Chief x

Operating Reactors Branch #3 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 9, 1979 1393 314

ATTACHMENT TO LICENSE AMENDMENT NO. 54 FACILITY OPERATING LICENSE N0. DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:

Remove the following pages and replace with th6 identically numbered pages:

f_5]S6 5

The underlined page is the page being changed; the marginal line on this page denotes the area being changed. The overleaf page is provided for convenience.

1393 315

4 TasLE 3.2.A FRIMART 0)tfTAtt01D(T AND RZ?.CTOR BUI1D1HC 150tATION INSTRtMDf7ATTOM b

Minimum Mo.

Operable Far Trip Sys (t)

Function Tvtp Level Settlog Action (1)

Rennerka Q

2 Instnament Channel -

1 338 above vessel zero A or 1.

Below trip setc. trig does the Reactor low Meter Leet (6)

(5 and E) followtagt a.

Inittstes Reactor Battetes Isolettee g

b.

Inittstee Frimary Cente1mmeet c=---- 3 teolettes g

c.

Inittetes SCTS W

1 Instru=est channel -

100 + 13 pelg 4

1.

Above trip setting toelates the shutdown cooltas euctice valves laatter Righ Pressure of the RER systet 2

Instruncat Channel -

> 47o*ebove veneel sere.

A 1.

Selow trip setting initiates Mets Reactor low Water tevel Steen Line toelattes u.

(LIS-3-16A-D. SU $1) 3 5 psig A er 1.

Above trip settias does th 2

Z twstrument Channet -

tilgh Da ywell Fressure (4)

(B and t)-

faltaving (rs-6 4 -36 A-0) a.

Inittetee Reactor Betidtag teolation b.

Intstatee Frimary Ceetatoment Isoletion c.

Instietes SCTS 2

Inst r-nt Giannel -

1 3 times normal ratel B

1.

Above trip setting lettlates Hets High 9 Jiettmi Mein Steam full power background Steen Lies Isolettos U

Line fiuuiel (6) 2 Inst rument Cbnnel -

• 825 pets (4) 3 1.

Below trip settlog isttletes Mete Steam Line teolation low Freneure Hein Steam Liec 2(3)

Instrument channel -

e_1401 of rated steam flow 3

1.

Above trip settias inittstee Main O

Steen Lise Isoletten talgh flow Hata Stese Lice 0

ut*nihw?n t No. 4, 54

TABLE 3.2.A (Continued)

Mir.i:num No.

'Jperable Per (1)

Func t. i on Trip 1,evel f.ettine, A. tion (Il Remarks Sv:5 g

0 B

1.

Above trip setting initiates 6

9 2

Instru.nent Channel -

1 200 F Main Steam Line Isoletion p

g Main Stean Line Tunnel Ilir,h Temperature 2

Inst.rument Channel -

160 - 180 F C

1.

Above trip setting initiates Isolation of Reactor '!ater M

teactor Water Cleanup Cleanup Line from Reactor and System Floor Drain !iigh Reactor Water Return Line.

b ch Temperature W'

lustru:nent Channel -

160 - 180 F C

1.

Sam.e as above 2

Reactor Unt.cr Cleanup b

Sf ut.en Space Illi;h Te npe rat.ure w

< 100 mr/hr or downscale G

1.

I upscale or 2 downscale will es 1

Ir.st.rument Channel -

e.

Initiate SGTS Itenetor Building Venti-b.

Isolate reactor zone and lation Ilich Radiation -

refuleing floor.

licactor Zone C1cse atmosphere control systen:.

c.

1 Inut runent. Channel -

< 100 r r/hr or downscale F

1.

I upscale or 2 dovr. scale vill, e.

Initiate SGTS.

Itcactor lhallding Venti-b.

Isolate refueling floor.

a t h.n ilirh Radi nt. ion Close atmosphere cont.rol c.

$b rul ai ne. Zone ny s t.cm.

? (7)(8) Inst.rument Channel Charcoal IIcaters < 2000

!! and 1.

Below P000 cfh, trip setting charcoa; S'iTJ Flow - Train A c fn R. II. I! eat.cri< 2000 (A or F) heaters will turn on.

2.

Below 2000 cfwi, trip sett*n6 R. H.

c fr.

lica t.c rs

'reaters will shut off.

U

? (7)(8) i.' inent Channel Ci:arcoal lleaters < 2000 11 and 1.

Pelow 2000 cfm, trip sett.ing charcoa.

W

• :i ;T:. Finu - Train il e th H. l!. lleaters]2000 (A or F) 1: eaters vill turr. ca.

2.

Below 2000 eth, trip nettin6 U. II.

e rm U

....a t e n s heaters vill shut of f.

.l.

B-lev 2000 cah, trip setting charcoa.

u Cha rcoal licat.cru< 2000 c fn !! and 2 (()(3) ifr:ta unent. Channel N

..rb n ow - Train C

!i.ll. ileat ars < 2000 c f-( A or F) heaters will turn en.

2.

Below 2000 cib, trip settin6 R.H.

liente rs heaters will shut c'f.

gR AIGO f

[o, UNITED STATES NUCLEAR REGULATORY COMMISSION y * ) s >(

g f.:

WASHINGTON, D. C. 20555

\\;O*w**4,/

-Q TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 '

BROWNS FERRY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. DPR-52 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated August 27, 1979, complies with the standards and requirements of the Atomic Energy A:t 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 cc,pliance 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.

1393 318

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 License No. DPR-52 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendices i

A and B, as revised through Amendment No. 49, 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 its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION G

Thomas olito, Chief Operating Reactors Branch #3 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 9, 1979 1393 319

\\

t 6

ATTACHMENT TO LICENSE AMENDMENT NO. 49 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET N0. 50-260 Revise Appendix A as follows:

Remove the following pages and replace with identically numbered pages:

55/56 The underlined page is the page being changed; the marginal line on this page denotes the area being changed.

The overleaf page is provided for convenience.

1393 320

TABLR 3.2.A FREMART 00MTAIHHDff AMD REACTOR BUILDING 150tAf t0N INSTRUNDf7ATTON Ntatsuma h.

b 9

Opvable rar b

Trip S a g Function Trip tevel Setttoj Action (1)

Researka A or 1.

Selow trip settlag does the M

2 toetrument Channel -

1 338" above vessel care Reactor low Water t m l (6)

(R and E) followingt Initiates Reactor Se11 ding g

g e.

Isolation M

b.

Inttistee Frimary Centalement teatation b

c.

Initiates SCT5 W

1 Instr e t Channel -

100 + L3 paig D

1.

Above trip eatting teolates the h

shutdown coottog auction valves Reactor tilgh Pressure h

of the EHR system.

A 1.

Below trip setting inttistes Kats 2

Instrument Channel -

3 iia-ro*above vessel sere.

Steam Ltae Isolattes Ranctor low Unter Ic el vi (LIS-3-56A-D, SU #1) 2 Instrumrut Channel -

3 2.5 psig A or 1.

Above trip e.ttias do** the (8 and E)-

follawings til h Daywell freasure (6)

Initiatee Reacter Bulldtag t

a.

(ri-4 4-56 A-b) teolartoo b.

InitLatee Primary Castainment toolation c.

Inttleteo Scr$

5 1.

Above trip settins tattistes his 2

Inst rument thennel -

13 times.;ormal rated Steen Lloe teotation ut gh kaJtstion Italo Staan full power background Line Tunnel (6) 3 1.

selev trip setting tettistes Mate 2

Instru ent Channel -

1825 Paf t (4)

Steam Llue Isolettom u

I..w rsessure Hein Steam g

Line u

1401 of rated steem flo" 5

1.

Above trip setting teittates Nata 8

v 2(3)

In.t ria.c nt Channel -

Steam Line leolatsoo N

talah flow Halo Steau Line

TABLE 3.2.A (Continued) tGnimum No.

Operable l'er

'T Sys(d Function Trip Level Sett.ing Action (1)

Remarks 6

d 2

Instrument Channel -

< 200er B

1.

Above trip setting initiates

}

Main Steam Line Isolation Main Steam 1.ine Tunnel liigh Temperature h

2 i n s t.rument Channel -

160 - 180 F C

1.

Above trip setting initiates Isolation of Beactor Water W

llenctor Water Cleanup Cleanup Line from Reactor and System Floor Drain liigh Beactor Water Return Line.

h Temperature 2

Instrument Channel -

160 - 180 F C

1.

Same as above 0

h Henctor Water Cleanup

[3 Syst.em Space liigh Teu.pe ratu re wos

< 100 mr/hr or downscale G

1.

1 upscale or 2 downscale vill 1

Instrument Channel -

~.

a.

Initiate SGTS iteac tor 1108Idin6 Venti-b.

Isolate reactor zone and lationi liigh Brulintion -

refuleing floor, Henctor Zone Close atmosphere control system.

c.

1 instrument Channel -

< 100 mr/hr or downscale F

1.

1 upscale or 2 downscale vill l(cactor huilding Venti- ~

a.

Initiate SGTU.

b.

Isolate refueling floor.

lation liigh linilint ion

~

c.

Close atmosphere control Herulcing Zone system.

(7)(8) i nnt rument. Channel Chare:ont llentei < 2000 Il and 1.

Below 2000 c fh, trip sett.ing charcoal

')

SGT:1 Flov - Train A e th H. II. lleaterri< 2000 (A or F) heaters vill t. urn on.

~

2.

Belov 2000 cih, trip setting R. II.

IIcat e rs crm henters vill shut off.

2 (7)(8) Instrument Channe!

Charcoal llenterh < 2000 li and 1.

Below 2000 cfh, trip setting cfiarcoal mir:i Flov - Train 11 c th it. II. llcatern{2000

( A or F) heat.ers vill turn on, 2.

Below 2000 cih, trip setting R.II.

flent ers c/h w

henters will shut. of f.

2 (7)(8) Instrument Channel Charcon1 llenters< 2000 cib 11 and 1.

helow 2000 cfh, trip setting charco,a1 u

U

GT

i Flov - Train C H.ll. llenters< 2000 cib

( A or F) heaters will turn on.

2.

Below 2000 cib, trip setting R.ll.

N llea te rs henters vill shut off.

'l i

I R Rf0g f[sk Io,i UNIMD STATES NUCLEAR REGULATORY COMMISSION y

)c(,

5[

/

E W ASHINGTON. D. C. 20555 sA ' /,/

v s,

TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 26 License No. DPR-68 l.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated August 27, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comnission'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 witn 10 CFR Part 51 of the Commissice's regulations and all applicable requirements have been satisfied.

[393 323

. 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 License No. DPR-68 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 26, 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 its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

%: bks

'h-fh, Ippolito, Chief Thomas W.

Operating Reactors Branch #3 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 9, 1979

)393 324

ATTACHMENT TO LICENSE AMENDMENT NO. 26 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET N0. 50-296 Revise Appendix A as follows:

Remove the following page and replace with the identically numbered page:

57 The marginal line on the above page indicates the area being changed.

1393 325

T A81.E 1.l.A PRIMARY C0tFTAINMErff AMD REAC'It>R BUILDING ISO 1ATION INSTRUMENTATIOt4 M a su mum No.

h i n,ma r.als t e

(<

) 78 41' OYP. (lj

_ _ Dyng soy

_ Tg g p Igvel Settag _

Act[onj y _

Reparks l'e r a

2 toseteament Chasisie l -

2 S J8" almsve vessel zero

.% or 1.

Below t rip set t ing does the (B and F) followany:

a.

Initlatee Reactos pu l l.li n 1 He.ict ies la>w Wates Imvel (6)

Isolatnon

('

)

b.

Init hat es Primary Contain,wnt i so l a t lose g

c.

In t e i at cas SGTS D

1.

Almve trip set. ting isolates t he bh 15 psig s hist dowin con 11:39 suction velves 1

lane.t r ument rinasuie l -

100

• He*actest liiqh Pressur e nf 1he RilR system.

7g 2

inntrument cleanne l -

2 9'70 almve vessel aero A

1.

Below trip setting initiates ttsin Steam Line Isolation g

heas-t or tm Water Level (I.I S 56 A- 0, SW 81)

A or 1.

Above trip setting does the 2

Inst a tement Channel -

s 2.5 psig l

(8 and El follownng:

lit y h pr ywell Pr essur e (6)

Inn t a ates Reactor Building a.

(PS-64-56A-Dl Isolation b.

Init iat es Prag.ary Containsient 3

toolatton c.

Initiates 64TS 1

ini.t r ument charviel -

5 1 times normal rated B

1.

Atwive t rip setting init.lates Main Steam Line Isolation it 91 Hadiat inni Main Steam f ull garwer lackgrousul I.i sie-T usis tel (6) 2 I s...t s iiment chansiel -

2 850 psig (4) 8 1.

Delow trip setting initiates Main Steam Line Isolation lasw 1*reneture Main Steam 1.s ne Q

2 ( J) leet t r ument Channel -

5 140% of rated steam f itas 8

1.

Aleve trip set t ing initiates Main U

Steam Line I sola t ion li s yh I' l ow Mann Steam Line 8

1.

Above trip setting initiates g

2 I nu t r ument cleannel -

s 200*r Main Steam Line I solat. m.

U Main St eam Line Tsannel N

Higin Temperature CB i

Ancehloent No. 1/),26

.