ML20033C283

Amends 77 & 73 to Licenses DPR-33 & DPR-52,respectively, Revising Tech Specs to Modify Conditions Under Which Start Buses 1A & 1B Must Be Operational

ML20033C283
Person / Time
Site:	Browns Ferry
Issue date:	11/16/1981
From:	Ippolito T Office of Nuclear Reactor Regulation
To:
Shared Package
ML20033C284	List: ML20033C283 ML20033C290 ML20033C293
References
NUDOCS 8112020993
Download: ML20033C283 (12)

Text

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o UNITED STATES

! } ) m (',i NUCLEAR REGULATORY COMMISSION W'tg v 7,;;

E WASHINGTON, D. C. 20555

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.77 License No. DPR-33 1.

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

A.

The application for amendment by Tennessee Valley Authority (tha licensee) dated September 17, 1981, 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 Ccmmission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted withcut endangering the health and safety of the public, and (ii) that such activities will be conducted in ccmpliance with.the Commissior,'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. Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility License No. DPR-33 is hereby amendec to read as follows:

(2) Technical Scecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 77, are hereby incorporated in the license. The licensee shall ocerate the facility in accordance with the Technical Specifications.

8112020993 811116 PDR ADOCK 05000259 P

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This license amendment is effective as of the date of its issuance.

FOR THE flUCLEAR REGULATORY COMMISSION

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Thomas A.~ Ippolito, Chief Operating Reactors Branch #2 Division of Licensing Attac hment:

Changes to the Technical Speci fications Date of Issuance:

November 16, 1981 l

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' ATTACHMENT TO LICENSE AMENDMENT 110. 77 FACILITY OPEPATIllG LICEllSE N0. DPR-33

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DOCKET NO. 50-259 Revise Appendix A as follows:

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Remove the following pages and replace with identically numbered pages:

292 293 295 i

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LIMIIING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS

- 3 '. C AUXILIAR? ELECT 3ICAL SYSTEM' 4.9 AUXILIA3Y ELECTRICAL SYSTEM Antlicability Applicability L,2 s

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Applies to all the auxiliary Applies to the periodic'tecting electrical power system.

requirements of the auxiliary-e cicctrical systc=s.

Cbjective Objective To a ure on adequate supply of Verify the operability-of the electrical powar for operation of auxiliary electrical systc=.

those systens required for safety.

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Spacificatien Specification A. Auxilicev Electrical Eculpment A. Auxiliary Elcetrical Ecutement i

a reactor shall not be started

1. Diesel Generators up (cade critical) frc the cold conditica unicss fcur units 1

a. Each diescl' generator shall and 2 diescl generator; are be manually started and c p era b,le,,the requirements of Icaded onco each conth to I.9.A.4 through 3.9.A.7 are met demonstrate operational

.:nd twc of the folicwing off-readiness. The test shall site power acure'er are available continue fer at least a one 20.stathd with nc credit taken hcur period at 75% cf rated for the two 500-kT Trinity load or greater.

lince.

During the acnthly

- Soth 151-kV linc3, both common sta-generator test, the.dicscl tion service transformers,.and both generater starting air star buses provided the second.

cc= pressor shall be checked source is from the 500kV system.

for operation and its i

ability to rechargo air

- The unit i unit station service receivers.

The operation trancforace TUSS 1B is available.

of the diesel fuel oil If the unit 2 etatica Ocrvice transfer pumps shall be trancforacrc is tho, ccend demonstrated, and the ccurec, a minicus of two 500-kV diesel starting time to line must be availabic.

reach rated voltage and speed shall be logged.

- The unit 2 unit s'3ticn service transfor=?r TUSS 23'is

b. Once per operating cycle, a a$ aim,able.

Iff the dnit i test will be conducted s

1 s

ctacionvatrvice transfor:ces is 1

simulating a loss of

'tPa,s_eEor[.d scurce, a sinica of t

offsite power and similar

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't (E?"s.tho-Sp0kVline: cust be conditions that would exist t

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's,ai,lable.

with the presence of an s

actual safety-injection s

.*k[ I y6.

- Both'161,kV lines, both cooling signal to demonstrate the c

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Amh7dmunt No. J8P, 7,7 292; 5

x 7. A.

LIMZTING. CONDITIONS FOR OPERATTON SURVEILLANCE REQUIREMENTS 3.9 ' AUX:LIARY ELECTRICAL SYSTEM 4.9 AUXILI ARY ELECT 3ICAL SYSTEM tower transfor: crc, and the bus following:

tie beard energi:cd and capabic of cupply pcwer to the units 1

1. Doenergi ation of the and 2 :hutdown beards, provided caergency buses and load that the seccnd scurce is fro:

shedding frc: the the 500-kV systoc.

crergency buces.

Both 161-kV lines, one cotten

2. The diesel starts rec stati:n service tran:for cr supply-ambient condition on the P

ing a start bus, and one cooling auto-start signal, tower transfor:er (through the bus energi:ce the c=erger. y tie board) provided the cooling buses with permanently tower transformer is not parallel tc connected loads, the cc= en station service trans-onergi:ca the auto-former and provided that the second ccnnected e:.orgency source is from the 500kV syster.

loads through the 1 cad cequencer, and c; crates for greater than or A reacter shall not be started equal to five minutes up ( ado criti:si) from the Hot while its C?nerattr 13 Standby Condi:icn unicsa all of loaded with the the fellowing conditicas are c:er;cncy leads.

cati:fied:

3. On dic cl generat:r 1.

One of the off-site power breaker trip, the loads

urces licted abcvc is are shed fec the available and capabic of c=crgency bu es and the

upplyins auxiliary pcVer to diesel restarts en the the chutdOwn beards.

au to-start signal, the cecrgency buses are

2. Three unit: 1 2nd 2 diccel energized with generat:rs chall bc per=anently connected operable.

loads,-the auto-connected c:crgency

3. An additienal cource of power loads are energi:cd con:icting of one of the through the lead f 11 cuing:

ecquencer, and the diesel operates for 3.

A seccnd off-site power Greater than or equal to source available and five minutes while its capable of cupplying power generator is loaded with to the chutdown beards.

L'te c:crgency leads,

b. A fcurth operabic units 1

c. Cnce a month the quantity and 2 diccel ionerator.

of diesel fuel available chall be logged.

4. Suces and Ecard: Availahic.

d. Each diesel generator shall a.

(deleted) be given an annual inspection in accordance

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Amendment No. JdI, 77 293

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,,LDfLTING CONDITIONS FOR OPERATION SURVEILIANCE REOUTREMENTc 3 3 AUXILIARY ELCCTRICAL SYSTEM 11.9 AUXILIARY ELECTRICAL SYSTEM 3.

Cneration with In:cerable B. Occration with Ineperable Ecuipment Equipment Whenever a reae cr it in Startup

1. When only one offsite pcwer mode or Run ::de and not in a cource is operable, all l

cold conditica, the avai.'. ability unit: 1 and 2 diccel of ciectric pcwcr shall be as generators and associated 0;ccified in 3.9.A exec;t es boards nust be demonstrated to specified horc in.

be cperable i nediately and daily thercaf ter.

1. Frc= and after the detc that only one off-site power

2. N.A.

scurce in available, reactor cperstien is per:1 :ible for

v:n days.

2. From and after the date that

3. When one of tne units ; and 2 the 4-kV bu: tie board diocel generator is found to beco=e inoperable, reactor be inoperabic, all of the CS, operaticn i: perni sible ESR (L?CI and Contain:ent indefinitely provided ene of C cling) 'ystems and the the requirc; cff-site power remaining dicael gencr:::rs courec is not cupplied frc and asecciated boards shall be

.hc 161-kV syste: through the de:0nctrated to be operable tus tio beard.

ictediately and daily thereafter.

3.

'a~ hen one of the unit: 1 and 2 diesel generator is

4. When ene 4-k-shutdown 5:ard ir.:perabic, centinued reactcr is Tcund to be incperatic, all Operation in pcreissible retaining 4-kV shutdown boards durins the succeeding 7 days, and as:cciated diesel Orovided that two off ite gancraters, CS, and nn...a s,pLA k wer seurac: are availabic, and Centainac.nt Cooling, c

$nd all of tne CS, RHR (LFCI Systc=s supplied by the and Containment C6 cling) rc aining 4-kV chutdown boards System:, and the rer.aining chall be dc=cnstrnted to be thr2e unita 1 and 2 diccel operabic, incediately and generaters are Operable.

If daily thereaf ter.

thi: require 2nt cannot be met, an crderly chutdown

3. When onc chutdown but is fcund chall te initiated and the to be inoperable all 1 and 2 raactor chall be shut down diesel generators shall be and in the cold conditica proven operabic it edtately within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

and daily thercarter.

4 When one units 1 and 2 4-kV

6. When one 2: nits 1 and 2 DR chutdcwn board is incperable, Aux. board is found to be centinued reactor operaticn ino,perabic, the re=aining is permissible for a period diesel Aux. board and each not to exceed 5 days, unit 1 and 2 diesel generator A=end:ent No. PI, 77 2ogs

1. pa nkcoq'o UNITED STATES

! } 3 # c [,j NUCLEAR REGULATORY COMMISSION

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WASHINGTON D. C. 20555 W~j,p s,

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT NO. 2 i

AMENDMENT TO FACILITY OPERATING LICENS1 Amendment No. 73 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 September 17, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as anended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 3.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Ccamission; 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 ccmpliance with the Commission's regulations; D.

The issuar.ce 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 Spec-ifications 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 follcws:

(2)

Technical Scecifications The Technical Specifications contained in A;,pendices A and B, as revised through Amendment No.73, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

. 3.

This license ;nendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION g,~.

. -, c., _.

Thomas 4. Ippoli to, Chief Operating Reactors Branch #2 Division of Licensing Attac hment:

Changes to the Technical Specifications Da te of Issuance: November 16, 1981 4

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ATTACHfiENT TO LICEllSE AMENDf!ENT NO. 73 FACILITY OPERATING LICEllSE NO. OPR-52 DOCKET NO. 50-260 Review Appendix A as folicws:

1.

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

292 293 295 2.

The overleaf pages are not changed and should be retained.

LTvTTINC CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.9 AUXILIAEY ELECT 2: CAL SYSTEM 4.9 AUXILIA37 ELECTRICAL SYSTEM An:11cabilitv

~Annlicability Applie: to all the auxiliary Applies'to the periodic.tecting cle:trical power system.

requirencnts of the auxiliary clectrical syntc=s.

Cbjective Ob'ective To accure an adequate supply of Verify thc. operability of the electrical power for operatien of auxiliary electrical cyctc=.

those systens required for safety.

Scecificatien Specification A. Auxiliary Electrical Ecuipment A. Auxiliary Elcetrical Equic=ent A reactor shall not be started

1. Dioscl Generators up (made critical) frca the cold condition unicss fcur units 1 a, Each dicscl generator shall and 2 diesel generaters are be manually started and cperable,'the require:ents of loaded ence each conth to 3.9.A.4 thecugh 3.9.A.7 are met-demonstrate operational' and twc of the folicwing off-readiness.

The test shall '

cite ;cwor : urce: are availabic centinue fer at least a one 2c stated with no credit taken heur period at 75% of rated fcr the two 500-kV Trinity load or ;;rcator.

lines.

During the centhly

- Ecth 161-kV lines, both common sta-generator test, the diccel tion service transformers, and both generater starting air start buses provided the second ecmpressor shall be checked source is fro = the-500kV system.

for operation and its ability to recharge air

- The unit 1 unit staticn crvice receivers.

The_cperation tran: forcer TUSS 1B is available.

of the dicael fuel oil If the unit 2 staticn service transfer pumps shall be tran:fer:ces in the necend demonstrated,'and the scurec, a minitu: cf two 500-kV diesel starting time to linen v.ust be available.

reach rated voltage and speed shall be logged.

- The unit 2 unit station service transforcer TUSS 23 is

b. Once per operating cycle, a available.

If the unit 1 test will be conducted station cervice transfor crs is simulating a loss of l

th: seccnd curce, a =inieu of offsite power and simile-two 500kV line: =ust be conditions that would exist i

available.

with the presence of an actual safety-injecticn-

- Both 161 kV lines, both cooling signal to de=onstrate the i

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Amendment No. }( 73

. e-292

_L_I_MITING CONDITIONS FOR OPERATION SURVEILLANCE REQUXREMENTS

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tower tr1nsformers, and the bus following:

tie beard energized and capable of supply power te the units 1

1. Doenergination of the and 2 chutdown boards, provided energency buses and load that the second ccurce is from shedding frc the the 530-kV :ysten.

c=ergency buces.

Ecth 161-kV lines, one cc =0n

2. The diesel starts frc Ot tien cervice transferact supply-ambient condition on the ing a start bus, and one cooling auto-start signal, tower transformer (through the bus energine: the c=ergency tie board) provided the cooling buses with permanently tower transfor:er is not parallel tc connected loada, the common station service trans-onergi:en the auto-former and provided that the second ccnnected emergency source is from the 500kV syste.

loads through the lead coquencer, and c; crates for creater than or A reacter chall not be started equal to five minutes up (cade critical) frc: the Hot while its generater is Star.dby Condition unless all of loaded with the the following c:nditiens are c ergency leads.

.a.

s.m.n.s.

3. Cn diesci senerator

1. Cne Of the eff-site power breaker trip, the leads

urces licted abcVe is are shed fro the available and capable of c=crgency buses and the cupplyirg auxiliary power to diesel restarts on the the chutdown beards.

auto-start signal, the cecrgency buces are

2. Three unit: 1 2nd 2 diccel energized with generat:rs shall be per anently connected

cperable, loads, the auto-connected c=ergency

2. An additienal ccur:e of power loado are energi:cd cencieting of one of the through the lead following:

scquencer, and the dicsel operates for

a. A see:nd eff-site pcrer Greater than or equal to scuroc available and five minutes while its capable of supplying power gener2ter is leaded with to the shutdown bcards.

the emergency loads.

5.

A fcurth operabic units 1

c. Once a conth the quantity

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and 2 diesel generater.

of diescl fuel available

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hall be logged.

4. Suces and Scard: Available

d. Each diesel generator shall a.

(deleted) be given an annual inspection in accordance Amendment No. J2' 73

_ LDfITING CONDITIONS FOR OPERATION SURVEILLANCE RFOUIRF"ENTS

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3.

Cr?rntien with 'n::erable B. Occration with Inocerable Equi; ent Equipment Whenever a reseter 10 in Startup

1. When only one offsite power

de er Run code and not in a cource is operable, all l

Ocid conditJen, the availability unit: 1 and 2 diesel of electric pcwor shall bc 30 generators and associated

ecified in 3.9. A execpt as bcards nuet be der.onstrated to 2;ecified hert.n.

be cperable inmediate.ly and daily thereaf ter.

1.

Frca and af ter the date that only cne off-site power

2. N.A.

scurce in available, reactor operstien is perniccible for

--.n du,.,e.

-n.

2. Fre and after the date that

3. When one of the unita and 2 the 4 -k? bu tie board diesel generator is fcund to bec0:ec inoperable, reactor be inoperabic, all of the CS, speration is pernicsible RHR (L?CI and Containment

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the required cff-site pcuer remaining dicael gener:terc Ocurce is n:t cupplied frc and acccciated boards shall be the 151-kV cy:te: through the de cn=trated to be operable bus tic beard.

12:ediately and daily thereafter.

I. 'Jhon one Of the unit: 1 and 2 di2:el generat:r is

4. When ene 4-kV :hutdown board ir.cperable, c:ntir.ued reactcr is found to be incperable, all Operatien 1 ;cr=issible rc aining 4-kV shutdown tocrds during the cucceeding 7 days, and asecciated diesel provided that two off ite g:ncraters, CS, and EdR (LTCI pcwer sour:c are available, and Contain=c.nt Cooling) and all of One C3, RiiR (L?CI Systens cupplied by the and Contain en-Cooling) remaining 4-kV shutdcun boards Syrte

, and the rcr.aining chall be demonstrated to be three unit: 1 and 2 diesel operable, ir.nediately and generators are Operable.

If daily thereaf ter.

thi require 2nt cannet te 200, an trder'y chutdown

3. When onc chutdown bu i

fcund chall te initiated and the to be inoperable all 1 and 2 reacter shall be shut down diecel generators shall be and in the cold condition proven operable 12:ediately within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and daily thereaf ter.

4. When ene units 1 and 2 4-kV

6. When one units 1 and 2 Diesel chutdcwn beard is incperabic, Aux. Scard i found to be centinued reactor operatien inoperable, the retaining is permissible for a period diesel Aux, board and each not te exceed 5 days, unit 1 and 2 diesel generator 205 Arendment No.,77,73

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