ML19345E250

Amends 63,59 & 35 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Changing Tech Specs to Resolve Auxiliary Electrical Sys Ambiguities in Section 3.9

ML19345E250
Person / Time
Site:	Browns Ferry
Issue date:	12/02/1980
From:	Ippolito T Office of Nuclear Reactor Regulation
To:
Shared Package
ML19345E252	List: ML19345E250 ML19345E256 ML19345E260
References
NUDOCS 8012230515
Download: ML19345E250 (34)

Text

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O pa asc<,,9'c, UNITED STATES

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!N 3.'. ), c. 'i NUCLEAR REGULATORY COMMISSION E

WASHINGTON, D. C. 20555 k,'% a j!

g TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLAN'T, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 63 License No. OPR-33 1.

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

A.

The application for amendments by Tennessee Valley Authority (the licensee), dated August 6, 1980, 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; 8.

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 License No. DPR-33 is hereby amended to read as follows:

(2) Technical Specifications l

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 63, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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

i FOR THE NUCLEAR REGULATORY COMMISSION

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Thomas A. Ippolito, Chief l

Operating Reactors Branch #2 Division of Licensing i

1

Attachment:

Changes to the Technical l

Specifications Date of Issuance: December 2,1980 i

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ATTACHMENT TO LICENSE AMENDMENT NO.63 FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:

1.

Remove the following pages and replace with identically numbered pages:

292/293 5 /295 296/297 255/299 2.

The underlined pages are those being changed; marginal lines on these pages indicate the area being revised.

Overleaf pages are provided for convenience.

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LIMIT!NC CCNDITICNS FOR OPE 3ATICN SURVEILLANCE RECUIRDfENTS 3.9 AUXII.IARY ELEC IICAL SYSTEM 4.9 AUXILIARY ELEC IICAL SYSTEM Anolicability Aeolicability Apolies to all :he auxiliary elec-Applies to the periodic :esting

rical power system.

requirements of the auxiliary electrical systems.

l Obtective To assure an adequate supply of elec:rical power for operation of Verify the operaoili:7 of :he

hose systems required for safety, auxiliary electrical system.

5:ecification Soecificatien A.

Auxiliarv 21ectrical Icuioment A.

Auxiliarv Elec:Tical Ecui cen:

l A reactor shall not be started 1.

Diesel Generators up (made critical) from the cold condition unless four a.

Each diesel generator uni:s 1 and 2 diesel generators shall be nanually star:ed are operable, both 161-kV :rans-and loaded once each month mission lines, :vo common sca-to demonstrate operational tien service transformers readiness. The test shall continue for at least a and the require-one-hour period at 75% of ments of 3.9.A.4 through rated load or greater.

3.9.A.7 are met.

During the sonthly gene-A reactor shall not be started rator test the diesel up (made critical) from the generator starting air Hot Standby Condition unless compressor shall be all of the following condi-checked for operation and l

tions are satisfied:

' ts ability to recharge i

air receivers. The opera-1.

At least one off-site 161-kV tion of the diesel fuel transmission line and its oil transfer pumps shall common transformer are be demonstrated, and the available and capable of diesel starting time to automatically supplying reach rated voltage and auxiliary cover to the speed shall be logged.

shutdown boards.

b.

Once per operating :ycle 2.

Three uni:s 1 and 2 diesel a test vill be conducted generators shall be operable.

to demonstrate the emer-gency diesel generators 3.

An additional source of will start and accept power consisting.of one of emergency load within the following:

a.

A second 161-kV trans-sission line and its

.292 Amendment No. //, 36, 37, 63

'!M !!NG CONDITIONS ?CR CPERAT!CN SURVII'.'J!C2 RECUIRD'EN*S 6

3.9.A Auxiliary Electrical Ecuitment 4.9.A Auxiliarv Electrical E uitment I

common ::ansformer

he specified :1:e sequence.

capable of sup-c.

Once a =onth :he quan:1:7 g

plying power to :he l

of diesel fuel available shutdevn boards.

I shall be logged.

b.

A fourth operable units d.

Each fiesel genera:or 1and2dieselgenerator.j shall be given an annual inspectica in accordance 1

3uses and 3 cards Available vi:h instructions based on :he =anufacturer's a.

Star: buses la and 13 rec==endations, are energi:ed.

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Once 2 month a sample of b.

The uni:s 1 and 2 4-kV diesel fuel shall be shu:down boards are

hecked for quali:7 The energi:ed.

quali:7 shall be vi:hin acceptable li=1:s c.

The 480-kV shutdown specified in Table 1 boards associated with of the lates: revisica ho uni: are energized.

to AS23 3975 and logged.

2.

3. O Peve System - Uni:

d.

The Uni:s 1 & 2 Diesel 3at:eries (250-Voi:) Diesel Aux Boards are energized Generator 3at:eries (125-Vol:)

and Shutdown Board 3at:eries e.

Undervoltage relays (250-Vol:)

operable on start buses LA and 13 and 4-kV shut-a.

Every week the specific down boards, A, 3, C, gravi:7 and :he vol: age of and D.

the pilot cell, and

" temperature of an adjacan:

f.

Shutdown Buses 1 and 2 cell and overall battery energized vol: age shall be =easured and logged.

5.

The 250-volt uni: and shut-down board bat:eries and a bat:ery charger for each 5.

Every three senths :he battery boards are operable.

zeasurements shall be made of vol: age of each 6.

Logic Systems cell :o nearest 0.1 vol:3 specific gravi:7 of each a.

Ccamon accident signal cell, and camperature of i

logic system is opsrable.

every fifth cell. These measurements shall be b.

480-7 load shedding logic logged.

system is operable.

c.

A bat:ery rated discharge 7.

There shall be a sinimum of (capacity) :est shall be 103,200 gallons of diesel performed.and :he vol: ige, fuel in :he s:andby diesel time, and output :urrent generator fael :anks.

measurements snall be logged at intervals not

."mendment No. JA, JJ, J/, 63 293 1 :o exceed 24 aonths.

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StMtvrtLLiise! REOUTRLwENTS LMT!MC

• cown tTIONS Pgn orfAATtcM 1.9.A Aust11a ry tiestrical Zeuipeest 4.9.A Avriliarv Elsetrical toutseent 3.

Logic Systems a.

both divisions of the common accident s ignal legit system.

shall be tested every 6 months to demonstrate that it will i

function ovi actuation of the core spray systee of each reactor to provide an auto-matic start signal to all 4 u=i's 1 and 2 diesti generators, b.

Once every 6 renths, the enndi-tion under which the &a0-f olt load shedding lazie sys t re is regatted snail be s t aula ted using pendant test rwitches enc /or pus 5 button te s t esitthe e to de-menstrate that the loa d sie cding logic systes would ini tiat e lead shedding signals on the die =el auxiliary boards, reaccet 50V boards. and the 480-Volt abwt-devn boards.

4 Undervoltage telays a.

Ones every 6 months, the con-dition under which the under-voltage relays are required shall be simulated with an undervsltage on start buses lA sad 18 to desonstrats that the diesel generatora vill start.

b.

Once every 6 months. the con-ditions under which the end er-voltage relays are tequi ed shall be simulated with an undervoltage et each shutdcrwu board to demonstrate that che associated diesel generster will start.

c.

The undervolta ge retsys which start the diesel generators from start buses LA and *!

and the 4-kV shutdown mee rd s,

l shall be calibrated ano.al* y for trip sad reset and tse esasurements logg ed.

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L gg I,IMITING C::NDIT!CNS FCR OPEMTION St"AVEI:.I.M;CE REQUI:tD'E CS 3.9.3 Oeeration vi:5 Inceerable

!4.9.3 Coerstion vi:h Inocerable Ecutoment Eouiement i

Whenever a reactor is in Startup mode or Run mode and not in a cold I

condition, :ha availability of f

electric power shall be as specifi-i ed in 3.9.A. excent as specified I

herein.

1.

From and after the dc:e tha:

1.

When one 161-kV line or one comon one 161-kV line or one conunon station transformer or one star:

s:stion ::ansformer.or one start i bus is found to be inoperable, all bus becones inoperable, reactor [

uni:s 1 and 2 diesel generators opera Mon is permissible under and associated boards must be this condi:1on for seven days.

i demons::sted :o be operable 2.

From and sf:er the data :ha:

ne akV tus :1e board becomes 2.

When the 4kV bus tie board is inoperable reac:ce operation i

inoperable both comen statica is permissible for 30 days service : ansformers shall be provided both common station shown to be energi:ed daily.

service transformers are I

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When one of :he uni:s 1 and :

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3.

When one of :he uni:s 1 and 2 diesel diesel generator is inoperable, generator is found to be innoerable.

continued reactor operation all of the CS, RhR (I.PCI and Contais-is permissible during :he ment Cooling) Systems and the succeeding 7 days provided that remaining diesel generators and both offsi:e 161-kV trans-associated boards shall be demon-nission lines and both comen strated :o be operable immediately station transformers or one and daily thereafter.

common transformer and one cooling tower transformer (not parallel with the ener-gi:ed ccamon transformer) and bus tie board are available, and all of the CS. RHR (I.PCI and Containment Cooling)

Systems and the remaining

hree uni:s 1 and 2 diesel generacers are operable.

295 Amendment No. M, 36, 37, 63 i

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t:r =c cesrrens rea errunes semnac u~;nts - s 3.9.3 C;eratien vich Inoperable 4.9.3 Cperation with Inocerable reuiteen:

Ecuipr.en:

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Wen one uni:s 1 and 2 4-iV l l

4. kten one 4-kV shu:devn board shutdcun board is inoperable, is found to be inoperable, all con:inued reactor operation remaining 4-kV shu devn boards is pernissible for a period and associacea diesel genera-not to exceed 5 days, provided l tors, CS and RIiR (1?CI and

hat bo:h off-si:e 161-kV I

Con: sin =en: Cooling) 3ys:e=s

ansmission lines and both l

supplied by :he re=41aing 4-k?

c==cn s:a:1:n ::ansfor=ers shu:dcun boards shall be de=cn-i or one :cte.cn transfor=er and strated to be :perable, i==e-ene c:oling tower transfor=er f diately and daily :hereaf:er.

and 4-k7 bus tie beard are available and the re 41:ing

5. kten one shu:devn bus is f:und

-k? shu:::vn beards and l

o be hoperab'e all 1 i diesel associa:ed diesel genera::rs, genera::rs shall be pr:ren :persble C3, 70iR (1?C an: Cen:ain=e--

' ediately anc daily :hereaf:er.

Cooling) Systa=s, and all 430 7 e=ergency ;cver beards are operable.

5. Wen one of the shutdevn buses is inoperable reactor operati:n;;

is permissible for a period l

cf 7 days.

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6. W en one of :he 480V diesel Aux. boards be M es inoperable reac: r operation is per-missible for a period of 5 days-l

7. From and after the date : hat one of the three 250-Volt unit batteries and/or 1:s associated battery board is found to be inoperable for any reason, continued reac:c; operatica is permissible during the succeeding seven days. F.xcept for routine surraillance testing :he NRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the si:uation, the precautions to be :aken during

his period and :he plans :o re: urn the failed componen:

to an operable scace.

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3. From and after :hu date : hat l

one of :he four 250-vol:

shutdown 296 Amendment No. 39, 36, 37, 63

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' IMI**NC 00N*JI?*0NS FOR OPL'tA*!ON SU2'/{!L;x;CT ?rct'I3,Drr-e 3.9.3 Cperation with inocerable i 4.9.3 coeration with Inoperable Eouipment Equienent I

board bacteries and/or its 6.

• 4 hen one units 1 & 2 diesel associa:ed battery board'is Aux board is found to be found to be inoperable for inoperable the remaining diesel any reason, continued reactor l Aux board and each uni: 1&2 operation is pe:=issible diesel generator shall be proven during the succeeding five l

cperaole i==ediately and daily days in accordance with thereaf:er.

I 3.9.3.7.

I 9.

• ihen one dirision of :he Logic Sys:en is inoperable, continued!

reactor opera:1on is pernis-l sible under this condi:ica for ;

seven days, provised :he C3C3 recuirenen:s lis:ed in specifi--

l ca:icn 3.9.3.3 are sa:iafied.

~he '.*RC shall be notified wi:hin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the si:ua-tion, :he precau:1ons to be

aken during this period and the plans :o return the failed conponen :o an oper-able sta:e.

10.

Underiol: age ralays on 1A or 13!

star: bus may be inoperable I

for a period of 7 days provided!

the other star: bus and under-voltage relay are operable (wi:hin surveillance schedule of 4.9.A.4a).

11. Underioltage relays on a shu:down board may be inoperable shutdcun boards and undervol:agl 5 days provided :he other p

relays are operable (vichin surveillance schedule of 4.9.A.4.b) 12.

'4 hen one 430 vol: shutdevn boated is found :o be inoperable the l reactor will be placed in hot standby within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

13.

If the requirements for operating in the conditicas specified by

• 3.9.3.1 through 3.9.31 cannot be met, an orderly shutdown shall be ini:iated and the reactor shall be shu:devn and in :he cold condi: ion within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

297 Amendment No. 36, 37,63

5 i,iM t?tNC c?mt?!ONS FOR OPDE'ON et"JVe" ? WP-Tret"tru v e 3.9.C Coerstion in Cold Shutdewn Whenever both reactors are in cold snutdown condition with irradiated fuel in ei:her reactor..the avail-ability of elec:ric pewer shall be as specified in sec: ion 3.9.A except as specified herein.

1.

At least two units 1 and 2 diesel generators and their associated 4-kV shutdown boards shall be operable.

3.

An addi:ional source of power consisting of at least one of the following:

i One161-kVtransmissionlinh a.

station transformer or eithlat and its associated common l

cooling cwer transformer and a 4-kv bus tie board capable of supplying power to the Uni:s 1 and 2 shu:-

down boards.

b.

A third operable diesel generator.

3.

At least one 480-V shutdown board for each unit must be operable.

298 Amendment No. 33, 56, 37, 63

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3.9 3ASES The objec:ive of this specification is :o assure an adequate source of elec::ical power :o operate facill:ies to cool the plant during shut-down and :o operate the engineered safeguards following an accident.

There are three sources of al:ernating current electrical energy available, namely, the 161-kV cransmission system, the nuclear genera-ting units, and the diesel generators.

The 161-kV offsi:e power supply consis s of two lines which are fed fr:m different sec: ions of the TVA 161-kV grid.

In the normal : ode of opera-tien, :he 161-kV sys:em is operating and four diesel generators are pera-tional. If one diesel generator is out of service, there normally re ain the 161-kV sources, the nuclear generating uni:s, and the o:her :hree diesel generators. 7:r a diesel generator to be considered peraole i:s associated 125 V bat:ery =ust be operable.

The nini=us fuel oil requirement of 103,200 gallens is suffi:1ent f:: 7 days of full lead opera:icn of 3 diesels and is ::nserva:ively basec :n availabili:7 of a replenishment supply.

Auxiliary power for 3r:wns Ferry Nuclear plan: is supplied fres rac sources; ei:her :he uni: station ::ansformers or from :he 161-kV ::ansmission systes

hrough :he co= mon sta: ion ::ansformers or the cooling tower ::ansfor:ers.

If a co=cen station ::ansformer is lost, :he units can con:inue to operate since :he unit statica ::ansfor=ars are in service, :he other cem=en s:atica transformer and the cooling :cwer ::ansfor:ers are available, and f:ur diesel generators are Operational.

If a cocmon station service transforse is out of service the shutd wn buses can be fed through a cooling tower transfor=e and bus tie board. 3cch cooling : ewer ::ansfor=ers or 4kV bus tie board =ay remain out of service for 30 days as 1cag as both common transformers are in service. This is allowed due to the standby service required of the cooling tower transfer =ers and bus tie board and the high reliability of :he offsite power circui:s.

The shu:devu buses distribute power :o the shutdevn boards and alicu for flex 1 bili:y of access to the offsite circui:s. A 480V diesel Aux board is allowed to be out of service for shor periods of ti=e for :ests and maintenance.

A 4-kV shutdown board is alicwed to be out of operation for a brief period to allow for maintenance and testing, providing all remaining 4-kV shu:down boards and associated diesel generators CS, RHR, (1?CI and Contain=en:

Cooling) Systems supplied by :he remaining 4-kV shutdown boards, and all l

emergency 480 V power boards are operable.

There are eight 250-vole d-c battery systems each of which consists of a bat:ery, bat:ery charger, and distribution equipment. Three of :hese sys-tems provide power for unit control functions, operative power for uni:

motor loads, and al:ernative drive power for a 115-vol: a-c uni: preferred motor-generator set.

One 250-vol: d-c system provides power for ce==cn plan: and ::ansmission system control functions, drive power for a lif-volt l

a-c plant preferred motor-generator set, and emergency drive power for certain unit large motor loads. The four remaining systems deliver con-l trol power to :he al60-volt shutdown boards.

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Amendment No. 3), JJ, J/, 63 299

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UNITED STATES

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-,' i NUCLEAR REGULATORY COMMISSION l

W ASHING TON. D. C. 2055s A

t' TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.59 License No. OPR-52 1.

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

A.

The application for amendments by Tennessee Valley Authority (the licensee) dated August 6, 1980, 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; i

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 l

l E.

The issuance of this amendment is in accordance with 10 CFR Part 51 I

of the Commission's regulations and all applicable requirements have been satisfied.

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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 1

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59, 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 QtLdpp.lCb Thomas W.'Ippolito, Chief Operating Reactors Branch #2 Division of Licensing s

Attachment:

Changes to Technical Specifications Date of Issuance: December 2,1980 1

ATTACHMENT TO LICENSE AMENDMENT NO. 59 FACILITY OPERATING LICENSE NO.'DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:

1.

Remove the following pages and replace with identically numbered pages:

291/292 293/2T4 295/296 B7/276 2M/T03 2.

The underlined pages are those being changed; marginal lines on these pages indicate the area being revised. Overleaf pages are provided for convenience.

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3.a.c/4.3. C Mechanteni vaevv Fuse _

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De pur;ose of isolating the mechanical vacuus pwsp line is to limit the the main condenser. During an accident, fission release of activity f ree traneported free the reactor through the main stese lines products vould be to the condenser. Oc fission product radioactivity would be sensed by the isolation.

line radioactivity monitors which initiate mais eteam 4.!.A and 4.f.!

1 AS ES given under Specification 4.3. A and 4.3.3 T r.e survei'lan:e r e:u i r e-en t s

'a: it;uid and gaseo a va s:es are properly controlled rrrvid, =* sura-ee e y release of ind icactive -at e:ia ls in :he liquid

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-.e.::eree curi a r.. cascoe, ef!; wee:. Bese eurveilla..ce re:41remen:s provide the ca:s fer :Me !!:ensee a+d the "c=:21 s s ion to evaluate the s* stion's pe rf or ance re.a:ive :: radies::tve wastes released is the environment. 1eier:s en t r.r c wa.9 : 1 ies of radisoctive ruiterts'.s released in ef fluents shall be Commission on the basis et Section 6 of these technical f urnis*ed :n the On the basis of such resort s and any additional informa-s:ecifica:iens.

licensee or others, the Corrcission tion tie C.3-:-is s ion aay ob tain f ror- :Me arv fren time to itse require the licensee to take such actions as ene Ceutission deems appropriate,

3. 8. 3 a.d 4. 3. D 3ASES f.-c objective of this specification is te assere tha: leakage fr m t.7t oduc t, sour:c, and spe:ial nuclear radica::1ve material sources 4:e s =c t exceed allevable limita.

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'.MIT!NC CON 0!!!ONS FOR CPERA*!CN SURVIILI.ANCE RI2U!REINTS i

3.9 AUX:LIARY ELIC 2!CAI. SYST S

{4.9 AUI!!!ARY II.ECUICAI, SYSTS ASolicabili:V Aeolicabili:V Acciies :o all :he auxiliary elec-l Applies to :he periodi testina

1:41 pcver system.

i requirements of :he auxiliary I

elec:rical systems.

25*ec:1ve Ob4ective To assure an acequa:e supply of ele::rical ;over for operation of 7erify :he operab111:7 of :he

nose syt: ens ;* quired for safety.

auxiliar-r elec:rical systen.

3:ecifics:1:n S:ecifica:1:n A.

Auxiliar-Electri:21 I:ui:9en l

A.

Auxil ia r-r E'.e :rical E uirne-:

i A reac:or snail not be s:ar:ed 1.

01esel Generators up (nace ::1:i:21) from :he

old condition unless four a.

Each diesel genera::r ant:s 1 and 2 diesel generators shall be manually started are opersola, both 161-k? ::ans-and loaded :nce each son:a siasion lines

.ro :ocanon sta-

o demonstra:e operational

1on service ::ansforsers readiness.

~he test sna11 i

entinue for at less: a I

and :he require-i one-hour period a: 75% of sen:s of 3.9.A.4 through rated load or greater.

3.9.A.7 are net.

Juring the non:hly gene-l A reac:or shall not be started rator test the diesel up (cade critical) from the generator starting air i

i iio t S:andby Condition unless compressor shall be all of the following condi-checked for opera:ica and

ions are satisfied:

its abill:7 :o re:narge air receivers.

• he opera-1.

At least one off*si:e 161-kV tion of the diesel fuel

tnsnission line and i:s oil ::ansfer pumps shall con: mon transformer are be demonstrated, and :he availaole and capable of diesel starting :ine :o automatically sucolying reach rated vol: age and auxiliary power :s the speed shall be lossed.

snu:down boards.

5.

Once per operating :ycle 2.

Three uni:s 1 and 2 diesel a :ese will be concue:ed genera: ors shall be operable.

to demonstrate :he eser-gency diesel genera: ors

[

3.

An additional source of will start and actest power consisting of one of emergency load wi:nin

he following:

a.

A second 161-kV tranA-(

sission line and its

.292 A=endmen; No. 37, 31, 32, 59

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LIMI**NG CONDIT!CNS 70R Op! RAT!CN SURVE!I.IANCE RECUIREMEN*S i

3.9.A Auxiliarv Ilee: ical Zeutemen:

4.9.A Auxilisrv Electrical I:ut: rent I

common ::ansfor:er the specified time sequence.

capable of sup-c.

Once a =onth the quanti:7 plying power to :he of diesel fuel available shutdewn boards.

shall be logged.

i b.

A fourth operable units ;

d.

Each diesel genersto:

1 and 2 diesel generstor.'

shall be giren an annual inspec:1on in ac:ordance 4

3uses and 3 cards Available wi:h instrue:1:ns based on the manufac:::er's a.

3:s:: buses la and 13 rec:==enda:1:ns.

are energized.

e.

Once a month a sa ple :f b.

he uni:s 1 and 2 4-kV diesel fuel shall be shutdown boards are checkac for quali:7

~he energi:ed.

I' quali:7 shall be w1:hin acceptable li=i:s c.

The aSO-kV shu:down specified in Table 1 boards associatad with cf :he la:est revisien the uni are energi:ec.

o AST'.i 0975 and logged.

e i

j 2.

J. O Power System - Uni:

d.

~he Uni:s 1 & 2 Diesel l

3atterics (250-Vol:) Diesel Aux 3 cards are energized !

Generator 3atteries (125-Vol:)

I and Shutdown Board 3atteries Undervel:sge relays (250-Vol:)

l e.

operable on 3:sr: buses la and 13 and 4-kV shut-a.

Every week the specific down boards, A, 3, C, gravity and the vol: age of and 3.

,the pilot cell, and temperature of an adjacen:

f.

Shutdown 3uses 1 and 2 cell and overall ba:tery energi:ed vol: age shall be =easured and logged.

5.

The 250-Vol: unic and shut-down board bat:eries and a bat:ery charger for each b.

Every :hree =enths :he battery boards are operable.

=easure=ents shall be made of voltage of each 6.

Logic Syste=s cell to nearest 0.1 volt, l

specific gravi:7 of each a.

Common accident signal cell, and :emperature of logic sys:em is operable.

every fifth cell. These measure =en:s shall be b.

480-V load shedding logic!

logged.

system is operable.

l c.

A battery rated discharge g

7.*

There shall be a minimum of (capaci:y) :es: shall be 103,300 gallons of diesel performed and the vol:' ge, a

fuel in the standby diesel time, and output current generator fuel tanks.

measuramenes shall be logged at ince:vals not 293 to exceed 24 sonths.

Amendment No. JI, 32, 39

~

~

o

.0 h

-. T tv. Ce. n tT ION.% F.O.R__OP P.UT 1 M St!1tYttt.* MC! RICUIRMCS c

.9.A austiterv tiectriest Equireent 4.9.A Avuiliarv Electriesi Eevipment 3.

Logic Systres a.

Both divisions of the ensamen accident signal logic system shall be tested every 6 months to descastrate that it will fune. tion on actuation of the core spray systes of each reactor en provide an auto-ma !c s t a rt siensi to all 4 uni'.s I and 2 diesel generat rs, b.

Once every 6 renths, the cendi-tion u: der which the 630-Volt load shedetne tagic sys ten is required small be s1=ulated using pendant test rvitches end/cr pushbutton test esitches es de-monstrate that the lo.d sheddint

-logTc systes would initiate 1:ad sheeding signals on the die:e1 auxilia ry boards, resetor Mov boards, and the 480-Volt shut-d evn bo a r d s.

4 Und e rvolt a ge Relays a.

Once eve ry 6 noo th s, the con-dition under vni:5 the under-voltage relays are required shall*be simulated with an und e rvolt a ge oc start buses 1A snd 13 to desonstrate that the diesel generatora vill start.

l b.

Once every 6 sonths, the con-ditions under which the under-voltagt relays are required shall be simulated with an undervoltage on each shutdevn board to demonstrate that the associated diesel generator vill start.

C.

The unde rvol t s te relays which start the diesel generate:s from s' tart buses LA and 11 and the 4-kV shutdown beordt, shall be ca11 bested anunallf for trip and reset and the seasurements logged.

294 l

fl f /:

sq.,

O

IMITING CONDITIONS TCR OPERA!!ON SURVE! O WCE REQUI:tEMENTS

3.9.3 coera

ion wi:5 Inocerable i 4.9.3 Oceration with Inoperable Eculement i

Ecutement I

Whenever a reactor is in Startup mode or Run mode and not in a cold I

condi:1on, :he availabili:7 of electric power shall be as specif1-ed in 3.9.A, except as specified herein.

t 1.

Frem and af:er :he da:e thaa When one 161-kV line or one common ene 161-kV line or one cenron station :ransformer or One start s:ation ::ansformer.or one star:

bus is found to be inoperable, all I

bus bec =es inoperable, reactor; ani:3 1 and 2 diesel generators and associated boards sus: be opera:1on is permissible under i

this condi:icn for seven days.

I demonstrated to be coerable i=cediately anc daily :hereafter.

2.

Frem and after the date :ha:

2.

When the ekV bus tie board is the akV bus tie boarc bec==es i

inoperable, reactor opera:1:n l

inoperable both c:mmen s:a:icn is permissible for 20 days l

service :ransfor=ers shall be provided both ::==en s:stion shown to be energi:ed daily.

service ::ansformers are energi:ed.

l 3.

When one of :he uni:s 1 and l

3.

When one of :he uni:s 1 and : diesel diesel generator is inoperable, {

generator is found to be inoperable, all of the CS, RER (LPC and Contain-continued reactor operation is permissible during the ment Cooling) Systems and the succeeding 7 days provided :ha:

remaining diesel generators and both offsi:e 161-kV trans-associated boards shall be demon-mission lines and both common strated :o be operable immediately station transformers or one and daily thereafter.

common transformer and one cooling tower :ransformer (not parallel w1:h the ener-gi:ed ce= mon transformer) and bus tie board are available, and all of the CS, RHR (LPCI and Containment Cooling)

Systems, and the remaining three units 1 and 2 diesel generators are operable.

295 Amend =ent No. 37, 31, 32, 69

c d

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r,..

43. c_;a.....

e. ~u R r. _...._.. - _

3. _, ~.., e_v_ _-. _ e_

....___.v

_____..s t

3.9.3 Ceera:1 = with ! ere able

4.9.3 C;eratic vi

h Ice:erable Iqu:: en:

l Equi; en:

t

[

4 When ces uni:s 1 acc 2 4-k7

{l

4. When : e 4-i? shutdev: beard shu:dev bear is inc;erable, is found :s be ineperable, all c:::inued reac:cr 0;eratic:

l re:aining 4-kV shu:dev bearts is per=issible f:: a pert:c l

and assccia:ec diesel genera-se: =c exceed 5 days, ;;:vided l

s, OS and IHR (LPCI as:

tha: be:h off-si:e 161-k?

i Cc :ain=en: C:: ling) Sys:ers

ans=1ssi:n lines and bet:

supplied by the re=alcing 4-k7

==== stati:n ::ansf:::ers shu:dev: beards shall be de:c:-

c

=ce :::=ce ::ansf:r:e and s::a:ed :: he :;erable, i=:e-

e :: cling ::ver ::ansf::=e dia:ely and daily thereaf:er.

and '-k? bus :1e bear:

are aisilable and :he re:aini:g'

5. Whe ::e stu:dev: bus is f:und 4-k7 shu:dev beards and

be inc;erable all 1 i diesel 2

associated diesel genera:::s, geners:::s shall be ; :tes :;ersh."e a

CS, IER (L?C as: "en:ain:en:

i==acia:ely and daily : ereafter.

Coeling) Sys:ers, and all 450 7 ere:gency ; ver bear:s l

are ;erable.

5. When ::e of :he shu:dev:

buses!

is ine;erabia react:: Opera:1:

is per=issible f:: a peri:d

=f 7 days.

l

5. When c=e of the 4307 diesel l

Aux. beards be::=es inc;erable reae::: cperatics is par-missible f:: a peried of 3 days-f j

l

7. Tres and af:e :he da:e that l

c e of the three 150-7elt uni: }

bat:eries and/c its associa:ed ba::ary heard is f und :o be incperable f : any reasen.

isued reac::: 0; era:10: is l

permissible during :he succeediag j

secen days. Exce;: for ::u:i=e surveillance :es:ing :he NRC small be actifies withis 2a l

hours of :he si:ua:10, the i

precau:icus :: he taken during i

this peried and :he plans :o l

re:are :he failed cespecent j

= an operable 3:a:e.

l l

3. 7::= and af:e :he da:e :ha:

cce of :he f ur 150-vc1:

shutdev:

196 l

Amendment No. 37, j!, 32, 59

D FP o Pl0 W KAi 1 J 65 oNJ3Q n ;~, q,

i LIMITINC CONDITICNS FOR OPERATICN MTli:11.ANCT ?Ict'IR_W. T'f 9 3.9.3 Ceeracien vi:5 Inocerable

!4.9.3 Oeers: ion with Inocerable I uipmen:

E:uiement board batteries and/or its 6.

klen one units 1 & 2 diesel associated battery board'is Aux board is found to be found :o be inoperable for inoperable the remaining diesel any reason, continued reactor Aux board and each uni: 1&2 n

opera:1on is pernissible I

diesel generator shall be penven during :he succeeding five operable i=nediately and daily days in accordance vi:h j

hereaf:er.

I 3.9.3.7.

I 9.

kten one division of the logi: l Sys:em is inoperable, continued!

reac:or opera:ics is persis-i sible uncer this cendi:icn for; eeten days, pr:vided the CSCS ;

requirements listed in specifi-l ca:icn 3.9.3. 3 are satisfied. ;

Ite NRC shall be notified l

vi:hin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of :he si:ua-tien, :he precaucions to be taken during this period and :he plans to return :he failed ::=ponen: :o an oper-able 3:2:e.

l 1.

10.

Undervol: age relays on la or 13; scar: bus may be inoperable l

for a period of 7 days provided!

the other star: bus and under-vol: age relay are operable (within surveillance schedule of 4.9.A.I.4).

11. Undervol: age relays on a i

shutdevn board =ay be inoperable shutdevnboardsandundervol:aggl 5 days provided the other l

l relays are operable (vi:hin l

surveillance schedule of l

4.9.A.4.5) 12.

kten one 480 vol shutdown board is found :o be inoperable the l reactor will be placed in hoc j

l standby vi:hin 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and l

cold shutdown vi:hin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

13.

If the requirements for operating i

in :he conditicas specified by '

3.9.3.1 through 3.9.312 cannot i

be met, an orderly shutdown shall be initiated and the reac:or shall be shutdown and in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

297 Amendment No. 31, 32, 59

l s

a h

t,* g ic cmmi?!cNs ens _ corn -!cN e:mve" ' wt-e sem?'5 m e'r-e 3.9.C Coerstion in Cold shutdown

'4henever both reactors are in cold shutdown condi:icn with irradiated fuel in ei:ner reactor, the avail-ability of electric power shall be as scocified in section 3.9.A l

except as specified herein.

1.

At leas: two units 1 and 2 diesel generators and their associa:ed 4-k7 shutdown boards shall be 3perable.

2.

An modi:ional source of power consiacing of a: less: one of the following:

6, a.

One 161-kV ::ansmission line and i:s associated common !

l station transformer or aithat cooling cover transforser and a 4-kw bue tie board cacaole of supplying power to :he 'Jnits 1 and shut-down boards.

b.

A :hird operable diesel generator.

3.

At least one 480-V shutdown board for each unit must be operable.

298 A:nendment No.

37, 3I, 32, 59

D**D

• D.b A

ww o

a 3.9 3 ASIS The objec:ive of :his specification is :o assure an adequate source of electrical power to operate facilities :o cool the plant during shu:-

down and to operate :he engineered safeguards follewing an accident.

There are :hree scurces of alternating current electrical energy available, namely, the 161-kV ::ansmission system, the nuclear genera-ting uni:s, and :he diesel generators.

The 161-kV cffsi:e power supply consists of two lines which are fed from differen: sections of the TVA 161-kV grid.

In :he nor=al =cde of opera-

ion, the 161-kV sys:es is opera:ing and four diesel genera: rs are :pera-ticnal. If one diesel genera:or is cut of service, there normally renain

he 161-kV sources, :he nuclear generating uni:s, and the other :hree diesel genera: ors. For a diesel genera:o: :s be censidered operable its associa:ad 125 7 ba::ery =us: be operable.

The =ini=um fuel oil requiremen: of 103,300 gallens is suffician: f:: 7 days of full lead operatica of 3 diesels and is ::nserva:ively base: :n availab111:7 of a replenish =ent supply.

Auxiliary pcwer for 3 :vns Ferry Nuclear Plan: is supplied f :s :wo sour:es; ei:her the uni: s:a:ica ::ansfor=ers or fro :he 161-kV ::ansmission systes through :he cc= mon s:ation ::ansfer ers or the ecoling :ower ::ansformers.

If a ce= men sta:1ca ::ansformer is icst, the uni:s can continue :o :pers:e since :he unit station ::ansfor=ers s;e in service, :he other com=cn s:::ico

ansformer and :he cooling ::ver ::ansfor:ers are available, and four diesel generators are opera:icnal.

If a commen station service ::ansformer is out of service the shutd:wn buses can be fed through a ecoling tower transfor=e and bus :1e board. 3o:h

coling tower ::ansformers or skV bus :1e board =ay remain cu: of service for 30 days as long as both cemmon transformers are in service. This is allowed due :o :he s:andby service required of the cooling cwer ::ansfor:ers and bus tie board and the high reliability of the offsi:e power :ircuits.

The shutdcun buses distribute pcwer to the shutdown boards and allev for flexibill:7 of access to the offsite circuits. A 480V diesel Aux board is allowed to be out of service for short periods of time for :ests and main:enance.

A 4-kV shutdown board is allewed to be out of operation for a brief period to allev for maintenance and :es:ing, providing all remaining 4-kV shutdo'.m boards and associated diesel generators C3, RHR, (L?CI and Contain cn:

Cooling) Systems supplied by the remaining 4-kV shutdown boards, and all emergency 480 7 power boards are operable.

There are eight 250-volt d-c battery systems each of which consis:s of a bat:ery, bactery charger, and distribution equipment. Three of these sys-tems provida power for unit centrol func:icns, operative power for uni:

motor loads, and alternative drive power for a ll5-volt a-c uni: preferred motor-generator set.

One 250-vol: d-c system provides power for co==en plant and :ransmission system control functicus, drive power for a lif-vol:

a-c plant preferred socor-generator set, and emergency drive power for car:ain uni: large =otor loads. The four remaining systems deliver con-

al power :s the 4160-vol: shutdown boards.

Amendment No. 31, 32, 59 299 l

~

~

1.9 B AST.3 -

f.ach I'O-volt d-c shutdevn beard control power supply can receive power s

~he f ree its own batte:7 battery charger, or f rom a spare charger.

ch.argers are powered f rom normal plant auxiliary power or free the standby diesel-driven generator system. Zero resistance short tircuits between the control power supply and the shutdown board are cleared by fuses located in the respectiv-centrcl power supply. E.sch power se 17 is located in the reactor building near :ne shutdown board it supplies. Each battery is located in its own independently ventilated battery roca.

The 150-vol: d-c syste= is so arranged, and the batteries sized such, that the loss of any one unit battery will not prevent the safe shutdewn and cocidown of all three uni:s in the event of the loss of offsite power and a design basis accide.: in any one unit.

Loss of centrol power to any engineered safeguards ::ntrel circuit is annunciated in the main control roca of the uni affee:ed. Tae loss of one 150-volt chu:deve boart batterf affects nornal :entrol power on!. for the !.150-volt snutdow boarc which it supplies.

~'5c s:st on ba::er/ supplies leads that are not essen-tial f er saf e shu:de -. and ::oldes : of the nuclear syster. Tais tattery was nc: censidered in :he a:tisent 1:ad :alcula:1:r.s.

300 t

pa 88%

UNITED STATES

! i*.

NUCLEAR REGULATORY COMMISSION i

W ASHING ton, D. C. 20555 if s

• ...a TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT NO. 3 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 35 License No. DPR-68 1.

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

A.

The application for amendments by Tennessee Valley Authority (the licensee) dated August 6, 1980, 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; r

8.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; j

C.

There is reasonable assurance (i) that the activities authorized by l

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 1

I 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.

I l

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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 License No. OPR-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.35, 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.

i FOR THE NUCLEAR REGULATORY COMMISSION 06-kyu

(

Thomas A. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical i

Specifications Date of Issuance: December 2,1080 l

l l

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ATTACHMENT TO LICENSE AMEN 0 MENT NO.35 FACILITY OPERATING LICENSE NO. OPR-68 DOCKET NO. 50-296 Revise Appendix A as follows:

1.

Remove the following pages and replace with identically numbered pages:

320 323 324 325 327 328 2.

Marginal lines on the above pages indicate revised area.*

1 3.

Add the following new page:

325a 2

i i

• Note:

The change on page 328 was to move, verbatim, the paragraph that was l

at the bottom of page 327 to the top of page 328. Thus, there is no marginal line on page 328.

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LIMITING CONDITIONS FCR CPERATICN SURVEILLANCE REQUIREMENTS 3.9 AUXILIA.RY ELECRICAT SYSTEM 4.9 AUXILIARY ELECRICAL SYSTEM b.

The fourth ooerable unit 3 i

diesel generator.

4 Suses and Boards 4

Undervoltage Relays Available a.

Once every 5 a.

Both start buses to months, tne unit 3 are energi:ed.

condition under which tt:e undervoltage b.

The 4-kV bus tie relays are board and required shall shutdown boards be simulated (3EA, 3EB, 3EC, with an 3ED) are undervoltage on energized.

start buses 1A and la to c.

The 480-V de.?.onstrate that shutdcwn boards the diesel associated with generators will the unit are start.

energized.

b.

Once every 6 d.

Undervoltage months, the relays operable conditions under 1

on start buses k

which the 1A or 1B and 4-undervoltage kV shutdown relays are boa rds, 3EA, required shall 3E3, 3EC, and be simulated 3ED.

with an under'mLeage on e.

The 480V diesel each shutdown Aux Boards are board to ener;;ized.

demonstrate that tne associated diesel generator l

will start.

320 Amendment No. 35

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIRDENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM 2.

When one unit 3 diesel 2.

When ene unit 3 generator (3A 3B, 3C, diesel generator is or 3D) is inoperable, found to be continued reactor inoperable, all of ooeration is permissible the CS, RHR (LPCI and during the succeeding 7 Containment Cooling) days, provided that both Systems and the offsite 161-kV trans-remaining unit 3 mission lines, and both diesel generators and cooling tower trans-associated boards formers are available shall be demonstrated and capable of supply-to be operable ing power to the Unic 3 immediately and daily x

shutdown boards, and thereafter.

all of the CS, RHR (LPCI and Containment Cool-ing Systems, and the regaining three unit 3 diesel generators are operable.

l 3.

When the 4kV bus *cie or a 3.

When the 4kV bus tie or l

unit 3 start bus is a unit 3 start bus is inoperable or not capa ble found to be inoperable all of being supplied from the unit 3 diesel generators cooling tower transformers and associated boards shall

(

operation is permissible be demonstrated operable for 7 days provided that immediately and daily l

both 161-kV lines and both thereafter. The cooling cooling tower transformers tower transformers and start l

and the unit 3 diesel buses shall be shown to be l

generators are operable.

energized daily.

l l

l Amendment No. 13, 35 323 l

1 LIMITING CCNDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM

[

4.

When one unit 3 4-kV i

4.

When one unit 3 4-kV shutdown board is shutdown board is inoperable, continued found to be reactor opera tion is inoperable, all permissible.>r a remaining unit 3 4-kV period not to exceed shutdown boards and 5 days, provided that associated diesel i

both offsite 161-kV generators, CS and l

transmission lines RHR (LPCI and and both cooling tower Containment Cooling) i transformers are Systems supplied by available and the the remaining 4-kV remaining unit 3 4-kV shutdown boards shall shutdown boards and be demonstrated to be associated diesel operable, Lamediately generators, CS, RER and daily thereafter.

(LPCI and Containment Cooling) Systems, and all unit 3 480-V emergency power boards are operable.

If this requirement cannot be met, an orderly shutdown shall be initiated and the reactor shall be shutdown and in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

5.

From and after the date 5.

When one 480 Volt diesel that one of the 480 volt auxiliary board is found diesel Aux boards inoperable, the remaining becomes inoperable, diesel auxiliary board and reactor operation is each unit 3 diesel shall l

permissible for a period be verified operable immediately of 5 days.

and daily thereafter.

i l

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Amendment No. 13, 29, 30, 35 324

~-,

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 1.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM l

6.

From and after the date that the 250-Volt Shutdown board batteries or one of the three 250-volt unit batteries and/or its associated battery board is found to be inoperable for any reason, continued reactor operation is permissible during the succeeding seven days. Except for routine surveillance testing, the NRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the situation, the precautions to be taken during this period and the plans to return the failed co.iponent to an operable state.

l 7.

When one division of the Logic System is inoperable, continued reactor operation is permissible under this condition for seven days, provided the CSCS requirements listed in Specification 3.9.B.2 are satisfied. The NRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the situation, the precautions to be taken during this period and the plans to return the failed component to an operable state.

325 Amendment No. 28, 29, 30, 35

LIMITING. CONDITIONS FOR OPERATION SURVEILLANCE REQUIR*EtTS 3.9 AtNILIARY ELECTRICAL SYSTEM 3.

Undervoltage relays on 1A or 13 start bus may be inoperable for a period of 7 days provided the other start bus and undervoltage relay are operable (within sur-veillance schedule or 4.9.A.4.4).

9.

Undervoltage relays on a shutdown board may be inoperable 5 days provided the other shutdown boards and undervoltage relays are operable (within surveillance schedule of 4.9.A.4.b).

10.

When one 480 volt shutdown board is found to be inoperable, the reactor will be placed in hot standby within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

11.

If the requirements for operating in the conditions specified by 3.9.3.1 through 3.9.3.12 cannot be met, an orderly shutdown shall be initiated and the reactor sha3".

be shutdown and in the cold con-dicion within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

I 1

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Amendment No. 35 325a

3.9 3ASES The objective of this specification is to assure an adequate source of electrical power to operate fscilities to cool the unit during shutdown and to operate the engineered safeguards following an accident. There are three sources of alternating current electrical energy available, namely, the 161-kV transmission system, the nuclear generating units, and the diesel generators.

The 161-kV offsite power supply consists of two lines which are fed from dif f erent sections of the TVA 161-kV grid.

In the normal mode of operation, the 161-kV system is operating and four diesel generators are operational.

If one diesel generator is out of service, there normally remain the 161-kV sources, and the other three diesel generators. For a diesel generator to be considered operable its associated 125 V battery must be operable.

The minimum fuel oil requirement of 103,300 gallons is sufficient for 7 days of full load operation of 3 diesels and is conservatively based on availability of a replenishment supply.

Offsite auxiliary power for Browns Ferry Nuclear Plant Unit 3 is supplied from two sources: the unit station transformers from the main generator or the 161-kV transmission system through the cooling cover transformers. If a cooling tower transformer is lost, the unit can continue to operate since the station transformer is in service, the other cooling tower transfor=er is available, and four diesel generators are operational.

The 4-kV bus tie board provides the shutdown boards with backup access to the offsite power system through either cooling tower transformer.

A 4-kV shutdown board is allowed to be out of operation for a brief period to allow for maintenance and testing, providing all remaining 4-kV shutdown boards and associated diesel generators CS, RHR, (LPCI and Containment Cooling) Systems supplied by the remaining 4-kV shutdown boards, and all emergency 480 V power boards are operable.

The 480V diesel Aux board may be out of service for short periods for tests and maintenance.

l There are five 250-Volt d-c battery systems each of which consists of a battery, battery charger, and distribution l

equipment. Three of these systems provide power for unit control functions, operative power for :nic motor loads, and alternative drive power for a ll5-volt a-c unit preferred motor-generator set.

One 250-Volt d-c system provides power for common plant and l

transmission system. control functions, drive power for a 115-Volt a-c plant preferred motor-generator set, and emergency drive l

power for certain unit large motor loads. The fif th battery system I

delivers control power to a 4-kV shutdown board.

327 Amendment No. 28, 29, 30, 35

4 The 250-Volt d-c system is so arranged, and the batteries sized such, that the loss of any one unit battery will not prevent the safe shutdown and cooldown of all three units in the event of the loss of offsite power and a design basis accident in any one unit.

Loss of control power to any engineered safeguard control circuit is annunciated in the main control room of the unit affected.

The station battery supplies loads that are not essential for safe shutdown and cooldown of the nuclear sys' tem.

This battery r

was not considered in the accident load calculations.

r t

I 328 Amendment No. 35

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