ML20052A196

Amend 52 to License DPR-68,reflecting Mods to Electrical Distribution Sys

ML20052A196
Person / Time
Site:	Browns Ferry
Issue date:	03/29/1982
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Tennessee Valley Authority
Shared Package
ML20052A197	List: ML20052A196 ML20052A199 ML20052A200
References
NUDOCS 8204270578
Download: ML20052A196 (20)

Text

,'

a at%q'o UNITED STATES

+

85 NUCLEAR REGULATORY COMMISSION

&,k)".s ()c. i s

WASHINGTON, D. C. 20555 c,, W fj f

s.~....

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT N0. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. DPR-68 1.

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

A.

The application for amendment'by Tennessee Valley Authority (the licensee) dated December 1.1, 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 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 Cor. mission's regulations';

3.

The issuance of this amendment will not be inimical to the cccmon cefense and security or to the health and safety of the public; and E.

The issuance of this acencment 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-68 is hereby amende'd to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and 5, as revised through Amendment No. 52, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

82042705 78

c-a

.e 2

3. - This license amendment is effective upon startup of Unit No. 3 in the fifth fuel cycle.

FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Divisio1 of. Licensing

Attachment:

Changes to the Technical

]

Specifications Date of Issuance: March 29,1982 1

l O

e e'

4 O

e I.l l

..a : :s ATTACHMENT TO LICENSE AMENDMENT NO. 52 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 i

Revise Appendix A as follows:

i 1.

Remove the following pages and replace with identically numbered pages:

31 6 324

^

317 325 318 325a 31 9 32E 320 327 321 328 I

322 330 l

323 l

2.

Marginal lines on each page indicate the area being revised.

I 3.

Add the following new pages:

325b 326a e

W b

b e

-_ o n'

s..

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM Applicability

• Applicability 1

Applies to the auxiliary elec-Applies to the periodic testing requirements of the auxiliary trical power system.

electrical systems.

Objective Objective To assure an adequate supply of electrical power for operation Verify the operability of the of those systems required for auxiliary electrical system.

safety.

Soecification Specification A. Auxiliarv Electrical Equiument A. Auxiliary Electrical a

1. Diesel Generators Ecuipment

1. The reactor shall not be

a. Each unit 3 diesel generator started up (made critical shall be manually started from the cold condition) and loaded once each month unless the following are to demonstrate operational satisfied:

readiness. The test shall continue for at least a one-

a. Diesel generators 3A, hour period at 75% of rated 3B, 3C, and 3D operable.

load or greater.

b. Requirements 3.9.A.3 through 3.9.A.6 are met.

~

,~2na.2ent 30,.73, 52 316

~

a s

s..

LI!!1 TING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM

c. At least two of the During the monthly gen-erator test the' diesel following offsite power sources are available:

generator starting air

1. The 500-kV system is compressor shall be checked-available to the for operation and its ability unit 3 shutdown to recharge air receivers, boards through the The operation of the diesel fuel oil. transfer pumps shall unit 3 station ser-be demonstrated and the diesel vice transformer TUSS. 3B with no cred-starting time to reach rated it taken for the two voltane and speed shall bc 500-kV Trinity lines.

logged.

2. The Trinity 161-kV

b. Once per operating cycle, a line is available to test will be conducted simu-the unit 3 shutdown lating a loss of offsite boards through a power and similar conditions common station ser-that would exist with the vice or cooling presence of an actual safety--

tower transformer.

injection signal.to demon-strate the following:

3. Until June 1, 1983, the Athens 161-kV

1. Deenergization of the line can be consid-emergency buses and lead ered an offsite shedding from the emer-source if it is gency buses.

available to the unit 3 shutdown boards

2. The diesel starts from thronhh a common ambient condition on.the station service or autu-start signal, ener-cooling tower trans-gi:cs the emergency buses former not operating with permanently cennected in parallel with loads, energi:cs the auto-source (2) above.

connected emergency loads through the load. sequencer, and operates for greater 4

than or equal to five minutes while its genera-ter is loaded with the

('

emergency loads.

i 317-Amendment No. 7?, 52

e-t

~ _ _.. _,

. ~

e-SURVEILLANCE REQUIREMENTS LI!!ITING CONDITIONS FOR OPERATION 4.9 AUXII.IARY ELECTRICAL SYSTEM 3.9 AUxttt ARY ELECTRICAL SYSTEM -

3. On diesel generator A. 2. The reactor shall not be breaker trips the loads started up (nade critical) are.shed from the emer-

~

from the hot standby con-gency buses and the diesel

~

dition unless all of the restarts on the auto-following conditions are start signal; the emer-satisfied:

gency. buses are energized with pcreanently connected

a. At least ene offsite loads, the auto-connected powcr source is avail-emergency load.S are ener-dble as specified in gized through the load 3.9.A.1.c.

sequenter, and the dienet operates for greater than

b. Three unit 3 diesel or equal to five minutes generators shall be while its generator is

operable, loaded with the ' emergency loads.

c. An additional source of power consisting of one

c. Once a month the quantity of the following:

of diesel fuel available shall be logged.

1. A second offsite power source avail-

d. Each diesel gererator shall able as specified in be given an annual inspec-3.9.A.1.c.

tion in accordance with instructions based on the

2. A fourth unit 3 manufacturer's recommenda-diesel generator tions.

operable.

e. Once a month a sample uf diesel fuel shall be checked for quality. The quality shall be within acceptable limits specified in Table I of the latest revisien to ASTM D975 and logged.

2. D.C. Power System - Unit Batteries-(250-Volt) and Diesel Generator Batteries (125-Volt).

and Shutdown Board Battery (250-Volt) j

a. Every week the' specific gravity and the voltage of the pilot cell, and temp-erature of an adjacent cell.

and overall' battery voltage.

shall be measured *and logged, 316

/mendment tio. 2E, 52

~

..o -~~ t s..

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM

b. Every three mont,hs the

~

measurements shall he made of voltage of each cell to nearest 0.1 volt, specific gravity of each cell, and temperature of every fifth cell. These measurements shall be logged..

c. A battery rated discharge (capacity) test shall be performed and the voltage.

time, and output current measurements shall be logged at intervals not to exceed 24 months.

3. Logic Systems

a. Both divisions of the accident signal logic system shall be tested every 6 months to demon-strate that it will func-tion on actuation of the core spray system of the reactor to provide.an auto-matic start signal to all 4 diesel generators, i

I r

f

' Pan 0nent "O,-JJ, 52 319

_-.$_. _ a...._.__

L1:!'TI::G CO :DITIO::S FOR OPERATION SURVEILI.A:'CE Rr.qUII:E:!E::TS 3.9 AC"II.I ARY EL CTRICAL SYSTEll 4.9 AUXILIARY E!I.CTP.ICAT. SYSTT:

A.

3.13uses and 130ards 4 Undervol La :e Helay..

Available

a. (deleted)

s. The respective start bus is ener;;ized for

b. Once every 6 months, the ca.:h common station conditionn un.ier which *he ervice transformer

! css nf vel:a;;c and de:;r:d-Jes ena:cd au an off-e? '.oltrqe re1.;ys,. re re-si:e - cuer snurec.

';ui r J shal' i.e wit h u.u i. r vo '...

++

b. The 4-kV bus tic board each nhutdown boar.! to is ener",ived if a cool-ih m.nes t ra t e that the f :. t e.,e r t r. :s f o r:re r I

a s s'.ic ia ted d i e 4e l ;,e n s_ ra t u r in designated as an off.

wil1 start.

site power sourcc.

c. Shutdown boards '3EA,'-

3EE, 3EC, 3ED) are en-ergi:cd.

d. The 4S0-V shutdown boards 3A and 3B are energized.

e. Loss of voltage and de:raded voltage relays operable on 4-kV shut-down boards, 3EA. 3Eli, 3EC, and 3ED.

f.

1. 2.. P!, lie c; Aux.

h irei i W \\ a nd '3 Ef', a r e e:h r/,-:ed.

. h e

f. S OY ~,x. 510V 3 cards D 5 E are enargized w i.h 1:-G S c t.s 3 D:,, 3DA

'3E::, and 3EA in service >

I 4

1 Amendraent No. 3E, 37, 52 3;o i

. o:

s e-L1111 TING CONDITIONS F,0R OPERATION SURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM

c. Tre loss of voltage and

4. The 250-Volt Shutdown Board 3EB battery, all de,raded voltage relays which start the diesel three unit batteries, a

' battery charger for each generators from the 4-kV shutdown boards, shall be

. battery, and associated calibrated annually for battery boards are oper-trip and reset and the sble.

measurements logged. These relays shall be calibrated

5. Accident signal logic as specified in table system is operable.

4.9.A.4.c.

6. There shall be a minimum

d. 4-kV shutdown board voltages of 103, 300 gallons of shall be recorded once every diesel fuel in the unit 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

standby diesel generator fuel tanks.

5. 480-V RMOV boards D and E

a. Once per operating cycle, c

the automatic transfer feature for 480-V RMOV 4

boards D and E shall be functionally tested to

+

verify auto-transfer capability. -

B. Operation with Inoperable B. Operation with Inoperable Ecuipment Eauierent Uhenever the reactor is in Startup mode or Run mode and not in a cold conditior, the avai2 ability of electric power shall be as specified in 3.9.A, except as sp.cified herein.

1. From and after the date

1. tihen only one offsite power source is operable, al,1 unit that only one offsite power 3 diesel generators and source is available, re-associated boards must be actor operation is per-demonstrated to be operable missible under this condi-immediately and daily there-tion for seven days, after.

Amendment NO. 23, 77, 52 321 v

-. - -- t

. _ ~.

O s..

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9

' AUXILIARY ELECTRICAL SYSTEM

2. When one unit 3 diesel

2. When one unit 3 diesel gener-i ator is found to be" inoperable.

generator (3A, 3B, 3C, or all of the CS, RHR (LPCI and-3D) is inoperable, contin-ued reactor operation is Containment Ceoling) Systems and the remaining unit 3 diesel permissible during the succeeding 7 days, provid-generators and associated boards shall be demonstrated ed that two offsite power sources are available as to be operable immediately and specified in 3.9.A.l.c, daily thercaf ter, and all of the CS, RHR (LPCI and Containment Cool-ing) Systems, and the re-maining three unit 3 diesel generators 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 />.

3. From and after the date

3. When a required offsite power that the 4-kV bus tie sources is unavailable because board becomes inoperabic, the 4-kV bus tie board or a reactor operation is per-start bus is inoperable, all missible ir. definitely pro-unit 3 diesel generators ar.d vided one of the required assnciated boards shall he offsite power sources is demonstrated operable immedi-not supplied from the ately and daily thereafter.

161-kV systera through the The remaining offsite soutcc bus tie board.

and associated busses shall be checked te be energized daily.

I

\\

~

.Amencment No. 77, 52 322-

o e

.~

l.IttlTING CONDITIONS FOR OPERATION SURVEILt.ANCE REQUIREMENTS 3.9.

AUXII.IARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM

4. When one unit 3 4-kV shut'-

4. When one unit 3 4-kV shutdown board is found to b'e inoper-down board is inoperable, able, all remaining unit 3 continued reactor opera-4-kV shutdown boards and tion is permissible for a associated diesel generators, period of 5 days, provided CS and RHR O.PCI and Contain-that two offsite power ment Coolinn) Systems supplled sources are available, as by t he re:;.aininn 4-kV shutdown specified in 3.9.A.l.c and boards shall be demonstrated the remaining unit 3 4-kV to be operable, immediately shutdown boards and associ-and daily thereafter.

ated diesel generators, CS, RHR (LPCI and Coatsinment

)

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

If this requirement cannot be met, an orderly shut-i down 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. When one 480 Volt diesel aux-

5. From and after the date iliary board is f ound inoper-that one of the 480 volt able, the remaining diesel diesel Aux, boards becomes auxiliary board and each unit inoperable, reactor opera-3 diesel shall be verified tion is permissible for a operable immediately and period of 5 days.

daily thereaft'er.

l l

Amendment flo. V7, 77, 52 323

~

y

• ._ _ ;i_-

r-Ll!ITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM

6. From and after the date that the 250-Volt Shutdown board 3EB battery or one of the three 250-Volt unit batteries and/or its associated battery board is found to be inoperable for any reason, continued reacter operation is per-missible during the succeeding seven days.

Except for routine surveil-lance 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 periods and the. plans to return the failed component to an operable state.

7. When one division of the Logic System is inoperable, continued reactor operation is permissible under this condition for seven days, provided the CSCS require-ments listed in Specifica-tion 3.9.B.2 are satisfied.

The SRC 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 sit-4 uation, the prceautions to be taken during this period and the plans to return the failec component to an operable state.

Amendment'No. 73, 29, 30, EE, 5e;3:

4

_s

,e._..._-a.._

p SURVEILLANCE REQUIREMENTS L1111 TING - CONDITIONS,FOR OPERATION 3.9 AUXII.TARY E!.CCTRICAL SYSTEM-4.9 AUXILIARY E1.ECTRICAI. SYSTEM

8. (deleted)

9. The f ollowing limiting conditions for operation exists for the under-voltage relays which start the diesel generators on the 4-kV shutdown boards.

a. The loss of voltage re-lay channel which start

-the diesel generator fo:

a complete loss of

' ~

voltage on a 4-kV shut-down board may be inop-i erable for 10 days pro-

~

vided the degraded vol-tage relay channel on that shutdown board is operable (within the surveillance schedule of 4.9.A.4.b).

4

b. The degraded voltage re-l lay channel which starts i

the diesel generater for degraded voltage on a 4-kV shutdown board may be inoperable for 10 days provided the loss of voltage relay channel on that shutdown board is operable (within the surveillance schedule of 4.9.A.4.b).

c. One of the~three phase-j to-phase degraded vol-tanc relays provided to detect a degraded vol-tage on a 4-kV shutdown board may be inoperable for 15 days provided both of the following conditions are satis-fled.

i-325

-ce.cment-No.:23, 29, 30, 35, 52

, e

• w

--r.-.

' SURVEILLANCE REQUIREMENTS LIMITI::C CONDITIONS FOR OPERATION 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 ' AUXILIARY ELECTRICAL SYSTEM d

1. The other two phase-

-to-phase degraded voltage relays on that 4-kV shutdown board are operable (within the surve.il-lance schedule of 4.9.A.4.b).

2. The loss of voltage-relay channel on that shutdown board is operable (within the surveillance schedule of 4.9.A.4.b).

d. The degraded voltage relay channel and.the-loss of voltage relay channel on a 4-kV shut-down board may be inop-erable for 5 days _ pro-vided the other shut-down boards and under-voltage relays are operable.

(Within the surveillance schedule of 4.9.A.4.b).

10. When one 480 volt shutdown board is found to be inop-crable, 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 one 480-V RMOV board MG set is' inoperable, the 2

reactor may remain in oper-i

~

ation for'a period not to exceed ceven days, provided

.the remaining 480-V RMOV-board MG sets and their associated loads remain operable.

B am I

325a a niment No. 3",

37 52

-m-p

~

-w

.e-i.

, 9y y

~3-LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM

12. If any two 480-V RMOV board MC sets become inop-erable, the reactor shall be-placed in the cold shut'

.down condition 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 condi-tions specified by 3.9.3.1 through 3.9.B.12 cannot be met, an orderly shutdown shall be initiated and the reactor sh.111 he sliittdown 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 />.

1

~

C. Operation in Cold Shutdown Condition Whenever the reactor is in the cold shutdown condition with irradiated fuel in the reactor, the availability of electric power shall be as specified in Section 3.9.A except as specified herein.

1. At least two unit 3 diesel f.e ne ra t e r s. mil t he i r

.issociateil 4-ky shutdown boards shall be operable.

2. An additional source of power energized and cap-able of supplying power to the unit 3 shutdown boards consisting of at least one of the following:

a. One of the offsite power sources specified in 3.9.A.l.c.

b. A third operable diesel generator.

e 325b in v r. cr r."0. 32

~..

+-...

m*-

4 L1111T!NG CONDITIONS FOR Ol'ERATION SURVEll. LANCE 'ItE(jUI REf!ENTS i

- 3.9 AUXIT.IARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTD1 i

e

)

4 t-

3. At least one unit 3 480-V shutdown board must be

-s operable.

1

4. One 480-V RMOV board motor generator (MG) set is required for each RMOV t

board (D or E) required to

}

support operation of the RHR system in accordance with 3.5.B.9.

4 4

V t

i 326 re

,nt lio. 73, 37, 52 a

y v

g

-w g-

.-w-r-

,.--.g.,.p, y

v m,.

-.a--

n

-y,

,,ne-

j 3

I r

d i

e l e d

e t

r l

i e t

eg

n. ;

r s s a

'e r.

f.

c er r

et e

n eil ei c n h : se e

gd o ss eiet : a t.

i i

a v

n pt h

'5 u.

s t t e

s at t

r.

l rd rs r

u or oae o

s ewl a t c vt d

e e re ec :

i c al i.

e.

r s a t

e dMh r o e

r s a n

e ~'

e ep d - g rt a ebi n

n e

el rh cs t

ee usd no t eeay gt y

iv t

b pb t y i

l a n t r nt s

i b i al el l s el o e

ef ve yd ohl srid sf cr r rn pt i eab e

. t wm ai eo I

o nu i st f gt i

s ee i

s df d na ysr st eai i l

e k

o nir i ea ue s

r t

ose

<: vl cs ml np e a

r s c nn ueeb si aaep m

a :

e e e.

Al rT at cr r.

e t

o S sp Sl ti e

p m

i T

it r

1 T s tla n

d i

t A

s o

l a

/

e S

c a

e c-R s

e c ;

5 i e h

t s C

s a

5 i(

T d

A n

V r

1 R

o 5

C l

c V7 a

l:

e

- 2 1

'I s

09 e

C h

72 g

d g

t i y n6 8

a

)

t s 0

0 0

0 lE i

wa o

2 o t

0 n

4 t

E t

se e

f o

9 a

nd 1

1 1

1 t

i c1 S

t l

soV oV v

3 e

in t -

r t u oo 1

1 i

i I

e t d 0%3 e

0 0

el pc 3

0 9

3 D

S l

21 d

2 0

sa t e oe 1.47 8

8 n

9 9

ev es

/

i12 12 U

3 3

R S(

0 4

6 1

S l

vm T

e i

N v

Ot e.

lo 1

p s

T p

s e

E i

e u

t t

S r

t u t

l n

T nl Y

i a:

n a

i t

V o

n i

A.

oV e l.

ep g

o p

i A

A A

A e

gt en p

e t

t o

t l

e nel a 1

2 3

4 p

l 1

t e

b S

e b

a s b P-S a

r 1

1 1

1 l.

S a eR a

u t

p o

e e

1 1

1 1

t vt i

l s

i t

wu ee m

2 2

2 2

\\.

l ip ol p e, l s

T l

ai T

J 2

2 2

r l

e

_ l e

V r o

A 1 8 AR T

A I

l 2

V 1

1

_j 1

1 V

3 k

r s -

.s af s

d 'i Adl o f

s d

r t ri i

r ar 3 ace n

a o

o. f oig a

o b sn F

3 B

d a

0 nnr n

,h 1

n wwa wD c u.

w oo o oE o

dhb d3 r te d

t s t

o c.

n d

t iu n udf o

t u

swh n

)

4 l

i i

h S r o sat x u

S ed pf A.

t lS V mtiV

,ef ac V

ki ukC cf 9

o V

k

- Tl - E xu K

4( s 4 1 es 4

l 4

c v

4 a

1, i

l 3

e 2

s R

1

>Y~

i.

J e

s t &

T e

.i

e:

e

..., 9 3.9' BASES,

'The objective of this specification is to assure an adequate source

';of electrical power to operate facilities to cool the unit during shutdown and to operate the' engineered safeguards following an There are three sources of alternating current electrical the 500-kV accident.

energy available, namely, the 161-kV transmission system, i

transmission system, and the diesel generators.

j ice transformer for unit

.The generator breaker and a unit station serv 3 provide a non-interru transmission system to the unit 3 shutdown boards.. Auxiliary power 6

can also be supplied from the 161-kV transmission system through the common station service transformers or through the cooling tower trans-The 4-k formers by.way of the bus tie board.

out of service indefinitely provided one of the' required offsite i

sources is not 103, 300 gallons is sufficient The minimum fuel oil requirement of for 7 days of full load operation of 3 diesels and is conservatively based on availability of a replenishment supply.

The degraded voltage sensing relays provide d start signal to the that a deteriorated voltage condition diesel generators in the event This starting signal is independent exists on a 4-kV shutdown board.

of the starting signal generated by the complete loss of voltage relays and will continue to function and start the diesel generators on complete loss of voltage should the' loss of voltage relays become The 15-day inoperable time limit specified when one of inoperable.

the three phase-to-phase degraded voltage relays is inoperable is f

justified based on the two out of three permissive logic scheme pro-vided with these relays.

1 of operation for a brief A 4-kV shutdown board is allowed to be outin:., providioc ell remainion and t er,i perlea to allow for is tint eo.nce' associated diesel generators CS,10iP., (1,PCI 4-kV shutdo Tr board.s a '-

and Containment Cooling) Systems supplied by the renaining 4-kV shut-down boards, nad all emergency 480V power hoards are operable.

The 480V diesel Aux. board may be out of. service for short per10ds for tests and maintenance.

4 E

327

- 'e-d: r.tJha. RE, 29, 30, 35, 52

X -,

There are - five 250-Volt d-c battery ' systems associated with unit 3, each of which cqnsists of a battery, battery charger,~and distribu--

tion equipment. -Three of these' systems provide power for unit control

' functions, operative power for unit motor loads, and alternative drive 4

power-for a ll5-volt a-c unit _perferred motor-generator set.

One 250-Volt d-c system provides power for common plant and transmission system control functions, drive power for a 115-Volt a-c plant preferred motor-generator set, and emergency. drive power for certain unit large motor loads. The fifth-battery system delivers control power to a 4-kV shut-

~

down board.

The 250-Volt.d-c system is so arranged, and the batteries sized l

- such, that the loss of any one unit battery will not prevent the s:..w -she down and cocidcun 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 tain control room of the unit affected.

The station battery supplies loads that are not essential for safe shutdown _and cooldown of the.n. clear system. This battery was not u

censidered in the accident load calculations.

here are two.480-V ac Reactor Motor-Operated Valve (RMOV) Boards that contain motor-generator (M-G) sets in their feeder lines.

These 480-V ac RMOV boards have-an automatic ~ transfer from their normal to alternate power scurce (480-V ac shutdown boards). The M-G sets act as electrical isolators' to prevent a fault from propa-gating between electrical divisions due to an automatic transfer.

The 480-V ac RMOV boards involved provide motive power to valves associated with the LPCl mode of the RRR. system.. Having an M-G set out of service reduces the assurance that full RHR (LPCI) c:.pacity will he availabic when required. Since sufficient equip-ment is available, to maltrain the minimum complement required for R1tR (LPCl) operation, a 7-day servicing period is justified. -

Having two M-G sets out of service can considerably reduce equipment l

availability. Therefore, the affected unit shall be placed in cold shutdewn within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

h 9

+

t

[

i e

a 32S s

.6 q

gr y

7 y

• ,v.-y~,,, -,,, - - -. - -,

w op

,ry-,

-m---

.i--

J.'

• r e 3.

250-volt D.C. Power Supply and Distribution (BFNP FSAR subsection 8.6) 4

. Memorandum f rom T. G. Campbell to G. T. Jones concerning capacity of 161-kV transmission lines dated October 28, 1981 (L23 871014 929) s O

4 330

..., c..,,

tu

,