ML20148B131
| ML20148B131 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/14/1980 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20148B137 | List: |
| References | |
| NUDOCS 8001180364 | |
| Download: ML20148B131 (2) | |
Text
.
TENNESSEE VALLEY AUTHORITY CH ATTANOOG A. TENNESSEE 374o1 400 Chestnut Street Tower II January 14, 1980 TVA BFNP TS 135 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Denton:
In the Matter of the
)
Docket Nos. 50-259 Tennessee Valley Authority
)
50-260 50-296 In accordance with the provisions of 10 CFR Part 50.59, we are enclosing 40 copies of a requested amendment to licenses DPR-33, DPR-52, and DPR-68 to change the technical specifications of the Browns Ferry Nuclear Plant units 1, 2, and 3.
This is a request for an expedited change to the technical specifications to provide a temporary second offsite power source to the unit 3 4-kV shutdown boards through the 4-kV bus tie board (Enclosure 1). We are also enclosing a description and justification of the proposed temporary modifications (Enclosure 2).
These mody.fications to the technical specifications will be in effect while unit 1 is in cold shutdown for refueling and until the principal source of offsite power for unit 3 through the cooling tower transformers is repaired and back in service. We request your most expeditious consideration of this request.
This matter has been discussed with T. A. Ippolito and R. J. Clark of your staff.
In accordance with the requirements of 10 CFR Part 170.22, we have determined this proposed amendment to be Class III for unit 1 and Class I for units 2 and 3.
These classifications are based on the facts that the proposed amendment for unit 1 involves a single safety issue which does not involve a significant hazard consideration and the proposed amend-ments for units 2 and 3 are duplicates of the unit 1 proposed amendment.
The remittance for $4,800 ($4,000 for unit 1 and $800 for units 2 and 3) is being wired to the NRC, Attention: Licensing Fee Management Branch.
l
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Very truly yours, T
ESSEE VALLEY AUT110RITY O. hl. TAM 6 l
L. M. Mills, Manager Nuclear Regulation and Safety l
Subscribed and sworn to before me this
/ N day?of > / // H 1980.
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Notaky Public g
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Enclosures 800J l80 364 0028230 An Equal Opportumty Employer
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,,' Mr. Harold R. Denton January 14, 1980 cc (Enclosures):
Mr.' Charles R. Christopher Chairman, Limestone County Commission P.O. Box 188 Athens, Alabama 35611-Dr. Ira L. Myers State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36104 v
90028231
ENCLOSURE 1 BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (DOCKET NOS. 50-259, -260, AND -296)
PROPOSED Cl!ANGES TO TECHNICAL SPECIFICATIONS (TVA BFNP TS 135) 1 90028232 4JMr%E8 8001180 36 7 a
UNITS 1 AND 2 I
i 13tc Too rus s u r-90028233 l
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tJ. MITING CONDITIONS FOR OPERATION SURVEll.t.ANCE REQUIRDiFNTS 3
AU1tLIARY ft.t.CTRICAl. SYSTDi 4.9 AUXILIART ti.tCTHICA1. SYSTEM b
.9
.A p p l i c e b t,11 ty Applicability D
Applies to t he sus t 11e ry elec-Applies to the periodic testing trical power eyetem.
requiremente of the auxiliary electrical systems.
Objective Objeceive, To assure an adequate supply of Verify the operability of the electrical power fot operation of auxiliary electrical system.
those systema required for safety.
Specificatton, Speciftestion, A.
Auntitary Electrical Equipment A.
/.u r i l l a r y, t. l e c t r i c a l E<tu t pmen t A scactor whall not lie s t.i r t ed 1.
Diceel Cenerators up (made iritical) Item the cold condition unles; tror a.
Each diesel 7.cnerator unit.. I and ! die.ul generatuts shall be manually started are operabic, bot h 161-kV t rans.
and loaded once each month mission lines, two conv,on s t a-to dermonstrate operations!
tion servire t r. ins f ormers readiness. The test shall 7.
continue for at least a are operable, and the require.
one-hour period at 75I of ine n t., o t~
"l. '). A. 4 t h r o ug h rated load or greater.
3.9.A./ are mit.
A reactor sh Lli not be started genna r starting air up (made critical) from the e mpress r shall be llot Gtandby Condition unless checked for operatton and all of the following condi-its ability to recharte tions are satisfied:
air receivers. The opers.
tion f the diesel fuel 1.
At least one off-site 161-kV Il trJnaler Puepe shall trarnminston line and its be demonstrated. and the ecemn transformer are diesel starting time to available un<1 capable or reach rated voltar,e ard au t or' ult ic a ll y supplying auxiliary power to the speed shall be logged, shutdown beard s,
b.
Once per oper.itin t cycl.
a rest will be o nducted F.
Tnree units 1.nd ? dieset to dec.onstrate the emtr=
l eenera to: - stiall t e operable.
gency dietel generators 3
An addttional source of will start and accept power connia.tng er one or emerRency load within I
t rie followin<:
a.
A second 16L-kV trane-mission line and its 292 b
)
?
d Amendment No.
19 e
i 1
900282 R l
Reviud 11-16-78 LIMttluc contT1ons ton OPERATION 501(V f.ltlEtC E Rf Q('I s D. f ST S 3.9.A Aust11ary tiectrical Equipment 4.9.A Aue11tery Electrical fautpisent, A
d the spectfled time sequence, ctinsuun t r.uu.1 o e me r c.
Once a month the gusatity
%/
of diesel fuel eve 11eble capable of supplying power ehen be lossed.
to t he shotriown br>a rds, d.
Each diesel generator shall be given en ennval inspec-D.
A fourth operable units tion in accordance with 1 arvi 2 diesel generator.
lostructions based on the manufacturer's i t c ases e nda-k.
Buses and Boards Available tiona.
e.
Start bu m, IA and 18 ore sample of e.
Once e month a enerFlied.
diesel f sel shall be CheChed for quality, The qualit y b.
The an t ts 1 and 0 6-kV shall be within the errepte-seu do m bunrds ar" ble limits specified in e
'D" 4'1'4-
'feble 1 of t 'N L1 L c.. t rm'i9 ion E" ^S MM 308 'O$ed.
c.
The 180-V shu'down boards esssenetel with the untt 2.
D.C. ?ower A y s t en - Unit Patteries are energ1:ad.
(250-Volt) Dir e.I Cener at er Betteries (125./ott) and ShutJovn d,
Und e r vol t nsf nlays
&cerd Battertes 1250-vo!:)
operable en start buses 1A and 18 and L-kV a.
Every week the spec i fic ehutdovn boerds, A. B, C, greetty and the voltage af and D.
the ptiot c all, and t espc t a-g tute of an adjacent cell end d
e.
Shu tdowri busses 1 & 2 be sessuiel and loped.
V energized with each bus supplying no more than b.
Eury three esuth, the e,e e -
31
- d' two units 1 & 2 shutdown
I boards and the bus tie nearest 0.1 volt. erecific board.
,,,,,,,,,,,,n,,,,,,,
t e mp e r a t u t e o f e v e r y fifth cell. These measuremente 3.
The 230-v lt ucit and e5utdown o
shall be logged, board betteries and a bettery charger for eacn battery and A battery ra ted dis cha rge c*
eseociated battery boarde are (eapaelty) test shall br>
eperable.
perfer,ed on2 the v W..Me, L L%,.i n.1 o u t uu t current d.
Logic Systees so a r.u r er un t.s shall be logged at blervals not to enceed e.
Casmos acesdent signal legte systre le operable.
- 21. risnths.
b.
400-7 lead shedJing logic 9 0 0 2 8 2 h*-
e yit eit is orerable.
2.
The,e
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103,300 sellone of d1eart fuel 10 the steedby diesel genere-1 '7 / C 77i ter fuel tanks.
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293
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l b Askl 4;.z;. yg, LIM 1711sG COMOITIONS FOR OPERATION SURVElli.ANCE RIOUIREMDff 5 3.9.8 Operation ytth Inoperable 4.9.3 operation with Inoeerable q
kuiseent teuipeent Whenever a reactor is to Startup l
ande er Run mode and not in a cold eendittoa. the availability of electric power shall be as speci-fled ta 3.9.A. escept as specified bettine 1.
From and after the date that 1.
When one 161-kV line or one commom one 161-kV line or one connon station transformer or one station transformer start bus is found to be inoperable, all units or one start bus I and 2 diesel generators and becoe.cs inoperable, reactor associated boards must be demon-operation is perinissible st rated to be operable icunediately under this condition for and daily thereafter.
seven days.
2.
When one of the units 1 and 2 2.
When one of the units 1 and 2 diesel generator is inoperable, diesel generator is found to be continued reactor operation is inoperable, all of the C5, RxR peristasible during the succeeding (LPCI and Conta1.noent Cool.ing) 7 days, provided that both off.
Systems and the rensining diesel site 141-kV transmission lines generators and associated boards and both common station trans-shall be demonstrated to be operable formers famediately and daily thereaf ter.
are avail-able, and all o f the CS, RHR (LPCI and Containment Cooling) Systems, and the remaining three units 1 and 2 diesel generators are ope rable. If this requireient canadt be met, an orderly shut-down shall be initiated and both reacters shall be shutdown and in the cold condition within 26 heuts.
295 90028236 Ancndnent No. 39
.7er 777 i
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L-ke% 's W 6-23-78 4
usset seu casse),1,e_es{ ])$ et rLATines sunyt ti.t.ANCr. atqui*MxTt j
,i 1 9.a operatte,n with inoperable 4.9.8 operetton with Ino,erable teelpment 54mipment 3
When one units 1 ar.d 2 t-kV y
shutdovn board is inoperable.
continued reactor operation I
is permissible for a period not to exceed 5 days, provided that both off-site 161-kV tranrrission lines and both cosuson station transforisers 3.
When one 6-kV shutdevn board is are aksilabic ted the reasin-(ound to be inoperable, all
]
ing b-zV shutdovn teards and remaining 6-kV shutdove, boards as sociated die s el gensrators, and associated diesel genero.
CS, nHa (LPCI r.nd Contaixsent tors. C5 and RMM (LPCI and Cco11ng1 Systems, and all la&o V Containment Coolin3) Systems ereergency power boards are supp!!es by the remaining 6-kV eperable. If this requiretsent shutdown boards shall be de-on-cent. t te ret, an orderly shut-strated to be operable, ix. e -
dow. stsil be initiated and distely and daily thereafter.
I both reactors shall be shutdown sad in the cold condition within 2h how s.
4.
From and after the date that one 4.
When one shutdown bus is found 4 KV shutdown bus is inoperable, to be inoperable the following continued reactor operation is will be verified immediately:
permissibic for a period of 7 days provided the following conditions a.
The remaining shutdown bus are satisfied:
is energized.
a.
The bus tie board is immediate1) b.
The unit 3 bus tie board is de-energized if supplied from disconnected from the a shutdown bus.
shutdown bus by opening the supply breaker.
b.
The breakers to the bus tie board from the shutdown busses are racked out and placed under administrative control within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
c.
The remaining shutdown bus is operable.
296 Amendment No. 39 90028237 C
v 333 l7 03
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS Fran and af ter the date that one of the three 250. volt unit bat.
(-(,,%
teries and/or its associated battery board is found to be inoperable for any ressen, Q
continued reactor opsre ties is l
per*,issible during the succeeding i
seven*deys.
Except for routine curveillance testing the MC 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 eituation, the precautions to be taken during this period and the plans to return the failed component to an operable state.
6.
I' rom and after the date that one of the four 250-volt shutdown 296A Amendment No. 39 u
90028238 l
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[
e-LIMITING (0401T1055 ron opr(ATIoM SURYEILLANCE RF.QUIR EMENTS
) 9.8 ogn, ration with Inoperabic 4.9.3 Operation with Inoperable Equipment _
{ quip cnt
,_s board ba t t e r ics and/or its
%=,'
ascociated bettery board Le fou.1d to be inoperable for any reason. contlnued vesc-tot opetation is permissible durtnr the succeedina (Lve days
'l In accordance with 3.9.B.5.
7.
When one division of the Lotte Systc= in inoperable, enntinued reactor creration is permissible undar thin condition for seven days, provided the CSCO terutre-ments its:e4 tn <pecification 3.9.5.2 are satisfied. The NRC Shall be n4Llfled uithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> el the situJtton.'the precautions to be taken 'uring this period an<
the plans to return the failed component to an operable stete.
v 297
-4 m
90028239 v
l va's d b-21-78 (ItG?PtG CONDITIO'65 FOR OPDtATION SURVEILLANCE REOllIRFXENTS 1.9.C oferation in Cold Shutdown M enever both reactors are in cold shutdown condition with irradiated fuel in eithe r reac tor, the avail-ability of electric power shall be as specified in section 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.
2.
An additional source of power consisting of at least one of the following:
- a. One Ibi-k V t ransmission line and its associated common i
station transformer capable et supplying power i
to the Units I and 2 shut-dovn boards.
- b. A third o>crable diesel S
p generator.
\\
y 3.
At least one 480-V shutdown board for ca.h unit must be opere ie.
l l
298 Amendment ;o. 39 l',
90028240
hw's d 6 7 8 19 Sanft The objective of this specification is to essure an adequate source of elecpricalpowertooperatefacilitiestocooltheplantdurinAshut-downg and to operate the engineered saf eguards following an accident.
A Therr are three sources of alternating current electrical energy eval Mble, naemely, the 161-kV transatselon systeis, the nuclear genere=
%/
ting unite, and the diesel generatore, i
The 161-kV offsite power supply consists of two lines which are fed from ill i f t r e n t sections of the TVA 161-kV grid.
In the normal mode of opera-tion the 161-kV nystem is operating and four diesel r,eneracore are opers-7 tionpl. If one diesel generator is out of service, there normally rensin the 161-kV sources, the nuclear generating units, and the other three diesel generators. For a dicael generator to be considered operable its sonociated 12$ V battery must be operable.
The etntrum fuel oil requirement of 103,J00 gallone to sufficient for 7 days nf fuit load operat ton of ) diesels and is conservatively beoed on sveilability of a replenishment supply.
Auxiliary power for Brovng Ferry Nuclear Plant is supplied from two sources; cither the unit i, L n t i o n transformers or from the 161-kV transatssion system through the c oms 6on s.t.i t i on transformers If a commion station transformer is lost. the units can continue to operate since the unit station trans-formerg are in s e rv i c e, t he o t he r cousson s t a t ion t rans f orme r and four diesel generators are operational.
The shutdown busses distribute power to the shutdown boards and allow for flexibility to the offsite power circuits.
The shutdown busses will temporarily supply the bus tie board until normal supply is restored, but no later than 2/2/80.
The capacity of the shutdown bus is such that any four shutdown boards can be supplied and provide adequate power for the
^
designed basis accident.
In the event a shutdown bus is lost, unit 3 bus tie board will be disconnected to ensure no more than four shutdown boards are supplied.
A 4 4V nhuttovn hnArd is allowed to be out of operation for a brief Per$od to allow for maintenance and testing, providing all rom 41ning 4-kV shutdown heards and a==ociated diesel generators CS, AHR, (LPCI and Containment Coo t tur.) Systema supplied by the remaining 4-kV shutt.own boards, and all emergency 480 V rower boards are operable.
There are eight 250-vnit d-c battery systems each of which constats of a hatterv, battery charger, and distribntion equipment. Three of these eye-teme provide power for unit control functions, operative power for unit rintor I n ul v, and alternative drive power for a ll$-volt a-c unit preferred sin t a r -r e n c r a t o r get, One 230-volt d-c system provides power for comon plant and tranamtanton aygtem content functions, drive power for a 115-volt n-r plant p re f e r v est motor-cencrator set, and emergency drive power for certain unit larce sector loads.
The four remaining systems deliver con-trol pnwer to the 6160-volt shutdown boarde, I
(
Amendment No. 39 299 m
90028241
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UNIT 3 t
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e 90028242
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6 - 2 3
~7 9' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 6
3.9 AUXILIARY ELECTRICAL SYSTEM
^
3.
When one unit 34 - kV 3.
When one unit 3 4-kV shutdown board is shutdown board is ""
inoperable, continued found to be reactor operation is inoperable, all permissible f or a remaining unit 3 4-kV period not to exceed shutdown boards and 5 days, provided that associated diesel both offaite 161-kV generators, CS and t ransmission lines RHR (LPCI and and both cooling tower Containment Cooling) 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, immediately generators, CS, RHR and daily thereaf ter.
(LPCI.and Containment Cooling) Systems, and 4.
When the bus tie board is i
all unit 3 400-V inoperable the unit #3 4-KV emergency power shutdown boards and unit 3 boards are operable.
If this requirement diesel generators will be verified operable immediatelyi cannot be met, an orderly shutdown and daily thereafter.
I 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 />.
4.
From and after the date the bus tie board is found to be inoperable, reactor operation is per-missibic for a period of three days provided that unit #3 shutdown boards are operable and supplied from the unit boards and the diesel generators are operable.
~
90028243 Nnendment No.13 324
Revised 11-30-79 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM 5.
From and after the date that the 250-Volt Shutdown board batteries or one of the three 250-Volt tmit 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 ba 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 f ailed component to an operable state.
6.
When one division of the Logic System is inoperable, continued reactor operation is permissible under this condition for seven days, provided the CSCS requirements 3isted in Epecification 3.9. B. 2 are satisfied.
The ime 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 t ho sit uation, the precautions to be takan during this per iod and the plans to return the failed component to an operable state.
325 Amerrhent No. 28
Revised 11-30-79 3.9 BASES The objective of this specification is to assure an adequate source of electrical power to operate f acilities to cool the unit during chutdown and to operate the engineered safeguards following an accident. There are three sources of alternating current electricat energy available, namely, the 161-kV transmission system, the rmelent ganerating unita, and the diesel generatore.
The 161-kV of fsite power supply consists of two lines which are fed from different 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 cervice, t here 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.
Of fsite suxiliary pcwer for Prowns Ferry Nuclear Plant Unit 3 is nupplied from two sour es: the unit st atien transformere from the main generator or the 161-kV transniotion system through the cooling tower transformers.
If a cooling tower transformer in lost, the unit enn continue to operate since the station transformer is in service, the other cooling tower transformer is available, and four dicoel generatore are operational.
The 4-kV bus tie board provides the shutdown boards with backup access to the offsite power system through the common station service transformers.
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 boardo, and all emergency 480 V power boards are operable.
There are five 2',0-volt d-c battery systems each of which consists of a bat.tery, bat.tery charger, and distribution equipment.
Thr ee of these systems provide power for unit control functions, operat ive power f or unit motor loads, and alternative drive power for a 115-volt a-c unit preferred motor-generator net.
One 250-volt d-c system provides power for common plant and transmission cyst em control functions, drive power f or a 115-volt a c plant preferred motor-generator set, and emergency drive power f or certain unit. large motor loads. The fifth battery system delivers control power to a 4-kV shutdown board.
The 250-Volt de system is no 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 pouer to any engineered safeguard control
(-
9002826-327 Ameruknent No. 28
ENCLOSURE 2 JUSTIFICATION (TVA BFNP TS 135) l l
90028246 1
l
Change Requested Removal of interlocks associated with either shutdown bus breakers 1612 and 1622, or 1712 and 1722 and bus tie breakers 1642 or 1742 to allow either shutdown bus 1 or shutdown bus 2 to provide power to the 4-kV bus tie board.
Power to shutdown bus 1 and 2 will be provided during unit 1 shutdown through:
1.
Backfeed from unit 1 500-kV main transformer through unit 1 station-service transformer.
2.
Unit 2 generator through unit 2 station-service transformer.
3.
Common station-service transformer 1 and 2.
Reason for Request
To provide a temporary second off-site power source to the unit 3 4-kV shutdown boards through the 4-kV bus tie board.
The interlocks on these breakers prevent the cross tie of the cooling tower transformer with transformers supplying shutdown bus 1 and shutdown bus 2.
The cooling tower connection to the bus tie board has been physically removed until repairs are completed.*
Other Considerations Alternate power from the unit 3 4-kV bus tie can only be provided to either of the units 4-kV shutdown board pairs 3EA and 3EB or 3EC and 3ED.
This limitation is due to the shutdown bus 1 and shutdown bus 2 feeder breaker 1200 amp current ratings.
However, loss of normal offsite power to all four unit 3 shutdown boards would require two independent single failures.
We have verified that the loading and voltage levels will remain within equipment ratings under the worst case loading conditions. We have also verified that existing protective relaying is fully adequate and no changes are required.
See notes A through D on the attached figure.
This figure was included in the enclosure to T. A. Ippolito's 6/23/78 letter to N. B. Hughes of TVA.
90028247
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