ML20126B040
| ML20126B040 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/31/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20126B044 | List: |
| References | |
| NUDOCS 8003030070 | |
| Download: ML20126B040 (31) | |
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WASHINGTON, D. C. 20555 G
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TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT NO.1 1
AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 57 License No. OPR-33 1.
Tne Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendments by Tennessee Valley Authority (the licensee) dated January 24, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and...
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regulatie's set forth in 10 CFR Chapter I; B.
The f acility will operate in conformity with the application, the provisions of the Act, and the rules and regulttions 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 amendmer.t 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.
8 0 0 3 03 o
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a
. 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-33 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 57, 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 s@M c
Thoma
. Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors w.':. ~
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 31, 1980 t
l ATTACHMENT TO LICENSE AMENDMENT NO. 57 FACILITY OPEPATING LICENSE N0. DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:
1.
Ferove the following pages and replace with identically numbered pages:
292/293 294/295 296/297 298/299 The underlined pages are those being changed; marginal lines on these p aces indicate the area being revised.
Overleaf pages are provided
- or convenience.
2.
E,eiste the folbwing page:
1 296a 1
- u. =
l
l QM2 TING CONDITIONS FOR OPCMTION SURYE11MHCE REQUIMf, l
1 3.9 AUKILIARY ELECTRICAL SYSTDi 4.9
,A, lf %ILI ART IUC*
SYSTEM Applicability APP 11eability Applies to the auxiliary slee-Appites to the periodic testins trical power system.
requirements of the a.uxiliary elec trical sys tems.
Objective Objective
- To assure an adequate,eupply of Verify the operability of the electrical power for operation of auxiliary electrice: cysten, those systems required for safety.
Specificatton Specificatton A.
Auxiliarv Electrical Equipment A.
Auxiliary El ec trical F.q u i e~ e n t A reactor shall nut be started 1.
Dic*e1 Cenerators up (r.ade critical) from the a.
Each die s el r.cne r a tor cold condition unless four chall be mant. ally storted units 1 and 2 diesel generators and leaded once e a c h raon t h are operabic, both 161-kV trans.
t o d err.on ? t t a t e o c e r r. r io n al mission lines, two common sta-readinces.
The tect shall tion service transformers and continue for at les:t a one cooling tower transforver one-hocr period at 75: of are operable, and the require-rated 1 nd or grecter.
ments of 3.9.A.4 through 3.'9.A.7 are met.
During s e rno n t h l y 7,e n e -
retor t the diecel A reactor sha.11 not be started geners startinf. air up (cade critical) from the compre
'r shall be liot Standby Condition unless checket (or opere.tton and all of the folloving condi-its ability to recharge tions are satisfied:
air receivers.
The opere-tion of the diesel fuel At least one off-site 161-kV g3 g
gg transmission line and its be denenntrated, and the conuron transforwer are "E
I" available and capable of reach rated voltar.e and, autocatically supplying speed shall be lo p,r;ed,
auxiliary power to the shutdovn boards,
b.
Once per o p e r.) t ifi s, ey.
a test W 1 M conheted 2.
Three units 1 and 2 die sel to demonstrate the crer-generators shall be ope rable.
gency diesel generators vill start and accept 3
An additional source of emergency load vithin pover consisting of one of the following:
A second 161-KY trans-a.
mission line and its 292 Amendment Nos. k J8, 57
,o I:
i 4
LTWttlkc toclTions tot oPERAftow 59tvtlLtxtet M Quta n't_'Lif 4.9.A Austitert tiectrieel toutpoent 3.9.A u titer 7 tiectrieel touta=aat the specified ties sequence.
a i
e or:rnin translormer and t.
Oece e ennth the questity C oo l i tik t% er tron >forener i
of diesel fuel evetlebte capable cf s.npplying power 8h811 be lested.
to ttw s t.n t d.ivo b oa r d s.
j d.
Each diesel generator shall i
be given an annual inspec.
t).
A rwr tn ci;.e abl e unit s tion in e<cordence with l
1 er.d 2 diesel generator.
tuot tvet it,ns b a s ed on the manufacturer's i e c cpus e nd a-k.
Bu s e ? and Boe-ds A vellable tions.
i a
e.
Start buset 1A and 18 are e.
Once a santh a semple of enerptted diesel feel shall be checked for quell 87 The quellt?
t'.
- he s i' ? I and 2 b-hV ehall be withle the ortepte-l' shutdown t.vards are ble limits spec t f led in energ6tet Tetle 1 of the latest ea" icon i
~~ ~ t A 1008Cd.
f c.
The k60-. s h u ' j e.vn b>,ard s e s s or t e '. e i with the unit 2.
D.C. Powei sitten - Unit patteries (250-Volt) Die sel Cener at or ar e enerv::ed letterlee (175 tolt! and shut down 4
board latterles (MO-vol:)
d.
Und e r vel t.c r e l e > =,
i operetle
.r s '. a r t a,
Every week the specifte buses 1A and 18 and k.6 y gravity ead the % 1tage nf shutdovn toords, A, B,C, the pilot cell, and trapeta.
and P.
ture of an a d j a c e n '. cell and everall bettely wei tage thall 3.
The ISO Vo!t u r. ! t and e5utdevn be measuseJ and lotted.
board betterles and a battery 1
cher6er for eacn bat tery and uty ree tent e the see-assoc iat ed be t te r y boarde are outement s M. ell Se== e d e of voltsge of e ach cel; to meanst 0.1 vo l t. erectric 6.
Legte spetese gravity of e a c h c e l l. and te-pera ture of eve r y f it c h
.. C e ac cid,ni.ignai cell. The s e me s au r e men t e logic ersten le operable.
shall be logged.
b.
440-V loed shedding logic A ba W O ra w m eM ye c.
system te operatie.
(empacity) test shall be 90 d. age, perfe red W tuo, and outuut current 7.
There shell be e aidnieve of 101. M0 g ellone of 41, set to,g mes m eront6 shall be logged la the stendt; diesel genere, et ut.rnis not to onesed tor fuel tense.
24 conths.
293 AmendmentNos.34 p(, 57 i
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^ - - - - - - - - -.
SmtVEILLANCE REQUIREMENTS LgMITINC COHf1(T10HS F0,R OFF"KATION
).9.A Austitary Elect rical Equipment 4.9. A Auxiliary Electrical Equipment 3.
Logic Syst ems a.
Both divisions of the common accident signal logic system shall be tested every 6 months to demonstrate that it will function on actuation of the core spray system of each reactor to provide an auto-natic start signal to all 4 units 1 and 2 diesel generators.
b.
Once every 6 renths, the condi-tion under which the 680-Volt load shedding legic sys tem is required shall be s i mu la t e d using pendant test twitches anc / o r pushbutton test rvitche s to de-monstrate that the load shedding logic systes vould initiate lead shedding signals on the die cel auxiliary boa rds, reactor KOV boa rd s, and the 480-Volt shut-desm boards.
4.
Underveltage Ralays s
a.
On c e e ve r y 6 moc c h e, the con-dition under which the unde r-voltage relays are required shall be simulated with an undervoltage oc start buses lA and IB to desonstrate that the diesel generatora vill start.
b.
Once every 6 months, the con-ditions under which the und er-voltage relays are required shall be simulated with an undervoltage ce each shutdevr.
board to demonstrate that the associated diesel generator vill start.
c.
The undervoltaic rela ys which start the diesel generators from start buses LA and and the 4-kV shut down bea rd s,
shall be calibrated annually f or trip and rese t and the l
maasurements logg ed.
294
i LIMITINC CONDIT10M5 POR OPERAT!0N SURVEll.l.ANCE LIOUIREMENTS
~;
3.9.3 Operation with Inoperable 4.9.3 operation with Inoverable
$4wipment kuipment Vbenever a reactor is in Startup a
mode et Run anode and not in a cold condition, the availability of 1
electric power shall be as speci-j fied im 3.9.A. except se specified hersia.
i t
i 1.
From and after the date that 1.
When one 161-kV line or one commom i
one 161-kV line or one common station transformer and its parallel l
station transformer and its cooling tower transformer and 4 kv f
parallel cooling tower bus tie board or one start bus is transformer and 4 kV bus found to be inoperable, all units tie board or one start bus 1 and 2 diesel generators and becomes inoperable, reactor associated boards must be demon-t operation is permissible strated to be operable immediately under this condition for and daily thereafter.
s even days.
2.
When one of the units 1 and 2 2." Wen one of the units 1 and 2 5
diesel generator is inoperable, diesel generator is found to be continued reactor operation is inoperable, all of the CS. RHR l
permissible during the succeedinr.
(1,PCI and Containment Cooling) 7 days, provided that both off-Systems and the remaining diesel d
eite 161-kV transmission lines generators and associated boards I
and both common station trans-shall be demonscrited to be operable f o rme r s o r one common t r ans fo rme r immediately and daily thereaf ter.
and one cooling tower transformer (not parallel with the energized coasson transformer) are avail-able, and all of the C5, RXR (1.FCI and Coatsinnent Cooling) Systems, and,ths remaiaing three units 1 l
and 2 diesel generators are operatie.
If this requirement i
canadt Te set, an orderly shut-dows shall be initiated and both reacters 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 />.
295 I
l Amendment Nos, g, fd, 57 l
1 i
a
SultVtli.LANCr. Agou! AWEXTS LAMfT ist Casdo,1,T,fM M 011 RAT 10H 3 9.A gerattonwitle taeperable
. 4.9.3 operetten with Inoperable Eauipmen t h uipment 3
When one units 1 and 2 L-kV sh'utdown board is inoperable, continued reactor operation is permissible for a period not to exceed 5 days, provided that both off-site 161-kV traner.iesion lines and both common ttation transformers or one cosmon transformer med one cooling tower transformer 1 When one 6-kV shutdovn board is and 4-kV bus tie board found to be inoperable, all are available and the remain-remaining 4-kV shutdove bestda ing L-XY shutdosm boards and and associated diesel geners-as s ociated die sel generators,
CS, una (LPCI and Contaisment tors, CS and RKR (LPCI and Ccoling ) Systeos, and all k80 V Containment C ooling ) Systems energency power boards are supplies by the r ema inir.g 4-kV cperable.
If this requirenent shutdown boards shall be decon-c anc.ct te r.et, an orderly shut-strated to be operable. inte-dovr. shall be initiated and distely and daily thereafter.
bo t h reactors sball be shutdovn and in the cold condition within 2L hours.
i k.
Fron and after the dste that one of the three 250 Volt unit bat-terles end/or its associated battery boa rd is found to be ci%
inept.'a ol e for any reason, continued res ctor operatien is partissible during the succeeding seven days.
Except for routine curveillance testing the NRC shall Se 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 tha f ailed cooponent to an operable state.
l S.
From and after the date that one of the four 250-volt shutdown 296 Amesdment Nos, M Kf,' 57 1'
}j SURYE11.1 ANCE req L1MITIN,C r.ONn1TIONS FOR OrtstATION 3.9.3 Operation with lueperabic 4.9.8 Operation (,
gerable Equipment f.quipment l
board batteries and/or ita l
associated bettery board is found to be inoperable for any reason, continued reac-tot operation is permissible duttnr.the succeeding five days j
l in accordance with 3.9.8.4.
l
)
I j
l l
l l
f.
When one division of the 1.or,1c System in inoperable, continued re:,e t or crcrat ion te permissible under thin condition for seven days provided the CSC:1 tervire-
~~
i
~ ~ ~ ~
ment s liste'ri in wrecifiCAtton l
3.9 H.2 are satisfied. Thc NRC I
shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I
of the situnion,'the precautions to be taken 'uring this period anc the plann to return the failed comleonent to an operable state.
l 1
297 Amendment Nos. M 57 L
t 4f tcTpre, COffDfTION.e, F0Q OPEFAT10N SURVEIL!Ah!
XDns 1.9.C Operation in Cold Shutdove Whenever both reactors are in cold i
shutdown condition with irradiated i
fuel in either reactor, the avail-ability of electric power shal.1 be as specified in section 3.9.A except as specified here14.
i 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:
I
- a. One 161-kV trans aission line and its associa t ed con:raon sta tion t ransfor.er either cooling tower trar.sformer and a 4 V bus tie board i
capable of supplyi.ag power to the Units 1 and 2 shut-down boards.
- b. A third operabic ciesel i
generator.
3.
At least' one 480-V shatdown board for each unit mus t be operable.
298 A endment Nos. Je[, [, 57
~w 1
3, 9 4Anfg t
The objective of this specification is to assure an adequate source of l
electrical power to operate f acilities to cool the plant during shut-devng and to operate the engineered saf eguards following an accident.
Ther) are three sources of alternating current electrical energy avai)able,namely, the 161-kV transmission system, the nuclear geners-ting units, and the diesel generators.
The 161-kV offsite power supply constate of two lineo which are fed from
,liffbrent acetiona of the TVA 161-kV grid.
In the normal mode of opera-tion, the 161-kV aystem is operating and f our diesel r,enerators are opers-tionhl.
If one dieael generator Is out of service, there normally remain j
the 161-kV sources, the nuclear generatinp, units, and the other three diesc1 generators.
For a diesel generator to be considered operabis its associated 125 V battery must be operable.
The minteum fuel oil requirement of 103.300 gallone 1o sufficient for 7 day = of full fond operation of 3 diesels and is conservatively based on availability of a replenishment supply.
Auxiliary power for Browns Ferry Nuclear Plant is supplied f rom two sources; either the unit utntion transformers or f rom the 161-kV transmission system through the l
c ommon. t at ion transformers or the cooling tower transformers.
I f a common s ta t ion s
transformer is lost, the units can continue to operate since the unit station trans-f o rme r s are in s e rv i c e, t he ot her connon stat ion t ransf ormer and the cooling tower l
I t rans f o rmers are available, and four diesel generators are operational.
cz"2-A 4 -AY nhuutovn board is allowed to he out of operation for a brief period to allow for maintenance and testing, providing all remainint 4-kV shutdown kontds and sw=ociated diesel generators CS, RHR, (LPCI and Containment Coo l in r. ) S y.a r ema supplied by the remaining 4-kV shutcovn boards, and all eme rgenc y 480 V power boards are operable.
There erc etAht 250-vnit d-c battery systems each of which conslot s of a hatterv, battery charger, and distribution equipment. Three of these sys-tems provide power for unit cont rol f unctions, operat ive power for unit nator I n ul*, and alternative drive power for a ll5-volt a-e unit preferred antar-pencrator act.
One 250-volt d-c system provides power f or conson plant and tranamtselon aystem control functions, drive power for a 115-volt n-c plan ( p re fe r f ell mo t or-gCnC ra to r se t, and emergency drive power for certain unit la rge mot o r load s. The four remaining systema deliver con-trol power to the 6160-volt shutdown boards.
299 Amendment Nos. M %, 57
I g># Rich UNITED STATES 8
NUCLEAR REGULATORY COMMISSION y
g i
5
- E WASHINGTON, D. C 20555
)
f o
gh TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSt' Amendment No. 52 License No. DPR-52 1
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendments by Ter.nessee Valley Authority (the licensee) dated January 24, 1980, complies with the standards and requirements of tqe Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and....
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regulati(1s set forth in 10 CFF. Cnapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulat,ons of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangerinc 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 amendmen; 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 amendmen; is in accordance with 1C CFR Part 51 of the Commissien's regulations and all applicable requirements have oesn satisfied.
1
2.
Accordingly, the license is amended b:
anges to the Te:hmical S;ecifications as indicated in the attachment to this li:emse arendmnt and paragraph 2.C(2) of Facility License No. COR-52 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Speci#ications contained in Appendices A and B, as revised through Amendment No. 52, are
' ereby incorporated in the license.
The licensee 1shall operate the facility in accordance with the Technical Specifications.
3.
T.is license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULA F Y l0MMISSIO.1 hffa Thomas',A. Ippolito, Ch'ef Operating Reactors Brard M Division of Operatina 'ea ct:rs c= =.
A-t ac.me r.t :
C.anges to the Technical Sce:ifi:ations C.ite af Issuance:
January 31, 1980 l
l i
f
ATTACHMENT TO LICENSE AMEN 0 MENT NO. 52 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:
'l.
Remove the following pages and replace with identically numbered pages:
291/292 293/294 295/296 297/298_
299/300 The underlined pages are those being changed; marginal lines on these pages indicate the area being revised.
Overleaf pages are provided for convenience.
2.
Dele'te the following page:
296a
' i il i
i
- 3. 6.C/4.8. C Mech *"ic'I V8C""" ' " " '
i the T%c purpose of isolating the mechanical vacuum pump line is to limit release of activity f rom the main condenser.
During an accident, fission transported f rom the reactor thrnugh the main steam lines p roducts would be to :he condenser. The fission product radioactivity would be sensed by the isolation, mais steam line radioactivity monitors which initiate i
4.1. A and 4.E.!
BASES T he s u rv e i'. l a nc e requirements given under Specifiestion 4.8. A and 4.6.5 liquid and gaseous vastes are properly controlled p r r v ist e assurance that art -o c. i t o r e il d u r i, A any release of radioactive materials in the liquid ar; caseous effluenta. 'These surveillance requirements provide the data fer the licensee and the Commission to evaluate the s ettion's pe rf or ance r e '. a t i v e to radioactive wastes released to the environment. Feports on t h 'quan t itie s of radienctive mAterisis released in effluents shall be furnis5ed to the Comnis s ion on the basis of Section 6 of these technical On the basis of such reports and any additional informs-spec ific a tie na.
tion the Commis s ion may obtain from the licensee or others, the Comp.ission may from tine to time require the licensee to take such actions as tne ccumission deems appropriate.
can
- 3. S. D a r.d 4. S. 0 BAsrs De objective of this specification is te assure that leaka g e from j
t.*pr oduc t, source, and special nuclear radioac tive material sources d:c a r.o t exceed allowable limita.
291
i 1
i SURVEll. LANCE REQUIRCMr.NTS
,1.!NITINC CONDITIONS TOR OPERATION 4
3 i
3.9 AUKILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM Applicability
. App li c a b ili t y_
9 j
Applies to the auxiliary elec-Applies to the periodic testing requirements of the auxiliary trical power system.
electrical systems.
1 Objective Objectiv_e l
To assure an adequate supply of Verify the operability of the electrirsl power for operation of auxiliary ciectrical system.
those systems required for safety.
j Specification Specificatten I
A.
Auxiliary Electrical Equipment A.
Auxiliary El ec t r ical F.quipment l
A reactor shall not be started 1.
Dicael Cenerators l
up (made critical) from the i
's,
Each diesel r.cnerator
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}
cold' condition unless four chall be manually s t a r ted l
units 1 and 2 diesel generators and loaded once each month are operable, both 161-kV trans-to demonstrate operational mission lines, two cor.rnon sta-readiness. The test shall tion service transf ormers and con,tinue for at least a i
one cooling tower transf ormer one-hour period at 75Z t i
are operable, and the require-rated load or greater.
l ments of 3.9.A.4 through 3.9.A.7 are met.
During the monthly gene-I rator test the diesel A reactor sha.11 not be started generator startint, air e
up (made critical) from the
- N**
l Hot Standby' Condition unless
. r opun t i n and all of the following condi-its ability to recharge tions are satisfied:
air receivers. The opera-ti n i the diesel fuel l.
At least one off-site 161-kV il CT8"MICr Pumps shall transmission line and its be demonstrated, and the eosunon trans former are diesel starting time to available and capable of reach rated. voltage and.
automatically supplying speed shall be loRged, auxiliary power to the shutdovn boa.rds.
b.
Once per ope r.s tin.' ey e "
s test will be conducted 2
Three units 1 and 2 diesel l
t demonstrate the emer-generators shall be operable,
gency diesel generators vill start and accept 3
An additional source of emergency load within power consisting of one of the following:
A second 161-kV trans-a.
mission line and its 292 Amendment Nos.)f, M 52
ST Rv tl t L A.vC t 1.t QU l t N !'C f I
LINTYlNC COVOIT10lli FOR OP t%AT 10w 1,9.A aust11ery tiect riest toutpoent 4.9.A Auxillery f l e c t ri e e l 14ut teen _t ti,e epec1 fled (Las sequence.
c ocr.on transIorTner and c.
Doce a month the quantity c oc'l i ng t ow e r t r ant. f o rv.e r of diesel fuel available capable of supplying power shall be logged, to the shutdtvn boards, d.
Each dieert genera tor shall be giver, an annus! I M *,p e e -
b.
A fc fLh Opfrat;e u.n!ts.
'I'"
I" d**f' "I8h I a n: I ciese; generator.
instructicas beeed on the aanwfacturer'e
- c cane e n d a -
L.. Ases v.d ha r d s availatle tg,n,,
e.
Ne a e,3 nth a eacFle of a.
Start bubes 1A and 18 are
'OfflIt'U' diesel fuel sha ll be checked for quality The twality t; Tre
- v. a t t, 1 and O l.
k V ehall be within the orcepte-snuscovn Leares are ble 1 =tts spectfled la energinee.
Table 1 of the latest revision e
7 n
- 1. 8 c -. S t., ' d '; *t b o a.r c s assorasted =>tr the unit 2.
D.C.
Po-cr 4vi!!, - Unit latteries (250-vott) Ctesel Cenerator are energ::co
('
la t t e r l e e (I M vol t !'e4 5%tdovn Soord lattertes (150-vol:)
d.
Und e r v el i ns e re;sys opereele cr. S'. art s.
Every week the spe c if ic buses 1A a r.d 19 a nd L -4 y shutdow'n boeras. A, B, C,
3ravity and the voltage af the Pilet
- ll.
8^d trer(Id-and D.
ture of an adjacent fell and overall battefy voltage thall S.
The 250-volt ucit and e 5u t d on board bat terles a6: a battery charget for eacn tattery end b.
Every three cenths the ses-secociated battery boarde are swresents ' ell h *ade of operable.
ve]Lege of e ach celi to oesteSt 0.1 volt. 8PeCIIIC 6.
Logic $ystees gg,yggy of e a r n c e l l, an d temperstwee of ever7 Illth f
a.
Cosamo s ac c i d e n t s i g r. a l cell. These easeveemente logic syste te operable.
og g3 5, legged.
b' 480-7 lead shedding logic A. ba ttec raw disWye c.
(e.pa ci y ) test ' hill b(
erstes le *Perable-t pe,. r c re d irs tne v o '. '.e e.
7 There shall be a *J n izoe o f gg, 3n: catout carrent
- 10) 300 galloao of diesel fwel
,,3 3 g 7,,,,, t s snail be IcHed to the standby diesel genere-gg.fgeyvais net to exceed toe f uel t ar.ke,
p
.293 Amendrnent Nos. [ 52
)
d 2 [..C'l'#"'T10H.(F0R_0P QAT10N StntY El1.1. ANC E R.EQU 1 R Ew? NT5 e
.9.A Ausi t t e ry Ciecteical Equipment 4,9,A Auxiltery Electrical Eeulpment
)
3, Logic Systeen a.
Both divisions of the c newen j
li accident signs! logic system shall be teuted every 6 months 1
to de
- nstrate that it will function on actus tion uf the I
core spray system of each reactor to provide an auto-ma t i c s t a r t sitnal to all 4 2
units 1 and 2 diesel l
generators.
I b.
Onc e e v e r y 6 ren t hs, the cendi-tion under which the ABO-volt 4
load sheddir.g legic system is required shall be simulated using pendant test vvitches and/cr pushbutton test svitches to de-monstrate (b s e the lo.1d o be dd ine
-logic system would initiate load shedding signals on the diesel auxilia ry boards, resetor Mov boards, and the 480-Volt shut-d evn be s t d s.
3 i
4.
Und e rvo l t a g e Relays cr n?
a l
4 a,
Once eve ry 6 roo tha, the :en-dition under which the under-l voltage relays are required shall'be simulsted with ac und e rvo l t a g e oc start buses 1A and IB to deaanstrate that j
the diesel generatora vill start.
b.
Once every 6 months, the con-ditions under which the under-voltage relays are required shall be simalsted vith at und e rvol t a g e on each shutdevn board to demons t r at e that the associated diesel generator vill start.
c.
The undarvoltage relavs which start the dicoel generaters from start buses LA and 11 and the 4-kV shutdosm bcr:d r,
I oball be calibr a ted anenallf for trip and reset and the i
mea surement s logg ed.
294 1
i
EURVt1Lt.ANCE R10VIRth.
LIMITINC CONDITIONS FOR OPERATION 3.9.8 Operation with inoperable 4.9.3 operation with lace _ 3 huir'eent h uipeent_
Whenever a reactor is to Startup mode of Run mode and not in a cold condition, the svallability of electric power shall be se speci-fled in 3.9. A. eacept as specified berein.
1.
Fror and after the date that 1.
When one 161-kV line or one commom station transf ormer and its parallel one 161-kV line or one comon cooling tower transfomer and 4 kV station transfomer and its bus tie board or one start bus is parallel cooling tower found to be inoperable, all units transf omer and 4 kV bus 1 and 2 diesel generators and tie board or one start bus associated boards must be deson-becomes inoperable, reactor strated to be cperable ircediately operation is pemissible and daily thereafter.
unde r this condi tior, f or seven days.
2.
W an one of the units 1 and 2 1.
Wen one of the units 1 and 2 diesel generator is found to be diesel generator is inoperable, iAoperable, all of the CS, R.ER continued reactor operation is (LFCI and Containment Coolir.g) permissible during tne succeedinr.
7 days, provided that bcth off.
Systems and the reuining diese; generators and ar s ciated boards site 161-kV transmission lines shall be demonst:
ed to be operable and both cr mon station trans.
lanediately and
- y theraaf ter.
formers or one commen transformer and ons cooling tover transformer (not parallel with the energized common trans fermer) are avail-able, and all of the CS, RHR (LFCI and Containment Cooling) Systems, and the remaining three units 1 and 2 diesel generators are operable.
If this requirement cannot be met, an orderly shut-dovn shall be initiated and both reactors shall be shut dovn 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 />, t
295 Amendm.ent Nos.
[, 52
4 Meetil4 CdusDI,T,fg g et'rsAT1h*f
_ All4 VE I t.LANC F. R tt7u ! R DeF.NTS 3 3.a senit.n with to.perable 4.9.s operation with inoperable u l pme n's E491pment
~
3 When one ur.its 1 ar.d 2 L-kV shutdown board is inoperable,
continued reactor operation is permissible for a period not to exceed 5 days, provided tha t both of f-site 161-kV tranrr.ission lines and both common station transformers i
or one cosmon transformer sud ene coeling tower transformer and 4-kV bus tie board I
when one 4-kV shutdovn board is are a' aila'c;e ard the remain.
found to be inoperable, all v
4 ics L-kV shutdovn boards and re ma ining 4-kV shutdevn besids j
associated diesel generators.
and associated diesel geners-CS, RHR (LPCI Lnd Contailment tors, C5 and RHR (LPCI and 3
(
Ceoling ) Systems, and all k80 V Containment C oo ling ) Systeos energency power boards are supplies by the r e ma i n i r.g 4-kV 8
l cperable.
If this requirenent shutdown boards shall be de=oa.-
j canc.ct te cet, an orderly shut-strated to be operable. i nc. e -
)
i dovn shril be initiated and diately and daily thereafter.
both reactors sbtil be shutdovn and in the cold condition within 2L hours.
I b.
Fron and after the date that one of the three 250 Volt unit bat-4
' _ ~, ",,
i taries and/or its associated battery boa rd is found to be inopora cle for any reason, 3
continued rea ctor opera ties is l
Permissible during the succeeding seven d9ys.
Ex c e pt for routine curveillance testing the NRC i
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 cit ua tion, the precautions to be taken during this period and the plans to return the failsd component to an operable
- state, i
{
5.
From and after the date that ons i
of the four 250-volt shutdown d
1 j
e 296 AmendmentNos.M)P(,52
LIMITING f0N71T10ss FOR orr#1710N
$URVEILL ANCT. RF.Q'J1REw.ENTS 3.9.0 Ogeration with luoperable 4.9.8 Operation with Inoperable
[rgulpment Equipmera t board batteries'and/or ita associated bettery board is fcund to be inoperabic for any reason, continued reac-tot operation is permissible durine the succeeding five days l
in ac:ordance with 3.9.B.4 l
f.
When one division of the Logic System 19 inoperable, continued rc.ctor c;cration is permissible under thfn conditton for seven dayo, provided the CSCJ c c r,u i r e -
p.e n r e listed ;n <pect'icatten 3.9.H.2 are sati:fied The NRC shall be notified uithin 24 hnuts of the s!!us*.lon,'the precaution:
to be taken Juring this p:riod an.
the plans to return the failed r
comioonent to an operable state.
n..... -
297 AmendmentNos.g,52
~
(IfGTPff; flOflDITIO!!r, FOR OPERATXON SURVEXLLANCE ht"DLTIRPMDrTS
+
4 1
1.9.C Operation in Cold shutdown Whenever both reactors are in cold i
shutdown condition with irradiated 4
fuel in either reactor, the avail-i ability of electric r*wer shall ba as specified in see'.sn 3.9.A except as specified herein.
1.
At least two units 1 and 2 diesel generators and their associated 4-kV shutdown boards j
shall be operable.
[
An additional source of power 1
consisting of. at Isast one of l
the following:
- a. One 161-kV transmission linc and its associated couanon station transformer either l
cooling tower transformer d
and a 4 kV bus tle board capable of supplying power to the Units 1 and 2 shut-down boards.
i
- b. A third operable diesel generator 3.
At least one 480-V shutdown board for each unit must be operable.
4 l
l 298 f'
Amendment Nos. g g 52 a.
o I,
t
- 3. 9
.M.A.%.F. '.
The objectIvr of this unecification in to assure an adequate nource of electrical power to operate facilitten to con 1 the plant during, shut-down and to operate the engineered soleguntds f ollowing an accident.
There are three sources of alternating current electrical energy availatic, namely, the 161-kV t ansmission systen, the nuclear geners-ting units, and the diesel ger setors.
The 161-kV offsite power supply constata of two linen which are fed from ill f f e r e n t acetion* of the TVA 161-kV grid.
In the normal node of opera-tion. the 161-kV aystem is operating, and four diesel generators arc opere-tionnl.
If one dicact generator is out of se rvice, the re normally r e r.a i n the i t.14 V si'u r c e s, the nuclear generating units, and the other three diesel generators.
For a diesel generator to be considered operable its asacciated 125 V battery nust bc operable.
The mininum fuel oil requirement of 103,300 gnilons 10 sufficient for 7 daya of fuli lond operation of 3 diesels and is conse rva t ively ba sed on replenishment supply.
evollnbility of a
nuxiliary power for Browns Ferry Tuc1 car Plant i t, sapplicJ tron twc sourc, i :t er
- ne unit *tation t r a n c, t' o r re t t ec frce the 161 - k'l t r.tnsmi s :
'n system throui ' ar concon st at jan trarsformers n: the cooling tnwer *ransformor;.
I f a comon,.at:on transforact is lost, the units can cont inue to crerate since the unit stat ua tr ns-i n r'ne t, are in s e rv i c e, the other comon stat ic n transforner and the c oo l i c (c.or t rans f onners are available, and four diesel ger.eratars are operaticnal, t..'.'
A 4-kV nhu u'evn boa rd is allowed to be out of oper3 tion for a brief rcried te allow for n.3!ntenance and testing, providing a'.1 remainint 4-kV shutcovn hontds and awaociated dicac1 generators CS, RHR, (LPCI and Containment Cooline) Syntema supplied by the remaining 4-kV shttdosv. boards, and all emergency 480 V power boards are operable.
There ore eight 250-vnlt d-c l>attery systerr. cc: af ut.!:5 c e r. 9 t o ! 3 ;f a battetv, bd(terf charger, And distribotlon r;u ' p en t
~hree c. f t h a.s e sys-temn pr ov id e power for unit control functions, oteta;ive power for ur.it intor Inwh, and alternative drive power for a 1 : 5 - v c '.
- a-c unit preferred mntnr-pencrator act.
One 253-vo!! d-c ev9 ten :r:v; des rever for corr. -
plant and trana-t=91on avste-co trol functicns, srivo oower for a i;5-v:.:
a -r plant reeferrei motor.cocrator se t, and e cir.cnc y cr ive powe r for l
certain unit large motor loads.
Toe four remaining systems delive r con-trol pnwer to the 4160-volt shutouvn boards.
299 Amendment N0s.
52
1,9 BASES Each 250-volt d-c shutdown board control power supply can receive power f rom its own battery, battery charger, or froe a spare char ge r. The chargers are powered f rom normal plant auxiliary power or from the standby diesel-driven gene stor system. Zero resistance short circuits between the control power supply and the shutdown board are cleared by fuses located in the r espec t iv-contrcl power supply. Each power ur ly is located in the reactor building near the shutdown board it supplies.
Each battery is located in its own independently ventilated battery room.
The 2 50-volt d-c systet is so arranged, and the batteries sized such, that the loss of any one unit battery will not prevent the safe shutdown and cooldovn of all chree 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 safeguards control circuit is annunciated in the main control room of the unit affected. Th e loss of one 250-volt shutdown board batte ry af f ec ts normal cor.t rol,ower only f or the 4160-vol t shutdovn board which it supplies.
~h s t at ion bat te r/ supplies l e:.j s that are not essen-tial f or saf e shutde n and cooldown of the nuclear system. This battery was not considered ir. the accident load calculations.
300
[
UNITED STATES oq
'n NUCLEAR REGULA'f0RY COMMISSION 1[Alj E
I o WASHINGTOtI, D. C. 20$55
% *)N
%,vfa o
f
...e TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT N0. 3 AMENDMEllT TO FACILITY OPERATING LICENSE Amendment No. 30 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 January 24,19E9, complies with the stanfards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and..
" ~ '
regulati[qs set forth in 10 CFR Chapter I; B.
The facility will operate in confor.Tity with the application, the provisions of the Act, and the rules and regulations of the tomission 1
C.
There is reasonable assurance (i) that the activities authorized i
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 1
commot defense and security or to the health and safety of l
the p61ic; and E.
The issuance of this amendment is ir accordance with 10 CFE Fart 51 of the Commission's regulations and all applicable requirements have been sa-isfied.
'i II
l
. 2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license arnendrnent and paragraph 2.C(2) of Facility License No. DPR-68 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 30, 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 COMiilSS10N
'WM' A'.Nppolito, Chief uIs-4:>
Thomas Operating Reactors Branch e3 Division of Operating Reactors
Attachment:
Charges to the Technical Specifications Date of Issuance: January 31, 1980 i
ATTACHMENT TO LICENSE AMENDyNT NO. 30 FACILITY OPERATING LICENSE N0. DPR-68 DOCKET NO. 50-296 Revise Appendix A as follows:
l l
1.
Remove the following pages and replace with identically numbered pages:
324 325 327 2.
Marginal lines on the above pages indicate revised area.
~
l l
t f
i l
l l
1 l
LIMITING CONDITIONS FOR OPEPATION SURVEIIIANCE REQUIRI'
When one unit 3 4-kV 3.
When one unit 3 4-kV shutdown board is shutdown board is "
inoperable, continued found to be reactor operation is inoper abl e, all permissible f or a remainine unit 3 4-kV period not to exceed shutdown boards and 5 days, provided that associated diesel both of f sit e 161-kV generators, CS and t ransmission lines RHR (LPCI and and both cooling tower Containmont cooling) transformers are Systems 5.upplied by available and the the rema_ninq 4-kV r emain i ng unit 3 4-kV shutdown boa r ds shall shutdown boards and be demonstrated to be associa ted diesel operable, immediately generators, CS, RHR and daily thereaf ter.
(LPCI and Containment Cooling) Systems, and all unit ' 480-V emergency power boards are operable.
I f this requirement cannot be met, an orderly shutdown shall be initiated and the reactor shall be shutdown and in the cold condition within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> s.
AmencmentNos,J/I,)MI,30 324
LIMITING CONDITIONS FOR OPEP.ATION SURVEILLANCE REQUIREMENTS 4.9 AUXILI ARY ELECTRICAL SYSTEM 3.9 Al'XI L1,kRY ELECTRICAL _SYSTQ1 4
From and ofter the dele t hat the 250-volt Nhu s.hiwn board lua t et ien or one of the three 250-volt un2t batteries and/or its associated battery board is found to be inoperable for any rea son, continued reactor operation is permissible during the succeeding seven days.
Except for routine surveillance t es t in g, 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 durina'this period and the plans to return the f ailed
' com ponen t to an operable state.
-l S.
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 Specif ication 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 t he s it ua t i on, the precaut ions to ba taken dur inq this period an.) the plans to ret urn the f ailed l
component to an operable state.
325 Amendment flos. pf, M 30
3.9 BASES The ob ective of - this specification is to assure an adequate l
source of e lect ri ca l power to operdte f acilities to cool the unit during shutdown and to operate the engineered safeguards following an accident. There are three sources of alternating current ele trient ane rry available, nnmely, the 161-kV transmission system, the 1
nucienr vararnting unita. and the dicael generators.
Tho 161 - k V of i nit e powe r supply consists of two lines which are fed f rom dit t erent sections of the TVA 161-kV grid.
In the normal mole of operation, the 161-kV system is operating and four diesel generators are operational.
If one diesel generator is out of se rvic e, there normally remain the 161-kV sources, and the l
other thr ee diesel generators.
For a diesel generator to be considered operable its associated 125 V battery must be operable.
1 The minimum fuel oil requirement of 103,300 gallons is sufficient for 7 days of full load operation of 3 dieselo and is conservatively based on availability of a replenishment supply.
Of feite auxiliary pmer for TrNns Ferry Nuclear Plant Unit 3 is supplied frorr.
two scurren: the unit et tti n transfomers fror the main generator or the 161-kV
' r ar. m l a " l on > va t a. through t re accling tover transformers.
If a cooling tower t r o fc cm"r 19 loot, tha u rd ' crm contir.ae to operate since the station j
t r ann fo nn. r 15 in sarvice, tv i ti ar cciolinE tower transformer is available, and four diconi generntora nra perational.
A 4-kV chutdown board is allowed to be out of operation for a brief period to allow f or maintenance and testing, providing all remaining 4-kV shut.down 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.
There are five 250-volt d-c battery systems each of which consists of a battery, battery charger, and distribution equipment.
Thr ee of these systems provide power for unit control functions, operative power f or unit motor loads, and alternative drive power f or a 115-volt a-c unit preferred motor-generator set.
One 250-volt d-c system provides power f or common plant and t.ransmission system control functionn., drive power for a 115-vol t
.s-c plant preferred motor-aenerator net, and emergency drive power for certain unit large motor loads. The fif th battery syster:
delivers control power to a 4-kV shutdown board.
The 250-Volt de system is so arranged, and the batteries sized such, that i
the le of any one unit battery will not prevcnt the safe shutdown and conidown ol all threr units in the event of the loss of offsite power and a des t en basis nectrien t in any one unit.
1.o m a or contral power to any engineerH safeguard control 327 i
i Amendment Nos. [, M 30