ML18283B735
| ML18283B735 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/29/1978 |
| From: | Lear G Office of Nuclear Reactor Regulation |
| To: | Niav Hughes Tennessee Valley Authority |
| References | |
| Download: ML18283B735 (69) | |
Text
p~-:~gQ'ggQR1TY FEE K)PY UNITED STATES NUCLEAR' EQULATORY COMMISSlON-WASHINGTON, D. C. 20555 March 29, 1978 Do N0T RLMO~F Docket Nos.
-259 and 50-29 Tennessee Va11ey-Authority ATTN:
Mr. N. B. Hughes Manager of Power 830 Power Building Chattanooga, Tennessee 37401 Gentlemen:
The CoITmission has issued the enclosed Amendments Nos.. 37, 34 and 11 to Facility Licenses Nos.
DPR-33, DPR-52 and DPR-68 for the Browns Ferry Nuclear Plant, Units Nos. 1, 2 and 3.
These amendments consist of changes to the Technical Specifications in response to your request of March 22, 1978.
The amendments change the Technical Specifications to permit you to provide a third offsite power source by connecting the onsi te 4160 volt distribution system to the 500,000 volt offsite system through the main transformers and station service transformers.
Copies of the Safety Evaluation and Notice of Issuance are also enclosed.
Sincerely,
Enclosures:
1.
Amendment No. 37'o DPR-33 2.
Amendment No.
34 to DPR-52 3.
Amendment No.
11 to DPR-68 4.
Safety Evaluation 5..
Notice George Lear, Chief Operating Reactors Branch
Ã3 Division of Operating Reactor s cc w/enclosures:
see next page
e~
4 h
Tennessee Valley Authority 2
CC:
H. S. Sanger, Jr.,
Esquire General Counsel Tennessee Valley Authority.
400 Commerce Avenue 118 33 C
Knoxville, Tennessee 37902 Mr. D.
- McCloud, Tennessee Valley Authority 303 Power Building Chattanooga, Tennessee 37401 Mr. William E. Garner Route 4,, Box 354 Scottsboro, Alabama.
35768 Mr. Charles R. Christopher
- Chairman, Limestone County Commission Post Office Box 188
- Athens, Alabama 35611'hief, Energy Systems Analyses Branch (AW-459)
Office of Radiation Programs U.S-. Environmental Protection Agency.
Room 645, East Tower 401 M Street, SW Washington, D.C.
20460 U. S. Environmental Protection Agency Region IV Office ATTN:-
EIS Coordinator 345 Courtland Street Atlanta, Georgia 30308 Ira L. Myers, M.D.
State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36104 Mr. C, S. Walker Tennessee Valley Authority 400 Commerce Avenue W 90199 C
Knoxville, Tennessee 37902 Athens Public Library South and Forrest
- Athens, Alabama 35611
c 7
UNITEDSTATES NUCLEAR'EGVLATORYCOMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUT80RITY DOCKET NO. 50-259 BROWNS FERRY" NUCLEAR'LANT'NITNO.
1't1ENDHENT TO FACILITY OPERATING LICENSE Amendment No.
37 License No.
DPR-33 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority
'(the licensee) dated f1arch 22,
'l978, complies with the standards and requi rements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations, and all applicable requirements have been satisfied.
2.
Accordingly,. the license is amended by chanqes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paraaraph 2.C(2) of Facility License No.
DPR-33 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
37;. are hereby incorporated in the license..
The licensee shall operate the facility in accordance with the Technical Specifications.
,C
3.-.
This, license amendment is effective. as. of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION.,
Attachment:
Changes to the Technical Specifications, George Lear,. Chief Operating. Reactors Branch 83 Division of Operating Reactors.
Date of Issuance:
March 29, 1978
0 l
~
~
ATTACHMENT TO LICENSE AMENDMENT NO.
37'ACILITY OPERATING LICENSE NO.
DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:
Remove the following pages and'eplace-with identically; numbered pages:-
292/293 294/295 296/297 298/299 Marginal lines indicate revised area.
Overleaf pages are provided for convenience.
LIMITIHG'ONDITIONS FOR OPERA SURUEII LANCE RF UIR-:
EENTS r.9 AUXILIARY ELECTRICAL SYSTEM
- 4. 9 AUXILIARY ELECTR.ICAL SYSTEM--
t Appl.ies to the. auxiliary elec-trical power system; Applies to the periodic testing requirements of the auxiliary electrical systems.
~Ob ective.
~Ob ective To assure an adequate. supply of electrical power for operation of those systems required for safety..
Ve'ri'fy. che operability of the auxiliary cl.ectrical system..
A.
Auxiliary Electrical E uioment A reactor shall not be started up (made critical) from the cold condition unless four units 1 and 2 diesel generators are operable, both 161-kV trans-mission lines are operable and supplying power to the plant, at least one 500 kV transmission line is operable and supplying power to the plant backfeeding through the Unit
- 2. main and station transformers, and the requirements of 3.9.A.4 through 3.9.A.7 are met.
A reactor shall not be started up (made critical) from the Hot Standby Cond.ition unless all of the following condi-tions are satisfied:
l.
At least one off-site 3.61-kV transmission line and its common transformer are available and, capable of automatically supplying auxiliary power to the.
shutdown boards.
2.
Three units 1 and 2 diesel generators sha'1 be operable-.
3, An additional source of power consisting of one of the following:
A.
Auxili*t El ettticel
~Eui eeet Diesel Generators a.
Each diesel generator shall be manually started and loaded once each month to demonscrate ooeracional readine s.
The ces t shall continue for at least a
one-hour period at 75% of rated load, or greater.
Duririg the monthly gene-rator cesc the diesel generator starting air compressor shall be checked for operacion and its abilicy co recharge air receivers.
The opera-tion of the diesel fuel oil transfer pumps shall be demonstrated, and the diesel starting time to reach rated voltage
- and, speed shall be logged.
b.
Once per operating cycle
- a. test will be conducted to demonstrate che emer-gency diesel. gene ra co r s vill start and accept emergency load within a.
A second 161-kV trans-mission line and its 292 Amendment iso.
37
c
LmTTTNC CONDLTTO??S FOR OPERATTOM SURVEILLANCE RE UMPIRE?ITS-
- 4. 9'. h~ AuxiIiar. El'ectrical E ui ment common transformer or cooling tover transformer (not parallel vith the energized:
common trans"ormer
)
capable of supplying pover to the shutdovn boards.
b; A fourth operable un'ts 1 and 2 diesel generator.
4.
Buses and, Boards Available czd'he-specified. time. sequence..
Once a month the. quaatiry.
of diesel fuel available-ahall be logged.
Each. dieseL g nerator shall'e given an annuaL'nspec-tion. in accordance with instzuctions based on the manufacturer'e':
cormenda-tions.
5.
a.
Start buses M and LB are energized.
b, The units 1 and. 2 4-kV shutdovn boards are energized.
c.
The 480-V shutdovn boards associated vith the unit e"e energized.
d,.
Undervoltage relays opezable on s art buses lA and 1B and 4-kV shutdovn boards, A, B, C, and D.
The 250-Vo'c't and shutdovn board batteries and a battery charger for eacn battery and associated battery boards are operable.
2 ~
eo Once a month a.- sample of diesel fuel shall be checked Eor quality.
The quality.
shall be vithin the accepta-ble limits specified in Table 1 of ASTM D975-68 and logged.
Every veek the speciElc gravity. and the voltage nf the pilot cell, and tempcra-tuze of an ad)acent cell and overall battezy voltage "hall be measured and, logged.
b.
Every three ccnths the mea-surements shall be made of voltage of each cell ro D.C. Povez Syst m Unit Batteries (250-Volt) Diesel Generatoz Batterlcs (125-Volt) and Shutdovn Board Batteries (250-Volt) 7 ~
6.
Logic Systems a.
Common accident 'signal logic system is: operable.
b.,
480-V load; shedding logic system is operable.
There shall be a minimum of'03,300 gallons of diesel fue'n the standby diesel gencz'a-tor fuel. tanks.
Co nearest 0.1 volt,, specific gzaviry of each cell, and temperature oE every fifth cell.
These measurements shall be. Logged.
A battery rated discharge (capacity) t'est shall be performed and the vo3.tage,,
time, and output curre,.t measurements shall be 'ogged.
at in 'ervals not to exceed 20 months.
- 8. At least one offsite 500-kV transmission line backfeeding through the un':t 2 main and station service transformers is available and capable of supply-ing auxiliary power to the shutdown'oards.
Amendment No.
37 293
I 4 ~
~
p
~
%+8>
+
~ 'lt
LIKlTING..COHAQTYOHS FOR' TION SURVEILLANCE RE RVKHTS
) 9 A '>uxiliar 'Electrical E ui ment 4.9.A Auxilia
,Electrical E ui ment 3'.
Logic Systems b..
Both divisions~ of the common accidenc signal logic system.
shall be tested. every
- 6. months to demonstrate-that it Mt.11 function~ on. actus tion<<of the core spray system of each reactor to provide an auto-matic start signal to all 4 units 1 ant 2'diesel.
generators Once every 5 months, the condi-tion under which the 480-Volt load shedding logic system is required shall be simulated. using pendant test'vicches and/o pushbutton cest ~itches to de-monstrate chat the load shedding logic system vould initiate load shedding signals on the. diesel auxiliary boards, reactor
..OV
- boards, and the 480-Volt shut-dovn boards.
4.
Vndervoltage Relays a.
Once every 6 months, chc con-dition under Mh'ch the under-voltage relays are required shall be simulated vith an undervolthge on start buses lA hnd 1B co demonscrace that the diesel generators vill 8th'r't.
b.
Once every 6 months, the con-ditions unde". which the under-voltage relays are required shall be simulaced vith an undervoltage on each shutdown board to deraonscrate that the associated diesel generator vill start'..
294 C ~
The undervolthge relays vhich" start the d'chel generaccrs from start buses lA end 13 and che-4-kV shutdo~a
- boards, shall be calibrated annually for crip hnd resec and the measu'rcments logged
.LIMITIHC.CONDITIONS FOR OPERATION SURVEILLANCE'E UIREHEHTS 3.9'.S.:
eration with Inoperable
~Eut neve Whenever a reactor. is in Startup
<<ode or Run mode and not in a cold.
condition the availability of el'eccric. pover: shall be as speci:-
fied'n 3.9.A, except as specified herein.
4.9.B" eration with Inoperable
'~Eal vent 1'.
Prom and after the date that one 161-kV line or one common station transformer and its parallel cooling tower trans-former or one start bus becomes inoperable, reactor operation is'ermissible under this condition for seven days.
2.
When one of the units 1 and 2
diesel'enerator is inoperable, continued reactor operation is permissible during the succeeding 7 days, provided that both off-side 161-kV transmission lines and. both common station trans-formers or one common transformer and one cooling tower transformer (not parallel v'h the energized common transformer) are ava able, and all of the CS, RHR (LPCI 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-down shall be initiated and both reactors shall be shutdo~w, and, in. the cold condition vithin
- 24. hours.
1, When one 161-kV line or one common station transformer and. its parallel cooling tower transformers or one start bus is found to be inoperable, or when one 500kV line or Unit 2 main or station service transformer is found to be inoperable, all units 1 and 2 diesel generators and associated boards must be demon-strated to be operable immediately and daily thereafter.
2.
When one of the Units 1 and 2
diesel generator is found to be inoperable, all of the CS, RHR (LPCI and Containment Cooling)
Systems and the remaining diesel generators and associated boards shall be demonstrated to be operable immediately and daily thereafter.
295 Amendment No.
K-'
l 0
tin'".(1~'6 ['CF'()8!". I'()K nl'I'.RATlnkf SlNVEl I.LANCF.
R EOlllR L. lRilTS Pnnnpimmeenn ee 4.9;B' eration Mith. ?no crab'e
~En1 en e When one Units 1 and 2 4-kV shut-down board is inoperable, con-tinued reactor operation is per-missible for a period not to exceed 5 days,. provided. that both off-site 161-kV transmission lines and both common station transformers are available or one offsite 500kV source is back-feeding through the Unit 2 main generator and station service transformers, and the remaining 4-kV shutdown boards and asso-ciated diesel generators, CS, RHR (LPC1 and Containment Cooling) Systems, and all 480V emergency power boards are oper' able.
Xf this requirement cannot be met, an orderly shut-down shall be initiated and both reactors 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.
When one 4-kV shutdown board is found to be inoperable, all remaining 4-kV shutdown boards and associated diesel genera-
Systems supplies by the remaining 4-kV shutdown boards shall be'demon-strated to be operable, im-..e-diately and daily thereafter.
Fron and after the date that one of the three 250-Volt unit batme tories and/or its associated battery boar" is found to be inoporable for any reason, continued reac.or operation is permissible during the succeeding seven days.
Except for rour inc wrveillnrce testing the NRC shall be notified within 24-hours of tne situation.,
the precautions to be taken during this period and the plans to return the failed component zo an operable state.
From and after the date that one of the four 250-volt shutdown 296
1E~
4 0
I IHITINC COND?TIONS F
OPf RATION SURVEILLAHCF.
F. UIRE'HFMTS 3.9.5.
caret>>nn c>>th>>nn~cr'e>>>>>>c
~Kul m>> nt board. batterics and/or its associated bcttery board is.
found to bc inopcrablc for any. reason, continued reac-tor operation is pcrnissible durinR thc succc<<dfnZ. five days in>> ac=ordnnce vith-3.9.6.4.
~Eul ment Mhen on<< division of the Logic System is inoperable, continu<<d rc'ctor cpcrat ion 's permissible.
und r this condition for scren
- days, provided the CSCG rcquirc-mcn t r. I' "<<d '
s pec I fication 3.9. M. 2 arc sat i-ficd.
Thc NRC shall bu notified uithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of thc situation, 'rhc precautions to-bc taken
'urinl; this period an the plans to return thc tailed componcn to an operable state.
297
LXI5~X?!4 CQ!iDXTXO?IS FOR OPFRATXON SURVEXLLA?ICE-REQUIRE.!TS-3.9.C 0 eration in Cold. Shutdown Mhenevcr both reactors are in cold, shutdown condition with irradiated fuel in either reactor, the avail-ability of e3,ectric power shall be as specified in section 3.9.A except as speci. fied, herein.,
l.
At least two units 1 and 2
diesel generators and'heir associated 4-kV shutdown boards shall be operable..
An additional source of power consisting of at least one of the fol'owing:
a ~
One 163.-kV transmission line and its associated common station transformer or cooling tower 'transformer capable of supplying power to the units 1 and 2 shut-down boards, b.
A third operable diesel, generator.
c.
One 500kV transmission source backfeeding through the Unit 2 main and station service transformers.
3.
At least one 480-V shutdown board for each unit must be operable..
298
t 8
I
~3.
BASES The obJective of this speci.fication is, to assure an adequate source of e3,ectrical pover to operate facilities to cool the-plant dueing shut-down and-to operate the engineered safeguards.
following an accident.
There are four sources of alternating current electrical energy available, namely,, the 161-kV transmission systen,. the nuclear genera-ting units, the 500-kV transmission
- system, and the diesel generators..
W ~
The-161-kV offsite pover supply consists of two lines which are fed fron different sections of the TVA 161-kV grid.
In the normal mode of operation the X61-kV system is operating and four diesel generato.s are operational.
XXe diesel generator is out*of service, there rornally remain the 161-kV'ources, the-nuclear generating units end. the other three diese3.
generators.,
For, a diesel. generator-to. be considered. operable its associated 125 V'attery nust be operable.
The minimum fuel oil requirement of 103,300 Gallons is sufficient for 7 days of full load operation of 3 diese' and is conservatively
- based, on availability of a replenishment supply.
The 500-kV offisite pov r supply consists of 6 lines which are connected
'to different parts of the TVA 500-kV grid.
Unit 2, in a shutdown anode,,
can bc backfed through its unit main transformers
- and, unit station transformers.
Am.iliary pover for-Browns-Ferry Nuclear Plant is supplied from three 6ources; the unit station transformers from the main generators, the 561.-kV transmission systen through the co "on station transformers or the cooling tover trensforners,,
or tne unit 2 station transformers from the 500-kV system.
If a co~on station trans cr er is lost, the units can co'nt'nue,
" op r".c "'nc the unSt station transfor.ers are in service, the o'ther common stet"on transformer end the cooling tover trersfo ers Me available, and four diesel gereretors are operational.
A. 4-kV shutdovn board. is alloved to be out of operation for a brief per'od
%o 'allow for mainterence and testing, providing a'1 remaining "-kV shutdo a bo'ards and associe ed diesel generators CS, R".Z, (LPCI end Containment Cooling) systems supplied. by the remaining 4-kV shutdown boards, and all Oluergency 480 V power boards are operable.
Were'are eight 250-volt d-c battery systems each of which consi ts of e
'b'attery, battery charger, and dis ribution eauipnent.
Three of these sys-tems provide pover.or urit control functiors,. operative pover for un't Rotor loads and, alternative cr've power for a 115-volt a-c unit preferred Rotor-generator set.
One 250-volt d-c system provides power for common
/la'nt and transmiss3 on system control funct'ons, crive power for " 115-volt a=c plant preferrcc =otor-genera or set,, end ene Gency drive power for cer'tain unit large motor loads.
The fou" renaining systems deliver cor.
'trol pover to the 4160-volt shutdown boards.
299 Amendment No.
pe RECI
+4 Po p%
0
/:
<<0 UNITED'STATES:
NUCLEAR REGULATORY'COMMISSION-WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT UNIT NO.
2'I1CaIOtiENT TO FACILITY OPERATING LICENSE Amendment No.
34 License No.
DPR-52 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated t1arch 22,
- 1978, complies with the standards and requirements of the Atomic Enerqy 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 ConImission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted wit'Iout endangering tlIe healttI and safety of the public, and (ii) tha-such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E..
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's requlations and all applicable requirements have been satisfied.
2..
Accordinqly,. the 1'icense is amended by changes to the Technical Spec-i.ications as indicate< in the attachment to this license amendment and paragraph 2.C(2) of Facility License No.
DPR-52 is hereby amended to read as follows:
(2) lechnical S ecifications The Technical SpecificatioIIs contained. in Appendices A anu B,
as revised throuqh Amendment No.
34,, are hereb'ncoroorate in The license.
The licensee shall operate tlIe facility in accordance with the Technical Specifications,
3.
This license amendment is effective as of the date of its issuance..
FOR'HE NUCLEAR" REGULATORY'Oh1MISSION
Attachment:
Changes to the Technical Specifications George Lear, Chief Operating Reactors Branch 83 Division of Operating Reactors Date of Issuance:-
Harch 29, 1978
r
ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO.
DPR-52'OCKET NO. 50-260 Revice Appendix A as follows:
Remove the following:. pages and replace. with identically. numbered. pages':
Marginal line indicate revised area.
Overleaf page is provided for convenience.
This'ocument presents tre tech specs. for'he Browne Fed'ry 101clear Plsnt.
unit, 2 only.,
Browns Ferry unit 2 is in the WeWeli~ mode and is exoected to remain in this condition unti3. a, safe y ana+sis has been performed ensuring adequate offsite capability fo" three-unit operation in accordance with T/S 3.9.,
One offsite 500-kV transmission source. shall be backfed through the unit 2.
main and. unit statioz: service transformers.
Amendment No.
34
I
I>>O'EFINITION5
- ~
The; succeeding.- frequently used cerms are explicitly defined, ao that a uniform interpretation. of che-speci,ficatioos. may be achieved.
able maintenance-of che cladding.and primary systems: are assured; Exceeding, such
- s. limit requires unit shutdovn and. reviav by the Atomic Energy. Commission. before resumption of unit operation.
Operation beyond, such ailimit may-not; in, itself result in serioue-consequencesi buc ic. indicates>> sn operationaL deEiciancy aub]ect.'o-regulatory reviev.
3'. 'Limitin Safet S stem Se cin (LSSS) - The limiting safety system.
setting are settings:
on instrumentation vhich initiate. the: automatic protective-action: ac s". leveL such chat: che safety limits:vill not: be exceeded.
The region betveen. the saEety. limit and.'hese setting+
represent margin; vith normal operation lying; belov: these, settings.
The margin has been eacablishd so that. vith proper operation of.
the'nstrumentation the: safety limits villnever be exceeded'.
C.
Limitin Conditions for era tion LCO)
The limiting conditions for operation specify che minimum acceptable levels of system performance necessary to assure. safe scsrcup and operation of the Eacility.
%hen these conditions are
- mcc, the plant-can be operated safely and abnor-mal situations can be safely controlled.
( f 0
~$ RKoo c<
~o 4p
~i
~ >+
C' lO p'
+,
~'o
<<>>*<<+
UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT'. UNIT'O 3.
At1ENDt<ENT TO FACILITY OPERATING LICENSE Amendment No.
11 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 Harch 22,
- 1978, complies with the standards and reauirements of the Atomic Eneray Act of 1954, as amended (the Act), and the CorIImission's-rules and regulations set forth in lu 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'uthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied 2..
Accordingly, the license is amended by changes. to the Technical Spec-ificatinns as indicated in the attachment to this, license amendment and paragraph 2.C(2) of Facility License No.
DPR-68 is he'reby amended to reaa as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.. 11, 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'HE NUCLEAR REGULATORY COMMISSION.
George Lear, Chief Operating Reactors Branch 83 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 29, 1978
0
ATTACHMENT TO LICENSE AMENDMENT'O.
11'ACILITY OPERATING LICENSE NO.
DPR-68 DOCKET NO. 50-296 Revise Appendix A as follows:=
Remove the following pages and replace with identically numbered,'ages,:
316 317 321 322 323 324 326 327 Marginal lines indicate changed areas.
Z ZiZMITING CONDITIONS:- FOR OPERATZONz SURVEILLANCE:=.REQUIREMENTS.
.9 AUXZLZAR~YRL CTRZCA 'Y T te r
4 ~ 9~
~Aica bilist Applies to the auxiliary electrical power system.
A licabilit Applies; to the periodic testing requirements of the auxiliary electrical systems
~ob ective To assure an adequate supply of electrical power for operation of those systems required for safety.
~OR ective Verify the operability of the auxiliary electrical system.
S eci fica tion S
cification Auxiliar Electrical E~ui nent A
Auxiliar El'ectrical
~Eui anent 1 ~
DieseZ Generators The reactor shall not be started up (made critical from the cold condition) unless four unit 3 diesel generators (3A, 3B, 3C, and 30) are oper-
- able, both 161-kV transmission lines are operable and supply-ing power to the plant, at least one 500 kV transmission line is operable and supplying power to the plant by back-feeding through the Unit 2 main and station service transformers and the require--
ments of 3.9.A.4 through 3.9.A.7're met.
The reactor shall not be started up (made critical from the hot Standby Condition) unless all of the following conditions are satisfied:
a ~
Each unit 3'iesel generator shall be manually started and loaded once each month to demonstrate operational readiness.
The test shall continue for at least a one-hour period at 75% of rated load or greater.
Amendment No.
11 316
g4 \\
~
P
LIMITING:CONDITIONS FOR'PERATION:
SURVEILLANCE REQUIREMENTS:
3'+9' XIL ARY ELECTRICAL SYST 0 ~ 9
. AUXILIARYELECTRICAL SYSTEM" At least. one. off-site.
f61-kV transmission:
line and its common station-service.
transformer or cooling tower transformer are available and capable of automatically supplying auxiliary power to the-shutdown hoards.
b.,
During; the monthly generator test the diesel generator starting air compressor shall be checked" foz, operation and its ability to recharge air receivers.
The operation of the diesel fuel oil transfer pumps shall be demonstrated, and the diesel starting. time to reach rated voltage and.
speed shall be logged.
Once per Unit 3 operating cycle a test will be conducted to demonstrate the unit 3 emergency diesel generators will start and accept emergency load.
within the.
specif ied'ime sequence C ~
Once a month the quantity of diesel fuel available shall.
be logged..
3l7
,GZHXTZNG CONDXTXONS FOR OPERATION SURVEILLANCE. REQUIREMENTS.
3.9'UXILIARYELECTRXCAL SYSTEM 4* 9'UXILIARYELECTRICAL SYSTEM The-undervoltage relays which start the. diesel generators from start: buses 1A and 1B and the.
4-kV shutdown boards,, shall be calibrated annually for trip and reset and the measurements logged.
5.
The 250-Volt unit batteries and a'attery charger for each battery and associated battery-boards are operable.
6.
Logic Systems a.
Accident signal logic system is operable.
7.
There shall be a
minimum of 103,.300, gallons of diesel, fuel in the unit 3 standby diesel generator fuel'anks..
8.
At least one offsite 500kY transmission line back-feeding through the Unit 2 main and station service transformers is available and capable of supplying auxiliary power to the shutdown boards.
Amendment No.
321
LX~'<QHQ.CO~LDZTXOJS >~OR OPFRATXOsJ SU:EVZXLLANCZ RFQUXRK~~HTS 3
9 AUXXLIABYELZCTRXCAL. SYS7."8 4
9 AUXXLXARYFLECTRZCAL SYST=H
.B
.. Operation with Xnooerable
~CCQ1. Gal&lit whenever the reactor is in Startup mode or Run.rode
-and'ot in a cold condition, the availability of electric power shall be as spec'f':n 3.9.A, except as specified herein.,
B 0
ra"ion with inoperable r rom and afte-the date tha one common station trans=orm r and one cooling tower transformer, or one 161-kV line becomes inoperable, reactor operation is permissible under this con-dition for seven days.
Rhen one common station transformer or one cooling tower transformer, one l61-kV line or a 500-kV unit back-feeding is found to be inoperable, all unit 3 diesel generators and associated boards must be demonstrated to be operable immediately and daily thereafter.
322
r P
I
LZNZTXNG CONDITIONS: FOR'PERATION SURVEILLANCE REQUIREMENTS 3 ~ 9'UXILXARYELECTRICAL SYSTEM'~.9'OXXLXARYELECTRICAL SYST 2%
When~ one unit 3>
diesel generator (3A',.
3B3C, or 3D) is inoperable,, continued.
reactor operation, is permissible during the succeeding 7'ays,.
provided that both offsite 161-kV transmission lines,,
both common transformers or one common transformer and-one cooling tower transformer, or one offsite 500 kv transmission line backfeeding through the the Unit 2 main and station service transformers are available and capab'ie of supplying power to the unit 3 shutdown
- Systems, and the remaining three unit 3 diesel generators are operable.
If this requirement cannot be met, an orderly shutdown shall'e initiated, and-the reactor shall be shutdown and in.
the cold. condition within 2Q-hours.
24 When: one-unit 3'iesel'enerator is; found to. be inoperable,, all of the CS, RHR (LPCX and Containment Cooling)
Systems and the remaining unit 3 diesel generators and associated boards shall be demonstrated, to be operable immediately and daily thereafter.
Amendment No.
11 323
J 'r 4,,
g tl
~
"LIMITING'ONDITIONS:FOR'PERATION'URVEILLANCE.REQUIREMENTS' 3'~9'UXILIARY ELECTRICAL SYSTEM'
~ 9 AUXILIARYELECTRICAL'YST 3 ~
When one unit 3 4-kV shutdown'oard's inoperable~
continuecb reactor operation is permissible for a period. not to exceed.
5 days, provided that..
both offsite 161-kV transmission lines and both common transformers or one offsite 500 kv source backfeeding through the Unit 2 main and station service transformers are available and the remaining unit 3 4-kv shutdown boards and associated diesel generators, CS, RHR (LPCI and Containment Cooling) Systems, and all unit 3 480-V emergency power boards are operable.
If this requirement cannot be met, an orderly shutdown shall be initiated and the reactor shall be shutdown and in the cold condition within 24'ours.
3 ~
When one-unit 3 4-kV shutdown:. board'. is found>> to, be.
inoperable, all remaining unit 3 4>>kV shutdown boards and associated. diesel generators, CS and RHR (LPCI and Containment Cooling)
Systems supplied by the "remaining 4-kV shutdown boards shall be demonstrated to be
- operable, immediately and daily thereafter.
- 324,
LIMITINGCONDITIONS FOR OPEPATION SURVEILLANCE-REQUIREMENTS
--"-3o 9" AUXILIARY-ELECTRICAL SYSTEM 4+.9'UXILIARY ELECTRICAL SY Ci 0 eration in Cold'hutdown Condition Whenever the reactor. is in the. cold; shutdowni condition vithi 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 generators and their associated 4-kV shutdown boards shall be operable.
2.
An additional source of power consisting of one of the following:
a ~
One. 161-kV transmission line and its associated common transormer or cooling tower transformer capable of supplying power to the unit 3
shutdown boards.
b', third operable diesel generator.,
C.
One 500 kv trans-mission source back-feedina throuah the Unit. 2 main and station service transformers capable of supplying power to the Unit 3 shut-down boards, 3.
At least one unit 3 480-V, shutdown board must be operable.
326
0 t
I C
0
3.9 BASES The oh)ective of this specification is to assure an adequate source of electrical power to operate facilities to cool the unit during shutdown and to operate
.he engineered safeguards following an accident.
There are three sources of alternating current electrical energy available,, namely, the 161-kV transmission
- system, the 500-kV transmission system,.
and. the.
diesel generators.
The 161-kV offsite power supp'y consists of two lines which are fed from different sections of the TVA 161-kV grid.
In the'ormal mode of 'operation, the 161-kV system is ope ating and four diesel generators a e operational.
If one diesel generator is out of'service, there normally remain the 161-kV sources,,
and, the other three diesel generators.
For a diesel generator to be considered operable its associated 125 V battery musf be.
The minimum fuel oil requirement of 103,300 gallons is sufficient for 7 davs of full load operation of 3 diesels and is conservatively based on availability of a replenishment supply.
The 500-kV offsite power supply consists of six lines which are connected to dif erent parts of the TVA 500-kV grid..
In the unit 2 refueling mode this source is backfed through the unit 2 main transformers and, unit station transformers.
Offsite auxiliary power fo Browns Ferry Nuclear P" ant is supplied fro three sources:
he unit station trans ormers from the main generators, the 161-kV transmission system through the common station transformers or the coo'ing tower transfor=er, or he unit 2 station r."nsfo.=. rs from the 500-kV system.
Z.
a comon station transformer is lost, the u.".'t can continue to c-e ate since the station trans or". " is in service, the other co=.on s ation transformer and the coo i..g tower transfor=ers are ava'lable, and four diesel generators are operational..
A 4-kV shutdown board is allowed o be out of operation for 'a brief period to allow for maintenance and tes ing, p"oviding all remaining 4-kV shutdown boards and assoc'ated diese gene ators CS,
- RHR, (LPCI and Containment Cooling) Syst ms, supplied by tne remaining 4-kV snutdown boards, and all emergency 480 V power boards are operaole.
There are four 250-volt d-c battery systems each. o which consists of, a battery, battery charger;,
and. distr' tion equipment.
'iiree of these systems provide powe= for unit control functions, ope"a-'ve power fcr uni" motor loa"s a."" alternativ drive power fo a '5-volt a-c unit preferred mo-cr-gene ator set.
One 250-vol. d-c system provides power for co=-on p'ant and transmission sys em control unctions, drive powe" =or a 115-volt a-c plant preferred motor-generator
- set, and e.ergency drive power for cer a'n unit large motor loads..
The 250-, vo t d-c system is so arranged, and the-batteries sized such, that the 'oss of any one unit will not prevent the safe shutdown and cooldown of all three units in the event of the loss of offsxte power and a design basis accident in any one unit..
Loss of control power to any engineered sa eguards control
J
<gR AKC>
~o 4p p%
ClO p'.
~+*++-
UNITED STATES NUCLEAR REGULATORY COMMISSION.
WASHINGTON, D. C. 20555 SAFETY EV LUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT'O. 37 TO FACILITY OPERATING LICENSE NO. DPR-33 AMENDMENT NO.
34 TO FACILITY OPERATING LICENSE NO.
DPR-52 AMENDMENT NO.
11 TO FACILITY OPERATING LICENSE NO.
DPR-68 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT NOS. 1, 2 AND 3 DOCKET NOS. 50-259, 50-260 AND 50-296 1.0 Introduction By letter dated March 22, 1978, the Tennessee Valley Authority (the licensee or TVA) requested changes to the Technical Specifications (Appendix A) appended to Facility Operating Licenses Nos.
DPR-33, DPR-52 and DPR-68 for the Browns Ferry Nuclear Plant, Units Nos.
1, 2 and 3.
The proposed amendment and revised Technical Specifications would pro-vide a third offsite power source.
As described in Section 8.4 of the Final Safety Analysis Report (FSAR) the startup an'd alternate power source for unit auxiliaries is either of two (161 kV to 4.16 kV) common station transformers which are fed from the TVA 161 kV system.
Currently, the two normal offsite power sources are the 1) Trinity 161 kV trans-mission line through eithe~ the common station service or cooling tower transformers and 2) the Athens 161 kV transmission line through either the common station service or cooling tower transformers.
Browns Ferry Unit No.
2 shut down for refueling on March 19, 1978 and is expected to be down for 3 months.
While Unit No.
2 is in the refueling configuration, the proposed change will provide a third offsite power supply from the 500 kV transmission system by "backfeeding" through the Unit No.
2 main generator transformers and the unit 2 station service transformer, 2,0 Back round On October 17, 1977, while= Browns Ferry Units 1'nd 3 were in a shutdown condition, Unit 2 tripped from essentially full load.
TVA management was concerned that low voltage on Browns Ferry buses connected to the offsite system contributed to this loss of a unit.
TVA established an interdisci-plinary task force to investigate the incident, to determine the cause of the trip and to make recommendations to prevent a reoccurrence.
This investigation included an evaluation to ensure that the information pro-.
vided in TVA's July 22, 1977, response to NRC concerns on bus undervoltage was still valid in the light of actual measured inplant conditions.. Pre-liminary conclusions of the TVA'nvestigating group (January ll, 1978)
t P
C
indicated that safety-related implications-did not exist for the October 17th event, but that additiopal analysis and inplant measurements were necessary to evaluate the incident.
Also,. additional investigations of design improvements were initiated.
On the basis of inplant measurements of actual real and reactive load, TVA performed detailed calculations.
These calculations evaluated. the inplant.
voltage that would result from various assumed onsite events coupled with degraded offsite transmission conditions.
These calculations, which were completed March 18, 1978, indicated that for a simultaneous 3-unit trip with the Athens or Trinity 161 kV line or one common station service transformer out of service, that acceptable voltage could not be main-tained from the remaining offsite sources.
However, at the time these calculations were completed, only Units Nos.
1 and 2'ere. in operation and Unit No.
3 was shutdown to repair electrical connectors.
Additional calculations were performed based on operation of one or two units, with the third unit shutdown.
While these calculations were being performed, Unit 2 was shutdown to investigate the cause of unidentified leakage in the drywell.
Since Unit 2 was scheduled to shutdown on March 26, 1978 for refueling, TVA decided to place Unit 2 in a cold shutdown condition and commence its refueling outage a week earlier than scheduled.
Unit 2 is expected to be shutdown for three months for refueling and.repair of feedwater spargers.
Unit 3 was subsequently returned to power operations on March 21, 1978.
3.O Discussion Assuming certain postulated conditions, including degradation of the two 161 kV offsite power systems, and simultaneous 1-unit LOCA and 1-unit trip or a 2-unit trip, the calculations discussed above demonstrated to the licensee that operation of two units (Units 1 and 3), while the third unit (Unit 2) was shutdown, could result in the potential for degraded voltage conditions* on the 4160 volt emergency buses that satisfy the minimum voltage conditions described in "ANSI C84.1-1970".
Additional calculations were performed based on a plant electrical'ineup which included blocking of certain automatic transfer features of non-safety-related loads in the Plant.
These calculations and associated safety evaluation confirmed that satisfactory voltage could be-maintained on safety-related buses under degraded offsite conditions for a postulated simultaneous trip of the two operating units or a simultaneous trip of one unit and a
LOCA in another unit with the third unit in the shutdown mode.
This arrangement,
- however, would not provide sufficient operational flex-ibility during the Unit 2 refueling outage.
8ased on the provision of a third offsite power source, additional calculations confirmed that satis-factory voltage could be maintained on inplant buses, even if there were loss of one of the 161 kV offsite lines, under conditions which postulated 1) a simultaneous two unit trip, or 2) a simultaneous one unit LOCA and a
one unit trip with Unit 2 in the refueling shutdown configuration.
C J l
~
While the general subject'f offsite power for the Browns Ferry Station is under review, TVA has proposed to provide a third offsite power source during the Unit 2 refueling outage.
The third offsite power source will be authorized by the proposed changes to the Technical Specifications.
The-changes will allow the 500 kV offsite power system to be backfed; to. the onsite. 4160 volt emergency buses-through the Unit 2'ain generator transformers-and the Unit 2 station service transformer.
This arrangement'ould be for the approximately 89 days that Unit 2 is shutdown for. refueling.
Meanwhile, TVA is per-forming additional studies on means of providing a permanent third offsite power supply.
This change has no adverse safety effects and does not detract from the availability and reliability of onsite emergency power supplies.
In addition to the change in Technical. Specifications, the licensee s
submittal supersedes the Browns Ferry FSAR Amendment 40 description which indicated that the two capable offsite sources were either the Athens and Trinity 161 kV lines and either the two common station service trans-formers'r the cooling tower transformers added to increase offsite capabilities.
Evaluation 5.0 We concluded that the proposed changes to provide a third offsite power source during the Unit 2 refueling outage will ensure safe operating conditions without the undesirable interruption of non-safety-related equipment.
Although Units Nos.
1 and 3 can be safely operated without the proposed change during the Unit 2 refueling outage, the addition of a third offsite power source will provide operational flexibilitywhich is desirable.
Based on our review, we conclude that the licensee's proposed changes to the Technical Specifications are acceptable.
Environmental Considerations We have determined'hat these amendments do not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.
Having made this determination, we have further concluded that these amendments involve.
an action which is insignificant from the standpoint of environmental
- impact, and pursuant to 10 CFR 551.5(d)(4) that an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of these amendments.
r
6.0 Conclusion We have concluded that:
(1) because the amendments do not involve a significant increase in the probability or consequences or accidents previously. considered and'o not involve a'ignificant decrease-in a safety margin, the amendments do not invoTve a significant hazards con-sideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered.
by operation in the proposed
- manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Dated:
March 29, 1978
r
7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NOS. 50-259, 50-260 AND 50-296'ENNESSEE YALLEY AUTHORITY NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U. S. Nuclear Regulatory Commission (the Commission) has issued.
Amendment No.
37 to Facility Operating License No.
DPR-33',. Amendment No.
34 to Facility Operating License No.
DPR-52,. and Amendment No.
11 to Facility Operating License No.
DPR-68 issued to Tennessee Yalley Authority (the licensee),
which revised Technical Specifications for operation of the Browns Ferry Nuclear Plant, Unit Nos.
1, 2 and-3, (the facility) located in Limestone County, Alabama.
The amendments are effective as of the date of issuance.
These amendments change the Technical Specifications to permit opera-tion of the facility with a third offsite power source to augment the two existing 161 kV sources, while Unit No.
2 is shut down for refueling.
The application for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and
'the Commission's rules and regulations.
The Commission has made appro-priate findings as required by the Act and the Commission's rules and regulations. in 10 CFR Chapter I',. which are set forth in'he license amend-ments.
Prior public notice of these amendments was not required since the amendments do not involve. a significant hazards consideration..
The Commission has determined that the issuance of these amendments will not result in any significant environmental impact and that pursuant
~ I
to 10 CFR 551..5(d)(4) an environmental impact statement,. or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of these amendments'.
For further details. with respect to this action,, see (1) the appli-cation for amendments dated March 22,
- 1978, (2) Amendment No.
37 to License No.
DPR-33, Amendment, No.
34 to License No.
DPR-52, and Amendment No.
11 to License No.
DPR-68, and (3) the Commission's related Safety Evaluation.
All of these items are available for public inspection at the Commission's Public Document
- Room, 1717 H Street, N. W., Washington, D.
C.
and at the Athens Public Library, South and Forrest,
- Athens, Alabama 35611.
A copy of items. (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D.
C.
20555, Attention:
Director, Division of Operating Reactors.
Dated at Bethesda, Maryland, this 29th day of Parch 1978.
FOR THE NUCLEAR REGULATORY COf'EMISSION George L ar, Chief Operating Reactors Branch ¹3 Division of Operating Reactors
~
~