ML18030A978
| ML18030A978 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/30/1985 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18030A977 | List: |
| References | |
| TVA-BFNP-TS-199, NUDOCS 8601060169 | |
| Download: ML18030A978 (38) | |
Text
ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION REVISIONS BROWNS FERRY NUCLEAR PLANT UNIT 2 (TVA BFNP TS 199 SUPPLEMENT 1)86020602b9
-851230'DR ADQCK 050002b0 P PDR J we'iack',+Kg PROPOSED CHANGES UNXT 2'PRO~OS'-"'p"CXFrcz"'vz J,o fS BROriNS FERRY NUCLEAR PLANT i8$XT 2 (Tl'Z 3L"i~fP TS 199 SUPPI ENEliT 3.)
bAS!s ff<<n (uel dasLade~ass>>aint a steady state operation as the C tip vetelnR over~nc[re scelseulat tan f lou range.The narbin co the Safety Lfolt increases the f lov dec ceases for the spvc 1 f 1cd.t s 1 p sett lnR s ersus 1 lou sc latfonshlp;(bees jpre~she uorst ease WCPR uhich could occur due 1>>R s eady-~tate operation~s inst of satrd shrrnal rcwer brc ause of she AplVi red bloeb t rip eettlnb~The~s gv$1 padres d ps(c lbus Ini~I>>sbw core L'stabl l shed by spec 1 1 1<<d control sod sequences~nd li nvnl<ored cont tnuously by the fn-core OIW sysseo,/Reactor uater Lov level sabras and I oint icn (Face c ttaln sit ael ines)The set point for the lou level scram ls above the bot toss of the separator skirt..his level has been used ln transtent analvsci deal ant vieh coolant inventory decrease.The res<<lt s reported ln FSAR subsect ion 1<.S sb<<M that scram and isolation ol all process lines (except naLn stem)at this level adequately pcotccts chc fuel and the pressure barrier, because 11CPR 1s Rreater than 1.07 ln all cases, and~ysteo pressute does not reach the safety valve sett lnss.'The scraLs sett i>>a ls~pproafsLacely
)1 inches beloM the noraal opetatfnR range and ls thus adequate to~void spur1ous acres.n.n w~~il<<~., s Thi turbinr.stop valve closurr trip anticipates the pressure, neutron flux anl 4<dl, flux increases that would result.from closuse of the stop valves.'Mith a trip setting of 10" of valve closure fromm full open, the resultant increase in heat flux is such that adequate therma'l margins are n@inta<ncd even during the worst case trarsient that assumes the turbine bypass valves remain closed.(Reference 2)V..T>>rhine Control Vnlvn Fnnt Closure or Turbine Tri Scram Turbine control valve fast closure or turbine trip scram anticipates the pr<so>>re, n<<>>tron flux, a>>d bent fl>>x increase that co>>ld result from r>>ntrol valve fn>>t clos>>rc due to load rejection or rnnrrol valve closure d>>e tn t>>rhl>>c trip;each without bypass valve capahiiity.
Thc reactor protection"ystcm initiates a scram in less than 30 milliseconds after the start of control valve fast closure due to load re)ection or control valve closure due to turbine trip.This scram is achieved by rapidly reducinR hydra>>lie control oil pressure at the main turbine control valve actuator disc dump valves.This loss of prcssure ic srnsed by prcssure switches whose contacts form thr one-out-ot'-two-twice ionic input to the reactor protection system.This trip scttinq, a noniinally 50" nreatrr closure tip'nd a diffe>cnt valve character istic from that of the turbine stop valve, combine tu produce transients very similar to that for the stop valve.Relevant transient analyses are discussed.in tlcfcrenccs 1 ai)d 2.This scram is bypassed when turbine stcam flow is below 30Ãof rated, as m asurcd by L>>rbinc first slate pressure.23
%de S&tcb fo Haouaf Scran IRH*Hfgh Plum TABLE irl>A REACTOR PROTECTION SYSTEH (SCRAH)IHFPQ~ATION FUHCTIOHAI; TESTS KWQUH PVHCTIORQ.
TEST FREgUKHCIES POR SAPETT IHSTRI>AHD COHTROLJCIRCUpg.
r~I'QKDVIi~g Puoctfooai".Teat l.: ".J,>>Hfnfoui Fte ueocy ())>o A Place'"Horde Sbitch frl'Shutdoun,.
'.-.Each Refuelfog,outiRe-
~rJ A).;Trfp Chiaoel",aad Alai','-"Eac'ty)Hontha r>J<~Q>I lo)m 7 r~1~a~a Q ta C j Trf p Chaane Lccod Ala pa (4)', j,y, Once>Fat Veal'urloR
'R n a r efue~I ffn lnopcratf ao'a'I'a a Tant c AFRH!Iligh Flux.(FloM Biased)QfBh Flea (F)xed Trip)1 I laoperctfac "Do+a 4 ca I c Flou Bfca DIRb Reactor Ereaoute (PIS-3-2?AA, BB, C, 0)"I Ar-"sNs Y-b'), Reactor Lou Vatet Level'LIS-3-203 A-0)HIRh Vatcr Ecacl fo Scran Dfachar'gc'loat SMitches (LS-85-45 C-F),lectronic Level.Switches (LS-85-45A, B, G, H)D o'>>C~J r C~,B o B r~g I>>B'-'.0~-'..==:.')";-B'A r rr r", Ttfp Cbiooel add Ala~T<
>/clays (4)Trip Output->Relays Trip Outpu~Rclcya (4)J>>'I Ja>J'r J'I I*(4)',%I t>~\r'rfp Output R'elaya (4)Trip Outpuc Relays (4)u (l'J)J I Trf p Channel.,"aod Alan<Trfp CbannoL anJL'lara Trip Channel aod Alans lJJ Trip Channel and Ala E.Trip Cliannel yh6 Ala!N r Ca a (7)=" (7).rJ rm g rm (7)~u<aod Before Each Stiitaup.rOacca Pet Veelr, DurfoR Refuelfn oand Before Each, Startup'.1 o>J J iBeofotc hach Stcttup>a'nd Veetl 0'Vben Rcgufred to bcOpetalJIo .Once/M'cek <Ooe C'/Vector. ~'O>a r C e r: Once/Vega~.ce/Veen I\P J>(g)>J w r.l aa~r u>>~~:;o"cet I.month>1 r)~Ia>>>>>>>=a>">*~\1 JI')month"~~r>!Ar)>>~1~f, o J.,~~" ence/l-month o>>>J g1 r>" c~~1>>u J'o JJ!>J~Ollhe/month >J Once/month>>Hain Steam Line lliph Radiation Trip Channel anJl hlnrm (4)Once/3 months (8) TABLt a 1.i REACTOR PRO'I ECTION SYSTEM (SCRAM)IH.'iTi?:: 4L:~a'ATION FUHCT IOflAL TESTS-'1II41HUH PUbC'TIOIIAL TEST PREQUENCIES FOR SAI=~I I MS.R.AMD CONTROL CIRCUITS Group (2)Functional Test Minimum Frauen y (3)Main Steam Line Isolatron Valve Closure Turbine control Valve Fast;Closure or Turbine Trip Trip Channel and Alarm Trip Channel...i Alarm OnCer 3 montgS(8)Once/Honth (1)Turbine First Staqe Pressure Permissive)PIS-)-81 QB~/IS-1-91 ASB)Trip Chancre and Alarm(7)Trip C:.anncl and Alarm Every 3 Honths Once/Month (1) NOTES FOR TABLE 4~1.A Initially the minimum frequency for thc kndiratrd tests shall he once pcr month.H r 2..',A deicription of the three groups is included in the Bases of this specification. .Il 3.":Functional tests arc not required when thc systems are not required to he opcrablc or are operating, (i.e., already tripped).Tf tests are.,missed,= they shall be performed prior to returning thc system., to an operahli status.4.This instrumentation is exempted from the instrument channel test definition. This instrument channel functional test will consist of injecting a simulated electrical signal into the measurement channels.(DELETED)6..The Functional test of the flow bias network is performed in accordance with Table 4.2.C.7.Functional test.consists of the injection of a simulated signal into thc electronic 'trip circuitry in place of the sensor signal to verify oper'ability of, the trip and alarm functions. 8.The functional test frequency decreas d t/3 t e o once months to reduce tern iZ.K.J.16.chal cages to relief valves par NUREC 0737 1 39 TABLE 4~1~B REACTOR PROTEC?IOH SIST EN (SCRAH)IHSTRUHZHT CALI BRATIOH HIHIHOH CALI BRATIOH PREQOE1C'IES FOR REACTOR PROTECTIOH IHSTROHEHT CHAHHELS Instrwent Channel IRH High Flux ARRH R)gh Flux Output Signal F lov Bf as Signal LPRH Signal Croup (1)Calibration Caeparison to APRH on Control led etartupa (6)Heat Balance Cali"rate Flo~Bias Signal{7)TIp System Traverse (I))tiniam Frequency II)note (4)Once every I days Once/operating cycle Every 1000 Efiective Full PoMer Hours"'I'PS-7-'>O'A'; S, C, 0)'-tran"r NVA",.1 High Hater Level in scran Discharge voluse Floa t Switches (LS-85-45 C-F)Electronic Level Switches (LS-85-<5 A, S, 0, H Turbine Condenser Low Vacuum A B Turbine First Stage Pressure Permissive (PIS-1-81 ASB, PIS-1-91 ASB)B Turbine Stop Valve Closure A Main Steam Line Isolation Valve Closure A Main Steam Line High Radiation B Standard Pressure Source Standard Pressure Source Pressure standard Note (5)Calibrated Mater Column Standard Vacuum Source Note (5)Standard Current Source (3)Standard Pressure Source Note (5)Once/Operatinq Cycle (q)Onte/Operating'ycl e (9)Once/Operating Cycle (9)Note (5)Once/Operating Cycle (9)Every 3 Months Note (5)Every 3 Months Once/Operatinq Cycle (0)Note (5)Turbine Cont.Valve Fast Closure on Turbine Trip Standard Pressure Source Once/ODerating Cycle tow.4<1.TABLE 3 2 F SURVEILLANCE ZtiSTRUMEHTAT Intt<r<i)(b N*n';Hininulr'of 0 per able Instrument Channels 2 Instrument 4 LI-3-58A LI-3-58B PI-3-74A PI-3-74B-c p->>4 J Isa~]trd;t.rrvt,,) Type Indicatxon Instrument and Range ReaCtOr Materi'LeVdlr I Indicator-155", J r')IOL<a.-...$60" Reactor PresVure.'.=T'r=': , Incicator 0-)200, 11~1 Notes to, d(1)(2)-r'g pst 9.-(I (/I g)'jcvr (3)(3)N NI l'R-64-So P I-64-678 TI-:64-52AB XR 69 50 XR-69-S2 I N/A, tt/A;PS-64-67B TS-64-52A8 PIS-64-58AR IS-64-67A LI-84-2A LI-84-13A Dryvell Pressure'<~J"anv<Dr@sell Temperature ta..,rd Suppression.,Chachyr Ai r Temperatur"e,"",'at:d.:1'V-Cut;-,, co<IT CAD Tank A Level CAD Tank"B" Level)', EO,J)y, Control RodaPqoigion, Neutron Monitor ing<I tot 4,"')1',1 r,rc p, Dryvell Pre"oury~DryMell Temperature and~Prcssure<and Timer tnt'1 l Recorder 0-80~gpia,r)r Indicator 0-80 psia'ecorder, Indicator 0 400oFg(1)(2)..'t l hg (7)Recorder 0-400OF (1)(2)~>)"'"r--'-'-fn~~4;c),-": 3.',Jnt),-.. (5)r6V Indicating <L'ights I-'~y.onths SRM, IRM, LPRH)(1)(2)0 to 100%pover)Alarm at 35 psig,)Blat)riq C'",: Alarm if enp.)281OF and)(1)(2)Pressure>g: psf8.)after 30 minute'delay)Indicator 0 to 100'ndicator 0 to 100%(3)(3)(3)(3)(")(3)(4) TABLE 3 2.P SURVEILLANCE It!STBU!!ENTATIOB Hfninua I cf Operable In r'--.cn'hannels !!8 IG 9!2 R H-g6 lo4.2 Pdi-64-13I PdI-64-138 ~r~Dryvcff end Torus!!jdroRen.Ccncertraticn Drwclf to Suppression Chsnber Differential Pressure~c Inhfrctfon L.d Rcn-!0 1 20r Indicator 0 to 2 paid Rrtes (1)(2)(3)1/Valve BR-90-272CD RR-90-ZI3CD Belief Valve Tailpipe Themocoupfe Tcnpcraturc or Acoustic Ronftor on Relief Valvo Tailpipe!!fgh Range Prinary Contaf anent Radiation Bccordcrs Recorder>1-10 R/!fr (5)(7)(8)LI-64-159A /XR-64-159 Suppression Indicator, Chanbcr'Lister Recorder 0-240" (l)(2)(3)Level-Midc Range PI-64-160A XB-64-159 TI-64-161 TB-64-161 TI>>64-162 Tn-6'162 Dryvcll Pressure Mfde Range Suppres fcn Pcol Oulk, Tcoperatutc Indicator, Recorder)(1,)(2)(3)0-300 psig)Indicator, Bceordcr)(1)(2)(3)(4)N))3o-23o r')RR-90-322A Wide Ranpe Gaseou's Effluent Radiation Honitor Recorder'oble Gas))0 7-10"5 pCi/cc)(7)(8) iodf)e and Particulates) 10"-10+2)fCi/cc) ())prom end after tho data that ono o these parameters ia reduced to one indication, continued operaticn ia pemsaiblo dur-ng aha succeeding dirty daya unleaa such inst"um~tac'cn sooner made opcrahla.(")I".om and after the data Jet cno o{thcaa para=ctcra js not indicated in tho cont"ol roon, continued operation Ls p+rmiaaphlo during the ouccccdwg aaven d ya unlcao auc5~".'natruncntaticn Ls aoonor+ado oporahla.(3)If tho requircaoats of aotas (I)and (2)cscaot ba cat, snd if one of the indications car~at bo restored--in (6)hours, sn orderly" shusdawn shall be ini.tiatad and ho riiactor shall ba in a cold.conditAoa within"4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.'(a).heaa au=veillancc inatwznta are conaido od to 5 redundant. co'oach other.IJ~g (5)7rcu and after the date that both the, acoustic monitor and tha-"temperature indication on any one valve fails t'o indicare~m,the;conrrol roca,'cont'nued operation is pemiasible during,the succeeding hirty days, unless one of the two monitoring cl~anela is, sooner~cade -,operablc. I~'both the pricary and secondary indication'on'ny SRV tail , pipe ia inopara51e, the torus temperature will'e-onitored a't least F: once'per shift to observe any unexplained tecpcraturc increa e which'might bc indicative of an open-,SRV. ~o*f,*wl Ek 1t 1 il tl (6)h c Haniicl consistj of,'B:, ensors,*one,;from, each alternating rnrus bay,', Seven" sensors must, be~operable;for the';channe1= to~be, oped;abler;-,gy w~~.<<.e~~.~~i~~~*'i I's L)~l0 (7)'lihun ono of'these instruments is inoperable for more than 7 days, in)iran nf any other report required by specification 6.7.2, prepare and suhmit a Special Report to the Commission pursuant.to'spo~.ificatlon
6.7.3 within
the next 7 days outlining the action~tal'en, the'ause nf inoperabilityand the, plans agd,sd)edule for..resto>-ing the system to operable, status.4 vi (8),'.With the plant in the power operation, startup, or hot shutdown condition and with the number of operable channel's"less chan the required operable channels, either restore the inoperable channel(s) to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or initiate the preplanned alternate method of monitoring the appropriate parameter.
iA ra~7 if><~80 TAbLE a~3.h SORYEILLLHCE REQOIRKHEHTS IOR RRIHhRT CottlhlttNEttc hHD REACTOR SOILDIHG ISOLhT IOH IIISZRIJKEÃfhTI OH inunction InatcusIsat Cbannol-Reactor Lov taster Lovel (Lzs-3-203A-0)
Inotrusont Channel Reactor IIIgh preaauco Instrument Channel-Reactor Lov uatec Level (LrS-3-5eA-D) inatcusont Cbannol Sigh Dryvell Pressure (Prs-64-SGA-D)
Inatcutsant Channel Oigh Radiation Hain Stean LI ne Tunne 1 Instcuoent Cbannol-Line)PIS-i-V3/6 82, 86)instr+ant Channol-Blgh tlov Hain Stean Line Pdzs-l-13A-D, 25A-D, 36A-D.natrment Channol Hain Stean Line Tunnel Blgh Taoperaturv Inotrusatnt Channel Reactor building Ventilation IIIgh Radiation Reactor tone tunct lonal Test II)(27)II)(27)II)(27)(29)(29)(27)(29)(27)SOA-D)(Z9)(I){Ia)Ill)once/3 tsonths none Once/Operating Cycle (28)once/day~V Once/Operating'Cycle (28)once/day Ance/Aper atinII Cycle (28)Once/Operating Cycle (28)once/day once/operating cycle none once/3 eonths once/day Ib)Calibration Frequency Instcunent Checir, Once/Operating Cycle (28)once/d y TABLE CD SURVKTLLAXCE REQUTRPfP.
TS FOR TMSTRL~ATlnlf THAT TM?rlATK nl COVFLOL TRK CSCS Function Functional Test Cslfbrstfon Tnstrus4ant Chaclr.laotruaent Channel Reactor Lou Mater Level (LTS-3-SGA-D)
(1)(27)Ance/Operating Cycle (28}ance/des'astruaeat Channel Reactor Lcv Mater Level (L?S-3-184 R 105)Taatruacat Channel Roactar Lc4t Mater Level (LIS-3-52 8 62)Tnatnrscnt Channel Reactor Lou Mater Level (LIS-3-56A-D) 4~(1)(27)Once/Operating 4 Cycl e (28)ance/dsf<1)(27)Ance/Operating Cycle, (28)l..(aa<</d41 4 4 f, 4<'4II'u.IIP-(1)(27)Once/Operating Cycle (2B}Zactruuant Channql Reactor High Preasura.(P IS-3-204A-0)
Taatruacat Cheanel Drywall UKRh Praaaura (PIS-64-58E-H)
Eaat~t Chan>el Dr3n~ll HtRh PreaoarofPIS-64-58A-D) lnat~t Chaaaal Drywall Btgh Preaaura (PIS-64-57A-D)
Zaat~at C~ol.QaactoL.Lm Paeceara (PIS-3-74A88, PS-3-74AIlB)(PIG-68-95, PS-68-95)(PrS-68-96, PS-68-96)(1)(27)Once/Operating Cycle (2)(1)(27)(r (1)(27)Once/Operatinq Cycle (@)'nce/Operating Cycle (28)(1)(27)Once/Operating Cycle (28)(1)(27)Once/Operating Cycle (28)I 4
TABLE a~2ec SQRVEZLLA14 E RF4QZRENENTS POR ZNSTRQkENTATZON tHAT INITIATE ROO DLOCKS~~Function APRk Qpscale{tl~Dias)APRk Dpscale (Startup kode)APRk Dovtlscale APRk Inoperative REk Qpscale{tie Bias)RSk Downscale RSk Inoperative IRk Upscale IRk Dowlscale IRk Detector not in startup Position IRx Znoperatise M~SRk Qpscale SRk Dovnscale SRk Detector not in Startup Position SRk Inoperative Floe Ries cooperator tlcw Siss Qpscale Rod Slock Logic RSCS Restraint West Scram Discharge Tank Water Level High (LS-85-45L)
East Scram Discharge Tank Water Level High (LS-85-45M)
Functional Test{11.{13){1){131{11{13){1){131{1){13)(1){13)(1)(13){1){2){13)(1)(2){13)(2){once/operating cycle)(1)(2){13)(1){21 (13)(1){2)(13){2)(once/operating cycle){1){21{13){11{1>){1){1$)('16)once/quarter once/quarter Calibration
{17)once/3 sonths once/3 sonths once/3 sonths once/6 nonths once/6 sonths once/3 scathe once/3 sonths once/operating cycle (12)0 Instrument Check once/day (8)once/day{8)once/4ay{8)once/day{8)once/day{8)once/day (8)once/day (8)ence/4ay (8)once/day (8)S/A once/3 aaaths once/3 sonths once/day{8)once/day{8)once/operating cycle{20)once/3 soaths k/A oncel3 sonths IVA once/operating.
cycle N/A once/operating cycle'/A once/operating cycle{12)N/A 0
TABLEq).,2.
Fc HIIIIMUM TEST AHD CA'LIBRATION FtrFQUI:ttCY'OR SUIIVEIIrLAHCE IttSTRUtlt:trTATIOH h C Instrument Channel~g h Il h, hh Once/6 months"~Once/12 months Once/6 rqonths;,<,, Once/6 mBHths.Once/6 morlt)ls 1)Reactor Water Level tr (LI-3-58A88) 2)Reactor Pressure (PI-'3-74ASB) 3)Drywell Pressure ilail (PI-64-67B) and XR-64-50,l r;3, 4)Dr ell Temperature TI'-64-52AB) and XR-64-50 trt 5)Suppression Chamber Air Tepperature (XR-64 52)43'.C~Qyy~Crh'Each Shift t>t Each Shift<<I Each Sllift trrt Each Shift'-.Ct Er~=.h=i Crhh:a Instrument Check:..~:y I;., Each Shift h~:3+8)Control Ror)Position 9)Neutron Honitoring lh pl'jh ttA (2)C hh'res Each Shift I'1 ,-I Each Shi f t h 10)Drylrell Pressure (PS-64-67,B)
Once/6 moil'ths'l)Drywel 1 Pressure (PIS-64-58'A) r g 12)Drywel.l Temperature (TS-64-$2$)I Once/6 Once/6 monttie ttc mon ths.l heal h'IA HA 13)Timer-(ZS-64-67A) tr~14)CAD Tank Level c'lce/quar<or 15)Con tiiiiraerrt Atmosphere Horlit:ore hrS-l6)Dryqcll.to Suppreooion ChamberDifferential Freosure Once/6 Once/6 once/6 moll t ll s o",>""., retie moll tile rrontho mr ir Once/6 months~h)l re Once/day Once/day.Each Shift 0
TABLE 4llINIHUN TEST ANO CALIBRATION FREQUEllCY FOR SURVEILLANCE IHSTRU!lENTATION Instrument Channel Calibration Fre uenc Instrument Check I 7 Relief valve Tailpipe Thermocouple Temperature Once/month (24)lS Acoustic Vnnitor on Relief Valve Tailpipe Once/cycle (25)Once/month (26)19 High-Range Primary Containment Once/cycle (3o)Radiation lionitors (RR-90-272CD)(RR-')0-273CD)
Ance/month 20 21 Suppression Chamber Hater Level-Hide Range (LI-64-159A)(XR-64-15q)
Drywell Pressure-Hide Range (PI-64-160A)(XR-64-159)
Once/cycle Once/cycle Ance/month Ance/shi est 22 Suppression Pool Bulk Temperature Once/cycle (TI-64-161)(TR-64-161)(TI-64-162)(TR-64-162)
Once/shift 23 High Range Gaseous Effluent Radiation 1fonitor (RR-90-322A)
Once/cycle Once/shift rrorts fOR TASI CS 4.2.A TNROUCII 4.2.ll ConC tnurd 14.Upscale trip te functionally tested during functional teat ttrLe ao raqutred by oect,ton 4.7.b.l.a and 4.7.C.l.c.
15.The ftov bias d'osparator-'vill"tie tested..bv putting.one Clov uoft Ln-Tesc" (producing 1/2 rcrarr)and ad)uottng the teac tnput:Ito obtain coaparacor rod block.Tha Clov bias upscale uttf be verified by observing~local upscale trip light duitng opera ion and vrrtfLad that it vL11 produce~rod block during'the operattng cycLo.16.Parforrred during operating cycle.Portions of the logic io checked rrora frequently durLng Cuncttorral teoto of tha functions that produce~rod block.17.Thts calibration conatsca oC reerovtng tho function Crora oarvtca and perfomfnb an electronfc calfbration of tha channel.14.PunctLonal tert ts ltrrtted to the condition adhere secondary contatnuont integrtty ts not requtred ao opect fied tn oections).7.C,2 and),7.C.).19~,PunctLonot ccac ts Ltrrt ted to the t trrre vhere the SCTS to required to.'rreet the rrqutrerrento of aectton 4.7.C.l.e.
20.21~22.Caltbratton of the cooperator requtreo the inputs Crorr both recLrculation Loops to be tncerrupted, thereby rerravtng the flov btaa afgnal to the.hPRPI and AN a rd scra~tng the reactor.This calfbratfon can only be.pcrforrrcd durtng an outage.'r I~Logic trot to llrrttad to the,ctrse vhero actual operation oC ths equipoant'fs pervrtrstbte.
I e One channel of etther the reacce one ur r!Cueltna aonr Reactor building:Vent tta(ton Radiation Horrttoring Syotarr rray be adrrtntatrat tvety byparord lor a period not to cacerd'ours Cor functional testing and calibration.(Deleted)l'Q 24.This instrument check consists of cocrparing the therrrmcouple reodinps for all valves for consistence and for notrfnal expected values (not required during refueling outages).25.During each refueling outage, all acoustic=~n!torin'4 channels shall ba calibrated.
This calfbrotion includea verification of actelerocreter response due to crechanfcal excitation in tho vicinity of tho sensor.26.This tnstrunent check consists of conpartng the background signal levels Cnr all valves for consistency and for nocrfnal expected values (not required durtng refueling outageo).110 NOTES FOR TABLES 4.2.A THROUGH 4.2.H Continued 27~Functional test consists of the in)ection of a simulated signal into the electronic trip circuitry in place of the sensor signal to verify operability of the trip and alarm functions.
I Calibration consists of the ad)ustment of the primary sensor and associated components so that they correspond within acceptable range and accuracy to hnown values of the parameter which the channel monitors, including ad)ustment of the electronic trip circuitry, so that its output relay changes state at or more conservatively than the analog equivalent of the trip level setting.29.The fmccicnal cast frequency decreased tn once/3 months to reduce chal}cnges so relief valves per NUREG-0737, Item Zl.K.3.16.
v 3p.Oalibration shall consist of an electronic calibration of the channel, not including the detector, for range dccadog above 10 Ruhr and a one-point oourcc check of the detector bclov 10 R/hr with an installed or portable gamma source.llOa LI!'.ITING CONDITIONS FOR OPERATION SURVEILLANCE R NTS r.@VI RFHE 3.5 CORF.AND CONTAIN"NT COOLING SYSTE'iS 8'h l 3'.Y"Pin'imum Critical'Power." Ra'tio (1".CPR)'he m nxmum" rcritibal.:sawer;rati,o---n-(llCPR)a~a-Suncttorriof'.CScrarr
>tine anrL cor e rf$ow;, rshall-be.
equal to or preater than shown in Figure 3.5.K-1 multiplied by the F;f shor1n in'igure,.3;5,.2, where;..., f=0 or~av-B, whichever is A-r-R gr eater~A=0.90 sec (Specificati'on
'3~3.C;1-.ct,".r ,scran time",limit'-to 20$-c'nser tion" from'full.'withdrawn) 8~~B=O.710+1.65 N (0.053)'Ref.
2J'z n<ave=ai n=number of surveillance rod tests performed to date in cycle (in-cluding BOC test).=scram time to 20<insertion f'rom fully withdrawn of the.ith rod N=total number of'ctive rods measured in Specification 4.3.C.1 at BOC If at, any time during steady state operation it is determined by normal surveillance that the limiting value for HCPR is being exceeded, action shall be ini.tiated within 15 minutes to".estore operation to within the prescribed limits.If the steady state 11CPP.is not returned to within the prescribed limits within two (2)hours, the reactor shall be brought to the Cold Shutdown conditi.on within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, su.veillance and corresponding ac ion shall continue urrtil".eactor operation is within the prescr'bed limits.4.5 CORE AND CONTAINYiEHT
- --:-COOLING SYSTE11S 4.5.K.Mininum-C~itical Power Ratio (HCPR)1,->>.YCPR,@hall, be determ ned,"rdaily
,during.reactor powe~'-oPYrat.5on-
't~25$p'at~a'0'hermal power~and followinr-any change in power level or distribution that would cause ope"ation with a"3,imitinp control rod pattern as descrihed in:.the bases for Specification
~.3.D'll Jr~~~)~2..cThe rHCPR limit.pha3,3.be deter-hzined for.each fuel type BXB,"-BXBR, PBXBR, fron'Figure 3.5.K-1 respectively using: a.'9i 0.0 prior to in'tial scram time measurements for the cycle performed in accordance with Specification 4.3.C.1~, h.Was defined in Specification 3.5.K following the conclusion of each scram time surveillance test requi.ed by Specification 4.3.C.1 and 4.3.C.2.The determination of the limit must be completed with 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of'ach scram time surveillance required by Specification 4.3.C.160
TABLE).S.I-1 I'O'LIICR VL'RSV" AVERACE PLA)IAR D(l'OSVRE@vers<le Pls<<sr Exposure I)"..Id/c)200), o<)0 S,O00 IO,OOO 15,000 2O,OOO'S,OOO Ln,non)S.ooo cn.non Fuel T>oes: PQDRB284L, QUAD+and 8DRB284L NAPLHCR (kM/Ec)11.2 II~3 I I.<)12.<)12.0 11.8 LO,R 10.0 9,4 Table 3.5.I-MAPLHCR VERSUS AVERAGE PLANAR EXPOSURE Fuel Typ<<:: P8l)R82GSH Av<!rn);e I'10<<;<r Exposure (Mvd/t)MAPLHCR (IEW/<L)200 11.5 1,000 5,000 10,000 15,000 20,000 25,000 30,000 35,000 40,000 45,000 11.6 11.9 12.1 12.1 12.0 11~6 I l.2 L0.9 10.5 10.0 I~~vv v vv v'v~>>~>>~C)Q'I)I)'vv~>>>>~v i~'~~~~~v~~.v~~v A v v~i~~~~v'v~~~~~i~~~~~~v~~~v~~~i~~v~~i~~~.~v v l~~v~~~~~v%i V<<.~0~I~I iv'c~, iv li~'~v'v>Ca.~i~~~~v~'~PgSCv i<vr v4v~v'4, iv jv%'Si3 v i~~~i~~~~I~~~~~~~~i I~~v~~~/~0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 v~)v Figure 3.5.K-l MCPR Limits for P8 x 8R/8 g 8R/qUAD+-172-
TAMH3 1 A PRIHARZ CONTAIHHENT IQ)LATION VALVES Croup Valve Ideutif ication Hain steaal inc isolation valves (PCV 1 14'6t 37r 6 51(1-15d 27d 38 6 52)Huuher of Pobder Operated Valves zuboard outboard Haxiuua Operating Tiao (sec.)3<T<5 Horual Position Action on Initiating Signal 1 Hain steauline drain isolation valves (PCV-1-55 6 1-56)Reactor Mater sauple line isola-tion valves RHRS shutdovn cooling supply isolation valves (PCV-74-48 6 47)RHRS-LPCI to reactor (PCV-74-53 6 61)40 30 0 C GC SC Iv 2 U<CI HHRS flush and drain vent to suppression chaubcr (PCV-74-102'03d 119120)20 C SC 2'uppression Chaaber Drain (PCV 75 51 6 58)2 Dryuell equipnent drain discharge isolation valves (pcv-77-15A 6 158)Dryvell floor drain discharge isolation valves (pCV-71-2A 6 28)15 15 15 0**GC CC**Tllcse valves arc normally open when thc prcssure suppress)on head tank is aligned to serve the RIIR and CS<lisc)>argo piping and closed when rhc condensate head tank is used to serve the RIIR and CS discharge piping~(Scc speaification 3.5.1))these valves isolate only on.reactor vessel low low water level (470")and main steam line high radiation of Group 1 isolations.
TABLE 3.7.B TESTABLE PENETRATIONS WITH DOUBLE 0-RING SEALS Penetrat.ion No.Identification X-1A X-1B X-4 x-6 X-25 X-25 X-25 X-25 X-26 X-26 X-35A X-35B X-35C X-35D X-35E X-35F X-35<: X-47 X-200A X-200B X-205 X<<205 X-205 X-205 X-205 X-205 X-223 X-231 X-231 Equipment Hatch Equipment Hatch Head Access, Drywel CRD Removal Hatch Flange on 64-18 Flange on 64-19 Flange on 84-8A Flange on 84-8D Flange on 64-31 Flange on 64-34 TIP Drive TIP Drive TIP Drive TIP Drive TIP Drive TIP Indexer Purge Spare Power Operation Tes Suppression Chamber Suppression Chamber Drywell Head Shear Lug No.1 Shear Lug No.2 Shear Lug No.3 Shear Lug No.Shear Lug No.5 Shear Lug No.6 t Ace'ess Hatch Access.Hatch ,Shear Lug No.7Shear Lug No.8 Flange on 64-20 Flange on 64-21 Flange on 84-8B Flange on 84-8C Flange on 76-18 Flange on 76-19 Suppression Chamber Access Hatch Flange on 64-29 Flange on 64-32":256-
TABLE 3.7.C TESTABLE PENETRATIONS PITH TESTABLE BELLOWS X-7A X-7B X-7C X-7D X-S X-9h X-9B X-10 P r imary S team 1 inc Primary Steamline Primary Steamline Primary Steamline.Primary Steamline Drain Feedvater Line Fcedvater Line Gteamline to RCIC Turbine X-11 X-12 X-13A X>>13B X-14 X-16h X-16B X-17 Steamline to HPCI Turbine RHR Shutdovn Supply Line RHR Return Line RHR Return Line Reactor Water Cleanup Line Core Spray Line Core Spray Line Blank 257 ENCLOSURE 2..QW BFNP TS 199 SUPPLEMENT 2}BFNP UNIT 2 Determination of No Significant Hazards Considerations Description of Amendment Request The amendment would'revise the Technical Sp'ecifications (T.S.)of the operating license to: (1)modify the core, physics,.thermal and,.hydraulic
'Limits to b'e'"consist:ent with the reanalyses associated with replacing about one-third of the core during the cycle 6 core reload outage, and (2)reflect" changes in var'ious specifications as a result of plant modifications performed during the outage.-Specifically.;'the amendment would result in changes to the T.S.in the following areas: Core Reload Changes related to the cycle 6 core reload involve removal of depleted fuel assemblies in about one-third of the nuclear reactor core and replacement with new fuel with attendant T.S.changes in the core protection safety limits.The new fuel will include fuel assemblies of the same type as previously loaded, plus four Westinghouse"QUAD+" demonstration assemblies.
The latter assemblies will be located in non-limiting locations.
The actual T.S.changes include changes in the Operating Limit Minimum Critical Power Ratio (OLMCPR), deletion of tables on maximum average planar exposure for fuel types no longer used, and changes to the references cited in the bases to reflect that TVA performed the reload analyses.2.Accident Monitoring Instrumentation Changes to T.S.instrumentation tables to add new instrumentation for high-range gaseous effuent monitors and containment high-range radiation monitors, and replace drywell pressure and suppression chamber water level instruments with new wide-range instruments in response to requirements in NUREG-0737;items II.F.'l.1, II.F.1.3, II,F.1,4 and II.F.1.5.A note similar to Standard Technical Specifications will also be added to describe operating limitations with less than the required instrumentation channels operable.3.Analog Instrumentation Modify the T.S.to apply the new calibration frequency and indicator range for the new reactor pressure instrumentation.
In the tables for surveillance requirements and calibration frequency for the instrument replaced, adjust'he instrument range-and change the calibration requirements to incorporate an extended calibr ation interval.The new calibration requirements, together with the new instrumentation, are expected to provide a more reliable instrumentation system.
Basis for No Significant Hazards Consideration Determination 1.Core Reload The proposed reload involves fuel assemblies of the same type (P8X8R and 8X8R)as previously found acceptable by the staff and loaded in the core in previous cycles.The reload also includes four Westinghouse fuel assemblies (QUAD+)in non-limiting locations.
These assemblies are analytically similar to the P8X8R fuel such that results of analytical methods used by licensee for the P8X8R fuel bound the QUAD+assemblies.
Therefore, this proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated.
The analytical methods used by the licensee to demonstrate conformance to the technical specifications are applicable to P8X8R, 8X8R and QUAD+fuel and have not been significantly changed from those previously approved by the staff.Since each replacement fuel assembly is of the same type as previously added to all three Browns Ferry units and other BWRs, or is analytically similar to those fuel asssemblies, and since the codes, models, and analytical techniques used to analyze the reload have been approved by the NRC, the changes to the T.S.associated with the reload will not involve a significant increase in the probability or consequences of an accident previously evaluated.
Finally, the proposed amendment will not involve a significant reduction in a margin of safety due to the reasons given above since no changes have been made to the acceptance criteria for the technical specification changes involved.Therefore, TVA proposes to determine that the proposed amendment does not involve a significant hazards consideration.
2.Accident Monitoring Instrumentation Item II.F.1 of NUREG>>0737,"Clarification of TMI Action Plan Requirements," requires all licensees to install five new monitoring systems and provide onsite sampling/analysis capability for a specified range of radionuclides.
For all six categories, NUREG-0737 states: "Changes to technical specifications will be required." During this refueling outage, the licensee will install: (a)a gaseous effluent high-range radiation monitoring system, (b)a containment high-range radiation monitoring system, (c)a drywell wide-range pressure monitoring system, and (d)a suppression chamber wide<<range water level monitoring system.These items were required by NUREG<<0737, items II.F.1.1, II.F.1.3, II.F.1.4, and II.F.1.5, respectively.
The changes to the T.S., which track the model T.S.provided to the licensee by the staff, are to add operability and surveillance requirements on the new monitoring systems.The revisions also delete the present drywell pressure and suppression chamber water level instruments since they are being replaced by items (c)and (d)above.The changes to the technical specifications are necessary administrative follow-up actions required by the Commission.
I<<a i.The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated; or create the possibility of new or different k1nd of accident, from any accident=previously.evaluated since no modifications are made to.any safety related;equipment and.: procedures;for..plant.
operation are not changed..Neither does the proposed;amendment.involve a.significant,'reduction'ina.
margin of safety,-sinceftechnical>specification-acceptance, criteria are not, reduced;.;.
Therefor e',,;TVA;.praposescto det'eemine;that;.thecproposed, amendment daes notninvolve"a>significant:..-hazards consideration.
~y1]", 3.Analog Instrumentation, iiv i"\C'i~ii&1 UI 4 I I-<<'4 v'tJiI'APPPll Ak 0 4".t-}V4~+-'I c-The modification,'involves-.removing,'one.
devic'e"and substituting another device to perform-'the same funct1on-..".
Changes.in';-design bases';" protect!ive.
function,.redundancy,=-
setpoints-and logi'c'-ar e not involved..However, the new indicator range is.0-1200 psig and the c'alibration-".interval has been increased commensurate with the reduced drift-for'"the new instrument:
'However'~because the"--modification..and T.S.change will.not eliminate or modify any"-i protective.
functions nor:.permit any new operational
'conditions, they"do="not create'he.
possibility-of a'ew'-kind of.'accident or significantly increase'the probability or consequences of-an--accident previo'usly
"-evaluated.
Because'of the increased reliability and-stability,='and-r educed>>drift of-=.the analog trip system, the increased cal1bration.intervals would:not-reduce any safetyimargin"'e:;ro,:o=".'~end".on;-
c.c-.-s no-1:.'.-.;h.'"igns f'.c..'..c~ar.'" considcri"'.'-'c:..
Therefore, TVA proposes to determine that the proposed amendment does not involve significant hazards considerations.
c~a 4.i v V>>T'i.~~'f'1=II*gP C.-.--=)i pppp,r<
>limitations with less'than the required instrumentation:.channels o'operable for.the instruments zadded by-<the,-orggkpal~~amengnent. in-=responsento requirements"Xn NUREG-0737verÃokq 8~qequfrqs an,~s-a'lternateimcnitoeing;method'ctocbe used when less than the required operable channels are available. Therefore, the amendment'does.not adversely:,effect safe plant operationo -.,~',-Jl"~<<2..Pages.78 and 105-.Page 78,.shows the.correct instrument range (0-=-]200psig) <for=the=reactor, pressure indicator and, page,105.shows anthe required, calibration,.frequency of-once.per.,12 months for this indicator at its proposed range.The original amendment request pdiscussed-replacing the old reactor pressure, instrument with a elqew.analog-system .-.This;new~system-.is more..accurate.and.,3.ess ,-pr one to drift than the:old system, and the required calibration frequenoy for the new reactor pressure indicatorI.3ias.been.-;evaluated and determined.to.be greater than 12 months.Since a 0-.1200 psig, range is acceptable for all, required postaccident monitoring functions and the 12-month calibration interval is ,.preferred to,a,6-month intervaland this, combination maintains.,~>the required accuracy,.this changeiwill.not adversely effect~plantsafety.,. icy,'as xnac~crtenzd cp't~~~.3.-;.Pages 171 and 172.--Revise~the~tables.for,iHAPLHGR,and..the..Figure d.3.5>K-1 for-HCPR limits to reflect the updated limits for cycle 6 operations. The Justification and safety analysis for these..revisions are described in TVA-RLR-002 ~Revision,1. A Jg*<<P+PhfOPi*~Q ki