ML20058A307
| ML20058A307 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  (DPR-52-A-040, DPR-52-A-40) |
| Issue date: | 11/16/1978 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058A306 | List: |
| References | |
| NUDOCS 7812050017 | |
| Download: ML20058A307 (29) | |
Text
._.
S UNITED STATES j
NUCLEAR REGULATORY COMMISSION y
f ;
g
. j WASHINGTON. D. C. 20555
%, '**...f TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No. DPR-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendments by Tennessee Valley Authority (the licensee) dated August 2,1978 and August 11, 1978, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Commission; P
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 amendmer t is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 6120500 4
781go 5 9 9(y
~~
. 2.
Accordingly, the license is amended by changes to the Technical Speci fications as indicated 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) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 40, 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 0c:nn e/Clc.
Thomas A / polito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 16, 1978
4 ATTACHMENT TO LICENSE AMENDMENT NO. 40 FACILITY OPERATING LICENSE NO. OPR-52 i
DOCKET NO. 50-250 Revise Appendix A as follows:
l Remove the following pages and replace with identically numbered pages:
33/34 35/36 51/52 73/74 75/76 113/114 131/132 205/206 207/208 241/242 293/294 303/304 Revise Appendix B as follows:
Remove the following page and replace with identically numbered page:
41/42 Marginal lines indicate revised area. Overleaf pages are provided for
- onvenience.
4 A
w
-<m g
, - r
TABLE 3.1.A REACTOR PROTECTIO.4 SYSTDi (SCRA.M) INSTRUMENTATICN REQUIREME.VT Min. No.
of Operable Inst.
Modes in Which Function Clannels Must Be Operable Per Trip Shut-S y r. t. m (1)
Trip Tunction Trip 1.evel Setting Startup/ Hot down Refuel (7)
Standby Run 1
Mode Switch in Shutdown X
X X
X 1.A 1
Hanual Scram X
x X
X 1.A IPM (16) 3 Ittsh Flux I2kkNtJndicated y,
X (22) x (3) 1.A 3
Inuperative X
x (3) 1.A u
APPyt (16) 2 Htgh Flux See Spec. 2.1.A.1 t
2 lit r.S Flux
< 15I ra ted power 7
1,A gy },g 2
Inoperative (11)
X(21) x(17)
(13)
- 1. A o r 1. 3 2
townscale 1 3 Indicated on Scale X(21)
X(17)
X 1.A or 1.3 (11)
(11) x(12) 1.A or 1.5 2
If tp K.: actor Pressure < 1055 pe t s X(10) x X
1.A I
Hir.h Drvvell
< 2 pstg Pressure (14)
X(8)
X(8)
X 1.A 2
R e a c to r t.ov Wa t e r 1538" above vessel tero 1.evel (14)
X x
x 1.A 2
It t s h *.la t e r f. eve l in Sc rais
< 50 Cellone D*1 charge Tan's, X
~
X(2) x x
1.A
TABLE 3.!.A (Continued)
Min. No.
of 3'*
,}5 Modes in Which Fun: tion Ch.n ::cl s f'US1 Be Operable Pei Trip Startun/ Hot Sy j t e: q(l_1 Trie function Trip Level Settino Percel(7)
Standby _
Run Action (l) 4 Main Ster Line Isolation ICT Valve Closure X(3)(6)
X(3)(6)
X(6) 1.A or 1.C Valve Clos,2re 2
Turbine Cont. talve fast Upon trip of the fast X(4)
X(4)
X(4) 1.A or 1.0 Closure acting solenoid valver 4
Turbine Stop Valve Closure i 10'; Valve Closure X(4)
X(4)
X(4)
- 1. A or 1.0 2
Turbine Centrol Valve -
550 psig X(4)
X(4)
X(4) 1.A or 1.0 Loss of Control Oil y
Pr es su re 2
Turbine first Stage
< 154 psig X(18)
X(18)
X(18)
(19)
Pressure Permissive 2
Turbine Condenser Low
> 23 In. Hg, Vacuum X(3)
X(3)
X 1.A or 1.C Vacisuin 2
Main Stean Line High
< 3X Ne mal full Power X(9)
X(9)
X(9) 1.A or 1.C Radiation (14)
Background (20) m
%,/
%d b
IIDT ES ro;< T A P.t.E 3.1_. A,
,A 1.
There shall b.- two opers ble or tripped trip syitems for each function.
If the mintme:n n'mber of op=rable in,s t r ume n t channeta per trip '.,yster.
cannot be met for both trip oystems, the appropriate actions listed below chall be taken.
A.
Initiate insertion of operabia roJs and cosplete insertion of all operabic roda within four hours.
B.
Reduce power Icvel to ILM range onJ place mode'svitch in the Startup/ Hoc Standby powition within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Redoc.e turbine load and close main steam line isolation valves within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D.
Reduce power to less than 30% of rated.
2.
Scrnm diocharge volume high bypass nay be used~1n shutdown or refuel to bypans otra., discharge volume scram vith control rod block for reactor protection ayaten recet.
1055 peig and node avitch no: in run.
3.
Bypassed if reactor pressure 4.
Bypassed when turbine first stage pressure is less than 15h psis.
I PJi' a a r e by pa c ed wh e n id'RM' o are onstale and the reactor code sultch is in the run position.
6.
The design permits clonure of any two lines without a scran bein;;
initiated.
7.
hn the reactor is suberitical and the reactor v. iter tenperatere is Icos thrin 212*F. only the following trip f unction s need to be operable; g
A.
Mode switch in shatdown B.
Hano.1 acram C.
liigh flor. I R.M D.
Scram discharge volume high leve'l E.
APFli 15 scram 8.
Not required to be operable when primary containment int e.gr it y 1.4 not required.
9.
Not required if all eain ate inlines are iaolated.
35
c..
he ad i s r* c t bolt ed to the vessel.
- 11. The A PR'1 dcwnscale trip function is only active when the reactor mode switch is in run.
- 12. The AFM dew scale
- t. rip is automatically b, passed when the IBM inatntmenta ticn is cperable and not high.
- 13. Less than 1u ope.rable LPP.P a will cause a trip system trip.
Ia. Channel shared by Reactor Protection System and Primary Cont a i r.:1e.m t and Reactor Ve:ssel Isolation Control System.
A channel f ailure may be a channel f ailure in each system.
- 16. Chartnel sha red by Heactor Protection System and Reactor Manua.1 Control System (Rod Bicck Portion).
A channel f alltire may be a channel f ailure in each system.
\\
- 17. Not required while performing Icv power physics tests at
/
atmospheric pressttre during or af ter refueling at power levels not to exceed 5 M'd (t).
- 18. Operability is required whes normal first-stage pressure is below 30%(<154psig).
- 19. Action
- 1. A or 1.0 shall be taken only if the permissive f ails in such a manner to prevent the affected PPS logic frem perforrting its intended function.
Otherwise, no actica is required.
- 20. An alarm setting of 1.5 times nor na; background at rated co-er shall be established to alert the c;erate-to abnor.a1 radiatten levels in crimary coolant.
21.
The APPM High Flux and Inoperative Trips do not have to be operable in the Refuel Mode if the source Range Monitors are connected to give
)
a non-coincidence, High Flux scram, at < 5 x 105 cps.
The SRM's shall be operable per Speci fication 3.10.B.1.- The removal of eight (8) shorting links is required to provide non-coincidence high-flux scram protection from the Source Range Monitors.
- 22. The three required IRM's per trip channel is not required in the Shutdown or Refuel Modes if at least four IRM's (one in each core quadrant) are connected to give a non-coincidence, High Flux scram.
The removal of four (4) shorting links is required to provide non-coincidence high-flux scram protection from the IRM's.
36
)
t 1.1MITINC CONDIT!045 r0R OPERATION SURv!!ilANCE R* QUI 1DCMTS 3.2.3 Core and Containment Cooling 4.2.3 Core and containment Cooling Systrua - Inittstion & Contrel Systems - Initiatton 6 Control are required to be operabla shall be considered operabis if they are within the required surveil-lance testing frequency and there is no reason to suspect that they are inoperable.
C.
Control Rod Dieck Actuation C.
Coetrol Rod 81ock Actuation i
IEstrus ntation shall be function-The it et t ing CenJ1t ions of g
operetton f or the in s t r u men-ally tested, calibrated and checked tation that initiates control as indicated in Table 4.2.C.
rod block are given in Table 3.2.C.
System logic shall be funct1Jn411V tested se indicated in Table 4.2.C.
DELETE Nov covered by note 7.C.
D.
Off-das Feat Treatment Isolation Off-Cas Post Treatment Isol? tion 3,
Functions
((netton
- 1. Off Cas Fost
- cateent P.c n i t o r s 1, Off-C13 Post Treat =ent *:nitorin2 Syste=
(a) Cacept as ep(cified in (b)
Ins t run.at ation shall be fune-below, both off-gaa tions11y testec, calibraved and pest trest-ent radiation checked as indicated in Table noniters shall be crerable 1 4.2.0.
l during reactor operation.
The isolation function
(
51 stem logic shall *os func tion-trip settin3s for the j
ally tasted as indicated is Table 4.2.0.
(
centters shall be set at a value n.* t to exceed the I equivaient of the stack r elease limit specifted i v.,
specification 3.5.B.1.
l l
51
t 1.txtT!t CONDITIONS FOR OPEU TICM StntVIItt.AN0Z RICUIXN'TS 3.2.D Of f-cas Pos t Treat =ent Isola tion 4.2.D Off-Cas Post Trea tnent Isolation Functions Function (b) Frem and after the date that one of the eve off-gas post treat =ent radiation" monitors is.ade or found to be inoperable, centirued reactor power operatten is permissible during the next seven days previdad that the inoperable monitor is tripped in the devnscale position. One radiation monitor may be out of
}
service for four hours for functional test and/
or calibration without the monitor being in a g
i downscale trippsd condition.
(c) Upon the loss of both off-gas post treatment radia-tion conitors. initiate at orderly shutdown and shut the mainsteam isolation valves or the of f-cas isolat ien valve viihin 10 h --
E.
Isryvell Leak E2$ection I.
D ryve ll Le a's S e t te t f ag The li=iting conditiens of epera-Instrur.entati:n shcil be calibrated tien for the instrutantatien that and checked as indic:ted La Tshl:
monitors dryvell lesi detection 4.2.3.
are given in Ta'ala 3.2.Z.
F.
Survatilsnes Interu entatien 7.
Eurvet!!rece t e a t t'. :.atition
)
The limitins ccediti:n: for the Instru::ntstien sht:1 he calitrstsd instru antstien that previdos and checked as indicated in Tabla surveillanes intern:tien readcuta 4.2.7, are given in Tabis J.: F.
C.
Centrol leo-Isolatten O.
Centrol ?.eem !3:12ff t1 The limitin: car.diti:na for Instrunantatiet sh:li be :411)rstad ins t rumen ta tion tha t !selaces and chs:kcd as indiestad in "abis the centrol ter: and initiates 4.2.0, the centrcl roca c=argency pres surizatics systesa are given in Tabis 3.2.C.
St
'... ^' :.
TABt.E 3.2.C
~
INSTRUNUffATION TilAT Ill!TIATES ROD BIDCKS Hintasma No.
Operablo Per 1 rip Sys (Q I' unction Trip I.evel Setting
_ 0,66W + 42%. (2) 2(1)
APluf Upscale (Flow Biss) 2(1)
APKH Upscale (Startup Mode) (8)
< 12I 2(1)
APRM Dovascale (9) 13I 2(1)
APRM Inoperative (10 )
b 1(7)
RBM Upscale (Flow'Blas)
< 0.66W + M% (2) 1(7)
RDH Dovoscale (9)
L 32 1(7)
RBH Icoperative (10 )
g 3(1)
IRH Upscale (8)
,< 108/125 of full scale 3(1)
IRH Uownscale (3)(8) 15/125 of rull ocale I
3(1)
IIUf Detector not in Startup Position (8)
(11) l l
3(1)
Ik!( Inoperative (0)
(10*)
l 5
2(1)(6)
SRltlipscale (8)
_1 x 10 counts /sec.
2(1)(6)
- Slut Downscale (4)(8)
L 3 counts /sec.
2(1)(6)
S2N Detector not in Startup Position (4)(8)
(11) 2(1)(6)
SRM Inoper"tive (8)
(los) a 2(1)
Pl<m Dias Cceparator
_ 10% difference in recirculation flows
_ 110% recircuLstion'flov 2(1)
Plov Elas Upocale If t)
Ref Block f.octe N/A i'( 1 )
It::f:S lie::t.rairit.
II47 psig turbine
( P ' - ]..8 (1,}) ?<
fi re.t s t.ar,a pressitre (apprOyImately 30% power)
4
..er : rn. TAni.e 1.7.r 1.
For the startup and run poettiona of the kractor Made selector switre..
chere shall be two operable or tripped trir systeam for each function.
The $44 IkM. a nd A P RM (Startup mode), blocks ne:J not be operable in "Aun" mode, and the A/RM (Flow blesed) and REN red blocks need not be operable in "Startup'* mode.
If the first column cannot be met for one of the two trip systema. this condition==y exist f or wo to seven daye provided that during that eine the operable systr. is functionally tested imnediately and daily thereafter; if this conditLan last lonyer than seven days. the eystem with the inoperable channal shall be tripped.
If the first colusn cannot be met,for both trip systess, leth trip syste=* ehall be tripp.d.
2.
k' is the recirculatica loop flow in percent of design. Trip level settinc is in percent of rat ed power (3293 tr..*t ). A ratio of TRP/CMTLPD <1.0 is pernitted at reduced power.
See Specifi/ation 2.1 for APRM control rod block setpoint.
'N
- 3..I?.M down s eal e i s bypa s s ed wh en i t t o un it s i cve s t r ar.g o.
)
4.
This f unc tion le bypes aud when the count rate is ; 100 cp e sad IRM abare ranse 2.
S.
One in s t ruaest channel; i. e., on e A P RM o r 1 RM o r R FM, per trip oyetes may be bypa s sed e acs pt enly one of four 3RM may be bypaeaed.
6.
IRN channele A, E, C. C all in range 8 byp a s s e s ' tM c hAc = e l e A & C functions.
IRN cnannele 8, r, D. H all in range 8 by7 esses FAM chancola I & D functione.
7.
The fc11cving oper aticnal restraints apply t: the EEN cr.ly, Ecth REM channels are bycassed when reseter power is g 30".
a.
b.
The REM need not be operable in the "startup" pcsitien of the i
J reacter mede selectar svitch.
c.
Two REM chsnnels are provided and cnly cne cf these may 'ce typassed fr: the :enscle.
Ar. REM channel nay te cut of service f:r testing and/cr maintenance previded this condition dccs not isst lenger th.a.n 2* hours in any thirty day peri;d.
d.
If minimum eenditions for Table 3.2.0 are net net, administrative centrcis, shall be i==eiiately imposed to prevent centrol red ithirsval.
I 1
l 7k
TADf.E 3.2.C IttSTRinfDrTATION THAT INITIATES ROD BI4CKS Mislensa 50 Operable Per Trip Sys ($)
Tunction Trip 1.evel $ctting 2(1)
APRM Upscale (Flow Biss)
- 0,66u + 42%,(2)
, 12%
2(1)
APEJ{ Upac41e (Startup lfode) (8) 2(1)
APRM Downscale (9) 1 3I (10 )
2(1)
APRM Inoperative b
1(7)
RSH Upscale (Flow Biss)
< 0.66u + 41% (2) for two recirculation loco ooeratioe
_ 0.56W + 37.7%(2) for one recirculation loop operatic 1(7)
R2H Dovnecale (9) i 3Z (10 )
1(7)
RM Inoperative
_ 108/125 of full scale 3(1)
IPJf Upscale (8) 3(1)
IRM Dovuscale (3)(8) t 5/125 or rull ocale uw 3(1)
IRH Detector not in Startup Position (8)
(11)
(10*)
3(1)
IM Inoperative (8)
< 1 x 10 counts /sec.
2(1)(6)
SPJ( Upecale (8) 2(1)(6)
SUt Downscale (4)(8) t 3 counts /sec.
l 2(1)(6)
Sri Detector not in Startup Position '(4)(8)
(11) 2(1)(6)
SM Inoperative (8)
(los)
<10% difference in recirculathm flows 2(1)
Flow Bies Ccesarator
<110% recirculation flow 2(1)
Flot) Bias Upocale N/A 1(1)
Rof Block Locic 2(1) 1:SCS !<estrnirit 147 psig turbine (IS-35-61A &
first stage pressure (approximately 301 pover) l 10-:i5-6111)
a
.t m r.n. _erw...TA_Nr ).7 :-
1.
For the startisp and run pos it iona of the Strac tor Mode Selector Switeli, there shall be two operable nr tripped trip systeme for each function.
The SRM, IM, and APM (Startup e.ede), blocks need not be operable in "Aun" *= ode, and the APR.*t (Flow biar,ed) and RBM rod blocks need not be operable in "Startup" rode.
If the first column cannot be rest for one of the two trip syetams, this condition may exist for up to seven days provided"that during th.st time the operable sys:em is functionally tested i mediately and daily thereaf ter; if this cendition last lon,te r than seven days, the system with the inoperable channel chall be tripped.
If the first column cannot be ciet,for both trip eystems, both trip e y s t e rne shall be tripped.
2.
is the recirculation loop ilov in percent of design. Trip 1cvel setting is in percent of rated p.,rer (32n.1 m't).
A ratio of FRP/C".TT.PD <1.0 ic pernitted at reduced power.
See Specif ic'at ton 2.1 for APPJI control rod block setpoint.
.s 3
IFM dcweeals is bypsse 100 cp s a nd lu above range 2.
One ins t ruinent channel; i.e., one APM or IM or REM, per trip systte m.ay be bypassed except cmly one of four SPJi ray be bypassed.
6.
IM channels A, E, C, C all in range 8 bypasses FM chaesels A & C functions.
IM channels B, T, D. H all in range 8 bypassee SM channole 3 & D fuactions.
7 The f;11cvinc cr+ rational restraint: apply to the EB: only:
I Feth EE4 char.nels are typassed when reactor pcver is 3 305, a.
b.
The EUs need nct be operable in the "startup" positien of the reacter mode select r switch.
Tvc RTM channels are provided and cnly cne of these may be c.
typassed fr = the console. An RE' channel may be out cf service fer testing e.r.d/cr mainteasnee prcvided this cendition does last lenger thcn 2'. hours in ar.y thirty day pericd.
not d.
If ninimu. ccnditions fcr Table 3.2.C are nct tet, administrative centrols shall be inmediately imposed to prevent ecntrci rod vi?M raval.
1 Tk
8.
This function is bypassed when the roda evitch is placed in Run.
9.
This function is only active when the code evitch is in Run.
This function is auto utically bypassed when the IM inserventi. tion is operable and not high, 10.
The inoperative tripe are produced by the following functiona:
a.
SRM and I U (1) Loc al ope r e t a -c a lib r a t e" ev i t ch no t in operate.
I (2) Pce r eupply voltage lov.
(3) Circuit beards not in circuit, b.
AP R.M (1) Loc al "operat e-calibra te" rsit:h net in operste.
1 (2) Lene t ha n 14 LJM inpu t s.
(3) Circuit te a r d o r.o t in circuit.
c.
RAM (1) Local " operate-calibrate" evitch not in operate.
(2) Circuit boards not in circuit.
(3) REN faile to null.
(4) Less than required number of LFKM inputs for rod selected.
11.
Detector traverse is adjusted to 1141 2 inches, placizs the detector lower position 24 inches below the lower core plate.
75
i
'k i
TABLE 3.2.D OFF-GAS POST TREA'nsT ISOLATIO:t INSTRtT'EWATION Min. No.
Operable (Il Function Trip t.evel Setting Actios (2)
Remarks 2
Of f-Ces Fost Treatt-e nt Note 3 A or B 1.
2 upscales, or 1 downscal Honitor and I upscale, or 2 dovn-scales v!!! isolate off-gas line.
1 Of f-Cas l'ost Treat =ent Note 3 5
1.
One trip system with auto Isolation transf er to another source el NOTES:
1.
Whenever the statex number operable cannot be met, the indicated action shall be taken.
2.
Action A.
Refer to Section 3.2.D.l.b B.
Refer to Ocction 3.2.D.1.c 3.
Trip setting to correspond to Specification 3.2.D.l.a e
%^
'%. J'
1 3.2
.sasts The HPCI hir,h s' ; ow and ten,,rrature inst rueent at lun a re provided to detect a break in the hPCI steam P!Pini.
Trig ping of tFis lastrm.entation re-suits in actuotton of HPCI isv1.tton valves.
Tripping lotte f or the h1Rh flow is a 1 out of 2 logit, and all ser.sor s are trquired :o be operable.
Ill y h teaperatur.
n the ej tr.ity of the HF"I equipment is sensed by 4
~'he 16 tr perature suitches sets el 4 bircral'It t e t,,e r a t u r e switches.
6 are arranged tr 7 tilt syntest with 8 temperator.- switche in each trip eystem.
The MrC1 trip t e t t in. ? c.
90 rit f i-iagh alc< v.J 7:C*T for high tem-perature are suc h thet cer. t ce ova r y is pe r ve n t re a..J f l >s f on product release is wfth;n 21.;ts.
The kCIC higt, fin. a n.1 reararatwir le. truarnietsc. irt arranged the samt as that for rh. HTC:.
The trit seteing of 450" e.,n to. htch flow and 200*T for ter.peratute art base d on it.c same c ri t t i :a as cl.e HPC1.
Iltgh temperateier at the Feactor Cicanuo System floor driln could Indicate a break in the c;tL...; syste~.
M.cn high teoper;ture ccrurs, the cleanup system is isola;ed.
The instrusentittna *$tth intttares Ctf5 artien it arrinced in a dual bus s y e t r e.. As fer cther vi:al testrue.entatton arranted in this fashion, the Specifttaflo*, reserves the effectiveness of the tystem even during periods w%+n 'a'v ca mee or testing. Is Le!,p perfOrned An erecption to this is when ! r tc !wectiona testinr. to beint perforce The contrc! t er b !.t. functarme are prnsided to parvent escessive control rod wt P Jr e.al t o t *.. ' !K!f daes no'. decreas* t c. 1. Ot'. The trip logic for th:$ functic-la 1 out of n.
c. E. ' n / t r i,s o r, one of sta APR.M's, eight I P.M ' s, or fc.: 5LM's w 11 result in a r c. 3 t. ! oc a.
The mir1 ur n-channes r retra-ents
,*S*; r 5 f'tcfent itss t rumen t a -
tion to a,no.,
r..
r.. r. : e fa.ture triter:-
t-ces.
Two REM char.nels are pro-vided and only one of these may be bypassed from the console, for mainte-rr.r.ce an;/cr testing, prcvided that this condition does not last longer than 2L neurs in an;. thirty day period. This time period is only 3% of the operating tire ir. a month and c:et nct significantly increase the risk of preventir6 ar. ins d certent centrcl rod withdrava:.
The A P R ". r ad i a x. focCr19n 14 fic= b!Jstd ans preve9ts a s!An!fifant redWC-tion in FF1
<6, c:.:.< :.r ng eperatton at r et se c
- flew.
The APA4 pro-vite: Cress <cre prm c-ttso, i.e
!!"Its the gress ccre po.ar increase f r o r. with.*ra.ai ef
- .c. rol rods in the normal wit %c raval sequence. The trips are set e r, t,ar x;re is ente:atned greater than 1.00.
The RE= red ricc.
f.-
- .m pro.1/cw L...i.' pretccrira of the core:
1.e.,
the preventics o' critteil loca! ret;on of the core, for a p0.cr in a etnale rod witnJra..) error tree a Itsit:ng control rod pattern.
II)
3,2 BAsf5 If t he IRM channels are in the vuret condition of allowed bypass, the acaling arrangement i= wuch that 'or unbypa ssed IL" channels, a rod block signal is generated heiore the dete.trJ neutrons flux has increened by more t han a Isetur ut 10.
has failed or the A downscale indication is an indication the instrument instrument is nnt sensitive enough.
In either case the instrument will in control rod notion and thus, control rod motion not respond to changes is prevented.
The refueling interlocks alpe operate onc logic channel, and are required for safety only when the code switch is in the refueling position.
cooling fer small pipe breaks, the HPCI system Per effective emergency core must function since r actor pressare does not decrease rapid enough to or LPCI to operate in time.
The automatic pressure allov eftr.er core spray relief func: ton is prevtJed as a backup to the HoCl in the event the HPCI does not onerate.
The artsngement et the tripping centacts is s'uch as to provide this functton when neccansrv and minimize sourtous operation. The trip settings given in the specification are adequate te assure the above w s criteria are met.
Th* apccifiention preserves the effectiveness of the
)
testing, or calibration, and slao system during periods of naintenance, minimi:es the risk ef inadvertent operation; 1.e., only one instrument channel out of mervice.
Two pest trest:(nt nff-;ar radiation Ornitors are previded and, when their trip peint is r eached, casse an 1selstian of the of f-gas line. Isolation is initiated when botn instrumcnts reach their high trip peint or one has an upscale trip and the other a deenscale trip or both have a downscale trip.
Botn 'ustruments tre required for trip but the instruments art set so that any instrueents are wet so that the instantaneous stack relesae rete limit given in Specifteation 3.5 is not exceeded.
N tar each unit <nich initiate ?tinary j
Four t.id t o t ion iuntturi nic pi iv !.t Containment isolation (Croap o isol: tion valves) Reactor duilding isolation and operation of the Standby Gas Treau.ent Systee. These instrument channels monitor the rad 1Atlen in the Reactor Zone ventilation e1haust ducts and in the Refueling Zone.
Trip setting of 100 mr/hr for the ninitors in the Refueling Zone are based upen initiating ncr9al vantilaticu i solation and SCTS operation so that none of the activity released during the refueling accident lesves the Reactor Building via the normal ventilation path but rather all the activity is processed by the SCTS.
Flev integraters ane sump fill rate and pump out rate timers sie used to detcruine leata:e in the drywe;1. A system whereby the tist interval to fill a known volume will be utilized to provide a backup.
An air saepling systes is also provtced to detect l e a ka g e inside the pri=ary centai= ment (See Table 3.2.E).
114
t t
2 / t.
1 fi a s n.
sf r.c e,. i.i 1.' c :! r n:$*ra:nr.sith n vlsaal indtratloa of neu-tren ? e + 1.
T 'i e cr.ose<pic, ira u! t t.. t t s r ;i, c t id n t i art f unc t io s.n et t h.- trf:!al nc.ttrn fla..
'.*h.- r. :3e f ree-a t of at I r.' i t )
(. n u n t i t.* r art seno 4aso-r) that... f r r e r.,1 c n t,
shots!d it nc.ur.
- t.. Ins at or a l.o v e ! !..e is.: t ' el value of 10 of a n t..t isi. r la tt: ensty
. of.ratisients : r o.
cold c.u1 t.na O... o,erebs- ?. 7/1 t h e r. n i un sid ne atletu st e to em !'6: t M a p,t r u x fi to (: lt!:slity us:n.- r.cao '.e n c o u:s pn t:rr.. o f s: n t e r.J c u,t r al r od v' t'.d ::va l. A iir.1 et cf tse e,sersbl. 5?.1".3 are provided a s an cddeo conoe:v tin.
5.
The Pcd 111oc k 'tonitor (RE'*J is dest; sed t re automati*cally p r e v e rit fuci e s n o J r.
tn: cvent of cr:orcows rod vit'sdraval fro, Io:::le s ct hi;n cover den;'1 7 durt,t high povtr Icvel ope:4tton.
' Ivc P3M channels are provided, and one of these may be bypassed from the console for maintenance and/or testing.
Autematic rod withdreval blocks from one of the channels vill bicek erroneous rod withdrawal soon enouEh to prevent fuel dar: age. The specified restrictions with one channel out of service conservatively assure that fuel dar. age vill not occur due to red withdrawal errers
.t.en this ccr.fition exists.
A liriting ( c r. t r e l red pattern is a pattern whici. rerults in the core being on a thermal hydraulic linit, (ie.
M: tr cis en by Specification 3.5.k or LHGR of 18.5 for 7x7 or l ~s. ; far 8x6)
Durint, use of such patterns, it is jidr~i that testinr. of the R B f! system prior to v i t le -
drava! nf such rods to assure its operability vill aerure that f r.p r o p e r withdrawal d c' e s not occur.
It is normally the responsibility of the Nuclear T r. r f n e e r to identify these l itn i t i ng patterns and t'c designatcJ rods either when the patterns arc initia!!y established or as they develop due to the occurttnce of inoperable control rods in other than i
linfting p a t t e r ri s.
Other personnel qualified to per-4 f o r t-these functions rn a y - b e designated by the plant s u p e r t r. t e n d e n t to perform these functions.
Scram In..rt:on T!.c s The centre; red system is designated to bring the reacter suberiticA' at the rate fast enough to prevent fuel datage:
1c.
to trivert the fl C T T<
f r o::; b e c e rn i n e, l e s s than 1.06.
T li e I t :- i t i n g re.t transient is given in Reference 1.
Analysis of this trarcient s !. n u s that t r. e negative reactivity rates resultfrir
'r:-
t '. c ceran with the a v e r s. r e response of all the drivt > a *. r.t v e n in the above s p e c i f f e a t f o r; provide the ter;uf re c rr tret!cn. and MCPR r e tn a i n e greater than 1.06.
On an e.'
T, S c r.c d e r. r.= d a t J o n of centrol rod scrat neifore i ured during n] ant startur and was d e t e r r-i n e d
'r i
131 l
{
I
~
part1;ulate caterial (probably cortstructiop Jebris) p'u*,ging an internal control rod drive filter. The design of the present control rod drive (Model 7 RDB144 3) is gre= sly improved by the relocation of the filter to a lo ation out of the scram drive path:
1.e..
It can no longer interfere with acram performance, even is c^mpletely blocked.
The derraded per f ormance of the original drive (CRD7RD3144A) unde' dirtv operating conditions and the insensitivity of the rede=1gned drive (C of 7 RD Bl = 4 5 ) has been demonstrated bY a cert a of engineerine tests under simulated reactor operating cond.tions The succ e s sf ul perf ernance of the new drive under actus1 operating conditions has also been demonstrated by cena atent.y too.- in-service test resulte for plants'using the new Irtve.ind nas be irferred f r 7= plante using the older model driv with a modified tlarRet screen site, inte rnal filter which to 1 se prunc to plugging.
Data has been decu.ented by surveil-lanc. repcrte in varteus operattug planta.
These include Oyster Creck, Monticello Dresden 2 and Diesden 3.
Approximately 3000 drive testa have been recorded to date.
-3 1
/
Folleving identification of the 'plugr,ed filter" probles, very freqaent scram te sta were necessary to ensure proper perf ormance.
However, t h e mo r e frequent scra-tests are now considerec totally unnecessar, and (nwise for the following reasons:
1.
Crratic sc r ar. cerfor:aace has been identified as due to an obstructed drive filter in type "A" d rive s.
The drives in B F N7 are of the new ** B" type desigr whose scra p e r f o rr.a n c e ta unaffected by filter condition.
2.
The dirt lead is prirarily relcance' d sting startup of the reactor when the itector and its systres are first subjected to flows and prentire and therr.41 stresses. Special atten-tion and cea e.a re c e ra now being taken to assure cleaner syeters.
Re,ctora with drives identles! or similar (shorter otroke. sr. aller pieten areas) have operated thtough r.any refueling cyrles with no sudden or erratic changes in scrs=
eerfor ance.
This presperational and startup teacing is
.uffittent to detect ano:rlous drive performance.
3.
he 72-hour nucage limit which initiated the start of the
- requent actsm testing is arbitrarv. havint no logical basis other than quantifvinc a " major outage" which eight reasone-bly be caused by an event so severe as to possibly affect d r i v e p e r f o rra.s c e. This requirement is unwise because it provsces an incentive for shertcut ac tions to ta st en re turni,4 "on line' to avoid the additional testing due a 72-hour outag2.
132
UNIT 2. page 7 TABt.E 3.6.11 SHOCK SUPPRESSORS (SNUBBERS) m 8
Snubbers Snubbers in liigh Inaccessible Snubber's Radiation Area During Snubbers Especially During. Nomal Accessible Our Snubber No.
Systm Elevation Shutdown
- Dif ficult to Revnove Operation' Normal _Operat R9 - north RCIC 564 X
R9 - south RCIC (ring hdr) 564 X
X R1 upper Condensate S&S 548 (ring header)
X RI lower Condensate S&S 518 (ring header) l X.
R2 - north Condensate S&S 548 (ring header)
X R2 - west Condensate S&S 548 (ring header)
R3 - east Condensate S&S 548 X
(ring heaster)
X R3 - west Condensate S&S 548 (ring header)
R4 - north Condensate S&S 548 X
X (ring header)
R4 - east Condensate S&S 548 X
X (ring header)
R5 upper Condensate S&S 548 X
X (ring heador).
P.S - l owe r Condensate S&S 555 X
X (ring he-ider)
= -. _ -
TABLE 3.6.H UNIT 2 page 8 k-SHOCK SUPPRESSORS (5NUBBERS)
Saubbers Snubbers in High Inaccessible Snubbers Radiation Area During Snubbers Especially During Nonral Accessible During Snubber No.
System Elevation Shutdown
- Of f ficult to Recove.
Operation Nonnal Operation i
551-2 PSC (ring hdr) 525 I
t 551-3 PSC (ring hdr) 525 I
.55Z-4 PSC (ring hdr) 525 I
$5Z-5 PSC (ring hdr) 575 I
55I.7 PSC (ring hdr) 525 I
$5Z-1A PSC (ring hdr) 525 I
551-2A PSC (ring hdr) 525 I,
551-3A PSC (ring hdr) 525 I
552-4A PSC (ring hdr) 525 I
$5Z-5A PSC (ring hdr) 525 x
551-6A PSC (ring hdr) 525
-I 55I-7A PSC (ring hdr) 525 I
$52-8A PSC (ring.hdr) 525 I-Q, s'
i
TABLE 3.6.H IJNii 2 -
page 9 SHOCK SUPPR QSORS (SNilBBERS) c!
~
Snubbers in High inaccessible Snubbers Radiation Area During snubbers Especially During Nomal Accessible During Snubber No.
System Elevatinn Shutdown
- Difficult to Remove Operation _,
Nomal Operation I
R33 EECW 605 X
R1 upper RBCCW 615 X
R1 lower RBCCW 615 X
R2 upper RBCCW 615 X
R2 lower RBCCW 615 X
R3 upper RBCCW 615 X
R3 lower RBCCW 615 X
R4 upper RBCCW 615 Y
R4 lower RitCCW 615 X
SSI-A Recirculation 556 X
551-B Recirculation 556 X
552-A Recirculation 558 X
4
TABLE 3.6.H UNIT 2 - page 10 SHOCK SUPPRESSORS (SNUBBERS) m S
Snubbers Snubbers in High Inaccessible Snubbers Radiation Area During Snubbers Especially During Nomal Accessible During Snubber No.
System Elevation Shutdown
- Difficult to Remove Opera tion Nomal Operation S52-B Recirculation 558 X
_SS3-A(295*)
Recirculation 564 X
1 SS3-A(335')
Recirculation 564 X
553-B(l'5*)
Pecirculation 564 X
SS3-B(154*)
Recirculation 564 X
SS4-A Recirculation 570 X
'554-B Recirculation 570 X
SSS-A(262*)
Recirculation 581 X
SS5-A(325*). Recirculation 581 X
~
SSS-B(35*)
Recirculation 581 X
555-B(93*)
Recirculation 581 X
SS6-A Recircula tion 568 X
5S6-8 Recirculation 568 X
SS7 Recirculation 564 X
- -558 Recirculation 564 X
otiodifications'to this Table due to changes in high radiation areas should be submitted to the NRC as part '
(
of the next 1icense amendment.
\\-
)
g -
o
3.7.C Secc-dary Containeent 4.7.C Seconier,; Containnent capability to maintain 1/4 inch of water vacoam unoer calm vind ( < 5 mph) condi-tions with a systet inleakaze rate of not more than 12,000 c6e, i
b.
Secondary containnent capa-bility to naintain 1/4 inch :
water vacuum under caln wing
( e 5 mph) conditions with a systen inleakage rate of not more than 12,000 e gn, shall be demons t ra t ed i.t each refueling outage pria-to refueling.
2.
If reactor rene secondary con-2.
After a secondary containment tainment integrity cannot be violatien is decernined the maintained the folleving enn-standby gas treat =ent system diciens shall be met:
vill be operated immediately 1
a f t'e r the affected :ones are isolated from the remainder of a.
The reactor aball be made the secondary containment to
[
suberitical and Specifica-confirm its ability to main-tien 3.3.A shall be met.
tain the remainder of the secondary containment at 1/'-
b.
The reactor sball be cooled inch of vster negative pressure down below 212*T and the under calm vind cenditior.s.
reactor ecolant ayacem
- vented, c.
Tuel n.ovement shall not be permitted in the teat-tor tone, d.
Prinary centsir..ent integri y, maintained.
3.
Secondary centsinment integrity l ahall be maint11ned in the re-fueling zone, cacent as spect-I fled in 3.7.C.4 l
l 1
241 l
1 l
TINC coNntTIONS Foif OPERATION SURVElLLANCE MECUlf..Cil't!
?.
Secondary Containment 4.7.C Secondary Containesnt 4.
If refueling zone secondary containment cannot be maintained the following conditions shall be met:
a.
Hand 11nr. of spent fuel and all operations over spent fuel paole and open reac-tor wells containing fuel shall be prohibited.
b.
The standby aas treatuent system suction to the re-fueling zone vill be T \\
blocked except for a con-trolled leakage area si:ed to assure the achieving of a vacuum of at least 1/4-inch of water and not over 3 inches of water in all three reactor zones.
Primary Containment,_1nolation Valves.
D.
Prinary Containnent Isolatfen V:lvaa 1.
Durinr. reactor pcwer operation, 1.
The primary centsinnent iscla-all iselation valves listed in tion valves surveill,u.ce chall Tsbic 3.7.A and all reactor be performed as folloV6!
coolant systen instrunent line flow check velves shall be a.
At least once per operating operable except as specified cycle the operable isols-in 3. 7.D. 2.
tion valves that sre
}
power operated and auto-matically initiated shall le tested int simulatad automati: initiation and closure times.
b.
/.t least ence per quarter:
$ ) All normally open pever 1
cperated isolation valvee (except for the main atsan line pcver-operated itolatien valves) shall be fully closed and re:pened.
242
o a
StRVt1LLUct Rf Qvie rwt'T!
LDttTINC C0 CIT 10rt5 FCs OrtsATION 0*I*A Austigary r i ce t rie el Equipmen_t_
).9.A 3.a l l t a r? Electrical Etu!P9'"f the s pec if ied tima esquence.
cos.on transformer and c.
Once a month the guentity cooling tower t ranbl ont.er
- f d1'*e1 fuel available capable of supplying power shall be logged, to the shutdown board *.
d.
2ach dieert generator shall be stver. en annual in.pec-b.
A f c r t h o p e r a t ' e un ' t s tion in arcordence with 1 a nd 2 c n e s e ' generator.
Ins t ruct ions ba sed on the manufacturer's e t c omme nd a-k.
Bu s e s tr.d Bcards Acanlatle gg,,,,
s.
Start buses lA an$ 18 ore e.
Once a month a sample of energtre:-
diesel fuel anett be checked for quellt7 The qualitt t,
Tre unats 1 ent 0 4-av ehall be witnin the accepts-s hu t e o wr, bo a r d s are ble Itatts specified in enersstee.
Table 1 of the latest revision to ASTM D975 and logged.
c.
Tre L 8 s....
sha'dost bo ar d s a s sor,a t e d = s th tne unat 2.
D.C. Po-cr %vstti - Unit Battertes (230-Volt) Diesel Cenerator are ener g ::e1 tatterlee (l?5. dolt and 55wedown board Battertes (JS0-vol:)
d.
Usservelinse re.ny5 cretable er s'. art a.
tvery ween the specific bases 14 a r.d 12 and L kV s h ut d ov?. boaras.
A. B. C.
greetty a,,4 the voltage af the ptlet call, and tee.pcra-ar.d D-gute eg an adjacent cell and overall battery voltage thall 3,
T%e 2 30-V ol t uttt and e%utdovn be eenested and logged.
board batteries sac a battery charger for esto tattery and b.
Zwery t %* c e tenthg the ses-a s so c i a t ed pattery boarde are suresents -tell is made of operable.
voltage of esch cell to seasest C.1 volt. erettfle 6.
!4gte Systems gr,, tty of e ar n c e !!. and temperatwee of
- t7 fifth e.
Coumon accident e t t e. a l cell.
These measuremente logic eyeten le operable
- eAall be lodged.
A batte P7 ra ted dis charge b.
Af0 r load sheddtng logic c.
erst ee le ope r able.
(espaetty) test shall bo I"'
'O
"'i
I ' ' I C P d '" I 7
There shall be a -J nte..e of t L? e, an: catout curreSt 10),3*3 ga!!ees of diese1 f.I AJ43cre*o*.tb Shall De IC{f ed is the StandDy diesel geaerg.
at *mtervals net to exceed ter fuel tar.he.
2k can'r.s.
.2i3
- f StfRVEII.I.ANCE REOUIRDENTS L I MI T I Ng,,,Co,rm t T10 NLTO,R_,0 P @T 104 3.9.A Austit*iy Electrient Equipment 6.9.A Auxiliary Electricsl Ec_uipment 3.
Logic Systems Both divisions of the common a,
accident signal logic system shall be tested every 6 months to demonstrate that it will function on actuation of the core spray systen of each reactor to provide an auto-matic start signal to all 4 units 1 and 2 diesel gencretors.
b.
Once eve.y 6 nonths, the condi-tion under which the 480-volt load sheddir.g Ingic system is
,,.)
required shall be simulated using pendant test switches and/or pushbutton test svitches to de-monetrate that the lo.1d shedding logic system would initiate !oad shedding signals on the diesel auxiliary boards, reactor MOV boards, and the 480-Volt shut-down boards 4
Unde rvolta ge Relays a.
Once every 6 nooths, the con-dition under which the under-voltage relays are required shall'be simuisted vich so undervoltage oc start buses lA sad 1B to der.onstrate that the diesel generatora vill start.
b.
Once every 6 months, the con-ditions under which the under-voltage relays are required shall be simulated with an unde rvoltage on each shutdevn i
board to demonst rate that the l
associated diesel generator vill start.
c.
The unitarvoltage relays which start the dicoel generaters from start buses LA and 18 and the 4-kV shutdovn beordr.,
shall be calibrated ancus11y for trip and reset and the j
measurements logged.
l l
294 1
{
,t,8$tTINC CCN01 TION' FOR orFRATION SURVE!!. LANCE REOUTREMENTS J.10.A Retueitng inter 1ccks 4.10.A Refueling Interlocks control rods are fully
/ 'N inserted and have had f
(
their directional con-trol valves electrically disarmed, it is suffi-cient to demonstrate that the core is sub-critical with a margin of at least 0.38 ok at any time during the maintenance. A control rod on which maintenance is being perf ormed shall be considered inoperable.
3.
The fuel grapple hoist load switch shall be set at,y1.000 lbs.
4.
If the frame-mounted auxi-11ary hoist, the menorail-mounted auxiliary hoist. or the service ' plat form hois t is to be used for handling fuel with the head eff the reactor vessel, the load limit switch on the hoist to be used shall be est at
< 400 lbs.
ft 5.
A asximum of two non-adjacent control rods may be withdrawn from the core for the purpose of perfor-ming control rod and/or control rod drive mainten-ance provided the follow-e ing conditions are satis-fled:
I a.
The reactor mode evitch shall be locked in the
" refuel" position. The refueling interlock which prevents more than one control rod from being withdrawn may be bypassed for one of the control rods on which maintenanct is being P e rf o rr.e d.
All other 303 L
i 3.10.A Refueling Inter 1ncks 4.10.A Refueling Interlocks refueling interlocke shall be operable.
b.
A sufficient number of control rods shall be operable so that the core can be made sub-critical with the strongest operable con-trol rod fully with-
, drawn and all other operabic control rods fully inserted. or all directional control valves for remaining a
control rods shall be disa rmed elec trically and sufficient marCin j
to criticality shall be demonstrated, c.
If maintenance is to be perforned on two control rod drives they must be separated by more than two control cells in any direction.
d.
An appropriat e nu.-be r of SRH'o are available as defined in specifi-
\\
cation 3.10.A.
6.
Any number of control roda 3
With the mode selector switch in
')
r.ay be withdrawn or removed from the reactor core pro-the refuel or shutdown mode, no' viding the following condi-control rod may be withdrawn until j
two licensed operators have confir. ed ;
tiona are antisfied:
that either all fuel has been removed I from around that rod or that all s.
The reactor mode switch
~
i is locked in the "re-control rods in immediately adjacent f uel" position. The cells have been fully inserted and refueling interlock electrically disarmed.
which preventa more than one control rod from 3 04
.d
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. Figure 4.2-1 LOCAL MONITORING STATIONS BROWNS FERRY NUCLEAR PLANT 5
ATHENS 5
w_
U.S. HWY 72
[
1 O
k
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9 ALA HWY 20 f
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Legend O
Air Monitor DECATUR S
Air Monifer 8 TLD Station N
~
A TLD Station
{
A Automctic Well Sort;ter Scale O
I 2
3 4
Q O
Dairy Form i
uaes
[
.