ML19210B067
| ML19210B067 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/27/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19210B066 | List: |
| References | |
| NUDOCS 7911020484 | |
| Download: ML19210B067 (29) | |
Text
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ja are.i,y'c, UM T E D STs.TES y
NUCLE AR REGULATORY COVYlsslON y y[,,.f' > 'g Ye ASHING TO'e, D C. 20%5 4
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JERSEY CENTRAL POW'ER AND LIGHT C0"PANY PENNSYL'/ANI A ELECTRIC CC"PANY D_0CKET NO. 50-289 TiiREE MILE ISL AtiD N'.! CLEAR STATI0'1, UNIT NO.1 AMENDf'E'iT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. DPR-50 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Metropolitan Ediscn Company, Jersey Central Power & Light Corpany, and Pennsylvania Electric Company (the licensces), dated January 9,1978, as supplemented, cusplies with the standards and requirements of the Atomic Energy Act of 1954, as ar. ended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity 'with the application ~, the provisions of the Act, and the rules and regulations of the Coc. mission; C.
There is reasonable assurance (i) that the activities authorized by this ar.end ent can be corducted without endangering the health and safety of the Dublic, and (ii) that such activities will be conducted in ccepliance with the Co nission's reculations; D.
The issuance of this arend ent will not be inimicci to the comnon defense and security cr to the health and safety of the public; and E.
The issuance of this a endcent is in accordance with 10 CFR Part 51 of the CP mission's regulations and all applicable rer;uirenents h:ve been satisfied.
1564 210 a
7911020
('
, 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-50 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through /randment No. 29, 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.
FORTHENUCLEARREGULATOEC0F.MISS!0't y
)
f~' ~3 o
-l l~ 0 c' < I I - z', _ -l Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 27,1978 1564 211 e
ATTACi ';';T T0 l. ICE!!SE ff'E'lC 'E'!T :10. 39 FArILITY CPFolTIFI4 1.ICr"SE ::n. DPP-50 DOCKET ::0 50-220 Thechangedareasontherevisedpagesareshownbymarginai, lines.
Insert Paces Renove Paces vi and vii vi and vii 2-3 2-3 Figure 2.1-1 thru Figure 2.1-3 Figure 2.1-1 thru Figure 2.1-3 2-4 2-4 2-6 and 2-7 2-6 and 2-7 2-9 2-9 Figure 2.3-1 and Figure 2.3-2 Figure 2.3-1 and Figure 2.3-2 3-34 and 3-30a 3-34 ana 3-34a 3-35 and 3-35a 3-35 and 3-35a 3-36 and 3-36a 3-36 and 3-36a Figure 3.5-2A thru Figure 3.5-2tl Figure 3.5-2A thru Figure 3.5-2H 1564 212 8
I.T.07 07 F*c'-:q h
'r' U e Ti'cere 2.1-1 Core Prctectica Screty Lf:;it 2.1-2 Cwe lYetcetie.a Cr_fety Lf::ita 2.1-3 Cere Protcetien Safety Ensic Protectica Syste.' 15xi.12 Alle.teb1c' Cet Poin',3 2 3-1 2 3-2 Protectica Sy:: ten l'arit'r2 /J1our.ble Get l'of nts 3.1-1
.Ecceter coolat Sycten Ecctup Li::iteticas 3.1-2 liancto-coolcat system cc,ou.evn I&_itatienc Lir.iting. Prd.: cure Vs. Tc: p. rnterc curve for 3 00 STD 3.1-3 cc/ Lit.cr U:0 3.5-1 In:. ore Inc.trrent tica Cpecific: tion I.zic'l I.,Salesce Ir.dic..,1cn 3 5-2 Iue:.re In u r antctica c ecific:'.ica lir.:licl r
'ilux Tilt I~..:..cc.tica i
3 5-pf, Rod ronitir Li2 r, for l' PO O dC3 APliC M U"M the Peri od ron 0 to 12 5 _+ 5 EFPD; Cycle *,
i 3.5-23 Reserved l
t 3 5-20 Rod Positier.i.inits for 2 and 3 Purm operation Appliaole *urie-l th. PerioJ n 0 to 123 + 5 EirD; rycle 4 i
3 5-2?
n" served l,
3.5-2E Power Inbalar.co Envelope Applicable to Operation frun 0 to 125 i 5 EFPD; Cyc!" 4.
~
1564 213
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'.e h. !;-1 Rir.s Gi:.. 'Mr <ci ll;'.v e 4.h-2 Eint; Gi:9r fur ecf 21ance Critch Patterr. Ci._ct
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re.7t ri ctive of all pussible runctor The curve of Figure P.1-1 1:, the noot The cooln.t pu p-naxinc. ti. ::il T ower cerhinzi enn shown in Figure 2.1-2.
t.e ccnditicns at which a dninu"i U R of 1.3 c urv t.1 of Figure 2.1-3 : epro w.tpo:cibic ther.al rever for the nr.ber of reacto:'
is pred*cted at the.axinzt coolant punpa in operat2;n c: the local quality at the point of minimum D::2R (3) whichever condition ic ore rastrictive.
is equal to 22 percent, l
~
The nTximum thermal power for three punp cperation is 87.1 percent due to power level trip produced c.t 80.7 percent power) plus the maxinu= calibratien and inctrumentation error.
The c1xirun thernal power for other reseter coolant pump ccnditiens is produced in a similar manner.
Using a lo:11 quality limit of 22 percent at the point cf minimum D733 as c basic for curve 3 of Figure 2.1-3 is a conse:vstive criterion even though the D"33.
in higher than the quality at the point of nininu:
quality at the exit the calculated by the ELi-2 correlation continually increasco frc The DMBR 23 point of nini=un D::LH, so ths; the exit "::3? is always higher and is a functicn of the pressure.
above and to the For each cu: ee of Figure 2.1-3, a pressure-terperature point lef t of the curve would rcsult in a D::33 gretter than 1.3 er a local quality at the point of mininum I:2? lens than 22 percent for that particular resetcr restrictive than any other reactor coolant puup situation.
Curte 1 it nore
. pre: ure/tenperature poinc abcvc and to th7 coolant pump cituaticr be:Eu:e en, left of this curve vill be above and to the left of the c:her curves.
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AT-'li c e t o + he li.i t en reacter cc;1e.nt cyate:~ pressure.
Obj ec i i ve_
inte.~rity of the reactor ecol:.nt nycte:1 und to prevent the
':'o r:sintain the relcare e' SiFnifier.nt t.. cunts cf fiscion prc:'.uct cetivity.
Tgeci fie r.ti en The reacter coM er.*. synt"- 1.ressure r'.all not execM 2750 pr.it when 2.2.1 fuel nsec:611er in :ne rea-tcr veccel.
there are Faces (1) cervac c.c c btvrier to prevc::t rcdior.ucli !cs in The receter ccd ent syrte: 1 the rencter c oelrelt fr, - rer:.. hin e t).e nt-rmphare.
In t!.c < vent of n fuel c?';dd! -
c.1 :ri ar c ae.in,t the releuc of fieris7 fr.f lur e, the recctor ec:k.nt r..t e:-
- 4. r tel;- to cc,xre the intercit, le r redu c '. :.. E t,.M ir..in r s; cen t re., viro of the re t-tcr :c :w r tte.
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'9 e d&
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l Ther..at Power Level, %
I l
-- 120 I
(-39.112) p PS. Limit (112)
(44.112)
- 110 ACCEPT!.BLE 4 PUMP
-- 100 Kw/Ft Kw/Ft OPERATION
(;njt g,33,37,,)
-- 90 (87.1) 2 (44.87.8)
Limit I
-- 80 (sc. 8 c )
(-57,80)
ACCEPTADLE 3&4 PU:!P
-- 70 OPERATION
(-39.59.6) 60 (59.s) 3 (44.59.6)
ACCEP1ABLE 2,3 & !! PUHP
-- 50 (49.2.49.2)
(-4s.u.46.4)
OPERATION
-- 40
..- 30 20 10 l
l I
t 1
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t I
f 50
-40 20
-10 0
10 20 30 40 50 60 Reactor Po. er Ir. balance, %
Curve ReactorCcolantFlc',(Ib/hr) 6 I
139.8 x 10 6
15 4
'7 2
104.5 x 10 6
3 68.8 x 10 CORE PROTER. TION SAFETY L li:l i f IP!-l, CYCLE 4 Figure 2.l-7
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eg :yg (Lt..'i.a) 130.0 x 10"> (1:C'.)'
11 '/ '
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'lhe pra:t'r level trip cet point proluced by the power-t>..av rstio providca both hich 1:ver level and lov fin protu tion in the event the reactor power level in:rcacer or the ren: tor ecolant flcv r:;t.e decreasen.
The power level tri; cet point produced b;p the pcwcr to flow ratio For providec overpove: D::B protcetien for all noden of pt. p creration.
every flow rate thico is a nuinam portiu ibic power level, and f,r Typical every power level there is a ninimun Fern.icaible lov flow rate.
power 1cvel and lov flow rate combinations fer the purp situaticns of Table 2 3-1 are as folleuc:
Trip would occur when four reactor ecolant pumps are operatihc 1.
if power la 108 percent and reactor flev rate la 100 percent, or flow rate ic 92.5 percent and power level is 100 percent.
l 2.
Trip would cecur when three reactor coolant pumps are operating if power is c0.7 percent and reactor fl0V rate is 7L.7 percent or flev rate in c;.L percent and power level is 75 percent.
3 Trip vculd c: car when ene reacter coolant pu p is operating in each loop (totil of two p=ps c;erating) if the power ic 531 percent and reactor flev rate is L9.1 percent or flow rate is h5 3 percent v.i the power level is !.9 percer.t.
The flux /flev ratio: account for the maxic= calibration and instrumentation errors and t"a
.ui
.u. variation fr:= the averace value of the W: flow signal in such a manner that the reactor protective cyctem receive.s a concervative 1:1dicatien of the pC flov.
taken for an I!o per..lty in re.ctcr ecclant flow throuch the core va:
open core vent valve tecauce of tne core vent valve curveillance 1.rocrrc:
during each refuel;::c outect.
For cafety analycia calculaticn the r.aximum calibration and instrumentation errora for the ic..r: level vere used.
po'..c r-imt alence t c." Mri e r are es tabli p.ed in order to r>re'." :.t The reac tar ther 11 2 i ;i'.
fr u t<
- cre,2dc i.
2ece thert11 lir.it:- are cit: v w-cr pe%.,,
./:L W: cr
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(pare: M the in-
' o f the erre -i'w: pc.: in tha t0* tem half of cere) red; :
the le.el t-it trait. cd 1
-tio T: 4r-t.-flow ratia Jo tnat ti e '
1.,'
af Tigure 2.3-2 are preda:il.
The. mic r-to-fj :. ratio re;'.y t;.c r., 4 r level t rip. ad a;;0ci t(,1 re.' :t,
- c r /- we t -
.cc./ 1.03 parrent for a one p~ruent f ic.. r n act:
n.
pow r-::
ilance bc: : 22:
b.
Pump men!1 era The r':h.
'-t x -- i ter
- rc ot the nini m : c aru D:'" f rcr decror e t-lt:
- 2. 3 F, trir:
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1:
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n '.
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w.r ren!- r: alco '
trict
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pl/*.0 ; in CDeratiCn.
RT GT I IM P u h e d]Li l A
A pl O jfM hi i
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=
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ta 7:: v 1"Ju th" rarcty l i ::i t ( F'l'. 3 !. 3 y) I c e c:
den i:m t; r 9ient.
Thie
+.o eclibr<tt !cn and instrrJv:nt c r: ors, the '.fe ty. '. . f c i 3 m3=r'l " 45 pi ;<rc nsurc l
crror in th:' hic,h reactor coolun*,
c t e:.1 prenauen trip cettinj.
The lou pre" cure (1TC. ;i g ) 1.nr1 vt.ri nble Ic i r,reture (ll.'IS Rut - 5103) trip retrcint rhn n in icure 2.3-1 h-vc teca catabli:;hti to raintcin the result D:ill rc. tic ; rco.ter t'ur. m equal to 1. 3 for ther e de;i gn cccident s that in n prer.~.ure rcla' i'n (3, f).
i Due to the calibr. tit
- 1 it.n r'
- nta titn ecr ra, ti.e ~- f e t,. ora.lyr*, used a var;
- 11-low r. r.c tu m,,1
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.? < lu? ci ( 31. Y5 'fcut -
';1143) and a lov ; ccc: a tr ip v tim of ITIC ;;ic.
o r:0
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d.
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'. ting lin'.t
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, i'1,.ure P. N hw
< n c. tCli' :. d to cre. unt (619.') rin -
ea cer ':l e er r.
' ~,, s n t t e'. P ".. '.n c e, in tr-n;mrn. i ng rnnv.c.
The cLlibr:tt..l r w+
of t he ten;'e r tt.re ch.unel; of the RP."1 13
$20 to G.'O
'F.' c t r i p :. c t, i
- c f t'c e che.. :1 1 C 9 F.
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bn 2503
=
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P = 2'405 psig I
2300
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i 1564 223
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j, 7.,
h I $0$6$&NQ THERMAL POWER LEVEL, '<
-_ 120 110 (108) (17,108)
(-17,108)
I
__100 l
M2 = 10 ACCEPTACLE y,j,,
4 PUPP
( 35.90)
CPERAil0N
- 90 (35.90) 1 I
(80 7) i ed i
CCEPTABLE 70 l
3 L 4 PU'4P (35,62.7)
( 35,62.7)
OPERATION l
-- 60 l
(53.1)t 50 6
ACCEPTABLE
-. 40 2,3, L 4 PUYP
( 35,35.1)
OPERATICN l
_ 30 I
l j
-- 20 m
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-10 0
10 20 30 40 50 60 70 Reactor Pc,er Iraalance, 1564 224 s2:u;c, w n,...
s.:..;vca
- r. t r
,.: ' i'i:C
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(
o.
IV I -l L5CLE i iir,urc 2 3 f
H J,,,
N. a,;.co r ::a.
If a contrel rod in the reCulating or axi.a1 po ter shaping f.
grourc is declared inoper ble per Specifiention h.7.1.2.,
operation ra; continue -'rovided the roda in the 6roup are positiene3 such that the rod that was declared inoperah2 is maintainel within allu.lable group average pocition liraits c f Speci fication h.7.1.2.
If the inoperable rod in Paragraph "e" above is in groups 5, 6, 6
7, or 8, the other rods in the group may be tric=ed to the care I:ornal cperaticn of 100 percent of the thermal power position.
allowable for the rearter coolant pump combination may then continue provided that the red that was declared inoperable is maintained within allcvable group average position limits in 3525 The verth of single inserted centrol red: during criticality are 3 5 2.3 limited by the restrictions of Specificati:n 31.3.5 and the Control Fod Fcsition Linits defined in Specification 3.5 2.5 3 5.2.h Quadrant tilt:
Except for rhysics tests tne qu cirant tilt chall not exceed a.
+k.0lf, an determined ucing the fu'l incore detector system.
When the fu]l incore detector ::iote-is not n.-ailable and except for rhysics tests qu'idrant tilt chall not exceed +2.82C l
b.
cs deterr#.ned using the mininun incore detector system.
available end When neither incere detector systen abe re 13 for.:ysics tests quairant tilt chall not exceed 42. Chi c.
except as dete:~:ned u ing the power rance channels displayed on the console fo" each quadrmnt ( '.ut, cf care detec tor sy. sten).
d.
Excert fo* +csics terta if quat ant ti ?t execcl3 the tilt 1
. chal'. be reducad irr^diatel:.
t'.
%1cw t *.e ib 2 r 1cvel cutof f (see :'ig.:re.- 3 5-2!, and 3.5-23
- brcover, the f
limit peru pcVer le.'l cu off si w_ +.11 k red ::cd 'i i ercent for u.' '1 percem t.
- in m:n.
0-til'. Jinit.
For less thrm feu.
_. d 2 ':^rcer ' c
't.u pump o r '_
- cn * - E
- il r. aw n.
11 bc :=
thern,1
.e' alle
.al=
-* ^ enactor coolint b.:p cc.b:
m.
of tuo tilt li::it.
for ca ':.
percent tilt.n cxet r n '- '11 h Within a r"riod of L nours, the qu'1drant pu.2f tilt e.
e
- c..
c..,.
p.
a..,. _.. -
4,.
,4-4-
m.
-. ~,
.,, _.. u. 4,,.. t. a, u c.
u uo
,.e <1,...,,, a.
4...
Or the foll%in.* ay a.,1 int. in Cetpoin'.5 nd li -i ts 5 all be
...'.i,s 4aas.'
.s m : m:ec a n m.. r - rc..rn +.: = e env a 1.
for tT.I p retpoin",3 -" Nil Ce rCluced 2 perc0nt in F0wer e..
u 31 1564 225
~
m
-a 5m Ypp';jhh dun L..
a c
n.nnt u.,i,,r. m m
i
.tithdrawal limits (:-igures 3.5-2A, 2.
The control rod ccm.m 3.5-25, 3 5-2C, 3.;-2D, and 3.5-21I, chall be reduced 2
[
tilt in excess of the percent in power for each 1 percent tilt limit.
3 Tne operational intalance limits (Ficure 3 5-2E,.cnd 3 5-2F) shall te reduced 2 percent in pcVer for each 1 percent tilt in excess of the tilt li=dt.
Except for physics or dicgncatic testing, if quadrant tilt is f.
in excess of +27 105 determined using the full inecre detectcr systen (FIT), or +25 515 deterrined using the ninimum incore detector systen (MIT) if the FIT is not available, or *23 0LC determined using the out cf core detec:cr systen (OCT) when neither the FIT nor MIT are available, the rea: tor vill be placed in the het shutdovn conditier.
Diagnosite testing during p0ver operation with a quadrant til is pernitted provided that the ther:21 power allevable is restricted as stated in 3 5.2.L.d at ve.
Quadrant tilt shall te :nitored cn a ninitun frequency of cnce g.
every two hours curing power operation above 15 percent of rated power.
' ' R0 19fi{@@[]
1
'b 1
6
~ + ~,
, ~ -
1564 226 I
Y, J, 19 Arrndmeo r No.
j-T.a
3.h.2.5" Control Rod Po;.i tienn Operating red crcup overlap chall not exceed 25 percent +5 per-for physics testa.
a.
cent, tetween two cequential Croupa except Position linits are npecified for reculatinC and axial power b.
Execpt for physics tects er exereininc shaping centrol roda.
control roda, the regulating centrol rod insertion /vithdrawal limits are specified on Figurec 3 5-2A, and 3.5-23 for fcur pump operr.ti ca and Ficurca 3. 5-2C and 3. 5-20 three or' tvo pump Also exceptin6 physic; tests or exercising, control operation.
rods, the axial pcVer shapin6 centrol rod insertion /vithdrawal limits are rpecified en Ficure 3.5-2H.
If any of these control l
rod pocition limita are exceeded, corrective neasures shall be taken ittediately to achieve an acceptable control rod position.
Acceptable control rod positiens shall be attained within four hours.
Except for physics tests, ;cuer chall not te increased above the power level cutoff of c2 percent of rated thermal power c.
unless one of the folleving conditicns is satisfied:
Xenon reactivity never deviated = re than 10 percent frcn 1.
value for operation at 100 percent of the equilibriu:
rated thernal power.
Xencn reactivity deviated more than 10 percent and is now 2.
within 10 percent of the equilibrium value for operaticn at 100 percent of rated thernal power and asymptotically accroachint; stabilitv.
Except fer Xenon free startup (when 3.5.2 5.c.2 applies) 3.
of 37 to 92 perecnt the rea: tor nas operated within a rans:
of rated thermal pre.cer for a period exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in the coluble poisen control ecde.
tininum frequcncy cf Core imbalnn e ch211 he =cnitere?. en a d.
e hcurs d:rinc power operrticn above LO percert of once e.u,
u Except icr phraico tests, correctivu neasures rated pa-'r.
in (reducticr of inbulance by AFSH to eccento and /or reduction reactor retur) shall be taker to maintain cy, ration.cithin the If the imbalance envelope de fined by Ficures 3 5-2E, and 3.5-2P.
- i ct in the envelope define d by Figures 2.5-25, and 3.5-2I correu
.c causurea chall be taken to achieve an acceptabic
{
la not If an acce ptable intal,.nce is not achieved ziti.;.'
i t..balt.n e e.
' en.ctar pcuer shall be reduced until %bc. lance four h
linita n ' nat.
1: nits are given in 3 1.3.5 c.
Cafe ty r:a leched at all tirra v:th 3 5.2.6 Tac contro.1 ro l ute mtuh panela
te
.uth H x.. tl.e n.,m Jntm m t.
ii -f ad accen-ia ne 1564 227 pq v rn3 o
o A
u
. ; Q, oof
- g, n
u,wm a.v,y,,
/
- O_7, 1
A power -19 chall be taken at intervals not to exceed 30 cffective 3 5 2.7 full po.; r co /n usin?, the incore inctrumentation detection system to p:wer distribution ic -ithin the limits chmm in Figure verify the 3.5-ZG.
Pasen The power-inbalance e:rselope defined in Figures 3.5-2E, and 3.5-2i is based on 1xinu linear heat rate (cee Figure 3.5-LOCA analyues vnich h 'te defined the r:
2Q such th1t the r.ar:irm clad temperature vill not excee1 the Final Adecptance O,rere tion cutnide of the power imbalance envelope alone Criteria (2230F).
does not constitute a situatien that ticuld enuse the Final Acceptance Criteria
'~he pmem imbal:.nce cnvelepe represents to be exceeded should a LOCA cccur.
of operation limited by the rinal Acceptance Criteria caly if the the boundar.,
sif.iraval/incertion limit; as defined. by Figures 3.5-centrol rois are at ti.e 11
+.
Aa.
,. + - >.,
-a
<o c.. ~a an.<,.
<a 3.5,m...,
--v w
- 3. e-e-n, J..-
s, ge., 3. W,-,
s d.i ' ' e- ". ". '.. c.,n.~.-. rs..i. &
.i r.
~4 " c M,.
b g- ' a.~:w^ -i^n of-s
" r 4
L'uclear uncertainty facters a.
- m..^
<.a 7 ca_'..~m'.'.~.'. ". c e.
- a. ' -. ' "s b.
l h@'-d [l"E 'n]O q rg i j
A
_ t
- -y
'i t i
O, T a
Fuel densification effecto
- a._m J b, /
l c.
d.
Hot rod r.snufac t:. ing tolerir.ce f actors Postulated fuel rod bow effectn e.
c: Iicures 3.5-PA, 3.3-27., 3.5-20, The Eod index versus.'s11cnble Feuer curve: Tr-se three recienc are:
l 3.5-2D, and 3.5-2E descri;e three recians.
o.,.... 4, - nr. 1 a.
1.
1v...<.r n,,aa-
....u c
g.
u, c.c. ' ".' c '. ' l "..t' '. ' ~.,
m i
prca s4.,.a c.t.~ n (n,.e...,.4,-.,
4.-
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.,,g<,.
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si
.~
-n 3
a
.. D. o " ' ^ "> o.'
". C '1".'
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M.. *.." i ' t - " ".. <~-.' '. n v'."
cent'doru. a.-iolati ca of.a limi t: nc cc:' iticr f;.
four hour; i
.ot operation.
'.~'.c limiting cr: teri within the Ik ctricted r:ccicr
- e
.n.... c. a.
- ~.,.o.
..~a~
vnye,.
n.. : n. <. v~a
- c.,n :.,. a..
. m $..a,.
1, e..
n r
po c.n+4 h hcar v
m 1
,ery lov est_;iall.,
in probabili'c cf tue e acci ' _..t:
time fruce, inndvertant c+creier within the Restri<;ted Rccion for r-per.iol of L hours is clioved.
1564 228 Y..
s ).
., s.1 g 19 e..- *.. (. g
- ..}.
/
't ' ) k
1
'ups is n] to. d tween succescive cont r7 ga.
The 25:5 percent o.
lover at the u;per and le
, #, of the n t rc'.:e.
since the worth cf a red 20 Control rods are arranged in groups or banks defined as follcar-Funetten Orcup D [] (()
$,h,kff[3I[q l,G 1
Safety (J )
2 Safety i
10.y ? ' ; /
3 Safety
" O h
Safety 5
Regulating 6
Regulating Regulating (Xenon transient override) 7 APSR (axial power shaping tank) 8 Groupo l
Control rol groups are withdrawn in sequence beginning with group 1.
The normal pcsition at power is for 5, 6 and 7 are overlapped 25 percent.
l group 7 to be partially inserted.
limiting of the following three The red position linits are based en the most ECCS power peakini;, shutdcun =argin, and potential ejected rod criteria:As discussed ateve, compliance with the ECCS power peaking critcrien vorth.
is ensured by the rod position limits.
'~ne =ininun available red worth,
shutdown consistent with the red positica limits, pro. ides for achieving hot by reactor trip at any tina, ascuming the highest verth control red that 10 vithdrawn ren ins in the full cut position (1). The rod pcsition limita also ensure that incerted rod ercups vill nct conta:.n single rod verths 6reater These values have been shown to be safe by than: 0.655 Ak/k at rated pcVer.
A maximum the safety analysi (2) of the hypcthetical rod ejecticn accident.
allcred by the rod pcsit.icn sin 6 e inserted ecntrol rod worth of 1.05 fk/k 10 1
A single irrerted control rod worth 1.05Ak/k at limits at hot zero pcver.
beginning of life, hot, ~.ero pcVer would result in a lover transient pcak ther:nal power and, therefore, less severe envircnnental consequences than 0.65:~ J.k/k ejected rod worth at rated pover.
The plant cenputer..-111 scan for tilt and i.chalance and v111 satisfy th9 tec!.nical specification requircrcnts.
If the cen,ruter la out of service, than nc:.anl calculation fer tilt abcve 15 percent pouer end i:rbalance above '-0 percent power.uct te performed at least every two hours until the cc :pute ; s returned to service.
licits set forth in Specification 3.5.2.h have teen The quadr.nt p:ver tilt establiched within the ti'.rnal c.nalycia design case using an actual core tilt with the full.:. core l
of +h.9^:5 whi ch i. eqm ralent to a +k.015 tilt ecnnu:ca l
uncertainties included.
instrumentation i tt teast.e: e.
a l.r.' u -
Du ring the phy.' en testin-prcLg n, the high flu;. trip retpoin',c are sti cU rel; c e ', a fol:r:s 'n ascure an adi tionn.1 cafet;.
";in is pro.o c2.
Trin Setra- :t Tec* h _ar 1564 229 0
5 0.-
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e q --
b D
./
l
(*l st a I NN 9
9 t
/
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B EF.C. 7.CES (1) FS/3, Secticn 3.2.2.1.2 l
(2) FSAE, Section l!. 2.2.2 1564 230 a
O Mie:.1..'u t.;o. 39 3-?'.
'e b
I 27s.l.102 l
- ~
230.102 POWER 100 -
LEVEL CUT 0FF 274.1.92
~
= 92%
P 90 RESTRICTED 30
M I
~'* 70 N
La
'O 60 E
l 'e 8. 5 0 e
50 PERMIS$1SLE I; so 30 l
20 118.15 430.15 (y.'.=
- ,~
l t
R0D POSITION LIMITS FOR 4 PUM c
25 50 75 100 125 150 175 200 725 250 275 3C0 OPERATION FROM 0 70 125 1 5 E Red Ir.' Jew. t Witndrawn TMI. CYCLE E 0
25 50 75 100 figure 3.5 64 Group 7 0
25 50 75 IOC 1
1 1
i g
Group 6 g
0 25 EO 75 100 h
e i
i i
i e
Group 5 Nu
Reserved for Figure 3.5-2B Ane ndrien t L.,10, i f, p'.,f, ja
6ou O.
9 o
U tuo. lot 23C l*I 1so. rot
~~
I C,-
o NOT ALLOWED sv 90
~
2=e.89 t3 F2 8
s e
to ' 7C 5
8 60
~
p PERMISSIBLE
,~
2: SC est.30 o
s-23 J
RESTRICTED
{ 20 FC7 2 & 3 FUuP a.
20 j/
ele.is I30 it
[G 0.7.4 se r U? -
f t
t t
t e
t 0
25 50 75 100 125 150 175 200 225 250 275 300 Rod Index. "J Withd rawn 0
25 50 75 100 R0D POSITION LlHITS FOR 2 & 3 PUMP OPERATION FRCH 0 T0 125 1 5 EFPD 0
25 59 75 ICO THI, CYCLE 4 Gr n 6 Figen 3.5-20 Q 0 25 50 75 100 Q
t 9
1 s
A Group 5 Nuu
se Reserved for Figure 3.5-2D 1564 234 f
Av ni?~.en t ;;o.
17', 2f, 39
/
Po,er, 7. of 2535 Mdt I ESTRICTED l'EGION
- 110
-23.40.102 10.25.102
-- g Go_ i
~
-21.59,92 9.25,92
-- 90
- 80 PERMISSIBLE ~~
OPERATING REGION
. 60 50
-. 40 30
-- 20
-- 10 I
t i
I I
i I
I I
I 40
-30
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UNITED STATES OF AMERICA f;UCLEAR REGULATORY COMMISSI0il In the Patter of
)
)
METROPOLITAN EDISON COMPAT;Y,
)
JERSEY CENTRAL POWER & LIGHT
)
DOCKET ti0. 50-289 COMPANY, AND
)
PENNSYLVANIA ELECTRIC COMPANY
)
)
(Three Mile Island Nuclear Station )
Unit f;o. 1)
)
EXEMPTION 1.
Metropolitan Edison Company, Jersey Central Power and Light Company, and the Pennsylvania Electric Company (the licensees), are the holders of facility Operating License No. DPR-50 which authorizes the operation of the nuclear power reactor known as Three Mile Island Nuclear Station, Unit No.1 (TMI-l or the facility), at steady reactor power levels not in excess of 2535 megawatts thermal (rated power).
The facility consists of a Babcock & Wilcox Conpany (B&',-l) designed pressurized water reactor (PWR) located at the licensees' site in Dauphin, County, Pennsylvania. '
II.
In accordance with the requirements of the Comission's Emergency Core Cooling Systen (ECCS) Acceptance Criteria,10 CFR 50.46, Metropolitan Edison Company (Met Ed) submitted on July 9,1975, as supplemented 1564 239 DUPLICATE DOCUMENT Entire document previously entered into system under:
ANO_
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