NL-16-070, Core Operating Limits Report
| ML16174A099 | |
| Person / Time | |
|---|---|
| Site: | Indian Point |
| Issue date: | 06/15/2016 |
| From: | Coyle L Entergy Nuclear Northeast |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-16-070 | |
| Download: ML16174A099 (14) | |
Text
-==~ Entergx NL-16-070 June 15, 2016 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk 11555 Rockville Pike, TWFN-2F1 Rockville, MD 20852-2738
SUBJECT:
Dear Sir I Madam:
Core Operating Limits Report Indian Point Nuclear Generating Unit Number 2 Docket No. 50-247 License No. DPR-26 Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box249 Buchanan, NY 10511-024 Tel 914 254 6700 Lawrence Coyle Site Vice President Entergy Nuclear Operations Inc. (Entergy), as holder of License No. DPR-26, is providing in the Enclosure a copy of the Core Operating Limits Report (COLR) for Indian Point 2 Cycler 23 in accordance with Technical Specification 5.6.5.d.
This letter contains no new regulatory commitments. If you have any questions please contact Mr. Robert Walpole, Manager, Regulatory Assurance at (914) 254-6710.
Sincerely,
Enclosure:
2-GRAPH-PPC-6, Rev. 17, Core Operating Limits Report (COLR) cc:
Mr. Douglas Pickett, Senior Project Manager, NRC NRR DORL Mr. Daniel H. Dorman, Regional Administrator, NRC Region 1 NRC Senior Resident Inspector Mr. John B. Rhodes, President and CEO, NYSERDA Ms. Bridget Frymire, New York State Dept. of Public Service
ENCLOSURE TO NL-16-070 2-GRAPH-PPC-6, REV. 17, CORE OPERATING LIMITS REPORT (COLR).
/
ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247
~Entergy,
.Nuclear Noriheast A**** rovedB :
pp
... y
- Team'Staff Procedure Owner Procedure Use ls:
D Continuous a Reference PARTIAL REVISION.
Control Copy:.. ----
Effective Date: 3/J (e lzi;J (p P~ge ~ qf 12 (COLR) 0 er.at.\\o~
.. REVISION'
SUMMARY
1 jj
'REASON FOFrRE*YISION.
NJ?:*,2"'GflAPH~RPQ~§ fl(:)v: 17 Pa~~ 2Qf '~~
1.'i
- lncdrpotate,.cycis 23 ehanges from.E.c 52275 mark~p.
2~0
- $0MMAR\\t;()F GHANGES;.
- 2:1
'Formatdhanges:.(no* rev bar$}. JEdlforial4.6;7J 2.2 Made NOTE'.box prior toTs* 2~.f.t., and revised.:second $entenc~ t~: l1$(:l:'1may11*
li~e IRS~ Heyis.e.cFNOJE Je> Qyc,I~ g3.
12,3 AdCl.C3~:tnew.CAUTION :ppx lo.T$ 3A*1 *Cl.l)Q rePr<:le.req ~µQ$teP$*.
No:,2.;G'RAPH~RPC.:6 Rev: 17
- Page 3 of f2 TXBLE '.OF **c.<lNTENTS.
'SECTION ts~2. t.. 1: *Reacto*r core *sLs:,............................................. ff......................................................,4 t:S:3.tA: Shutdown Margin:(SDM}......................................................,,................................. 4 TS:*3.1* ~3 Moct.eratot Temperature :cQeffiplen.t {MTQ),. *'!*~,..* ;;.*;..-, *'!:**' *!.*,,.,,.,,,,, ~*~ ~... ~fo*** **fr**:;* *** -4 T$~3.t;6 ShLitcl9wn l3c;l1Jlflo~ertior:i*~imits **.., *** ~.+i****************~****.**:*~*'d'**i.*"'**~~:**************~*~* 4 TS:$.~1~6. GQtitro.1 B~h.K'lfJ$~.ftiqnJ.Jr!iits.~~;;..... !'.~*1.*. *.. :*********.**.o:-* *..*. ~,.:********~.**.,*********......................... ~
T$'s.2.. 1 Heat 'Ft ax Hot ChanneLi=actor*:.(Fo(Z))................................................,............. ::5 TS*~.2.. 2 NQcl~8;r Eilth~lpy R!$~ H.ot Cfi~l'.ln~I, f~9tor (F~l'.l)...,~*~..................................... '5 T§;~.2-? Axial Ffox*Diffetelice'(AFD). (Constant Axial Oflset.Controi (GAOC)
.rvtetho.dology) :.................................................,...................................,.........................,............... ~5 TS>a:s.. J Reactor Prot~ctio.n $)'$tern (flPS) :1nstrµm~nt~dioo..,.;~***,,; ;; ;;;**.*:* ;...,.* ;.;:* !..* *~r--*****........ 9 TS::a,4.J R'CS Pr~.s~ure*, Temperatµr~.- :~!'lc:I :Fl9w Oept:!t1Y~la ftqrn 'NuQl~fil~
.~QJl.ilJ*Q. (I?N;~).<~i rrj j~~ *~~ ~,~ **.=~-~'.~*~-~,.~:~;~.~.!.* ~:**:~'*:*~~;~f~.-.~.. ~;-~ ~-! ~-~:~.~:~:.~;!.-~:,~ _,_:-: *.,_1l~: ~:!-*},* ~:~.~;*.,............ *-**....... -.: **** -. :*'*............. :.6 1:$,~.9. f Refueling Boron Concentration........................................................................ ~6
~,,.;..
- Attachments:
Attaehment1 Atta'Cnment2 Figures:
Figure. 1
- f~9ure 2 F'g~ue. 3
.Overtemperature *AT\\A.llowable,Value.*.......*.........**....................... 'Y
- overpower l\\T)\\llowable value......................................
H.................. J3 BsaoforCore:Safety:L.imit-F°"Our Lo9ps in-Operation..................... :9 AodBank lnser:tion Lfrnits\\,...,;;.:;.. ;.~******:~.~.. -;:~-..~.*~*A.***,**:._ **,.~..... ; *., *.** F;., *** Ao.
Roi'Ohannel Factor Normalize.d :Pperatin,9; EtwelQP~***~F***~:**********... :11
NOTE J\\tgt 2"*G RAPH-:RPC-~ fl~v; '1. 7
.. Pa,g~r4of1~-.
The; dafa?,presented in this. r~pott applies:to Cycle 23 ONLY and may 'NOT be used
.* :for*Qth~r:q~pl~~ Qf*oper.iEdlQO* '.)\\11~rte¢hnioefch,£lnge0 tp ttli~:* qpc.ui:nentmav J~qqire; a
- Sater Evaluation to*be ertormed in accorciance:witli 10 CFR so~ss - ** ***
- y Jl....... " *.*
TS 2.1..1 Reactor:core Sls i-.. :.,
(n MODES* 1 and 2~ the combination of thermal power level, pressurizer pressure, and highesUoop:average coolant temperature SHALL not exceed the: limits: shown 'in i=igure. 1.
Itie s,£tf~fy lh:nit ~is ~~Qee.ded if Jh~: ppiot d~fine,c:I by the combination: of Beactt>r*Coo.la11t
$yi:;t~rn. ~¥Ejra9$ t~Jtipe*r~tQrl9, ~na pow~r* iev<;i! i$ at :e,iriY tifiie* ~~~v$ the c.J.ppropria~~
. pressure line~
- The shutdown margin SHALL be.gJeaterthan or equal to**1.3% Aklk~
TS 3.t.3. ModeratorTenn.Jerature Coefficient CMTC)
- The MJ'.C,upper limiLSHALL be ~
- :cto.1ktk/°F'*~t hot zero power.
The MTC lower limit SHALL be less,ne ath/e,than.or e ual to::
g
...,q,.,....
- 05.s
- omi~F'@r 300 ** *m
- .. p,,, '**'
pp 4*a*o *.;.;;.'°F@*
e*o* ***.**"*
~.. ~ * *pc1111 ' *
- pp** m 45.S pcni/°F@
.o ppm.
ts 3d.s: *Shutdown Bank lns-ed:ion limits The SbiittJbwti B.~nl<$ SMALL-.b.e f!Jl~y. witbdtawn. Wh~r1 toe teactqr is i11 MQOJ: 1 ~nd MOOE 2..
- sh.~tdo.wn B:anks with a gro~p :step coun\\rar demand. position ~, ~23. steps :ar.e POflsi.d~rE!¢t fUl!y. Wit.fJCJrawn ile¢Eiu$$ the, t>ank d~mcJ.ncl P.Q$iti6n. is: CJ.bq\\fe th~' tpp of* Jh~
>(lOt.iV,~ fq~I~
No: 2-0RAPH-RPC-6 Rev::17 CORE OPERATING LIMITS REPORT (COLR)
Page 5of12 TS 3~1.6 Ccntroi Bank Insertion Lhnits Tbe Control Ba.nk Insertion Limits for MODE 1 and MOOE 2 with katt ~ t~o are,as indicated Jn Fig.ura 2. Control.Bani< Insertion.Limit$ apply to the step counter demand position.
EC!¢h Cpntrol B~(lk f:>hall be con$id¢r~ fully withdrawn at ~ 223 steps.
TS 3.2.1 Heat Flux Hof Channel Factor (Fg{Zl}
NOTE P is the fraction of Rated Thermal Power (ATP) at whictl tne cqre is operating.
K(Z) is the fraction given in Figure 3 AND Z is the cdre height location of Fa.
IF P >.5, Fa(Z), s (2.30/P) x K(Z)
IF. P s.5; Fa(Z) ::;;. (4.60) x K(Z)
TS.3.2~2 Nuclear Enthaley Rise Hot.Channel Factor l~l NOTE Pis the *fraction of Rated Thermal* Power (RTR) at Which 'the core is operating.
TS:3.2.3 Axial.Flux Difference (AFDl (Constant Axial Offset Control (CAOC)
MethOdolOQy)
TH$ indiqe1ted lirnlt istneTarg~t Ban9{ i.e.,. the Target+/-S%
The AFD SHALL be maintained Within ths ACCEPTABLE OPERATION portion of l=igure 4. as required by TS 3;2.3.
C'ORE OPERATING LIMITS REPORT (COLR)
No:**2.,GRAPH.,f{PC-e Page6of1*2 TS 3.3.1 Reactor P'rotectiorl'System (RPS) lnstrume*ntation
- 1. Ov,ertemperature AT Allow~ble Vafue as referencedin Technical Specific.atie>n$
Table 3 *.3.1"'1, Functions, Note 1.
Ref et.to Attachment t.
- 2. Overpower AT Allowable Value as referenced in Technical Specifications Table 3.s.1.. t, Function 6:, Note 2.
Refer to.Attachment 2; TS 3.4.1 RCS Pressl1re. Temperature. and Flow Departure from Nucleate Boiling CDNB) Limits.
The fblle>Wihg DNB related parameters are applicable in MOOE ~:
CAUTION Rev:17 The following RCS TAvG limits should be decreased one degree for:each degree
,th~tthe fufl power TAvG is less than 565°F. For example, if the full poW,er T1wG. is equal to 562°F, then th~ RCS average TAvG limit is s 565.'1°F am;I the highest lopp TAve limit is.ssae,1°F.
- a.
Pres~urizer PrE3SSUre ~.~21 a p~ia
- b.
Reactor Coolant System average TAvG ~** 56,8,.1'°F and highest loop T AVG s; 571~1°F for full powerTAvG 'Of 565.0°F
- c.
Reacforcoolant Sy$tem Total Flow Rate ~ 34$,300 gpm TS 3.9.1 Refueling Boron Concentration When required by Technical Specification 3.9.1, tbe minimum boron 'concentration in the RGS, Refuc:lling Canal. and Retictor Cavity SHAl.L Qe: the more, resfrictivf3 pf f>ither
- ~ 2050 ppm orthat Which is sufficientto provide a shutdown margin ~5.% Ak/k,
- CORE OPERATING LIMITS REPORT (COLR)
(Page i of 1)
OvertemperatunH\\ T Allowable Value No: 2-GRAPH~RPC;;6 Rev: *f7 Page7of12 The OverternperatDre.AT FU,n¢tioti Altowaqle Yal.ue Sl-IAL,L NOT exc~ed th.a Jecil11!c~l,
.$pecification tabie 3.3:1.,.1
- Note 1 value.
TheJollowing provid.es. the computed value:
- ,..r
.... ** * { * * * (l+ ns) [r r*]
- (P P') f < "*1*>}.
u
- Sufo K.1~ K1(r+ 1'as)
- +K3
~ 1 u Where:
AT is measured RCS at, °F (measured by hot lsg an'd cold leg RTDs).
ATp is the loop ~pacific indicated AT at ATP, °F.
s,is* t~e Laplaqe transform operator, secf1*
Ti$ the rne~suredRCS averag~ terope~ature, 6F~
T' is the loop specific indicated T avg at ATP,*~ 572 °F.
P is the measured pressurizer pressure. psfg.
Pl:is toe nominal.RCS operating* pressure, ~ 2235 psig.
K1~*t~22
- t\\~*25 sec K2 ~ Q.020/°F t2 *~ 3. sec l<s ~ Q.00070/ psig ft(:dl) =,.. t.97 {30 + (qt - qb)}
Qo/oofRTP 2.:25 ((qt "qb) ~ 7}
when q1 - qt, ~ ~30% ATP when -30%_ RTP < ~ - qb s 7% RTP.
when qt - qt>.> 7% ATP Where. Qt and qbare percent FlTP in the upper and. lower halves of tpe co~e, respectively, and q1 + qb is the fatal THERMAL POWER-in percent ATP.
- Attachmenr:2
.. :~
- . **.*.-=*
(Pag~ 1:;of1')
Overpower ~T:,Anowable,\\falue TheJollOwing provtdes*the computed vallJe:
4T *s;*11'Eo*.{K4***-Ks'( _T3's } t* ~K6:.(T'*._T"). **:f. ;,(A Il}. *
... /*+ _t3S *.
- Where*i*.ar Is measureo RCS AT, QF.
ATo is' the loqp specific indicated AT at Rf P, <?F~.
s, Js.-the *haplac~ t_i:a[1$fQIJTl operat9r,.s~c~
1 *
. T i~tbe: meCi$UfecfRGP.ci.v~r~Qe~:ternperatµre1 :ofi.*
t" if? th~ lp()p ~pe¢ifici: lfl<JJ~~t~c,ITav11, i;it RIP, s*$7g. ~F..
k.~ o::oo:tst°Fwnenl':>'T"
- JI..
- 01~:i= ~ht:in 'T:~::r"
\\
No: 2*:C3 RAPH-RPG-6 Rext:: rt
'\\
Fi9~re. *1 Aeac.tor Core.Safety.Limit.... F.o:ur Loop$ irr Operation (Pag~l of 1) 680.-.-----------------------.
620 60.0 560' 2440psla ACCEPTABLE C()NSEQU~NCES uNAcce.r>T.t\\BL.e CQNSEQ~ENCES 540~._._..................,l-'-_....__,_f-'"'---...'-:....I ----------+----~-+-~l__...1~1-+-"--"-""'-.I o
,;2
- 4
.s
.;a l
h2 tA
z 0
t::
ii>
0
£1.
~
z <
m Q
0 a:
~
BANKBI *
(().209;1)
'Figure2:
Rod a*anfdhsertion L:imits*.
(P'c)l.ff l-;opp Qper~tipn)
- 1 oo~step <bveflap **.*
- (Page. 1 df t
- )'.
' 'IJ No: 2'-GRAPf*HRPo~e; :R~v: *11
.P,i;lge,;to.At l2,'
BANl(01 25 """"'-t-t-t--t--4~+-+-+-.~,~'~"-+-+-t-t-t-++-+-+-+-t-t-t-+-Mt-+....... 1-1-+-to""l-t-+-t-ll
I p
'0 to*
20*
30 40 so so 10 ao:
too
- p()Weftevel (Percent of Aated Power)
Q
- .=19utea NC.; 2~~RAPtt"'flPO-()* R&v: t7 Pag~t't1, *pf 1,2:.
Hot Cbann*I Factor. Normaliz~d Operating Envelope (f;'()r s~ G. Tube Plugging.. UP to 5%)
(p~ge t qf :O * * *
- pQ:2~3Q FQ Js.00 Elev(ftl 11----+--J----+-f 2.. a*o 1.0 o.o.
- :2~30 *t.o s~o 111--.,....,.+,,...,.....,..-1-,----t-i
- 2~30 t~'O 12~0:
- 12
CORE 'OPERATING LIMITS REPORT (COLR)
No: ~;.GRAPH-RPC:,;6
- Page 12 of. 12 Fi9ure '4 A#t:1.1 FhJx Differe11ce EnyeloPe Limits (Page 1 of 1) 1Q()-r-=--------r---r-T--n""""""'--------...,
Power L~vel Tech Sp~~ Envelope as***
'5,p***
lJNACCEPTASLE OPERATION I
I I
I t
i I
I I
j
- ' J.
I i I
I ACCEPtA.BLE OPERATION.
l I
i 90..
.. :-11.0 11.0 80
~16;0 16.Q 10
-~to 21.0 eo
~26;0 26:0 56
- 31.0' 31.0 UNACCEPTABLE OPERATION.
I..,.._..._ ______...,
I *v~~Targ¢1 r
I J
I
'1 I
I i
I j
- l.
I I
50 -i: ___,,~_...,____,,,,.,.,,._....,._.,~~~~~--',,.-,....,_---,-_,....,-.._,.,..-_,.,.i.-..,.....--1
,~o
~2.0
-to 10
'40 Axial FiuxDifference Bev; l7
...