ML19347F042
| ML19347F042 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 04/30/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19347F043 | List: |
| References | |
| NUDOCS 8105150130 | |
| Download: ML19347F042 (32) | |
Text
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,f UNITED STATES
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NUCLEAR REGULATORY COMMISSION 5, x'g / p,
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c WASHINGTON, D C 20555
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C0tiMONWEALTH EDISON COMPANY DOCKET N0. 50-237 DRESDEN STATION UNIT NO. 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 59 License No. DPR-19 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The ' application for amendment by the Commonwealth Edison Company (the licensee) dated November 1, 1979, complies 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 application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 3.B of Provisional Operating License No. DPR-19 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 59, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
810815 ORA
... 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION s
o to, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
' Changes to the Technical Specifications Date of Issuance: April 30,1981
.-e
ATTACHMENT TO LICENSE AMENDMENT NO. 59__
PROVISIONAL OPERATING LICEllSE N0. OPR-19 DOCKET N0. 50-237 Revise the Appendix "A" Technical Specifications as follows:
Remove Replace 6
6 7
7 188 18a 42 42
DIH-19 1.1 SAFETY LIMIT 2.1 LIMITING SAFEIT SY5 TEX SETTING 1
APRM Flux Scrar. Trip Setting (Rt:n Mode) k* hen the reactor mode switch is in the run position, the APRM flux scram setting
, shall bei s6 58wn + 62_
vith a maximum set point of 120% for core flow equal to 98 x 10 lb/hr and greater,
',tho re S - setting in per cent of rated power V
per cent of drive flow required to produce o
a rated core flow of 98 Mlb/hr.
In the event of operation with a manimun f raction of lielting power density (rflP3) greater than the f raction of rated power (FRP). the 5
setting shall te a:odified as follows:
M s 6 (.58WD + 62)
Were:
FRP = f raction of rated there41 power (2 527 ItW t)
~
NLP0 = ranimum f raction of limittog power density where the limittr.;
power. density for each t>undle is the design linear beat sa'd*"
ger.eration rate for that bundle.
es The ratto of TRP/PJLTD shall be set equal to 1.0 unless the actual operating value is less than 1.0, in which case the aclu.31 cg eratihg value wiII te used.
This adjustment may also be performed by increasing the APM ga an by the inverse ratto, prLpD/fMP, wh1Ch aCComplishe s the degree of protection as reducing the trip setting by 2.
APRM Flux Scram Trip Settins- (Refuel or Sta rtup and Hot Standby Mode)
When the reactor mode switch is in the refuel or startup/ hot standby position, Amendment.o.
59 the APax scram shall de set at less than d
or equal to 15% or rated neutron riux.
6
(
^
DPR-19 1.1. SAFETY LE1IT 2.1 LIMITUiG SA~.i.TY SYSTEM SE.TTIhD
- 3. Core Thermal' Pouer Limit (Reactor 3*
D h hm M" MW i
'?ressure (800 psig)
The IRM flux scram setting shall bc set at less than or equal to 120/125 of Wen the reactor pressuce is < 600 Psig or core flow is less than 10%
full scale.
of ratede the core thernal power shall not exceed 25 percent of rated therraal power.
3 APRM Rod Block Setting C. Pouer Tranc.f ent The APRM rod block setting shall be:
1.
The neutron flux shall not exceed the scrats' f
setting established in Specification 2.1. A for longer than 1.5 seconds as indicated by S$
58WD + SO-T the process computer.
. ne, definitions itsed above for the APFJ1 scraat trip-spply,
- 2. 'When the process cosiputer is out of service s g
this safety limit shall be asstned to be In the egent or operetten vita esetsun tracttee Itetstes power cenesty (nrs) exceeded if the neutron flux exceeds the scram greater shari tee traction or rated rover (in), the eetstas chau be meurtes
- U*
setting established by Specification 2.1. A N
O and a control rod scram does not occur.
S 6 (.58W3+W N
_N.
We deflotstone used aboee for the ffM( ecram trty apply.
N
"' ***** b' ' ' 9"
- 1 t o ' ' "a l' ' ' t h'
- * * " ' ' 'en "u *s e* d P
8**
Re&ClOr Water Level (Shutdown Conditien)-
Th'g w' * 'g e'*le s s th e n"f **
".0.
1 An which case the actual operating valve =ttl This ad)veteent may also t,e performed by laceeastnq the APM qa nn by the nnwette s et to, NFLPD/ Tar. which accomptishes the espo degree of psotect nen as sedecang p
Wenever the reactor is in the shutdcun condition the tesp setting by rar/nrcro, y
with irradiated fuel in the reactor vessel, the vater level shall not be less then that corres-PonJ!ng to 12 inches above the top of the active fuel *vhen it is seated in the core.
Amendment No. 59 7
- Top of ar.tive fuel is defined to be 360 inches above vessel zero (see 13a s es 3 2 ).
s DIO"19 IfC RODBLOCK
... C KUP S.CR AM-. ~. -. ~. -. -. -. -. -.
.Lgtgg APRM B A gNyggcgpy
-.-..~.~.4 1y3 f
/
/
APRM ROD BLOCK
,e LINE (o,$3.gg $o f
s' ROD BLOCK thTERCEPT j
POINT 185/61) 100 s'
/
/
/
APRM SCRAM LINE (0 5 'g 62) 8 p
8 to b
3 5
p f
- NATURAL.
1 NOMI N AL, CCNSTANT X C tJON CIRCU LA T IO N
[
LIN[
100/100 POwtR/F LOW Lir4E 60 4
8
-[
v 40 OPCR AT INO R(CICN SUFFtaic 0 2b: 67 BY N.C.C O.
20% Puur SPE E0 LfNE Operating en Single Loep or Natura, Circulaticn is Limited per Tech Specs.
3.6H.3 and 3.6A.h 3_
R AT CD COrc e T IONS f *d1 M.
25 hem /==
POWCR 9a t CORE FLOW O
~
40 60 80 100 170 0
- 0 Vy, CORC FLOV R ATC ($ Of R Al[D)
($C HCt*AT I C)3 faCUR[
2,l.
APam Ftw ei As sCRAv Rrt at.cussie Amendment No* 59 10 NCRM AL OPE E al t N'. CCw3: 1 t ot:5 P00R ORIGINA 1e.,
OPR 19 INSTRt.HENTATION T!!AT INITIATES ROD BLOCX Table 3.2.3 t'inimun No. of Co:rnble Inst.-
C*nanacis Per T:-in systen(1) _
Instrument
_. Trio TAvel,5cttinh
~
1 A?.?.!i upsenic (flow bias) (7)
I rnP 0.58WD + 50,gppro (2) 1 AP.'01 upscale (refuel end Startup/ Hot
$12/125 full ccale
=
Standby code) 2 APRM downscale (7) 2 3/125 full scal'c g
g 1
Rod black monitor upreale (flow blas) (7) 0.65 w + 42 (2) p D
1 Rod block raonitor downscale (7) 2 5/125 1011 ' scale g
3 2H.'1 acrmsecle (3) 2,5/125 Cull scaiu 3
IRM upsc' ale-f.100/125 full. scale w
j a
3 IRM detector not fully inserted in g
the core M
~
b 2(5)
Siuj detector not in otartup posit: ion (4')
2 (5) (G)
- SPR upscale 6.105 ccunts/see 42' Amendment No. 59
p *KE?u y,.
,o, UNITED STATES NUCLEAR REGULATORY COMMISSION y'
r WASHINGTON, D. C. 20555 3
g
%.... /
+
COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-249 DRESDEN STATI0' '!IT NO. 3 AMENDMENT TO FACILITY vr'ERATING LICENSE Amendment No. 52 License No. DPR-25 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by the Comonwealth Edison Company (the licensee) dated November 2,1979, complies 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (il 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all appliceble requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indi:ated in the attachment to this license amendment, and paragraph 3.8 of Facility License No. DPR-25 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 52, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
I 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
<D a
Thoma
. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 30,1981 t
e
~
ATTACHMENT TO LICENSE AMENDMENT NO. 52 FACILITY OPERATING LICENSE NO. DPR-25 DOCKET NO. 50-249 Revise the Appendix "A" Technical Specifications as follows:
Remove Replace 6
6 1
7 7
188 18B 42 42
.P L
f i
E A
.i -
A
.. _ _.DPR-25
- ~.
s r-2.1 I,IMITING SAFEIT SETEM SIT. TSG ~
)
1,1 SArgry LIMI7
~)
1 APRM Flux Scram Trip Setting (Run Mode)
When the reactor mode switch is in the st.
un position, the APRH flux scram setting
. shall bei
,4 s6 58Wp + 62_
vith a maximum set point of 120% for core 6
flow equal to 98 x 10 lb/hr and greater, where S - setting in per cent of rated power V - per cent of drive flow required to produce D
a rated core flow of 98 Mlb/hr.
In the event of operation with a manimum fraction of Ilmitleg power density (NFLPD) greater than the f raction of rated power (TRP), the setting shall be sodified as follows:
S $ (. 5'3Wp + 62) g IRP = fraction of rated thermal power (2527 HWt)
HitPD = easieurs fraction of limiting power density where the lletting power. density for each bundle is the design linear beat O
gerieration rate for that bundle.
1he ratto of TRP/MTLPD shall be set equal to 1.0 unless the actual a--=="
operating value is less than 1.0, in which case the actual operating value will be used.
2.
APRM Flux Scram Trip Setting (Reruel or Sta rtup and Hot Standby Mode)
When the reactor mode switch is in the reruel or startup/ hot standby position, knendment No. 52 the APRM scram shall be set at less than or equal to 15% or rated neutron flux.
6
0
~
f
~
~
~
1.1 'SAFTrY Ln!IT 2.1 LIMITDC SA".TrY SYSTEM SETTDC
- 3. Cor'e Thermal' Power Limit (Reactor h
3.
IRM F1tm Scr: m Tric Settine ;i
' Pressure g_800 psig)
The IRM flux scram setting shall be set at less than or equal to 120/125 of Wen the reactor pressure is < 800 psig or core flow is less than 10 full scale.
of rated, the core therm.t1 power shall not exceed 25 percent of rated thermal power.
3.
APRM Red Block Setting C. Pouer Transient _
The APRK rod block setting shall be*
1.
The neutron flux shall not exceed the scram"
~
i setting established in Specification 2.1. A j
f or longer than 1.5 seconds as indicated by S4 58vD + 50_
the process computer.
. The definitions used above for the APF,H scram
,g
- 2. Den the process coniputer is out of service, trip-spply, this safety limit shall be assumed to be In the event or creratten with. coatsu tr csson Itetstas power ceasttr (K'Lrs sreater than the av.cston or rated rever (try). the setstos.n.1.1 n.
4.tra.e D
exceeded if the neutron flux exceeds the soram se r uovn D
setting established by Specification 2.1. A
_FRP _
S 6 (.58WD + 50) and a control rod scram does not occur.
-M
}
O
'[h. dettatttoos used 6%ove for the ArP.M ocraa trip applr.
,,,,,,,,,,,,,, t o,1. 0 va le,,s s t h,,,a c t u,,s t '
act equal Reactor Water Level [ Shutdown gonfitic t{
The,,,e at,,lo of rar to Mrt,rn,,sha t t,be g,,,,,,,
g,,,
QJ D.
g Wenever the reactor is in the shutdcun condition with tiradiated fuel in the reactor vessel, the g
vater level shall not be less then that corres-Ponding to 12 inches above the top of the active fuel *vhen it is seated in the core.
Amendment No. 52 7
- Top of active fuel is defined to be 360 inches above vessel zero (see Bases 3~.2).
1
DPR-25 1:0 ROO BLOCK
.,...CKUP S. CRAM-. --. -. -. -. -. -. -. -. E P T U N E APRM BA INTERC
.- ~..-
-.-.----.-.y..
33
/
e'
/
APRM ROD BLOCK
- t. NE (O.$8v e 50
/
D s'
POINT 825/61)
,f-(
ROD BLOCK INTE RCEPT T
100
/
/
/
/
tint (0 58vg 62)
O
/
0 E
eo b
3 5
l b
- Nr.TURAL r
fcMINAL, CCNST ANT xErcN CI A CULA T s O N
[
LINE 100/100 POWE Rt F LOW LINE 60 A
u 40 OPCRATING REGION SUPPORT!O
- 24867 1
BY N.E.O O.
- Operating on Single LOOP or Natural Circulatien is Limited per Tech. Specs.
3.6H.3 and 3.6A.14 R AT ED COrcI T IONS POWER 2} 27 f *d1M.
CORE FLOW 90 Mts / a I
l I
l 0
- 0 40 60 80 100 1
- 0 Wg, CORC TLOV R ATE ($ Or RA1CO) r: CURE 2.t.3 (5CMCf TAT IC)
'""" N Bs sCR m RetAticusNiP Amendment flo. 52 gggg gg 18,3 10 NonMat, OPER 18 e
9
~
DPR-25 INSTRI.41SNTATION TifAT INITIATES ROD BLOCK Table 3.2.3
~ l'ini.T.u= 1*o. o f Co:rnb12 Ins t.-
Channels Per 7:-in Systen(l)__
Instrur::ent Trio TAvel, Scttinh F
1 A?P.M upscale (flow bins)(7) 4 PitP
,0.58WD + 50 Hmo (2) 1 AP.'ot upscale (refuel and Startup/ Hot
$12/125 full ccale-Standby code) 2' APrJt downscale (7) 23/125 full scal'c 1
Red block anonitoc uptcale (flow bins) (7) I 0.65 W D + 42 (2) 1 Rod block monitor downscale (7) 2 S/125 fell scale ON 3
IPJi dcunscele (3) 15/125 full scals O
3 IM upscalo 1100/125 full.scalg N
e 3
IRF1 detector not fully inserted in the core Zp 2(5)
SRH, detector not in startup posit 1"on (4)
Y SRM upscale d.105 ccunts/see 2 (5) (G)
Amendmen't No. 52 4i
[(
o UNITED STATES g
g NUCLEAR REGULATORY COMMISSION g.
E WASHINGTON, D. C. 20555
/
COPHONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 QUAD CITIES UNIT N0. 1 AMENDMENT T0' FACILITY OPERATING LICENSE Amendment No. 70 License No. DPR-29 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Comonwealth Edison Company
(~the licensee) dated November 1,1979, complies 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 application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment ano paragraph 3.B of Facility License No. DPR-29 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 70, are hereby incorporated in the license. The licensee shall operate the facility in accor-dance with the Technical Specifications,
d 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COPEISSION
-. s -
Th to Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 30,1981 I
9 1
l
.I i
ATTACHMENT TO LICENSE AMENOMENT NO. 70 FACILITY OPERATING LICENSE NO. OPR-29 MCKETNO.50-254 i
Revise the Appendix "A" Technical Specifications as follows:
Remove Replace 1.1/2.1-1 1.1/2.1-1 1.1/2.1-2 1.1/2.1-2 1.1/2.1-2a 1.1/2.1-2a Figure 2.1-1 Figure 2.1-1 Figure 2.1-3 Figure 2.1-3 3.2/4.2-14 3.2/4.2-14 4
b i
i e
g wr---
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,,r-.,
,-w--
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-gn-e,
,,r---,
I
. n.n.v... v..
r* _:_
~~;V%V, *,:..R[
- Tn @h L..- -
- Q:M12 n 'n2
- Jr - N:=
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1.1/2.1 FUEL CLADDING INTEGitlW 1
SAFITY UMIT BJMITINC sal'I;TY hYN10.M SimlNG
.t Applicabilisy Appliesbility:
The safety limies established in preserve the feel he limising ufrey sysicm sciiings opgily to trip i g; et.dd.cg integrity apply in ihase vars.t.lci whech settings of she in.aronienn and derkes niikh are sionitor s e feel thermal bchasor provided so paesens the feel cladding integrity esfety limits froin being curri!cJ.
r.
06]eesive:
OHeeslet:
The objective of the safety limits is to estahhsh The objective of t'.e limiting safety system settints limits below a hich the sniegrity of the fuct cladding is to de Anc the levet of the process variables at u hich la p eserved.
autorr.ah protecent.etion n insuated to preent te fuel etadJing iniettoy ufety hmit from bcing eaceeded.
SPf.CtrlCATIONS A.
liestief l*rseuse > 800 pig and Core Flow A. Neutron 11.s Tsic Sentiar.s P 10% of Rased The Emitier safsty systert trip settings shaft he
%e existerce of a mimlauti u specia,a hc w critical poWr ratio (f tTR)
- 1. Aritti lles seram Trip settin; t Run less than 1.07 shall constitute m den i
ViolatiOrt Of the fuel Clad-Whea the reactne mc/c switch is in the ding intCgrity SafCty limit.
g,, pc,aion, et,e A1.!tM r.un scram act ing. sLtt le e shimp in Iituse j
2.1 1 and shall tir.
1 B.
Core hersial rewee usalt (steereer he%.re s soo psi:)
Ss f.58Wp + 62) l M 8
"'I"*"'
When alw reactor pressure is s 800 psig er M"*I '* " * #
eore now h less than 10"o of rated. the core I"##*
thermal pover shall not escred 2.5". cf rated 6ermal power.
wheve.
l 3
. se: ting in pereeni o[ rated C NetTransient P"
- l. The neutron f.ut sh.iff not escred the
,,7 g,;g,, g,,,,,
actam setting estabhshed in Spetincs.
pseed to pes luci, a ested enes ti tien 2.lA for longer than 1.3 scecads g3.,e et 90 statione a bA.e.
In es indicated.by the Ptnctst computer.
Ows event of eperativu teatti a unnsteem treetlon er !!aiting
- 3. When the penress computer is out of pensee eeneLty tasrt.rn) greette tervice. this sifsty hmit shall Lt at.
than the fesetles er eatte sumed in be s sc citeil if the nevison posee (rpr). the settirn ahatt Rut eacccJt its. usans wtiier e. sal he med&fted ee follonass lished by $g. tsse.tuon 2.l.4 and a
,gf control evJ wram does s.os oscar.
3S D
)
vs.rp,,
1.1/2.1-1 Amendment No. 70 P00R ORIGINAL 9
QUAD-CITIES l l DPR-29 1
I r i where l-D. Resetor Water Lesel(Shutdown Condillon) n rated whenever the reactor is in the shut-g down condition with irradiated fuel (2511 MWt) in the reactor vessel, the water level shall not be less than that part.PD = maximum fraction of i
corresponding to 12 inches above the limiting power dens-top of the active fuel
- when it is ity where the limit-1 seated in the core.
trug pcuer density for each bundle is
- Tor of active fuel is definod to be the design linear t
j 360 inches above vessel sero (See heat generation rate Bases 3.2).
for that bundle.
The ratio of FRP/MrI.PD shall be b
eet equal to 1.0 unless the actu-l l
al operating value is less than 1.0 in which case the actual
- l operating value will be used.
,l This adjustment may also be performed by increasing the APRM gain by the inverse ratio, MFLPD/FRP, which j
accomplishes the same degree of pro-tection as reducing the trip setting i
by FRP/MFLPD.
- 2. APISI Flux Scrat, Tr!p Setting (Re-fuellr:s or Startup and Het Standby Mode)
% hen the reactor mode rwlich is in the Refuel cr Simup Hot Standby posi-tion. the APMI :: tam shall be set at
[ A --
less than or equal to 157, of rated neutron flux.
1he IRM flux scram setting shallbe set at i
less than or equal to 1:0/125 of full i
4 sca!e.
j
- 4. When the reactor mode switch is in the startup or run position, the reactor shell not be operated in the na' ural circula.
tion flow mode.
R.
APRM Rod Block Setting The APRM rod block setting shall be as shown
'q'
' in Figure 2.1 1 and shall be:
Ss
(. 58Wo + 50) i 1.1/2.1-2 1
D M I R ' N '1 [
'{
Amendment No. 70 11 Ustlu sil l
Gb eO O I
QUAD-CITIES
~
nPR-29 The definitions used above for the AP t.M J
, scram trip apply. In the event of oper-I'
' ation witPr a maximu:s f raction limiting '.
. power density (ftTLPD) greater than the fra-tion of rated power (FRP). the setting 4
shall be modified as followse i
TPP Ss
(.5BWo + 50) artro l
The definitions used above for the APR.'t ecram trip apply.
The ratio of TRP to MTLPD shall be set equal to 1.0 unless the actual operating value is less than 1.0, in which case the actual operating value will be used.
This may also be performed by increasing the APRM gain by the inverse ratio, MFLPD/FRP, which accomplishes the same degree of pro-tection as reducing the trip setting by l l FRP/MFLPD.
C. menetor low water level scram setting shall be 144 inches above the top of the
{
active fuele at normal operating condi-tions.
-D. nesctor low water level Ices initiation shall bo 84 inches (+4 inches /-0 in:h) above the top of the active fuel
- at e
normal operating conditions.
l E. Turbine stop valve scram shall be s 10% valve 4
.f closure ftom full open.
F. Turbine control valve fssi closure scram shall Initiate upon actuation of the fast closure sole.
noid valves which trip the turbin: control valves.
1 O. Main steamline isolation valve closure scram shall be s 10% valve closure from full open.
l H. Main steamline low pressure initiation of main steamline isolation valve closure shall be 2 850 psig.
.2 of ac.tive fuel is defined to
- Top 60 inches above vpssel :ero be 3 (See Bases 3 2) a I
e i
1.1/2.1-2a lb sl n
Amendment flo. 70 l~
l
DPR-29 3..,,_.j,....,_.
- v.,...... /.y...; >..,,..,.
130 g
120 110 APRM FLOW REFERENCE SCRAM ico (ALLMODES) 90 E.,
2 s0 o
APRM ROD BLOCK 3
7o 5
C' 60 E
cc 5
50 s
40 30 20 Il 10 0
I I
I I
I O
20 40 60 80 100 120 RECIRCULATION LOOP FLOW (7, of design) i FIGURE 2.1-1 i
Amendment No. 70 APRM FLOW REFERENCE SCRAM AND APR!t R00 BLOCK SETTINGS i
Quad Citics
)
DPR-29 140
,~
MOD 8 LOCK
..,. C KU P S.CR AM-.
. -. -. -. L.I N E APRH D A INT [RC(PT gyg
/
s'
/
.arnu noo aLOCK
,e LINE (o,$8%.j $o f
s' AOD BLOCK thTERCEPT j
POf".T185/61) 100
/
/
/
/
LINC (0.$8WJ (,2) j
~
8 e.
83
~
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b 3
5 p
f
'reATURAL N
i NDPi t 8l A(, ( CN$1/.N1 X(NON Ci84CULAllON i
LINE tecinco PO.'.t n/r LOW LINI
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60
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d w
8v 40 N
OP(R ATING R(GION SUFFOR11 0 26167 1
UY N.C.D O.
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- m euwe setto LINE g Operating on Single Loop or Natural Circulation is Limited per Tech. Grecs.
3.6.H.3 and 2.1.A.h M-R A1(D COrce I TONS POW [R 2 1 f *.' t H.
C OR E F L OW M69=/aa 0
40 60 80 100 1.N 0
30 Wy, CORE FLOV R ATC ($ Of R AI(?)
fICURE 2.I-3
( $( H( f' Al l C )
Amendment flo. 70
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10 NORM AL OP( R Al l NO CONO l l l CN5 1
P00R BRIGINAl.
~
i QUAD-CITIES DPR-29 i
If 8LE 3.24 INSTIL'MENTATICH THAT INITIATES R03 BLC:I greemme tanter of Oper:We or Tripped lastnseest Channels per Trip SystenP lastrement Trip Lsvel Sett4 2
APRM upscak (Rew biasyn 4 0.58WD + 50 w ---
yyLpp 2
APRM escah (Refuel and Startup/Het
.s12/125 fua seat Standby enode) 2 APRM downscakm 23/125 fut scak so.65Wp + 42 (2) l
~
1 Rod bbck mor.:ter mscah (fc= biasyn 1
Rod bbet monitor downscakm 23/125 fue scat 3
1RM downscak m m 23/125 fuG scak
~
3 RM escak*
s10.?/125 fus scak 2*
SRM detector net et Startup pcsiton'81 22 feet bebe core center.
Int 3
RM detector nct h Startup pesitien*
22 feet beba core center.
ine 28
- 3RM wscak s 105 counts /sec 28 SRM downscak*
210' coets/sec
~
1 H(i water kvel in scram dist.arge vck.me 525 galons Notes
- 1. For the Startup/ Hat Standby ar;d Hun positions of the reactor mode scleeter switch, ther? shall be two opc able or tripped trip systems for cac: fune-tiers except the SRM rod blocks. IN! upscale and IRM downscrale need not be operable in the Ruri position, AP tM downecale, AFRM upscale (flow biised),
and RBM downecale nt cd not be opcrable in the Startup/ Hot Standuy medo.
Tac MN! upscale f.ced raot be operabic ut less than 30% rated thor =si tower.
Orie chsnnel may be bypnesed aboyc 307. rated thermal power'provided that a limitinc control rod pattern stoes not exist. For systc=s with more than one channel per trip systect, if the first column cannot be met for one of the two trip syrtems, this conditinn e.ay exist for up to 7 days provided that during that tinse the operabin systen is functionally tested ics mediately and daily thereafter; if this condition lasts longer than 7 days the syntes shall be tripped. If the first column cannot be met for both trip systems, the systems shall be tripped.
- 2. W is the percent of drive flow required to produce a rated core flow n' g9e million Ib/hr. Trip level setting is in percent of rated power (2511 Kdt).
1 stu esmeza' eey to bresues seende en es beest rage.
d A b bactas a byeennes enereseemsteeee e 2100 CPS.
1 Die of Um lar 9M seats rar es heessede '
L h 7M Nnctus may to typensee a me nigest stM ranges tranges L L and tt) s'un Se FM sewsis red back a sperabit y.
Ret resoned to toep ese.a.ie eereweeg tre acurer pe scs testiat atmos 4rc premere sereg er a*tse roweg at power lent act to saceed s ifwt r
L h zu twistas erws =$ss the'esseer mode sorten e a me Re%es or startus/ Hot 1:midipy pendus.
t h s, a w ause =am me as e e,a,..erteds..
endment fio. 70 3.2/42-14
p M ahiqD UNITED STATES
+8\\
NUCLEAR REGULATORY COMMISSION
,C WASHINGTON,0. C. 205SS 5,." '
%**.../
COMMONWEALTH EDIS0N COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated November 1,1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operat'e in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-30 is hereby amended to read as follows:
B.
Techrical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 64, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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This licen'..se amendment is effective' as of'..the date of its issuance.
3.
FOR THE NUCLEAR REGULATORY COMMISSION
/
Thomas /
Ippolito, Chief Operating Reactors Branch #?.
Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Is ;uance: April 30,1981 G
t i
A 1
4 i.-,
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. ATTACHMENT TO LICENSE AMENDMENT NO. 64 FACILITY OPERATING LICENSE NO. OPR-30
' DOC'KET N0'.' 5d-265"
~
Revise the Appendix "A" Technical Specifications as follows:
Remove Replace 1.1/2.1-1 1.1/2.1-1 1.1/2.1-2 1.1/2.1-2 1.1/2.1-3 1.1/2.1-3 Figure 2.1-1 Figure 2.1.1 Figure 2.1-3 Figure 2.1-3 3.2/4.2-14 3.2/4.2-14 I
m,.
QUAD. CITIES DPR-30 1.1/2.1 l'Ul:1. CLADDING INT 1:GillTY
'~
SAFETY I.lMIT IJMITINC SAfl3Y SYs10M SCT11NG Applicabilh):
Applienbi!ity:
The safety limits estatlished to preserve the fact The fitniting urcty system settings app!) to trip cladding integrity apply in those varisb!cs which settings of the emirements and devites whish are monitor tae fuel therrr.al behasior.
provided in picsens the fuel c!adJang integraty safety limits ftom besng catteded.
Objectiie Objecifie:
The objective of the safety limits as to estahtisti The objective of the hmiting sarciy sysicm settings limits b: low which the integrity of the fuel cladding is to denne the Icvcl of the prrx ess = ariaNes as u heela is preserved.
automatic protective action is initiated to preens the fuel c: adde; intertity safety hnute t' rom being exceeded.
SPECITICATIONS A Iteetter l'ressure > $00 psig and Core llo v A Neutron I'lut Trip Settins.s
> 10'L et Rated the esistence of a minimum critleal The limitint ufety syster, trip settings shall be power ratic (trPn) less t han 1.oG as specaneJ be!or.
for core Irviding patterns contain-ing no retrofit esa guel (two water
Pettern. containitwy retrofit 4u8 feel shall e.matitute violation of When the reacter mode switch is in.he t he fuel claddirv) integrity e.fety Run potioon. the AlitM flus serani limit.
setting slull le as shewn ist l'agus e 2.1 1 and shall Ic B.
Core Thermal Poner Limit (Restior 1*rcisure s s00 pil:)
Ss (0.58WD + 62) l When the reactor pressure is s 800 psig or with a nonii.iuns setroint i f 120 e for core now h less than 10*. of rated, the core con hw citual to 98 a 10* lb/hr and thermal power shall not czeced 2P* of rated 8"* '#
thermal power.
, here:
w C. Foner Tranticat S
8 tin 8 n Percent of rated i
Po**'
I. The neutron flut shall not exceed the f
sera t setting established in Specif.ca.
Wp = percent of delve now re.
,,,g9,,,g,.,,,,g,,,,,,,
tson 2.1.A for longer than 1.5 secends flow of 90 millioe. Ib/hr. In as indicated by the proects cornputer.
the event of eperatiou with a maximus fraction of limiting
- 2. When the process computer as out of power density (sat.rpt greatee service, this lifety limit shall be at.
than the fractio.i or rated tumed to be cacceited if the neutron power (rwe*). the settints eP.all ilus eseceds the strani witics estal be modified as followse fished by S.wirication 2.l.A and a t
vrP control roJ scram does r.oi occur.
Ss (0.58WD + 62) im o Amendment No. 64
,. 5 QUAD-CITIES g.
"h*I'*
D. Resessr Water Level (Shutdown Condition)
TRP = fraction of rated whenever the reactor is in the shut-thermal power down condition with irradiated fuel (2511 *t) in the reactor vessel, the water level shall not be less than that MTLPD = staximum fraction of corresponding to 12 inches above the limiting power dans-top of the active fuel
- when it is ity where the lisait-seated in the core.
ing power density for each bundle is
- Top of active fuel in defined to be the design linear 360 inches above vessel zero (See heat generation rate Bases 3.2).
for that bundle.
The ratio of TRP/.w.rl,PD shall be set equal to 1.0 unless the actu-al operating value is less than 1.0 in which case the actual operating value will be used.
% hen the reactor r.sode ruitch is in the Refuel or Startup Hot Standby pesi-tion, the APRM scram sha!! be set at less than or equal to 157. of rated neutron flux.
- 3. IRM Flux Scram Trip Setting The IRM flux scram wtting sha!! be wt at less thats or equt! to 120/125 of full scale.
- 4. % ten the reactor mode switch is in the startup or run position, the reactor shall not be operated in the natural circula-tion flow mode.
B.
APRM Rod Block Setting The APRM rod block setting shall be as shown in Figure 2.1 1 and shall be:
Ss (0.58Wp + 50) l.
Amendment No. 64
QUAD-CITIES L
gg g The definitions used above for the APRM scram trip apply. In the event of oper-ation with a maxi:num fraction limiting power density (MFLPD) greater than the fraction of rated power (TRP), the setting shall be sodified as follows:
TPP Ss (0.58Wp + 50) mpo The definitions used above for the APRM scram trip apply.
The ratio of TRP to MTLPD shall be set equal to 1.0 unless the actual operating value is less than 1.0, an %hach case the actual operating value will be used.
C. Reactor low water level scram setting shall be 144 inches above the top of the active fuel
- at nor:nal operating condi-tions.
D. Reactor low water level ECOS initiation shall be 84 inches (+4 inches /-0 inch) above thw top of the active fuel
- at normal operating eenditions.
E. Turbine stop valve scram shall be s 10% valve closure from full open.
F. Turbine control valve fast closure scram shall initiate upon actaation of the fast closure sole.
noid valves which trip the turbine control valves.
G. Main steamline isolation valve closure scram shall be s 10% valve closure from full open.
H. Main sicamline low. pressure initiaria ofmain steamline isolation valve closure sha!! be a: 850 psig.
- Top 60 inches above vof active fuel is defined be 3 essel zdro (See Bases 3 2) 1.1/2.1-3 Amendment No. 64
QUAD-CITIES OPR-$O
, p. -A '
.v 130 I
I I
i i
120
)
110 APRM FLOW REFERENCE SCRAM 100 (ALL MODES) 90
_a3 2
80 o
S 70 APRM ROD' BLOCK 5
d 60 5
E 50 8
=
40 30 20 p 10 O
I I
l I
I O
20 40 60 80 100 120 RECIRCULATION LOOP FLOW (*, Of design)
FIGURE 2.1-1 4
Amendment NO. 64 APRM FLOW REFERENCE SCRAM AND APRM R0D BLOCK SETTINGS I
Qu*d Citico
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- DPB-30 14c e
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- ^
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INTERCEPT LINE APRM BACKUP SCR AM
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120
=
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APRM ROD BLOCK
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8 LINE (o,$ w t $0
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s ROD BLOCK INTERCEPT j-POINT 185/611
,e 100
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APRH SCRAH tiNC (0 58wg 62) to
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I NCMI N AL, CONST.*JT x CNON
- NATUR/.L i
g Cla CU LA T IO N d
LINE 100/100 PCWER/F LOW LirJC 6
E 60 E
v 40 OPCR AT I NG RCGION SUPPORT,0 BY N.C.O O. - 24167 4
- Operating on Single LCCP or Natural Circulation is Limited per Tech. Specs.
3.6.H.3 and 2.1.A.h
- c RATfD CONDITIONS POWCR 2 1 f *di n.
CORC FLOW 9 MLea/-a I
I 1
1 40 60 80 100 1M 0
0 30 CORC TLOW R ATC (% Or R ATCD)
Wy, isGURC 2.1-3
( SC HCt' AT I C )
Amendment No. 64 APRs rto./ ei AS sCR tJ< RCL Af s ONSHI P TO NORMAL OPCRAllNG CON 3tTIONS S
M-
QUAD-CITIES DPR-30
.m TABLE 3.24 INSTR!!MENTATICN THliINITIATES ROD BLOOK trame ammkr of operawe er Tripped lastntment Channels per Trip systanP instrument Trip Level settng 2
APRM Wscat (f!cw bes?"
4 0.58WD + 50]MFLPD FRP e--
2 APRM upsca'e (Refuel and Startup/Het s12/125 fuD scaie Standby mode) 2 APRM downstale:"
23/125 fut sca'e 50,65Wp + 42(2)
}
I Rod bM rnon:ts upscak (f<w biasyn q
1 Tod block rnoruter downscre" 23/125 full seak t
3 1RM downsca'e m*
23/125 fua scat 3
IRM upscat )
s103/125 full scale 8
i 2*
SRM detects not n Stau pcs: ton
- 22 feet betw cze center.
line 3
IRM detector not h Startuo pestcr 22 feet belcw care center.
Irie 28
- lt102 counts /sec 1
H@ water level h scram dist.srie vclume s25 gehs Notes
- 1. For the Startup/ Hot Standby and Hun positions of the reactor mode eclecter switch, there shall be two opc able or
- ripped trip systems for cac: fune-tion except the SRM rod bInchu. IIU4 upscale and IRM dcwnscole need riot be operable in the Run rc11 tion, AMtM down=cale, APRM upscale (flow biised),
and R3M downecalc nt cd not be operable in the Startup/ Hot Standoy maio.
Tuo MPM up:cale twed riot be operable at loss than 30% rated thermal tower.
One chantiel may be byp=a: sed above 307. rated ther=al power provided that a liniting control rod l atterft does not exist. For systemo wi th r. ore than one channel per trip system, if the first column cannot be met for one of the two trip syster.s, this conditinn may exist for up to 7 days provided that daring that ti.tc the operabin systes is functionally tcs ted in-mediately and daily thereafter; if this condition lasts longer thari 7 days the systemi chall be tripped. If the first column cannot be met for both trip cystems, the systems shall be tripped.
- 2. V is the percent of drive flow required to produce a rated core ficw of 39e million Ib/hr. Trip level setting is in percent of rated power (2511 E4t).
1 Ru es= scale mer k bysm.ed =%a e o es sts beest tret 4.
N hectma e bronses =hes the comet r ate a 2100 CPS.
1 Die of the law 2M epvn may be twas 4.
- g i h 25 Wtas mer be typased a the heer IRii raeres haates L i ed 10).'un the *W epicale rot bext s sostates L Ret regesed to tus coerat's eMe pe *arerg c= power ##rics this e atmcsper ;iressse seres or aner re've es at pe=er ieves not ta encsed 5 Mwt L h zu Wues ears =%n tN 'eactor moce seten o a the h%ei e starta/% itscy poemet i k 39 s bypaust own me SW s boy morted.
/
Amendment No. 64 m 2-u l
-