ML20069C618
| ML20069C618 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/17/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co, Iowa Illinois Gas & Electric Company |
| Shared Package | |
| ML20069C621 | List: |
| References | |
| DPR-30-A-078 NUDOCS 8303180073 | |
| Download: ML20069C618 (8) | |
Text
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UNITEJ STATES g
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NUCLEAR REGULATORY COMMISSION l
-8 WASHINGTON. D. C. 20065 COMMONWEALTH EDISON C0K3ANY AND 10WA ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMEf:T TO FACILITY OPERATING LICENSE Amendment No. 78 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 May 12, 1981, 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; 3.
The facility will operate in conformity with the application, tFe provisions of the Act, and the rules and regulations of t!w Commission; C.
There is reasonable assurance (i) that the activities authorized by this anendnent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Concission's regulations; D.
The issuance of this amendnent 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 Connission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the licen'se is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license anendment and paragraph 3.B of Facility License No. DPR-30 it hereby anended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised thrcugh Anendnent No. 78, are hereby incorporated in the license. The licensee shall operate the facility in 1
accordance with the Technical Specifications.
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8303100073 930217 PDR ADUCK 05000265 P
2 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COPMISSION enic B. Yassallo, Chief Operating Reactors Branch #2 Division of Licensing Attactinent:
Changes to the Technical Specifications Date of Issuance:
February 17, 1983 l'
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ATTACHMENT TO LICENSE AMENDMENT NO. 78 FACILITY OPERAT.ING LICENSE NO. DPR-30 DOCKET NO. 50-265 Revise the Appendix "A" Technical Specifications as follows:
Remove Replace 1.1/2.1-2 1.1/2.1-2 1.1/2.1-2a 1.1/2.1-2a 1.1/2.1-8 1.1/2.1-8 1.1/2.1-9 1.1/2.1-9 3.1/4.1-1 3.1/4.1-1 i
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QUAD-CITIES.
i pyR.30
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D. Reecser Water level (Shuidown Condie3en) a
= - 3:* 2,:',s e,. or u,e re.eter is in u,e ei;.t.
(3511 sett) down eendition with arradiated fuel in the reacter vessel, the water sys,PD e maalmuen fraction of level shall nett he less than that limiting power dens.
corresponding to 12 inches aheve the Sty where the limit.
top et the active fuel
- when it is Aseg power density seated in the eere.
for each bundle is the design linear
- Top of active fuel is defined to be heat generetten rate 360 inches aheve vessel sets (See for that bundle.
Bases 3.21.
g The rette of FRP/MFLPD shall he I
set equal to 1.0 unless the actu.
i al operating value te less than 1.0 in which ease the actual operating value will be used.
This adjustnent any also be perfarned by ircreasing the AM M gain by the inverse ratio, MUD /77tP, dich l
accorplishes the same degree of pres-i tacticm as reducing the trip set, ting i.
by 71tPAfUD.
i
- 2. AFMI Fim scrarn Trip Settag (Re.
fbeling or Startup end Hot standby Mode)
Men the reactor mode switch is h the Refuel or Startup Hot Standby posi-tion, the APMI scrarn shsl; be at at has than er equal to 15T of rated asutron Au.
- 3. IRM Flus scram Trip setting The IMI flux scram wtting sha!! be at at has than or equal to 120/125 of full scale.
- 4. Men the reactor mode saitch is in the martup or run pontion, the reactor shall not be operated a the satural arcula.
tion flow mode.
- 5. APRM Red Block Setting s
The APRM rod block setting shall be as shown i
la Figurt 2.1 1 and shall be:
5 S [ (0.58% + 50) 1.1/2.1-2
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Amendment flo..f4, 78 l
QUAD-CITIES m -se D(
t
. The definistene esed above for the APAM scram trip apply. In the event of oper.
ation with a maximum fraction limiting '
power density (MrLPol greater than the fraction of rated power (FRP), the netting rpill be modified as follows 56(0.58g+50)h Tfie definitions used above for the APRM ser:4 trip apply.
The ratio of FAP to PIFLPD shall be set sgual to 1.0 waless the actual operating value le less than 1.0, in whi h ease f
the actual operating value will be used.
'!his adjustnent may also be performed by increasing the APM gain by the inverse ratio, MrIJD/MtP, idlich acewplishes the sene degree of pro-taction as reducing the trip setting 1
by rRPMUD.
C. meneter low water level scram setting shall be 144 inches above the top of the active fuele at normal operating condi.
l tiene.
f D. Reactor low water level ECCS initletion shall be 44 inches (*4 inches /-0 inch) abeve the top of the active fuele at moraal operating conditions.
E. Turbine stop valve scram shall be s 10% valve 4
elosure from full op:n.
F. Turbine control valve fast closure scram shall Initiale upon actuation of the fast closure sole.
acid valves which trip the turbine sentrol valves.
O. Main steamfine Isotsilon valve closure scram shall be s 10% valve closure from fuD opea. ;
H. Ma'in sieamiine low. pressure initiation ofinain steamline Isolation valve closure shan be k.s2s psig.
of' active [uel is defined to
- Top 60 inches above vessel sero be 3
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(SeeBases32) i)
1.1/2.1-2a'
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Amendment No. $f, 78
DPR-30**
. e f
the An increase in W AFM eeres trip esiting would decrease th d
by an analysis of margins required to provide a ressenable y
ope r ation.
li thermal stresses.
l which have en adverse ef fect en reactor asfety beesuse of the resu t ng the Wo. the APM scram trip setting was selected because it p
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i sty of unnecessary scrame.
l N scram trip setting saast be adjusted to' ensure that the 1mm transient peak is not.
Ancreased for any t webinetten of mastaun fraction of limiting pwer density (M71 I
W seras setting is adjusted in accordance with'the ferruta in Specification 2.1.A.1. whqn the Mr1.Ps la grostar than the (rnesien of rate l
reactor core thermal pwer.
We adjuswent may be acxxrglished by ircreating the APIN gain by the reciprocal 21s pcwides the sene degree of potection as reducing the trip setting by TRPMLIV by raising the init141 PJ9N rsadinga closer to the trip settinga of FRPMtPD.
l mch that a scram would be recieved at the *ame point in a transient as if the trip settings had been reduced by FRP E po' d
Aym Flux Scram Trip Setting (Refu'el er Startup/ Jet Standby Mode) 2.
i For operation in the Startup mode while the reacter is et low pressure, the APM screa of 15% of rated pwer trovides adegante thereal cargin htveen the s l
limit, 25% of rated.
Ef fects of inevensing r.ressere at sore or new weld estntent siein the,
l d
ainor, cold unter from sources avellable durir.g, startep la aat with ower plant startup.
l Of all possible secrees unifois by operating piecedures beeked up by the red worth minimirer.
et reattivity input, uniform control red withdrawal le the seat probable cause of signific l
ascouse the fluz distribution asecciated with uniform red withdrawa l
i fi-involve high local peats, and becesse several rede must be moved to change power by a s pwar rise.
l ennt percentage of rated power, the rate of pewwr rise is very slow.In an assumed uniform ro i
)
is in near equilibriurt with the fission rete.
i and to the scram level, the rate of power rise.is ne sare than SE of rated power per a nste, i
ld escoed the APM eyeten would be core than adegust's to aerure a scram before the This switch securs when reactor pressure is greater than 525 psig.
the safety limit.
Run positten.
2RM Fina seras Trip setting logie 3.
The 3M systen consiste of eight char.hers, four is each of the reactor protection system The Ir.M is a* S-decade instrur. ant which ecvers the range of power level betwee The 5 decades are broken devn into 10 ranges, each being l
channels.
eevered by the SM and the AFM.
{
ene-half a decade in oise.
yet exanple, The IM scram trip setting of 120 divistene le setiva in each range of the IM.
4 if the tristrument were en Range 1. the scraa settiaq would be 120 divirions for that range likewise, if the instrimment ware sa Range S the scram would be 120 divialons on that r We, as the IM le ranged up to accommodate the increase la pwer level, the scram t j
]
j ting is oise ranged up.
W most significant eenrces of reactivity ebange durlirs the pow'et increase are In eeder to ensure that the JAM provides adequate protection against the d
This saalysis j
eingle red withdravel error, a range of red withirawal accidents was analyse.The mos red withdrawl.
j included starting the seeident at various power levels. initial eenditien es j
j l lose st t:
Additional senservatism was tehn la t41e analysis by assumiag that t scale.
l alsfJir4 and peak power limited to 15 of rated power. thus maintaining MCP the withdrawn rod is bypassed.
and local centrol red withdrawal errors sad eentinueas withdrawal of control rods i integrity' safety limit.
provides backup preteettom fee the AraM.
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Amendment No. g, 78 1.1/3.1-e*
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QUAD-CITIES *
- . DPR-30
=
a_=
2C C.
&PRM Red Block Trip Setting peneter power level may be varied by eeving control rods or by varying the reeiseulatics flow The APAM system provides a sentr%1 red block to prevent gross red withdrawal at constaat Seeirculation flew rete to protect against grossly escoeding the McPR Puel Carddir$ Ir.tegrity este.
j This red bleek trip setting, which is automatically varied with recarculation Safety Limit.
leep fles rate, prevents an increase in the reacter power level to emeessive valuss due to
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The flev variable trip setting provides svhatantial margin frem feet
'esat.rel red withdrawal.
damage, assuming a steady-state operation at the trip setting, ever the entire recirculatten increases as the flow decreases for the specified flew range. The margin to the safety limittherefore the worst sase McPR which esuid occur during trip setting versus flow reissionshirt steady. state operation is at 100% of rated thermal power because of the APRM red block trip j
The actual power distribution in the core is established by specified control red setting.
As with APM scram trty sequences and is monitored continuously by the incere LPM system.
setting, the APRM red bleek trip setting is edjusted dow. ward if the maximum freetion of limit.
Lag power density ascoede the fraction of rated power, thus preserving the APRM red bloc *r.
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As with the serse setting, this say be accesplished by adjusting the AFN( gains.
3-
- c. meanter Lee water Level seren The reactor low water level seram to set at a point which will asente that the water 1. vel seed The scram setpoint is based on nerea', operat.
in the bases for the safety limit is maintained.
Lag temper, ture and pressure conditions because the level instrumentstaen is density eutpensatst.
s Batetor low Low water 1.evel Ecc5 Zaitiation Trip Point 3.
The energency eere cooling subsystems are designed to provide sufficient eoeling to the core to dissipate the energy assectated withthe loss.of ccolant accident and to limit fuel claefing
- temperature to well below the cladding melting temperature to assure that eere geo -etry rematns j
To accomplish their fr; tact and to limit any cladding metal. water resesien to less than 1L 1 hd I
. intended function, the especity of each ensrTency core cooling syste's ernponent was estas &s e j
EE based en the reactor low water level scram setpoint'. To lower the sospoint of the low water for each cf the 1:cs co penents. Thus, the V-level seras would increase the capoeity reauire ment ass:sor vessel low water level scrate was set low enough to permit margan for operation, yet will l
met be set lower because of Ects espacity requirements.
The design of the Eccs compenents to meet the above criteria was dependent sa three previously the --W-break sise, the law water level scraa sospont, and the 2c:s l
set parameters:
l initiation setpoint. To lower the sospoin*. for initiation of the ECCS esuid lead to a less af effective core ecoling. To raise the ECCS initiation setpotat would be in a safe direetten.
l het it would reduce the margin established to prevent actuation of the ECCS 4% ing aermal j
speration er enzing normally expoete,d transients.
j 3.
N bias Stop valve seres The turbine stop valve closure scram trip anticipates the pressure seutres flow, and heas' flux increase that could result fram rapid closure of the turbine stop valves. with a scram trip increase in surface heat !!ux is setting of Icn of valve closure frart full open, the resultant
,t limited such that McPR remains above the McPR fuel claddir.g integrity safety lamit even during the worst-ease transient that assumes the turbine bypass is elesed.
l F.
Tarbine centrol Talve Past closure Seren The turhine sentrol valve fast elesure scram is provided t7 anticipate the rapid intresse la pressure and neutron thax resalting from fast closure of the tu:bine control valves due to a lead rejection and subsec-Jent failure of the bypass, i.e., it pr' events M PR from beesming less for this transient. For the Acac than the McPR fuel claddtag integrity safety limit rejection without bypass transient from 100% power, the peak heat flux
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increases on the order of 151 which provides wide i
(and therefore LHCR) corresponding to 1% P astic strain of the cladding.
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naargin to the value h*t...
1.1/2.1-9 Amendment No'. E/, 78
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oilAli rInr.S DPel.Je I
11/4.1 REACTOR PHOTECTION SYSTEM l
i IJMlllNC tmlilTIONS FOR oil'.IIATION SURYEllJ ANCE RT.QtflRfAllATK Apps abilit}:
';, " _" " 3 :
w Applici to the inseremenuden anJ astedsent ak.
ne the serveillance of sine instrumenstion usw s hich initute a rearine geram.
asetnisigJ desnts which inatiatr seactor sessa.
Obiershc:
ggeregre:
1 e re 'ihe ope.haii3 erik marini pria..si.e To ap cify one syre and thg cr.*y ~ sweveiusase in staars.
he applied m the prowoion seservsmessauen.
SPF.CIFICATIONS A. The inspi.ints, mainimum cumhet of trip syd A. Instrumenistian e3 sems shall he functier.alty arms. and minimum numb.r of instrument sessed anJ eelsbraieJ as indicancJ in Tables thanacts slut must he operrble for each pnti.
d 8 8 and 4.12 wipruisely.
aion of the teat 1er mode seisth shall he as C
given in Tables 3.1 1 through 3.14. Taw system
- 3. Daily dvring remes pn=er creration. the nice respnner times (sprn the opening of the senwr eeniaci op so and iniluding she crening of the
' pon er dettihstaur shalt iv ehecLrJ l'or maximum fraction of limiting power dens-l erip ectuaier eenusts shall mas eneeed 50 mihi'**d*-
ity (MrLPD) and compared with the
,*If, during operation, the maximum fraction of rated power (FRP) fraction of limitdng power dens-when operating above 25*4 rated ity exceeds the fraction of rated thermal power.
power when operating above 25%
rated thermal power, either In the sansfe tenditi.e and Column I of Ta.
- 1. the APRM scram and rod hiss 3.11 shsevgh 3.3 3 cannas he met. Aat block oettinga ahall be wi I"p symm must be poiin the trapped csediuen reduced to the values
I given by the estuntions able shall be funciennally in Spccifications 2.1.A.1 trued within R hoort The trip avseern su ala-hiled chseinet mas he entrippd"for a persed or and 2.1.3.
This may also eine aos a euled I li.wr m concers this be accor:plished by estias. As la*t as she irip sysiem. th ine inereasing the APPM gain "J 'i"* "'I **"'*I*' **' 'f"*
- l as described therein.
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trip sysseni may be pimed sa che en: ripped ILion Air thort periodt of time to allou-messanal ersting of all RPS int:rsment chan.
aels as spried by T4tJe 4.1 1.The seir 33seem i
may be en the sa ripped resision Die ne more dise 8 hears per fonctier.al seis perical far this 2.
the pcver distribution
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shn11 he changed such i
that the snaximum fraction
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of limiting power density no longer exeriods the
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fraction of rate:d power.
3.1/4.1-1 Amendwant No. N g 78
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