ML20092C000
| ML20092C000 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/06/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co, Iowa Illinois Gas & Electric Company |
| Shared Package | |
| ML20092C007 | List: |
| References | |
| DPR-29-A-088, DPR-30-A-083 NUDOCS 8406200517 | |
| Download: ML20092C000 (12) | |
Text
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UNITED STATES g
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COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 OUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. DPR-29 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated April 25, 1983, 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 oper&te in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assuranc,e (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 Comission's regulations and all applicable requirements have been satisfied.
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-29 is hereby amended to read as follows:
8406200517 840606 PDR ADOCK 05000254 P
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. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 88, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NDCLEAR REGULATORY COMMISSION
/
Domenic B, Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 6, 1984 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 88 FACILITY OPERATING LICENSE N0. DPR-29 DOCKET NO. 50-254 Revise the Technical Specifications by deleting the following pages and inserting the enclosed pages.
PAGE 3.2/4.2-11 3.2/4,2-16 3.2/4.2-17 L
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s QUAD-CITIF.S DPR-29 TABLE 3.21 f?l5TRULtEliTAil0N THAT ll !TIATES PRIM ART COWT AINMENT 150L Afl0!! TUI!Cil0lls l*!rhum l'ccher
..r of Oprat: er frfs;:d lastivm st Cuw.stans instruments T1p tevel $stting Acticam 4
Reactor hw water 8
>144 inches above top of A
active fuel' 4
Reacter bw bw wats 284 inches above te'p of A,
active fuel' 4
High drywel pressure s2 psig,
- A 5
m
$14cg of ated steam Bow 8
S 16 Ksh Sow mah steamine f
8 16 High temperature mah s200* f.
steamine, tunnel 4
High radialbn mah 57 x samal rated powtr 8
steamfce tua.ncfsi background 4
- tow mah steam pressure
- 2825psig B
4 Kth Bow RCIC steamice
$300% of rated steam flow"3C l
16 RCIC turbine. area high s200* f C
temperature 4
Kth Sow HPCI steamroe 5300% of rated steam f.sw"'D HPCI area h't temperature
$200*f D
h 16 rstes 1.
%Naever p. unary canlainment irtegnty is resoned. there shal be las operatte a tiipped spterns for each fu cton, encept n
ter Le presswe naam steamime =hch only aese be evartatie a the R.m positen.
2.
Alan W the bst ulume cannet be met for one of the,tr$ sptems,that trip sptein skal be trypd E the bst alume caanet be met ter both trip sptems, the appropr'ete utions listed 6ebw shas be takaa.
A, hitete sa ederty shtdent and have the reacts in Cold htdens conditas k 24 heers.
3, betete an oderty lead isductam and neve reacts a Het it.andtf withas 8 heart f
C', Ckne estatsa valves a #0C spfeeL D. chi etatma.aives k lirci sahipiaat h Ammiast he speabis she erseeis cantahment hiegeity is met reteired.
L the seistas tre sgaalls bytened ebe the ende sedst is b Re! ele Start pNot hidesa.
j l
,1 1he estrumentatius she belates the sentrolseen ventistina spleuL s this signol she setematketyIM 9s machesel venne puso dbr.htge the inehtim udsu.
7.
Includes a time delay oe 3dM10 seconds.
1 s
top oc active euel is deelned as 360* above vessel sero cor all water levels usei j
in the LOCA analysis (see sases 3.23.
w n.n
QUAD-CmES DPR-29
.(
5-la8LE 4.21 tilMIM"M TEST AND Call!R111CN F7E"!NCY FCR CORE AND CONTA'hMENT COOUNC $75TE R3D BLOCK $, AND150LAT10NSh krtnpent hetnment Fev.ional Imrtivmeet tasassi issp2 tardrstine )
tae:e*
r2 gets batn = e.atum 1.
Reactor icw.bw water kvel
. 0)
.0nce/3 months On:e/ day 2.
Drywell kgh presswe U)
Once/3 months None 3.
Reactor be pressee Q)
On:r/,3 months None 4.
Contan.e t s;ay oterbek
- s. 2/3 : ore heet 0)
On:e/3 months None
- b. Certar. ment pressure (1)
Once/3 months None 5.
Low-pressee cue coc:.g pens (1)
Once/3 monttts None ds:harge 6.
(Nervo!! age 4 W essental Refalog outage Refueirig outage None tad Biscis 1.
APRM downs:aie U) 0)
Once/3 months None 2.
APRM fbw vanable U) 0)
Refuefog outage None
'(
3.
IRM cs: ale
- 5) 0) 51 0)
None 4.
RM downs: ale
- 5) 0) 51 0)
None 5.
RBM ucscaw n) 0)
Ref4teg outage None 6.
RBM downs: ale 01 01 Once/3 months None 7.
SRM ups: ale 51 0) 51 0)
None 3.
3RM detector net a startuo
- 5) 0)
(6)
None postten 9.
RM detector ft! n startup postem 5)
(6)
None 10, 3RM dona.5:aie
- 5) 0) 51 0)
None
!!. He water leve! e seam Chee/3 s:entis Not anchcatie None
. (scharge volume (STN)
- 12. SDV high level trip Refuelik Not appli[:able hone bypassed DJtage tisie stasaraw Isolatan 1.
Steam tunnel he temperature Refueleg outage Refueleg outage None 2.
Steamine hp Son U)
Once/3 months Once/ day b
3.
Steamine be pressure U)
Once/3 months Mone 4
Steamime he fad.aton Q)(4) 5.
Reacter kw b = ster level Refueles outage Once/ day 0)
Once/3 inantns once/ der sc* imiatma 1.
Steamine he now Once/3 months (a) Once/3 meths(a)None l
2.
Twtme area he temprature Refueleg outage Refue!ng outage None 3.
ts= reactor preswe Once/3 mertas Once/3 montns None E endment No. p g 88 3.2/42-16
1 QUAD-CITIES DPR-29 l
i I
I TABLE 4.21 (Cont'd) butnanest Instrumettt hectional lastnansat Cheamel fest*
Calibratleem Check 0
.JIPCI insistuut 1.
Steamine Ngh Ron (1) ( )
Once/3 months (8)
- None, l
2.
Steamine area hgh temxrature' Refueleg outage Refuelog outage None 3.
Low teactor pressure (1)
Once/3 months None Reactor tvilding Yeat2! atma System is:4ation And Standty Treatment System lastiation 1.
Ventilaton exmst duct radaten (1)
Once/3 months Once/ day monttors 2.
Refuelog floor radaten rnontters (1)
Once/,3 months Once/ day Itsom Jet Air gpetor M-tas taoistion 1.
Of gas radiaton monitors (1) (4)
Refuelt.g outage Once/ day Castrei Rasm Vesttisuon Sptem isolation 1.
Reactor low water level (1)
Once/3 months
,0nce,.;y 2.
Drywen hig' pressure (1)
Once/3 months None 3.
Mac steamfre he flow
-(1)
Once/3 months Once/ day 4
Ventilaton exhaust duct fadoton (1)
Once/3 mont.1s Once / day fnonttors M OS I
1.
Inttd#y once per montit untd et005gre hou' LIM at debed On figure 41 )) are 2 0 a IQ, the eaMer ac:ydeg to Figure 4 it wrth an stersa; het less than [ maritti nor mo's tftas ] ffia*!ts The com;dehoe of mitrument ratigre rate data map mClude data 3 Blamed trem Other !)cilm{ ne'er feettert ler whadt tfbe safr*t feta (M IPltrament Operatel m an ent#onme8tt $dfisLI* te tha! 010;iad C*es Units I and 2.
2.
fentienal tirl!s Catshratent and attenment Cneckt are not regured when these estrumenf t s's not Mused ta be C0eratie Or are triODed 3 The estrunwtotse o excetted from the functonaltest detmeten The tumtenaltest shas coast et a-etag a saviated ewtreat sc4 sto 8
tite meahnernent Cha*nel a ths m3frufnent Chawel 2 egepted fr0F the fuSClenal test definites aM M De tal: Ora'ed ggeg simubted elect' Cat 5 fall Once eve') 3 8Aenfht k FunCtenal tests shalt he g riormed before each startus eet'i a retured frequenC, est to escoed once pe seet Ca;.brale.rs anati be performec durme each startup er dormg cJitselled shutdowes esta a reg;;wed frequency not to ecsed once per seen Die positene( met *-anism shall be Caliterated every refuetet OWlate I.
Laet lytteEl funct4nal telt$ afe po'lermed as speCIW m the appitallie legten ter ttlete Sybtemt 8.
Functional test shall include verification of operation of the degraded voltage 5-minute timer and 7-second inherent timer.
9.
Verification of the time delay setting of 3 5. T 110 seconds shall be performed during each refueling outage.
a Amendment No.
, 88 3.2/4,2-17
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UNITED STATES NUCLEAR REGULATORY COMMISSION g
j WASHINGTON, D. C. 20555 t'
/
COMMONWEALTH EDIS0N COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 00AD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 83 License No. DPR-30
~
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated April 25, 1983, 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 (1) that the activities authorized 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 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, i
and paragraph 2.C.(2) of Facility Operating License No. DPR-30 is hereby amended to read as follows:
2-(2)TechnicalSpecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 83, are hereby incorporated'in the license. The licensee shall operate the facility,in accordance with the Technical Specifications.
3.
Thi!I license amendment is effective as of the date of its issusnce.
FOR THE NUCLEAR' REGULATORY COMMISSION jf/,3,
,c f
Domenic B,'Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 6,1984
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ATTACHMENT TO LICENSE AMENDMENT NO. 83 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-265 Revise the Technical. Specifications by deleting the following pages and inserting the enclosed pages.
PAGE 3.2/4.2-11 3.2/4,2-16 3.2/4.2-17 L
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QUAD-CITIES, i DPR-30 16BLE 3.21 sc' s,,
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,t INSTRUL!!!!T Ail 0!! THki II;!TI Aff5 PRil!ARY CONTA!Wk'41 150L Ai!0!I FWCTIDMS i,
g f' ' *'
st 1*
g!n! sa Ecmber of Ontat.'s er
..r fris;:4 Instrwnest Chaar.tlalII
'estrurienta Isly leve! $41 ting Acti AS s
\\m-
>14(inches 'abWe top of A
-e 4
Seufct hw WAf
' \\
[sclive fuel' s}.
s A
(
s
_s m,
y 4
Reactor hw kw water 284bches above teg of
% A e
~
t
' acSve fuel *
.\\-
s
,s s2 psgm
'j s,
S 4
High drpet pressur 16 H4h Scw mah 51eamkeS.
s14ctE*ratet steam kw,
8 N
r
%, f $2A'f:
(,
8, 16 H4h temperature mah N
'i steamine, tunnel m
.s g
4 Hih sa5ation mah
,} 57.Q,ma! sated peser 8
steamfme tunnef53
- backgrourf y 4
Low mah steam pressure'83 as25psig B \\Nw
\\'
4 4
HQh Son RCIC stranJoe s300% of rated steam Bow'73 C
'f.
s N-16 RCic tubhe area h4h s200*F C
g tempe.:tcre -
~
7) 4 H(h flow NPCNiesmSe s300% of rated steam ey%
+
<~
0*
16 HPCI ter '.gh temperature S200*F s
\\
t
\\
ha
.i r
s s
retes S
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1.
Whenever prenavy cantainment ** #flity is sequ' sed, there that be tme operaue y tripped sptems for uch Wltion. escept les les pmiere mas steamece wtAt ply med be available in the Ren positism.
, j\\"
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s Acten e the bst ce wes caneA be eneiler one et the trip solems, that tr*, systes shae be b*eped. g
,7 s
a 2.
r
- (
p ;,
8 the test eiwse cam,::4 met is Sr.h trip spttes, the appropriate actens had bows shaB be teen:
A, hAnate as yderly shtdows and have the regther Colt Shut /psro con 6en 's 24 heuri N
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)
- t
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y e,
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B. htete an.Mr had redvetisa st' haw ruder W3tandbA I bows, A
('
C, Cnne inelaties salves a RCIC rystem.
k d
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Is(
D. cbne iisait.si.viin spc i.bintact (No.
s
+
7t
,(
3 ased asl he speedle when primary contaimeent inteerg is set legelred.
- _g y
x %
+
g 5
ti'
. q' 45 1he asietus t, sageal's bypsued shes the made seitsh a ' Releel er Stas:sfMer Ateese.
s
^ 's + s s?
-t
.e
~
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,4./
l 1 lbs astrumentaties she ineinter. De senhof rese ventRates systaat-
- /
4 s;
l 4,
his signal ahe setematir.asy theet the machental secuus peutp disch6:gt Tee asialist sta3gg,
(.. -
x,4
(
e e
N 7.
Includes a time del.ny o'f 3d M1o seconds.
.j?A ( & l,
%.s r
y~
- .9 N
h Top of active euel is deeined as 16o* above essel aero for a'n water levels used
- I l-in the 14CA analysis (see Bases 3.2),
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MDdl!Ient No.' [,1'83 w
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QUAD-CITIES DPR-30
-k TABLE 4.21 N!MINUM TIST AND Call 2RAIlCN FRET.'!NCY FCR CORE AND CCMTAINMENT CCOLING STTTIMS INSTRU 300 BL3CKS. AND ISOLAT10NT78 hstnament hatuneet Feetmani hetnsnest tw Testm cardratiosm thecsP gets hetnuneststan 1.
lleacts bw.bw water level u)
.Once/3 months Once/ day 2.
Dynell hd pesme G)
Once/3 months None 3.
Reactor bw gessure u)
Once/3 months None 4.
ContJament spray eterlock
- e. 2/3 cae heet u)
Once/3 months None
- b. Contactnent pressure u)
, once/3 months
.None 5.
Law.pesswe core coo!cg pump n)
. Once/3.wths None 1schage 4.
tindervottage 4-W essential Refueling outage Refuefog outage None tai lischs 1.
APRM downscale (1) 0)
Once/3 months None 2.
APRM flow vanable (1) 0)
Refuelet outage None f,.
3.
stM upscale
- 5) 0)
- 5) 0)
None 4.
ItM downscale 51 0)
G) 01 None 5.
ITEM upscale 6.
R8M downscale (1) 0)
Refueleg outage None U10)
Once/3 months None 7.
SRM escale
- 5) 0)
- 5) 0)
None 3.
SRM detector not a startup
- 5) 0)
(6)
None positen 9.
ItM detector ret n' startup position 5)
(6)
None
- 10. SRM downscale 51 0)
. 5) 0)
None 11 H@ water level e scam Once/3 nenths Not applicable None
.. dschage vobne (SW)
- 12. SDV high level trip Refueling Not applicable None
- bypassed outage u'se asselhe imetism 1.
Deam tunnel h@ temperatwe Refuelhg outage Refueling outage None l
2.
Reamine h@ flow (1)
Once/3 months Once/ day 3.
Steamtme bw presswe (1)
Orce/3 months None 4.
Steamroe he radaten (1) (4)
Refueleg outage Once/dar 5.
Reactor bw bw water level G)
(hte/3 months Once/ day
. ECC hebthm 1.
Steamise hp Ilow Once/3 months (s). Once/3 monthstal None l
fi 2.
Totne sea he temocratwe itefueleg outage Refuehng outage None l
3.
1sw reactor,pessure Once/3 menths
_Once/3 montas None AmendmentNo.7T,[,83 3.2/42-16
QUAD-C1 TIES DPR-30 TABLE 4.21 (Cont'd) hetnament justrumest Functiemal lastnament Casamal Testm Coutraties*
CaeckW i
WCl leslettes
- 1.
Steamisie h(h Ibr (IX )
Once/3 months (a)
None l
2.
Steamline area h(h tempenture Refueleg outage Refueleg outage None 3.
Low reactor pressure (1)
Once/3 months None teacter Buuding Ves'Jiatics System isolation And Standby Trastment System lattistion 1.
Ventilston exhaust duct radiaton (1)
Once/3 months Once/ day monitors Once/3 months Once/ day 2.
Refueling noor radiation monttors (1)
Steam Jet Air E)seter Of4as testation 1.
Of. gas radiat~ n monitors (1) (4)
Refueling outage Once/ day e
'Cestral iteam vestsstion system isolation 1.
Reactor low water level (1)
Once/3 months Once/ day 2.
Drywen high pressure (1)
Once/3 months None 3.
Most steamime h(h flow (1)
Once/3 months Once/ day 4.
VentWaton exhaust duct radiation (1)
Once/3 months Once/ day leonflors Bates 5
L been, ence per month unti aposwe hours Od as deined on Figure 4.111 are 2 0 10 ; thereafter, accordsg to Figure 4.1-1 with an stervat met less then I month nor more than 3 months. The competaten of mstrument failure rate data may eclude data ottamed from other boileg ma:er seesters Ier unch the same design estrument operates e an envronment smular to that of Quad Cates Umts 1 and 2.
2.
Fenctanal tats. cs*stans, eid estrument checks are not regered when these estruments are mt resured to be operable or are tnooed.
3.
k astrumentaten a encepted from the functenal test delniten. The functonal test shah con. st of sjectag a sunulated electrtal signal sto the mesestament channel.
4.
k astrement channel e acepted kom the functonal test defnitens and shaR be calibrated vsmg saastated electrzal signals once every 3 austhL i Fametunsi tests shall be performed twfore each startup wrth a recared hoevency not to exceed once per meet Ca*stens shall be periormed dereg east startup er dermg controlW shutdowns with a regered frequency not to seceed once per weelt 6.
lhe peutunag mechanem shal be caldirated every refusent estate.
y.
tags spetun hectanal tests are pertermed as specreed a the apposable sectan ter these systems 8.
Functional test s' hall include verification of operation of the degraded voltage i
5-minute timer and 7-second inherent timer.
9.
Verification of the time delay setting of 3 5. T 110 seconds shall be performed during each refueling outage.
i i
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Amendment No. 83 3.2/42-17