ML20153C476
| ML20153C476 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/31/1986 |
| From: | Kronich C, Tamlyn T COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| TKT-86-13, NUDOCS 8602210020 | |
| Download: ML20153C476 (102) | |
Text
" %
QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JANUARY 1986 COMMONWEALTH EDISON COMPANY AND IONA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 8602210020 860131 PDR R ADOCK 05000254 pg ,
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TABLE OF CONTENTS I. Introduction II. Summary of Operating Experience A. Unit One B. Unit Two III. Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A. Amendments to Facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approval D. Corrective Maintenance of Safety Related Equipment IV. Licensee Event Reports V. Data Tabulations A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossary I
I. INTRODUCTION 1
+
Quad-Cities Nuclear Power Station is composed of two Bolling Water f
! Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in
[.
j Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply a
Systems are General Electric Company Bolling Water Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary
! construction contractor was United Engir.eers & Constructors. The Mississippi l
River is the condenser cooling water source. The plant is subject to license ,
numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Docket Numbers 50-254 and 50-265. The date of initial Reactor criticalities for Units One and Two, respectively were October 18, 1971, and April 26, 1972. Commercial generation of power began on
! February 18, 1973 for Unit One and March 10, 1973 for Unit Two.
This report was compiled by Becky Brown and Carol Kronich, telephone number 309-654-2241, extensions 2240 and 2157.
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II.
SUMMARY
OF OPERATING EXPERIENCE A. Unjt One January 1-31 Unit One began the month of January holding load at approximately 710 MWe due to Off Cas recombination outside the Recombiner. On January 1, at 1825 hours0.0211 days <br />0.507 hours <br />0.00302 weeks <br />6.944125e-4 months <br />, the unit was placed on Economic Generation Control (EGC). EGC was tripped at 700 MWe, on January 3, at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />. At 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br /> load began an increase to 750 MWe at 100 MWe/ hour. At 1810 hours0.0209 days <br />0.503 hours <br />0.00299 weeks <br />6.88705e-4 months <br /> the load increase was terminated at 720 MWe, At 1853 hours0.0214 days <br />0.515 hours <br />0.00306 weeks <br />7.050665e-4 months <br /> load was decreased to 700 MWe due to Off Gas Recombiner fires. Load re-mained at approximately 700 MWe until January 5, at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />, when a uait shutdown for the End of Cycle Eight Refueling and Maintenance Outage commenced. On January 6, at 0003 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, the unit was manually scrammed. The unit was shutdown for the remainder of January.
B. Unit Two January 1-8 Unit Two began the month of January on EGC. On January 3, at 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br />, the Reactor was scrammed due to a spurious Group I Isolation caused by an air hose hitting an instrument rack. The Reactor went critical at 2238 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.51559e-4 months <br />, and on January 4, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, the Generator was placed on line. A normal startup proceeded. At 2210 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.40905e-4 months <br /> load was held at 790 MWe due to the Condensate Demineralizers. On January 6, at 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />, load was dropped to 700 MWe for Condensate Demineralizer maintenance.
At 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> load was increased to 780 MWe and held until January 7, at 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br />, when load was increased further to 800 MWe. On January 8, at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />, load was increased to full power.
January 9-23 On January 9, at 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br />, Icad was dropped below 800 MWe and the unit was placed on EGC at 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br />. On January 10, at 2320 hours0.0269 days <br />0.644 hours <br />0.00384 weeks <br />8.8276e-4 months <br />, the unit was taken off EGC to perform surveillances. The unit returned to EGC on January 11, at 0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />. On January 13, at 0238 hourn, the unit was taken off EGC, and load was increased to full power. Load was dropped to 800 MWe on January 16, at 1655 hours0.0192 days <br />0.46 hours <br />0.00274 weeks <br />6.297275e-4 months <br />, then the unit was placed on EGC. The unit was taken off ECC on January 18, at 0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />, to perform surveillances. At 021L hours the unit returned to ECC. At 1655 hours0.0192 days <br />0.46 hours <br />0.00274 weeks <br />6.297275e-4 months <br /> the unit was taken off EGC, and load was increased to full power.
On January 22, at 0307 hours0.00355 days <br />0.0853 hours <br />5.076058e-4 weeks <br />1.168135e-4 months <br />, the unit was placed on ECC. At 1140 hours0.0132 days <br />0.317 hours <br />0.00188 weeks <br />4.3377e-4 months <br /> the unit was taken off ECC and load was decreased to 750 MWe to change over Reactor Feed Pumps. At 1228 hours0.0142 days <br />0.341 hours <br />0.00203 weeks <br />4.67254e-4 months <br /> the unit was returned to EGC.
O B. Unit Two (continued)
January 24-31 On January 24, at 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br />, the unit was taken off ECC, and load was dropped to 430 MWe at 150 MWe/ hour for MSIV surveillances. On January 25, at 0310. hours, 430 MWe was reached and held steady. At 1340 hours0.0155 days <br />0.372 hours <br />0.00222 weeks <br />5.0987e-4 months <br /> load began an increase to 800 MWe at 100 MWe/ hour. AT 1/30 hours 800 MWe was reached, and load continued to increase at 5 MWe/ hour to full power. On January 31, at 0150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />, load was dropped below 800 MWe and the unit was placed on ECC at 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br />. The unit remained on EGC for the remainder of January.
O s
III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.
B. Facility or Procedure Changes Requir ing NRC Approval In accordance with Technical Specification 6.8.B.l., the following documentation concerning revision 11 to Quad-Citiet Station Off-Site Dose Calculation Manual (ODCM) has been included.
C. Tests ar.d Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.
D. Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the major safety related maintenance performed on Units one and Two during the reporting period. This summary includes the following: Work Request Numbers, Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.
i
' QAP 1400-T1 Revision 2 CUAD CITIES STATICN CNSITE Sectem er 1935 REVIEW ASSIGhMENT -
CATE lkf31 RI REVIEW NO. 89-33 REVIEW PARTICIPANTS:
H , L , h,y C 5 Pd \ 1 %.
P. L ag-s T" %. % HL h . L e w,
. Y e G 6 en c- n b . be w e s. t ASSIGio!ENT:
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A%Sk[ -
STATIC:I R/* NAGER. l APPROVED 0CT ' 01985 (fin 31) 0. 0. 0. S. R.
9/03211 \
N Commonwealth Edison
- I li ) 72 West Adctns Street. Chicago. Illinois k V 7 Address Reply to: Post OMce Box 767 V Chcago. lilinois 60690 - 0767 November 7, 1985 To: T. Lihou Gubject: Onsite Review of the Offsite Dose Calculation Manual, Revision 11 Quad Cities Station Site Specific Sections 7.2 and 8.0 Enclosed please find a copy of the revised site specific sections 7.2 and 8.0 of Quad Cities Station's Offsite Dose Calculation Manual. This revision must go through an onsite review prior to submittal to the NRC and general distribution.
The Quad Cities ODCM is scheduled to be included with the December Operating Report for submittal to the NRC in January 1986. Since the ODCM must also be offsite reviewed, I would appreciate the onsite review be completed by December 1, 1985.
Your cooperation in expediting the review process is greatly appreciated.
O W Rick L. Thacker Environmental Health Physicist LlA&
CaroF J. Bennett Lead Environmental Health Physicist cc: EPG-04-RE-ODCM-Revil W. Brenner J. Goldan JCG/DMK/ Ink /6451E/70
Rev. 7 3-1-02 OSR F0iW i RECCP.O OF REGUES T FOR G 75ITE RE'!IEW Sta. ion byLM b.be3 Onsite Review IJo. TI'd Submittad by __ _ k_/_[ e c y Oate /-lf)2/(\
i Test or experiment not involving an unrevie ved safety question.
Proposec test or experiment involving an unreviewed saf ety questien Propo:cc ch;nge te procedure, equipment or system involving an unreviewed safety question.
Proposed change to Tech. Spec. or license.
unanticipated deficiency o f design or operation of safety related structures, systems, or c mponents.
Jroposed cnange to GSEP.
s/_ Referrai by T. S. Supervisor, Station Superintendent, Division Vica Presicent Nuclear Stations, or Manager of Quality Assurance
( 'citional setject ds:cription: DOUVJ See In r a e 7. ,2 a dy..p Supporting dccumants attached: O D C A7 J
[dlte b e O G yaE
, th T.)lhw uh/r '
/
Date required for Offsite Review completion: If M II Reason for specified cate: Mu \la O r, bOA E t,/ n@ b r
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .W. . . . . .%. .d. . .\ . bM. .' .I.$8.G...........
0 T.
Received by Date Senior Participant Of fsite Revicw 140.
OAP 14CC-72 CUAO-CITIES STATICN Revision 3
- CN-SITE REVIEW REPORT Sectemcer 1985 Reference Information: OSR Recuest Originator:
OSR No: k E~ M Station Off-Stie Review Review Cate: f3.f t3 f 8 S' NLA Other' N Request Date: lA fl3,l f { NFS Was Request Complete:
~
SNED Yes NO (Attach material submitted)
Subject:
Reason for Review:
Tech. Spec. 6.1.G.2.a (On-Site)
Tech. Spec. 6.1.G.I.a (Off-Site)
Other: NRC Bulletin Deviation AIR Request __ Station Cr-Site Deference Materials (attach):
Safety Evaluation Precedures Affected Tech S;ec Pages W1 Number FS;R Pages AIR Number C4 Vanual Pages Other ()WM lt ID5 YY
! . Cf'-Stic C0coletion Info- M)jls 05 C 3
Check List Complete Advance Notificatten EU rm =IO
, Fcrward to Off-Site / Cate Off-Site Review Number Persen Cis esiticn:
Rcuttne Recort Cff-Sit- Review for Cencurrence (T.S. 6.1.G.2.a.(S))
AIR Iss: d (1 )
F.C Sct-ittal Needed T.ennical Suecificaticn Change U..revie,ted Safety Questien j Gthr l No furtt r Action j Oth3r APPROVED 9/c322a -t' OCT .'. 0 E83 OPOCO
QA? 1:00-T2
. Revision 3 QUAD-CITIES STATION CN-SITE REVIEW REPORT OSR NO M- 3 3 CN-SITI REVIEW SUMMArr: 71 05R4 1 _ d i % _ td ooon 94 J W .tt fJA - d . o., ,, e.; -y j'M " 3 ,12 _L tat 1.E m11Em p l))
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Mw we t? I ma GN-SITE OEVIEW RECCMMENDATION:
7/i O5 R d a. ,1 d d f IA. % , .k w-J - J J ILt g L l tJ A _ '
(Si a bg*A.
PARTICIP/NTS: , ( # M R1+1 ' A%id mala Apprded: [:1:9)b ATTACHMENTS:
cate: )2 85
- StaddeL,ksLeh*tifST APPROVED ecm x 72n.ot. % OCT _. 01985 Q cQ C65% inai) 9/03223 O. C. O. S. R.
D '
QUAD-CITIES REVISION l'.
- DECEMBER 1285 In addition to the GE noble gas monitors, the gas cample is I routed through a filter paper on which particulates are der nited, through a charcoal cartridge which traps the iodines, and
[A[ff[
. a. g
-f through Eberline low and medium range noble gas detectors.
l Under accident conditions, the above pathway can be bypassed and the sample routed through an Eberline/Victoreen system which has an Eberline high range noble gas monitor and a Victoreen postaccident particulate and iodine sampler.
The Eberline low and medium range noble gas de.ectors view .
the same volume, while the Eberline high range noble gas !
detector views externally a section of one inch stainless steel tubing as its sa=ple volume. The low range is monitcred I
by a beta scintillation detector (Eberline Model RDA-3A), i while both the medium and high range measurements are performed j hy ar. energy-compensated GM detector. E r rf< r"M ruh t r a c t i.sn. e ggg; Fr provYdEc :or all chtec &a.3;a. Sample flow is provided by a stainless steel diaphragm vacuum pump and an air flow I regulator. Sample flow is set to insure isokinetic sampling monitored by a solid-state flow sensor. ,
The three Eberline noble gas detectors are part of a microprocessor-controlled gaseous effluent monitoring system (Eberline SPING-4).
The monitoring system's control terminal, strip chart recorder !
panel 912-1 and annunciating panel 912-4 are located in tha control room on Panel 912-1. The control terminal provides f immediate access to current detector activity, operating parameters, and history files for any detector. Changes in detector operational status are automatically printed and
- audibly acknowledged. The SPING-4 microprocessor's memory has battery backup to maintain all operating parameters and history files for any detecter in the event of a system power loss.
8.1-4
TAHIE 8.4-1 ,
- 1:NVIRONMl',NTAI, RAD ltII.(X;1CAf, MONITOltING PROGRAM SAM!'LI NG Olt TYPR AND FRr(;fn:Ncy EXPOSI8HE PATHWAY Ol' ANAf.Yt;I:;
SAMPLING OH MONITOHING I,0fATIf)NS COI.tE TION FHl:QUFNCY AND/UN SAMPLE Particulate Sampler:
- 1. Alrhorne a. Oniste or_Ne.sr Fielr'#
Continuoisn sampler Cross 1.cta ana!ynis 0-01 Oncite Station 1 0.. mi N following filter cl'ange" Q-02 Onsite Station 2 0 . 's mi IGNR operation with partic-Q-03 Onsite Station 3 0.6 mi S ulate filter collee-tion weekly and Ita<l i n i o.l i ne C
- n i e. t e r Q-04 Mitrin 1.5 mi NC 0-05 Saddle Clule l'a i r y I.H mi S!;M radioliatine canister Farm collection bi-weekly I-111 analyqin bi-weekly Q-06 Ilinson's Doat 1.8 mi NNW Landing flampling Train:
Test and maintenance weekly
- b. Far Field" @
3+
Particulite Fomplor E
-' .* Q-07 Clintos. 9.n mi NR Continuous sampler ' ~ '
Q-08 Sikkema l' arm 7.0 mi ENE operation with partic-7 f _ Q-o y ire 13.0 mi ESM ulate filter collec- Crons t> cts analynl*: b 'I o'
O
'/ { u-10 IIll i n la t e 10.0 mi SE tion weekly and f ollowing f ilter change p Q-11 Port Byron 8.0 mi S sadios<xline canister 13.0 mi collection bi-weekly Ridioindina Canietart Q-12 Bettendonf SW Q-Il Princeton 4.11 m i SW Q-14 Utica Rielga Hoael 11.0 mi ESE I-131 annlysin b!-weekly ,
Q-15 DeWitt 13.0 mi WNW Sampiin.] Tr; In: n J-16 Low Moor 6.0 mi NNW Test and maint.anance weekly e, ,.'
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QUAD CITIES ODCM SUBMITTAL
- MAY 17, ]983 9
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J ~ _ .2 :. .. . . . . _ - ___a..._.___ _. , ,_ L ,,1 7 ~ ~ ~ i I
QUAD-CITIES REVISION 7 MARCH 1983 8.0 RADIOACTIVE EFFLUEW TREATMEM . SYSTEMS ,
~
1 MODELS FOR SFFTING GASEOUS AND LIg ,
- EF.?LUEW MONITOR ALARM AND TRIP SETPOIMS, O dr, '
D ENVIRONMEffrAL RADIOLOGICAL MONITORING f
l 8.1 . GASEOUS RELEASES ,
Alarm and trip setpoints of gaseous effluent monitors at the principal points of release of ventilation exhaust air containing radioactivity are established to ensure that the release limits l 'd(, f%%f 10 CFR 20 are not exceeded. The setpoints are found by f solving Equations 2.9 and 2.10 for each class of release.
g ;fmal e o.e.
'UL f [S u air For this evaluation it assumed the radios.;tivity to have the composition of gases lis,ted mixture in in the exh Table 3-3 froa *rechnical Derivation of SWR 1971 Design Basis -
_ Radioactive Material Source Termis'",1NEDO-1087L March 1973,
" *{ Ceneral Electric Company. This mix'ture of M ioactive gaser ,
% is representative of the activity found at,the point,of release from the fuel with no - radioactive decay accounted for. .--
Equation 2.9 is rewritten using the fractional composition of each nuclide, f g, and a total release rate, O g, for each class:
1.11 Og , Sg a ft) + Og, @g a ft ) + <500Yr (8.1) sc.e, e.., 4
- fg Fractional Radionuclide Composition Pc S k id km The release rate of radionuclide i divided
- d , g,,,.ft , j .g,,,
tae.h p % way. by the total release of all radionuclides.
I kv a k's a kh O, Total Release mate, .
g i
J Stack Release (pci/sec) f The release rate for all radionuclides j due to a stack release.-
l 8.1-1 .
f
, QUAD-CITIES REVISICN 7
. BUGICE 1983 O, Total melease mate, (uci/sec)
Vent Release
(.
The release rate for all radionuclides ,
I '
due to a vent release.
~
! O, g Total Release Rate, . (wci/sec)
. Ground I,evel Release The release rate for all radionuclides due to a ground level release.
Og,= Og ,fi (8.2)
Oiv = Og ,fi (8.3)
Ogg = Oggfg (g,43 Equation 8.1 can be solved for Q t
for each class 05 release for release limit determinations.-
,i Simi1arly, Equation 2.10 can be rewritten:
i (X/Q)s O ts fi *MP(-AgR/3600u,) + (X/0), Og ,f g exp(- A gR/3600uy)
+ (X/0), Ogg f g exp(-A gR/3600ug ) + 1.11 SOg ts fi
. L
.q
+ Vig Q ,fg+GQi gg g f < 3000 r (8.s)
Equation 8.5 can be solved for o g for each class of release and a corresponding release limit be determined. The most conserv tive ,
release limit determined from Equations 8.1 and 8.5 will b ' jJ gcd used in selecting the appropriate alarm and trip setpoints X)f$
for,each class of release.,
C4~Jc
- { The exact settings will be selected to ensure that 10 CFR 20 l' .. limits are not exceeded. .
eca%d:nLk+b=&~0$pfd l *t*'T*"Y sJr,:A = Os 7 , . p +...t s l e J j I
.a. Ine.lsM & %. 8.1-1 e rc+peint. se fusserfsel forord. -
QUAD-CITIES
. REVISION 7 MARCR 1983 i
,;,, overage ,lo. . ate, -
<f,><sec, ,
j Initial Dilotion, stream N *" The average flow rate of the initial t .1-
>G Melaled de tha. Cilation stream which carries the g gg .
radionuclides to the unrestricted area 1ngyerfed fee &. * * * '1 '
- 1 :
I surveillance frequencies for liquid effluent monitors will be as stated in Table 4.2-3 of the Technical Specifications.
M. fCalibration methods will be consistent with the definitions 4 ,ound in section 1.0 of the Technical specifications.
5 +p4 a ca .y cal;kk M., + Lseky-J 8.2.1 Radweste Discharge Line Releases in y '
8.2.1.1 Radwaste Discharge Monitor i
The radwaste discharge line is continuously monitored for radioactivity with a gamma sensitive detector.
The monitoring channel cor.sists of a 2-inch by 2-inch sodium i
iodide-thallium activated scintillation detector, pulse pre-amplifier, and process radiation (log count) monitor. The sensing element is positioned on a vertical section of the process liquid piping. ~
The radwaste discharge monitor provides a signal to a recorder and trip auxiliary, which initiates a high radiation alarm.
The process radiation monitor, alarm, and " annunciator are located on the panels in the main control room.
t The recorder is located in the radwaste control room. -
t The process 11guld monitor has a logarithmic scale with a i
fs range of 10'1 to 10 0 i counts per second. The monitor is powered I from the station's 48/24-Vdc battery sys' tem.
8.2-2
- L Draft 1 Nsycmber 4, 1985 Pcg3 1 of 2 REVISED RESPONSES TO EG&G MAY 17, 1985 REVIEW OF QUAD CITIES ODCM SUBMITTAL 3
- r n
b d
Draft 1 Novembsr 4, 1985 Pags 2 of 2 l Comment Response
- 1. Page 7.2-1: The value of U" 1. Agree. The value has been is about one half the changed to 0.083 liters /hr Reg. Guide 1.109 value of to conform.to the Reg. Guide 7.30 Kg/yr. 1.109 value.
- 2. Page 8.1-1: f, should be 2. Disagree. Subscripting is i subscripted f6r each pathway, not necessary as the same
- i.e. f gy, f g ,, fig. composition is assumed for each release point, as
- explained in paragraph 2 of the text.
- 3. Page 8.1-2: An equation 3. Disagree. All of the gaseous should be included for the release setpoints are based setpoint. See suggested on Eqs. 8.1 and 8.2, as format. stated in the text. The procedure for applying these equations to individual monitors varies with the monitor and cannot be succinctly summarized.
- 4. Page 8.2-2: An equation 4. Disagree. All of the should be included for the liquid release setpoints are setpoint. See suggested based on Eq. 8.3, as stated format. in the text. The procedure for applying this equation to individual monitors varies with the monitor and cannot be succinctly summarized.
\
OFFSITE DOSE CALCULATION MANUAL QUAD CITIES SECTIONS 7.2 and 8.0 Revision 11 Summary of Changes to be submitted in The Monthly Operating Report Revision 11 SECTIOW/PAGE CHANGE Table 7.2-1/ UW value (water usage) has been changed to the 7.2-1 value 0.083 liters /hr upon NRC reviewer's request to provide agreement with Reg. Guide 1.109.
Table 7.2-3/ Removed old Quad North tower from data table 7.2-3 because Quad South tower is operable one.
Table 7.2-4/ There are no longer any dairy farms within 7.2-4 5 miles.
8.1.3.1 / 8.1-4 Chimney Noble Gas Monitor section has been revised to reflect current monitoring system.
Figure 8.1-1 Simplified diagram has been added to clarify release pathway.
8.2.3.1 / 8.2-2, Radwaste Discharge Monitor section has been 8.2-3 revised to reflect current monitoring methods and the new system being installed.
8.2.3.2 / 8.2-3 An indication of how allocation of waste is achieved has been added.
8.2.4.1 / 8.2-5 Service Water Ef fluent Monitors section has been revised to reflect current monitoring methods and the new system being installed.
Figure 8.2-1 Simplified diagram has been added to clarify system.
Figure 8.2-2 Simplified diagram has been added to clarify release pathway, i
i rty re 8.3-1 Simplified diagram has been added to clarify system.
i
(
- CHANGE SECTION/PAGE Table 8.4-1/ Ercire table has been revised to reflect current '
8.4-2 through 8.4-5 environmental radiological monitoring program.
Table 8.4-2/8.4-6 Reporting level table has been revised to be made consistent with Tech Specs.
Table 8.4-2/ LLD table has been revised for clarification and 8.4-7 through 8.4-9 consistency with Tech Specs.
Figure 8.4-1 Figure has been revised for clarification.
Figure 8.4-2 Figure has been revised for clarification.
Figure 8.4-3 Figure has been added to show sampling locations.
Page 2 0513/77 N
QUAD-CITIES REVISION 11 DECEMBER 1985 ODCM LIST OF TABLES FOR QUAD-CITIES SECTION 7.2 l
NUMBER TITLE PAGE 7.2-1 Aquatic Environment Dose Parameters 7.2-1 7.2-2 Annual Design Objectives Set by 10 CFR 50, Appendix I for Each Reactor 7.2-2 7.2-3 Station Characteristics 7.2-3 7.2-4 Critical Ranges 7.2-4 7.2-5 Terrain Correction Factors (ht) 7.2-5 7.2-6 X/Q and D/Q Maxima At or Beyond the Unrestricted Area Boundary 7.2-6 7.2-7 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles 7.2-6 7.2-8 Maximum Offsite Finite Plume Gamma Dose Factors for Selected Nuclides 7.2-9 i
l 7.2-i L
l QUAD-CITIES REVISION 11 o DECEMBER 1985 ODCM LIST OF FIGURES FOR QUAD-CITIES SECTION 7.2 l NUMBER TITLE 7.2-1 Unrestricted Area Boundary .
l l
l l
i 7.2-11 r - _ - . . - . _ . ___. _ _ . . _ . _ - . - . _ _ . .-_-__ - - - _ - - _ _ . _ . _ . .__ . , _ - . _ _ _ . . . _ _ _ _ _ _ .
QUAD-CITIES REVISION 11
, DECEMBER 1985 TABLE 7.2-1 ,
AQUATIC ENVIRONMENT DOSE PARAMETERS PARAMETER QUAD CITIES U", water usage, liters /hr 0.083 U,f fish consumption, kg/hr -3 2.4 x 10 1/M" l I
1/M 1 F", ft /sec 4.7 x 10 4
I 3 F , ft /sec 4.7 x 10 f
t , hr* 24 t", hr** 7.5 B.1 - Regulatory Guide 1.109, Revision 1, October 1977, Table A-1, Column 2 for freshwater fish. See Table 7.1-12.
F,t ft /sec F , ft /sec 1/M" Not applicable. No outdoor tanks y > without overflow pipes connected T , hr to other storage pipes.
t V, g,y to, hr J f
- t (hr) = 24 hr (cl1 stations) for the fish ingestion pathway
- t" (hr) = 7.5 hr (Distance to Davenport is 15 miles, flow rate of 2 m.p.h.)
7.2-1
QUAD-CITIES REVISION 11 DECEMBER 1985 TABLE 7.2-2 ANNUAL DESIGN OBJECTIVES SET BY 10 CFR 50, APPENDIX I FOR EACH REACTOR TYPE OF DOSE ANNUAL DESIGN OBJECTIVES Airborne Releases Gamma Air Dose 10 mrad Beta Air Dose 20 mrad Whole Body Dose 5 mrem Skin Dose 15 mrem Infant Thyroid Dose 15 mrem Liquid Releases -
Whole Body Dose 3 mrem Thyroid Dose 10 mrem Bone Dose 10 mren Skin Dose 10 mrem I
l 7.2-2
QUAD-CITIES REVISION 11 DECEMBER 1985 TABLE 7.2-3 STATION: Cuad-Cities Nuclear Power Station LOCATION: Cordova, Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT
- 1) Release Height = 95 m 2) Diameter = 3.35 m
~1 4.1E3 ~1
- 3) Exit Speed = 20.3 ms 4) Heat Content- KCal s CHARACTERISTICS OF VENT STACK RELEASE POINT
- 1) Release Height = 48 m 2) Diameter = 2.74 m
~1
- 3) Exit Speed = 15.3 ms .
CHARACTERISTICS OF GROUND LEVEL RELEASE
- 1) Release Height =0m
- 2) Building Factor (D) = 36 m METEOROLOGICAL DATA A 296 ft. Tower is Located 1623 m SSE of Elevated Release Point Tower Data Used in Calculations Release Point Wind Speed Differential And Direction Temperature Elevated 296 ft. 296-33 ft.
Vent 196 ft. 196-33 ft.
Ground 33 ft. 196-33 ft.
l
- 7. 2- 3
ISION 11 QUAD-CITIES DECEMBER 1985 TABLE 7.2-4 CRITICAL RANGES PRACTICAL SITE NEAREST NEAREST DAIRY FARM BOUNDARY
- RESIDENT ** RANGE ***
DIRECTION (m) (m) (m)
N 864 966 NNE 1029 1600 NE 1212 2100 ENE 1367 4600 E 1170 3700 ESE 1170 3219 SE 1189 1600 SSE 1422 1800 S 1198 1300 $
SSW 2140 4800 l
SW 1372 4600 WSW 823 3219 W 713 4000 WNW 713 4000 NW 823 3219 NNW 1481 3200
- Nearest land in unrestricted area
- Estimate range t
- Within 5 miles 7.2-4 l
1
i TABLF. 7.2-5 i TERRAIN CORRECTION FACTORS (h ) - QUAD -CITIt:S bTATIUN 1
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1 TABLE 7.2-6 X/Q AND D/Q max 1MA AT OR BEYOND INE UNRESTRICTED _ AREA _80UNDARY DOWNWIND , ELEVATED {STACMJ_ RELEASE MixE0 MODEtyENTJ_ RELEASE _ GROV40 lev _EL RELEASE M/O + RADIUS 0/QA RADIUS X/Q + D/Q A RADIUS A/Q + D/QA
~-~~~DI REC T I ON _. RADIUS (METERS) ,[SEC/M**3) (1/M**2) (METERS) (SEC/Me*3) (1/M**2)
(METERS) [SEC/M**3) (METERS) (1/M**2)
N 864. 3.359-08 R64 1.627-09 864. 1.569-06 1.050-08 864 3.785-06 2.085-08 fh NNE 1029. 4.304-08 1029 1.869-09 1029. 5.723-07 4.333-09 1029. 1.151-06 6.452-09 >
1212. 1.419-09 1212. 7.858-07 3.502-09 1212. 1.299-06 4.967-09 O NE 2800. 3.649-08 8 2000. 2.203-08 1367. 6.363-10 1367. 5.866-07 2.572-09 1367. 1.003-06 4.418-09 ENE
%J E 3219. 2.288-08 1170. 8.769-10 1170. 4.843-07 3.558-09 1170. 1.010-06 6.056-09 ()
- 2000. 3.026-08 1170. 1.317-09 1170. 7.185-07 4.754-09 1170. 1.228-06 7.493-09 F3 ESE H 1189. 1989. 1.681-06 9.041-09 I'
2800.
3.906-08 3.067-08 1189 1422.
1.428-09 8.104-10 1422.
9.715-07 5.276-07 5.298-09 2.488-09 1422. 1.108-06 4.828-09 M S 3000. 2.526-08 1198. 7.757-10 1198. 3.412-07 2.253-09 1198. 1.261-06 5.022-09 SSW 3219. 2.194-08 1024 7.054-10 1024. 2.913-07 2.639-09 1024. 1.002-06 5.535-09 Sw 654. 3.439-08 654. 9.739-10 654. 6.155-07 4.495-09 654. 2.794-06 1.168-08 494. 7.298-08 500. 1.672-09 494. 1.039-06 6.518-09 4 94. 3.338-06 1.697-08 wsw 5.717-06 2.636-08 451. 6.637-08 500. 1.729-09 451. 2.657-06 1.238-08 451.
w wNW 451. 7.002-08 500. 1.800-09 451. 5.104-06 1.824-08 451. 9.660-06 3.163-08 485. 7.614-08 500. 1.698-09 485. 5.043-06 1.490-08 485. 1.218-05 2.980-08 Nw NNW 640. 3.829-08 640. 1.335-09 640. 2.773-06 1.04f.-08 640. 5.197-06 1.810-08 QUAD-CITIES 142 SITE METEOROLOGICAL DATA 1/74 - 12/75 ts :n MM n<H f,11 H
Mo
+ Beta air, beta skin, and inhalation dose pathways. :n z A Produce and leafy vegetable pathways. Z co U1
QUAD -CITIES REVISION 11 DECEMBER 1985 TABLE 7.2-6 (Cont'd)
QUAD-CITIES 1&2 AVERAGE WIND SPEEDS FOR EACH RELEASE MODE DOWNWIND AVERAGE WIND SPEED (m/sec)
DIRECTION ELEVATED MIXED MODE GROUND LEVEL N 6.5 4.4 4.0 NNE 5.7 3.9 3.4 NE 5.8 3.7 2.9 ENE 5.8 3.9 3.5 E 6.4 4.6 4.4 ESE 6.7 4.7 4.4 SE 6.2 4.1 3.8 SSE 5.2 3.7 3.2 S 5.2 3.7 3.3 SSW 5.3 4.2 4.1 SW 5.4 4.0 3.7 WSW 4.5 3.5 3.3 W 5.7 4.0 3.7 WNW 6.1 3.7 3.4 NW 5.9 3.4 2.8 NNW 6.2 3.8 3.5 7.2-7
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TABl.E 7.2-8 OUAD-CITIES 1&2 MAXIMUM OFFSITE FINiiE PLUME GAMMA DOSE FACTORS FOR MR 83M DOWNWIND RESTRICTED ILLVATEDlST AGE) RELU$( _MLRED MODElyENTI RELEASE GROUND LEVEL RELEASE SBAR RADIUS V V8AR RADIUS G GBAR DIRECTION AREA 80UND RADIUS 5 (METERS) (METERS) (MRAD gRjf,10C M E_[_) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD]YR)/(UCI/SEC) O C
N 864 864. 4.43G-06 4.006-07 864 1.726-04 1.559-05 864 4.081-04 3.685-05 h
-J NNE 1029. 1029. 5.563-06 5.024-07 1029. 6.291-05 5.681-06 1029. 1.210-04 1.092-05 g NE 1212. 1282. 4.239-06 3.828-07 1212. 8.139-35 7.350-06 1212. 1.336-04 1.206-05 O H
$# ENE 1367. 1367. 2.259-06 2.040-07 1367. 5.986-05 5.406-06 1367. 1.019-04 9.203-06 u; E 1170. 1870. 2.396-06 2.164-07 1170. 5.173-05 4.671-06 1170.
1170.
1.048-04 9.461-06 1.149-05
[]
ESE 1170. I170. 3.347-06 3.022-07 1170. 7.541-05 6.810-06 1.272-04 m SE 1185. 1189. 4.093-06 3.696-07 1189. 1.019-04 9.200-06 1189. 1.737-04 1.568-05 u)
SSE 1422. 1422. 3.15G-06 2.850-07 14?2. 5.367-05 4.847-06 1422. 1.114-04 1.006-05 S 1198. 1198. 2.567-06 2.318-07 1191 3.656-05 3.301-06 1198. 1.298-04 1.172-05 S$w 1024 1024. 2.291-06 2.071-07 1024 3.283-D5 2.965-06 1024. 1.050-04 9.481-06 Sw 654. 654. 4.231-06 3.820-07 654. 7.185-05 6.488-06 654. 2.932-04 2.648-05 494. 494. B.240-06 7.441-07 494 1.164-04 1.051-05 494. 3.653-04 3.298-05 WSw w 451. 451. 7.616-06 6.877-07 451. 2.770-04 2.501-05 451. 5.883-04 5.313-05 WNw 451. 451. 7.837-06 7.077-07 451. 5.155-04 4.655-05 451. 9.168-04 8.279-05 Nw 485. 485. B.367-06 7.556-07 485. 4.985-04 4.501-05 405. 1.109-03 1.002-04 NNw 640. 640. 4.750-06 4.289-07 640. 2.900-04 2.6 9-05 640. 5.238-04 4.730-05 QUAD-CITIES 142 SITE METEOROLOGICAL DAT A 1/74 - 12/75 jj O<
MH T to tp H MO
- D Z H >-*
@H G3 U1
TABLE 7.2-8 (Cont'd)
OUAD-CITIES 1&2 MARIMUM,0FFSITE FI, NITE PLUME GAMMA _ DOSE FACTORS F0_R KR 85M DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE CRDUND LEVEL RELEASE
$8AR RADIU5-~ ~~ V V84R RADIUS G GBAR DIRECT !DN AREA BOUND RADIUS S (WETERS) (METERS) (MRAD /YR)/(UCI/SEC) } METERS) ,(MRAD /YR)/(UCI/SEC) (METERSL (MRAD /YR)/(UCI/SEC) ()
CO
-J N 864 864. 2.001-04 1.066-04 864. 1.192-03 6.175-04 864 2.252-03 1.158-03 >
. U kJ NNE 1029. 1029. 2.401-04 1.278-04 1029. 6.266-04 3.278-04 1029. 7.455-04 3.847-04 l NE 1212. 1212. 1.692-04 9.001-05 1212. 6.397-04 3.325-04 1212. 8.024-04 4.134-04 b H
ENE 1367. 1367. 9.321-05 4.965-05 1367. 4.656-04 2.419-04 1367. 6.447-04 3.327-04
[$ 1970. 1170. 1.134-04 6.037-05 1870. 4.396-04 2.291-04 1170. 6.585-04 3.400-04 >3 E
ESE 1170. 1t70. 1.41G-04 7.539-05 1870. 5.1158-04 3.045-04 1170. 7.905-04 4.000-04 hj SE 1189. 1189. t.772-04 9.431-05 1989. 7.843-04 4.075-04 1189. 1.097-03 5.662-04 u)
SSE 1422. 1422. 1.212-04 6.446-05 1422. 4.612-04 2.403-04 1422. 7.236-04 3.738-04 5 1198. 1198. 1.232-04 6.559-05 1998. 3.642-04 1.905-04 1198. 7.618-04 3.922-04 55w 1024. 1024, 1.326-04 7.066-05 1024. 3.430-04 1.797-04 1024 6.186-04 3.187-04 SW 654. 654. 1.973-04 1.051-04 654. 6.135-04 3.199-04 654 1.439-03 7.360-04 494 494. 3.307-04 1.760-04 494. 9.683-04 5.047-04 4 94. 1.600-03 9.210-04 wSw w 451. 451. 3.395-04 1.008-04 451. 1.668-03 8.605-04 451. 2.739-03 1.398-03 wNw 451. 451. 3.176-04 1.690-04 451. 2.666-03 1.367-03 451. 3.988-03 2.028-03 Nw 485. 485. 3.193-04 1.699-04 485. 2.597-03 1.332-03 485. 4.722-03 2.399-03 NNw 640. 640. 2.252-04 1.199-04 640. 1.659-03 8.538-04 640. 2.466-03 1.259-03 QUAD-CITIES 142 SITE METEOROLOGICAL DATA 1/74 - 12/75 e M
O H
ut H
MO
- O Z HH to F
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TABLE 7.2-8 (Cont'd)
OUAD-CITIES l&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR KR 85 DOWNWIND RESTRICTE D ELEVATED (STACM) RELEASE MINED MODElVENT) RELEASE GROUNO LEVEL RELEASE RADIUS -~ V RADIUS G GBAR DIRECTION AREA BOUND ffAlil'U5-- ~ F ~ ' SDAR VBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (3 C
B64. 864. 2.59G-06 1.607-05 864. 1.350-05 8.354-06 864. 2.484-05 1.538-05 >
-4 N E3 NNE 1029, 1029. 3.135-06 1.94, 1029. 7.378-06 4.567-06 1029. 8.309-06 5.143-06 NE 1212. 1212. 2.200-06' 1.36's 1212. 7.455-06 4.614-06 1212. 9.040-06 5.596-06 O
)# 1.224-06 7.57' 1367. 5.424-06 3.357-06 1367. 7.313-06 4.526-06 H Fa ENE 1367 1367.
Fd E 1170. 1170. 1.475-06 9.10 1170. 5.086-06 3.148-06 1170. 7.362-06 4.557-06 [
ESE 1170 1170. 1.039-0G 1.138 6 1170. 6.750-06 4.178-06 1170. 8.840-06 5.472-0f m SE 1189. 1189. 2.309-06 1.429-06 1189. 9.048-06 5.601-06 1189. 1.229-05 7.606-06 U3 SSE 1422, 1422. 1.595-06 9.074-07 1422. 5.427-06 3.360-06 1422. 8.222-06 5.090-06 S 1198. 1190. 1.616-06 1.000-06 1190. 4.296-06 2.660-06 1198. 8.551-06 5.293-06 SSw 1024. 1024 1.740-06 1.077-06 1024. 4.033-06 2.497-06 1024. 6.861-06 4.247-06 SW 654 654 2.564-06 1.587-06 654. 7.098-06 4.394-06 654. 1.575-05 9.750-06 WSW 494 494 4.303-06 2.664-06 494. 1.124-05 6.955-06 4 94. 1.960-05 1.213-05 w 451. 451 4.446-06 2.752-06 451. 1.880-05 1.164-05 451. 2.973-05 1.841-05 WNw 451. 451. 4.163-06 2.577-06 451. 2.961-05 1.833-05 451. 4.328-65 2.679-05 Nw 485. 485. 4.160-06 2.575-06 485. 2.891-05 1.790-05 485. 5.130-05 3.175-05 NNd 640. 640. 2.919-06 1.807-06 640. 1.060-05 1.151-05 640. 2.697-05 1.669-05 QUAD-CITIES 142 SITE METEOROLOGICAL DATA 1/74 - 12/75 ty y MM O <l H
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'*)Fb
i TABLE 7.2-8 (Cont'd)
QUAL >-CITIES 1&2 MAXIMUM OFFSITE FINITE PLUME _ GAMMA _ DOSE _FA_CTORS FOR MR 88 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MINED MODEiVENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND WADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) JMRAD/YR)/(UCI[SEC), (METERS) (MRAD /YR)/(UCI/SEC) (METERS) { MRAD /YR)/(UCI/SEC) ()
C*
-J
. N 864 864. 2.135-03 1.647-03 864. 9.137-03 6.971-03 864 1.636-02 1.244-02 >
bJ NNE 1029. 1029. 2.535-03 1.956-03 1029. 5.143-03 3.930-03 1029. 5.449-03 4.149-03 I NE 1212. 1212. 1.764-03 1.361-03 1212. 4.977-03 3.802-03 1282. 5.803-03 4.416-03 m 1367. 1367. 9.697-04 7.478-04 1367. 3.550-03 2.710-03 1367. 4.669-03 3.555-03 H b$ ENE 1870. 1170. 1.193-03 9.200-04 1970. 3.454-03 2.640-0J 1970. 4.797-03 3.652-03 8 E
ESE 1170. 1970. 1.484-03 1.145-03 117C. 4.541-03 3.468-03 1970.
1189.
5.762-03 7.984-03 4.387-03 6.079-03 SE 1189. 1189. 1.852-03 1.428-03 1189. 6.050-03 4.619-03 U)
SSE 1422. 1422. 1.252-03 9.654-04 1422. 3.598-03 2.750-03 1422. 5.247-03 3.996-03 S 1198. 1998, t.290-03 9.947-04 1998. 2.952-03 2.260-03 1998. 5.496-03 4.182-03 SSW 1024 1024. t.407-03 1.086-03 1024. 2.825-03 2.163-03 1024 4.488-03 3.415-03 SW 654 654, 2.101-03 1.622-03 654. 4.995-03 3.821-03 654 1.040-02 7.900-03 WSW 494 494. 3.541-03 2.738-03 494. 8.043-03 6.154-03 494 1.311-02 9.965-03 W 451. 451. 3.672-03 2.833-03 451. 1.304-02 9.942-03 451. 1.986-02 1.508-02 WNw 451. 451. 3.433-03 2.648-03 451, 2.012-02 1.531-02 451 2.878-02 2.184-02 NW 485. 485. 3.442-03 2.656-03 485. 1.963-02 1.494-02 485. 3.396-02 2.576-02 NNW 640. 640. 2.407-03 1.857-03 640. 1.256-02 9.568-03 840. 1.777-02 1.349-02 QUAD-CITIES 142 SITE METEOROLOGICAL DATA 1/74 - 12/75 ty m m tis O<
MM
- E U2 tD H MO 00 Z HH cH CD U1
TABLE 7.2-8 (Cont'd) 4 OU AD -C TTI F.S 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR MR 89 DOWNWIND RESTRICTED . E L EV A T ED ( S T_ACM ) RELEA_S( MIKED MODE 1VINTJ_ RELEASE __ GROUND LEVEL RELEASE S S8AR RADIUS V VBAR RADIUS G GBAR DIRECT !DN ARE A BOUND RADIUS (METERS) (METERS) (MAAD/YR)/(UCI/SEC) (METERS), (MRAD /YR)/(UCI/SE.C), (METERS) JMRAD[YR)/(UCI/SEC) {3
.' N 864 864 8.056-04 5.943-04 864. 2.160-03 1.576-03 864. 3.780-03 2.753-03 $
bJ NNE 1029. 1029. 6.806-04 5.020-04 1029. 8.818-04 6.449-04 1029. 8.991-04 6.552-04 e 5
1212. 4.057-04 1212. 5.668-04 4.130-04 O 1212. 1212. 4.23G-04 3.124-04 5.550-04 1
$[
NE ENE 1367. 1367. 2.140-04 1.57R-04 1367. 3.773-04 2.755-04 1367. 4.751-04 3.462-04 y E 1170. 1170. 3.4RG-04 2.571-04 1170. 6.405-04 4.677-04 1170. 8.439-04 6.148-04 H 1170. 1170. 4.631-04 3.415-04 1170. 8.0'.5-04 5.882-04 1170. 1.025-03 7.469-04 M ESE M SE 1989. 1189. 5.01S-04 3.69H-04 1189. 9.150-04 6.687-04 1189. 1.259-03 9.173-04 SSE 1422. 1422. 2.346-04 1.729-04 1422. 3.G97-04 2.702-04 1422. 5.091-04 3.709-04 5 1190. 1190, 2.75H-04 2.034-04 1198. 4.251-04 3.107-04 1198. 6.592-04 4.802-04 SSW 1024 1024, 3.404-04 2.511-04 1024. 5.820-04 4.253-04 1024. 8.797-04 6.408-04 SW 654 654. 7.494-04 5.520-04 654. 1.365-03 9.976-04 654. 2.595-03 1.890-03 WSw 494 494 1.414-03 1.043-03 494. 2.503-03 1.830-03 494. 4.276-03 3.114-03 w 451. 451. 1.745-03 1.287-03 451. 4.334-03 3.164-03 451. 6.959-03 5.067-03 WNw 451. 451. 1.C30-03 l.202-03 451. 5.883-03 4.291-03 451. 8.959-03 6.523-03 Nw 485. 485. 1.535-03 1.132-03 485. 4.917-03 3.5b8-03 485. 8.718-03 6.347-03 NNw 640. 640. 9.993-04 7.372-04 640. 2.760-03 2.014-03 640. 4.153-03 3.024-03 QUAD-CITIES 142 SITE METEOROLOGICAL DATA 1/74 - 12/75 ty y MM O<
H t,n H
MO
- O Z
>*H
@H CD (D
l TABLE 7.2-8 (Cont'd)
OUAD--C ITI ES 1&2 MARIMUM OF FSITE F INI TI PLUME GAMMA DOSE FACTORS FOR WR 90 DDWNWIND RESTRICTED ELEVATED (STACM) RE1. EASE M1AED MODE (VENT) RELEASE GROUNO LEVEL RELEASE 584R RACIUS V V84R RADIUS G G8AR DIRECTIDN AREA BOUND RADlus S (MESERS) (METERS) (MRAD /YR)/(UCl/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (WE T E RS) (MRAD /vR)/(UCI/SEC) ()
C'
-J N BG4 864. 1.015-04 7.277-05 864. 1.480-04 1.047-04 8 64. 1.835-04 1.295-04 >
1029. 2.365-05 1.669-05 U kJ NNE 1029. 1029. 5.079-05 3.641-05 1029. 3.336-05 2.365-05
[, NE 1212. 1212. 2.263-05 1.622-05 1212. 1.122-05 7.957-06 1212. 5.414-06 3.823-06 b (p ENE 1367. 1367. 8.713-06 6.242-06 1367. 7.049-06 4.989-06 1367. 6.174-06 4.360-06 H 1.718-05 1170. 2.571-05 1.819-05 1170. 2.491-05 1.759-05 63 E 1170. 1170. 2.397-05 ESE 1170. 1170. 3.671-05 2.630-05 1170. 3.368-05 2.383-05 1170. 3.320-05 2.343-05 hj SE 1189. 1189. 3.289-05 2.354-05 1189. 2.564-05 1.815-05 1189. 2.389-05 1.687-05 m SSE 1422. 1422. 6.624-06 4.744-06 1422. 4.173-06 2.957-06 1422. 3.379-06 2.387-06 S 1198. 1 98. 1.289-05 9.233-06 1198. 9.167-06 6.494-06 1198. 8.062-06 5.692-06 SSw 1024 1024. 2.230-05 1.598-05 1024. 2.678-05 1.895-05 1024 3.068-05 2.166-05 Sw 654 654 1.085-04 7.776-05 654. 1.430-04 1.012-04 654. 1.925-04 1.358-04 wsw 494. 494 2.325-04 1.666-04 494 3.155-04 2.237-04 4 94. 4.241-04 2.992-04 w 451. 451. 4.430-04 3 175-04 451. 7.115-04 5.036-04 451. 8.884-04 6.270-04 wNw 451. 451. 4.456-04 3.194-04 451. 7.985-04 5.648-04 451. 9.518-04 6.715-04 485. 485. 3.687-04 2.644-04 485. 5.259-04 3.722-04 4 95. 6.338-04 4.470-04 Nw NNw 640. 640. 1.869-04 1.340-04 640. 2.602-04 1.841-04 640. 2.887-04 2.036-04 OW Quad-CI7IES 142 SITE METEOROLOGICAL DATA 1/74 - 12/75 nE MH 2 (n 6H MO WZ HW ww CD US
3 TABLE 7.2-8 (Cont'd)
QUAD-CITIES 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE131M DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S 58AR RADIUS V VBAR RADIUS G G8AR (WETERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) ()
C
-J N 864. 864. 7.856-06 2.614-06 864 1.679-04 2.624-05 864. 3.832-04 5.531-05 >
pg NNE 1029. 1029. 9.733-06 3.179-06 1029. 6.641-05 1.193-05 1029. 1.168-04 1.748-05 f p NE 1282. 1212. 7.163-06 2.273-06 1212. 8.439-05 1.369-05 1212. 1.318-04 1.943-05 r3 Fs ENE 1367. 1367. 3.90.1-06 1.252-06 1367. 6.241-05 1.007-05 1367. 1.018-04 1.527-05 H cn 1170. 1170. 4.399-06 1.483-06 1170. 5.307-05 8.942-06 1170. 1.018-04 1.533-05 >3 E
ESE 1170. 1170. 5.762-06 1.874-06 1170. 7.659-05 1.244-05 1170. 1.236-04 1.852-05 y SE 1189. 1189. 7.100-06 2.348-06 1189. 1.039-04 1.679-05 1189. 1.695-04 2.554-05 u3 SSE 1422. 1422. 5.280-06 1.649-06 1422. 5.711-05 9.571-06 1422. 1.120-04 1.695-05 s 1198. 1198. 4.792-06 1.620-06 1998. 3.897-05 6.984-06 1198. 1.270-04 1.859-05 SSw 1024 1024 4.744-06 1.703-06 1024. 3.457-05 6.363-06 1024. 1.004-04 1.480-05 Sw 654. 654. 7.621-06 2.564-06 654. 7.147-05 1.217-05 654 2.691-04 3.740-05 WSw 494 494. 1.360-05 4.359-06 494. 1.144-04 1.930-05 4 94 3.309-04 4.619-05 w 451. 451. 1.325-05 4.404-06 451. 2.578-04 3.854-05 451. 5.281-04 7.239-05 WNw 451. 451. 1.295-05 4.169-06 451. 4.716-04 6.683-05 451. 8.198-04 1.099-04 Nw 485. 485. 1.344-05 4.232-06 485. 4.588-04 6.511-05 405. 9.954-04 1.324-04 NNw 640. 640. 8.598-06 2.912-06 640. 2.731-04 3.992-05 640. 4.793-04 6.570-05 QUAD-CITIES 182 SITE MF.EOROLOGICAL DATA 1/74 - 12/75 h h!
n <:
MH fwHU1 MO
- x! Z HH
@H CD U1
TABLE 7.2-8 (Cont'd)
QUAD-CITIES 1&2 s
MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE133M DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIU5 G GUAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) '("F7ERS) (MRAD /vR)/(UCI/SEC) <>
-J N 864. 864. 3.220-05 1.557-05 864. 3.141-04 1.020-04 864. 6.591-04 1.072-04 hh NNE 1029. 1029, 3.913-05 1.8n3-05 1029. 1.437-04 5.239-05 1029. 2.007-04 6.491-05 t; 1212.
I'Fa NE 1212.
1367.
1212.
1367.
2.794-05 1.534-05 1.333-05 7.367-06 1212.
1367.
1.640-04 1.206-04 5.514-05 4.034-05 1367.
2.315-04 1.821-04 7.088-05 5.677-05 I
fl
-J ENE E 1170. 1170. 1.826-05 0.866-06 1170. 1.074-04 3.726-05 1170. 1.831-04 5.730-05 y ESE 1170. 1170. 2.307-05 1.109-05 1170. 1.490-04 5.013-05 1170. 2.211-04 6.889-05 s 1189. 1189. 2.889-05 1.390-05 1189. 2.011-04 6.735-05 1189. 3.049-04 9.554-05 M SE U1 SSE 1422. 1422. 2.025-05 9.614-06 1422. 1.148-04 3.966-05 1422. 2.022-04 6.362-05
$ 1198. 9198. 1.995-05 9.692-06 1198. 8.410-05 3.061-05 1190. 2.214-04 6.729-05 SSw 1024. 1024. 2.100-05 1.037-05 1024. 7.677-05 2.847-05 1024. 1.765-04 5.402-05 SW 654. 654. 3.160-05 1.533-05 654. 1.463-04 5.121-05 654. 4.449-04 1.273-04 WSW 494. 494 5.367-05 2.568-05 494. 2.321-04 8.067-05 494. 5.497-04 1.581-04 w 451. 451. 5.428-05 2.625-05 451. 4.605-04 1.431-04 451. 8.607-04 2.421-04 wNw 451 451. 5.134-05 2.460-05 451. 7.960-04 2.332-04 451. 1.305-03 3.564-04 Nw 485. 485. 5.208-05 2.479-05 485. 7.754-04 2.275-04 485. 1.571-03 4.246-04 NNw 640. 640. 3.590-05 1.745-05 640. 4.761-04 1.444-04 640. 7.807-04 2.196-04 QUAD-CI71ES 142 SITE METEOROLOGICAL DATA 1/74 - 12/75 hh O<
H U)
H to O 0Z He.
@W G3 LTI
TABLE 7.2-8 (Cont'd)
QUAD-CITIES 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE133 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MINED MODE (VENT) RELEASE ~ GROUNO LEVEL RELEASE
$8AR RADIUS V V8AR PADIUS G G6AR DIRECTION AREA BOUND RADIUS S (METERSI (METERS) (MRAD /YR)/lUCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) O d 864 864. 3.323-05 1.26A-05 864 3.515-04 1.056-04 864. 7.318-04 2.092-04 C kJ N
NNE 1029. 1029. 4.043-05 1.538-05 1029. 1.619-04 5.209-05 1029. 2.347-04 6.892-05 y i NE 1212. 1212. 2.900-05 1.100-05 1212. 1.840-04 5.641-05 1212. 2.597-04 7.550-05 h" ENE 1367. 1367. 1. 60 'J - 0 5 6.101-06 1367. 1.361-04 4.167-05 1367. 2.053-04 6.041-05 [3 1170. H U'
E 1170. 1170. 1.R82-05 7.204-06 1170. 1.214-04 3.800-05 2.069-04 6.110-05 ESE 1170. 1170. 2.390-05 9.085-06 1170. 1.677-04 5.149-05 1170. 2.494-04 7.343-05 [
SE 1189. 1189. 2.995-05 1.140-05 1189. 2.263-04 6.928-05 1189. 3.447-04 1.018-04 m SSE 1422. 1422. 2.128-05 8.026-06 1422. 1.294-04 4.035-05 1422. 2.285-04 6.766-05 u)
S 1196. 1198. 2.059-05 7.887-06 1198. 9.490-05 3.053-05 1190. 2.481-04 7.179-05 SSw 1024 1024. 2.148-05 0.319-06 1024 8.670-05 2.821-05 1024. 1.977-04 5.746-05 654 654. 3.239-05 1.238-05 654 1.635-04 5.127-05 654. 4.873-04 1.351-04 SW 494 494. 5.596-05 2.121-05 494 2.566-04 7.985-05 4 94 6.018-04 1.673-04 wsw w 451. 451. 5.613-05 2.143-05 451. 5.031 04 1.460-04 451. 9.354-04 2.559-04 wNw 451. 451. 5.329-05 2.022-05 451 8.636-04 2.415-04 451. 1.403-03 3.755-04 Nw 485. 485. 5.444-05 2.056-05 485. 8.414-04 2.355-04 485. 1.683-03 4.469-04 NNw 640. 640. 3.675-05 1.407-05 640. 5.222-04 1.497-04 640. 8.494-64 2.325-04 i
OUAD-CITIES 142 SITE METEOROLOGICAL DATA 1/74 - 12'/75 g n<
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- r U1 fy H tn O lO Z ww W bd CD U1
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TABLE 7.2-8 (Cont'd) 4 QUAD-CITIES 1&2 MAXIMUM OFFSITE FsNITE PLUME GAMMA DOSE FACTORS FOR XE135 ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUM9 LEVEL RELEASE DOWNWIND RESTRICTED G G8AR S SBAR RADIUS V VBAR RADIUS DIRECTION AREA 800ND RADIUS (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /VR)/(UCI/SEC) ()
C 864. 864. 2.814-04 1.522-04 864. 1.627-03 8.738-04 864. 3.046-03 1.633-03 >
[d N 1029, 3.387-04 1.831-04 1029. 8.676-04 4.670-04 1029. 1.015-03 5.448-04 f b) NNE 1029.
8 NE 1212. 1212. 2.389-04 1.291-04 1212. 8.843-04 4.753-04 1212. 1.097-03 5.886-04 o 1367. 6.446-04 3.464-04 1367. 8.644-04 4.746-04 H bJ ENE 1367. 1367. 1.320-04 7.135-05 4 c) E 1170. 1170. 1.590-04 8.643-05 1170. 6.063-04 3.260-04 1170. 8.982-04 4.820-04 1170. 1970 1.995-04 1.078-04 1970. 8.064-04 4.334-04 1170. 1.078-03 5.784-04 hj ESE SE 1189. 1989. 2.499-04 1.351-04 1189. 1.081-03 5.007-04 1189. 1.497-03 8.034-04 m SSE 1422. 1422. 1.717-04 9.281-05 1422. 6.407-04 3.445-04 1422. 9.941-04 5.335-04 S 1198. 1198. 1.74J-04 9.424-05 1198. 5.054-04 2.720-04 1198. 1.040-03 5.576-04 1024 1.874-04 1.014-04 1024. 4.747-04 2.556-04 1024. 8.404-04 4.507-04 SSw 1024.
Sw 654 654, 2.773-04 1.499-04 654. 8.413-04 4.525-04 654. 1.934-03 1.036-03 wSW 494 494. 4.630-04 2.508-04 494. 1.325-03 7.127-04 494. 2.413-03 1.292-03 451. 451. 4.760-04 2.575-04 451. 2.257-03 1.211-03 451. 3.660-03 1.959-03
- w. 1.922-03 451. 5.316-03 2.844-03 WNw 451. 451. 4.452-04 2.408-04 451. 3.587-03 Nw 485. 485. 4.475-04 2.420-04 485. 3.499-03 1.875-03 405. 6.296-03 3.367-03 NNW 640. 640. 3.161-04 4.709-04 640. 2.247-03 1.205-03 640. 3.309-03 1.771-03 O Al MM QUAD-CITIES 182 SITE METEOROLOGICAL DATA 1/74 - 12/75 o<
pH 5W to H MO
- O Z HH
@W CD U1
4 TABLE 7.2-8 (Cont'd)
QUAD-CITIES 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR RE137 ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUNO LEVFL SELEASE DOWNWIND RESTRICTED G GUAR DIRECTION AREA BOUND RADIU5 5 58AR RADIUS V VSAR RADIUS (METERS) (METERS) (MRAD /YR)/(UCl/SEC) (METERS) (MRAD /VR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC)
()
C
%J N 864. 864. 1.103-04 7.148-05 864. 3.458-04 2.226-04 864. 6.269-04 4.031-04 $
- NNE 1029. 1029. 9.706-05 6.286-05 1029. 1.429-04 9.211-05 1029. 1.551-04 9.976-05 g h3 1212, 1212. 6.142-05 3.977-05 1212. 9.384-05 6.046-05 1212. 1.041-G4 6.693-05 0 NE H 1
1367. 1367. 3.14G-05 2.037-05 1367. 6.455-05 4.156-05 1367. 8.642-05 5.557-05 ENE 1
[3 ps E 1170. 1870. 4.952-05 3.206-05 1870. 1.038-04 6.686-05 1170. 1.438-04 9.247-05 1.739-04 1.119-04 h
ESE 1170, 1170. 6.53H-05 4.233-05 1970. 1.306-04 8.411-05 1170. pg i 1189.
SE 1889. 1189. 7.175-05 4.646-05 1189. 1.515-04 9.758-05 2.184-04 1.404-04 U3 SSE 1422. 1422. 3.533-05 2.287-05 1422. 6.340-05 4.084-05 1422. 9.355-05 6.016-05 5 1198. 1898. 4.051-05 2.623-05 1198. 7.053-05 4.545-05 1190. 1.176-04 7.561-05 1024. 1024 4.912-05 3.181-05 1024. 9.325-05 6.007-05 1024. 1.483-04 9.534-C3 i SSw Sw 654 654. 1.03H-04 6.723-05 654. 2.145-04 1.382-04 654. 4.306-04 2.768-04 '
WSw 494. 494 1.944-04 1.259-04 494. 3.884-04 2 503-04 494. 6.907-04 4.441-04 451. 2.344-04 1.518-04 451. 6.798-04 4.377-04 451. 1.11F-03 7.175-04 w 451.
t 4 wNw 451. 451. 2.191-04 1.419-04 451. 9.533-04 6.133-04 451. 1.467-03 9.426-04 NW 485. 485. 2.071-04 1.341-04 465. 8.128-04 5 230-04 485. 1.471-03 9.457-04 NNW 640. 640. 1.355-04 .n.779-05 640. 4.535-04 2.918-04 640. S.983-04 4.476-04 i
i ty 33 QUAD-CITIES 142 SITE METEOROLOGICAL DATA 1/74 - 12/75 MM O<
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00AD-CITIES REVISION 11 DECEMBER 1985 8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS, MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMENTAL RADIOLOGICAL MONITORING TABLE OF CONTENTS PAGE 8.1 GASEOUS RELEASES 8.1-1 8.1.1 System Design 8.1-1 8.1.1.1 Gaseous Radwaste Treatment System 8.1-1 l 8.1.2 Alarm and Trip Setpoints 8.1-1 8.1.3 Main Chimney Releases 8.1-3 8.1.3.1 Chimney Noble Gas Monitors 8.1-3 8.1.3.2 SJAE Off-Gas Monitors 8.1-5 l 8.1.3.3 Allocation of Effluents from Common Release Points 3.1-6 l 8.1.4 Reactor Building Ventilation Stack Releases 8.1-7 8.1.4.1 Ventilation Stack Monitors 8.1-7 8.1.4.2 Allocation of Effluents from Common Release Points 8.1-E 8.1.5 Symbols Used in Section 8.1 8.1-9 8.1.6 Constants Uced in Section 8.1 8.1-11 8.2 LIQUID RELEASES 8.2.1 8.2.1 System Design 8.2-1 8.2.2 Alarm Setpoints 8.2-1 8.2.3 Radwaste Discharge Line Releases 8.2-2 8.2.3.1 Radwaste Discharge Monitor 8.2-2 8.2.3.2 Allocation of Effluents from Common Release Points 8.2-3 8.2.3.3 Administrative and Procedural Controls for Radwaste Discharges 8.2-4 8.2.4 Service Water Header Releases 8.2-5 8.2.4.1 Service Water Effluent Monitors 8.2-5 8.2.5 Determination of Initial Dilution Stream Flow Rates 8.2-6 8.2.6 Symbols Used in Section 8.2 8.2-7 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM 8.3-1 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING 8.4-1 8-i
QUAD-CITIES REVISION 11
, DECEMBER 1985 ODCM LIST OF TABLES FOR QUAD-CITIES SECTION 8.0 l NUMBER TITLE PAGE 8.4-1 Radiological Monitoring Program 8.4-2 8.4-2 Reporting Levels For Radioactivity Concentrations In Environmental Samples 8.4-6 8.4-3 Maximum Values For The Lower Limits of Detection (LLD) 8.4-7 9
8-1i L
QUAD-CITIES REVISION 11 DECEMBER 1985 1
ODCM LIST OF FIGURES FOR QUAD-CITIES SECTION 8.0 l NUMBER TITLE 8.1-1 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram 3.2-1 Simplified Liquid Radwaste Processing Diagram 8.2-2 Simplified Liquid Effluent Flow Diagram 8.3-1 Simplified Solid Radwaste Processing Diagram 8.4-1 Fixed Air Sampling Sites and Outer Ring TLD Locations 8.4-2 Inner Ring TLD Locations 8.4-3 Milk, Fish, Water and Sediment Sample Locations l 8-iii
, QUAD-CITIES REVISION 11 DECEMBER 1985 8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS, MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMENTAL RADIOLOGICAL MONITORING 8.1 GASEOUS RELEASES 8.1.1 System Design A simplified gaseous radwaste and gaseous effluent flow diagram is provided in Figure 8.1-1.
8.1.1.1 Gaseous Radwaste Treatment System A gaseous radwaste treatment system shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off-gases from the primary system and pro-viding for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
8.1.2 Alarm and Trip Setpoints Alarm and trip setpoints of gaseous effluent monitors at the principal points of release of ventilation exhaust air containing radioactivity are established to ensure that the relcase limits
, of 10 CFR 20 are not exceeded. The setpoints are found by solving Equations 2.6 and 2.7 for each class of release.
}
For this evaluation the radioactivity mixture in the exhaust air is assumed to have the composition of gases listed in Table 3-3 from " Technical Derivation of BWR 1971 Design Basis Radioactive Material Source Terms", NEDO-10871, March 1973, General Electric Company. This mixture of radioactive gases is representative of the activity found at the point of release from the fuel with no radioactive decay accounted for.
8.1-1
. _ _. _ ._ _ _ __ _ _ ._. - - . . ~-
QUAD-CITIES REVISION 11
, DECEMBER 1985 Equation 2.6 is rewritten using the fractional composition of l each nuclide, f , and a total release rate, Q , f r each class:
i t 1.11 O ts I81*f) &Oty(Vg i
xf)i <500 (8.1) f f
Fractional Radionuclide Composition The release rate of radionuclide i divided by the total release of all radionuclides.
O ts Total Release Rate, Stack Release (pCi/sec)
The release rate for all radionuclides due to a stack release'.
Q tv Total Release Rate, Vent Release (pCi/sec)
The release rate for all radionuclides due to a vent release.
Equation 8.1 can be solved for Q t for each class of release for release limit determinations. ,
Similarly, Equation 2.7 can be rewritten: l
~
}" L] i_ ~ -
(X/Q) Q tssi **PI-A R/3600us) f i
+
IX/0)v O tv f i **EI~ A iR/3600uy) -
1 vO (6.2)
+ 1.11 "S gQ ts fi itvff<3000"["
y
.)
Equation 8.2 can be solved for Q t f r each class of release and a corresponding release limit be determined. The most conservative t release limit determined from Equations 8.1 and 8.2 will be I
j used in selecting the appropriate alarm and trip setpoints for each class of release.
i The exact settings will be selected to ensure that 10 CFR 20 limits are not exceeded.
- 8.1- 2 l
-e . - - - - - . - , -e e -,,--w - ---->m y.---w.< ,,w. r - - - - --
=-
1
{
QUAD-CITIES REVISION 11 )
. DECEMBER 1985 l l
Surveillance frequencies for gaseous effluent monitors will be as stated in Table 4.2-4 of the Technical Specifica'tions.
Calibration methods will be consistent with the definitions found in Section 1.0 of the Technical Specifications.
8.1.3 Main Chimney Releases 8.1.3.1 Chimney Noble Gas Monitors Releases of radioactive noble gases from the main chimney release point are continuously monitored by a General Electric (GE) off-line monitoring system consisting of two instrument channels, each of which uses a scintillation detector as its sensing element. Samples of the effluent stream are taken high in the chimney, where good mixing is ensured, and drawn through a constant flow-and-pump network, past the detectors.
The detector equipment part numbers are RE 1/2-1731A and RE 1/2-1731B.
Each. monitoring channel consists of a 2-inch by 2-inch sodium iodide thallium activated scintillation detector, shieldec l sample chamber, pulse preamplifier, and process radiation (log count) monitor with integral power supply for providing high voltage to the detector. The channels share a common recorder and common trip auxiliaries unit whose output initiate high radiation alarm annunciations. The recorder, alarms, and remote contro] switches for the chimney gas monitoring system are located in the main control room.
The monitor display has a logarithmic scale with a range of
-1 6 10 to 10 counts per second.
! 8.1-3
. QUAD-CITIES REVISION 11 DECEMBER 1985 In addition to the GE noble gas monitors, the gas sample is ,
routed through a filter paper on which particulates are deposited, through a charcoal cartridge which traps the iodines, and through Eberline low and medium range noble gas detectors.
Under accident conditions, the above pathway can be bypassed and the sample routed through an Eberline/Victoreen system which has an Eberline high range noble gas monitor and a victoreen postaccident particulate and iodine sampler.
The Eberline low and medium range noble gas detectors view the same volume, while the Eberline high range noble gas detector views externally a section of one inch stainless steel tubing as its sample volume. The low range.is monitored by a beta scintillation detector (Eberline Model RDA-3A),
while both the medium and high range measurements are performed by an energy-compensated GM detector. Background subtraction is provided for all three ranges. Sample flow is provided by a stainless steel diaphragm vacuum pump and an air flow regulator. Sample flow is set to insure isokinetic sampling i monitored by a solid-state flow sensor.
The three Eberline noble gas detectors are part of a microprocessor-j controlled gaseous effluent monitoring system (Eberline SPING-4).
The monitoring system's control terminal, strip chart recorder !
i panel 912-1 and annunciating panel 912-4 are located in the I I
j control room on Panel 912-1. The control terminal provides immediate access to current detector activity, operating parameters, and history files for any detector. Changes in
(
l detector operational status are automatically printed and audibly acknowledged. The SPING-4 microprocessor's memory has battery backup to maintain all operating parameters and history files for any detector in the event of a system power loss.
8.1-4
m QUAD-CITIES REVISION 11 DECEMBER 1985 For all of the above monitors, the sample pumps and datectors, with local controls,'are located in the chimney sample house ;
at the base of the chimney. Power is supplied to the process radiation monitors from the station 48/24-Vdc battery systems. ,
The main chimney noble gas monitor alarm setpoints will be selected to ensure that the combined release rate of the main chimney and the reactor building vent stack does not exceed the most conservative release limit determined from Equations 8.1 and 8.2.
'l 8.1.3.2 SJAE Off-Gas Monitors The major source of radioactive noble gases is from each unit's off-gas system. Each unit's off-gas system has its own radia-tion detection instrumentation capable of isolating the off-gas release pathway.
Off-gas from the main condenser is monitored for gross gamma activity downstream of the steam jet air ejectors (SJAE) and prior to release to the main chimney. Continuous radiation monitoring is maintained on the off gas hold-up pipe. The off-gas mon-l' itoring system for each unit is performed in two channels, i
- each of which includes a gamma sensitive ion-chamber detector, l and a logarithmic radiation monitor with integral power supply.
The two channels share a common two-pen recorder and a trip auxiliaries unit whose outptt feeds an interval timer. System l
! controls, alarm annunciators, recorder, and dicplays are located
! on panels in the main control rcom. The ion-chamber detectors are mounted adjacent to and at the beginning of the off-gas ,
hold-up pipe, a 36-inch diameter header whose function is f to contain the off-gas for a period of time dependent on off-gas flow and allow for radioactive decay prior to release to the chimney.
l 8.1-5 1
,-,-,,m,,~.-.. n-,.. , . , - - , . - - , , , . . , , . , - , . - - - . . , - . , - , - , . - - . . . ~ . , , , . . . - . , . _ - - _ . . - - - - . - . - - , . . - - - - - - , - . . . - -
QUAD-CITIES REVISION 11 DECEMBER 1985 A high radiation condition in the hold-up pipe will initiate an interval timer with a variable setting of 0 to 15 minutes.
When the preselected time interval has elapsed, an isolation valve at the inlet to the chimney from the off-gas system will automatically close, preventing release of radioactive gases from the affected off-gas system.
Power is supplied to the off-gas process radiation monitors from the station's 48/24-Vdc battery systems. Power to tne interval timer is from the 120-Vac essential service bus.
The timer provides the signal to the solenoid-operated valves which control the air supply to the air-operated isolation valve (equipment part number A0 1(2)-5406) . The monitor display is a logarithmic scale and has a range of 1 to 10 6 units (mR/hr).
The detectors equipment part numbers are RE 1(2)-1733A and RE 1(2)-1733B.
The SJAE monitor alarm setpoints will be selected to ensure that the combined release rate of the main chimney and station vent stack does not exceed the most conservative release limit determined from Equations 8.1 and 8.2.
l 8.1.3.3 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the main chimney are comprised of contributions from both units. Under normal operating conditions, it is difficult to allocate the radio-activity between units due to fuel performance, in-plant leakage, power history, and other variables. Consequently, allocation wi31 normally be made evenly between the units. During extended unit shutdowns or periods of known differences, the apportionment will be adjusted accordingly. The allocation of the effluents will be made on a monthly basis.
8.1-6
QUAD-CITIES REVISION 11 DECEMBER 1985 8.1.4 Reactor Building Ventilation Stack Releases 8.1.4.1 Ventilation Stack Monitors Leleases of radioactive noble gases from each reactor building's ventilation system are monitored prior to introduction to the ventilation stack. Two sensor and converter (detector) units are located in each unit's reactor building exhaust duct, and provide continuous gamma radiation monitoring.
The sensor is a Geiger-Mueller tube, polarized by high voltage from the power supply. The output signal from each sensor converter is applied to an indicator and trip unit, where it is amplified and used to drive a meter. This unit also provides trip functions for upscale and downscale alarms through auxiliary units. A downscale trip in either channel annunciates a low radiation (malfunction) alarm. An upscale trip in either channel initiates a reactor building ventilation system high-high radiation alarm. Control logic is such that one channel high level trip or two channel low level trips will shut down and isolate the reactor building ventilation system for both units and initiate the standby gas treatment systea.
The exhaust duct monitors provide a signal to a two pen recorder which will annunciate a high radiation condition in the exhaust duct. This is an alarm only, and does not initiate corrective action. The recorder, controls, indicator and trip units, alarms, and annunciators are located on panels in the main control room.
The power supply to each sensor channel is supplied from a different power source. The A channel is fed from the 120-Vac.
A reactor protection system and the B channel are fed from the 120-Vac B reactor protection system.
8.1-7
QUAD-CITIES REVISION 11 DECEMBER 1985 The indicating meters have a logarithmic scale with a range of 0.01 to 100 mR/hr. The sensor and converter units have equipment part numbers RE 1(2)-1735A and RE 1(2)-1735B.
Each reactor building's ventilation System is isolated by closure of two air-operated butterfl, valves (A0 1(2)A-5741 and A0 1(2)B-5741) located in series downstream of the reactor building ventilation supply fans, and by closure of two air-operated butterfly valves (A0 1(2) A-5742 and A0 1(2)B-5742) located in series downstream of the radiation sensors and up-stream of the exhaust fans. Air supplies to these valves are controlled by solenoid valves powered from the 125-Vdc station battery systems. The control logic relays which operate these solenoids are powered by the 120-Vac essential service bus.
The reactor building ventilation stack monitor alarm setpoint will be 2 mR/hr above background. Using an empirical relationship of mR/hr and u/Ci/sec at design flowrates, the calculated reactor building ventilation stack release rate will be employed in Equation 6.1 and 8.2 to select the most conservative main chimney monitor alarm setpoints.
8.1.4.2 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the reactor building vent stack are comprised of contributions from both units. Estimater of noble gas contributions from each unit will be made by analyzing grab samples from the individual units. Allocations of radioiodine and radioactive particulate releases will be made by analyzing samples taken from continuous samples on each unit. The allocation of the effluents will be made on a monthly basis.
8.1-8
QUAD-CITIES REVISION 11
- DECEMBER 1985 8.1.5 Symbols Used in Section 8.1 SYMBOL NAME UNIT Q ts Total Release Rate, Stack Release (pCi/sec)
S Gamma Whole Body Dose Constant, Stack (arad/yr per t
Release pCi/sec) fg Fractional Radionuclide Composition O tv Total Release Rate, Vent Release (pCi/sec)
V Gamma Whole Body Dose Constant, (mrad /yr per Vent Release pCi/sec))
Q is Release Rate of Nuclide i, Stack Pelease (pCi/sec)
O gy Release Rate of Nuclide i, Vent Release (pCi/sec)
Eg Beta Skin Dose Constant (mrem /yr per WCi/m )
(X/Q) s Relative Effluent Concentration, (sec/m )
Vent Stack Release Ag Radiological Decay Constant (hr-1)
R Downwind Range (m) u, Average Wind Speed, Stack Release (m/sec) f i
8.1-9
QUAD-CITIES REVISION 11 DECEMBER 1985 SYMBOL NAME UNIT (x/Q) y Relative Effluent Concentration, Vent ,,cj ,3)
Release uy Average Wind Speed, Vent Release (m/sec)
Sg Gamma Dose Constant, Stack Release (arad/yr per pCi/sec)
V i
Gamma Dose Constant, Stack Release (mrad /yr per pCi/sec)
I I
5
! 8.1-10 l
QUAD-CITIES REVISION 11 DECEMBER 1985 8.1.6 Constants Used In Section 8.1 L
NUMERICAL VALUE NAME UNIT 1.11 Conversion Constant (mrea/arad) 3600 Conversion Constant (sec/hr)
S f
8.1-11 '
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_p. c .ea sm.m n c.?imas QUAD-CITIES STATION
() Ust, sad't f
- - - *gPath = Untes 1 & 2
.. . m .ci.,n ..nt.: ,
fi 6.1-1
-i'Ni P+aO ICW A?t
(-- MA && h W PAN g
. Ji7 ,.,u,,,.. a .m. t ' " - s a= ,a = < SI$Ft !F 1 0 GALLOUS RAIMA$TE AND
.. m,o, mtrs urttm im otAr.aAM
- . . - - - - - . . -- . .. wi . .a.. . . .n. ..s. m..-.a a...u l
QUAD-CITIES REVISION 11 DECEMBER 1985 where:
Cf = pCi/ml of nuclide 1; MPC i = maximum permissible concentration pCi/ml of nuclide is and Ag = pCi of nuclide i released in time t.
3 E
F ,,, Maximum Flow Rate, Radwaste Discharge (ft /sec)
The maximum flow rate of radwaste from the discharge tank to the initial dilution stream.
d F Average Flow Rate, (ft /sec) ve
- qitial Dilution Stream -
The average flow rate of the initial dilution stream which carries the radionuclides to the unrestricted area boundary.
Surveillance frequencies for liquid effluent monitors will be as stated in Table 4.2-3 of the Technical Specifications.
Calibration methods will be consistent with the definitions found in Section 1.0 of the Technical Specifications.
. 8.2.3 Radwaste Discharge Line Releases 8.2.3.1 Radwaste Discharge Monitor The radwaste releases are currently monitored for radioactivity using two grab samples and a composite sample. These samples are analyzed for alpha, beta, and gamma radiation. MPC calculations are done to determine discharge rate and dilution volume. l 8.2-2
1 QUAD-CITIES REVISION 11 DECEMBER 1985 l
Installation of a new continuous monitor for the radwaste discharge line is in progress. It is an offline monitoring l system which uses a 2-inch by 2-inch sodium iodine thallium actuated scintillation detector in a lead-shielded housing.
The sample container is bowl shaped to minimize crud buildup.
A GM tube is used to determine the background radiation level.
The radwaste discharge monitor provides a signal to a recorder '
and an Eberline CT-2 control terminal. A high radiation alarm will be activated by the control terminal. The process radiation monitor, control terminal, alarm, and annunciator are located on panels in the main control room.
t l
Tne process liquid monitor has a logarithmic scale with :
a range of 10 -1 to 10 6 counts /sec. The monitor is powered by 120-Vac.
4 The radwaste discharge line detector (RE 1/2-1799-01) is mounted adjacent to the radwaste control rocm. The flow is routed there after the flow control valves and prior to the selection of several alternate discharge routes.
1 The alarm setpoint for the radwaste discharge monitor is established at or below the maximum concentration determined by Equation 8.3. The concentration is converted to an alarm setpoint using an efficiency curve developed for the monitor through use of a Cs-137/Ba-137m liquid calibration sources.
i 8.2.3.2 Allocation of Effluents From Common Release Points Radioactive liquid effluents released from the radwaste treatment system are comprised of contributions from both units.
Determination of the allocation of waste is achieved by comparing (
8.2-3
QUAD-CITIES REVISION 11 DECEMBER 1985 the pump timer totals for each unit's floor drain and equipment drain pumps to the amount of waste sent to the river discharge tank from the floor drain and waste collector storage tanks.
Liquid effluents from laundry and chemical waste are allocated i evenly between units. During extended unit shutdown or periods I of significant plant input differences, the apportionment will be adjusted accordingly. The allocation of the effluents will be made on a monthly basis.
8.2.3.3 Administrative and Procedural Controls for Radwaste Discharges Administrative and procedural controld have been implemented to ensure proper control of radioactive liquid radwaste discharges, to preclude a release in excess of 10 CFR 20 limits. The dis-charge rate for each batch is calculated by a technician and then independently verified by two operating staff personnel.
A single river discharge tank has been designated and modified from which all radwaste discharges will normally be released.
This tank has manual inlet and discharge valves which can be locked.
The inlet valve is locked closed during recirculation of the tank prior to sampling and during the discharge to preclude an accidental addition to the tank which could change its activity.
The discharge valve is locked closed at all times except during the discharge. All other lines, unich tie-in with the discharge line, are locked closed. The high and low flow control valves are selected by a key-lock switch which allows the use of only one of the two flow control valves at any one time. The key to this switch and the locked valves is under the administrative control of the radwaste foreman.
8.2-4
O
, QUAD-CITIES REVISION 11 DECEMBER 1985 A documented valve checklist is prepared for each batch discharge.
The proper valve lineup is checked by the operator and the radwaste foreman, prior to release. If any sudden significant increase of the radiation monitor occurs during the discharge, the release is terminated. These controls are documented in Station Operating and Administrative Procedures.
8.2.4 Service Water Header Releases 8.2.4.1 Service Water Effluent Monitors Each unit's main service water effluent header is monitored for radioactivity by taking grab samples every twelve hours and analyzing for gross beta activity.
Installation of a new continuous monitor for both service
~
water headers is in progress. It is an offline continuous monitoring system. The process liquid monitor uses a 2-inch by 2-inch sodium iodine thallium-activated scintillation detector in a lead shielded housing. The samp,le container is bowl shaped to minimize crud buildup. A GM tube is used to determine background radiation levels.
The service water effluent monitor on each unit provides a signal to a recorder and to an Eberline CT-2 control terminal, which initiates a high radiation alarm. The process radiation monitor, recorder, alarm and annuciator are located on the panels in the main control room.
The process liquid monitors have logarithmic scales with a
~1 6 The monitors are range of 10 to 10 counts per second.
i powered from 120 Vac.
i 8.2-5
. QUAD-CITIE REVISION 11 DECEMBER 1985 The service water system detectors (RE 1(2)-1799-01) are located adjacent to the main service water effluent header on each unit prior to release to the discharge bay.
The alarm setpoints for the service water effluent monitors are established at or below the maximum concentration determined by Equation 8.3.
8.2.5 Determination of Initial Dilution Stream Flow Rates For those release paths which have installed flow monitoring instrumentation, that instrumentation will be used to determine the flow rate of the initial dilution stream. This instrumenta-tion will be operated and maintained as prescribed by the Tech-nical Specifications. For those release paths which do not have installed flow monitoring instrumentation, flow rates will be determined by use of appropriate engineering data such as pump curves, differential pressures, or valve position indication.
l l
8.2-6
QUAD-CITIES REVISION 11 DECEMBER 1985 8.2.6 Symbols Used In Section 8.2 SYMBOL NAME UNIT C
lim Liquid Release Limit (pCi/ml)
MPC Weighted Maximum Permissible (pCi/ml)
Concentration Cg Nuclide Concentration (pCi/ml)
MPC g Maximum Permissible Concentration (pCi/ml)
Ag Nuclide Quantity Released (pCi)
F[, Maximum Flow Rate, Radwaste (ft /sec)
Discharge d (ft3 73,c)
F ,
Average Flow Rate, Initial Dilution Stream 8.2-7
i e
fij REVISION 11 I
h DECEMBER 1985
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t
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QUAD-CITIES STATION Units 1 & 2 FIGURE 8.2-1 SIMPLIFIED LIQUID RADWASTE PROCESSING DIAGRAM
j REVISION 11 5 .t DECEMBER 1985
- - . e i
a 1 E E j !
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QU AD-CITIES STATION Units 1 & 2 FIGURE 8.2-2 SIMPLIFIED LIQUID EFFLUENT FLOW DIAGRAM
i
. QUAD-CITIES REVISION 11 DECEMBER 1985 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM The process control program (PCP) shall contain the sampling, analysis, and formulation determination by which sol'idification of radioactive wastes from liquid systems is ensured. Figure 8.3-1 is a simplified diagram of solid'.radwaste processing.
l t
A l
t
-l 8.3-1
. - . _ . _ . _ , _ _ . _ _ . _ _ . , _ _ _ _ , _ _ - _ . . - - - . _ - _ _ _ . _ _ . _ _ _ _ _ _ _ ~ _ . _ _ , . - . . _ . . _ . _ _ - - _ _ _ _ _ . . _ _ . _ - _ _ _ _ _ _
I l
. ! E" REVISION 11 i Ik DECEMBER 1985 Bo =
1 l,
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QU AD-CITIES STATION Units 1 & 2 FIGURE 8.3-1 SIMPLIFIED SOLID RADWASTE PROCESSING DIAGRAM
QUAD-CITIES REVISION 11
. DECEMBER 1985 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING The environmental radiological monitoring program to be performed in the environs around Quad-Cities Station is given in Table 8.4-1.
Figure 8.4-1 shows the 16 fixed air sampling sites and TLD
- locations; also shown are the " outer ring" ($pproximately 5 miles distant) TLD locations. Figure 8.4-2 shows the " inner ring" TLD locations. The TLD's are code numbered as follows:
XYY-N, !
where:
X= 1 means inner ring, X= 2 means outer ring, and YY-N is an identification code.
Figure 8.4-3 shows the milk, fish, water, and sediment sample locations. .
The reporting levels for radioactivity concentrations in envi-ronmental samples are given in Table 8.4-2. The practical lower limits of detec' tion for this program are given in Table 8.4-3.
t 8.4-1 P
, j - n-,
4 TABLE 8.4-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM EXPOSURE PATHNAY
' SANPLING OR TYPE AND FREQUENCY SAMPLING OR MONITORING LOCATIONS, COLLECTION FREQUENCY OF ANALYSIS AND/OR SAMPLE Oniste or Near' Field
- Particulate Sampler:
- 1. Airborne a.
Q-01 Onsite Station 1 0.5 mi N Continuous sampler Gross beta analysis following filter change b
Q-02 Onsite Station 2 0.5 mi ENE operation with partic-Q-03 Onsite Station 3 0.6 mi S ulate filter collec-Q-04 Mitrin 1.5 m i NE tion weekly and Radiolodine Canister 0-05 Saddle Club Dairy 1.8 mi SSE radiolodine canister Farm collection bi-weekly I-131 analysis bi-weekly Q-06 Hanson's Boat 1.8 mi NNW Landing Sampling Train:
Test and maintenance weekly
- b. Far Field" @
." Q-07 Clinton 9.0 mi NE Continuous sampler Particulate Sampler: 7 Q-08 Sikkema Farm 7.0 mi ENE operation with partic- O 7 13.0 mi ESE ulate filter collec- Gross beta analysis U u Q-09 Fire b m Q-10 6,illsdale 10.0 mi SE tion weekly and following filter change
- 0-11 Port Byron 8.0 mi S radiolodine canister Q-12 Bettendorf 13.0 mi SW collection bi-weetly Radiciodine Canister Q-13 Princeton 4.8 mi SW Q-14 Utica Ridge Road 11.0 mi ESE I-131 analysis bi-weekly Q-15 DeWitt 13.0 mi WWW '
Q-16 Low Moor 6.0 mi NNW Sampling Train:
Test and maintenance weekly RR RS 55 2R 3
TABLE 8.4-1 (Cont'd) .
EXPOSURE PATHMAY SAMPLING OR TYPE AND FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATIONS COLCECTION FREQUENCY OF ANALYSIS
- 2. Direct Radiation a. At Air Sampling Sites
- Quarterly Gamma dose quarterly Same locations as fixed air sampling locations in Item 1.
- b. Inner RinqU Quarterly Gamma dose quarterly 101-1 0.7 mi N 101-2 0.8 mi N 102-1 1.7 mi NNE 102-2 1.7 mi NNE 103-1 1.2 i NE 104-1 1.1 i ENE 104-2 0.95 mi ENE 104-3 0.63 mi ENE 105-1 0.75 mi E g 106- 1 0.71 mi ESE >
, 106-2 0.71 mi ESE ?
. 107-1 0.73 mi c= n 107-2 SE Ei 7 0.78 mi w 107-3 0.86 mi SE N 108-1 0.96 mi SSE 108-2 0.89 mi SSE 109-1 0.87 mi S 109-2 0.98 mi S 111-1 2.6 mi SW 111-2 2.6 mi SW 112-1 2.5 mi WSW 112-2 2.2 mi WSW 113-1 2.6 mi W 113-2 ?.5 mi W 114-1 2.6 mi WNW 114-2 2.5 mi WNW 115-1 2.6 mi NW 115-2 2.0 mi NW 116-1 2.2 mi NNW 116-2 2.4 mi NNW $$
@ ye
=s
e .
TABLE 8.4-1 (Cont'd)
EXPOSURE PATHWAY SANPLING OR TYPE AND FREQUENCY AND/OR SANPLE SANPLING OR NONITORING LOCATIONS COLLECTION FREQUENCY OF ANALYSIS
- 2. Direct Radiation a (cont'd) c. Outer Ri_ng Quarterly Gamma dose quarterly 201-1 4.6 mi N 201-2 4.0 mi N 202-1 4.4 mi NNE 202-2 5.0 mi NNE 203-1 5.0 mi NE '
203-2 4.5 mi NE 204-1 4.5 mi ENE 204-2 3.9 mi ENE 205-1 5.6 mi E 205-2 4.7 mi E ,
206-1 5.0 mi ESE 206-2 4.8 al ESE 207-1 4.3 mi SE 207-2 4.6 mi SE o e 208-1 4.4 mi SSE $
O
. 208-2 4.7 mi SSE i 209-1 4.4 mi S g 209-2 4.5 mi S H 210-1 4.4 mi SSW N M
210-2 4.4 mi SSW 211-1 3.5 mi SW 212-1 5.4 mi WSW .
212-2 4.7 mi WSW -
213-1 4.7 mi W 213-2 5.5 mi W 214-1 4.4 mi WNW 214-2 4.4 mi WNW 215-1 4.8 mi . NW 215-2 4.5 mi NW 216-1 4.5 mi NNW 216-2 4.2 mi NNW a
UnS B
NE 3
i
)
TABLE 8.4-1 (Cont'd)
EXPOSURE PATHWAY SAMPLING OR TYPE AND FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATIONS COLLECTION FREQUENCY OF ANALYSIS ___
d
- 3. Waterborne J
- a. Public Water Q-19 East Moline Water 16.0 mi SSW Weekly collection Gamma isotopic analysis Supply Works composited monthly monthly Q-20 Davenport Water 18.0 mi SSW Works
- b. Cooling Water Q-21 Inlet at station Weekly Cross beta analysis week 1)
Sample Q-22 Discharge at station
- c. Sediment Q-23 Lock and Dam 15.0 mi SSW Annually Gamma isotopic analysis No. 14 annually
- 4. Ingestion d
- a. Milk Q-17 Hansen Dairy Fare 6.0 mi ENE Weekly collection when I-131 analysis on each $2 0-18 Musal Farm 5.5 mi SW animals in pasture sample >
.' (May to Oct.); monthly, ?
y Nov. to March Q u.
H
- b. Fish Q-24 Davenport Farm 15.0 mi SSW Semi-annually Gamma isotopic on N edible portions of each
- Market (Pool 614 of Miss. River) sample See Figure 8.4-1.
b A gamma isotopic analysis shall be performed wherever the gross beta concentration in a sample exceeds by five times (5x) the average concentration of the precedadg calendar quarter for the sample location.
i C
See Figure 8.4-2.
d See Figure 8.4-3.
NN li:s C
~
TABLE 8.4-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBORNE PARTICULATE WATER OR GASgS FISH MILK FOOD PRODUCTS ANALYSIS (pCi/t) (pCi/m ) (pCi/Kg, wet) (pCi/t) (pCi/Kg, wet)
H-3 20,000*
Mn-54 1,000 30,000 Fe-59 400 10,000 m
Co-58 1,000 30,000 o
Co-60 300 10,000 $
?
Zn-65 300 20,000 Q
. s Zr-Nb-95 400** 5-m I-131 2 0.9 3 100 Cs-134 30 16 1,000 60 1,000 Cs-137 50 20 1,000 70 2,000 Ba-La-140 200** 300** g MN R$
- For drinking water samples. This is 40 CFR Part 141 value. NN
- Total for parent and daughter. 4D "5 2 N
TABLE 8.4-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)**
AI RBORNE PARTICULATE WATER OR GASgS FISH MILK SEDIMENT ANALYSIS (pCi/t) (pCi/m ) (pCi/Kg, wet) (pCi/t) (pCi/Kg, dry) c Gross Beta 5 0.01 1,000 5 2,000 Gamma Isotopic 20 0.01 200 20 200 d
I-131 5 0.1 100 5(0.5)*
n co Cs-134 10 100 10 gj a e 4 Cs-137 10 100 5 5 H-3 200 tiw
. m o
I;$S s
i p
u.
O
QUAD-CITIES REVISION 11 DECEMBER 1985 TABLE 8.4-3 (Cont'd)
NOTES:
- a. Other radionuclides which are measurable and identifiable by gamma-ray spectrometry, together with the nuclides indicated in Table 8.4-3, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide,
- b. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability with only 54 probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system.(which may include radio-chemical separation)
LLD =
4.66- (Sb) f (A)- (E)- (V) . (2.22) . (Y) . (exp (- Aat) ) . (t)
Where:
LLD is the "a priori" lower limit of detection for a blank sample or background analysis as defined above (as pCi per unit mass or volume). ,
Sg is the square root of the background count or of a blank sNmple count; it is the estimated standard error of a background count or a blank sample count as appropriate (in units of counts).
E is the counting efficiency (as counts per disintegration) .
l A is the number of gamma-rays emitted per disintegration
( for gamma-ray radionuclide analysis (A = 1.0 for gross alpha l
and tritium measurements).
V is the sample size (in units of mass or volume).
2.22 is the number of disintegrations per minute per picocurie.
Y is the fractional radio-chemical yield when applicable (otherwise Y = 1.0).
I l
l
[ 8.4-8
QUAD-CITIES REVISION 11 DECEMBER 1985 TABLE 8.4-3 (Cont'd)
Lambda is the radioactive decay constant for the particular radionuclide (in units of reciprocal minutes) .
Delta t is the elapsed time between the midpoint of sample collection and the start time of counting. (at = 0.0 for enviromental samples and for gross alpha measurements.)
t is the duration of the count (in units of minutes).
The value of "S " used in the calculation of the LLD for a detection sysNem shall be based on an actual observed background count or a blank sample count (as appropriate) rather than on an unverified theoretically predicted value.
Typical values of "E", "V", "Y", "t", and " delta t" shall '
be used in the calculation.
For gamma-ray ra'dionuclide analyses the background counts are determined from the total counts in the channels which are within plus or minus one FWHM (Full Width at Half Maximum) of the gamma-ray photopeak energy normally used for the quantitative analysis for that radionuclide. Typical values of the FWHM shall be used in the calculation.
The LLD for all measurements is defined as an "a priori" (before the f act) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.
- c. Referenced to Cs-137.
- d. For thyroid.
- e. 0.5 pCi/t on samples collected during the pasture season.
8.4-9
[
REVISI0f 11
< DECEMBER 1985
(
p . .. ppi River Fulton ^
Clinton -
usao us30 _
7 '\ f 16e 20i-i 202i / _
2,..,..
2'6-2 x ,. . '"
I ai5-is , 20i:2 203.'2 lowa 2i5-2 Illinois
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s 204 2 e8 us67 1
< 34 ' = 2as-'
, 2, 2 213-1E u.3 2 3 205-2 21225 21215 e5 m 20s-2 us 61 211 g 1 (210-2 E2071 210 20 @
l 208-2 itt.g 2 l 80 110 Davenport us 67 Rock River 7 iLL e4 y,, neettendort c -
'N N ' N olin. S T [h M DP l l 9 Air Sampling Site M Outer Ring TLD Location i.74 1 80 0 , , , ,
5 1,0 1,5 2,0 Miles scale O 5 10 15 20 25 30km QU AD-CITIES STATION Units 1 & 2 FIGURE 8.4-1 FIXED AIR SAMPLING SITES AND OUTER RING TLD LOCATI0t;S I$'A'372
G REVISI0'i 11 DECEMBER 1985 l
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? "i' - Units 1 e. 2 l
o os ikm FIGURE 8.4-2 IfitlER RIf4G TLD LOCATI0fiS l
E'e'i'.3n ,
G REVISIO!J 11 A DECEftBER 1985 IOWA 13e Goose Ls. Us 67 f
es g
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N US6 g i r I a Sampling Station scaie o, , , , ? ip i,s 2p u.ie.
?,,,? '? '? 2p 2,s sp a,o QU AD-CITIES STATION Units 1 & 2 FIGURE 8.<-3 f t!LK, FISH, WATER, Af;D SEDIMEllT SAMPLE LOCATI0t;S l
O7e *- r2
UNIT 1 MAINTENANCE SUWARY CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q35071 Standby Liquid The relief valve The relief valve failed The valve was replaced Control Pump failed to seat to seat properly would like-for-like. The valve Relief Valve properly due to not allow 'B' pump to was tested and performed 1-1105B metallic foreign pressurize system above satisfactorily.
material on the 1350 psi. 'A' pump was seat. available and performed properly.
Q39495 CRD L-2 Unknown at this Control rod fell to Short term action was to time. Supplemental position 48 from 46 while fully insert CRD. Drive Deviation Report testing. The rod was then will be repalced during will be written fully' inserted to 00 and 1986 Unit 1 Refuel Outage.
pending investiga- disarmed to satisfy tion during 1986 Technical Specification Unit 1 Refuel 3.3.B.l.
Outage.
Q46155 1/2-6601 The Diesel engine The output breaker to Bus The governor wiring was Diesel governor was wired 13-1 tripped. The Diesel corrected and the wiring Generator incorrectly, and was then loaded on Bus lugs were replaced.
Governor there were some 23-1 successfully, but was readjusted; loose wiring lugs repeated attempts to load was causing on the RACR Synchro- Bus 13-1 failed. An auto-problems when Check Relay. start of Diesel Generator attempting to was possible, close on Bus 13-1 Q46843 1-2301-48 Wire on armature of The valve would not close The motor was replaced and HPC1 Cooling operator motor broke. by using the motor, the operator was tested l Normal This caused the motor Normal operating position three times successfully.
Return Valve to not rotate. is open. One other path of cooling was available.
0027H/0061Z
UNIT 1 MAINTENANCE SUWARY CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN 10 NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q46992 1/2-6601 A faulty contact While testing, the 1/2 A new SBM contact block Diesel block on the Synchro- Diesel Generator would was installed and tested Generator Switch in the Control not close into Bus 13-1. successfully.
Output Room prevented the It would close into Bus Breaker to HACR Synchro-Check 23-1. Unit 1 Diesel Generator Bus 13-1 Relay from conducting was operable.
the Bus 13-1 running voltage.
Q47147 86-005 1-1705-16B Probable cause due to The Control Room in- The signal cable will be Fuel Pool electrical noise in dicator tripped over the rerouted through a low Radiation the cable causing high limit, then dropped noise area.
Monitor voltage changes. to normal. The Reactor Building Vent System isolated and the Standby Gas Treatment System started as designed.
I I,
b
'0027H10061Z
UNIT 2 MAINTENANCE SUWARY CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q41021 85-006 A0 2-203-2B High pressure steam Failed Local Leak Rate The main valve seat was Outboard caused wear of main Test. lapped, main disc MSIV valve seat and disc, replaced, and pilot disc pilot valve seat and seat replaced.
and disc.
Q41344 Hanger Personnel error; A locking pin device was The base plate was replaced 3001A-W-102 left the pin device left engaged, a weld lug and the locking pin device engaged and thia pin was cracked, and base was removed.
made the hanger too plate was deformed.
rigid. This caused the weld to break and the base plate to deform.
Q41833 85-007 CV 220-62B Excessive rust and Failed Local Leak Rate The Check Valve was
'B' Feed- crud, caused by the Test. replaced like-for-like.
water Check always present water Valve affected the valve seating surfaces.
Q41850 85-006 A0 2-203-2B High pressure steam Failed Local Leak Rate The main valve seat was Outboard caused wear of main Test. lapped, main disc replaced, MSIV seat, disc, and pilot disc and seat replaced.
- pilot valve seat and disc.
Q41893 Line 2-2301- The snubber extension The cold position setting The machine snubber screws 4" 2-105 flange was 1/4 inch was not at proper were replaced with longer Snubber S/N too thick to allow position, but the snubber machine screws and achieved 16181 good thread engage- was functionally operable. full thread engagement.
ment for snubber screws.
Q42009 Snubber S/N Unknown. The snubber's cold SNED re-evaluated the snubber 6766 Line 2- position setting was 1/4 and its cold setting 1404-10" inch out of tolerance, tolerances and approved the Snubber 2-1 but the snubber was 'as found' setting.
functionally operable.
0027H/0061Z !
UNIT 2 MAINTENANCE SUWARY CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q47051 2-1001-65C Pump vibration The vent line cracked Modification in progress RHR Service caused vent line to 50% around and allowed to lessen vibration and Water Pump crack where it a small amount of water reduce fatigue of vent Vent Line attaches to pump to leak. pipe.
casing.
~
0027H/0061Z
~
\
IV. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1. and 6.6.B.2. of the Technical Specifications.
UNIT ONE Licensee Event Report Number Date Title of Occurrence 86-01 1-6-86 Leak Rate From All
, Valves and Penetrations in Excess of Technical Specification Limit 86-02 1-7-86 Excessive Leakage Through MSIV's During Local Leak Rate Testing 86-03 1-2-86 1/2 Diesel Generator i Cooling Water Pump Inoperable 86-04 1-18-86 ATWS AR1 Initiation While Draining Reactor Vessel 86-05 1-18-86 1B Fuel Pool Radiation Monitor Spiked Upscale 86-06 1-22-86 Isolation of Reactor Building Vent System UNIT TWO Licensee Event Report Number Date Title of Occurrence 86-01 1-3-86 Unit Reactor Scram Due to Spurious Group I Isolation Caused By Air Hose 86-02 1-17-86 Reactor Building Vent Monthly Tritium Sample Not Obtained
V. DATA TABULATIONS The following data tabulations are presented in this report:
A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and 90wer Reductions
OPERATING DATA REPORT DOCKET NO. 50-254 IJNIT ONE DATEFEBRUARY 4 1986 COMPLETED BYCAROL L KRONICH TEl.EPHONE(309)654-2241 OPERATING STATUS 0000 010186
- 1. Reporting period 2400 013186 Gross hours in reporting period 744
- 2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789
- 3. Power level to which restricted (if any)(MWe-Net): NA
- 4. Reasons for restriction (if any):
This Month Yr.to Date , Cumulative
- 5. Number of hours reactor was critical 120.0 120.0 96781.4
- 6. Reactor reserve shutdown hours 0.0 0.0 3421.9
- 7. Hours generator on line 120.0 120.0 93399.5
- 8. Unit reserve shutdown hours. 0.0 0.0 909.2
- 9. Gross thermal energy generated (MWH) 240485 240485 195205642
- 10. Gross electrical energy generated (MWH) 80622 80622 63199993
- 11. Het ei-ctrical energy generated (MWH) 74740 74740 59101273
- 12. Reac t or service factor 16.1 16.1 80.4
- 13. Reactor evollability factor 16.1 16.1 83.3
- 14. Unit service factor 16.1 16.1 77.6 15.. Unit avo11ob111ty factor 16.1 16.1 78.4
- 16. Unit capacity factor (Using MDC) 13.1 13.1 63.9 17.. Unit capacity factor (Using Des.MWe) 12.7 12.7 62.2
- 18. Unit forced outage rate 0.0 0.0 5.9
- 19. Shutdowns scheduled over next 6 nonths (Type,Date,ond Duration of euch):
- 20. If shutdown at end of report p e r i a d , e s t ina t e d d a t e o f s t ar t u p __3_-_24-86______
$The IOC nep be lueer then 769 IWe dering perleds of high onbient tenperatore dee to the thernal perfernance of the spray ceM1.
8W10FFICl#. COMPANY NWWERS ARE USED IN THIS REPORT
s Ji.+-+4 % 4 +A4h a .;.m._g OPERATING DATA REPORT DOCKET NO. 50-265 UNIT TWO DATEFEBRUARY 4 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309)654-2241
. OPERATING STATUS 0000 010186
- 1. Reporting period:2400 013186 Gross hours in reporting period 744
- 2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical roting (MWe-Net): 789
- 3. Power level to which restricted (if any)(MWe-Net): NA
- 4. Reasons for restriction (if any):
This Month Yr.to' Dote Cumulative
- 5. Number of hours reactor was critical 735.8 735.8 92003.9
- 6. Reactor reserve shutdown hours 0.0 0.0 2985.8
- 7. Hours generator on line 732.4 732.4 89030.0 4
- 8. Unit reserve shutdown hours. 0.0 _
0.0 702.9
- 9. Gross thermal energy generated (MWH) 1737237 1737237 187846260
- 10. Gross electrical energy generated (MWH) 573227 573227 59990009 f
- 11. Net electrical energy generated (MWH) 548173 548173 56422432 i
j 12. Reactor service factor 98.9 98.9 77.0
- 13. Reactor evollobility factor 98.9 98.9 79.5
- 14. Unit service factor 98.4 98.4 74.6 ,
l
- 15. Unit avo11obility factor 98.4 98.4 75.1
- 16. Unit capacity factor (Using MDC) 95.8 95.8 61.4
- 17. Unit capacity factor (Using Des.MWe) 93.4 93.4 59.9
- 18. Unit forced outage rate 1.1 1.1 0.1 I l 19. Shutdowns scheduled over next 6 nonths (Type,Date,ond Duration of each' NA
! 20. If shutdown at end of report period,estincted date of startup SThe IllC ner Se lever the 769 leie dering perleds of high onblent tenperatore det to the thernel perfernance of the sprey cael.
ILMFFICIAl. ColFAlfY IMIERS ARE USD Ill THIS REPORT n,.._-_._,_._.__,-_._______.. _ _ _ _ . _ . _ . . _ . _ - . _ . _ . . _ . . _ _ . . - _ . . _ - . _ . . . . .
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. APPENDIX B AVERAGE DAILY UNIT POWER LEVEL i I
DOCKET NO. 50-254 UNIT ONE DATEFEBRUARY 4 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309)654-2241 MONTH Januarv 1986 4 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) i
- 1. 671.5 17. -4.9
- 2. 644.7 10. -4.2 3, 662.6 19. -4.1 i I
4, 663.4 20. -4.1
- 5. 568.5 21. -4,0
- 6. -10.0 22. -4.0
- 7. -7.8 23. -4.0
- 3. -6.8 24. -4.1
- 9. -7.1 25. -4.0 _
- 10. -6.8 26. -4.1
- 11. -6.0 27. -4.1
- 12. -5.6- 28. -4.1
- 13. -5.4 29. -4.1
- 14. -5.5 30. -3.3
- 15. -5.5 31. -3.3
- 16. -5.4 INSTRUCTIONS fin this forn, list the everage daily snit power level in lele-Met for each day in the reporting nonth. Compete to the neerest uhele negeustt. '
These figeres will be esed to plot a graph for each reporting nonth. Mete that when noxinen dependeble copecite is esed illI line for (or the net electrical the restricted power rating of the unit,In such cases,the everage daily snit power setput sheet sh level line).
feetnoted to explain the apperent onenely
. APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-265 UNIT TWO DATEFEBRtlARY 4 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309)654-2241 MONTH Januarv 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (NWe-Net)
- 1. 731.9 17. 746.1
- 2. 739.5 18. 774.4
- 3. 427.3 19, 792.1
- 4. 560.7 20, 770.5
- 5. 746.4 21. 784.2
- 6. 708.8 22. 751.6
- 7. 745.0 23. 741.6
- 8. 788.0 24, 752.7
- 9. 737.3 25. 542.5
- 10. 749.1 26. 785.4
- 11. 732.7 27. 778.0 12, 748.2 28, 786.3
- 13. 778.9 27, 783'.0
- 14. 784.0 30, 791.9
- 15. 797.3 31, 750.6
- 16. 755.4 INSTRUCTIONS On this forn, list the everage daily unit powr level in ille-Net for each day in the reporting senth Compete to the nearest uhele negevett.
These figures will be osed to plot a graph for each reporting ner.!h. Note that when noxinen dependable capacity is used iHI linefor (orthe thenet electrical restricted powrrating of the snit,In sich cases,the overage daily snit powr estput sheet shesid b level line).
. festnoted to explain the apparent ansnely
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VI. UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the commission:
A. MAIN STEAM RELIEF VALVE OPERATIONS There were no Main Steam Relief Valve Operations for the reporting period.
B. CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO There was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.
v VII. REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E.
O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Information", dated January 18, 1978.
e QTP 300-S32
- Revision 1
. QUAD-CITIES REFUELING March 1978 '
lNFORMATION REQUEST l I
- 1. Unit: 01 Reload: 7 Cycle: 8
- 2. Scheduled date for next refueling shutdown: 9-14-87 3 Scheduled date for restart following refueling: 3-29-86
- 4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment: YES. A ROUTINE MAPLHGR AMENDMENT HAS BEEN SUBMITTED AS A PREPARATORY CHANGE TO ALLOW A 10 CFR 50.59 REVIEW OF THE RELOAD. TECHNICAL SPECIFICATION CHANGE TO ALLOW HAFNIUM ABSORBER MATERIAL HAS BEEN SUBMITTED.
5 Scheduled date(s) for submitting proposed licensing action and supporting information:
- 6. Important licensing considerations associated with refueling, e.g., new or
' different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
A) USE OF 8 ASEA-ATOM CONTROL BLADES CONTAINING HAFNIUM.
B) CONTINUED USE OF TWO BARRIER LEAD TEST ASSEMBLIES.
7 The number of fuel assemblies.
- a. Number of assemblies in core: 0
- b. Number of assemblies in spent fuel pool: 2538
- 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel essemblies:
- a. Licensed storage capacity for spent fuel: 3657
- b. Planned increase in licensed storage: 0 9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present IIcensed capacity: 2003 XPPROVED l APR 2 01978 l l
C3.c:.c).si.ft.
i O
QTP 300-S32 o
Revision 1
.. QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST
- 1. Unit: Q2 Reicad: 7 Cycle: 8
- 2. Scheduled date for next refueling shutdown: 10-6-86 3 Scheduled date for restart following refueling: 12-22-86
- 4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:
NOT AS YET DETERMINED.
- 5. Scheduled date(s) for submitting proposed licensing action and supporting Information:
SEPTEMBER 19, 1986, IF REQUIRED.
- 6. Important licensing considerations associated with refueling, e.g.,riew or
' different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
NONE PLANNED AT PRZSENT TIME.
D
- 7. The number of fuel assemblies.
- a. Number of assemblies in core: 724
- b. Number of assemblies in spent fuel pool: 842
- 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:
- a. Licensed storage capacity for spent fuel: 3897
- b. Planned increase in licensed storage: 0 9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2003 APPROVED APR 2 01978 C). c:. c>. si. Ft.
c o
VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined below:
ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI -
American National Standards Institute APRM - Average Power Range Monitor ATHS - Anticipated Transient Without Scram BHR - Bolling Hater Reactor CRD - ' Control' Rod Drive EHC - Electro-Hydraulic Control System .
E0F - Emergency Operations Facility GSEP - Generating Stations Emergency Plan HEPA -
High-Efficiency Particulate Filter, HPCI - High Pressure Coolant Injection System HRSS - High Radiation Sampling System IPCLRT - Integrated Primary Containment Leak Rate Test Intermediate Range Monitor IRM -
ISI -
Inservice-Inspection LER - Licensee Event Report LLRT -
Local Leak Rate Test LPCI - Low Pressure Coolant Injection Mode o'f RHRS LPRM - Local Power Range Monitor !
MAPLHGR -
Maximum Average Planar Linear Heat Generation Rate MCPR -
Minimum Critical Power Ratio MFLCFR - Maximum Fraction Limiting Critical Power' Ratio MPC -
Maximum Permissible Concentration MSIV -
Main Steam Isolation Valve NIOSH - National Institute for Occupational Safety and Health PCI -
Primary Containment Isolation PCIONR - Preconditioning Interim Operating Management Recommendations RBCCH -
Reactor Building Closed Cooling Water System RBM -
Rod Block Monitor RCIC -
Reactor Core Isolation Cooling System UHRS - Residual Heat Removal System RPS - Reactor Protection System RHM -
Rod Horth Minimizer SBGTS -
Standby Gas Treatment System SBLC -
Standby Liquid Control SDC - Shutdown Cooling Mode of RHRS SDV -
Source Range Monitor TBCCH -
Turbine Building Closed Cooling Water System TIP -
Traversing Incore Probe TSC -
- o - M 2e>
ouad Cities Nuclear Power Station 0 Commonwealth Edison 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 TKT-86-13 February 3, 1986 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk Gentlemen:
Enclosed for your information is the Monthly Performance Report -
covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of January, 1986.
Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION i
r T. K. Tamlyn Services Superintendent bb Enclosure rE2x C )'f