ML20059C729
| ML20059C729 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/30/1990 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20059C725 | List: |
| References | |
| NUDOCS 9009050287 | |
| Download: ML20059C729 (25) | |
Text
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QCP 100-525 Revision 5 EFF WENT AND NASTE DISPOSAL March 1989 SEMI-ANiki,% REPORT Jan.-June, 1990 GASECUS EFFLUENTS - S N LEASES PROCEDURE: QCPl100-7 Quarter Quarter Est. Total Unit First Second Error. %
A. FISSION & ACTIVATION GASES Cj 3.17E01 1.78E01 1.32E01
- 1. Total Release Averaae reloase rate for period uC1/sec 4.08E00 2.26E00
- 2. l.67E-02 Percent of "ech Spec limit = 4.92E-OZ 3.
Chimney & stack 1 3.65E-03 1.57E-03 I
B. IODINE Cj 5.40E-04 2.17E-04 3.18E01
- 1. Total Iodine-131 Averace release rate for period uCi/sec 6.94E-05 2.76E-05 2.
C. PARTICULATES Particulates with half-lives
- 1. 1. 77E01 Cl 9.62E-03 8.06E-03 1
> B davs Averace release rate for period uC1/seC 1.24E-03 1.03E-03 2.
Gross aloha radioactivity Cl 1.00E-05 1.07E-059
- 3.
D. TRITIUM 1.73E01 2.75E01 6.20E00
- 1. Total Release C1 Averase release rate for period uC1/sec 2.23E00 3.50E00 2.
E. Iodine 131 & 133 Tritium and Particulates Percent of Tech spec Limit -
6.72E-01 1.12E00 Chiguv & styk g I *N0BLE GAS GANIA/N0BLE GAS BETA DOSE LINITS
- Projected value based on last six month's available data, l
- 8F nss M 88s b APPftOVED R PDC L JUN 121989 1
.9/0295c Q.C.O.SJt. l l \
QCP 100-525 5* O Revtsion 5 MAIN CHIMNEY GASEOUS EFFLUENTS
..' Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit First Second 5 1. Fission gases Kr-8$ C1 <LLD <LLD Kr-85s 4.17E-01' 2.98E k_- C1 Kr-87 C1 4.61E-01 5.34E-01
= Kr-88 C1 1.46E01 3.52E-01 Xe-133 C1 1.27E00 9.66-01 Xe-135 C1 1.17E00 4.83-01 Xe-135m C1 2.41E00 2.71E00 __
gg.133- C1 1.04E01 1.19E01 ,
Qr gj Cg 2.46E-01 5~.49E-01 C1 C1 Ci Total for Period C1 3.10E01 1.78E01
- 2. Iodines I-131 C1 4.92E-04 2.17E-04 I-133 C1 1.87E-03 2.29E-03 I-135- Cl 7.91E-03 3.38E-03 Total for Period C1 1.03E-02 5.89E-03 APPROVED JUN 121989 9/0295c Q.C.O.S.R. 1 4
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.... 4 :. a QCP 100-525 Revision 5 MAIN CHIMNEY [ l GASEOUS EFFLUENTS
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~
Continuous Mode Batch Mocie Quarter Quarter Quarter (carter Nuclides Released Unit First Second
- 3. Particulates Sr-89
- C1 3.89E-04 2.87E-04 Sr-90
- C1 5.30E-06 3.64E-06 Cs-134 C1 <LLD <LLD Cs-137 C1 9.73E-06 <LLD Ba-140 C1 2.02E-04 1.67E-04 ,
l l
La-140- Ci 6.72E-04 1.56E-03 Cr-51 C1 <LLD <LLD Mn-54 Cj <LLD 1.56E-04 Co-58 Cj <LLD <LLD _
Co-60 C1 1.27E-04 1.16E-04 '
<LLD <LLD
! 'I-131 C1 E
L An-110m Cj <LLD <LLD I-133 C1 1.21E-04 9.19E-05 I-135 Cj 7.62E-04 (LLD MO-99 Cj <LLD 6.13E-05 C1 C1 Total for Period C1 2.29-03 2.44E-03
-
- Projected value based on last six month's available data.
APPROVED JUN 121989 9/0295c Q.C.O.S.R.
-QCP 100-$25.
. '.'
- Revision 5 REACTOR VENTILATION L. GASEQUS EFFLUENTS-
. :c 1- Continuous his Bateh Mm e
! Quarter Quarter Quarter (uarter l Nuclides Released Unit First second l
.1. Fission gases Kr-85 C1 <un <ttD l
Kr-85m Ci (LLD (LLD Kr-87 C1 <tLD <tLD Kr-88 C1 <tLD <LLD Xe-133 Ci <tLD <LLD ,
Xe-135 C1 1.78E-01 <LLD Xe-135m C1 4.93E-01 <tLD Xs-138 C1 <tLD <u;o C1 C1 Total for Period Ci 6.71E-01 <US l
I-135 Ci 6.87E-05 < LIE l
Total for Period C1 2.82E-04 7.14E-05 L
g L
j APPROVED JUN 121989 9/0295c L Q.C.O.S.R.
i 1
QCP 100-525
, Itevision 5 REACTOR VElf7ILATIC11 l:
GASECUS EFFLutilTS Continu ws Mode Batch Nm e !
Quarter Quarter Quarter (uarter Iluclides Released Unit First Second
- 3. Particulates tr-89
- C1 2.00E-05 1.39E-05 Sr-90 * ,_
C1 9.95E-07 9.38E-07 Cs-134 Ci <LLD <LLD Cs-137 Cj 9.97E-05 9.46E-05 Ba-140 Cj <LLD (LLD La-140 C1 <LLD <LLD Cr-51 Cj 3.83E-04 1.15E-03 Mn-54 Cj 1.94E-03 5.32E-04 Co-58 Cj 1.93E-04 1.37E-04 Co-60 C1 3.35E-03 2.87E-03 1-131 Cj <LLD <LLD As-110m Ci <LLD (LLD I-133 cj <LLD (LLD r 1-135 ct 8.00E-04 <LLD No-99 cj 4.93E-04 7.83E-04 Fe-59 C1 3.03E-05 <LLD Nb-95 Cj - 1.54E-05 <LLD Zn-65 C1
<LLD 2.30E-05 Hf-181 CI <LLD 2.03E-05 Total for Period CI 7.33E-03 5.62E-03
- Projected value based on last six month's availability data JUNf21989 9/0295c '
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QCP 100-525 Revision 5 LI@!D EFFLUENTS - SLBMATION OF ALL RELEASES 3.,.
Qv.grter Quarter Est. Total Unit nrat seen*d Error. 1 A. FISSION & ACTIVATION PRODUCTS
- 1. Total release (not including tritium eases. alnha) Ci 9.14E-02 1.31E-02 7.30E00
- 2. Average d1'uted concentration durina batch discharaesr seriod uC1/ml 6.18E-09 1,26E-09 8.49E-02 7.75E-03
- 3. Dercent of ==licable~ ' tai"
- 1 3.86E-02 3.25E-03
- 4. Itaximum diluted concenurat on durina batch discharaos uC1/m1 4.llE-08 2.73E-09 B. TRITI(M
. Total relouse Ci 1.88E01 4.24E00 5.90E00 i!. Average d' uted concentration durine batch discharaos uC1/ml 1.27E-06 4.08E-07
- 3. Percent of analicable limit 1 4.23E-02 1.33E-02 C. DISSOLVED AND ENTRAINED GASES
- 1. Total-relense C1 3.57E-04 6.27E-04 7.30E00
-2. Average d1'uted concentration durtnn-batch discharaes uti/ml 2.41E-11 6.03E-11
- 3. Percent of ann 11 cable limit 1 1.21E-05 3.02E-05 D. GROSS ALPHA RADI0 ACTIVITY
.- Total Release Cj <LLD <LLD 1.49E01 i!. Average concentration released-durine batch discharoes uC1/gl <LLD <LLD E. VOLUNE OF NASTE RELEASED (prior to-dilution Liters 4.80E06 1.44E06 F. VOLLME OF DILUTION NATER USED DURING BATCH DISCHARGES Liters 1.48E10 1.04E10 G. TOTAL VOLUME OF DILUTION NATE t DURING DERLOO (OUARTER) Liters 1.95E11 4.27 Ell APPRovgp
'lWX.E HQDYMtGhN 9/0295c ,JtM j2]Np o.c.o.s.n.
_ ;1 t
QCP 100-525 Revision 5
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~
LIQUID EFFLUENTS - SL201ATION OF ALL RELEASES Qu4rter Quarter Est. Total i Unit nrat Becond Error. 1 '
A. FISSION & ACTIVATION PRODUCTS I
- 1. Total release (not including tritius. eases. alpha) 9.14E-02 1.31E-02 C1 7.30E00
- 2. Average diluted concentration durine batch discharnesr seriod uC1/mi 6.18E-09 1.26E-09 j 8.49E-02 7.75E-03
- 3. Percent of ==11 cable 11st
- 1 3.86E-02 3.25E-03 1
- 4. Itax" mum diluted concentrat on '
durina batch discharoes uC1/ml 4.11E-08 2.73E-09
- 8. TRITILM '
1 l
L
. Total relense Ci 1.88E01 4.24E00 5.90E00 l!. Average di'uted concentration durine batch discharaos uC1/mi 1.27E-06 4.08E-07
- 3. Percent of annlicable limit 1 4.23E-02 1.33E-02 C. DISSOLVED AND ENTRAINED GASES
- 1. Total relouse C1 3.57E-04 6.27E-04 7.30E00 2 .- Average d' uted concentration durine batch discharaos uC1/mi 2.41E-ll 6.03E-11 1 Percent of man 11 cable limit % 1.21E 3.02E-05 D. GROSS ALPHA RADI0 ACTIVITY L . Total Release C1 <LLD <LLD 1.49E01 l!. Average concentration released durine batch discharoes uC1/m] <LLD <LLD E. VOLUNE OF NASTE RELD.!!D (prior l l to dilution i Liters 4.80E06 l1.44E06 ,
F. VOL196E OF DILUTION NATER USED DURING BATCH DISCHARGES Liters 1.48E10 1.04E10 G. TOTAL VOLUME OF DILUTION MATER DURI4G pet.00 (0UARTER), Liters 1.95E11 4.27E11 APPROVED
'NHClLE 80)Y/EnN 9/0295c ,JWj2g o.c.o.s.m.
C
QCP 100-S25
- Revisign 5 LIQUID EFFLUENTS Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit First Second Sr-89 Ci <LLD <LLD 4.62E-04 4.13L-05 Sr-90 C1 <LLD <LLD 5.90E-05 5.24E-06 Cs-134 Ci <LLD (LLD <LLD <LLD Cs-137 C1 (LI D <LLD 3.53E-03 3.53E-04 I-131 C1 <tLD cud <tLD <LLD Co-58 C1 (uD <uD 2.10E-03 6,26E-04 Co-60 Ci (UD <LLD 4.64E-02 8.63E-03 Fe-59 C1 (LLD <LLD 1.26E-03 4.06E-05 Zn-65 Ci (tLD <LLD 5.71E-04 <LLD Mn-54 Ci (LI D < LI D 7.49E-03 1.30E-03 Cr-51 Ci <tLD (LtD 2.32E-02 6.98E-04 Zr-95 C1 <ttD <uD <LLD (LLD Nb-95 Ci (LLD <tLD 4.70E-05 < LI D Mo-99 Ci <UD (LLD <uD (UD Aa-110m C1 (UD (LLD 5.93E-04 4.42E-04 Ba-140 Ci (LLD ( LI D (LLD (I Ln Cs-136 C1 (un con < i tn <un La-140 Ci (uo <un 1.9st-os <un Fe-55 Ci (un <itn s.49t-03 t.oie-o, NLLD KLLD 1.4Ub-U4 NLLU Au-76 sb-124 C1 (LLD <LLD 6.45E-05 <LLD Total for Period (above) Ci <un
<un 9.14E-02 1.11F-o2 Xe-133 Ci <un (I_I D 1.97E-04 2.7sE-04 Xe-135 M Ci <: o n run 1.60E-04 t sor-on Prepared by ffpl Approved by m >m
/f ' Chemistry Supervisor c (final)
APPROVED l 9/0295c
- Scaled in vaiue based on last six raon t h ' s available data Q.C.O.S.R.
- EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT-Supplemental Information-Facility' Ouad Cities Nuclear Power Station Licensee Commonwealth Edison Company
- 1. Regulatory Limits a.. For Noble Gases:
Dose rate b 1. Less than 500 mrem / year to the whole body.
- 2. Less than 3000 mrem / year to the skin.
Dose Gamma Radiation
- 1. Less than or equal to 5 mrad / quarter.
2.- Less than or equal to 10 mrad / year ;
Beta Radiation 1
- 1. Less than or equal to 10 mrad / quarter.
- 2. Less than or equal to 20' mrad / year, b.,c. For Iodine-131, for Iodine-133, and for all radionuclides in 4 particulate form.with half-lives greater than 6 aoy.
l Dose Rate I i
- 1. Less than 1500 mrem / year Dose j
l
- 1. Less than or equal to 7.5. mrem / quarter i
- 2. Less than or equal to 15 tarem/ year. .
[ d. For Liquid:
l 1 Less-than or equal to 3. mrem to the whole body during any calendar year.
Less than or equal to 10 mrem to any organ during any calendar quarter.
?
Less than or equal to 6 mrem to the whole body during any calendar year.
[
Less than or equal to 20 mrem to any organ during any calendar year. !
l 0506R
a_____.__ . .
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- 2. Maximum Permissible Concentration a.,b.,c. For fission and activation gases, iodines, and particulates with halflives greater than 8 days, allowable release limits are. calculated by solving equations 10.l_and 10.2 from the.
Offsite Dose Calculation Manual. The alarm setpoint is one half of the most conservative value from-the two equations,
- d. For liquid effluents allowable release limits are calculated by solving equation 10.3 from the Offsite Dose Calculation manual. The MPC values used for the monitors were as follows; radwaste discharge 4.17 E-05 uCi/mi service water 2.0E-05 uC1/mi
- 3. Average Energy The average gamma energy used to calculate the alarm setpoints for the noble gas monitors was 0.570 Mev for the first quarter and 0.594 Mev for the second quarter.
- 4. Measurements and Approximations of Total Radioactivity
- a. Fission and Activatto, Gases:
- b. Iodints:
- c. Particulates:
The main chimney and reacto'r building ventilation exhaust. systems are continually monitored for iodines and particulates. These samples are pulled every 7 days and analyzed by gamma isotopic. The particulate papers-are composited every 31 days and sent to a vendor for Sr 89-90 and gross alpha analysis. Noble gas grab samples are pulled and analyzed by gamma isotopic every 7 days. Tritium samples are pulled and analyzed every 31 days.
-The continuous strip chart recorders for the annitors on the release points are reviewed monthly for spikes and tht activity released is calculated. An additional calculated activity for. noble gases is added-to the Main Chimney release each month. This calculation is done because most of the grab samples show less than the lower limit of detection due to the low amount of activity and the large dilution flow at the sample point. The calculation takes into account the normal offgas train and the gland steam contribution to the release.
The average flow at the release points are used to calculate the curies released.
0506R
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- ~, ,. -c
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. d. Liquid Effluents The river' discharge tanks are: analyzed before discharge by gamma isotopic. A-composite sample is taken during discharge. This is :
composited with other discharges that occurred every 31 days and is' ,
analyzed for tritium and gross alpha. The batch composites are composited quarterly and sent to a vendor for Sr 89-90 and Fe 55. The I discharge bay,is sampled every 31 days and analyzed by gamma isotopic-' '
for. tritium and gross alpha. It is sampled quarterly and sent-to a l vendor for Sr 88-90 and Fe 55 analysis.
The tank volumes and activities are used to calculate the curies i released for'the river discharge tank. . The total water released during the quarter and the activity is used to calculate the curies released for the discharge bay.
- e. Estimated Total Error Percent The estimated total error percents were calculated by taking the square l 1 root of the sum of-the squares of errors for sampling and measurement parameters. An error for line losses was included in the calculation of the error for gasseous lodine and particulates which resulted in an increase from previous calculated errors.
- f. Less than the lower limit of detection (<LLD).
Samples are analyzed such that the Technical. Specification LLD requirements are met. When a nuclide is not detected during the a quarter then <LLD is reported.
l l -5. Batch Releases 3 '
1 I
- a. ' Liquid
- 1. number of releases 37 1
- 2. total time 2.56E04 minutes
- 3. maximum time 9.45E02 minutes
- 4. average time 6.93E02 minutes
- 5. minimum time 3.60E02 minutes
- 6. average stream flow, discharge 6.01E01.gpm, dilution 3.34E05 gpm.
- b. Gaseous NONE
- 6. Abnormal Releases
- a. Liquid NONE
- b. Gaseous
- 1. An abnormal event was documented in License Event Report 90-006. A tornodo touch down on site and some minor damage to ventilation systems occurred. -
l l
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SOLID RADIOACTIVE HASTE
SUMMARY
UNITS 1/2 t QUAD CITIES STATION !
I l JANUARY 90 e
TRANSPORT BURIAL DATE COMPANY SITE VOLUME MILLICURIES. i
.01/03/90 CNSI BSC 205.80 6230.00 i 01/08/90 CNSI' - BSC 205.80 6152.00- 1 01/09/90 HITMAN SDG 660.00 325.60 01/16/90 CNSI BSC 205.80 17200.00 01/16/90 HITMAN SEG 1290.10 2586.00 '
01/22/90 CNSI- BSC 205.80 5446.00 01/24/90 CNSI BSC 83.40 227.39
.01/30/90 CNSI HASH 10!i.00 1553.45 '
l AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA !
-i MONTHLY TOTALS = 2961.70 39720.44 ,.
USE = U.S. ECOLOGY '
BSC = BARNWELL SOUTH CAROLINA CNSI- = ' CHEM NUCLEAR SYSTEMS INC. '
SEG = SCIENTIFIC ECOLOGY GROUP
~ HASH = HASHINGTON RAY = RAYTECH ,
QUAD = QUADREX :*
CNSIC = CHEM NUCLEAR SYSTEMS INC. CHANNAHAN b
i h p v *' F f'---/ -p-vy ,,,,,,+-'y-e_,e g- +,.w--y %-=,yg -
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~
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NY3 = .= . ,
Y I
. i~
L i
SOLID RADI0 ACTIVE WASTE
SUMMARY
i UNITS 1/2 QUAD CITIES STATION ,
FEBRUARY 90
{
TRAN .<T BURIAL DATE. COMeaNY SITE VOLUME MILLICURIES l
..__.. ... ......... ..__... -- ... ........--- r 02/05/90 -CNSI BSC 205.80 21730.00 '
02/07/90 HITMAN SDG 1007.20 694.10-02/09/90 CNSI BSC 205.80 54300.00 j 02/13/90 CNSI. BSC 205.80 27920.00 '
02/20/90 HITNAN SEG 660.00 385.30 -
120.30 194700.00 02/22/90 CNSI BSC 83.40 50200.00 02/23/90 CNSI BSC 02/26/90 HITMAN SDG 660.00 321.90 .
02/28/90 USE HASH 474.60 812.91 j AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA ,
i MONTHLY' TOTALS =- 3622.90 3S1064.20 USE ' = U.S. ECOLOGY BSC = BARNWELL SOUTH CAROLINA <
~CNSI = CHEM NUCLEAR SYSTEMS INC. a SEG' = SCIENTIFIC ECOLOGY GROUP !
HASH = HASHINGTON
- RAY. = RAYTECH !
- QUAD ' = QUADREX _ . i CNSIC = CHEM NUCLEAR SYSTEMS INC. CHANNAHAN i ,
l.
i I'< +
l-.
I
.. . . i o l 1
o I
SOLID RADI0 ACTIVE WAS'IT3 SUIMARY , !
UNITS 1/2 i
QUAD CITIES STATION MARCH 90 TRANSPORT BURIAL f; DATE COMPANY- SITE VOLUME MILLICURIES 03/02/90 '
HITMAN SDG 2080.00 193.80 03/05/90 CNSI BSC 205.80 -13230.00 !
03/12/90 CNSI BSC 205.80 67770.00
.03/14/90 HITMAN SEG 1290.10 1294.00 :
03/34/90 USE WASil 495.00 622.33'
'03/19/90 CNSI BSC 205.80 56830.00 f 03/22/90 HITMAN SDG 660.00 503.10 i 03/28/90 HITMAN SEG 2080.00 22.60
-AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA MONTHLY TOTAL 3.= 7222.50 140465.80 .
USEL = U.S. ECOLOGY '
BSC = BARNMELL SOUTH CARULINA CNSI = CHEM NUCLEAR SYSTEMS INC. t SEG = SCIENTIFIC ECOLOGY GROUP ,
NASH = HASHINGTON RAY. = RAYTECH QUAD = QUADREX. .
L CNSIC = CHEM NUCLEAR SYSTEMS INC. CHANNAHAN 1
i, 1
- l. L
,t l-a
+
t l
l
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SOLID RADIOACTIVE WASTE
SUMMARY
UNITS 1/2 QUAD CITIES STATION APRIL 90 TRANSPORT BURIAL DATE COMPANY SITE VOLUME MILLICURIES 04/02/90 HITMAN SEG 2080.00 22.60 HITMAN SEG 935.40 255.00 04/02/90 170.80 1135.50 04/05/90 CNSI BSC CNSI BSC 205.80 27200.00 l
04/09/90 105.00 701.93 04/10/90 CNSI WASH 04/16/90 CNSI BSC 205.80 72940.00 l
WASH 495.00 674.74 04/18/90 USE 682.50 712.90 !
04/20/90 AAY CNSIC KINDRICK QUAD 2080.00 22.60 04/23/90 105.00 402.13 04/24/90 CNSI WASH CNSI WASH 105.00 749.98 04/25/90 1040.00 11.30 04/30/90 KINDRICK QUAD ,
oce************************************************************************
MONTHLY TOTALS = 8210.30 104828.70 USE = U.S. ECOLOGY BSC = BARNWELL SOUTH CAROLINA
, CNSI = CHEM NUCLEAR SYSTEMS INC.
l SEG = SCIENTIFIC ECOLOGY GROUP i l'- WASH = WASHINGTON RAY = RAYTECH QUAD = QUADREX CNSIC = CHEM NUCLEAR SYSTEMS INC. CHANNAHAN
SOLID RADIOACTIVE WASTE
SUMMARY
t UNITS 1/2 QUAD CITIES STATION MAY 90 i TRANSPORT BURIAL DATE COMPANY SITE VOLUME MILLICURIES 05/01/90 CNSI BSC 205.80 18660.00 05/07/90 CNSI BSC 205.80 24290.00 0$/09/90 CNSI BSC 83.40 266.95 05/11/90 RAY CNSI 682.50 596.30 05/15/90 KINDRICK QUAD 921.50 130.80 05/16/90 CNSI WASH 105.00 778.74 05/21/90 CNSI BSC 205.80 30980.00 05/24/90 USE WASH 495.00 854.65
~05/29/90 CNSI BSC 205.80 10010.00 ono************************************************************************ f MONTHLY TOTALS = 3110.60 86567.44 ,
USE = U.S. ECOLOGY BSC = BARNWELL SOUTH CAROLINA CNSI = CHEM NUCLEAR SYSTEMS INC.
SEG = SCIENTIFIC ECOLOGY GROUP WASH = WASHINGTON RAY = RAYTECH QUAD = QUADREX CNSIC = CHEM NUCLEAR SYSTEMS INC. CHANNAHAN
P SOLID RADIOACTIVE WASTE
SUMMARY
UNITS 1/2 ,
QUAD CITIES STATION JUNE 90 TRANSPORT BURIAL DATE COMPANY SITE VOLUME MILLICURIES 06/01/90 CNSI BSC 205.80 17950.00 1290.10 231.60 06/18/90 KINDRICK QUAD 06/20/90 CNSI WASH 105.00 843.94 06/25/90 CNSI BSC 205.80 12190.00 ce*************************************************************************
MONTHLY TOTALS = 1806.70 31215.54 USE = U.S. ECOLOGY BSC = BARNWELL SOUTH CAROLINA CNSI = CHEM NUCLEAR SYSTEMS INC. -
SEG = SCIENTIFIC ECOLOGY GROUP WASH = WASHINGTON >
RAY = RAYTECH QUAD = QUADREX CNSIC = CHEM NUCLEAR SYSTEMS INC. CHANNAHAN t s
s
. . f QAP 1400-T1 l Revision 2 QUAD CITIES STATION ONSITE September 1985 i REVIEW ASSIGNMENT l
DATE J//g/fd REVIEW NO. 98-f f I
REVIEW PARTICIPANTS: t J /daleg k $fkJ M $ j
). /tM4.$
$ hcTe!
J Mmt :
4
, ASSIGNMENT:
);
V/9N YlW ? #f f hy/ {thM3 ffpMS$ (0>1790l AdfMW k& fA00tGS/ *Y ,
fd$/0h77V\t kh YA$h3 Y ht/At / bSC4 *,5 ,
CVMMM h5MS ANY JR>9ftvb' fpggr/b / fl/9btJV$. 9
]v M STATION MANAGER v
[" l APPROVED OCT 01985 (final) 0. C. O. S. R.
9/0321a ,
-__m_-_-_-__ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ , _ -.+_.,--e +-----,-w+-w-v..-w---v- ww--,.----- w-. - - ----- ---+ -w-- -
s ,
i OAP 1400-T2 QUAD-CITIES STATION Revision 4 ON-SITE REVIEW REPORT November 1987 Reference Information: OSR Recuest Ortainator:
OSR No: O"b Station ! Off-Site Review Review Date: NLA Other' Request Date: NFS BWR Engineering Subitet; hyph b/gf hectL$ frp799l &B,4WM gg o f lA$H467/M Yob YNIf (fCV []
Reason for Review:
Tech. Spec. 6.1.G.2.a / (On-Site)
Tech. Spec. 6.1.G.I.a (Off-Site)
Other: NRC Bulletin ;
4 Station On-Site,R_eferentt Materials (attach):
Safety Evaluation 8$[ /l@ 7/3 Procedures Affected Tech Spec Pages FSAR Pages AIR Number Other _
Disposition:
Routine Report Off-Site Review for Concurrence (T.S. 6.1.G.2.a.(S)) 7 AIR Issued (# )
NRC Submittal Needed Technical Specification Change Unreviewed Safety Question f,/
l Other / %
No Further Act1on 7///vy,fe ty/pN ge/ger Dyw/,m art lenpes, 7'J. f.9. YMv4 C./
Other APPROVED 9/0322a NOV 2 S 1987 0.C.O.S R
04, iiOO.ri
.evision : 1 SAFETY EVALUAf!0N CNICKttlf September 1948
. $4fety Ev lustien f YO Y M System # 2000
Title:
> a Y>m - l 1.a of t co F N f CF 4 4##f [#W7 SPI 918#MW9 '
s Descrt'NYJ dnc rn: eMron/ De**ru a ,/ Mr .v,med Ci?$nuse&$a#8 e day os%rs rPose op tKev*1uag: Af-m Aer/ew /m nr/ awe venu Anaca.u i 6-1.C. L sys oms aWi~c5mponents af rected:phg/c ,
1.4. Is this evaluation a JC0 (see CAP 110012 step C.1.b.)? Yes to I l
- 2. List reference documents reviewed which describe the components or aministrative controls !
applicable to the subject of this evaluation.
REFtithCE 00CLPitNTS ttYIEED
- a. FSAR Section(s) N/ f. Fire Protection Pro r ocu Pkg Section(s)
- b. $tt lection(s) N/ g. Code of Federal Regulations M
- c. Tech Spect h. Reg. Guides M
- d. Previous Safety Evaluations *
- 1. Procedures b
- e. Unit Operating License j. Other ,A/M
- 3. State the ef fects on the following functions:
- a. $1te or Security \
- b. Mechanical
- c. Structural l d. Electrical / . .
- e. Instrument and Control / l[/4 -
- f. Fire Protection I
- g. Radiological }
- h. Flood Protection /
- t. Aeninistrativs Control / // M A > M
- b / dm Me -
( -
- 4. If this evaluation is for a procedure, does the procedure or procedure revision constitute a change to a procedure as descri in the F$ art Explain: s#.3 / #- YES ( ) NO ( /
Of$ /f0f kh0h$ /Mi 0!Y$$ 7'$$lfA*9Vrp91
- 5. Does the subject or this evaluation involve operattng methods or configurations contrary to l gth intent described i the F$AR and further specified in t3e Tech specs? Exp1stn:
/ deb ett en Athy s*tA!.f .frWNM N AAVt Yts ( ) N0 (W ky W 7'A>F/ hA69AAM y a Tech. Spec, change required? Exp1stn: */ k d .h8dJ #7p / Yt$ ( ) NO (V 6.
Wey&'/Ad StW//M Te A & f A ,7) $ 9thf M L ppp y h af gy ppy,,
- If ALL of the answers in 4. 5. or 6 are N0. this evaluation is complete.
- If AKI of the answers in 4. 5. or 6 are Yts, answer the 10 CFR 50.59 questions on 0.P. 3 51-2. (CAP 300-$13. CAP 1100-T12, or QAP 1500-512)
- Send a copy of this checklist and any applicable 10CFR50.59 review forms to the Tech Staff Clerk.
APPROVED PREPARIO BY: ) DATE: / f8 2 -, gs SEP 261988 Q70.t. - di- G Daft:
is/0630. & -i.< final) 0. C. O. S. R.
- - -.. - _- - - .- - - _ - - - .- -. - -- - . . . ~ . - _ - - _ _
Rev. 0
, 1-1-47 05R FORM - 1 RECORD OF REQUEST FOR OFFSITE REVIEW sukJect &# fM$l kt $4l hernden d WW.C St{AbM1 ? Beet $$ (m73rl hpMm AdjoAar>H & /A)Ask j Station dW) d /W OnsiteReviewNo.N'h l Submitted by Date !
l Test or ex question. periment not involving an unreviewed safety Proposed test or experiment involving an unreviewed safety question -
Proposed change to procedure, equipment or system
/ involving an unreviewed satety question.
Proposed change to Tech. Spec. or license.
Unanticipated deficiency of design or operation of saf ety l
related structures, systems, or components.
( Proposed change to GSEP.
t Referral by T. S. Supervisor, Station Manager, Assistant i
Vice President and General Manager of Nuclear stations Division, or Manager of Quality Assurance
.dditional subject descriptions /5 / Ave /wr Me Aw a br
'1 M Ah/M hCh AYnu) euiAb*d>$sa oh IrmueAl km /nms. '
~~ ~
Supporting documents attached:
Date required for offsite Review completion:
Reason for specified dates
- j. Received by Date senior Participant offsite Review No.
IV-16
CAP 1400-72 aevision 6 l QUAD-CITIES STATION ON-SITE REVIEW REPORT l
OSRN0kO"[
+
l ON-SITF REVIEW
SUMMARY
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fa Psecewb o/ /,* d e ri n to'+ 644sk erroh de <
irded ,/ st yded/a fe<, skr.< 4,< poeewh ./
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l l-ON-SITE REVIEW RECOMMENDATION: gt
< $,wJ C, lies S4/im here dd MmM #/ f.
,1 /s.tiawe u4/ seate G,,not hkym k .ish fee r ~ fe musp u/d a. -
h hter f M k!S h A9 Web kt y, t. ti. Also Mw/ % 1/exec &W/bfYm de *!
fdydend /Afk*ljo 4'!M' S*)***I y fe d S
- M C/
Ser;- aeol f
PARTIC) PANTS: !
x M M a" n' ~ -, -
[ Approved: 1>32h Sta t fon' ManagerO I l ATTACHMENTS:
- Date
- 4 / /b b '
i j APPROVED NOV 281987
- 0. C. O. S R.
9/0322a " ' " *d) 1 L ._- .--- _