ML20082K954
| ML20082K954 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/30/1991 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20082K939 | List: |
| References | |
| NUDOCS 9109030128 | |
| Download: ML20082K954 (15) | |
Text
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i QCP 100-525 l l Revision.5 C '
EFFLUENT AND HASTE DISPOSAL Harch-1989-
- SEMI-ANNUAL - REPORT _ Janua rv-June 1991
- GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES p;
j- PROCEDURE: QCP 100-7.
.i e Quarter Quarter .Est. Total Untt First Second Error. ,%__,
A. FISSION & ACTIVATION. GASES l-i: ..
8.8
- l. Totc) Release C1 6.36E00 1.09E01
- 2. Average release rate for period pCl/sec 8.17E-01 'l.39E00 4 3. Percent of Tech Spec limit
- 1.85E-02 1.10E-02
[
s Chimney & stack % 1.75E-03 1.02E-03 i B. IODINE l-i i 1. Total ~ Iodine-131- Ci 3.07E-04 3.44E-u4 31.8 l ' 2. Average release rate for period uC1/sec 3.95E-05 4.38E-05 C. PARTICULATES
- 1. 1. Particulates with half-lives
> 8-days Cl 6.26E-03 1.69E-03 17.7 ,
p 2. Average release rate for period uC1/sec 8.05E-04 2.15E-04 I :3. --Gross alpha radioactivity Cl LLD LLD**
4
- D. TRITIUM l '. Total Release C1 3.95E01. 4.07E01 6.9
! 2. Average release rate for period pC1/sec 5.08E00 5.17E00 E. IoJine 131:& 133 Tritium and Particulates t
Percent of Tech spec Limit ~
Chimney & stack 1 8.29E-Ol 6.39E-Ol
- NOBLE GAS GAMMA / NOBLE GAS BETA DOSE LIMITS
- Projected value based on previous 6 months available data.
? ,
i APPROVED JUN f 21989 9/0295c '
Q.CO.SA 9109030123 910725 POR N- ADOCK 05000234 PDR
- t. <-
QCP 100-S25 Rrvision 5 1
- a MAIN CHIMNEY-GASEOUS EFFLUENTS l--
Continuous Mode Batch Mode Quarter Quarter _Q uarter Quarter Nuclides Released Unit FIRST SECOND
- 1. -Fission gases-Kr-85 C1 lim Ltn Kr-85m -C1 5.13E-02 2 .,00E-01 Kr-87 Ci 1.99E-01 '3.08E-01 _
Kr-88 __
C1 1.20E-01 3.00E-01 Xe-133 C1 1.13E-01 1.71E-01 Xe-135 Cl 1.89E-01 2.89E -Xe-135m- Cl 1.00E 00 1.58E 00 Xe-138 Cl 4. 23E co 7.94E 00 Ar-41 C1 _
4.61E-01 1.12E-01 C1 Cl Cl Total-for-Period C1 6. 36E 0 0 1.09E401
-- 2 . Iodines I-131 C1 3.02E-04 3.37E-04 _
I-133 Ci 1.42E-03 6.58E-04 I-135 C1 2.49E-01 6.61E-04 4
Total for Period C1 4.21E-03 1.66E ,
i-APPROVED JUN 121969 9/0295c Q.C.O.S.R.
- QCP 100-S25 Revision 5 HAIN CHINNEY l GASEOUS EFFLUENTS Coritinuous Mode Batch Hode Quarter Quarter Quarter Quarter Nuclides Released Unit rIRST SECOND ,
- 3. Particulates Sr-89 Ci 1.s4F-04 j.19E-04 Sr-90 Cl 5.36E-07 < LLD Cs-134 Ci ' u .D <LLD Cs-137 Ci I.Ie2-0s < LLO _
Ba-140 C1 4.16E-0, 7.35E-05 La-140 Ci 2.07E-04 2 . 5 2 t'-04
__Cr-51 C1 1.28E-04 7.91E-05 _
Hn-54 Ci 1.26E-05 < LLD Co-58 C1 < LLD < LLD Co-60 Ci 1.65E-04 7 .15 E- 05 I-131 Ci < LLD 6.50E-06 Ao-llora Ci < LLD < LLD I-133 C1 2.53E-04 < LLD _
Mo-99 _
C1 1. 39E- 04 3.78E-06 Ci s Ci_
Ci ,
Total for Period C1 1.49E-03 6.07E-04 APPROVED JUN 121989 9/0295c Q.C.O.S.R. 1 l
c
" ~ '
-QCP 100-S25
. Revision 5-REACTOR VENTILATION GASmlS EFFLUENTS '
I' Contir#uous Mode Batch Mode ~
Quarter Quarter Quarter . Quarter
_Nuclides Released Unit FIRST. SECOND
. -- 1. Fission gases Kr-85 Ci < LLD < LLD Kr-85m Ci < LLD < LLD Kr-87 C1 < LLD < LLD ,
_Kr-80 Ci < Lt D < LLD _
_Xe 135 _
C1 < LLD < LLD Xe-135m Cl < LtD < LLD
-Xe-138 Ci < u.D < LLD _
Ci < LLD < t LD Ci < LLD < LLD Total for Perlod Ci < LLD < LLD _
< 2. -Iodines i
I-Ii131 C1 5.0$E-06 <LLD
~
I-133 C1 1.03E-04 < LLD
+
I-135 Ci < Lt o < LLD Total for Period Ci 1.08E-04 < LLD o
l-
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- L APPROVED l
JUN 121989 ,
9/0295c OR
. QCP 100-525 Revision 5 REACTOR VENTILATION l GASEOUS EFFLUENTS Continuous Mode Batch Hode Quarter Quarter Quarter Quarter Nuclides Released Unit FIRST SECOND
- 3. Particulates Sr-89 C1 6.34E-05 1.34E-04 Sr-90 Ci 1.41E-06 1.4lE-06 Cs-134 Ci (LLD < LLD Cs-137 C1 S.46E-05 5.45E-05 Ba-140 Ci <LLD <LLD l
_La-140 Ci <LLD <tLD Cr-51 C1 3.20E-05 8.05E-05 Mn-54 C1 4.75E-04 5.56E-05 ,
Co-58 Ci 7.37E-05 <1.LD Co-60 Ci 4.04E-03 5.96E-04 I-131 , , _
Ci (LLD <LLD An-110m Ci <LLD <LLD Zn-65 C1 9.37E 07 (LLD Co-57 Ci <LLD 2.f4E-06 Mo-99 Ci d.LD 1.60E-04 C1 C1
~
Total for Period C1 4.77r-01 1.08E-03 APPROVED JUN 121989 9/0295c Q.C.O.S.R.
--. _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ __-______A
< QCP 100-S25 .
Revision 5 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Quarter Quarter Est. Total Unit FIRST SECONn Error. %-
A. FISSION & ACTIVATION PRODUCTS
- 1. Total release (not including-tritium, cases, alpha) Ci** 7.20E-01 1.35E-03 7.2
- 2. Average diluted concentration during batch discharcesr period uC1/ml 3.63E-04 1.79E-09 2.02E-01 3.19E-03 3 .- Percent of applicable limit * % ** I.97E-01 1.44E-03 4, Maximum diluted concentration durina batch O tqharaes 9C1/ml 1.12E-08 1.79E-09 8 TRI TIUM .; **N0i u. A1 A3 and B1 First Quarter include activity from RilR leak.
All,other Fira.t Quarter are for normal batch release.
_1. _. Total reloase- Ci ** 3.35E-00 4.60E-01 6.7
- 2. Average-d,1uted-concentration durina batch lischarces uC1/ml 2.00E-06 6.08E-07 L
- 3. Percent of aDDlleable limit % 6.70E-0? 2.03E-02 C. DISSOLVED AND ENTRA:NED GASES
~
- 1. Total release ~
Ci 1.llE-05 < LLD 7.2
- 2. Average diluted concentration
' during batch discharaes uC1/mi 6.8sE-l? <Ltn
- 3. Percent of applicable limit ,
% 3.43E-06 0. 00E 0 0
, :D. GROSS ALPHA RADIOACTIVITY-
- durina batch discharaes uC1/mi <LLD < LLO e
i E. VOLUME OF WASTE RELLASED (prior -
to' dilution- Liters 6.15 E 05 9.84E04 F. VOLUME OF DILUTION HATER USED
, DURING BATCH DISCHARGES Liters 1.62E09 7.56E08 G. . TOTAL VOLUME OF DILUTION l
- l WATER DURING PERIOD (0UARTER) Liters 2.13 Ell lj.44 Ell APPROVED L "WHOLE SCDY/ ORGAN .
9/029Sc. JUN 121999-O.C.O.S.R. -
- - . .__ _ _ .~ _ _ _ - - - -
QCP 100-525 Revision 5 LIQUID EFFLUENTS Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit FIRST SECOND FIRST SECOND
_Sr-89 Ci < Lt D < LI.D 4.60E-03 1.87E-05 Sr-90 Cl <1la < Lt.D 1.77E-05 2.07E-06 Cs-134 C1 <t1.D < t I.D <1.1.D :1.LD Cs-137 C1 < L t .D < LLD 1.20E-03 1.48E-04 I-131 Ci < Ll D ( t.LD <Lt D <tLD
_Co-58 Ci <tt.D < Lt.D 2.02E-02 2.17E-05 Co-60 C1 <1 LD < LLD 5,80E-Ol 9.84E-04
_f_e-59 Ci <tLD < LLD <tLD < 1.L D Zn-65,, Ci <t.1.D < LLD 2.02E-02 <tLD
_Mn-54 C1 < 1.1.D < Lt.D 2.99E-02 6.00E-05 Cr-51 C1 <t.t.D < LLD ' LLD LLD Zr-95 C1 <1.LD < LLD <
LLD CLLD Nb-95 Ci < t.LD < LLD s LLD CLLD Mo-99 C1 <LLD < t.LD c LLD (LLD
-Aq-110m C1 <LLD < LLD 9.67E-5 (LLD c'
k _Ba-104 Ci <LLD LLD <LLD CLLD Cs-136 _
Ci <tLD < LLD (LLD CLLD La-140 Ci <LLD < LLD <LLD (LLD Fe-55 C1 <LLD < LLD 6.36F-02 1.18E-04 Unidentified C1 ' tLD
< <LLD < LLD ( 1.LD
_ Total for Period (above) C1 <LLD < LLD 7.20E-01 1.35E-03 Xe-133 Ci <LLD < LLD <LLD C 1.LD Xe-135 C1 <LLD < LLD 1.I1E-05 < LLD Prepared by M b 4T1- 9\ Approved by _ h.
's '
' ] Chemistry Supervisor l (final)
APPROVED
- 9/0295c JUN 121969
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EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information faci 1ity QV ALClticLNut]earlowetStation L1censee Comm0 weal th.. Edison.. Company
- 1. Regulatory Limits
- a. For Noble Gases:
Do5e rate
- 1. Less than 500 mrem / year to the whole body.
- 2. Less than 3000 mrem / year to the slin.
Dose Gamma Radiation
- 1. Less than or equal to 5 mrad / quarter
- 2. Less than or equal to 10 mrad / year Beta Radiation
- 1. Less than or equal to 10 mrad / quarter.
- 2. Less than o' equal to 20 mrad / year b.,c. For Iodine-131, for lodine-133, and for all radionuclides in particulate form with half-lives greater than 8 days.
Dose Rate
- 1. Less than 1500 mrem / year Dose
- 1. Less than or equal to 7.5 mrem / quarter
- 2. Less than or equal to 15 mrem / year,
- d. For liquid less than or equal to 3 mrom 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 MMn 154
- 2. -Maximum Permissible Concentration a..b.,c., For fission:and activation gases, lodines, and particulates with halflives greater than 8 days, allowable release limits are calculated by solving equations 10.1 and 10.2 fecm the Offsite Dose Calculation Manual. The alarm setpoint is one half of the.most conservative value from the two equations, d - for 11guld effluents allowable release limits are calculatad by solving equation 10.3 from the Offsite Dose Calculation manual. The MPC values used for the monitors were as follows:
radwaste discharge 4.46 E-05 uC1/ml service water 2.0E-05 uCt/mi
-3. Average Energy The average gamma energy used to calculate the alarm setpoints for the noble gas monitors was 0.514 MeV for the first quarter and 0.587 Hev for the-Second quarter.
! 4. Measurements and Approximations of Total Radioactivity
- a. Fission and Activation Gases:
- b. Iodines:
- c. Particblates: ;
The main chimney and reactor building ventilation exhaust systems are l 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 j and gross alpha analysis. Noble gas grab samples are pulled and analyzed by gamma isotopic weekly. Tritium samples are pulled and
-analyzed every month.
The continuous strip chart recorders for the monitors on the release points are reviewed monthly for spikes and the 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 19ss 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 91ard steam contribution to the release.
The average flow at-the release points are used to calculate the curies released.
STMOR 154
- d. Liquid Effluents i
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 discharge bay is sampled every 31 days and analyzed by gamma isotopic, for tritium and gross alphh. It is sampled quarterly and sent to a vendor for Sr 89-90 and Fe 55 analysis.
The tank volumes and activities are used to calculate the curies 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 root of the sum of the squares of errors for sampling and measurement parameters. The estimated total error percent for the solid radwaste curies is 13%.
- f. Less than the lower limit of detection (<LLD).
Saaiples are analyzed such that the Technical Specification LLD requirements are met. When a nuclide is not detected during the quarter then <lLD is reported.
- 5. Batch Releases
- a. Liquid
- 1. number of releases 6
- 2. total time 3502 minutes
- 3. maximum time 797 minutes
- 4. average time 584 minutes
- 5. minimum time 406 minutes
- 6. average streara flow. dfscharge 63.1 gpm, dilution 2.91 E+05 gpm
- b. Gaseous NONE
- 6. Abnormal Releases
- a. Liquid On January 14, 1991 a leak developed on the Unit One ' A' Residual Heat Removal Heat Exchanger. Unit One was in a refuel outage and this heat exchanger was being used for shutdown cooling. The 'B' heat exchanger was out of service for maintenance. The heat exchanger was isolated for repair on February 11, 1991. A total of 8.34 E+05 uCi of activity was released. This release was added to the liquid release for the month of January 1991.
b, Gaseous NONE STMOA IM I
i
4 SOLID RADIOACTIVE WASTE
SUMMARY
UNITS 1/2 QUAD CITIES STATION JANUARY '991 DATE TRANSPORT CO. BURIAL SITE VOLUME MILLICURIES 1/4/91 CliEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 33990.00 1/14/91 CllEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 45270.00 1/17/91 RAY-TECil U.S. ECOLOGY, WA 474.60 758.99 1/21/91 RAY-TECil CHANNAllAN 660.00 394.30 1/29/91 CilEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 27530.00
....... ....u.....
MONTHLY TOTALS 1752.00 107943.29 r
1 .
SOLID RADIOACTIVE WASTE OUMMARY UNITS 1/2 QUAD CITIES STATION FEBRUARY 1991 DATE TRANSPORT CO. BURIAL SITE VOLUME MILLICURIES 2/6/91 RAY-TECli CllANNAllAN 675.00 728.40 2/13/91 KINDRICK TRUCKING QUADREX 2080.00 2.33 2/14/91 KINDRICK TRUCKING QUADREX 1290.10 109.80 2/19/91 CllEM NUCLEAR SYSTEMS BARNWELL, SC 170.80 24260.00 4
2/22/91 RAY-TECH U.S. ECOLOGY, WA 493.70 902.27
== ===
MONTilLY TOTALS 4709.60 26002.80
t 4
^
SOLID RADIOACTIVE WASTE
SUMMARY
UllITS 1/2 QUAD CITitS STATIO!1 MARCil 1991 DATE TRAllSPORT CO. BURIAL SITE VOLUME MILLICURIES 3/6/91 NAY-TECil CilAN!1A51AN 630.00 564.50 3/11/91 CilEM NUCLEAR SYSTEMS 13ARb :,, s, SC 170.80 21850.00 3/19/91 CilEM NUCLEAR SYSTEMS bARNWELu, SC 170.00 35050.00 3/20/91 CllEM NUCLEAR SYSTEMS U.S. ECOIEGY , WA 107.00 3328.92 3/21/91 KINDRICK TRUCKING QUADREX 1350.10 175.50 MONTHLY TOTALS 2426.70 61768.92
. l 4 ,
r 1
i i
j SOLID RADIOACTIVE WASTE
SUMMARY
UNITS 1/2 l' l QUAD CITIES STATION 4
APRIL 1991
, DATE- TRA!! SPORT CO. DURIAL SITE VOLUME MILLICURII:S 4/9/91 CllEM NUCLEAR SYSTEMS BARNWELL, SC 170.80 23550.00 1 I
.4/12/91 CllEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 405.50 -
4/13/91 RAY-TECH CHANNAllAN 502.5C 497.61 4/16/91 CilEM NUCLEAR SYSTEMS DARNWELL, SC 205.00 539.50 l .
j 4/17/91 C}lEM NUCLEAR SYSTEMS BARNWELL, SC- 300.34 726.30 ,
4/34/91 IIITTMAN SCIENTIFIC ECOLOGY .1290.10 60.97
........ n........ ,
MONTilLY TOT;.LS 2683.34 26779.88 p
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SOLID RADIOACTIVE WASTE
SUMMARY
UNITS 1/2 QUAD CITIES STATION MAY 1991 DATE- TRANSPORT Co.- BURIAL SITE VOLUME MILLICORIES 5/2/91 CllEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 741.70 5/8/91 CHEM HUCLEAR SYSTEMS BARNWELL, SC 120.30 68660.00 ,
5/9/91 CHEM NUCLEAR SYSTEMS BARNWELL, SC 120.30 66590.00 5/9/91 RAY-TECH U.S. ECOLOGY, WA 382.50 958.55
- 5/15/91 CllEM NUCLEAR SYSTEMS BARNWELL, SC 120.30 63900.00 5/30/91 CHEM NUCLEAR SYSTEMS DARNWELL, SC 120.30 130900.00 5/23/91 KINDh1CK TRUCXING QUADREX 1290.10 81.32 5 5/38/91 CHEM NUCLEAR SYSTEMS 1ARNWELL, SC 120.30 163400.00 MONTHLY '10TALS 2479.90 495231.57
)
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1 I
SOLID RADIOACTIVE WASTE
SUMMARY
l UNITS 1/2 QUAD CITIES STATION JUllE 1991 l
DATE TRANSPORT CO. BURIAL SITE VOLUME MILL 1 CURIES l i
l 6/3/91 CllEM HUCLEAR' SYSTEMS BARNWELL, SC 120.30 103800.00 t
6/6/91 CllEM NUCLEAR SYSTEMS BARNWELL, SC 120.30 223600.00 6/13/91- CilEM NUCLEAR SYSTEMS BARNWELL, SC 120.30 184400.00 6/13/91 RAY-TECil CilANNAllAN 525.00 240.30-6/34/91 Cl!EM NUCLEAR SYSTEMS BARNWELL, SC 205.80 17990.00 6/27/91 CllEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 16200.00
======== == ......
MONTitLY TOTALS 1297.50 46230.30 L
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s QAP 1400-11 Revision P.
, QUA0 CITIES STATION ONSITE September 1985
- REVIEW ASSIGNMENT l
DATE _ N 2 / _
REVIEW NO. 9/-/7 _ _
REVIEW PARTICIPANTS:
P. Bahua
. /e WIS R . /Jerz i l d . 5%e<s& l
- d. bt/ot<Mll ASSIGNMENT:
6 L/16b0 SeV lO OI 7ke had cl dillec~ a Paocesb C o,,lu) Squ<m A,e % ce uil7 &diwe.li ve.
0 YASbCS bo k MUM 6 Ybflil c / e s c g ,4 (p 3 cejexesl p < ukes s , J na s c~<a a., s, s,,,,s.
kh+
, STATION MANAGERI / l APPROVED OCT 01985 (final) 0.C,0 S.R.
9/0321a '
X o, ,
- Mr >a. ,
s &(v ;a
(.
e.g .;!',i : : '.
gq.gn N ,, REPORT 05R C b lhb -
ON-Sill R[Vl[W (UMMR,p CL/ lL(Os1 \O o .' kg &gAh (; beg hgoces &g&
o9 pen bd. 4oCeLtth* $ /A$ IOAc $8 Ve h e b & A .sb e, h%eehb be InNe
- yh hII $6ChtYC Ac1Jl/f bInt b &
puee u.;, 4 2d,ose.iwe. wd edes And Re[hd6 .
SfA//m /24cd/c.c6
_0_N-SITE REVIEW RECOMMENDAt!ON:
b6 0$ f.gch7H1'H1t'nc.5 4knb YC "
ht/th$ lo hir,$
3!A ble'H hl0 CESS & n r2 0 l h /20 cf 2 M / W I ll4 f)/oceMlil 00 A0IOA&beJC Yeb h&c fey lC " $g /tyng),esgh><) /l1 sisk wdaus. 5s%if Ae c/sdiin Pcp 6 rhe N'ec.
M1 8ep$$r?M 5 Yet)tW/ h?clsodclWG Ilf/pt%7h St!leM$e hef04h M'fr(%$rs? h &
bff)G _.
SJ 6A U
0$s)
^ ' ?
Approvec: .
L -ATTACHMENTS:
/ 1--
Date: -
/ / --
l
! APPROVED L
mnn AUG 0 81990 o/0322a Q,C.O.S.R.
l q 4r N r M V - ye,- p u y 4-y- w's--gy ee-yPsy +>y--a-- -1r-m,e- yene e +- -- % m-Cru- -v-w 9 *e +twre -ev-w g- =%--f-ee--ewy
9 0@ i '
- 3U
' ;iA110N Ret '"" b 0' '. . i.tv'liW REPORT July i.490
.j 'erence Inf m * + t i_ ~ ' kt a ve s t Orj g i na t;-
- t '..
bl-M_ _ I./ Off-Site Ro ita .
Review Date: NLA Other' _
Re::etit N te: NFS BWR D ginetring Sut>m t - hgyp) [i feb fgocegg gy,l,quj (Q ,p,,,,n ,, l,5 ,
k u Ceb W if Ph b 1cll(M c W e e h &ph (ffg, /g)
Reason for Review: /
Tech. Spec. 6.1.G.2.a / (On-Site)
Tech. Spec. 6.1.G.I.a / (Off-Site)
Other: NRC Bulletin _
Station ,-
On-Site Reference Materials (attach):
Safety Evaluation 1/602. Procedures Affecter 1 Tech Spec Pages J,ffd.P (,'l-/ [p,/8-/
FSAR Pages AIR Number Other Disposition:
Routine Report _
Of f-Site Review for Concurrence (T.S. 6.1.C. I .a. ) l AIR l$ sued (# )
NRC Submittal Needect Technical Specificatior. Change Unreviewed Safety Question other ~/ R k / eb')r M m &#s / nn yk No Further Action fAcl,'veclrn 5ff/ve/1f /e/eASL Atf*Ef,^ 2Ad** '0 'l Other APPROVED 9/0322a AUG 0 81990 Q.C.O.S.R.
. '. s i
~?
QAP 1100-519 Revision 1 10CFR$0.59 SCREENING FOR PROCEDURE December 1990 CHANGES, TESTS AND EXPERIMENTS Procedure Screening Number: PS-7/- 622. ,_ _
NOTE Where the preparer is confident that a 10CFR50.59 screening will indicate that a 10CFR50.59 Safety Evaluation is required, it is permissible to proceed directly to the 10CFR50.59 Safety
- Evaluation (QAP 1100-521).
Procedure, Test or Experiment
Title:
O O Ak b les 2 oc ev. [on/2.o/
hi2cqu2Any A s.oM4iFM A l btY10Ab k ll b ll 1Ah Eev (b Procedure, Test or Experiment Number. ,,,,,
Unit (s): O Applicable Plant Mode (s): A Ll-.
(RUN, STARIUP/ HOT SINBY, REFUEL or SHUIDOWN)
- 1. Is the procedure revision, addition or deletion for a QGA procedure:
( ) Yes - STOP and perform 10CFR50.59 Safety Evaluation (this form may be discarded)
( K ) No - proceed to step 2
?. Is the procedure, test or experiment revition an editorial change to a previously approved procedure, test or experiment as determined below?
(This ir, applicable to both 'O' and 'QC' procedures.)
YES NO
( ) ( ) Rewording withc.ut changing actions to be accomplished (N ( ) Addition of clarifying information, such as:
- Location of conponents
- Lists of toolt required
( ) ( ) Changes to personnel proper names or pnone numbers
( ) ( ) Spelling, grammar or punctuation changes
( ) ( ) Forr.at changes (changes to form but not action)
( ) ( ) Other - provide justification as to why this change is an administration change:
APPROVED 4098a Q.C.O.S.R.
, QAP 1100-519 Revision 1 15 full scope of this change encompassed by one or more of the above?
( d Yus - screening is complete, proceed to step 9
( ) No - proceed to step 3
- 3. Has a 10CFR50.59 Screening of Safety Evaluation been previously performed that identiftes thtt procedure change, test or experiment?
(Previ usly performed screenings or safety evaluations are valid as long a'. systems are not modified in a way which would change interactions with systems described in the UFSAR.)
( ) Yes - screening is complet), proceed to step 8 (Note the previous evaluation nu.v.ber where indicated.)
( ) No - proceed to step 4
- 4. List the reference documents reviewed for this 10CFR50.59 screening.
(Identify documents referenced even if no information was found in that section.)
- a. UFSAR Section(s):
- b. SER Section(s):
- c. Tech Spec Section(s): ,,,,, __
- d. Fire Protection Program Document Pkg Section(s):
- e. Code of federal Regulations Section(s):
- f. Regulatory Guides (NUREGs):
- 5. Does the affected procedure do any of the following:
- Establish administrative controls described in the UFSAR.
- Control plant operating conditions described in the UFSAR.
- Implement specific UFSAR commitments.
( ) Yes - STOP and perform 10CFR50.59 Safety Evaluation (this form may be discarded)
( ) No - proceed to step 6
- 6. I:: the affected procedure or procedural activity outlined, summartzed, or completely described in the UFSAR or Technical Specifications?
( ) Yes - STOP and perform 10CFR50.59 Safety Evaluation (this form may be discarded)
( ) No - proceed to step 7
. APPROVED DEC 311990
" ~
Q.C.O.S.R.
'a, i
' 0AP 1100-519 .
Revision 1
- 7. Does the activity perform tests or experiments not described in the UfSAR or change the procedure for performing tests / experiments previously approved in accordance with 10CFRSO 597
( ) Yes - STOP and perform 10CFR50.59 Safety Evaluation (this form may be discarded) ,
( ) No - proceed to step 8 ,
I
- 8. Implement Chances - Based on this evaluation, I have determined that the '
proposed facility change:
(x) will not change procedures described in the UFSAR, and, will not result in a test / experiment not described in the UFSAR !
l or
( ) has been previously evaluated - note previous evaluation ciumber
\ u !T) AbM ~
Preparer 3Tgnature 'Da1 e'
- 9. [teview - The reviewer agrees with the determination that no Safety Evaluation is required.
Shih Reviewer Signature Ob 1)
Date
- 10. Ottain facility change screening number from the Tech Staff clerk and note on page 1. The original screening documentation shall be filed by the Tech Staff clerk. Cop!'s are to be placed . tith the applicable <
package (s).
l i
l l
l i
i APPROVED I
<rtnai) 4008a DEC 311990 l ncnce
-- - - . - .. ..