ML19224B249
| ML19224B249 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/08/1979 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| 1621, TM-0086, TM-86, NUDOCS 7906140289 | |
| Download: ML19224B249 (21) | |
Text
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e 3
D{I DOCUMENTS
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DOCUMENT NO:
COPY MADE ON OF DOCUMENT PROVIDED BY g
METROPOLITAN EDISON COMPANY.
Wilda R. Mullinix, NRC t
7906140289 I94 328 e
e
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1621 Revision 14 02/08/79 THREE MILE ISLAND NUCLEAR STATION
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STATION HEALTH PHYSICS PROCECURE 1621 RE!. EASING RADI0 ACTIVE LIQUID WASTE - UNIT 1 MASTER CO3 Tab:e of Effective Pages ace Date R evision Pace Date Revision Pace Date Revision o
1.0 02/25/76 a
2.0 01/04/79 13 3.0 02/25/7G 5
4.0 10/21/76 8
4.1 10/21/76 8
5.0 02/25/76 3
6.0 02/25/76 5
7.0 02/08/79 14 8.0 02/08/79 14 9.0 02/25/76 5
10.0 07/14/78 11 11.0 06/07/78 12 12.0 07/14/78 11 13.0 02/25/76 5
14.0 02/25/76 5
15.0 03/17/78 10 16.0 02/08/79 14 17.0 08/26/76 6
18.0 02/08/79 14 19.0 02/08/79 14 Unit 1 Staff Recornme d ' Approval Unit 2 Staff Rec mme ds kpproval Approval
/
r-Date A pproval....
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r Date CogndantWpt. head Coghizah/r/ept. Nead Unit 1 PORC Recommends Approval Unit 2 PORC R omme nde Approval 8 F.B" Date N7/M
\\
/
Date
(/ Chairman of PORC Chairrrpn oh1$ R d
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Unit 1 Super ~ tendent App.7 val Unit 2 Superi tend t proval E dA /A Date,k k
Date
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/ I l
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Manager Generation Quality Assur ince Approval Date l 9 4 3 2 %,.....,,,
Revision 5 e
SHP 1621 02/25/76 THREE MILE ISLAND NUCLEAR STATION STATION HEALTH PHYSICS PROCEDURE 1621 - Releasing Radioactive Liquid Waste - Unit 1 1.0 PURPOSE This procedure describes the regulations applicable to radioact !e liquid discharges to unrestricted areas and the mor. '1 ring programs designed to ensure compliance with these regulations.
2.0 DISCUSSION 2.1 In raie: sing radioactive effluents to the Susquehanna River, it is necessary to keep the resulting dose to man and lower biota as low as reasonably achievable.
Therefore, radioactive liquids discharged from the plant are analyzed so that releases will meet Technical Speci-fications. RM-L6 monitors liquid radioactive waste prior to entering the Mechanical Draf t Cooling Tcwer effluent. RM-L7 monitors liquid radioactive waste after dilution by the effluent from the Mechanical Draft Cooling Tower (MDCT).
2.2 Liquid radioactive wastes are diluted in the effluent of the mechanical draf t cooling towers by factors ranging from 167 times to 7600 times, depending upon the water intake from the river.
The diluted radio-logical waste coming from the mechanical draft cooling towers is further diluted by the flow of the Susquehanna River.
At low flow (1700 cfs), the river would dilute the effluer.t by a factor of 20.
However, at normal river flow (34,000 cfs), the dilution from
+
the river would be 403 times. A minimum effluent rate of 5000 gpm is 2
maintained from the mechanical draft cooling towers.
Dilution credit is taken for cooling tower effluent rates up to 38,000 gpm, although 194 330 1.0
I Revision 13 SHP 1621 01/04/79 higher flow rates (greater dilution) will exist at times.
2.3 Three sump (Borated Water Tank Tunnel Sump, Heat Exchanger Vault Semp, and Tendon Access Gallery Sump) normally collect ground water that may seep into the areas they drain.
The discharges from these sumps are joined and sent to the miscellaneous Waste Storage Tank for processing.
2.4 Laundry Waste Storage Tanks are sampled prior to discharge.
If the activity in the tank exceeds 1 x 10-7 Ci/cc, the contents will be processed in the radiological liquid waste disposal system.
2.5 The instantaneous concentrations of radioactive effluents from Unit-1 to the environment shall not excer ' the 10CFR20, Appendix B, unrestricted area MPC's.
2.5.1 The total curies released should not exceed 2.5 Ci per quarter (exclusive of tritium and dissolved gasses).
Under special conditions, this limit can be increased to 10 Ci per quarter, however, this requires notification of the Nuclear Regulatory Commission (NRC) within 3C days.
2.5.2 Specific chemical parameters must also be verified on each release of the Waste Evaporator Condensate Storage Tank (pH, Boron, conductivity, alkalinity, soligs, and iron).
2.6 Analyses performed will be in accordance with the Envrionmental Technical Specifications.
3.0 REFERENCES
3.1 FSAR, Volume 4 and 5
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194 33l 2.0
6 Revision 5 SHP 1621 02/25/76 3.2 10 CFR 20 3.3 10 CFR 50 3.4 OP 1104-43 3.5 OP 1104-29A thru W 3.6 Environmental Technical Specifications 3.7 HPP 1720 thru 1722 3.8 HPP 1629, HPP 1625, and HPP 1675 3.9 CP 1900, CP 1901, CP 1913, CP 1918, CP 1925, CP 1930, CP 1950, CP 1951, CP 1958.
3.10 Industrial Waste Permit No. 2270204 3.11 Victoreen Tech. Manual 3.12 SP 1301-6.3 4.0 EQUIPMENT 4.1 GeLi detection system 4.2 Liquid Scintillation detection system 4.3 Sampling container 4.4 Beckman Wide-3ata 5.0 OPERATING INSTRUCTIONS Prior to the release of liquid to the station effluent from the Waste Evaporator Condensate Storage Tanks A or B, the Laundry Waste Storage Tank or any other tank containing radioactive material, Liquid Release Permit must be obtained.
NOTE:
In these OPERATING INSTRUCTIONS the item number of section 5 will refer to the identically numbered section of the Permit.
5.1 The Shif t Supervisor initiates the request for release and is responsi-bile to provide items ([) thru (3).
332 3.0
u 1621 Revision 8 10/21/76 5.2 The appropriate box is checked to indicate the specific tank to be sa.npled, analyzed and released.
5.3 In order that no additional liquid is added to the tanks before the dump is complete, the tank is isolated, and a DO NOT OPERATE tag is conspiciously placed.
The tank level is recorder, and the volume in gallons determined, (conversion charts are kept in the control room). The form is then turned over to the Radiation Protection Department for completion of items @ to h.
5.4 The next sequential release numoer is assigned and recorded in the RECORD OF LIQUID RELEASES LOG (see HPP 1675).
5.5 The appropriate box is checked.
5.6 The Radiation / Chemistry Technician /Jr. will sample the designated tank in accordance with HPP 1629, Health Physics Procedure for Liquid Waste Disposal System Sampling, and/or OP-1104-43 Nuclear Plant Sampling.
The sample collector will record the sample location, date and time of sampling on the container.
The sample will be tagged with the appropriate radiation label.
5.6.a If the tank being sampled is a Waste Evapo ator Condensate Storage Tank, the Radiation / Chemistry Technician /Jr. will take a one liter of sample and save it for preparation of the weekly proportional composite per SP 1301-6.3.
The sample collector will sign his initials in the space available.
5.6.b The Radiation / Chemistry Technician /Jr. will also obtain a one gallon sample of each Waste Evaporator Condensate Storage Tank ta be analyzed for tritium and gaama emitting is~otopes (GeLi Scan).
Immediately upon returning this sample to the lab the
-Technician /Jr. will add approximately 75 milliliters of concentrated 77 c.
1621 Revision 8 10/21/76 hydrochloric acid to :.his gallon sample to preclude the possibility of isotopes plating out on the sample container walls. After mixing the sample and acid thoroughly, the sample may then be transferred to the counting container.
5.6.c The Radiation / Chemistry Technician /Jr. will obtain a one liter sample of each Waste Evaporator Condensate Storage Tank to be analyzed for pH, conductivity, baron, methyl purple alkalini ty, suspended and dissolved solids and total iron.
5.7 The Radiation / Chemistry Technician /Jr. responsible for performing the radiation analyses, and the Radiation Protection Supervisor /
Chemist is responsible for approving the data in sections ([) thru (h).
Both sign in the appropriate locations, after completion of the analysis.
5.8 The date and time,af each analysis is recorded.
5.9 The estimated volume to be released is calculated by multiplying the volume in the tank from ([) by 3785 cc/ gal.
G 9
e 4,)
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l94 334
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Revision 5 SHP 1621 02/25/76 5.10 Perform gross alpha, gross beta, and gamma analyses in accordance with appropriate chemistry procedures.
Record the number of the chemistry procedure used to perform the required analysis in this column.
Other chemistry parameters must be analyzed for each release as required in 5.10.1 Gamma Isotocic Analysis - A background must be perfcrmed on the counting container to be used for the tank sample analysis.
The background sample will have the same sample volume and counttime as the tank sample.
Use Demin. water for the background sample liquid.
Perform a background subtraction from the analysis result in accordance with chemistry procedure 1958.
If the Gama Analysis is not performed in accordance with chemistry procedure 1958.3, perform steps h thru @.
5.10.2 Gross Beta Analysis - The technical soecifications do not recuire a gross beta analysis for WDL-T-ll A or WDL-T-11B.
Therefore, c _,
aross 8 is not oerformed for these tanks. The only recuireme't for the Laundry Waste Storage Tank WDL-T-12, is that cross e must be <1 x 10-7 uCi/cc, or it must be processed thru the radiological licuid waste disposal system.
Therefore only a aross 8 analyses need be cerformed on the WDL-T-12 samole.
5.10.3 Gross Alpha Analysis - The aross a is not a limitina condition for release, therefore, is not performed on each batch. Gross alpha will be evaluated in a proportional monthly composite as per the Tech. Spec's Table I, in accordance with SP 1301-6.3.
5.11 The volume of sample counted is recorded.
5.12 The sample counting time is recorded.
5.13 The gross number of counts, including background, are recorded.
194 335 5.0
Revision 5 SHP 1621 02/25/76 5.14 The background counting time is recorded.
5.15 The total background counts are recorded.
5.16 The net sample count rate is calculated.
h)
(BACKGROUt1D COUtiTS h)
ROSS COUtiTS (SAMPLE COUtiT TIME h)
(BACKGRUUtiD COUtiT TIME h) 5.17 The % counting error (2a) is calculated (GROS., COUtiTS h)
(BACKGRLb D COUtiTS h) 2 x 100 x
+
SAMPLE COUtiT TIME h)
(BACKGRCUtiD COUtiT TIME h)
(tiET SAMPLE COUtiT RATE h) 5.18 The gamma abundance for the energy listed is tabulated for the nuclides expected to be of importance. All significant peaks must be identified.
If
.her nuclides are found, or if gamas nther than those tabulated are u,
for the isotopic quantification, the appropriate gamma abundance shall be obtained from TABLE OF THE ISOTOPES, lederer.
5.19 The Specific Activity (SA) is calculated.
Refer tc appropriate PCP for further i formation, the efficiency of the counter i:; obtained from 1
charts in the counting room.
(flET SAMPLE COUtlT RATE h)
S.A. =
6 (SAMPLE VOLUME USED)
(GAMMA Abut 1DAriCE)
(2.22 x 10 )
(EFFICIEtiCY OF COUt4TER) 5.231% of 10CFR20 MPC's are tabulated.
If other nuclides,are identified, enter 1% of the appropriate value from 10CFR20, Appendix B, Table 11, Column 2.
5.21 Enter the ratio of h to @
l
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6.0
1621 Revision 14 02/08/79 h,
5.22 Enter the product of in cc, and to convert to curies.
5.23 Enter the sum of all items in column 5.24 Enter the sum of all items in column This is the total estimated curie content in the tank and will be used to insure compliance with the 2.5 curie per quarter specification.
5.25 Analyze tank sample for the following parameters and record results:
pH, conductivity, boron, methyl alkalinity, suspended and dissolved solids, and iron.
5.26 The technician who obtains these samples and performs these analyses, signs in the space indicated.
5.27 If the gross 8 result of the Laundry Tank is >l x 10' uCi/cc, then the tank must be processed thru the radiation waste system, and cannot be dumped directly.
For Lcundry Tanks, if <1 x 10-7 pCi/cc, go to for approval of release.
For Laundry Tank releases thru and thru are not applicable.
5.28 Record all isotopes (excluding Tritium) identified in the sample by GeLi/MCA analysis.
5.29 Record tFe specific activity of each isotope listed in (Values are listed in h
).
5.30 Record the monitor (RM-L6) sensitivity for each isotope listed in Values are obtained from Table 1621-1.
5.31 Enter the product of x
for each isotope listed in h
This is the expected value of the 5.32 Sum the values listed in PM-L6 response (above background).
5.33 Calculate RML-6 setpoints in accordance with 7.0 194 337
1621 Revision 14 02/08/79 5.34 Determine the requir ed dilution factor based on RML-6 setpoints in aCCordar..e with h.
7c NOTE:
- 21. 5 cpm = (7.16 x 10
/cc ) (3x10 uCUcc) 5.35 Obtain from the shif t supervisor the present MDCT flow in gpm from FR-146, the maximum MDCT flow which could be made available if reruired, any critical time restrictions in the release time, and the MDCT flow which is to be used in the calculations.
the MOCT flow shall by >5000 gpm, and credit shall not be taken in excess of 38,000 gpm, as per Tech Spec. limits.
The name of the shift supervisor supplying this information is ta be recorded.
5.36 Minimum MDCT flow (FR-146 Alarm Setpoint) is calculated at 90% of the MDCT flow recommended in 5.37 Deleted 5.38 Delet d 5.39 The diiution factor determined in is divided by 10 and then compared with the dilution factor determined in
, and dilution factor based on baron from The maximum is the actual dilution factor required for release.
5.40 The RR Max is computed by dividing the minimum MDCT flow (from h by the required D.F. from This RR max is used in t
e
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I94 33g
1621 Revision 5 02/25/76 fl0TE:
If RR max is <5.55 gpm notify the Shift Supervisor and Radiation Protection Supervisor.
5.41 Record the value of RR Max. (FR-84 Alarm Set Point) chosen in @.
5.42 The actual release is calculated as 90% of RR Max from h.
5.43 If RR actual is based on MPC/10, liquid waste can be released at a rate greater than or equal to 5 gpm, but less than h.
Use this range of rates in h.
5.44 The estimated time period to complete the tank dump is calculated by dividing the tank volume from @ by the actual release rate from h.
5.45 The estimated reading of RM-L6 is calculated by adding h to the background reading of RM-L6.
5.46 The estimated reading of RM-L7 is calculated by dividing @ by the dilution factor required from h or h, whichever is used plus the background of RM-L7.
5.47 The appropriate. data from
@ and @ are transferred to page one of the permit.
5.48 This section is to assure compliance with the 2.5 curie qua'terly limit. The estimated curies to be dumped this release from h is multiplied by 100/2.5 = 40 to obtain the percentage of quarterly limit in this release. The total curies released to date in this quarter and the last release number tabulated is obtained from the RECORD OF LIQUID RELEASES LOG, as per HPP 1675. These two percentages are summed.
If the sum is greater than 100%, dumping of this tank requires notification of use fiRC within 30 days, as per the Ervironrvtal Tech Spec's 2.3.1 specification e.
Radiation Protection responsibilities
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include filling in all information containec within boxes in parts h and @.~
3]p 9.0
1621 Rerision 11 07/14/78
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RM-L6 Ala m Setpoint from and FR-84 Alarm Setpoint from FR-146 Alarm Setpoint from Valve Loading from FR-84 Expected Reading from 42 RM-L6 Expected Reading from 45 FR-146 Expected Reading from h RM-L7 Expected Reading from 5.49 The Radiation Protection Supervisor / Foreman will evaluate the data, check the calculations and recommend the release be approved or disapproved.
The Supervisor of Radiation Protection and Chemistry, the IMit Superintendent or designated representative will make a similar review and recommendation.
The final authority and approval for a liquid release rests with the Shift Supervisor.
Then, and only then will the tank be reieased.
NOTE:
Just prior to release of liquid e"' "=nt through WDL-V-257, RM-L6 must be proved operable using the installed check source (1301-1 Step 6.2.1) or equivalent (1301-1 Step 6.2.2.2 & 6.2.3).
5.50 Operations is responsible for sections thru The alarms and valves are set as indicated.
See Section 6.0 for RM-L6 setpoint procedure.
NOTE:
MDCT Flow should not be_ changed during release ur.less absolutely necessary.
5.51 Time and date are filled in when release starts and ends. Tank
~
Level and volume at start and completion of release are filled in.
The total gallons of MDCT Flow are calculated by subtra7t n the 340
1621 Revision 12 08/07/78 MDCT Flow Totalizer reading at start from reading at end of release.
5.52 Mark the RM-L6 and flow recorder charts at the beginning and at the end of the release.
At the end of the release, return the RM-L6 Hi-Alarm setpoint to 3600 CPM and the Alert setpoint to 1800 CPM.
-7 NOTE:
3600 CPM is based on 3 x 10 Ci/cc with a sensitivity 7
of 7.7 x 10 CMP /pCi/cc and a minimum dilution factor of 5000/30.
Flush RM-L6 in accordance with OP 1104-295,Section I.3 prior to closing WDL-V-257. After flush of RM-L6, reset FR-84 and FR-146 to
" normal" setpoint, i.e.
FR-84 0 GPM
=
FR-146 5000 GPM
=
5.53 Should the MDCT Flcw have to be reduced, the Actual Release rate will have to be recalculated as per Results of these changes will be recorded in 5.54 Shift Supervisor will supply a new MDCT flow.
The required dilution flow is from 37 or 39 whichever is used for this release.
5.55 Shift Supervisor wili verify that all data from thru are complete and accurate.
11.0
-t
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194 341
621 Revision 11 07/14/78 5.56 The form is then returned to Radiation Protection for completion, transfer of data to HPP 1675 forms, and filing.
Volume is calculated fromdatain().
5.57 The actual quantity of each nuclide released is a product of Specific Activity from (ff) the Actual release volume from (5 ' and 10 6
)
to convert to curies.
6.0 RM-L6 SETPOINT ADJUST PROCEDURE 6.1 Inform Shift Supervisor that the RM-L6 setpoints will be changed.
6.2 Place the function switch on the RM-L6 ratemeter in the CAL position.
6.3 Push the alert pushbutton on the front of the ratemeter and, while holding the pushbutton in, wet the indicator on the ratemeter to the desired setpoint by turning the adjust knob (labeled " Alert" on front of ratemeter).
Release the button.
6.4 Repeat 6.5 using the Hi Alarm pushbutton and the Hi Alarm adjust knob (labeled "Hi" on front of ratemeter).
6.5 Return function switch to operate position.
6.6 Notify the Shift Supervisor that the new setpoints are in effect.
e G
194 34^
12.0
1621 Revision 5 02/25/76 SHIFT SUPERVISOR REQUESTS RELEASE PERMIT TANK IS SAMPLED Af1D ANALYZED IF WASTE EV PORATOR CONDENSATE STORAGE TANK, TAKE ONE (1) LITER SAMPLE AND SAVE IT AS PER SP 1301-6.3, STEP 6.2.1 RELEAS2 CALCULATIONS ARE IMDE TO ASSURE THAT INSTANTANEOUS OR QUARTERLY LIMITS ARE MET ESTIMATED READINGS ARE CALCULATED FOR EFFLUENT MONITORS APPROVAL TO RELEASE IS GRANTED RELEASE IS MADE.
RELEASE DATA ARE RECORDED CALCULATIONS ARE MADE OF ACTUAL QUANTITY RELEASED
}
343 13.0
1621 Revisien 5 02/25/76 RM-L6 SENSITIVITIES TABLE 1621-1 Isotope RM-L6 Sensitivity (CPM /pCi/ml) 7 CR-51 1.18 x 10 7
MN-54 8.8 x 10 8
CO-58 1.17 x 10 8
CD-60 1.72 x 10 7
FE-59 8.52 x 10 ZN-65 4.21 x 10 KR-85M 9.56 x 10 7
NB-95 8.8 x 10 ZR-95 8.72 x 10 ZR-97 8.19 x 10 I-131 1.06 x 10 6
AE-133 9.25 x 10 XE-133M 1.82 x 10 8
XE-135 1.18 x 10 CS-134 1.99 x 10 7
CS-137 7.74 x 10
- or any isotope not listed, use 7.7 x 10 CPM /uCi/ml e
14.0 194 344
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1621 03/17/78 R ev i e. i On 10 1621 1 LIQUID RELEASE PERMIT RELEASE @
HPP 1621 NUMBER (1) DATE:
TI M E:
R EQU ESTO R :
(SHIFT SUPERVISCR)
@C WDL-T-11 A TANK A
@ C TANK ISOLATED & "DO NOT OPER ATE" Tagged DATE:
O WD L-T-118 TANK B TIME' C
WDT-T-12 LAUNDRY TANK LEVEL ft.
VOLUME gal O
Other SIGNED h
gom RR MAX (5-30 gpm) l minimum Estimated time for RELEASE ESTIMATED CURIES TO BE DUMPED x 40 =
% OF QUARTERLY LIMIT CURIES DUMPED TO DATE THIS OTR.
x 40 =
% OF QUARTERLY LIMIT LAST RELEASE :s INCLUDED TOTAL
% OF QUARTERLY LIMIT j
O RELEASE RECDMMENDED BY
_ RADI ATION PROTECTIOr/ SUP/ Foreman C RELEASE RECOMMENoED BY SUP 0F RAD PROT & CHEM /Uf!IT SUPERI!;TE !DEilT C
RELEASE APPROVED BY SHIFT, SUPE RVISO P RELtASE DATA:
RM-L6 Setpvint Hf. Alaan
- 4 EPh:
Alert
- CPM:t 43nitials -
FR-8 + AT. ARM 'IE1. POINT AT 8
- fGPM:C INtrT ALs -
WARNING SIGN (" CAUTION UNIT I MAKING l'lQUID RELEASE") HUNG ON WDL-99 Kr.Y SWITCH IN UNIT II AUX. BLDG.
C3 FR-146 ALAPld SETPOINT AT
~
GPM g -
INITIALS INITIALS VALV LCADED TO GPM RELEASE RATE G
_ INITIALS
'D -
J h TliAE RELEASE STOPPED Tank Level at Start of Release f t. _
gal.
ME DATE Tank Level at End of Relea:e ft.
gal TIME RELEASE STARTED Tank Volume Releas d f t.
gal TIM E DATE MOCT EcFLUENT TOTALIZER AT STCP 00000 gal.
TOTAL TIME OF RELEASE MOCT EFFLUENT TOTALIZER AT START 00000 gal MINUTES TOTAL DILUTION FLOW 00000 galc g FLOW AND RADIATION MONITORING RECORDER CHARTS MARKED:
Pfl-L6 Source Check Sat. Before Rel. O AT BEGINNING OF RELEASE Rf t-L6 Alara Returned to: lii-A13ra = 3600 CPf1 O
AT END OF RELEASE Flow Setroint INSTRUMENT READINGS:
Alert Alara = 1000 CPf! D Rft-L6 Flushed ilguged t g
"^
^
^
RE ADING EXPCCTED
^
AT START R E ADING
% COMPLETS
% COMPLETE
% COMPLETE RELEASE COMP.
l F R-84 gpm I l
l RM-LS cum l
F R-146 gom RM-L7 com l
g IF CH ANGES IN FLOW FROM THE MDCT (OR CH ANGES IN THE RELEASE R ATE (V124/V125 position) DEVELGP DURING THE ROLEASE. CALCULATION OF A NP*; HATE AND SETPOINTS MUST BE MADE. THE NEW CALCULA-TIONS WILL BE COMPUTED ON P4GE 2 OF mlS FORM AND THE FOLLOWING TABLE WILL BE COMPLETED
[
- ACTUA;.
F R 84 F R-146 APPROVAL BY TIM E TIM E TIMC RELEASE RATE SET POINT SET POINT SHIFT SUPV, ORIGINAL 1st CH ANGE l
2nd CHANG E
- RELEASE RATE CANNOT BE LESS THAN 5 GPM, MDCT CANNOT BE <5000 or >3500g ggm.
Q AELEASE DATA COMPLETED 7Y INITI ALS.
545 ALL DATA REQUIRED ON THIS FORM HAS BEEN COMPLETED.
SHIFT SUPERVISOR 15.0
6 uete cOtteCreD BY O wDL-T-ii A SA DATE & TIME OF ANALYSIS VOLUME IN TANK gal x 3785 cc WDL-T 118 DATE TIM E._.
ALPHA h
ACTUAL VOLUME BETA W D L-T-12 R AD. AN AL. Perf. by:
l GAMMA O OTHER APPROVED BY:
TRITIUM 6a Con,poSite Sample Collected By:
NET SPE CI FIC COUNT VOLUME S AMP L E DKG SAMPLE GAMMA EST ACTUAL ACTIVITY METHCD OF SAMPLE COUNT COUNT COUNT ABUN.
SPECIFIC MPC~
[ Procedure}
USED TIME GROSS TIME BKG RATE ERROR DANCF ACTIVITY IOO g Numtwr /
Imil (Mir4 COUNTS (MINI COUNTS (cpm) 2a
@ KL.
Ca/mi Cu mi 100 CURIES CURIES G ROSS $
^
N A.
7
)
G ROSSCR N A.
H-a N A.
3E 5 u
Cr 51
.09@320 2E-5 Mn 54 1.00@835 1 E-6 Co-58
.99@810 9E 7 Co-60 1.00@l332 3E-7
~
Zn-65
.47@1115 1E-6 C
Cs-134
.98@G05 9E-8 o
.85@GG2 2E 7 I131
.82O364 3E 9 Ba-140
~
.34 @537 2E-7 L a-140
.37@B1 3E 8 Xe-135
~
.91@250 3E 8 rs $
R5. N g
-;P cn
~
m 4
8 FOR WDL T 12;IF GROSS # SPECIFIC ACTIVITY > 1 x 10'7 Ci/cc. LAUNDRY TANK CANNOT BE DUMPED
"' j"' @
b cuniss o
AND MUST BE PROCESSED THRO'JGH RAD WASTE SYSTEM
a y
1621 Revision 14 02/08/79 SPECIAL OPERATION CALCULATIONS FOR UNEXPECTED CHANGES IN UiE MDCT FLOW OR ACTUAL RELEASE RATE THE FOLLOWING CALCULATIONS MUST BE RE-COMPUTED BY THE SHIFT SUPERVISOR.
THIS NEED ONLY BE DONE IF THE MDCT FLOW IS REDUCED.
1.
MAXIMUM RELEASE RATE = (FR-84 SETPOINT)
RR - MAX = NEW MDCT FLOW GPM x (0.9)
I GPM
=
REQUIRED D.F.
2.
AC'UAL RELEASE RATE + (RR MAX) x (0.9) =
l GPM 3.
MINIMUM /0WFROMMDCT(FR-146SETPOINT)=NEWMDCTFLOWx(0.9)=l GFM USE THIS AREA FOR CALCULATIONS:
25 CHEMISTRY PARAMETERS 26 Sample Obt&inec By:
Analysis Performed By:
Date/ Time:
Date/ Time:
Diluticn Factor Required Based on Boron (From Note 3) l t
RESULT LIMIT (1) pH 4.5 - 9.5 (2)
Conductivity
<10 umhc (3)
Limit at tank to insure not exceeding limit of 6 - 9 oH at plant discharge.
2.
Must be <10 pmho to consider water with a pH less than 6 or greater than 9.
If conductivity is >10 pmhos, release must be approved by Chemistry SJpervisor or his designee with a written evaluation attached to release form.
esu
(
PPM) 3.
0.7 PPM at final discharge.
M 16.0 k big l
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1621 Revision 14 02/08/79 NAME OF SHIFT SUPERVISOR CONTACT SHIFT SUPERVISOR FOR FOLLOWING DATA CONTACTED a)
PRESENT MDCT FLOW gpm.
b)
MAX MDCT FLOW WHICH CAN BE MADE AVAILABLE I l gpm.
c)
TIME AVAILABLE FOR RELEASE min (200 to 1200 min) d)
MDCT Flow to use for CALCULATIONS l gpm (must be >5000;
<38000)
MINIMUM MDCT = FR-146 ALARM SETPOINT = (0.9) (MDCT Flow F
)=
Deleted Deleted REVISED CAL TIONS FOR MPC/10:
{D.F. FROM 23
)=
v 10 0.F.FROMh MAXIMUM =
D.F. FROM h C40 MAX. RR = { MIN MDCT
} 36
{ REQUIRED D.F. FROM h
}
bTO U
hR MAX. =
GPM (5.S5 to 30 GPM) = FR-6-1 Alarm Setpoint 42 RR Actual = (0.9) (RR MAX) =
GPM (5 to 27 GPM)
If RR Actual is based on MPC/10, Liquid Waste c be released at a rate greater th or equal to 5 GPM, but less than Use this range of rates in 47 Estimated time of dump = {Est. Vol. to be dumped from gal 1
, MIN
=
{
GPM-RR-Actual}
045 Es tima ted Readir,g of RM-L CPM (From 32
)+
CPM (Background) =
CPM Estimated Reading of RM-L7
{
CPM (Est..eading of RM-L6)} +
CPM (RM-L7) =
{ Required 0.F. From
}
194 348 18.0 I
1621 Davision 14 02/08/79
~
n 28' (29J
,QO)
(31j Isotopes.dentified Specif~1c Activity Sensitivity of Moni cB~r' Response by Analysis (From 19
)
RM-L6 to Each (CPM)
(Exclude H-3)
I pCi/ml Isotope (From Table i
1621-1) i l
l l
d2')
I=
2 Estimated Reading of RM-L6 h
RM-L6 Setpoints A.
Background Limitations 1.
e ther the estimated monitor response or Bkg <3600 cpm, go to 2.
If RML-6 Bkg >3600 cpm, and 3600 cpm < Bkg < 27,000 cpm, calculate "e" in M.
3.
If Bkg > 27,000 cpm, Decon RML-6 liner and return t h A.
4.
e_3x N(Monitor Resoonse
)+f2 x (Bka
. __ ) } =;
(Monitor Response
)
NOTE:
e >0.2, flush and/or d ~ on RML-6 liner ar.d return to
'33 A.
If e <0.2 go to 33 B.
B.
High Alarm Setpoint 2 x ( (Monitor Response
) + (Bkg
)}= l C.
Alert Setooint (High Alarm
)
I 2
h Dilution Factor Based on RML-6 D.F. = (RML-6 High Alarm
)
j
-l 21.5 cpm 194 349 19.0
~