ML19224B256
| ML19224B256 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/14/1978 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| 1622, TM-0088, TM-88, NUDOCS 7906140300 | |
| Download: ML19224B256 (25) | |
Text
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TMI DOCUMENTS
~h DOCUMENT NO:
COPY MADE ON OF DOCUMENT PROVIDED BY METROPOLITAN EDISON COMPANY.
Wilda R. Mullinix, NRC
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1622
- I\\, g Revision 18 07/14/78 THREE MILE ISLAND NUCLEAR STATION
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STATIL:. HEALTH PHYSICS PROCEDURE 1622 i
RELEASING RADI0 ACTIVE GAS WASTE ASTR COPY Table of Effective Pages
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Pace Date Revision Pace Date Revision owe Date R evision 1.0 04/05/78 17 2.0 04/05/78 17
- 3. 0 04/05/78 17 4.0 01/17/77 13 4.1 Olf ! 7/77 13 5.0 06/17/76 10 6.0 07/25/74 3
7.0 01/17/77 13 7.1 01/17/77 13 8.0 05/15/75 5
9.0 04/05/78 17 9.1 08/18/76 11 10.0 05/20/76 9
11.0 07/14/78 18 12.0 04/05/78 17 13.0 04/05/78 17 14.0 04/05/78 17 15.0 05/05/75 4
16.0 11/28/77 16 17.0 05/05/75 4
18.0 04/05/78 17 19.0 07/14/78 18 20.0 07/14/78 18 21.0 04/05/78 17 Unit 1 Staff Recommend Aa Unit 2 Staff R'.co ends aroval AV/
proval Approval
'Date Approval Date Cognizant d'ept. Head Cogn/zant dep(. Head Unit 1 PORC Recom nds Approval Unit 2 PORC Rec men s proval Date C4
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Date
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Unit 1 Superintendent Approval Unit 2 Superinten ent Ap roql Date 7 /
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1622 Revision 17 04/05//8 THREE MILF ISLAND NUCLEAR STATION UNIT #1 HEALTH PHYSICS PROCEDURES 1622 - Relasing Radioactive Caseous Waste 1.0 PURPOSE This procedure describes the regulations applicable to radioactive gaseous discharges to unrestricted areas and the monitoring programs designed to ensure compliance with these regulations. 2.0 DISCUSSION 2.1 Radioactive gases result primarily from the escape of gaseous fission products from the fuel, and by neutron activation of consti-tuents in the water and air in the immediate vicinity of the core. Those radioactive gases that are produced in or released to the reactcr coolant should ultimately be collected in the low pressure vent header system and compressed in the waste gas decay tanks for decay and re-use or release to the atmosphere. Normal hold-up time in the waste gas dacay tanks will be at least 45 days. Shorter hold-up times can be employed provided the appropriate environmental tech. specs. are satisfied. 2.2 The other source of gaseous waste comes from purging the atmosphere of the reactor building. Radioactive gases in the reactor building come from neutron activation of the atmosphere or from gaseous leaks from the reactor coolant system. 2.3 Radioactive gases could also be relased through the main condenser vacuum pump exhaust vent (due to leaking steam generator tubes) and auxiliary and fuel handling building ventilation exhaust vent (due to the escape of radioactive gases to the atmosphere of these F95 025 1.0 1
1622 Revision 17 04/05/78 buildings). Although these releases are not anticipated to be a significant problem, the vent gases pass through HEPA filters and charcoal filters. The gases are continuously monitored and recordea. This is a continuous release and is sampled periodically as per Table 2 requirements in the Tech. Specs. 2.4 Analysis of gaseous effluent is necessary to ensure adherence to the "as low as practicable" philosophy to assure compliance to Environmental Technical Specifications. Environmental Technical Specifications limit the release rates for noble gases. radioactive iodine and particulates. 2.4.1 The Technical Specifications contain two types of limits (instantaneous release rates, and quarterly average release rates) for two classes of radioactive materials (Halogens and particulates with half-lives greater than 8 days, and gross gaseous activity except Halogens and particulates with half-lives greater than 8 days). Under unusual conditions, the quarterly average limit used in this report may be increased, but this requires notification of the NRC. 2.4.2 The values used for instantaneous releases are as follows: 5 3 Qi < l.2 x 10 g /sec.
- g{MPCi Gross Gaseous
Where Qi = uCi/sec release rate MPCI = 10CFR20, Appendix B, Table 11, Col.1 I - 131 + Particulates- < 0.3uCi/sec. 195r026 z,o
1622 Revisior. 17 04/05/78 The release flow rates are adjusted to insure that these limits are not exceeded. The above limits are applicable if the gas decay tanks are held for greater than 45 days and for Reactor Building Purge. If the waste gas decay tank is to ba held for less than 45 days the following limits apply: 3 3 Qi = <2.4 x 10 Gross Gaseous: b MPCI g /sec I-131 + Particulates: <0.003uci/Sec 2.4.3 The working quarterly average limits are as follows: 3 3 Oi = < 4.8 x 10 g /sec g MPCI Gross Gaseous: I-131 + Particulates: ~~<0.006pCi f .c l If these limits are exceeded, then the commission must be notified within 30 days. 2.4.4 Under unusual conditions, the following maximum quarterly average limits shall not be exceeded. s 4 3 Oi = :1.9 x 10 M /sec Gross Gaseous: 2 MPCi I-131 + Particulates: <0.024uCi/Sec 2.5 The release of radioactive gaseous effluents is continuously monitored by RM-A5 (Condenser Vacuum Punip Discharge), RM-A7 (Waste Gas Dacay Tanks), RM-A8 ( Auxiliary and Fuel Building Purge Exhaust) and RM-A9 (Reactor Building Purge Exhaust). ~ Monitors RM-A8 and RM-A9 detect radioactive ncble gases, io-dine and particulates. RM-A5 and RM-A7 detect only gaseous ~ radionuclides. ~' -~~ .. F95 027~~~ 3.0
1622 Revision 13 01/17/77 2.5.1 In the event one of the abcve monitors becomes inoperable, grab samples will be taken as required in the Technical Specifications. 2.5.2 Analysis perfcrmed will be as designated in the lates Environ-mental Technical Specifications.
3.0 REFERENCES
3.1 FSAR, Vol. 5, Technical Specifications 3.2 Environmental Technical Spec:fications 3.3 H.P.P. 1606, Air Sampling for Radioactive Iodine, and H.P.P. 1608, Air Sampling for Tritium. 3.4 PCP 1951, Determination of Tritium, and PCP 1958, Gamma Spec-trometers. 3.5 OP 1104-43, Nuclear Plant Sampling. 3.6 10 CFR 50 3.7 H.P.P. 1631, Sampling of Waste Gas Decay Tanks and Reactor Building, and H.P.P. 1675, Racioactive Waste Relea e Records. 4.0 EQUIPMENT 4.1 Charcoal Cartridges 4.2 2" G-5 air filters or equivalent 4.3 Geli Detection System 4.4 Sampling container 4.5 Liquid Scintillation Detection System 5.0 GPERATING INSTRUCTIONS Prior to releasing gaseous effluents to the environment from the Waste Decay Tanks (WDG-T-1A, WDG-T-18, or WDG-T-1C) or the Reactor Building, a Gaseous Release Permit must.be obtained. NOTE: In these operating instructions, the item number of m 4.0 ~ ~ I95 028
1622 Revision 13 01/17/77 section 5 will refer to the identically numbered sections of the Permit. 5.1 The shif t supervisor initiates the request for release, and is responsible to provide items @ through @ 9 =m e 195 029 4.1
1622 Revision 10 06/17/76 5.2 The appropriate box is checked to indicate whether the Reactor Building or a specific decay tank is to be sampled, analyzed and released. 5.3 Prior to purging the reactor building, the Kidney Filter System must be operated a minimum of 4 hours. The Shift Supervisor indicates the time and date which the System was placed in operation. In order that no additional gas is added to the waste gas decay tanks before the release is complete, the tank is isolated and conspicuously labeled with a DO NOT OPERATE tag. The date and time of tagging is recorded. The pressure in psig is recorded. This is obtained from the Waste Gas Control panel for the Waste Gas Decay Tanks; and from the control room for the Reactor Buil 'ing Pressure. The Estimated Volume to be released is calculated as indicated and converted to cc. The form is then turned over to the Radiation Protection Department for completion of items through 5.4 The next sequential release number is assigned and recorded in the RECORD OF GASE0US RELEASES LOG (see HPP 1675). 5.5 The appropriate box is checked. 5.6 The radiation / chemistry technician will then sample the desig-nated tank or reactor building in accordance with HPP 1631, Health Physics Procedure for Sampling of Waste Gas Decay Tanks and Reactcr Building. The sample collector will record the date and time of sampling; and tag with the appropriate radia- [ tion label. 5.7 The radiation / chemistry technician responsible for performing analyses, and the Radiation Protection Supervisor / Chemist res-ponsible for approving the data in sections throughh both sign in the appropriate location after completion of th 030 analysis. 5.0
1622 2 7/25/74 Revision 3 5.8 The date and time of each analysis is recorded. 5.9 The estimated volume to be released in cc is obtained from 5.10 The Plant Chemistry Procedure Number followed in performing the required analyses is recorded. The Tech. Spec. limits are divided into limits for two classes of radioactive ma-terials: Icdines and Particulates with half-lives of greater than 8 days, and gross gaseous activity exclusive of Iodine and Particulate with half-lives greater than 8 days. There-fore, the two classes of material are calculated separately. The sampling consists of drawing a known volume of air through a sampling train consisting of a Particulate Filter, and Iodine Filter (charcoal), and then taking a gas sample of the effluent of the sample train. The three samples are analyzed separately, therefore, there are three sections of columns on the fom. The nuclides listed are those expected to be found, or those required to be tabulated in the HPP 1675. All peaks must be quantified. If additional nuclides are found, add then to the fom. 5.il 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. 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. [ GROSS COUNTS M [ BACKGROUND COUNTSh3 v v }AMPLECOUNTTIMEh [BACKGROUNDCOUNTTIME h 6.0 f O
1622 Revision 13 01/17/77 5.17 The *. counting error (2 6) is calculated. 6'3[ [BACKGROUtJD COUtJTS GROSS COUtiTS 3 + 2 x 100 X [AMPLECOUflTTIME @]2 [BACKGROUfl0COUtiTTIME g[2 x f1ET SAMPLE COUf1T RATE h fl0TE : If the Gamma Analysis is not performed in accordance with Chemistry Procedure 1958.3, Perform Steps 11 through 19. 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 other nuclides are found, or if gamma's other than those tabulated are used for the isotopic quantification, the appropriate gamma abundance shall be obtained from TABLE OF THE ISOYOPES, Lederer. 5.19 The Specific Acvity (SA) is calculated. Refer to the appro-priate P.C.P. for further information. The efficiency of the counter is obtained from charts in the counting room. [tlETSAMPLECOUtlTRATE Sl [SAMPLEVOLUMEUSED] -GAMMAABUtiDAfiCE[2.22x10 [EFFICIEfiCY OF COUtiT ~ S.A. = 5.20 The sample is taken before the absolute filters and charcoal filters which are in the release path of the gaseous release. Therefore, to calculate the concentration released to the en-vironment, the concentration in the sample is multiplied by the FILTER FACTOR. This term is the fraction passing the filter, and is calculated by (1 minus the Filter Retention Efficiency). The methods of measurement are not exacting, and 195 032 7.0 I
1622 Revision 13 01/17/77 the efficiency will vary with the time, chemical composition, and particulate size. A conservative factor of 0.1 (90% filter retention) is used for particulates and iodine, and 1.0 for gases. Should these values prove to be too restrictive, they may be refined as a later revision of this procedure. e e O 6
.16,22 05/15/75 Revision 5 5.21 The MPC's for gases identified are tabulated. If other nuclides are identified, enter the appropriate value from 10 CFR 20, Appendix B, Table 11, Column 1. Enter the result of Specific Acitivity fron h multiplied by 5.22 Filter Fraction from h divided by tiPC from h, for Iodines and Particulates found. Enter the product of Specific Activity from h and Filter 5.23 Fraction from h, for Iudines and Particulates found. 5.24 Enter the sum of all nuclides on the particulate and charcoal filters. 5.25 Enter the sum of all nuclides on tha gas sample. This is a dimensionless quantity. 5.25A For waste gas decay tanks with hold up time <45 days sum the total of all gaseous Isotopes with half lives of greater than 8 days. All Isotopes with half lives of less than 8 days will be labeled with an asterick. Transfer the value from h to the top line and the value 5.26 from h to the bottom line. Transfer th; otimated volume to be released from @ 5.27 5.28 Enter the estimated quantity to be released (product of each lineofhandh)inthecorrespendingline. The next un-numbered column, (the quarterly release allotment) is the pro-duct of the applicable quarterly average limit (see 2.4.3) and the number of seconds in a quarter of a year. This is the i quarterly Release Allotment. The units for gaseous releases have been converted from M3 to cc. 8.0 -195 034
1622 Revision 17 04/05/78 5.29 Enter result of 100 x the estimated quantity in this release l-from h divided by the quarterly release allotment. 5.30 Complete the upper section if this is a waste gas decay tank with a hold-up time greater than 45 days, or if this is a Reactor Building sample. Two flows are calculated. Transfer the lowest value to the box to the right (lowest F/. This is the ma~imum ficw rate (F ) that can be allowed in m order not to exceed the instantaneous release limits. Complete the lower section in an identical manner only if this is a waste decay tank that has been isolated for <45 days. NOTE: If the flow rate in block @ is too restrictive for release go to block - complete block 30A as per step 5.30 above, with concurrence of the Shift Supet visor. 5.31 Fill in the'left side of the form for waste decay tank releases. If F is <l.1 CFM, then this tank cannot be released under m normal conditions; return form at this point to the Shift Supervisor. If Fm is greater than 1.1 CFM but less than 10 CFM, then the FR-123 alarm set point is the value of F. The m actual release rate, WDG-V-47 set point will be adjusted to 90". of F. F is obtained from @. If F IS m m m e 9 e a t
- gg 035 9.0
1622 Revision 11 08/18/76 >10 CFM, check the box. The maximum value the alarm can be set is 10 CFM, therefore, this value will be used. WDG-V-47 will be adjusted to 9 CFM. Caution: Insure fiOTT limits are not exceeded on purge valves. 5.32 Fill in this side of the form for reactor building releases. If F as calculated i'n @ u <5,550 CFM, the reactor building m air is too radioactive to be released under normal conditions; return form to the shift supervisor. If F is > 5,550 CFM but m less than 50,000 CFM; then FR-148 alarm setpoint is the value F from @ The reactor building purge rate gradual switch m is adjusted to 90% of F,. This is the actual purge rate of the reactor building and is recorded with che red pen of FR-148. If the Fm calculted in @ is >50,000 CFM then check the last box. The maximum the alarm can be set is 50,000 CFM. The flow will be adjusted to 45,000 CFM. fiOTE: If F is <50,000 CFM due to particulate and iodine m activity (from @) and a higher purge rate is desired. the shif t supervisor may request a resampling of the containment atmosphere for particulates and iodine after 4 hours of Kidney Filter System operation. F may be m recalculated based on the new particulate and iodine activities. -I O e
- /95 g3g 9.1
1622 $f b N 5.33 For gases, it is estimated that the dominant long lived activity will be Xe-133; therefore, this nuclide is used for the estimated reading. For RM-A7, multiply the sepcific activity of Xe-133 in uCi/cc from h by the calibration factor of RM-A7 in cpm /uCi/cc. Add to this the background of RM-A7. The calibration factor and background for this monitor and for all other monitors is obtainable from the control room remote readout or from the local meter on the monitor. 5.34.1 For RM-A8 gas channel, the Xe-133 specific activity in uCi/cc is obtained from F is obtained from The building purge m flow is obtained from FR-151 recorder. 5.34.2 For RM-A9 gas channel, the Xe-133 specific activity in uCi/cc is is obtained from h The flow out the obtained from Fm stack is obtained from the green pen of FR-148. 5.35.1 For RM-A8 iodine channel, I-131 is estimated to be the dominant activity, therefore the specific activity of I-131 is obtained from on the charcoal filter, the filter factor is obtained from , and V is the estimated volume to be released in Ft fror 5.35.2 For RM-A9 iodine channel, I-131 specific activity is obtained from the filter factor is obtained from . V is the 3 volume estimated to be released in Ft from The flow out the stack is from the green pen of FR-148. 5.36.1 For RM-A8 particulatr chanrel, Cs-137 specific activity from 3 is used, V is the estimited volume to be released in Ft from 195 037
1622 Revision 18 s 07/14/78 5.36.2 Fo r RM-AF ; articulate channel, Cs-137 is estimated to be the c'mi:.cnt o :1vity. There* ore, the specific activity of Cs-137 in pCi/cc is obtained from h the filter factor for particulate is obtained from The flow out the reactor building stack is obtained from the green pen of FR-148. V is the volume in 3 Ft of the reactor building from 5.37 The quarterly allotment used to date in this quarter for both I plus particulates and Noble pses is obtained from the RECORD OF GASEOUS RELEASES LOG (see HPP 1675). The estimated quarterly allotments of I-131 and Noble gases for this release are obtained from If either of the sums are greater than 100%, then this release cannot be made without notifying the AEC. Radiation Protection responsibilities include filling in the information contained in the boses in parts and from or @<<=@ @ @ @ 5.38 The Radiation Protection Supervisor / Chemist, Unit Supt or designated representative will evaluate the data, check the calculations and recommend the release be approved or disapproved. The final authority for approval of a gaseous release rests with the shift supervisor. Then, and only then will the tank be released. NC E: Juet prior to release of a waste gas decay tank, RM-A7 must be proven operable by a test using the installed check source (1301-1 Step 6'.2.1) or equivalent (1301-1 Step 6.2.2.2 & 6.2.3). ~ ~ 19[7 93g c 11.0
1622 Revision 17 04/05/78 5.39 Operations is responsible for completion of the remaining portions of sections @ through @ The alarms and valves are set as indicated. NOTE: If this is a Reactor Building Purce Release, Operations will notify the Radiation Protection Department prior to release, to insure the chanoina of RM-A9 particulate and charcoal cartridge. 5.40 Time and Date are filled in when the release starts and ends. NOTE: Insure that the Kidney Filter System has been operated a minimum of 4 hours prior to iniating the Reactor Building Purge. 5.41 Mark the records as indicated at the beginning and at the end of the release. 5.42 Record the appropriate instrument readings before, during and after the release. 5.42.1 Insure that a gas and tritium sample have been obtained from RM-A9 at approximately the 18 hour point of each reactoc building purge. 5.43 The shift supervisor will verify that all data from @through harecompleteandaccurate. After signing the form, it is returned to the Radiation Protection Department for completion. NOTE: Operations will notify the Radiation Protection Decartment after Termination of release, to insure the changing of RM-A9 particulate and charcoal cartridge. ~ 195 019-2 12.0 i
1622 Revision 17 04/05/78 5.44 The actual release volume is calculated based upon readings taken during the release AP is obtained from @ For reactor building purges, Fm is from @ (R.B. Purge Rate gradual switch set point) and t is from @ (total time of release). 5.45 The actual quantity released is calculated by multiplying the specific activity from @ by the filter fraction from @ by the actual release vo:ume from @ and entered in h. NOTE :: 'or reactnr building purges, the additional quan-tities of isotopes released due to primary system leakage must be accounted for. Therefore, complete steps 5.46 through 5.53 for reactor building purges only. NOTE 2: For quantities of Iodines and particulates released, unit vent filters are counted in accordance with SC 1301-4.7. 5.46 Total in-leakage time is calculated. Record the time the purge stopped from @ and the time the reactor building was sampled from@ The in-leakage ti.ae is the total time in minutes between these two times. 5.47 Total in-leakage volume is calculated by multiplying the purge rate from @ (R.B Purge Rate gradual switch set point) by the 4 total in-leakage time from 46 by 2.832x10. 5.48 List all gasses identified from gas and tritium samples taken from RM-A9 during the purge. (Several are already listed). 2 5.49 Record the specific activities of those isotopes identified in the gas and tritium samples taken during the purge. e 195 040 13.0
1622 Revision 17 04/05/78 5.50 Record the MPC values of those isotopes identified in the samples taken during the purge. 5.51 Divide the specific activities in @ by the MPC values in 5.52 Summarize all @ entries. 5.53 The additional quantity due to in-leakage (in curies) is calculated by multiplying the specific activities in @ by the total in-leakage volume from @ by 10-6. 5.54 For those isotcpes listed in @, the quantities released as listed in @ are recorded. 5.55 The actual quantities released (including in-leakage) are calculated by addirig columns @ and @ for each isotope. 5.56 Enter total from 5.57 Enter volume released from 5.58 Quantity this release is calculated by multiplying @ by 0 5.59 Enter the result of 100 times the quantity this release, from 16 h, divided by the quarterly release allotment,1.9X10 cc. 5.60 Station Superintendent / Unit Superintendent's approval is required prior to extending purges beyond 48 hours with the reactor coolant system pressurized. Addi tional 'mples must be obtained at this time. ~. y e nn- ~ 195 041 14.0 ~ '~~ ~~~
BAY 5 IS/6 ~ S 22 Revision 4 SHIFT SUPERVISOR REOUESTS RELEASE PERMIT TAf1K IS SAMPLED At1D Af1ALY7.ED _t RELEASE CALCULATl0t1S ARE MADE TO ASSURE THAT li:STAllTANEOUS OR i QUARTERLY LIMITS ARE MET l l l j ESTIMATED READit!GS ARE CALCULATED FOR EFFLUEflT l M0ff l TORS l i i APPROVAL TO RELEASE IS GRAtlTED L RELEASE IS MADE. RELEASE DATA ARE RECORDED -I f - ~ ~ - ~ ~ ~CALCULAT10flS ARE MADE 0F ~~ l 9h ~~pf } ~- ACTUAL QUAtllTY RELEASED ~ ~ 15.D
P AS E C U S R E ' E /.S E P E R '.'. ! T 1622 Revision 16 g g t gag g 'g HPP1622 11/28/77 NUU E R C A TE: TIME: RECUESTOR: (SHIF T SUPE RVISDRt, S WDG-T 1 A DECAY TANK A N(r t e a b C" ~ m m o WDG T 18 DECAY TANK 8 b ' ' Y "- O U WOG T 1C CECAY TANK C TANK ISOLATED AND "DO NOT OPER ATE" tagged: DATE: TIME REACTOR SUILDING HOLD UP TIME DAYS. P= TANK OR REACTOR BLDC. PRESSURE = psig ESTIMATED VOLUME TO BE RELEASED = R C 0 7 3 _j f t x 2.83 x 10" -
- 2.00 x 10 x
= G ce DECAY 1125 (P+ 14.7) = 3 4 l TANK 14.7 ft x 2.83 x 10 = cc SIGNATURE 9 % OF OUAR1 ERLY ALLOTf.*ENT USED TO D ATE I l-131; j INOBLE GASSES % OF OUAR1Eitt Y ALLOlMENT THIS DUMP ll131;L___~ NOSLE GASSES! LAST RELEASE u INCLUDED. TOTAL I131;[ NOSLE GASSES R E LE ASE R ECO*."'. ENDED BY RADI ATION PROT. SUPER / FOREMAN RELEASE RECCI.. MENDED BY SUPER. RAD. PROT. & CHEM / UNIT SUPT. RELEASE APPROVED BY SHIFT SUPERVISOR 39.1 Rad. Prot. Dept.notitled to grab Who nQtified 42.1 Sample obtained d RELE ASE D AT A 18 hour RM-A9 samole (H7. Gas) Notified by cro by FR 123 ALARM SET PCINT AT t o h FR 1'3 ALARM SET AT [ f t / min 3 WDG V 47 LCADED TO R R. B Purca Rate gr: dual sv.,tch set to I f t / min init ; 3 RELE ASE STCPPED TIME DATE h Decay Tank or R.B. PRESSURE AT ST ART psi i RELEASE STARTED TIME DATE Decay Tank or R.B. PRESSURE AT STC? psi ! l TOTAL TIME OF RELEASE MIN S P-psi [ FLCW RECORDS MARKED [ BEGINNING END or 9 Ch.in ge RAD MONITOR RECORDS MARKED [ BEGINNING END p, c, g.,,.7, METECROLOGY RECORDS MARKED [ BEGINNING [ END C1-A7 Source Check Sat. O Beoinnino INITI ALS INSTRUMENT READINGS: h M A Xf MUM g ESTIMATED R E A DING R E ADir:G R E A D t.*JG R E ADING READING AFTER HIGHEST l ' READING prior TO AFTER'. AFTER% AFTER % RELEASE READING DU.1;NU l 1 co-n G t RELEASE RELEASE RELEASE RELEASE COMPLETED RELEASE 4 5E RM A9P, @ t=l l y R M. A31 @t= E@ RM A9G l @ te l l RM A7G O to l l l l N E l RM ASP G t=l l l O2gg RM A81 @ toe l l l RM A8G l @ to l l l l l
- i l
RELEASE DATA COMPLETED ALL DATA REOUIRED ON THIS FORM HAS (1 COMPL ETED. IN!TIALS bh) - i' SHIFT SU3ERVISOR
,1G22 Revision 4 HAY'S Use thefpage for calculations '197'5 is22 2 e O e 4 e e N h o Y I95 044 e 17.0 [
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1622 Re, v,i s i o, nd 18 1622-4 26 Total from 27 ESTIMATED 28
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24 f or 1+part NO LNE TO BE Err. QTY. QTLY RELEASE 2 C+3G f. % ^ ' ALLOTMENT 75 for NA+ trat f t1om] THIS RELEASE ALLOTVENT THIS RELEASE 1.131 + PARTICULATES U[f u C. 2.35x10'uCi NOBLE GASSES + H 3 g 1.9x108 ce cc C COMPLETE THIS SECTION IF HOLD-UP TIME >4G DAYS OR IF REACTOR BLDG URGE 30 F, = (0. lgdi/Sec) (2.12 x 103 3 ft /ain/cc/Sec) 1 av Ci/ccTOTAL f rom 24 I + PARTICULATES 3 ft / min l 4 FGi6.0x 10 3 a 3 L w ST-m M /Sec) (2.12 x 10 +3 tr / min /M /Sec) - l TOTAL FROM 25 NG + H3 3 ft / min MPC O COMeLETe TsiS SEgTiON iF sOto-up Time <45 DAYS F Qxl0 ' u ) (2.12 x 103 3 g ft / min /cc/Sec) l p Ci/cc TOTAL COL 24 + PARTICULATES 3 ft / min I l LOWEST = FM i F Q. 2 x 103 3 G M /Sec) (2.12 x 10+3 3 3 ft / min /M /Sec)= l j TOTAL COL 25 NG
- H3 MPC FILL IN THIS SIDE FOR WASTE DECAY TANKS FILL IN THIS SIDE FOR REACTOR BLOG.
3 00 NOT RE LE ASt: TANK I I I'l 32 ] IF FM < 5500 F EN 00 NOT RE LE ASE TANK RETURN TO SHIFT SUPERVISOR RETURN TO SHIFT SUPE RVISOR C ,,3 b COMPLETE THfS PART IF 5500 (FM (50.000 f t 3 COMPLETE THIS SE CTION IF 1.1 < F M < 10,q / MIN F R 148 ALARM SETPOINT = F M = l l ft / men F R-123 ALARM SETPOINT = FM = ft fm,, R E Nga Rate 3 3 3 9'adu as seven seepoint = (0.9) (F M) = l ft / min a9 m FM d ft / min WOG-V47 5ETPOINT = b F M > 10 Ft / MIN 3 3 F M > 50.000 F T / MIN F R-123 A LA RM SETPOIN T = to I ft3/m en R Pu R 3 WOG-V-4 7 SE TPO IN T = 9 ft / min U gradual svvetch seepoint = l 45.000 F T / min ESTIM ATED RE AOINGS OF RM-A7 & RM-A8 33 RM-A7 (G AS CH ANNE L) ESTIM ATED RE ADINGS OF RM. A9 CI/cc Xe 1 CAL F ACT Xe 133 lcom + BKG = 34 R%A8 (G AS CH ANNE L) 34 G AS CHANNEL FM T lT l p Ci/cc Xe-133 F LOW cut STACK CAL F ACTO R Xe-133 f{ Ci/cc Xa-133ll, CAL FAC Xe.1.53f lFMj, ',g BKG = com RM-A9G F R ' 51 F LOW CF M + 35 RM-Al (IODINE CH ANNE L) 3S LODINE CH ANNEL ~V P CJ/cc I 13 F Af*T l-131 lit. f act C1/cc l-131 FILT. FACT F LOW out STACK CAL FACT,1 131 + BKG + BKG com RM. A91 J F R 151 A.OW CFM ' ] c om R M A 81 = 36 RM-A3 (PARTICULATE CHANNEL) 36 PARTICULATE CHANNE L a = C1/cc Co.137 CAL FACT filt, f act V, M 8KG f 1 m F6R Q + 8G ~ ~ F R-151 F LOW CFM cpm RM-A9P = com RM A8P = I95 nu CAL F ACTORS ARE AVAILA8LE IN CONTROL ROOM
- CAL FACTOR FOR C3-137 IS THE SAME AS SR-90 FOR THE PARTICULATE CHANNEL 19.0 e
1622 Revision 18
- t 07/14/73 COMPLETE THESE CALCULATIONS IF UNIT #2 WILL NOT RELEASm UNTIL THIS RELEASE IS TERMINATED
{ COMPLETE THIS SECTION IF HOLD-dP TIME >45 DAYS OR IF REACTOR BLDG. PURGE F 3 I= (0.3 uCi/Sec) (2.12 x 10-3 Ft / min /cc/Sec) = uC1/cc Total from 24 3 Ft / min LOWEST =FM F S G= (1.2x10 g3/Sec) (2.12x103 3 3 Ft / min /M /Sec) = Total From 25 3 Ft / min COMPLETE THIS SECTION IF HOLD-UP TIME <45 DAYS -3 F 3 I =(3.0 X 10 uCi/Sec) (2.12x10-3 Ft / min /cc/Sec) = pCi/cc Total Frc, 24 3 Ft / min F 33 3 3 3 G= (2.4x10 M /Sec) (2.12x10 Ft / min /M /Sec) = Total From 25 3 Ft / min NOTE: UNIT - 2 IS NOT RELEASING AND WILL NOT RELEASE UNTIL THIS RELEASE IS TERMINATED. Shift Supervisor d 195 047 ~ ~ 20.0
04/05/78 Revision 17 ' Yotal hable' Gas,a.nd Tritium Concentratioi3 During Redctor Cuilding Purges 1622 ~_ The following sections will be filled out 'or reactor building purges only. ~ = Total in-leakage Time: Time Fur ge Stopped Time Date Time of Original Rx Sample Time Date Total Time Min. h Total in-leakage Volume: 4 l Volume = CFM x min x 2.832 x 10 = cc I Specific S.A - Additional Qty. Released Actual Qty. Isotope Activity MPC MPC Curies from @ Released,includ4 (uCi) due to ing in-leakage l ( cc) In-Leakage l } I ~ @ I= l Re-Quantity this Qrtrly. Release % Allotment Total From eased Release Allotment this release g 16 l cc cc 1.9x10 cc ~ S 04 g. 21.0 .}}