ML19250C051
| ML19250C051 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/16/1979 |
| From: | Cantrell C, Pleva J TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19250C050 | List: |
| References | |
| TI-18, NUDOCS 7911060446 | |
| Download: ML19250C051 (64) | |
Text
a .
DISTRIBUTION Sequoych Nuclear Plant 1 Plant Master File Superintendent Assistant Superintendent (Oper.)
TECHNICAL INSTRUCTICN /0, Assistant Superintendent (Maint.)
Administrative Supervisor TI-18 Maintenance Supervisor (M)
Assistant Maintenance Supervisor (M)
RADIATION MONITCRING Maintenance Supervisor (E)
Assistant Maintenance Supervisor (E)
Units 1 and 2 //A Maintenance Supervisor (I) 1U Results Supervisor
- g Operations Supervisor Quality Assurance Supervisor Health Physics Public Safety Services Supv.
Chief Storekeeper Preop Test Program Coordinator
- autage Director 1C Chemical Engineer
- g Radiochem Laboratory Instrument Shop Reactor Engineer 1U Instrument Engineer Mechanical Engineer Staff Industrial Engineer 1C Training Center Coordinator PS0 - Chickamauga Engrg Unit - SNP Prepared By
- J.M. Pleva Public Safety Services - SNP 1C Shift Engineer's Office Revised By: Gridlev/ Williams /Di1 L 1C Unit Control Room QA&A Rep. - SNP Submitted By: N &hh .. [ 1U Health Physics Laboratory Supervisor U 1U Chief, Nuclear Generatior. Branci-1U P Prod Central Office File PORC Review: / O/l(.o[7 T 1U Superintendent, WBNP Date i Superintendent, BFNP Superintendent, BENP j () 1U EN DES - MEB NEG Approved By: . ,.
Superhendent b Supv., NPHPS ROB, MS NRC-IE:II Power Security Officer, 604 PRB-C Nuclear. Materials Coordinator Date Approved: l O / f (.9 /~79 Manager, OP-QA&A Staff
. / / 1U P Prod Plant Eng. Branch Rev. No. Date Revised Pages Rev. No. Date Revised Pages 0 7/6/76 All _
1 /r//6,/7di-i All The last page of this instruction is Number -h~
7 911060 Y Y w ,,
gi
a . .
. SQlP TI-18
, Punch 11st
. Page 1 of 1 Rev. 1 PU'ICHLIST (1) Plant procedures should be changed to comply with TI-18 (3 's, SI's 82, 83, etc.).
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1272 003 G
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SQ'I?
TI-18 Page 1 of 1 Rev. 1 -
INDEX A. SCCPE B. Sequoyah Nuclear Plant - Radiation Monitors C. Instructions and/or worksheets for setpoint determination and verification for adiation monitors.
D. Liquid Release Records - Batch and continuous releases E. Gas ReJease Records - Batch (containment purges and vaste gas decay tank releases).
Appendix A - Maximum instantaneous release rates (10 CFR 20)
AppendixB-SNPPlantVenthlovrates Appendix C - RD-35 Setpoint Derivation 1272 004
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SQNP TI-18 Pase 1 of 3
, Fev. 1 3ection A I. SCOPE A. Purpose This instruction serves the following purposes:
- 1. Establishes initial setpoints for process radiation monitors and adjustment setpoints to account for chan6es in background conditions.
- 2. Establishes initial setpoints for effluent radiation monitors and adjustment setpoints to account for batch releases and/or changes in backg1 und conditions.
~
- 3. Establishes a method to verify detector efficiencies.
- h. Sunmarices , for 'nformational purposes, batch gaseous and liquid effluent release data.
B. Requirements This technical instruction supports the surveillance programs used to satisfy technical specification requirements. Surveillance instructions reference this technical instruction for calculations of alar =/ trip setpoints.
II. REFERENCES A. General Atomic Calibration Reports
- 1. Required curves from these reports included in this instructicn.
B. SQNP Technical Specifications C. SQNP Final Safety Analysis Report III DESCRIPTICN The remainder of this technical instru : tion is broken down into four sections and four appendices. A description of the purpose of each section and appendix follows.
A. Section B.l' lists the appropriate section C portion to use for setpoint or efficiency verification of a particular detector type. Section B.2 lists each radiation monitor at Sequoyah and the section or sections required to determine monitor setpoints.
B. Section C is used to determine each or all of the following fcr a particular detector type.
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SQNP TI-18 Page 2 of 3
. Rev. 1 III. B. Continued
- 1. Initial operational setpoint determination.
- 2. Adjusted operational setpoint determination.
- a. Monitor setpoints are initially determined by best judgement of what radiation levels vill be and such that technical spec-ifications will not be violated. After enough operation Pas occurred, monitor setpoints ray require cha.7;es to allow for operational flexibility. However technical specifications vill still be observed.
3 Periodic operaticnal setp61nt determination
- a. For certain effluent monitors, such as the shield building exhenst (RM-90-100), setpoints must be changed to suit each different type of release. For example, a release setpoint fer a vaste gas decay tank would be different than for a release of the containment purge air volume. Each different type of release vill be controlled by an SOI and the performsnce of a surveil-lance instruction. The surveillance instruction vill reference this technical instruction to calculate the release monitor setpoints.
- h. Detector Efficiency Verification
- a. This technical instruction can be used to verify that a monitor is correctly responding. This is done by comparing the monitor's output to a ga==a scan determination of what the monitor should read.
- b. Section C and D provides a su= nary sheets of gaseous and liquid releases. These su==ary sheets are for historical purposes only and will be retained in the Radiochemical laboratory files.
NOTES: All data collected on these sheets are recorded in the appropriate surveillance instructions which become part of the plants lifetime records. Therefore, the section D su==ary sheets vill be maintained as QA documents because of number sequence for a release (batch or continuous).
- c. Appendix A provides a list of Sequoyah's maximum 111ovable instantaneous release rates which were calculated in accordance with the Of' site Dose Calculation Manual (CDCM). Each limit was established on the bases of limiting dose to 500 =r/yr to the total body frc= noble gases and 1500 =r/yr to the thyroid from iodines and particulates.
- d. Appendix 3 tabulates the maximum design flovrates for each vent exhaust to be used in Section C setpoint calculatiens.
7-12/2 006 9
SQ10 ,
TI-15 Page 3 of 3 Rev. 1
- e. Appendix C documents the derivation of the iodine monitor (RD-35) setpoint evaluation.
- f. Appendix D tabulates the FSAR and technical specifications limits required to calculate monitor setpoints in section C.
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S C,NP TI-18 Page 1 of 2 Rev. 1 Section 3 B. SEQUOYAH RADIATION MONITOR IDENTIFICATION B.1 TYPES OF DETECTORS Detector Model Number Refer to Section Noble Gas- /9 Jetector (RD-32, RD-32-01) C.1 Noble Gas j@ Detector (RD-32-05) C.2 Noble Gas jg Detector (RD-32-08) C.3 Noble Gas _4} Detector (RD-30-01) C.h Iodine - ( Detector (RD-35) C.5 Particula}te-X3 Detector (RD-36-01) C.6 Liquid- if Detector (RD-33) C.7 Liquid- }f Detector ( RD-33 -06 ) C.8 B.2 Sequoyah Nuclear Plant - Radiation Monitors Detector Type -
Monitor Samule Stream Refer to Section 1-RM-90-99 Landenser vacuum Pu p Exhaust, U1 C.3 2-RM-90-99 Condenser Vacuum Pump Exhaust, U2 C.3 1-RM-90-100 Shield Building Exhaust, U1 C.1, C.5 and C.6 2-RM-90-100 shield Building Exhaust, U2 C.1, C.5 and C.6 0-RM-90-101 Auxiliary Building Exhaust C.1, C.5 and C.6 1-RM-90-104 Reactor Coolant Letdown, U1 C.8 2-EM-90-10h Reactor Coolant Letdown, U2 C.8 1-RM-90-106 Contain=ent Building Lower Conpartment, U1 C.1, C.5 and C.6
.2-EM-90-106 Containment Building Lower compartment, U2 C.1, C.5 and C.6 1-RM-90-112 Containment Building Upper Cc=partment, U1 C.1, C.5 and C.6 2-RM-90-112 Containment Building Upper Compartment, U2 C.1, C.5 and C.6 0-RM-90-118 Waste Disposal Gas Effluent C.h 1-RM-90-119 condenser vacuum Pump Exhaust, U1 C.1 2-RM-90-119 Condenser vacuum Pu=p Exhaust, U2 C.1 1-RM-90-120 Steam Generator Blowdown Liquid Effluent, U1 C.7 2-RM-90-120 Steam Generator Blowdown Liquid Effluent, U2 C.7 1-RM-90-101 Steam Generator Blowdown Liquid Effluent, U1 C.7 2-RM-90-121 Steam Generator Blowdown Liquid Effluent, U2 C.7 0-RM-90-122 Wdste Dicposal Liquid Effluent C.7 0-RM-90-123 Component Cooling System Con =on C.7
' RM-90-123 Component Cooling System, U1 C.7 2-RM-90-123 Component Cooling System, U2 C.7 1-RM-90-12h Steam Generator Blowdown, U1 U.7 2-RM-90-12h Steam Generator Blowdown, U2 C.7 0-RM-90-125 Main Control Room Intake C.1 0-RM-90-126 Main Control Room Intake C.1 12L/2 008
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SQNP TI-18 Page 2 of 2 Rev. 1 Section 3 Monitor Detector Type -
Samtle Stream Refer to Section 1-RM-90-1?0 Containment Purge Exhaust, U1 2-RM-90 '30 C.2 Containment Purge Exhaust, U2 C.2 1-RM-90-131 Containment Purge Exhaust, U1 2-RM-9f-131 C.2 containment Purge Exhaust, U2 C.2 0-RM C)-132 Service Building Exhaust C.1,C.5 and C.6 0-RM- 0-133 Essential Rav Cooling Water, Header A 0-RM-90-13h C.T Essential Rav Cooling Water, Header 3 C.T 0-RM-90-lho Essential Rav Cooling Water, Header A 0-RM-90-lh1 C.T Essential Rav Cooling Water, Header 3 C.T 1-F 4-90-170 Boric Acid Evaporator Condensate, U1 2-RA-90-170 C.T Boric Acid Evaporator Condensate, U2 C.T 0-RM-90-205 Main control Room Energency Intake 0-RM-90 906 C.1 Main Control Room Energency Intake C.1 0-RM Plant Liquid Discharge - Cooling Tower Blowdown 0-RM-90-die C.T Turbine Building Station Sump Discharge C.T 0-RM-90-225 Condensate Demineralizer Discharge 0-RM-90-12 Fuel Loading Area C.T 0-RM-90-13 C.6 Fuel Loading Area C.6 1-RM-90-lh Unit 1 Hot -Sample Room 2-RE-90-lh C.6 Unit 2 Hot Sample Room C.6 0-RE-90-15 El. 690.0 Area 0-RE-90-16 C.6 Decontenination Room C.6 0-RE-90-17 El. 669 0 Area C.6 1-RE-90 .62 Lower Compartment Instrument Rocs 2-RE-90-62 C.6 Lower Compartment Instr ment Room C.6
. 1272 009
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GQNP TI-18 Page 1 of 5 Rev. 1 Section C Instructions and/or Worksheets for Setpoint Determination and Verification For Radiation Monitors Section 18.C.1 RD-32,-32-01 DETECTORS NOTE: These two detectors are identical with respect to detector size. The only difference is in the amount of shielding.
Monitors: 1-RM-90-100(E) 1-RM-90-106(P) 1-RM-90-119(E) 0-RM-90-205(P) 2-RM-90-100(E) 2-RM-90-106(P) 2-RM-90-119 (E) 0-RM-90-206(P) 0-RM-90-101(E) 1-EM-90-112(P) 0-RM-90-125(P) 0-RM-90-132(E) 2-rd-90-112(P) 0-RM-90-126(P)
NOTE: E= Effluent P= Process A. Setpoint Calculation
- 1. Obtain gaseous release rate (or concentration) limits for nuclides used to determine monitor setpoint.
- 2. Obtain vent flow of exhaust stream to be monitored.
Complete Worksheet No. 13-C.1A.
J.
Calculatesetppgrtcountrateoymulti-y plying nuclide concentration by its sensitivity and sunming for all expected nuclides.
B. Detector Efficiency Verification
- 1. Obtain gaseous sample of medium per TI-16, and record the appropriate monitor's count rate at time of sampling on worksheet TI-18-C.1.B.
- 2. Cour sample according to TI-12, Method B.S.
- 3. Complete Worksheet No. 18-C.13.
Calculateexpeyggdcountratebymulti-plying nuclide concentration by its sensitivity and senming for all detected nuclides. Compare with monitor count rate at time of sampling.
Calculate percent deviation.
NOTE: a. Sensitivities were determined for the beta rays (with intensities greater than one percent) of anticipated nuclides. The sensitivity for each beta ray was multiplied by the beta ray's intensity, and th'ese products were summed, yielding an overall sensitivity. Sen-sitivities for these and other nuclides may be determined from Figure 18-C.1 and the nuclide's beta rays and respective intensities.
Information supplied by " Nuclear Decay Data for Radionuclides oc-urring in routine releases from nuclear fuel cycle facilities" (Au6ust 1977, prepared by Cak Ridge National Laboratory), and General Atomics calibration reports. (March 1974).
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SQ3P TI-18 Page 2 of 5 Rev. 1 Worksheet No. 18-C.1A Setpoint Calculation Worksheet (Gas g Detector; PD-32,32-01)
Monitor Dat3 Time
- 1. Obtain Limiting Nuclide Concentrations a.
For 100, 101, 119 and 132 obtain applicable vent exhaust limiting concentration by dividing release rate ifmit (section D, Appendix A) by the maximum design vent flowrate (Section D, Appendix 3).
A Ci/S AR-41 =
Ci/S KR-85 "
=
jrCi/cc Ar-h1 g Ci/S KR-85m gCi/cc KR-85
=
g Ci/S KR-87 =
gCi/cc KR-85m
/g.Ci/S FR-88 gCi/cc KR-87 A.Ci/S KR-89 CFM x 28320 CC/CF j =
=
g,C1/cc Kr-88 g Ci/S Xe-131M . =
ACi/cc KR-89
,Ci/S Xe-1E -
60S/ Min =
gCi/cc Xe-131M g Ci/S Xe-133M Ci/cc Xe-133 g,Ci/S ( =
Ci/cc . 1.33M Xe-135 \ =
g.Ci/S Xe-135M =
ci/cc Xe 35 Ci/S Xe-137 gCi/cc Xe-135M
=
g Ci/S Xe-138 =
g Ci/cc Xe-137 g,Ci/S (Other) g Ci/cc Xe-138 p,Ci/S (Other)
=
gCi/cc (Other)
=
pCi/cc (Cther) b.
Monitors 106 and 112 have a Technical Specification Limit of 8.5E-03 j<.Ci/ce.
Iux..a1 setpoint concentration vill be 1/I' of this value based on Xe133. For 125 and -900-205 obtain limiting concen-tation from Appendix D Ci/cc Ar-h1 C1/cc Kr-85 ACi/cc Xe-133X g Ci/cc Kr-85m C1/cc Xe-135 g i/cc C Kr-87 C1/cc Ze-135M g Ci/cc Kr-88 g Ci/cc Xe-137
';i/cc Kr-89 gCi/cc Xe-130 g i/cc C Xe-131M g Ci/cc (other)
Ci/cc Xe-133 g Ci/cc (other) 1272 011 y
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SQNP TI-18
. Page 3 of 5 Rev. 1 Worksheet 18-C.1A bbnitor Date Time
- 2. Multiply Nuclide Limiting Concentration by Detecto Efficiency for Nuclide Isotope-Isotora Concentratier. Monitor Efficiency - Isotone ( ) Cal. Monitor Restonse pfCi/cc AR 41 x 6.00E07 CPM /f4 Ci/cc = CPM ff Ci/cc KR-85 x 5.66E07 CPM /f(Ci/cc = CPM f( Ci/cc KR-85M x 5.89E07 CPM / y Ci/cc = CPM f4 Ci/cc KR-87 x 6.00E07 CPM /jptCi/cc = __ CPM p( Ci/cc KR-88 x h.71E07 CPM //L Ci/cc = CPM ff Ci/cc KR-89 x 6.00E07 CPM /jq Ci/cc = CPM f4 Ci/cc 7E-131M x 3.2hE07 . CPM /f4 Ci/cc = CPM 6C Ci.'ec .(e-133 x 3.50E07 CPM /f4 Ci/cc = CPM f(Ci/cc XE-133M x h.57E07 CPM// q Ci/cc = CPM jq Ci/cc XE-135 x 6.00E07 CPM / = CPM f( Ci/cc XE-135M x 1.30E07 CPM/R/ptCi/cc Ci/cc = ___ CPM f( Ci/cc Xe-137 x 6.00E07 CPM //4 Ci/cc = CPM f(Ci/cc XE-138 x 6.00E07 CPM /jg Ci/cc = CPM
/4 Ci/cc ( )x ( ) CPM / p(Ci/cc = CPM jq Ci/cc ( )x ( ) CPM /jq Ci/ec = "'11 (a)Obtained From Figure 18-C.1. (Sum of isotopic energies multiplied by their respective percent abundances).
- 3. Tote.1 CPM
- h. Multiply Total (Step 3) Ey Appropriate Safety Factor (S.F.)
For 100 S.F. = 0. 2 119 S.F. = 0.2 101 S.F. = 0.5 125 S.F. = 1.0 106 S.F. = 0.1 205 S.F. = 1.0 112 S.F. = 0.1 NOTE: Safety factors can be changed only by the approval of the lead of cognizant chemical engineer and noted or worksheet in remarks section.
132 S.F. = 0.2 Safety Factor x Total (Value from Step 3) x CPM = CPM 5 Background Count Rate For Monitor: CPM NOTE: Established by isolating monitor and injectin,g service air or air frca room that radiation monitor is located into monitor. If cannot be obtained by this means use zero as the background (CPM) countrate.
- 6. Monitor Setpoint = (h) + (5)
CPM = + CPM = CPM (h) (5) (setpoint) 9, J.nalyst Date I 2
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Chem. Engr. Assoc. Date
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s 6 SQIIP rI-18 Page 4 of 5 Rev. 1 Worksheet 18-C.1B Section C.1 Detector Efficiency Verification (Gas p Detectors; RD-32, 01)
Fonitor . Date ~ime
- 1. Sample Activity Corrected to Time of Sampling. Cotain Count Rate.
Isotope -
Iluelide Concentration Mon. Efficiency-Isotope Calculated Mon. Ilesp.
,gCi/cc AR-41 x 6.00E07 CPM //4Ci/cc = CPM
)(Ci/cc KR-85 x 5.66E07 CPM //4Ci/cc = CPM
,. .Ci /c c KR-85M x 5.89E07 CPM //4 Ci/cc = CPM gCi/cc KR-87 x 6.00E07 CPM /g Ci/cc = CPM gCi/cc KR-88 x 4.71E07 CPM// 4 Ci/cc = CPM gCi/cc 12.- 8 9 x 6.00E07 CPM / g i/cc = CPM pCi/cc Xe-131M x 3.2hE07 CPM /g Ci/cc = CPM gCi/cc Xe-133 x 3.50E07 CPM /g.Ci/cc = CPM gCi/cc Xe-133M x h.57E05 PM/ Ci/cc = CPM jaci/cc Xe-135 x 5.00E07 CPM / = CPM gCi/cc Xe-135M x 1.30E07 CPM _Ci/cc
/g Ci/cc = CPM gCi/cc Xe-137 x 6.00E07 CPM / g i/cc =__ _ CPM f(C1/cc Xe-138 x 6.00E07 CPM /g.Ci/cc = CPM gCi/cc ( ) x ( ) CPM /S.Ci/cc = CPM gCi/cc ( ) x ( ) CPM /g 01/cc = CPM Obtained frca Figure 18-C.1. (Gum of Isotopic energies multiplied by their respective percent abundancies.)
- 2. Total Calculated Monitor Response CPM
- 3. Background Count hte for Monitor: CPM Il0TE : Established by isolating monitor and injecting service air or air from room shere monitor is located into monitor. If cannot be obtained by this means then use zero as the beckground count rate.
- h. Calculated Monitor Countrate: (2) + (3) -
CPM + CPM = CPM (2) (3) 5 Actual monitor count rate reading at time of sample: CPM 1272 013 40-e'
SQNP TI-18 Page 5 of 5 Rev. 1 Worksheet 18-C.1L Section C._
Moni+.or Date Time
- 6. Calculate Percent Deviation : (h) - (5) X 100 (h)
(h) (5)
X 100 > % (b), (c)
(4) .
NOTES:
Engr. for percent deviations greater than 30%. Note in remarks section.
- c. For count rates greater than 500 CPM, noti.'y chem. engr. assoc. or chem.
engr. for percent daviations greater than 10%. Note in remarks section.
Analyst Date Chem. Engr. Assoc. Date Remarks:
1272 014
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GQNP TI-18 Page 1 of k Rev. 1 SECTION C.2 RD-32-05 DETECTtR Monitors: 1-RM-90-130(E) 1-RM-90-131(E) 2-RM-90-130(E) 2-RM-90-131(E)
NOTE: E = Effluent A. Setnoint Calculation
- 1. Setpoint shall be a fraction of the SNP Technical Specification (initial 1/10 of 8.5E-03 jtCi/cc (tech. spec. limits) for containment concen-tration) based on XE-133 (XE-133 assumed to account for majority of activity at time of purge. ))
- 2. Reevaluation of radiation setpoints will be based on grab samples taken from lower containment (RM-90-106) 3"d allovable release rate through the shield building exhaust. The reevaluation of setpoint (tech spec fraction 1/10 of allovable limit) required approval of lead or cogni-cant chemical engineer and when initiated noted in worksheet remarks section.
. Detector ffficiency Verification
- 1. Obtain gar sample from both upper and lower compartments per TI-16, and record appropriate purge monitor's count rate at time of sampling.
- 2. Count sample (s) according to TI-12, method 3.5 Use the most restrictive results for calculations (either upper or lover).
- 3. Complete 'Jorksheet No. 18-C.23. Calculateexpeyggdcountratebymulti-plying nuclide concentration by its sensitivity # and summing for all detected nuclides. Compare with purge monitor count rate at time of sampling. Calculate percent deviation.
NOTE: (a) Sensitivities were determined for the beta rays (vith inten-sities greater than one percent) of anticipated nuclides.
The sensitivity for each ray was multiplied by the beta ray's intensity, and these products were su=med, yielding an overall sensitivity. Sensitivities for these and other nuclides may be determined from Figure 18-C2 and the nuclide's beta rays and respective intensities. Information supplied by " Nuclear Decay Data for Radionuclides occuring in routing releases from Nuclear Fuel Cycle Facilities" (August 1977, prepared by Oak Ridge National Laboratory), and General Atomics Calibration Reports E-115-721, April 1979).
1272 015 O
SQRP TI-18 Curve 18-C.1 Page 1 of 1 Rev. 1 i i i g- i 4 a .
Y-90 Xc-13$
it Kr 8 Kr-6) Kr-G3 p
Xc-133 t, '-
L
/i Tr.-99 gf xe-t33
/
mo / .
- - 2 -
k e
-5 -
9E Er 3
W0 c. 7 -
10
-1 3-h "c 6
8 v
1 4 -
V C-14 2 -
' ' ' ' ' '- ' I I ' ' ' ' '
10 0.3 0.9 1.0 1.2 1.3 1. 4 1.5 0.1 0.2 0.3 0. 'i 0.5 0.6 0.7 f.I g EldCRGY MeV NAX General Ato::ics Calibration Report E-199-350 (?! arch 197h) - RD-32 detecter.
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1272 016
SQNP TI-18 Page 2 of k Rev. 1 .
Worksheet No. 18-C.2A SETPOINT CALCULATION WORKSHEET (Gasj9 Detector; RD-32-05)
Monitor Date Time
- 1. Limiting isotope concentration: Ci/cc (Initial Setpoint: (8.5E-Oh jd,Ci/cc based on Xe-133)
- 2. Detector Efficiency for isoto.,e in step 1=
(obtained from Figure 18-C.2) ( CFM/4Ci/ce)*(0.0h4) f
- 3. Calculated Count Rate: (1) x (2)
JA Ci/cc x . CPM //4 Ci/cc = CPM (Initial Count Rate Setpoint: 22h3 CFM Sased on Xe133).
- h. Background Cour.t aate: CPM UOTE: sstablishe dby isolating monitor .nd injecting service air or air from room that .nitor is located into monitor. If cannot be obtained by this means are zero as background count rate.
5 Monitor Setpoint: (3) + (h)
CPM + CPM = CPM (3) (4) (Setpoint)
Analyst Date Chem. Engr. Assoc. Date Remarks :
1272 017
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SQNP TI-18 Page 3 of k Rev. 1 Worksheet No. 18-C.2B DETECTOR EFFICIE' ICY VERIFICATION (Gas 6> Detector; RD-32-05 )
Monitor Date Time
- 1. Sample activity corrected to time of sampling. Use most cestricting isotope (controlling 'ightest concentration).
(0.0kh) * ,
gCi/cc (controlling isotope) *( CPM //4Ci/cc)" = CPM NOTE: " Obtained from Figure 18-C.2
- 2. Background Count Rate: CPM UCTE: Established by isolating monitor and injecting service air or air from room that monitor is located into monitor. If cannot be obtained by this means then use zero as the background count rate.
- 3. Calculated Monitor Cer.nt Rate: (1) + (2)
- h. Monitor count rate reading at time of sampling: CPM 5 Calculate percent deviation: (3) -(h) .
x 1gg (h)
CPM CPM Percent deviation = -(13) (14)
X 100 = % (a),(b)
CPM (3)
N OTES: (a) For count rates10-500 CPM, notify chemical engineer associate or chemical engineer for percant deviations greater than 30%. Note in remarks section.
(b) For count rates greater than 500 CPM, notify chemical engineer
, associate or chemical engineer for percent deviations greater than 10%. Note in remarks section.
Analyst Late Chem. Engr. Assoc. Date Femarks:
Y.
,.- -/ E-
m< e TI-18 Page 4 of h Rev. 1 FIGURE 18-C.2 8
- i 4 . 4 . . . . . . , , .
Xc- l 15 y-99 ct-36 1 l t w
6 -
,/
&,g Kr-85n i
nr-37 Kr-85 Kr-23 4 _ Xc-133
/
/l
_. Tc-93 e x,:- 133 O o -
5 e [ _
S o9 E -, -
bk v
0 el ,
10' - ._
O .
l 1
- i l't: '
$ $ su ej u --
s
.o, 4 -
V C-14 2 -
5 ' ' ' ' '
10 - ' ' ' f ' r t O.! 0.2 0.3 0.4 0.5 0.6 0.7 0.3 0.9 1.0 1.1 1.2 1.3 1.4 1.5
/) El4tnr Y .*t. v MAX
}h GENERAL ATOMICS CALIBRATICN REPORT E-199-350 (!! arch 197h) . This is a curve for the RD-32 detector. Efficiencico for the RD-32-05 can be obtained by multiplying the efficiency from this curve by the ratio of the detector areas of the RD-32-05 to the RD-32 (Ratio equal to 0.0hk) and multiplying by percent abundance of each major photopeak.
- 4. P00R ORGIN1
SQNP TI-18 Page 1 of 6 Rev. 1 SECTION C.3 RD-32-08 DETECTOR Monitors: 1-RM-90-99(E) 2-RM-90-99(E) NOTE: E= Effluent A. Setpoint Calculation
- 1. Obtain gaseous release rate (or concentration) limits for nuclides used to deternfre netp? i nt.
- 2. Obtain vent flav of exhaust to be monitoza..
- 3. Complete Worksheet No. 18-C.3A. Calculatesetp7gytcountratebymulti-plying nuclide concentration by its sensitivity and summing for all expected nuclides.
- 3. Detector Efficiency Verificscion
- 1. Obtain gaseous sample per TI-16, and record,the appropriate monitor's count rate at time of sampling.
- 2. Count sample according to TI-12, method 3 5 3 Complete Worksheet No. 18-C.3.3. Calculate expected multiplying nuclide concentration by its sensitivity (gquat #
andrate by for summing all detected nuclides. Compare with monitor count rate at time of sampling. Calculate percent deviation. NOTE: (a) Sensitivities were dete rmined for the beta rays (with intensi-ties greater than one percent) of anticipated nuclides. The sensitivity for each beta ray was multiplied by the beta ray's intensity, and these products were su=med, yielding an overall sensitivity. Sensitivities for these and other nuclides may be determined from Figure 18-C.3 and the nuclide's beta rays and respective intensities. Information supplied by " Nuclear Decay Data for Radionuclides occurring in routine releases from nuclear fuel cycle facilities" (August 1977, prepared by Oak Ridge National Laboratory), and General Atomics calibration report E-115-721, April 1979 1272 020 47-9
SQNP TI-18 Fage 2 of 6 Rev. 1 Worksheet No. 18-C.3A SETPOINT CALCULATICH WORKS'E.ET ( Ge.s g Detector; RD-32-03) Monitor Date Time
- 1. Obtain Limitins Concentration by dividing release rate limit (Appendix A) by the maximum design vent flovrate (Secuon D, Appendix 3).
Isotore Concentration Maximum Desien Flowrate Isotope Limiting Cone. mci /S AR-kl = gCi/CC AR bl gC1/S KR-85 =_ 'g Ci/CC KR-85 gCi/S KR-85M . = g Ci/CC KR-85M gCi/S KR-87 = gCi/CC KR-87 gCi/S KR-88 = gCi/CC KR-88 gCi/S KR-89 g
=
gCi/CC KR-89 qCi/S Xe-13Di . i CFM x 28320 CC/CP = gCi/CC Xe-131M gCi/S Xe-133 7( 60S/ min = gCi/CC Xe-133 g,Ci/S X -133M = ci/CC Xe-133M gCi/S Xe-135 = ACi/CC Xe-135 gCi/5 Xe-135M =
/(Ci/CC Xe-135M C1/S Xe-137 = q Ci/CC Xe-137 f(Ci/S Xe-138 =
'A C1/CC Xe-138 gCi/S ( ) =
'gCi/CC( )
j(Ci/S ( ) = gCi/CC( )
- 2. Multiply Limiting Concentration by detector efficiency for each nuclide.
" Obtain from General Atomic Calibration Report E-115-721, April 1979 Isotonic Concentration Monitor Efficiency - Isotone (" Calc. Mon. Resucnce A Ci/CC AR-kl x 6.06E05 CPM /ACi/CC CPM Ci/CC KR-85 x 6.23E05 CPM /A Ci/CC = CPM
_ g.Ci/CC KR-85M x 6.h8E05 CPM / mci /CC = CPM Ci/CC KR-87 x 6.06E05 CPM /gCi/CC = CPM A Ci/CC KR-88 x 5 18E05 CPM /M.Ci/CC = CPM C1/CC KR-89 x 6.06E05 CPM /g Ci/CC = CPM g Ci/CC XE-13DI x 3 56E05 CPM /g Ci/CC = CPM Ci/CC Xe-133 x 3.85E05 CPM /g Ci/CC = CPM jrCi/CC Xe-133'4 x 5 03E05 CPM /g Ci/CC = CPM g Ci/CC Xe-135 x 6.06E05 CPM /ACi/CC = CPM g C1/CC Xe-135M x 1.h3E05 CPM / Ci/CC = CPM g Ci/CC Xe-137 x 6.06E05' CPM /g Ci/CC = CPM Ci/CC Xe-138 x 6.06E05 CPM /g Ci/CC = CPM
/4 Ci/CC( ) x( ) CPM /g Ci/CC = CPM ja.Ci/CC( ). x( ) CPM /A.Ci/CC = CPM (a)Obtained from Figure 18-C.3. (See note on figure).
1272 021
-/2 -
SQU TI-19 Pa c 3 of 6 Rev. 1 Worksheet No. 18-C.3A Monitor Date Time
- 3. Total calculated monitor response: CPM
- h. Background Count Rate for Monitor: CPM NOTE: Established by isolating monitor and inserting service air or air from room that monitor is located into monitor. If cannot be obtained by this method then use zero as the background count rate.
5 Monitor Setpoint = (3) + (h)
- 0.1 (safety factor)
(0.1)
- CPM + CPM = CPM (3) (k) (Setpoint)
NOTE: Safety factor can be changed only by the approval of the lead or cogni-zant chemical enginear and noted in remarks section of worksheet. Analyst Date Chem. Engr. Assoc. Date Remarks: 1272 022 s' "
SQRP TI-18 Page h of 6 Rev. 1 Worksheet No. 18-C.3B Detector Efficiency Verification (Gas g Detector; RD-32-08) Monitor Date Time
- 1. Sample activity corrected to time of sampling. Obtain count rate.
Isotone Concent: tion Mon. Efficienev-Isotope (" Computed Mon. Resocnse A Ci/CC Ar-41 x 6.06E05 CPM //( Ci/CC = CPM g Ci/CC Kr-85 x 6.23E05 CPM / A Ci/CC = CPM g Ci/CC Kr-85M x 6.h8E05 CPM /A Ci/CC = CPM g Ci/CC Kr-87 x 6.06E05 CPM /A Ci/CC = CPM g Ci/CC Kr-88 x 5 1TE05' CPM /A.Ci/CC = CPM g Ci/CC Kr-89 x 6.06E05 CPM / M Ci/CC = CPM g Ci/CC Kr-131M x 3.56E05 CPM /A Ci/CC = CPM g Ci/CC Xe-133 x 3.85E05 CPM /A Ci/cC = __ CPM g Ci/CC Xe-133M x 5 03E05 CPM /A Ci/CC = CPM g Ci/CC Xe-135 x 6.06E05 CPM / A Ci/CC = CPM g C1/CC Xe-135M x 1.h3E05 CPM /A. Ci/CC = CPM g Ci/CC Xe-137 x 6.06E05 CPM / M Ci/CC = CPM g.Ci/CC ( )x( ). CPM / A Ci/CC = CPM
.Ci/CC ( )x( ) CPM / / .{.Ci/CC = CPM
" Obtained from Figure 18-C.3 (See footnote on figure).
- 2. Total Calculated Monitor Response CPM
.3. Background Count Rate for Monitor: CPM NOTE: Established by isolating monitor and injecting service air or air from room that monitor is located into monitor. If cannot be obtained by this means, then use zero as the background count rate.
- h. Calculated monitor count rate: (2) + (3)
CPM + CPM = CPM (2) . (3) 5 Monitor Count Rate reading at time of sampling: CPM
- 6. Calculate percent deviation:
(h) (h)
- (5) X 100 = % dev.
CPM (k) - CPM (5) x 100 = % (1), (2) CPM (h) . ,-
, -2 0 - .
SQiP TI-18 Page 5 of Rev. 1 Worksheet No. 18-C.' Monitor Date Time NorES: (1) For count rates of 10-500 CPM, notify Chem. Engr. Assoc. or Chem. Engr. for percent deviations gerater than 30%. Note in remarks section. (J) For count rates greater than 500 CPM, notify Chem. Engr. Assoc. or onem. Engr. for percent deviations greater than 10".. Note in remarks section. Analyst Date Chem. Engr. Assoc. Date Remarks: 1272 024
-2. / -
SQNP TI-18
. Page 6 of 6 Fi 6ure 18-C.3 Rev. 1 3" . i e . . 4 6 , , ; , , ,
Xr.i35 Y-90 6w i CL-3fi l l l . i gM [ f 'j f p j Ar-d5 Kr-CC;n 77,3j K r - i,3
... / Xc-1;8
'/ i
/1 I L. 7 -93 g xc.133 l
-, j s - -
g 2 - 2 l r- / BM i U 44 / ga 7 _l 2 -
- x. _
Q .
> R g g 6 -
E *
~
4L _
.V c-14 2 '
'=-J ' ' ' '
10' r i .e . . , i I 6.1 0.2 0.3 0 . '. 0.5 0.6 0./ 0.3 0.9 1.0 1.1 1.2 1.3 1.1 i.S General Atomics Calibration _ Report E-199-350 (March 1974) This is a curve for the RD-32 detector. Efficiencies for the RD-32-03 can be obtained by multiplying the efficiency from this curve by the ratio of the by $h0enF a%un8anH *oPeHr1 8
,,gg ,39,,g ,ga,,( m o e w 1 to 0.0 m ana re v.,s 1271325 P00R DSM
SQNP TI-18 Section C.h Page 1 of h Bev. 1 RD-30-01 DETECTOR
?' aitor: 0-MR-90-118(E)
NOTE: E = Effluent A. Settoint Calculatien
- 1. Obtain sample, per TI-16, and pressure of gas decay tank to be released.
- 2. Count sample according to TI-12, Method 3 5 3 Complete workshee,t no. 18-C.hA. Calculate setpoint count rate by multiplying the detected.nuclides concentration by the detector sensitivity (a) for each nuclide. It is assumed that only KR-85 remains in significant quantity at the time of tank discharge when tank has been held for 60 days.
B. Detector Efficiency Verification
- 1. Obtain gas sample of gas decay tank exhaust header, per TI-16, and the monitor's count rate at the time of sampling.
- 2. Count sample according to TI-12, Method 3.5 3 Complete worksheet no. 18-C.hB. Calculate expected count multiplying nuclide concentration by detector sensitivity ({ ate by
. Compare with monitor count rate. Calculate percent deviation.
NOTE: (a) The sensitivity was determined for the beta rays (with intensi-ties greater than one percent) of KR-85. The sensitivity for each beta ray was multiplied by the beta ray's intensity and these products were summed, yielding an overall sensitivby. Sensitivities for the beta rays of KR-85 vere deter Ined from Figure 18-C.h. Information supplied by " Nuclear Decay Data for Radionuclides occuring in routine release from Nuclear Fuel Cycle
, Facilities" ( August 1977, prepared by Oak Ridge National Laboratdry),
and General Atomics Calibration Reports. 1272 026 e us e T
,A 0
SQNP TI-18 Page 2 of 4 Rev. 1 Worksheet No. 18-C.hA Setpoint Calculation Worksheet (Gas p Detector; RD-30-01)
- 1. Sample activit,y corrected to time of sampling. Activity concentration should be expressed. At ambient conditions. Multiply by detector isotopic s ent.itivity.
Isotope Concent:ation Monitor Efficiency-Isotope " Come. Mon. Response g Ci/CC AR '.1 x 5.h2E0h CPM /#.Ci/CC = CPM g Ci/CC KR 85 x h.86Evh CPM / g Ci/CC = CPM f( Ci/CC K3-85M x 6.12E0h CPM / X Ci/CC = CPM
/< Ci/CC KR-8T x 5 97E04 CPM / M Ci/CC = CPM fi Ci/CC KR-88 x h.23E04 CPN/ p Ci/CC = CPM
= CPM A Ci/CC XE-133 x 3.28E0h CPM / A.Ci/CC
= CPM A ci/CC XE-135 x 5 53E0h CPM / /( Ci/CC =
g CI/CC Xe-135M x 9/81E03 CPM / /( Ci/CC CPM g Ci/CC XE-133 x 5 10E0h CPM / g Ci/CC = CPM g Ci/CC ( ) x( ) CPM / g Ci/CC = CPM g Ci/CC ( ) x( ) CPM / f(Ci/CC = CPM
" Obtained from Figure 18-C.h.
- 2. Total Calculated Monitor Response CPM
- 3. Complete monitor setpoint by multiplying by a factor of 1.1 (factor to pre at inadvertent trips) 1.1 x CPM (value in step 2) = CPM
- 4. Monitor Background Count Rate:
Note: Obtained by taking monitor reading prior to initiating the release. 5 Monitor Setpoint: (3) + (h) CFM (3) + CPM (h) = CPM Analyst Date Chem. Engr. Assoc. Date Remarks: _g 1272 027
./
SQNF TI-18 Page 3 of k Rev. 1 . Worksheet No. 18-C.hB Detector Efficiency Verification (Gas g Detect;r; RD-30-01)
- 1. Sample activity corrected to time of samp1h.v. Express activity concentration at ambient conditions. Multiply by detector sensitivity.
Isotore Concentration Monitor Efficiency-Isotoue "
/JCi/CC Ar-41 x 5.h2E0h CPM / F.Ci/CC = CPM p Ci/CC Kr-55 x h.86E0h CPM / p C1/CC = CPM M Ci/CC Kr-85m x 6.12E0h CPM / A Ci/CC = CPM y C1/CC Kr-87 x 5.9"04 CPM / M Ci/CC = CPM Ci/CC Kr-88 x 4.23E04 CPM / M.Ci/CC = CPM j(Ci/CC Xe-133 x 3.28E0h CPM / A Ci/CC = CPM g C1/CC Xe-135 x 5.53E0h CPM / A Ci/CC = CPM g Ci/CC Xe-135M x 9.81E03 CPM / A C1/CC = CPM g Ci/CC Xe-138 x 5.10E04 CPM / p.Ci/CC CPM g Ci/cc( ) x( ) CPM / p.Ci/CC = CPM g Ci/CC(_ ) x( ) CPM / g Ci/CC = CPM (a)Obtained from figure 18-C.h
- 2. Total Calculated CPM 3 Compute monitor setpoint by multiplying by a factor of 1.1 (factor to prevent inadvertent trips).
1.1 x CPM (value in Step 2) = CPM
- h. Monitor background count rate: CPM NOTE: Obtained by taking reading prior to initiating discharge.
5 Add (3) + (h): CPM (3) + CPM (h ) = CPM
- 6. Monitor count rate reading at time of sampling: , CPM 7 Calculate percent deviation: (5) (6) x 100 (5)
CP 4 (5) - CPM (6) x 100 = _ % (a), (b) CPM (5) NOTES: (a) For count rates 10-500 CPM, notify chen. engr. asscc. or chen. engr. for percent deviations greater than 30%. Note in remark section below. (b) For count rates greater than 500 CPM, notify chem. engr. usoc. or chem, en6r. for percent deviations greater than 10%. Note in re srks section below. Analyst Date Chem. Engr. Assoc. Date Remarks: 1272 028
SGP TI-18
- Figure 18-C k hge h of 4 Rev. 1
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- t energy, fiev e n Operating at 760 mm Hg abs and 25 C.
.12./2 029 GENERAL ATOMICS CALIBRATIO3 RE" ORT E-115-593 (March 1978). ~ ~"~
P00R ORGINAL
SQUP TI-18 Page 1 of 5 Rev. 1 Section C.5 RD-35 Detector Monitors: 1-R'4-90-100( E ) 1-P24-90-106(P) 2-R!4-90-100(E) 2-P;4-90-106 ( P ) 0-EM-90-101(I) 1-R:4-90-112 ( F ) 0-RM-90-132(E) 2-RM-90-112(F) NOTE: P= Process E= Effluent A. Setnoint Calculation
- 1. Obtain iodine rele rate (or concentration) limit for nuclide used to determine setpoint
- 2. Obtain maximum design vent flow of exhaust stream to be monitored, monitor sample flowrate (controlled 4' 2 CFM), and sample time (usually 168 hours-one week).
- 3. Complete worksheet no. 18-C.5A. Calculate setpci count rate by multi-plying nuclide concentration by its sensitivity \"
B. Detector Efficiency Verification -
- 1. Obtain charcoal filter from monitor per TI-16, and record appropriate monitor's count rate at time of sampling.
- 2. Count sample according to TI-12, Method B.5
- 3. Completeworksgtno.18-C.5B. Calculateexpectegountratebymulti-plying nuclide concentration by its sensitivity . Compare with monitor count rate. Calculate percent deviation.
NOTE: (a) RD-35 is a single channel analy::er monitgring I-131. (b) Detector sensitivity for I-131 (2 7 x 10 epagci)suppliedbyGeneral Atomics Calibration Report (November 197h). 1272 030
- ) ]-
/*
SQNP TI-18 Page 2 of 5 Rev. 1 Section C.5 Worksheet No. 18-C.5A Setpoint Calculation Worksheet (Iodine Y Detector; RD-35)
- 1. Obtain Limiting Nuclide Concentration:
- a. For 100, 101, and 132, obtain limiting concentration by dividing release rate limit (Appendix A) by the maximum design vent flovrate (Appendix B).
3 g Ci/Sec I-13 . CFM x 28320 CC/ft C = g,Ci/CC
/\ -
60 sec/ min j I-131
- b. For 106 and 112, obtain limiting concentration from FSAR (Final Safety and Analysis Report), Table 12.1-1.
/( Ci/CC
- 2. Calculate average monitor flovrate for sample period.
(avg.) CFM x 60 min x 2h hr x 2.832E04 g3" day E hr ft day
- 3. Determine accumulation term by the following equation:
A = (Nuclide Concentration
- Monitor Efficjency("
- Monitor Flovrate (1) ( f4.Ci/CC) (I-131:2 7x10 CPM / /4C1) (2) (CC/ day)
(Sample Period (whole days) A= j4 Ci/CC (I-131) x 2.TE04 (CPM) x CyC, (1) (f4C1) (2) Day Days A= CP! Sy)2 Note: (a) Obtained from Ceneral Atomic Calibration Report 1272 031
-2 9 -
,/
., v c TI-18 Page 3 of 5 F.ev. 1 Section C.5 Worksheet No. 18-C.5A
- h. Determine nuclide decay tern:
NOTE: For I-131 and e. sampling period of 7 days DT = 16.5 D See Appendix C derivation of equations to evaluate nuclide decay term for sampling periods less than 7 days. 5 Monitor Setpoint = Accumulator term (A) x decay term (DT) (Less Background) (3) (b)
= CT:st x D 2
(3) D (3)
= CPM
- 6. Monitor background count rate: CPM
- 7. Add (5) and (6)
CPM + CPM = CPM (5) (6) 1272 032'
-2 9 -
e
SQNP TI-18 Page h of 6 Rev. 1 Section C.5 Worksheet No. 16-C.53 Detector Efficiency Verification (Iodine D' Detector; RD-35) Monitor Date Time
- 1. Sample activity corrected to time of sampling:
/4Ci (I-131)
- 2. Monitor Background count rate:
CPM - 3 Monitor count rate at time of sampling: CPM
- h. Calculated detector sensitivity for I-131:
CPM - CPM (3) (2)
= CPM gCi gCi 5 Calculate percent deviation:
_ CPM / g.Ci - 2 7E04 " CPM / A Ci x 100 = % 2.7E04 CPM / jutCi
" RD-35 Monitor effici ncy for I-131.
1272 033
-jo -
/
GQNP
.I-18 Page 5 of 6 Rev. 1 Section C.5 Worksheet No. 18-C.5B
!4cnitor Date Time Hotes: (1) For count rates 10-500 CPM, notify chen. engr. assoc. or chem. engr.
for percent deviations greater than 3C%. Note in remarks section. (2) For count rates greater than 500 CPM, notify chem. engr. assoc. or chem. engr. for percent deviatiois greater than 10%. Note in remarks section. Analyst Date Chem. Engr. Assoc. Date Remarks: L272 034
SCTP TI-18 Page 6 of 6 Rev. 1 Section C.5 RD-32 Monitor Setpoints - Initial (Does not include background count rate) Service Building (-90-132): 3710 CPM Auxiliary Building (-90-102): 3876 CPM (for 220,000 CFM) Upper Compartment (-90-112): 29750 CPM Lover Compartment (-90-106): 29750 CPM Shield Building (-90-100): 58333 CPM ' 1272 035 _. 9 - s-
,,e 9
S Q'IP TI-18 Page 1 of 5 Rev. 1 Section C.6 A. RD-36-01 Particulate p Detector for the following process monitors: (I) 8 CFM Effluent Monitors: 1-RM-90-100 2-I'.'~-90-106 2-RM-90-100 1-RM-90-112 0-RM-90-101 2-K4-90-112 1-RM-90-106 0-RM-90-132 (II) 10 CFM Area Monitors: 0-RM-90-12 , 0-RM-90-16
. 0,-RM-90-13 ,
0-RM-90-17 1-RM-90-14 1-E4-90-62 2-RM o0-lh 2-RM-90-62 0-L-90-15 0-RM-90-138 (III) Setpoints: Effluent Monitor Setpoint 1-RM-90-100 1.1E-8 /4.Ci/CC 2-RM-90-100 1.1E-8 g.C1/CC C-RM-90-101 1.hE-9 p.ci/CC 1-RM-90-106 1.SE-5 g Ci/CC
- 2. PS2.on-106 1. SE-5 g.Ci/CC 1-RM-90-112 1.5E-5 g.Ci/CC 2-RM-90-112 1.SE-5 .Ci/CC 0-RM-90-132 2.8E-9 .C1/CC Area Monitor Setpoints "
0-RM-90-12 3.0E-9 p,Ci/CC 0-RM-90-13 3.0E-9 p-C1/CC 1-EM-90-14 3.0E-9 Ci/CC 2-RM-90-lh 3.0E-9 p Ci/CC 0-RM-90-15 3.OE-9 p.Ci/CC 0-EM-90-16 3 0E-9 p.Ci/CC 0-RM-90-17 3.0E-9 / li/CC 1-RM-90-62 3.0E-9 Ci/CC 2-RM-90-62 3.0E-9 p.Ci/CC 0-RM-90138 3.0E-9 p.Ci/CC Notes: (a) Setpoints for area monitors are initial setpoints only, to be reset by Health Physiciet c llowing o operatinc experience. (h) I-131 is used to convert g Ci/CC to CPM for each monitor. 1272 036
-n-
../
SQ!TP TI-18 Page 2 of 5 Rev. 1 Section C.6
- 3. Detector Efficiency Verification
- 1. Obtain particulate filter sample according to TI-16, and record the monitor count rate at time of sampling on work sheet no.
18.C.6.1.
- 2. Count sample according to TI-12, method B.5 Identify the major contri-buting nuclides and its activity on work sheet no.18.C.6.1.
- 3. Obtain the monitors average flow rate for samples duration from SI-2.
Record on worksheet no. 18.C.6.a.
- 4. Complete vorrsheet no. 18.C.6.1. Calculate expected count rate by dividing eachnuclidesactivitybythemonitorsaverageflowrateanpjhe .asple duration time, then multiplying by the nuclides sensitivity and decay factors using the following formula:
IIldelide 9 f ensitivity S 9 I Decay 7 (_ Activity (ftC1)
- CPM /(f(Ci/CC)-l Correction (e - A t)
Monitor = , h expected Avg. Monitor (ft'/ min)*fample ( min )
- Conversion (2.83 x 10'ec/ft#)
CPM flow rate Factor (duration J Where: ) = 0.693 and, t = duration time (hr) Half life (hr) (c) Obtained from figure 18-C.6 5 Sum the computed CPM' for all detected nuclides and add monitor's back-ground CPM.
- 6. Compare total expecte d CPM vith the monitor's count rate at time of sampling.
Calculate percent dev.'ation.
- 7. For :ount rates 10-500 t'PM, notify chem, engr. assoc. or chemical engineer for percent deviations gceater than 30%.
- 8. For count rates greater than 500 CPM, notify chemical engineer assoc, or chemical engineer for percent deviations greater than 10%.
12L72 337
-n -
/
SQUP TI-18 Page 3 of 5 Rev. 1 Section C.6 C. RD-36-01 Particulate 4 Detector Sensitivitie,s_
' Sensitivities d) Sensitivities Rad *.nuu'. ides 8CFM 10 CFM Half Life Barium - 1?9 1.03E12 1.08E12 Berium '40 9 97E11 1.38 hours Cesium - 13h 0.07E12 3v7.2 hours 7 35E11 7 7hE11 Cesium - 136 6.26E11 1.82Eh hrs Cesium - 137 7.69E11 31h.h hrs 9.h5E11 1.037E12 Cesium - 138 ,.77E11 2.6h5E5 hrs 1.03E12 0 503 hrs Cobalt - 58 1 32E11 Cob.:lt - 60 1.52E11 1699 2 hrs 5.8E11 7.2E11 Fluorine - 18 9.86E11 h.62Ek hrs Iodine - 131 1.03E12 1.83 hrs 9.6E11 1.01E12 Iodine - 132 1.01TE12 192 96 hrs Iodine - 13h 1.069E12 2.03 hrs 1.0E12 1.07E12 Iodine - 135 1.076E12 0.9h3 hrs Iron - 59 1.15E12 6.61 hrs 6.69E11 7.99E11 Lanthanum - bt0 1.03E12 1070.h hrs Molybdenum - 99 1.09E12 h2.2 hrs 1.12E12 1.20E12 Rubridium - 88 1.009E12 66.0 hrs Zirconium - 95 1.06E12 0.297 hrs 7.1hE11 8.87E11 Yttrium - 99 6.26E11 1535 5 hrs 7.69E11 1hoh.3 hrs (c) Obtained from figure 18-C.6.
Notes: (c) Sensitivities were determined for the Beta decay (with intensities greater than one percent) of anticipated nuclides. The sensitivity for each Beta decay was multiplied by the beta decays intensitf, and these products were summed, yeilding an overall sensitivity. Sensiti-vities the for other nuclides may be determined from curve 18.C.6 and nuclides. Beta decay energy and respective intensities. Inform-ation supplied by " Nuclear Decay Data for Radionuclides occurring in routine releases from nuclear Fuel Cycle Facilities" (August 1977), prepared by Oak Ridge National Laboratory. (d) Figure 18-C.6 - sensitivities are based on monitor flow rate of 8 or 10 CFM operating in fixed filter mode for 1 hour (units for sensitivity are(CPM /(4(Ci/CC)) 1272 0 %
-3s-
SQNP TI-18 Page h of 5 Rev. 1 Section C.6 Worksheet 18.C.6.1 CALIERATION WORKSEEET NO. 18.6-1 ((RD-36-01) Particulate Monitors) Monitor Date Time
- 1. Monitor reading at time of sampling: CPM
- 2. Average monitor flow rate during- ft /3 min sample duration, from SI-2.
- 3. Ident' ried - Huclide nuclide
- Nuclides Activity (//Ci/CC) Count Rate (CPM)
Ba - 1h0 = Cs - 137 = Co - 58 = Co - 60 = Fe - 59 = I - 131 =
- h. Total CPM NOTE: (e) Count rate calculated by formula in section C.6 (B.h) 5 Expected count rate = total CPM + background
= (#h) + 100 CFM
= CPM
- 6. Calculste monitors percent deviation:
5 deviation = Calculated CPM - Actual CFM x 100 Calculated CPM
= (# 5) - (# 1) x 100
(# 5)
=
Lab Anal; st / 12/ z 039 Chemical Eng. Assoc. ~/ Approved By Chemical Engineer /
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~3 7-
.' 1212 040
SQNP TI-18 . Section C.7 Page 1 of 5 Rev. 1 RD-33 II DETECTCR Monitors: 1-RM-90-120(E) 2-RM-90-123(P) 0-EM-90-lkl(E) 2-RM-90-120(E) 1-RM-90-12h(P) 1-RM-90-170(P) 1-R'4-90-121( E ) 2-Fd4-90-12h ( P ) 2-Fd4-90-170(P) 2-RM-90-121(E) 0-RM-90-133(E) 0-EM-90-211(E) 0-RM-90-122(E) 0-RM-90-134(E) 0-EM-90-212(E) 0-RM-90-123(?) 0-RM-90-lh0(E) 0-RM-90-225(E) 1-RM-90-123(P) Note: P = Process E = Effluent A. Setroint Calculation -
- 1. Obtain liquid sumple of medium per TI-16.
- 2. Count sample according to TI-12, method B.5
. Complete Worksheet No. 18-C.7A. Calculate setpoint multiplying nuclide concentration by its sensitivity {gyntand rate by summing for all detected nuclides.
B. Detector Efficiency Verification
- 1. Obtain liquid sample of medium per TI-16 and record the appropriate monitor's count rate at time of sampling.
- 2. Count sample according to TI-12, method 3.5 3 Complete Worksheet No. 18-C.7B.
Ca3culateexpectedyountrateby multiplying nuclide concentration by its sensitivity "# and summing for all detected nuclides. Compare with monitor count rate at time of sampling. Calculate percent deviation. NOTES: Sensitivies were determincd for the gamma rays (with intensities greater than one percent) of anticipated nuclides. The sensitivity for each gamma ray was multiplied by the ga=ma ray's intensity, and these products were summed, yielding an overall sensitivity, Sensitivities for these and other n '1. ides may be determined from Figure 18-C.7 and the nuclide's gar- rays and respective intensities Information supplied by " Nuclear Dev , Jata for Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities" (August 1977, prepared by Cak Ridge National Laboratory) ar.d General Atomics Calibration Reports (February 1976). 1272 041
-3 8-s*
SGIP TI-18 Section C.7 Page 2 of 6 Rev. 1 Worksheet No. 18-C.7A Setpoint Calculation Worksheet (Liquid T Detector; RD-33) Monitor Date Time
- 1. Sample activity corrected to sample time.
Isotopic Computed Isotore Concentration Monitor Sensitivity-Isotore(" Monitor Restonse g Ci/cc Sb-122 X 3~.01E08 CPM /M C1/cc (Sb-122) = CPM g Ci/cc Sb-12h X 6.65E06 CPM /A Ci/cc (Sb-12h) = CPM g Ci/qc Ba-lho X 1.3hE08 CPM //4 Ci/cc (Ba-lh0) = CPM g Ci/cc Ce-1kh X 3.65E07 CPM /A C1/cc (Ce-1kh) = CPM g Ci/cc Cs-134 X 8.79E08 CPM /Aci/cc (Cs-134) = CPM g,Ci/cc Cs-137 X 3.h1E08 CPM /ACi/cc (Cs-137) = CPM g,,Ci/cc Cr-51 X h.08E07 CPM /A.Ci/cc (Cr-51) = CPM g Ci/cc Co-58 x 5 06ECS CPM /ACi/cc (Co-58) = CPM g,Ci/cc Co-60 X 6.h8E08 CPM /# Ci/cc (Co-60) = CPM g Ci/cc F-18 X 8.03E08 CPM /#.Ci/cc (F-18) = CPM g Ci/cc I-131 X h.02E08 CPM /A Ci/cc (I-131) = CPM g Ci/cc I-133 X h.06E08 CPM /A.Ci/cc (I-133) = CPM ACi/cc I-135 X 3 99E08 CPM /Aci/cc (I-135) = CPM g Ci/cc Fe-59 X 3.h7E08 CPM /A C1/cc (Fe-59) = CPM g Ci/cc La-lho X 7.05E08 CPM /p Ci/cc (La-lh0) = _ CPM g Ci/cc Mn-5h X 3.80E08 CPM /P Ci/cc (Mn-Sh) = CPM g Ci/cc Mn-56 X h.82E08 CPM /A Ci/cc (Mn-56) = CPM g Ci/cc Mo-99 X 1.19E08 CPM /g Ci/cc (No-99) = CPM g C1/cc Nb-95 X 3.89E08 CPM /M.Ci/cc (Nb-95) = CPM g Ci/cc Na-2h X 5.20E08 CPM /ACi/cc (Na-24) = CPM C1/nc Tc-99m X 3.09E08 CPM /p.Ci/cc (Tc-99m) = CPM Ci, cc Xe-133 X 1.85E07 CPM /#.Ci/cc (Xe-133) = RPM g Ci/cc Xe-135 X 3.80E08 CPM /ACi/cc (Xe-135) = CPM g C1/cc Zn-65 X 1.88E08 CPM /A Ci/cc (Zn-65) = CPM g Ci/cc Zr-95 x 3.89E08 CPM /ACi/cc (Zr-95) = CPM g Ci/cc Ru-103 X 3.80E08 CPM /p.Ci/cc (Ru-103) = CPM g Ci/cc ( )X( ) CPM /p.Ci/cc ( )= CPM g.Ci/cc ( )X( ) CPM /p.Ci/cc ( )= CPM g,Ci/cc ( )X( ) CPM /p.Ci/cc ( )= CPM 2. (Total Calculated) = CPM (" Obtained from Figure 18-C.T. (Summary of isotopic energies multiplied by their respectiv.e isotope (major per.ks) percent abundances). 1272 042 e
SC;IP TI-18, Section C.7 Worksheet No. 18-C.7A Page 3 of 6 Rev. 1 Date Time
- 3. For monitor (s) 1-RM-90-120(E) 2-RM-90-120(E) 1-RM-90-121(E) 2-RM-90-121(E) 0-R'4-90-122(E ) 0-EM-90-225(E)
NOTE: E = Effluent The setpoint vill be 3 1.25( } X Total calculated (from Step No. 2). Setpoint for monitor -RM is: 1.25 X CPM = ,__ CPM
, Background = + CPM Total CPM
" For monitor (s) 0-RM-90-123(P) 2-RM-90-12h(P) 1-RM-90-123(P) 1-RM-90-170(P) 0-RM-90-134(E) 2-RM-90-123(P) 2-RM-90-170(P) 0-RM-90-140(E) 1-RM-90-12h(P) 0-RM-90-133(E) 0-RM-90-lh1(E) 0-EM-90-212 (E )
The setpoint vill be 1.00 X Total Calculated (From Step No. 2). Setpoint for monitor is: 1.00 X CPM = CPM 3ackground = + CPM Total = CPM For monitor 0-RM-90-211 the setpoint will be 0 90 X Total Calculated (From Step No. 2). Setpoint for monitor 0-RM-90-211 is: 0 90 x CPM = CPM Background = + CPM Total = CPM NOTES: (1) Scaling factor to prevent alarms / trips due to variations in the effluent concentrations at the release point. This cannot be changed without the prior approval of the lead or cognizant chemical engineer and noted in the remarks section of worksheet. Lab Analyst Date Chem. Engr. Assoc. Date Remarks: 1272 043
SQNP
, TI-18 Section C.7 Page 4 of 6 Rev. 1.
Worksheet No. 18-C.73 Detector Efficiency Verification Worksheet-(Liquid Y Detector; RD-33) Monitor Date Time
- 1. Sample activity corrected to sample time. Obtaia Count Rate.
Isotopic Computed Isotore Concentration Monitor Sensitivity-Isotore " Monitor Restense W Ci/cc Sb-122 X 3.01E08 CPM /g Ci/cc (Sb-122) = CPM g Ci/cc Sb-12h X 6.65E08 CPM /p.Ci/cc (Sb-124) = CPM g Ci/cc Ba-lh0 X 1.3hE08 CPM /A Ci/cc (Ba-lho) = CPM g Ci/cc Ce-1kh X 3.65E07 CPM /g Ci/cc (Ce-1kh) = CPM g Ci/cc Cs-13h X 8.79E08 CPM /p Ci/cc (Cs-13h) = CPM g Ci/cc Cs-137 X 3.41E08 CPM /A Ci/cc (Cs-137) = CPM g Ci/cc Cr-51 X h.08E07 CPM /p.ci/cc (Cr-51) = CPM g Ci/cc Co-58 x 5.06E08 CPM /x Ci/cc (co-58) = CPM g C1/cc Co-50 X 6.48E08 CPM /ACi/cc (Co-60) = CPM g Ci/cc F-18 X 8.03E08 CPM /ACi/cc (F-18) = CPM g Ci/cc I-131 X h.02E08 CPM /A Ci/cc (I-131) = CPM g Ci/cc I-133 X 4.06E08 CPM /p.Ci/cc (I-733) = _ CPM g Ci/cc I-135 X 3.99108 CPM /g Ci/cc (I-135) = CPM p Ci/cc Fe-59 X 3.b7t?8 CPM /A Ci/cc (Fe-59) = CPM
/< Ci/cc La-lho X 7.05E08 CPM //tCi/cc (La-lh0) = _ JPM Ci/cc Mn-54 X 3.80EJ8 CPM /p.Ci/cc (Mn-5h) = CPM Ci/cc Mn-56 x 4.82E08 CFM/ACi/cc (Mn-56) = CPM g Ci/cc Mo-99 X 1.19F08 CPM /ACi/cc (Mo-99) = CPM g Ci/cc Ub-95 X 3.89E08 CPM / .Ci/cc (Nb-95) = CPM g Ci/cc Na-2h X 5.20E08 CPM /g.C1/cc (Na-24) = CPM Ci/cc Tc-99m X :. 09E08 CPM /p. C1,'ec (Tc-99m) = CPM Ci/cc Xe-133 X 1.85E07 CPM /ACi/cc (Xe-133) = CPM g Ci/cc Xe-135 X 3.80E08 CPM /A Ci/cc (Xe-135) = CPM g Ci/cc "n-65 X 1.88E08 CPM /A Ci/cc (Zn-65) = CPM Ci/cc Zr-95 X 3.89E08 CPM /p Ci/cc (Zr-95) = CPM Ci/cc Ru-103 X 3.80E08 CPM /p.Ci/cc (Ru-103) = CPM g Ci/cc ( )X CPM /ACi/cc ( )= CPM jc Ci/ec ( )X CPM /ACi/cc ( )= CPM
/4.Ci/cc ( )X CPM /M Ci/cc ( )= CPM
- 2. (Total Calculated) = CPM
" Cbtained from Figure 18-C.7 (Summing of isotopic energies cultipled by their respective irotope (major peaks) percent abundance).
1272 044
-p/-
(-
SQNP TI-18, Section C.T Worksheet No. 18-C.73 Page 5 of 6 Rev. 1 Date Time
- 3. Monitor Reading at time of sampling: CPM (Less 3ackground).
- h. Calculate monitor's percent deviation from calculated value:
% Leviation = (Valv 't Sten No. 2) - (Value in Sten No. 3) x 100 = % (a),(b)
(Value in Step No. 2) NOTES: (a) For count rates 10-500 CPM, notify Chemical Engineering Associate or Chemical Engineer for percent deviations greater than 30%. (b) For count rates greater than 500 CPM, notify Chemical Engineering Associate or Chemical Engineer for percent deviations greater than 10%. . Analyst Date Chem. Engr. Associate Date Remarks:
.s 1272 045
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SQNP TI-18 Section C.8 Page 1 of 6 Rev. 1 RD-33-06 Y DETECTOR Monitors: 1-RM-90-10h(P) 2-RM-90-10h(P) NOTE: P = Process A. Setpoint Determination
- 1. Setpoint is to reflect any detection of failed fuel in the primary coolant and remain above expected activity levels as the life of the core progresses. The alarm vill be arbitrarily set amid scale (10" CPM) initially and readjustment based on operating experience.
B. Detector .iciency Verification
- 1. Obtain liquid sample of coolant letdown per TI-16, and record the monitor count rate at the time of sampling.
- 2. Count sample according to TI-12, =ethod 3.5
- 3. Complete Worksheet No. 18-C.83. Calculayg)expectedcountratebymultiplying nuclide concentration by its sensitivity and summing for all detected nuclides. Compare with monitor ccunt rate at time of sampling. Calculate percent deviation.
NOTES: " Sensitivies were determined for the gamma rays (with intensities greater than 1 percent) of participated nuclides. The censitivity for each gamma ray was multiplied by the ga=ma ray's intensity, and these products were summed, yielding an overall sensitivity. Sensitivities for other nuclides may be determined from Figure 13-C.8 and the nuclide's gamma rays aad respective intensities. Information supplied by Nuclear decay data for Radionuclies occuriang in routine releases from nuclear fuel cycle facilities" (August 1977, prepared by Oak Ridge National Laboratory) and General Atomics Calibration Report (July 1975). 1272 047
- yv -
SQ'lP TI-18 Section C.8 Page 2 of 6 Rev. 1 Worksheet No. 18-C.8A Setpoint Calculation Worksheet (Liquid T Detector; RD-33-06) Monitor Date Time
- 1. Sample activity corrected to sample time.
Isotopic Computed Isotone Concentration Monitor Sensitivity-Isotope (" Monitor Resnonse g Ci/cc Sb-122 X 2 57E05 CPM /p.Ci/cc (Sb-122) = CPM g Ci/cc Sb-12h X 6.0hE05 CPM /A Ci/cc (Sb-12h) = CPM g Ci/cc Ea-lh0 X 1.1hE0h CPM /A Ci/cc (Ba-lho) = CPM gCi/cc Cc-lkh X 2 5hE0h CPM /A Ci/cc (Ce-lhh) = CPM g Ci/cc Cs-134 X 7.81E05 CPM / .Ci/cc (Cs-13h) = CPM g Ci/cc Cs-137 X 3.01E05 CPM /p.Ci/cc (Cs-137) = CPM g C1/cc Cr-51 X 3.h5E0h CPM / .Ci/cc (Cr-51) = CPM g Ci/ec Co-58 x h.h6E05 CPM /N.Ci/cc (Co-58) = CPM g C1/cc Co-60 X 6.0hE05 CPM /A Ci/cc (Co-60) = CPM g Ci/cc F-18 X 6.96E05 CPM / ACi/cc (F-18) = CPM g,C1/cc I-131 X 3.h3E05 CPM /M Ci/cc (I-131) = CPM gCi/cc I-133 X 3.56E05 CPM /ACi/cc (I-133) = CPM g Ci/cc I-135 X 3.67E05 CPF/p.Ci/cc (I-135) = CPM
,__ g Ci/cc Fe-58 X 3.16E05 CPM /A Ci/cc (Fe-59) = CPM g Ci/cc La-lh0 X 6.h5E05 CPM /ACi/cc (La-lkO) = CPM g Ci/cc Mn-54 x 3.39E05 CPM //4 Ci/cc (Mn-Sh ) = CPM g Ci/cc Mn-56 X h.k2E05 CPM /A Ci/cc (Mn-56) = CPM g Ci/cc Mo-99 X 9 95E04. CPM /pci/cc (Mo-99) = CPM g C1/cc Nb-95 x 3.h7E05 CPM //4Ci/cc (Nb-95) = CPM g Ci/ce Na-24 X 5.23E05 CPM //4.Ci/cc (Na-2h) = CPM A Ci/cc Tc-99m X 2.18E05 CPM /p.Ci/cc (Tc-99m) = CPM gCi/cc Xe-135 X 3.12E05 CPM /A Ci/cc (Xe-135) = CPM
,_ gCi/cc Zn-65 X 1.69E05 CPM /ACi/cc (Zn-65) = CPM g Ci/cc Zr-95 X 3.47E05 CPM /A Ci/cc (Zr-95) = CPM j4Ci/cc Ru-103 X 3.30E05 CPM /p.Ci/cc (Ru-103) = CPM g,Ci/cc ( )X CPM /A Ci/cc ( )= CPM gCi/qc ( )X CPM /A Ci/cc ( )= CPM g Ci/cc ( )X CPM //4 Ci/cc ( )= CPM
- 2. (Total Calculated) = CPM
" Obtained from Figure 18-C.8. (Summing of isotopic energies multiplied by their major peaks respective isotope percent abundances).
1272 08 .
-yr-
SQNP TI-18
. Section C.8 Page 3 or 6 Rev. 1 WORKSHEET N0. 18-C.8A Date Time
- 3. For Monitor (s) 1-PR-90-10h 2-RM-90-10h The setpoint vill be 1.00 X Total Calculated (From Step :lo. 2).
Setpoint for monitor -RM-90-10h is: (1.00) X ( CPM) = CPM Lab Analyst Date Chem. Engr. Associate Date Remarks: _g_ 1272 049 i
SQNP TI-18 Section C.8 Page 4 of 6 Rev. 1 Worksheet No. 18-C.83 Detector Efficiency Verification Worksheet (Liquid T Detector; RD-33-06) Monitor Date Time
- 1. Sample activity corrected to sample time. Obtain count rate.
Isotopic Computed Isotone Concentration Monitor Sensitivity-Isotooe " Monitor Resncnce
/4 Ci/cc Sb-122 X 2 57205 CPM /A ci/cc (Sb-122) = CPM p Ci/cc Sb-12h X 6.0hE05 CPM /A Ci/cc (Sb-12h) = CPM g Ci/cc Ba-lho X 1.14E04 CPM /A Ci/cc (Ba-lh0) = CPM p Ci/cc Ce-lkh X 2 5hE0h CPM /g.Ci/cc (Ce-lkh) = CPM g Ci/cc Cs-134 X 7.81E05 CPM /A ci/cc (Cs-134) = CFM g Ci/cc Cs-137 X 3.01E05 CPM /S Ci/cc (Cs-137) = CPM g Ci/cc Cr-51 X 3.h5E04 CPM /A Ci/cc (Cr-51) = CPM g Ci/cc Cc-58 x 4.46E05 CPM /p.Ci/cc (Co-58) = CPM g Ci/cc Co-60 X 6.0hE05 CPM /p.Ci/cc (Co-60) = CPM g Ci/cc F-18 X 6.96E05 CPM //tCi/cc (F-18) = CPM g Ci/r.c I-131 X 3.h3E05 CPM /p.Ci/cc (I-131) = CPM g,Ci/cc I-133 X 3.56E05 CPM /A Ci/cc (I-133) = CPM g,Ci/cc I-135 X 3.67E05 CPM / .Ci/cc (I-135) = CPM g.Ci/cc Fe-58 X 3.18E05 CPM //.t Ci/cc (Fe-59) = CPM p ci/cc La-lho X 6.L5E05 CPM /g C1/cc (La-140) = CPM p.Ci/cc Mn-54 X 3.39E05 CPM /A Ci/ce (Mn-5L) = CPM p.Ci/cc Mn-56 X h.h2EOS CPM /p.Ci/cc (Mn-56) = CPM g Ci/cc Mo-99 x 9 95E04. CPM /p,Ci/cc (Mo-99) = CPM Ci/cc Ub-95 X 3.47E05 CPM /g Ci/cc (Nt -95) = CPM g Ci/cc Na-2h X 5 23E05 CPM /g Ci/cc (Ha-2h) = CPM g.Ci/cc Tc-99m X 2.18E05 CPM /g Ci/cc (Te-99m) = CPM g Ci/cc Xe-135 X 3.12E05 CPM /X Ci/cc (Xe-135) = CPM g Ci/cc Zn-65 X 1.69E05 CPM /gCi/cc (2n-65) = CPM g.Ci/cc Zr-95 X 3.h7E05 CPM /g Ci/cc (Zr-95) = CPM g Ci/cc Ru-lo3 X 3.30E05 CPM /g Ci/cc (Ru-103) = CFM g C1/cc ( )X CPM /M Ci/cc ( )= CPM
/4,Ci/cc ( _X
) CPM /g Ci/cc ( )= CPM g Ci/cc ( )X CPM /M.Ci/cc ( )= CPM
- 2. (Total Calculated) = CPM
" Obtained from Figure 18-C.8. (Summing of isotopic energies multiplied by their respective major peak (s) isotope percent abundances).
1272 050
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SQNP TI-18 Section C.8 Page 5 Of 6 Rev. 1 Worksheet No. 18-C.83 Date Time
- 3. Monitor -EM-90-10h reading at time of sampling: cpl! (less background)
- h. Calculate monitor's percent deviation from calculated value:
% deviation = (Value in No. 2) - (Value in No. 3) X 100 = %
(Value in No. 2) NOTES: (1) Por count rates 10 - 500 CPM, notify Chemical Engineering Associate. or Chemical Eneineer for percent deviations greater than 30 percent. (2) For count ratus greater than 500 CFM, notify Chemical Engineering Associate or Chemical Engineer for percent deviations greater than 10 percent. 1272 051 Lab Aanalyst Date Chem. Engr. Associate Date Remarks:
,- 2 E. .:P TI-lO Page 6 of 6 Hev. 1 F1,,ucc .13-C.8 5
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SQNP TI-1A Section D Page 1 of 3 Rev. 1 D. Liquid Release Records. Batch and Continuous Releases. Attachment A is to number and to chronologically list releases - 3atch and Continuous. Attachment 3 is to number and to chronologically list all releases fe: a particular tank (separate sheet for each tank) *
- 1. Evaluate the release permit number to be assigned to the (batch or continuous) liquid release by obtaining the next sequential numbe.-
from Attachment A logsheet being used and log on an appropriate SI and TI-18 Attachments A a.td B. The release permit number is evaluated using the following numbered sequential ft:5ila: (1) - (2) - (3) - (h) Release Permit Number = (XX) - (XXXXX), (XX) - (XXX) (1) Current Year (i.e. 79, 80, 81, . . .) (2) Sequential Number of Total Plant Releases (3) Tank Number 01 Laundry and Hot Shower Tank "A" 02 Laundry and Hot Shower Tank "B" 03 Chemical Drain Tank Oh Waste Condensate Tank "A" 05 Waste Condensate Tank "B" 06 Waste Condensate Tank "C" 07 Monitor Tank 08 Cask Decontamination Collector Tank 09 High Crud Tank "A" 10 JIgh Crud 'Iank "B" 11 Hon-Reclaimable Waste Tank 12 Waste Evaporator Distillate Tank "A" 13 Waste Evaporator Distillate Tank "B" 1h U1 Steam Generator Blowdown Flash Tank 15 U2 Steam Generator Blowdown Flash Tank 16 CDWE Blowdown Tank (h) Sequ'ential Number of Individual Tank Releases 1272 053
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SQIIP TI-18, Section D l Page 2 of 3 ' Rev. 1 ATTACHMEliT A ,, Liquid-Batch and Continuous Releases
\'
Release Permit Time Time flaximum Dilution Volume Total 14PC Fraction Total fiumber Date Start Stop Allowable Flow Released Before After Release Analyst XX-XX-XXXXX-XXX , Flow (GPM) (GP!4) (GAL) Release Relea:,e Activity ( C1) ND 4 L I N s s N N O LD
.c:=
SQNP TI-18, Section D
/ Page 3 of 3 ,
Rev. 1 ATTACHMENT B .. Tank Tank Number _
\, Liquid-Batch and Continuour Releases Release Permit Time Time Maximum Dilution Volume Total MPC Fraction Total Humber Date Start Stop Allowable Flow Released Before Arter Releece Analyst XXXXXXXXXXXX Flow (GPM) (GPM) (GAL) Release Release Activity ( C1)
O b i = M
~1 N
CD W W
SQiP TI-18, Section E Page 1 of 2 . Bev. 1 E. Gu eous Release Record - Batch (Gas Decay Tank Releases) Evaluate the release permit number to be assigned to the batch gaseous release (gas decay Lank or contairment purge) by obtaining the next sequential release number from Attaci=ent C logsheet being used and log on appropriate SI and TI-18 Attachment C. The release permit number is evaluated using the following numbered' sequential formula. (1) (2) (3) (h) R1 ease Permit Number = (XX) - (XXXX) - (XX) - (XXX) (1) Current Year (i.e. 79, 80, 81. . .) (2) Sequential Release Humber (To' .1.for Flerc) (3) Gas Decar Tank (A, B, C, . . . ) or Contairment Purge (?) (h) Sequential Release Number (for individual tank) 1272 056
- .g; .-
SQIIP
.) TIl8, Section E Page 2 of 2 Rev. 1
. ATTACIIMEllT C { GASEOUS RADWASTE - BATCH RELEASES Release Permit Date Time Date Time Max. Allowable Monitor Total Curies Cumulative Ilumber Start Start Stop Stop Flowrate Setpoint Released Curies Release XX-XXXX-X-XXX XXXX XXXX (CFM) (/ /.t Ci/ce ) ( Ci) ( Ci) Analyst
~
e g. e I e, N N CD LD N
SQNP
, TI-18 Appendix A Page 1 of 3 Rev. 1 J. R. Calhoun, Director of Nuclear Power, 716 E3, C G. F. Stone, Acting Director of Occupational Health and Safety, ROB, M September 28, 1979 SEQUOYAH NUCLEAR PLANT ENVIRONMENTAL TECHNICAL SPECIFICATIONS This is in response to your memorandum of September 19, 1979 Attached are the revised calculations of maximum instantaneous plant 6aseous release rate limits for SQN which- include limits for the service building.
These release rates have been back-calculated from 10CFR20 dose limits of 500 mrem /yr to the total body from noble gases and 1,500 mrem /yr to the thryoid from iodines and particulates. Due to the addition of the service building releases, release rate limits for the containment, auxiliary, and turbine buildings are approximately 99 percent of those which were trans-mitted from E. A. Belvin to H. J. Green on March 29, 1979 Because the dose rates at any time, due to radioactive materials release in 6aseous effluents from the site, shall be . limited to the above values (Specification-tion 3.11.2.1, UUREG-ChT2, Draft Radiological Effluent Technical Specifica-tion for PWR's), the attached rel+ se rates represent upper limits which should not be exceeded. However, the plant vill not be in violation of Specification 3.11.2.1 unless the instantaneous total plant release rate exceeds the total plant release rate limit specified in the attachments. Where automatic isolation does not exist, the actual monitor alarm set-points should be set at sone fraction of the above values. This should be done to assure that total plant releases do not at any instant exceed the above limits. In all cases, detector fluctuations (e.g. , voltage variation) should be considered when calculating the setpoints. Please address questions to Regis Nicoll or Rod Reed at extension 2767. G. F. Stone RMN:SH = Attachments cc (Attachments). ARMS PP, 823 EB-C J. M. Ballentine, SQN E. F. Thomas, 550 CST 2, C L. M. Mills, 400 CST 2, C D. R. Patterson, W10Cl26 C, K be (Attachments): John Dills, SQ" Ronnie Kitts, SQH 1272 058 R. B. Maxwell, ROB, M M. L. Rollins, 401 KB, C
.' _f5-
SQUP TI-18, Appendix A Page 2 of 3 Rev. 1 TABLE 1 S0)I MAXI?E4 INSTAUTANECUS PLANT RELEASE RATE LIMITS FOR 10CFR20 COMPLIANCE" NOBIS GASES ( %L Ci/s) Containment Auxiliary Turbine Service Nuclide Building Building Building Building Total Ar k1 1.8E+03 - - 1.8E+01 1.8E+03 Kr-85m 1 7E+02 1.6E+02 1.1E+02 4.5E+00 4.hE+02 Kr-85 3 7E+0h 1.hE+02 9 1E+01 3 7E+02 3.8E+04 Kr-87 6.0E+01 8.7E+01 6.0E+01 2.1E+00 2.1E+02 Kr-88 2.6E+02 3.0E+02 2.0E+02 7.6E+00 7.7E+02 Kr-89 6.1E-01 2.0E+00 h.7E+00 ~7.3E-02 7.hE+00 Xe-131m 1 9E+03 1.2E+02 8.0E+01 2.2E+01 2.1E+03 Xe-133m 1.2E+03 2 7E+02 1.8E+02 1.7E+01 1 7E+03 Xe-133 1.8E+05 2.1E+0h 1.hE+0h 2.1E+03 2.2E+05 Xe-135m 5.8E+00 1.hE+01 1 5E+01 3.hE-01 3.5E+01 Xe-135 7.3E+02 5 1E+02 3.3E+02 1.6E+01 1.6E+03 Xe-137 1.3E+00 h.2E+00 8.7E+00 1.hE-01 1.hE+01 Xe-138 1. 8.7+01 h.3E+01 h.6E+01 1.1E+00 1.1E+02 Total 2.2E+05 2.3E+0h 1.5E+0h 2.6E+03 2.6E+05 a. Calculated for worst case land site boundary, N sector, 950 meters, where total body submersion dose equals 2.13E-01 mrem /yr. 1272 059 y SQNP TI-18, Appendix A Page 3 of 3 Rev. 1 TABLE 2 SQN MAXIMUM INSTANTANEOUS PLANT RELEASE RATE
- LIMITS FOR 10CFR20 COMPLIANCE IODIUE AND PARTICULATES (A Ci/s)
Containment Auxiliary Turbine Service Nuclide Buildine Buildine Buildinc Euilding Total H-3 - - 1.8E+03 1.8E+01 1.SE+03 C-lh 2 7E+01 - - 2.7E-01 2 7E+01 Cr-51 8.7E-07 6.7E-08 1.2E-06 2.2E-08 2.2E-06 Mn-5h 1.0E-06 5 5E-08 1.5E-06 2.6E-08 2.6E-06 Fe-59 1.0E-06 7.2E-08 1.8E-06 3.0E-08 2 9E-06 Co-58 3.0E-07 1.8E-08 3.1E-05 3.1E-07 3.2E-05 Co-60 1.0E-06 5 3E-08 9.2E-07 2.0E-08 2.0E-06 Br-84 1.7E-05 1.2E-03 5.8E-05 1.3E-05 1.3E-03 3r-85 4.hE-07 4.OE-05 8.3E-07 4.1E-07 4.2E-05 Rb-88 7.0E-02 5 3E-02 3.5E-oh 1.2E-03 1.3E-01 Sr-89 h.0E-07 2.6E-08 5.5E-07 9.7E-G9 9 9E-0T Sr-90 1.5E-08 7.hE-10 2.9E-08 h.hE-10 h.5E-08 Sr-91 h.0E-08 5 0E-08 3.0E-07 3.9E-09 3.9E-07 Y-90 1.6E-08 1.3E-09 2.8E-08 h.5E-10 h.6E-08 Y-91m 2 5E-08 3.1E-08 1.hE-07 1.9E-09 2.0E-07 Y-91 2.hE-06 1 5E-07 6.hE-06 8.9E-08 9 0E-06 Y-93 8.2E-09 1.OE-08 1.2E-07 1.LE-09 1.hE-07 Zr-95 7.2E-08 h.kE-09 2.9E-07 3.6E-09 3.7E-07 Nb-95 T.3E-08 3 7E-09 2.8E-07 3.6E-09 3.6E-07 Mo-99 1.0E-Oh 3.hE-05 h.8E-Oh 6.2E-06 6.2E-oh Tc-99m 9.5E-05 3.0E-05 3.5E-Oh h.7E-06 h.8E-Oh
.Ru-106 1.hE-08 7.hE-10 2.9E-08 h.3E-10 4.3E-08 Te-132 6.8E-06 2.0E-06 7.0E-05 7.8E-07 8.0E-05 I-131 2.1E-02 7.6E-02 1.6E-02 1.1E-03 1.1E-01 MI-131 2.1E-02 7.6E-02 1.6E-02 1.1E-03 1.1E-01 I-132 6.3E-Oh 2.8E-02 h.hE-03 3.3E-04 3.3E-02 MI-132 6.3E-Oh 2.8E-02 4.hE-03 3.3E-oh 3.3E-02 I-133 5.6E-03 1.1E-01 2.3E-02 1.LE-03 1.4E-01 MI-133 5.6E-03 1.1E-01 2.3E-02 1.4E-03 1.LE-01 I-134 1.8E-Oh 1.2E-02 8.5E-Oh 1.3E-oh 1.3E-02 MI-134 1.8E-04 1.2E-02 8.SE-Oh 1.3E-0h 1.3E-02 I-135 1.5E-03 5 5E-02 9 1E-03 6.6E-Oh 6.6E-02 MI-135 1.5E-03 5 5E-02 9 1E-03 6.6E-oh 6.6E-02 Cs-13h 3.6E-05 1 9E-06 2.2E-oh 2.5E-06 2.6E-ch Cs-136 9.0E-06 9 7E-07 1.2E-Oh 1.3E-06 1.3E-oh Cs-137 2.6E-05 1.3E-06 1.8E-Oh 2.1E-06 2.1E-Ch Ba-lh0 1.5E-07 1.6E-08 7.1E-07 8.TE-09 8.8E-07 La-lh0 1.6E-07 1.1E-08 4.8E-07 6.hE-09 6.6E-07 ce-1kh h.6E-08 2.hE-09 1.4E-07 1.9E-09 1 9E-07 Pr-lh3 3.8E-08 3.7E-09 1.hE-07 1.8E-09 1.8E-07 Pr-lkh h.6E-08 2.6E-09 9.5E-08 1.hE-09 1 5E-07 Np-239 2.hE-07 9.0E-08 h.1E-06 h.5E-08 h.5E-06 Total 2 7E+01 6.2E-01 1.8E+03 1.8E+01 1.8E+03
- 1. Calculated for vorst case land site boundary, N sector, 950 meters, where infant thyroid dose equals 1.39E+01 mrem /yr. ,
g, 1272 060
SQUP
. TI-18, Appendix B Page 1 of 1 Rev. 1 PLANT VENT FLOWRATES (Maximum Design Flow)
Shield Building: 28,000 CFM (Each) Auxiliary Building: 200,000 CFM Service Building: 10,h00 CFM (Monitored by radiation detector) Condenser Vacuum Exhaust (Turbine Building): 100 CFM Gas Decay Tank Exhaust Header: 22.5 CFM
Reference:
47W866 Series Design maximum flovrate is h5 CFM - using value of 100 CFM for conservatism. k e 1272 061
-.gg -.
SQ'IP
. TI-18, Appendix C
. Page 1 of 2 Rev. 1 RD-35 DETECTOR-IODINE SETPOINT CALCULATION EQUATIONS Assume infinte number of layers of radioative material being deposited on monitoring medium. The summation of the product of the rate of accumulation A(t) and the rate of decay EXP(-Lt) is proportional to the monitor count rate.
1.a. Counts = kA(ty)(EXP(-Ltg)( 6 t ) The limit of this summation as at approaches zero is the definite 1 integral of the above mentioned product. 1.b. LIM k, A(t)g EXP(-Lty) At= A(t) EXP(-Lt)(dt) = Counts i--+ 0 Assume linear rate of accumulation over 1 week relative to reactor life. One week is normal sample period. t s
- 2. A(t) = f(t) dt 0
where f(t) = A(t) Substitute Eq. in Step (2) into Eq. in Step (1.b) t t
- 3. Counts = A(t) EXP(-Lt) dt = A *(t)(EXP(-Lt) (dt)
Integrate Eq. (3) by parts Let U = t dy = EXP(-Lt)dt dU = dt v = -1_ EXP(-Lt ) L (t)(EXP(-Lt) (dt)= (-t) EXP(-Lt) - [EXP(-LY)dt
= EXP (-Lt) + EXP (-Lt)
EXP(-Lts) - EXP(-Lt )- 0-
= -t s
\ \L k L ( (L
- h. =
1_ ItEXP(-Lt,))-EXP(-Lt )) 3 2 k L
/ )
1272 062
SQIP
. TI-18, Appendix C Page 2 of 2 Rev. 1 where L (Landa) = LII(2) = 0.693 = 0.0862d -1 t(1/2) 8.04d ts = 7d t(1/2) = Half Life I-131 Insert these values for L and t into Eq. in Step (h) and evaluate.
s 7d (t)( EXP(-Lt))(dt) = 16.5d 0 5 The accumulation term is determined by the following equation. A(t) = (Max. instantaneous nuclide Cone.) X (Monitor Efficiency) X (Mon. Flowrate) (Monitor Time) Assume exhaust concentration is equal to concentration in monitor sample stream. The product of Eq. in Step (5) and Step (b) vill given the desired concentration.
\,$.
s' O
SQNP
. TI-18, Appendix D Page 1 of 1 Rev. 1 SETPOINTS FOR RADIATION MONITORING (I) Process and Effluent Monitor Setpoints in FSAR and Technical Specification (process / monitors) are tabulated as follows:
Monitor Reference Setroint
-2 RM-90-106 Table 3.3-6 (Tech. Spec) 1.95x10 j,(.Ci/cc - Noble Gas
-2 RM-90-112 Table 3.3-6 (Tech. Spec) 1 95x10 ACi/cc - Noble Gas RM-90-106 Table 3.3-6 (Tech. Spec) 1 5x10 ' A Ci/cc - Particulate RM-90-112 Table 3 3-6 ('ech.
T Spec) 1.5x10 ' S Ci/cc - Particulate RM-90-125 FSAR Section 11.h.2.2 5 1x10 -3 X Ci/cc Based on Xe-133 RM-90-126 FSAR Section 11.h.2.2.5 1x10 ' /4.Ci/cc Based on Xe-133
-5 A Ci/cc Based on Xe-133 RM-90-205 FSAR Section 11.h.2.2.5 1x10 RM-90-206 FSAR Section 11.h.2.2 5 1x10- S Ci/cc Based on Xe-133
-0 RM-90-123 FSAR Section 11.h.2.1.3 1.5x10 A Ci/cc Based on I-131 FSAR Section 11.h.2.1 5 5 0x10
-5 RM-90-124 /-(Ci/cc Based on I-131 RM-90-133 FSAR Section 11.h.2.1.2 1 5x10- /4. Ci/cc Based on I-131 FSAR Section 11.h.2.1.2 1 5x10-
/cc Based on I-131 RM-90-134 RM-90-lh0 FSAR Section 11.h.2.1.2 1 5x10- M Ci/cc Based on I-131 FSAR Section 11.4.2.1.2 -6 RM-90-lh1 1 5x10 M Ci/cc Based on I-131 RM-90-170 FSAR Section 11.h.2.1.6 1.0X10 -5 A Ci/cc Based on I-131 RM-90-102 FSAR Section 11.h.2.2.3 10 mr/hr RM-90-103 FSAR Section 11.h.2.2.3 10 mr/hr 1272 064
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