ML20128K691
| ML20128K691 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/30/1985 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20128K649 | List: |
| References | |
| PROC-850630-01, TAC-49588, NUDOCS 8507110099 | |
| Download: ML20128K691 (138) | |
Text
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
Docket Nos. 50-245 50-336 50-423 License Nos. DPR-21 DPR-65 DPR-RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL Mllistone Unit Nos.1,2, & 3 l
Northeast Utilities Berlin, Connecticut I
i June,1985 l
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SECTION 1 RADIOLOGICAL EFFLUENT MONITORING MANUAL FOR THE MILLSTONE NUCLEAR POWER STATION i
UNIT NOS.1,2, & 3
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l RADIOLOGICAL EFFLUENT MONITORING MANUAL I
TABLE OF CONTENTS l
i SECTION PAGE NO. REY. NO.
A.
INTRODUCTION A-1 1
B.
RESPONSIBILITIES B-1 1
l C.
l.
LIQUID EFFLUENTS SAMPLING C-1 1
i AND ANALYSIS PROGRAM l
2.
LIQUID WASTE TREATMENT C-11 1
l D.
1.
GASEOUS EFFLUENTS SAMPLING D-1 1
l AND ANALYSIS PROGRAM l
2.
GASEOUS WASTE TREATMENT D-9 1
l E.
RADIOLOGICAL ENVIRONMENTAL MONITORING l
1.
SAMPLING AND ANALYSIS E-1 1
l 2.
LAND USE CENSUS E-3 1
l 3.
INTERLABORATORY l
COMPARISON PROGRAM E-4 1
F.
REPORT CONTENT 1.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING F-1 1
REPORT g
2.
SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT F-2 1
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A.
INTRODUCTION l
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- The purpose of this manual is to provide the sampling and analysis programs which provide input to the ODCM for calculating liquid and gaseous effluent concentrations and offsite doses. Guidelines are provided for operating radioactive waste treatment systems in order that offsite doses are kept as-low-as-reasonably-achievable (ALARA).
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The Radiological Environmental Monitoring Program outlined within this f
manual provides confirmation that the measurable concentrations of radioactive material released as a result of operations at the Millstone Site are not higher than expected, in addition, this manual outlines the information required to be submitted to the NRC in both the Annual Radiological Environmental Operating Report and the Semlannual Radioactive Ef fluent Release Report, i
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B.
RESPONSIBILITIES All changes to this manual shall be reviewed by the Station Operations Review Committee and the Nuclear Regulatory Commission prior to implementation.
All changes and their rationale shall be documented in the Semlannual Radioactive Effluent Release Report.
It shall be the responsibility of the Station Superintendent to ensure that this manual is used in performance of the surveillance requirements and administrative controls of the Technical Specifications.
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C.
1.lQUID EFFLUENT SAMPLING AND ANALYSIS PROGRAM C.1 Radioactive liquid wastes shall be sampled and analyzed in accordance with the program specified in Table C-1 for Millstone Unit No.1, Table C-2 for Millstone Unit No. 2, and Table C-3 for Millstone Unit No. 3. The results of me radioactive analysis shall be input to the methodology of the ODCM to assure that the concentrations at the point of release are maintained within the limits of the Technical Specification 3.8.C.! for Millstone Unit No. I and within the limits of Technical Specifications 3.11.1 for Millstone Unit Nos. 2 and 3.
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i Table C-1 l
MILLSTONE 1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM i
i LOWER LIMIT MINIMUM OF DETECTION (a)
SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)
LIOUID RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS (uCl/ml)
A.
BATCH RELEASEf 1
- 1. Waste Sample Prior to Prior to Principal Gamma 5 x 10-7 Tanks Each Batch Each Batch Emittersb l-131, Mo-99 1 x 10-6
'Ce-141, Ce-144 5 x 10-6
- 2. Floor Drain Sample Tank One Batch Monthly Other Dissolved 1 x 10-5 per month and Entrained Gases l
- 3. Decon Solution Prior to Monthly H-3(l) 1 x 10-3 Tank Each Batch Composite Gross alpha ())
1 x 10-7 Prior to Quarterly Sr-89()I r-90())
5 x 10-8 S
Each Batch Composite Fe-55J 1 x 10-6 B.
CONTINUOUS RELEASE 4
Daily Weekly Principal Gamma i
Grab Composite (c)
Emitters (b) 3 x 10-7 Sample (d) 1-131, Mo-99 1 x 10-6 Reactor Building Ce-141, Ce-144 5 x 10-6 Service Water Monthly Monthly Dissolved and i x 10-5 Grab Sample Entrained Gases Weekly Monthly H 3(?)
1 x 10-5 Grab 5 ample Compositec Gross alpha (d) gx10-7 4
Weekly Quarterly (c)
Sr 89((e)i Sr-90(*)
5 x 10-8 Composito pe.33 e gxgo-6 Grab 5amplo l
C2
TABLE C-1 (Continued)
TABLE NOTATIONS The LLD is the smallest concentration of radioactive material in a sample a.
that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66 sb LLD =
E
- V
- 2.22 x IOb
- Y
- exp (-A4t) where LLD is the lower limit of detection as defined above (as pCl per unit mass or volume) i sb s the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting cfficiency (as counts per transformation)
V is the sample size (in units of mass or volume) 2.22 x 106 is the number of transformations per minutes per microcuric Y is the fractional radiochemical yleid (when applicabic) h is the radioactive decay constant for the particular radio-nuc!!de A t is the clapsed time between midpoint of sample collection and midpoint of counting time It should be recognized that the LLD is defmed as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori(af ter the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieve under routine conditions. Occaslonally background fluctuations, unavoldably small sample sizes, the presence of interfering nuc!! des, or other uncontrollable circumstances may render these LLDs unachievable, b.
The LLD will be 3 x 10-7 uCl/ml. The principal gamma emitters for which this LLD applies are exclusively the following radionuclides: Mn-54, Fe-$9, Co-33, Co 60, Zn 65, Cs-134, and Cs-137.
C-3
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This list does not mean that only these nuclides are to be detected and reported. Other peaks which _ are measurable and identifiable, together
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with the above nuclides,~ shall also be identified and reported. Nuclides hich are below the LLD for the analyses should not be reported as being
.w present at the LLD level. When unusual circumstances result in a priori LLD's higher than required, the reasons shall be documented in the Semiannual Radioactive Effluent Release Report.
c.
- A composite sample is one in which the quantity of liquid sampled is I
proportional to the quantity of liquid waste discharged and in which the method of sampling employed rsults in a specimen which is representative
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of the liquids released.
Prior to analysis, all samples taken for the composite shall be thoroughly-mixed in order for the composite sample to be representative of the effluents release, d.
Daily grab sample for service ' water taken at least five days per week.
e.
These analyses. are required only if weekly gamma analysis indicates a gamma activity greater than 5 x 10-7 uCi/ml.
f.
A batch release is the discharge of liquid wastes.of a discrete volume.
i Prioir to sampling,.each batch shall be isolated and at least two tank / sump volumes shall be recirculated or equivalent mixing provided.
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TABLE C-2 MILLSTONE 2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM i
LOWER LIMIT (a)
MINIMUM TYPE OF OF DETECTION SAMPLING ANALYSIS ACTIVITY (LLD)
LIQUID RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS (uCi/ml)
A.
BATCH RELEASE (b) Prior to Prior to Principal Gamma 5 x 10-7 Each Batch Each Batch Emitters (c)
- 2. Aerated Waste Monitor Tank One Batch Monthly Dissolved and(d) 1 x 10-5 per month Entrained Gases
- 3. Condensate Polishing Composite (f>8)H-3(d) Gross alpha (d) 1 x 10-7 1 x 10-5 Facility - Wagte Prior to Monthly Neut. Sump (e>
Each Batch Prior to Quarterly Sr-89(d), Sr-90(d) 5 x 10-8 Each Batch Composite (f,g)pe_55(d)
[ x 10-6 B.
CONTINUOUS RELEASE l
- 1. Steam Gen (h) erator Blowdown Daily Weekly Principal Gamma 5 x 10-7 Grab Sample (i) Composite (8) Emitters (c) 1-131, Mo-99 1 x 10-6
- 2. Reactor Building Ce-141, Ce-144 5 x 10-6 Closed Cooling i
Service Water Monthly Monthly Dissolved and (j) 1 x 10-5 i
Outlet Grab Sample Entrained Gases Weekly Monthly H-3(j) 1 x 10-5 Grab Sample -
Composite (8) Gross alpha (j) 1 x 10-7
- 3. Turbine Building Sumps (h)
Weekly Quarterly (8) Sr-89( )I-90(j) 5 x 10-8 Sr Composite Fe-55}
1 x 10-6 Grab Sample i
i C-5
TABLE C-2 (Continued)
Table Notations a.
The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability, with 5% probability of falsely concluding that a blank observation represents a "real" signia.
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For a particular measurement system (which may include radiochemical separation):
LLD =
4.66 sh E
- V
- 2.22 x 106
- Y exp (-y t) where LLD is the lower limit of detection as defined above (as uCi per unit mass or volume) sb s the standard deviation of the background counting rate or of the i
counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per transformation)
V is the sample size (in units of mass or volume) 6 s the number of transformation per minute per microcurie 2.22 x 10 i
Y is the fractional radiochemical yield (when applicable) his the radioactive decay constant for the particular radionuclide
.ht is the elapsed time between midpoint of sample collection and midpoint of counting time.
It should be recognized that the LLD is defined as an a, priori (before the f.act) limit representing the capability of a measurement system and not as g posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occassionally background fluctuations, unavoidably. small sample sizes, the presence of interferring nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors will be identified and recorded on the analysis sheet for the particular sample.
b.
A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling, each batch shall be isolated and at least two tank / sump volumes shall be recirculated or equivalent mixing provided.
C-6
TABLE C-2 (Continued)
Table Notations The LLD will be 5 x 10-7 uCi/ml. The principal gamma emitters for which c.
this LLD applies are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Cs-134, and Cs-137.
This list does not mean that only these nuclides are to be detected and reported.. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual circumstances result in a priori LLD's higher than required, the reasons shall be documented in the Semiannual Radioactive Effluent Release Report.
d.
For the Condensate Polishing Facility (CPF)- Waste Neutralization Sump, these analyses are only required if the gamma analysis of the CPF - Waste Neutralization Sump indicates a gamma activity greater than 5 x 10-7 uCi/ml.
For the Condensate Polishing Facility - Waste Neutralization Sump, these e.
analyses are only required when the steam generator gross activity (sampled and analyzed 3 times per week as per Table 4.7-2) exceeds 1 x 10-5 uCi/ml.
f.
A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
g.
Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluents release.
.. h.
For the Steam Generator Blowdown and the Turbine Building Sump, these analyses are only required when the steam generator gross activity (sgip and analyzed 3 times per week as per Table 4.7-2) exceeds 5 x 10-7 1.
Daily grab sample for the service water shall be taken at least 5 days per week.
J.
For the Service Water, these analyses are only required if a weekly gamma analyses indicates a gamma activity greater than 5 x 10-7 uCl/ml.
C-7
TABLE C-3 MILLSTONE 3 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT OF DETECTION (a)
SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD) 1 LIQUID RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS (uCi/ml)
A.
BATCH RELEASE (b)
- 1. Condensate
' Prior to Prior to Each Principle Gamma 5 x 10-7 Polishing Each Batch Batch Emitters (c)
Facility -
' Neutralization Ce-141, Ce-144 5 x 10-6 Sump (e)
- 2. Waste Test One Batch per Dissolved and (d) 1 x 10-5 Tanks month Monthly entrained gases
- 3. Condensate Prior to each Monthly (f, g) H.3(ai 1 x 10-5 Polishing Batch Composite Gross Alpha (d) 1 x 10-7 Facility -
Regenerate Distillate Task Prior to each Quarterly (f d Sr-89(d),
5 x 10-8
- 4. Low Level Batch Composite Sr-90(d),
1 x 10-6 Waste Drain Fe-55(d)
Tank B.
CONTINUOUS RELEASE Daily Weekly Principle Gamma 5 x 10-7 grab sample (i) Composite (8)
Emitters (c)
- 1. Steam Generator 1-131, Mo-99 1 x 10-6 Blowdown (h)
Ce-141, Ce-144 5 x 10-6
- 2. Service Water Monthly Monthly Dissolved and (j) 1 x 10-5 Effluent grab sample entrained gasses
- 3. Turbine Building Weekly Monthly H-3 (j) 1 x 10-5 Sumps (h) grab sample Composite (8)
Gross Alpha (i) 1 x 10-7 Sr-89( )f Sr-90(j) 5 x 10-8 Weekly Ouarter!
grab sample Composife(8)
Fe-55j I x 10-6 C-8
TABLE C-3 (Continued)
Table Notations
- a. '
The LLD is the smallest concentration of radioactive materialin a sample
- that will be detected with 95% probability, with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
.66sb LLD =
E
- V
- 2.22 x 100
- Y
- exp (-)At) where LLD is the lower limit of detection as defined above (as uCi per unit mass of volume) i sb s the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per transformation)
V is the sample size (in units of mass or volume) 6 s the number of transformation per minute per microcurie 2.22 x 10 i
Y is the fractional radiochemical yield (when applicable) his the radioactive decay constant for the particular radionuclide At is the elapsed time between midpoint of sample collected and midpoint of counting time It should be recognized that the LLD is defined as an a_ priori (before the fact) limit representing the capability of a measurement system and not as a posteriori(after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interferring nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing-factors will be identified and recorded on the analysis sheet for the i
l particular sample.
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TABLE C-3 Continued)
Table Notations 4
b.
A batch release is the discharge of liquid wastes of a discrete volume.
p Prior to sampling, each batch shall be isolated and at least two tank / sump
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volumes shall be recirculated or equivalent mixing provided.
The LLD will be 5 x 10-7 uCl/ml. The principal gamma emitters for which c.
this LLD applies are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, and Cs-137.
i This list does not mean that only these nuclides are to be detected and i
reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being t
present at the LLD level. When unusual circumstances result in a priori LLD's higher than required, the reasons shall be documented in the 1
I Semlannual Radioactive Effluent Release Report.
d.
For the Condensate Polishing Facility (CPF) - Waste Neutralization Sump, these analyses are only required if the gamma analyses of the CPF - Waste Neutralization Sump indicates a gamma activity greater than 5 x 10-7 uCi/ml.
For the Condensate Polishing Facility - Waste Neutralization Sump, these e.
i analyses are only required when the steam generator gross activity (gled and analyzed 3 times per week as per Table 4.7-2) exceeds 1 x 10-5 f.
. A composite sample is one in which the quantity of liquid sampled is 4
proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
g.
Prior to analysis, all samples taken for the composite shall be thoroughly i
mixed in order for the composite sample to be representative of the effluents releases.
I
' h.
For the Steam Generator Blowdown and Turbine Building Sump, analyses are only required when the steam generator gross activity (sampled and analyzed 3 times per week as per Table 4.7-2) exceeds 5 x 10-7 uCl/ml.
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Daily grab sample for the service water shall be taken at least 5 days per !
- week.
J.
For the Service Water, these analyses are only required if a weekly gamma analyses indicates a gamma activity greater than 5 x 10-7 uCl/ml.
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C.2 LIQUID RADIOACTIVE WASTE TREATMENT All applicable liquid radioactive waste treatment systems will be operated when the projected dose due to liquid effluents averaged over 31 days exceeds 0.06 mrem to the total body or 0.2 mrem to any organ.
The term all applicable liquid radioactive waste treatment is defined as that equipment applicable to a waste stream responsible for greater than ten percent ( 10%) of the total projected dose. The liquid radioactive waste treatment systems equipment is specified below for each unit.
Millstone Unit No. I 1
Waste concentrator A or B and Waste Demineralizer A or B.
Millstone Unit No. 2 Degasifier, clean liquid primary demineralyzer, boric acid evaporator, clean liquid secondary demineralizer and the aerated waste demineralizer.
Millstone Unit No. 3 Degasifier, ion exchanger, boron evaporator, boron demineralizer, waste evaporator or high waste demineralizer.
With radioactive waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission a report that includes the following information:
1.
Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
If the above treatment systems are not routinely operating, doses due to liquid effluents to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.
C-ll
D.
GASEOUS EFFLUENTS SAMPLING AND ANALYSIS PROGRAM D.1 Radioactive gaseous wastes shall be sampled and analyzed in accordance with the program specified in Table D-1 for Millstone Unit No.1, Table D-2 for Millstone Unit No. 2, and Table D-3 for Millstone Unit No. 3. The results of the radioactive analyses shall be input to the methodology of the ODCM to assure that the offsite dose rates are maintained within the limits of Technical Specifications 3.8.D.1 for Unit No. I and within the Specifications of 3.11.2.1 for Unit Nos. 2 and 3.
D-1
TABLE D-1 1
MILLSTONE 1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit of Detection (LLD)
Gaseous Release Type Sampling Frequency Analysis Frequency Type of Activity Analysis (uCi/cc)a _
Principal Gaseous Gammab i x 104 A.
Steam 3et Air Monthlyc - Gaseous Monthlyc Ejector Discharge Grab Sample Emitters B.
Main Stack Monthly - Gaseous Monthly Principal Gaseous GammaD 1 x 10-4 Grab Sample Emitters H-3 1 x 10-6 Weekly Charcoal I-131 1 x 10-12 f
Continuousd Sample I-133e 1 x 10-10 f
b 1 x 10-11 Continuousd Weekly Particulate Principal Particulate Sample Gamma Emitters Half Lives Greater Than 8 Days Continuousd Monthly Composite Gross Alpha 1 x 10-11 Particulate Sample Quarterly Composite Sr 39, Sr 90 1 x 10-11 Particulate Sample Continuousd Noble Gas Monitor Noble Gases-Gross Activity 1 x 10-6
TABLE D-1 TABLE D-1 (Continued)
TABLE NOTATION a.
The lower limit of detection (LLD) is defined in Table Notation a. of Tables C-1, C-2, or C-3.
b.
For gaseous samples, the LLD will be 1 x 10-4, uCi/cc and for particulate
. samples, the LLD will be 1 x 10-11 uCl/cc. The principal gamma emitters for which these LLDs apply are exclusively the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60,' Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. The list does not mean that only these nuclides are to be detected a'id reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in a, priori LLD's higher than required, the reasons shall be documented in the Semiannual Radioactive Effluent Release Report.
c.
Analyses shall also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following an increase, as indicated by the steam jet air ejector off-gas monitor, of greater than 50%, after factoring out increases due to changes in THERMAL POWER level.
d.
The ratio of the sample flow rate to the sampled stream flow rate shall be known.
e.
Analyses for I-133 will not be performed on each charcoal sample. Instead, at least once per month, the ratio of I-133 to 1-131 will be determined from a charcoal sample changed after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of sampling. This ratio, along with the routine I-131 activity detertmination will be used to determine the release rate of I-133.
f.
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter changing. Special sampling and analysis of iodine and particulate filters shall also be performed whenever subsequent reacter coolant I-131 samples show an increase of greater than a factor of 5.
These filters shall be changed following such a five-fold increase in coolant activity and every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter until the reactor coolant I-131 levels are less than a factor of 5 greater than the original coolant levels or until seven days have passed, whichever is shorter.
Sample analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. The LLD's may be increased by a factor of 10 for these samples.
D-3
TABLE D-2 MILLSTONE 2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM TYPE OF DETECTION (A)
SAMPLING ANALYSIS OF ACTIVITY (LLD)
G ASEOUS R ELEASE TYPE FR EQUENCY FREQUENCY ANALYSIS (UCl/CC)
A BATCH RELEASE
- 1. Waste Gas Prior to Each Tank Principal Gamma 1 x 10-4 Storage Tank (h)
Each Tank Discharge Emitters (b)
- 2. Containment H-3 1 x 10-6 Purge B.
CONTINUOUS RELEASE Grab Sample (c) Monthly (c)
EmiJiersb Monthly Principal Gamma 1 x 10-4 Gases H-3W l x 10-6 Continuous (d)
Weekly (f) 1-131 1 x 10-12 Charcoal Sample 1-133(e) 1 x 10-10 Vent Continuous (d)
Weekly (f)
Principal Gamma 1 x 10-11 Particulate Emittersb Sample (I-131, others with Half livesM days)
Continuous (d)
Monthly Gross Alpha 1 x 10-11 Composite Particulate Samples Continuous (d) Quarterly Sr-89, Sr-90 1 x 10-11 Composite Particula te Samples Continuous (d) Noble Gas Noble Gas 1 x 10-6 Monitor
-Gross Activity D-4
TABLE D-2 (Continued)
TABLE NOTATION a.
The lower limit of detection (LLD) is defined in Table Notation of Tables C-1, C-2, or C-3.
b.
For gaseous samples, the LLD will be 1 x 10-4 uC1/cc and for particulate samples, the LLD will be 1 x 10-11 uCl/cc. De principal gamma emitters for which these LLD's apply are exclusively the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. The list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and ident'flable, together with the above nuclides, shall also be identified and reported.
Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in a_ priori LLD's higher than required, the reasons shall be documented in the Semiannual Radioactive Ef fluent Release Report.
c.
Analyses shall also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following an unexplained increase, as indicated by the Unit 2 stack noble gas monitor, of greater than 50%, after factoring out increases due to changes in THERMAL POWER levels, containment purges, or other explainable increases.
d.
The ratio of the sample flow rate to the sampled stream flow rate shall be known.
e.
Analyses for I-133 will not be performed on each charcoal sample. Instead, at least once per month, the ratio of I-133 to 1-131 will be determined from a charcoal sample changed after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of sampling. This ratio, along with the routine 1-131 activity detertmination will be used to determine the release rate of I-133.
f.
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter changing. Special sampling and analysis of lodine and particulate filters shall also be performed whenever reactor coolant I-131 samples, which are taken 2-6 hours following a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour show an increase of greater than a factor of 5. Rese filters shall be changed following such a five-fold increase in coolant activity and every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereaf ter until the reactor coolant 1-131 levels are less than a factor of 5 greater than the originalcoolant levels or until seven days have passed, whichever is shorter. Sample analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. The LLD's may be increased by a factor of 10 for these samples.
g.
Grab samp!cs for Tritum shall be taken weekly whenever the refueling cavity is flooded and there is fuel in the cavity. The grab sample shall be taken from the stack (Unit I and 2) where the containment ventilation is D-5
being discharged at the time of sampling, b.
Waste Gas Storage Tanks are normally released on a batch basis. However, for the purpose of tank maintenance, inspection, or reduction of oxygen concentration, a waste gas tank may be continuously purged with nitrogen provided the following canditions are mett (1)
The previous batch of radioactive waste gas has been discharged to a final tank pressur 3 of less than 5 PSIG.
(2)
No radioactive waste gases have been added to the tank since the previous discharge.
'(3)
Valve lineups are verified to ensure that no radioactive waste gases will be added to the tank.
(4)
After pressurizing the tank with nitrogen, a sample of the gaa in the tank will be taken and analyzed for any residual gamma emitters and tritium prior to initiation of the nitrogen purge.
The measured activity will be used to calculate the amount of activity released during the purge.
l t
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D-6
TABLE D-3 MILLSTONE 3 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM OF DETECTION (A)
SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)
GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS (UCI/ML)
A.
BATCH RELEASES Principal 1 x 10-4 Containmen t Prior to Each Purge Emitters (gamma Purge Each Purge ui H-3 1 x 10-6 B.
CONTINUOUS RELEASES 1.
Unit 3 Monthly (c)
Monthly (c)
Principal gamma 1 x 10-4 Ventillation Grab samples EmlJters(DJ Vent Gases H-318) 1 x 10-6 2.
Engineered Continuous (d)
Weekly I-131 1 x 10-12 Safeguards Charcop1 1-133(e) 1 x 10-10 Building Sampleui Continuous (d)
Weekly Principal Gamma (b) 1 x 10 -11 Particulgte Emitters (I-131, Sampletfi others with half lives > 3 days)
Continuous (d)
Monthly Gross Alpha 1 x 10-11 Composite Particulate Samples Continuous (d)
Quarterly Sr 89, Sr 90 1 x 10-11 Composite Particulate Sampics Continuous (d) Noble Gas Noble Gas 1 x 10-6 Monitor Gross radioactivity D-7
TABLE D-3 (Continued)
TABLE NOTATION a.
The lower limit of detection (LLD) is defined in Table Notation of Tables C-1, C-2, or C-3.
b.
For gaseous samples, the LLD will be 1 x 10-4, uCi/cc and for particulate samples, the LLD will be 1 x 10-11 uCi/cc. The principal gamma ernitters for which these LLD's apply are exclusively the following radionuclides:
Kr-87, Kr-88, Xe-133, Xc-133m, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Cc-144 for particulate emissions. The list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in a, priori LLD's higher than required, the reasons shall be documented in the Semiannual Radioactive Effluents Release Report.
c.
Analyses shall also be done within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following an unexplained increase, as indicated by the Unit 3 vent noble gas monitor, of greater than 50%, af ter factoring out increases due to changes in THERMAL POWER levels, containment purges, or other explainable increases, d.
The ratio of the sample flow rate to the sampled stream fbw rate shallbe known.
e.
Analyses for 1-133 will not be performed on each charcoal sample. Instead, at least once per month, the ratio of I-133 to 1 131 will be determined from a charcoal sample changed after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of sampling. This ratio, along with the routine 1-131 activity detertmination will be used to determine the release rate of I-133.
f.
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter changing. Special sampling and analysis of iodine and particulate filters shall also be performed whenever reactor coolant I-131 samples, which are taken 2-6 hours following a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour, show an increase of greater than a factor of 5. These filters shall be changed following such a five-fold increase in coolant activity and every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereaf ter until the reactor coolant I-131 levels are less than a factor of 5 greater than the original coolant levels or until seven days have passed, whichever is shorter. Sample analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. The LLD's may be increased by a factor of 10 for these samples.
g.
Grab samples for tritum shall be taken weekly whenever the refueling cavity is flooded and there is fuelin the cavity.
l D-8 l
L
D.2 GASEOUS RADIOACTIVE WASTE TREATMENT All applicable gaseous radioactive waste treatment systems shall be operated when the projected dose due to gaseous effluents averaged over 31 days exceeds 0.2 mrad for gamma radiation,0.4 mrad for beta radiation or 0.3 mrem to any organ due to gaseous particulate eifluents.
The term all applicable gaseous radioactive treatment is defined as that equipment applicable to a waste stream responsible for greater than ten percent ( 10%) of the total project dose. The gaseous radioactive waste treatment systems equipment is specified below for each Unit.
Millstone Unit No.1 Offgas System - Recombiner Train A or B Charcoal Bed Train A or B and tl.e HEPA filter.
Radwaste Ventilation Exhaust Treatment System Radwaste ventilation HEPA filters.
Millstone Unit No. 2 Gaseous Radwaste Treatment System - at least two (2) gas decay tanks, the waste gas filter and one waste gas compressor.
Ventilation Exhaust Treatment System - Auxillary building ventilation HEPA filter (L26), containment purge llEPA filter (L25).
Millstone Unit No. 3 Gaseous Radwaste Treatment System - charcoal bed adsorbers, one HEPA filter, and one process gas compressor.
Building Ventilation - Auxiliary building ventilation filter, fuel building ventilation filter, SLCRS filter.
With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission a report that includes the following information:
1.
Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the Inoperability, 2.
Action (s) taken to restore the Inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
If the above treatment systems are not routinely operating, doses due to D-9
gaseous effluents to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.
D-10
E.
RADIOLOGICAL ENVIRONMENTAL MONITORING E.1 SAMPLING AND ANALYSIS The radiological sampling and analyses provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from Plant operation.
This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.
Program changes may be made based on operational experience.
The sampling and analyses shall be conducted as specified in Table E-1 for the locations shown in Appendix G of the ODCM.
(Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, reasonal unavailability, malfunction of automatic sampling equipment or other legitimate reasons).
If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period.
All deviations from the sampilng schedule shall be documented in the Annual Radiological Environme ital Operating Report pursuant to Section F.1. It is recognized that, at.mes, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.
In these instances suitable alternative media and locations may be chosen for the particular pathway in question and substitutions made within 30 days in the radiological environmental monitoring program.
In these instances identify the cause of the unavailability of samp!cs for that pathway and identify the new location (s) for obtaining replacement samples in the next Semlannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).
If the level of radioactivity in an environmental samp!!ng medium at one or more of the locations specified in Table E-1 exceeds the report levels of Table E-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a Special Report which inicudes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table E-2 to be exceeded. When more than one of the radionuclides in Table E-2 are detected in the sampling medium, this report shall be submitted if t concentration (1) + concentration (2)... g, 1.0 reporting level (1) reporting level (2)
If milk samples are unavailable from any one or more of the milk sampic locations required by Table E-1, a grass sample shall be substituted until a suitabic milk location is evaluated as a replacement or until milk is available from the original location.
Such an occurrence will be documented in the Annual Radiological Environmental Operating Report.
E-1
f I
When radionuclides other than those in Table E-2 are detected and are the result of plant effluents, this Special Report shall be submitted if the potential annual dose to an Individual is equal or greater than the appropriate calendar year limit of the Technical Specifications 3.8.C.2.1, 3.8.D.2.1 or 3.8.D.3.1 for Millstone Unit No.1 or 3.11.1.2, 3.11.2.2 or l
3.11.2.3 for Millstone Unit Nos. 2 and 3. This report is not required if the measured level of radioactivity was not the result of plant effluents, however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
(
The detection capabilities required by Table E-3 are state-of-the-art for routine environmental measurements in Industrial laboratories. It should be recognized that the LLD is defined as an a " priori" (before the fact) limit representing the capability of a measurement system and not as "a l
posteriori" (af ter the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved i
under routine conditions.
Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.
i
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E-2 i
l' I
E.2 LAND USE CENSUS The land use census ensures that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census.
This census satisfies the requirements of Section IV.B.3 of Appendix ! to 10 CFR Part 50. The land use census shall be maintained and shall identify the location of the milk animals in each of the 16 meteorological sectors within a distance of five miles.*
The validity of the land use census shall be verlfled at least once per 12 months by either a door-to-door survey, aerial survey, consulting local agriculture authorities, or any combination of these methods.*
With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the doses currently being calculated in the ODCM, make the appropriate changes in the sample locations of Table E-2.
With a land use census identifying a location (s) which has a higher D/Q than a current indicator location the following shall apply (1)
If the D/Q is at least 20% greater than the previously highest D/Q, replace one of the present sample locstions with the new one within 30 days if milk is available.
l (2)
If the D/Q is not 20% greater than the previously highest D/Q, consider both direction, distance, availability of milk, and D/Q in deciding whether to replace one of the existing sample locations. If applicable, replacement should be within 30 days. If no replacement is made, suf ficient justification should be given in the annual report.
i Sample location changes shall be noted in the Annual Radiological Environmental Operating Report.
- Broad leaf vegetation (a composite of at least 3 different types of vegetation) is sampled at the site boundary In each of 2 different direction sectors with relatively high D/Q's in lieu of a garden census.
E-3 l
t
E.3 INTERLABORATORY COMPARISON PROGRAM The Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.
With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
l I
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l E-4 i
TABLE E-l MILLSTONE RADIOLOGIC AL ENVIRONMENTAL MONITORING PROGRAM Sampling and Exposure Pathway Number of Collection and/or Sample Locations Frequency Type and Frequency of Analysis la.
Gamma Doso -
17 Monthly Gamma Dose - Monthly Environmetal TLD 1 b.
Gamma Dose -
22 Quarterly (a)
N/A(a)
Accident TLD
~
2.
Airborne 8
Continuous Gross Beta - Weekly, Particulate sampler -
Gamma Spectrum - Monthly on weekly filter composite (by location), and change on individual sample if gross beta is greater than 10 times the mean of the weekly control station's gross beta results.
3.
Airborne 8
Continuous 1-131 - Weekly lodine sampler -
weekly canister change 4.
Vegetation 5
One sample Gamma isotopic on each near middle sample and one near end of growing season 3.
Milk 6
Monthiy for Gamma isotopic,1-131, Sr-89 all animals and Sr-90 on each samp'e except semi-monthly for goats when on pasture 6.
Sea Water 2
Quarterly -
Quarterly - Fractional Beta, Composite of Gamma Isotopic and Tritium 6 Weekly Grab on each composite samples 7.
Bottom 7
Semlannual Gamma Isotopic on Each 5edimen t -
Sample E-3
4 i
TABLE E-1 (Continued)
MILLSTONE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling and Exposure Pathway Number of Collection and/or Sample Locations
_Frecuency Type and Frequency of Analysis 8.
Fin Fish-Flounder 2
Quarterly Gamma Isotopic on Each and one other type Sample of edible fin fish 9.
Mussles 2
Quarterly Gamma Isotopic on Each Sample 10.
Oysters 4
Quarterly Gamma Isotopic on Each Sample 11.
Clams 2
Quarterly Gamma Isotopic on Each Sample 12.
Lobster 3
Quarterly Gamma Isotopic on Each Sample (a)
Accident monitoring TLDs to be dedosed at least quarterly.
E-6 i
TABLE E-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS Airborne Particulate or Fish Milk Vegetables Analysis Water (pCl/l)
Gases (pCi/nd_)
(pCl/KL wet) (pCl/l)
(pCl/KL wet) 4I H-3 2 x 10
")
Mn-54 1 x 103 3 x 104 Fe-59 4 x 102 1 x 104 co-53 1 x 103 3 x 104 Co-60 3 x 102 g x 104 Zn-65 3 x 102 2 x 104 I-131 (b) 0.9 3
1 x 102 Cs-134 30 10 1 x 103 60 1 x 103 Cs-137 30 20 2 x 103 70 2 x 103 Ba-140 2 x 102 3 x 102 La-140 2 x 102 3 x 102 Zr-95 4 x 102 Nb-95 4 x 102 (a)
For drinking water samples. This is 40 CFR Part 141 value.
(b)
Level for I-131 not included since no radioactivity discharged to any drinking water pathwaysl other reporting levels are included for trending of long lived isotopes only.
E-7
l 1
l Table E-3 l
MAXIMUM VALUES FOR LOWER LIMITS OF DETECTION (LLD)a l
l l
AIRBORNE PARTICULATE i
WATER OR GAS FISH, SHELLFISH MILK FOOD PRODUCTS SEDIMENT 3
ANALYSIS (pCi/1)
(pCi/m._)
(pCi/Kg, WET)
(pCi/1)
(pCi/Kg, WET)
(pCi/Kg, DRY)
Gross beta 1 x 10-2 l
Factional beta 4
H-3 2000 Mn-54 30C 130 Fe-59 60c 260 Co-58, 60 39c g30 Zn-65 60c 260 Zr-95 60c Nb-95 30C I-131 d
7 x go-2 1
60b Cs-134 33c 5 x 10-2 130 15 60 150 Cs-137 40C 6 x 10-2 150 18 80 180 Be-140 120c,e 70 La-140 30C, e 25
TABLE NOTATION a.
The LLD is the smallest concentration of radioactive materialin a sample that will be detected with 95% probability with a 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
LLD =
4.66 sb E
- V
- 2.22 x 10b
- Y
- cxp (-Mt) where LLD is the lower limit of detection as defined above (as pCl per unit mass or volume) sb s the standard deviation of the background counting rate or of i
the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per transformation)
V is the sample size (in units of mass or volume) 2.22 is the number of transformation per minute per picocurle Y is the fractional radiochemical yleid (when applicable) his the radioactive decay constant for the particular radionuclide At is the elapsed time between sample collection (or end of the sample collection period) and time of counting it should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori(af ter the fact) limit for a particulate measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine cor.ditions. Occasionally background fluctuations, unavoldably small s2mple sizes, the presence of interfering nuc!! des, or other uncontrollable circumstances may render these a priori LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.
b.
LLD for leafy vegetables.
c.
To be reduced by a facter of two if the fractional beta for the sample exceeds 15 pCl/1.
E-9
r d.
Level for I-131 not included since no radioactivity discharged to any drinking water pathway.
e.
From end of sample period.
E-10
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' F.
REPORT CONTENT i
- F.1-ANNUAL RADIOLOGICAL ENVIRONMENTAUOPERATING REPORT y
- The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and statistical evaluation of the results of the
,,t radiological environmental sur"veillance activities for the report period, including a comparison with previous environmental surveillance reports s
and an assessment of the observed impacts of the plant operation on the
/
envir'onment. The reports shdif salso include the results of the land use
-.,I censu's required by Section E.2 'ois this manual. If harmful effects are W N'.G ,
detec_ted by _the monitoring, the r'eport shall provide an analysis of the
+
/p' probl.em and a planned, course of action.th alleviate the problem.
g The report shall include a summary table of all radiological environmental i
samples which.shall include the,following information for each pathway li sampled and each type of analysis:
/
(1) gotal number of analyses perfcrmed at indicator locations.
(2)
Total number of analyse,s performed at control locations.
a.'; 9
' hyy Lower limit of detection (LLD)..
3.-
' %g *.
(4)
Mean and range of all thdicator locations together.
t (5), Mean and range of all controllocations together. -
s s-s j, (6). Name, distance an[ direction fron$ discharge, mean and range for the (location with the. highest annual mean (indicator or control). -
4
'\\
t,,
t
-(7)
Number of noncoutisd reported' measurements as defined in these
\\_
specifications. ) Xj 4
st; In the event that some results are not available for inclusion with the report,1the report shall be; submitted noting and explaining the reasons for w,,
the nassing results. The missing data shall be submitted as soon as possible m'a supplementary report.
-g 9
TTi;e report shall also include a map of sampling locations keyed to a table C
. giving distances' and directions from the. discharge; the report shall also l
' include a summary of the Interlaboratody Comparison Data required by
,l [.
p Section E.3 of this. Manual.
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F.2 SEMIANNU AL R ADIO ACTIVE EFFLUENT R ELEASE REPORT De Semiannual Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents released from the unit es outlined in Regulatory Guide 1.21, Revision 1,
' June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
In addition, a supplemental report to be submitted 90 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the Drevious year. This annual summary may be either in 4
the form of an hour-by-hour listing on magnetic tape or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.** 31s same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the site during the previous calendar year.
De meteorological conditions concurrent with the time of release of radioactive material in gaseous effluents shall be used for determining the gaseous pathway doses. Dose calculations'shall be performed in accordance with the Offsite Dose Calculation Manual.
In addition, the report to be submitted 90 days after January 1 of each year shall include an assessment of radiation doses to the likely most exposed
~ REAL MEMBER OF THE' PUBLIC from the site for the previous 12 consecutive months to show conformance with 40 CFR 190. Doses shall be calculated in accordance with the Ofisite Dose Calculation Manual.
The semiannual effluent report.shall also include a summary of each type 4
s of solid radioactive waste shipped offsite for burial or final disposalduring the report period. This summary shall include the following information for each type of waste:
^ <
a.
Type of waste (e.g., spent resin, compacted dry waste, irradiated components, e tc.).
b.
Solidification agent (e.g., cement).
c.
Total curies.
3 d.
Total volume and typical container volumes.
Principal radionuclides (those greater than 10% of total activity).
e.
f.
Types of containers used (e.g., LSA, Type A, etc.).
De semiannual effluent report shall include the following information for all unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents:
a.
A description of the event and equipment involved.
F-2
.~
.... ~
b.
Cause(s) for the unplanned release.
c.
Actions taken to prevent recurrence.
d.
Consequences of the unplanned release.
Any changes to the RADIOLOGICAL EFFLUENT and OFFSITE DOSE CALCULATION MANUAL and Process Control Program shallbe submitted in the Semiannual Radioactive Effluent Release Report.
In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data onsite in a file that shall be provided to the NRC upon request.
F-3
.__.__m t
1 i
SECTION 11 l'
OFFSITE E OSE CALCULATION MANUAL FOR THE MILLSTONE NUCLEAR POWER STATION UNITS 1,2 and 3 DOCKETS: No. 50-245 No. 50-336 No. 50-423 i
a i
I 4
4 June,1985 i
OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS Section Page No.
Rev.No.
A.
Introduction A-1 1
B.
Responsibilities B-1 1
C.
Liquid Dose Calculations C-1 1
C1.
Quarterly - Total Body Dose C-1 1
a.
Method 1 - Any Unit C-1 1
b.
Method 2 - Any Unit C-2 1
C2.
Quarterly - Maximum Organ Dose C-3 1
a.
Method 1 - Any Unit C-3 1
b.
Method 2 - Any Unit C-4 1
C3.
Annual - Total Body Dose C-5 1
C4.
Annual-Maximum Organ Dose C-6 1
C5.
Monthly Dose Projections a.
Unit 1 C-7 1
b.
Unit 2 and Unit 3 C-8 1
C6.
Quarterly Dose Calculations for Semi-Annual Radioactive Effluent Report C-9 1
D.
Gaseous Dose Calculations DI.
10CFR20 Limits (" Instantaneous")
D-1 1
a.
Noble Gases - All Units D-1 1
b.
Iodines, Particulates and Other - All Units D-2 1
D2.
Appendix I - Noble Gas Limits a.
Quarterly Air Dose - Method 1 D-3 1
All Units b.
Quarterly Air Dose - Method 2 D-4 1
All Units c.
Arnual Air Dose - All Units D-5 1
I
OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Cont'd)
- Section Page No.
Rev. No.
D3.
Appendix 1 - lodine and Particulate Doses D-6 1
a.
Quarterly Doses - Unit i D-6 1
b.
Quarterly Doses - Unit 2 and Unit 3 D-7 1
D-8 c.
Annual Doses - All Units D-9 1
D4.
- Gaseous Effluent Monthly Dose D-10 1
Projections a.
Unit 1 D-10 1
D-Il I
b.
Unit 2 D-12 1
c.
Unit 3 D-13 1
D5.
Quarterly Dose Calculations for Semi-Annual Report D-14 1
D6.
Compliance with 40CFR190 D-15 1
E.
Liquid Monitor Setpoint Calculations E-1 1
El.
Unit 1 Liquid Radwaste Effluent Line E-1 1
E2.
Unit 1 Service Water Effluent E-2 i
Line E3.
Unit 2 Clean Liquid Radwaste Effluent Line E-3 1
9 E4.
Unit 2 Aerated Liquid Radwaste Effluent Line and CPF - Waste Neut. Sump Effluent Line E-4 1
E5.
Unit 2 Steam Generator Blowdown E-5 1
E6.
Unit 2 Condenser Air Ejector E-6 1
E7.
Unit 2 Reactor Building Closed Cooling Water E-7 1
11
OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Cont'd)
Section Page No.
Rev.No.
E8.
Unit 3 Liquid Waste Effluent Line E-8 1
E9.
Unit 3 Regenerant Evaporator Effluent Line E-9 1
E10. Unit 3 Waste Neutralization Sump Effluent Line E-10 1
Ell. Unit 3 Steam Generator Blowdown E-Il I
E12. Unit 3 Turbine Building Floor Drains Effluent Line E-12 1
F.
Gaseous - Monitor Setpoint Calculations F-1 1
F1.
Unit i Hydrogen Monitor F-1 1
F2.
Unit 1 Steam Jet Air Ejector Off Gas Monitor F-2 1
F3.
Unit 1 Main Stack Noble Gas Monitor F-3 1
F4.
Unit 1 Main Stack Sampler Flow Rate Monitor F-4 1
F5.
Unit 2 Vent Noble Gas Monitor F-5 1
F6.
Unit 2 Waste Gas Decay Tank Monitor F-6 1
F7.
Unit 3 Vent Noble Gas Monitor F-7 1
F8.
Unit 3 Engineering Safeguards Building Monitor F-8 1
G.
Effluent Flow Diagrams G-1 1
til
LIST OF FIGURES Figure Name Figure Number Rev.No.
G-1 MP1 Liquid Radwaste Flow Diagram 1
G-2 MP2 Liquid Radwaste Flow Diagram 1
G-3 MP3 Liquid Radwaste Flow Diagram 1
G-4 MP1 Gaseous Radwaste Flow Diagram 1
G-5 MP2 Gaseous Radwaste Flow Diagram i
G-6 MP3 Gaseous Radwaste Flow Diagram 1
e IV
APPENDICES Rev.No.
Appx. A - Derivation of Factors for Section C.1 - Liquid Doses 1
Appx B - Derivation of Factors for Section C.2 - Liquid Doses 1
Appx. C - Liquid Dose Calculations - LADTAP 1
Appx. D - Derivation of Factors for Section D -
Gaseous Doses 1
Appx. E - Gaseous Dose Calculations - GASPAR 1
Appx. F - Gaseouos Dose Calculations - AIREM i
' Appx, G - Environmental Monitoring Program Sampling 1
. Locations Appx. H - Methods for Calculating Releases from Unit 3 1
"Unmonitored" Releases V
o
Rev.1 A.
INTRODUCTION The purpose of this manual is to provide the parameters and methodology to be used in calculating offsite doses and effluent monitor setpoints at the Millstone Nuclear Power Station.
Included are methods for determining maximum individual whole body and organ doses due to liquid and gaseous effluents to assure compliance with the dose limitations in the Technical Specifications.
Also included are methuds for performing dose projections to assure compliance with the liquid and gaseous treatment system operability sections of the Radiological Effluent Monitoring Manual. The manual also includes the methods used for determining quarterly individual and population doses for inclusion in the Semlannual Radioactive Effluents Release Report.
Another section of this discusses the methodology to be used in determining effluent monitor alarm / trip setpoints to be used to ensure compliance with the imtantaneous release rate limits in the Technical Specifications.
The basis for some of the factors in this manuai are included as appendices to this manual.
This manual does not include the surveillance procedures and forms required to document compliance with the surveillance requirements in the Technical Specifications.
All that is included here is the methodology to be used in performance of the surveillance requirements.
Most of the calculations in this manual have two or three methods given for the calculation of the same parameter. These methods are arranged in order of simplicity and conservatism, Method I being the easiest and most conservative.
As long as releases remain low, one should be able to use Method I as a simple estimate of the dose. If release calculations approach the limit however, more detailed yet less conservative calculations may be used.
At any time a more detailed calculation may be used in lieu of a simple calculation.
This manual is written common to all three units since some release pathways are shared and there are also site release limits invovled. These facts make it impossible to completely separate the three units.
A-1
,Rev.1 B.
RESPONSIBILITIES All changes to this manual shall be reviewed by the Site Operations Review Committee prior to implementation.
All changes and their rationale shall be documented in the Semlannual Radioactive Etfluent Release Report.
It shall be the responsibility of the Station Superintendent to ensure that this manual is used in performance of the surveillance requirements specified in the Technical Specifications.
B-1
Rev.1 C.
LIQUID DOSE CALCULATIONS C.1 Quarterly - Total Body Dose C.I.a Method 1 - Any Unit Step 1 - Determine CF = total gross curies of fission and activation p oducts, excluding tritium and dissolved noble gases, released during the calendar quarter.
Step 2 - Determine CT = total curies of tritium.eleased during the calendar quarter.
Step 3 - Determine DQT = quarterly dose to the total body in mrem.
DQT = 1.9 x 10-2 + Cp + 5.6 x 10-7
- CT (See Note 1)
QT s greater than 0.5 mrem, go to Method 2.
Step 4 - If D i
(Note 1)-See Appendix A for derivation of these factors.
C-1
Rev.1 C. l.b Method 2 - Any Unit If the calculated dose using Method I is greater than 0.5 mrem, use the NRC computer code LADTAP to calculate the liquid doses. The use of this code and the input parameters are givers in Radiological Assessment Branch Procedure RAB 4-3, Liquid Dose Calculations -
LADTAP.
t C-2 i
Rev.1 C.2 Quarterly - Maximum Organ Dose C.2.a Method 1 - Any Unit Step 1 - Determine Cp = total gross curies of fission and activation products, excluding tritium and dissolved noble gases, released during the calendar quarter - same as Step C.l.a.
Step 2 - Determine Dgo = quarterly dose to the maximum organ in mrem.
Dqo = 0.2 Cp (See Appendix B for derivation of factor)
If D o is greater than 2 mrem, go to Method 2.
Step 3 -
Q C-3
i Rev.1 l-C.2.b Method 2 - Any Unit if the calculated dose using Method 1 is greater than 2 mrem, use the NRC computer code LADTAP to calculate the liquid doses. The use of this code, and the input parameters are given in Radiological Assessment Branch Procedure RAB 4-3, Liquid Dose Calculations -
LADTAP.
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1 C-4
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C.3 Annual-Total Body Dose - Any Unit i
Determine DYT = dose to the total body for the calendar year as follows:
I DyT = ZDOT where the sum is over the first quarter through the present quar ter to tal body doses.
i The following should be used as DQT8 (1)
If the detailed quarterly dose calculations required per Section C.6 for the semiannualeffluent report are complete for any calendar quarter, use that i
result.
(21 Ii the detalled calculations are not complete for a particular quarter, use l
the results as determined in Section C.I.
QT etermined as in Section C.l l
(3)
If D YT s greater than 3 mrem and any D i
d was not calculated using Method 2 of that section, recalculate DQ T using Method 2 If this could reduce DyT to less than 3 mrem.
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C-5 i
lley.1 C.4 Anntal - Maximum Organ Dose - Any Unit Determine Dyo = dose to the maximum organ for the calendar year as follows:
Dyo= 1DQO where the sum is over the first quarter through the present quarter maximum organ doses.
The following guidelines should be used:
(1)
If the detailed quarterly dose calculations required per Section C.6 for the semiannual ef fluent report are complete for any calendar quarter, use that result.
(2)
If the detailed calculations are not complete for a particular quarter, use the results as determined in Section C.2.
(3)
If different organs are the maximum for different quarters, they may be summed together and Dyo can be recorded as a less than value as long as the value is less than 10 mrem.
(4)
If Dyo is greater than 10 mrem and any value used in its determination was calculated as in Section C.2 but not with Method 2, recalculate that value using Method 2 If this could redence Dyo to less than 10 mrem.
i C-6 i
Rev.1 C.5 Monthly Dose Projections C.5.a Total Body & Maximum Organ - Unit i Step 1 -
Determine D'MT = total body dose from the last typical
- previously completed month as calculated per the methods in Section C.l.
Step 2 -
Determine D'MO = maximum organ dose from the last typical
- previously completed month as calculated per the methods in Section C. I.
Step 3 -
Estimate R1 = ratio of the total estimated volume of liquid batches to be released in the present month to the volume released in the past month.
Step 4 -
Estimate R2 = ratio of estimated primary coolant activity for the present month to that for the past month.
Step 5 -
Determine F = factor to be app!!cd to estimate ratio of final curie released if there are expected differences in treatment of liquid waste for the present month as opposed to the past month (e.g.,
bypass of filters or demineralizers). NUREG-0016 or past experience should be used to determine the effect of each form of treatment which will vary. F = 1 if there are no expected differences.
Step 6 -
Determine D$tT = estimated monthly total body dose as follows:
DhT = D'MT
- R1*R2*F Step 7 -
Determine DSiO = estimated monthly maximum organ dose as follows:
D$go = ffMO
- R1*R2*F The last typical month should be one without significant operational dif ferences from the projected month.
For example, if the plant was down for refueling the entire month of February and startup is scheduled for March 3, use the last month of operation as the base month to estimate March's dose.
Or, if there were no releases during September, do not use September as the base month for October if it is estimated that there will be releases in l
October.
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C-7
Rev.1 C.5.b Total llody & Maximum Organ - Unit 2 and Unit 3 Step 1 -
Determine D'MT = total body dose from the last typical
- previously completed month as calculated per the method in Section C.I.
Step 2 -
Determine D'MO = maximum organ dose from the last typical
- previously completed month as calculated per the methods in Section C.2.
- - See footnote in Section C.5.a.
Step 3 -
Estimate Rg a ratio of the total estimated volume of liquid batches to be released in the present month to the volume released in the past month.
Step 4 -
Estimate R2 = ratio of the total estimated volume of steam generator blowdown to be released in present month to the volume released in the past month.
Step 5 -
Estimate F1a fraction of curies released last month coming from steam genera tor blowdown.
i.e. F =
curies from blowdown 1
curies from blowdown + curies from batch tanks Step 6 -
Estimate R3 = ratio of estimated secondary coolant activity for the present month to that for the past month.
Step 7 -
Estimate R4 m ratio of estimated primary coolant activity for the present month to that for the past month.
Step 8 -
Determine F2 = factor to be applied to estimate ratio of final curie released if there are expected dif ferences in treatment of liquid waste for the present month as opposed to the past month (e.g.,
bypass of filters or demineralizers). NUREG-0017 or past experience should be used to determine the effect of each form of treatment which will vary. F = 1 if there are no expected dif ferences.
2 Step 9 -
Determine DhT = estimated monthly total body dose as follows:
Dhy = D'MT [(1 - F ) R R F + Pg R2R3 1
t 4 2
Step 10 -
Determine Dho a estimated monthly maximum organ dose as follows:
Dho a D'MO ((1 - F ) R R F+FRR3 1
t 4
2 1
2 C-8
7 Rev.I C.6 Quarterly Dose Calculations for Semlannual Radioactive Effluent Recort Detailed quarterly dose calculations required for the Semlannual Radioactive Effluent Report shall be done using the NRC computer code LADTAP. The use of this code, and the input prameters are given in Radiological Assessment Branch Procedure RAB 4-3, L quid Dose Calculations - LADTAP.
4 C-9
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l Rev.I D. G ASEctJS DOSE C ALClJLATIONS l
D.!
IOCFR20 Limits ("Inatanteneous")
l D.L.a Instantaneous Noble Gas Release Rate Limits - All IJnits lhe instantaneous noble gas release rate limit from the site shall be:
.b 00 21 00 l
where l
Qg = Noble gas release rate from MP1 stack (uCl/sec)
Q2 = Noble gas release rate from MP2 vent (uCl/sec)
Q3 - Noble gas release rate from MP3 vent (uCl/sec)
See Appendix D for deviation of this limit.
l As long n the above is less than or equal to I, the doses will be less than or equal to 500 mrem to the totalbody and less than 3000 mrem to the skin.
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Rev.0 D.I.o Release Rate 1.imit 131. Particulates With Half Lives Greater than 8 Dws, and Itadionuclides Other Than Noble Gases With Half L ves Greater Than 8 Days - All Units (1)
The release rate limit of I-131 and tritium from the site shall be:
l Qil Q12 QT1
+
QT2
+
QT3 Q13
+
+
+
4 I where, l
6.26 0.49 0.49 9 tx105 4,oxto4 4,oxto4 Qig = Release of I-131 from MPI Stack -(uCl/sec)
Ql2 " Release rate of I-131 from MP2 Vent -(uCl/sec)*
Qg3 = Release rate of I-131 from MP3 Vent -(uCl/sec)
QTg = Release rate of tritium from MPI Stack -(uCl/sec)
QT2 = Release rate of trltlum from MP2 Vent -(uCl/sec)*
Qr3 = Release rate of tritium frorn MP3 Vent -(uCl/sec)
(2)
The release rate limit for particulates with half lives greater than 8 days and tritium from the site shall be Q1
+
Q2 Q3
+
QT1 QT2 QT3
+
+
+
de I where, 35 4.2 2.1 9.t x105 4,oxio4 4,0xto4 Q1 = Release rate of total particulates with half lives greater than 8 days from the MP1 Stack (uC1/sec).
Q2 = Release rate of total particulates with half lives greater than 3 days from the MP2 Vent (uCl/sec).
Q3 = Release rate of total particulates with half lives greater than 8 days from the MP3 Vent (uCl/sec).
QT1 = Release rate of tritium from MP1 Stack -(uCl/sec)
QT2 = Release rate of tritium from MP2 Vent -(uCl/sec)*
QT3 = Release rate of trltlum from MP3 Vent -(uCl/sec)
With releases within the above limits, the does rate to the maximum organ l
will be less than 1500 mrem / year.
l 1
- Includes releases via the steam generator blowdown tank vent.
l D-2 I
l Rev.I D.2 Appendix ! Noble Gas Limits D.2.a Quarterly Air Dose - Method 1 - All IJnits Step I-Determine CN! " Total curies of nob!c gas released from Unit I during the calendar quarter.
Step 2 -
Determine CN2 = Total curies of noble gas released from Unit 2 during the calendar quarter.
Include all sources - ventilation, containment purges, and waste gas tanks.
Step 3 -
Deterinine CN3 = Total curies of noble gas released from Unit 3 during the calendar quarter.
Include all sources - ventilation, containment vacuurn system, gaseous radwaste system, main condenser evacuation system, and turbine gland scaling system (for the latter two systems, see Appendix 11 for inethods to deterrnine the number of curies).
Step 4 -
Determine Dgag a quarterly gamma air dose from Unit 1 (rnrad).
Dgc g 7.6 x 10-3 CN!'
Step 5 -
Determine Dqng a quarterly beta air dose from Unit 1 (mrad).
DQll! = 7.6 x 10 7 CN!
- Step 6 -
Determine DQG2 quarterly gamma air dose from Unit 2 (mrad).
DGB2 = 6.3 x 10-4CN2' Step 7 -
Deterinine DQB2 quarterly beta air doso from Unit 2 (rnrad).
Dqtg2 = 1.5 x 10-3 CN2' Step 8 Determine Dgc3 = quarterly gamma air dose from Unit 3 (mrad).
Dgc3 = 6.3 x 10 4 CN3*
Step 9 Deterinine Dqn3. quarterly beta air dose from Unit 3 (rnrad).
D [33 e 1.5 x 10-3 CN3' Q
!! D al, Dgc2, or Doc 3 are greater than 1.6 mrad; or Dggg, DQl)2, Sten 10 Q
or DQl)3 are greater tlian 3.3 mrad, go to Method 2.
'See Appendix D for derivation of factors.
D3
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Ilev. I D.2.b Quarterly Air nose - Method 2 - All Units i
Unit 2. 3 - For MP2 and MP3 dose calculations use the GASPAll computer code to determine the critical site boundary air doses.
For the Special I.ocation, enter the following worst case quarterly average meteorology:
X/Q = 0.13 x 10-4 sec/m3 (See Appendix D)
D/Q = 0.13 x 10-6 m-2 If the calculated air dose exceeds the Technical Specification limit use real time meterology.
Unit 1 -
For MP1 dose calculations use the AIREM computer code to determine the criticallocation air doses.
The 3rd quarter 1979 joint frequency data should be used as input for the AIREM code. The reason for this is given in Appendix D.
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!! the calculated air dose exceeds the Technical Specification limit, use real time meteorology.
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D4
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D 2.c Annual Air Dose 1.imit Due to Noble Cases - All Units Determine Dyct, DyG2, DYG3, Dynt, DYB2 and Dyn3 = gamma air dose and beta air dose for the calender year for Unit 1,2 or 3 as follows:
D og = 7 Dqct, Dygg = 7 Dqnt, nYG2 = 7 Dqc2, DYB2 "
I QB2; Dyc3 = 7 Dqc3, Dyg3 = { Dqn3 where the sum is over the first quarter through the present quarter doses.
The following should be used as the quarterly doses:
(1)
If the detailed quarterly dose calculations required per the section for the semlannual effluent report are complete for any calendar quarter, use those results.
(2)
If the detailed calculations are not complete for a particular quarter, use the results as deterrnined above in Section D.2.a or D.2.b.
(3)
If DYGI 2 or 3, are greater than 10 mrad or DYBI than 20,mr,ad and any corresponding quarterly dose, 2, or 3, are greater was not calculated using Section D.2.b -real time meteorology, recalculate the quarterly dose using real time meteorology.
0-3
llev. I D.) Appendix ! - todine and Particulate noses D. ).a Quarterly Doses - Unit I (1)
Meth d 1 - Unit i Step I - Determine C = total curies of I-131 released in gaseous ef fluents l
I from Unit I during the quarter.
I Step 2 - Determine Cp = total curies of particulates with half lives greater than 8 days released in gaseous effluents from Unit !
during the calendar quarter.
Step 3 - Determine DQT = quarterly thyroid dose as follows:
f Dgy = 13.7 Cg (See Appendix D)
Step 4 - Determine Dgg = quarterly dose to the maximum organ other than the thyrolas Dgo a 2.4 Cp (See Appendix D) i QT or D o. If it is Step )- The maximum organ dose is the greater of D Q
greater than 3 mrem, go to Method 2.
(2)
Metind 2 - Unit i Use the GASPAR code to determine the maximum organ dose. For the Special 1.ocation, enter the following worst caso quarterly average meterology as taken from Appendix D:
X/Q = 7.1 x 10-8 ec/M3 S
D/Q = 7.9 x 10-9 M2 Use the goat inilk, vegetation and inhalation pathway in totaling the dose.
If the maximum organ dose is greater than 7.3 mrem, go to Method 3.
(3)
Method 1. Unit i Use the GASPAll code with actual locations, real-time meteorology and the pathways which actually exist at the time at those locations.
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I D*b
I Rev.1 D.3.b Quarterly Doses -I' nit 2 or Unit 3 (1)
Method 1 5tes_l - Determine C irg the quarter.
a total curies of I-131 in gaseous effluents from Unit 2 or 3 &r Stes 2 - Determine Cp = total curies of particulates with half lives greater than 8 days released in gaseous effluents frorn Unit 2 or 3 durIng the calendar quarter.
jigg,J,- Determine Cy = total curies of trittur.: released in gaseous effluents from Unit 2 or 3 during the calendar quarter.
Step 4 - Determine DQT = quarterly thyroid done as follows:
1 3
Dgy = 285 C + 1.5 x 17 CT (See Appendix D) i itsg,1-Determine Doo = quarterly dose to the maximum organ other than the thyroW:
D o = 44 Cp + 1.5 x 10-3 CT (See Appendix D)
Q jggg 6-The maximum organ done is the greater of DQT or D o. If Q
greater than 3 mrem, go to Method 2.
(2)
Method 2 Use the GASPAR code to determine the maximum organ dose. For the Special Location, enter the following worst case quarterly average meteorology as taken from Appendix D:
X/Q = 0.13 x 10 4 sec/M3
/
,D/Q = 0.15 x 10-6 M-2 As shown in Appendix D, the same meteorology can be uwd for both continuous and batch releases. Therefore, the program need only be run l
once using the totalcuries from all releases from Unit 2 or 3.
Use the goat milk, vegetation and inhalation pathways in tuialing the dose.
If the maximum organ dose is greater than 7.5 mrem, to to Method 3.
(3)
Method 1 - Unit 2 f
l Use the GASPAR code with the actual locations, real-time meteoroiogy and the pathways which actually exist at the time at these locations. The code should be run separately for steam generator blowdown tank vents and l
ventilation releases, containment purges and waste gas tank releases.
D-7 i
(.
(4)
Method 3 - Unit 3 Use the GASPAR code with actual locations, real-time meteorology and the pathways which actually exist at these locations. This code should be run separately for ventilation, process gas, containment vacuum system, aerated ventilation and turbine gland seating exhaust; and containment purges and main condenser evacuation system.
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Rev.1 D.3.c Madmum Organ Annual Doses - All Units a.
y s - { D.stermine Dyol, D'YO2, and Dyo3 = maximum. organ dose for the calendar year for Units 1,2, and 3 respectively, as follows:
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Y01,2 or 3 o% D o' = sum of quarterly maximum organ doses where the sum D
Q is,c
\\.) zer the first quarter through the present quarter.
y l'the following guidelines should be used for use of D o:
-j Q
(ll If the detailed quarterly dose calculations required per the section for the semiannual effluent report are complete for any calendar quarter, use s
those results.
s g
r (2)
If the de' tailed calculations are not ccmplete for a particular quarter, use
. the results ds' determined abov,e in Section D.3.a or D.3.b.
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a (3)
If Dyo is ' greater than 15 mre'm and quarterly dose was not calculated l
using Method 3 of Section D3.a or D.3.b, recalculate the quarterly dose using Method 3.
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(4)
If different organs are'1he ' maximum organ for different quarters, they can be summed together and Dyo recorded as a less than value as long as the value is less than 15 mrem.g li'it is not, the sum for each organ involved should be determined.
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Rev.1 D.4 Gaseous Effluent Monthly Dose Projections D.4.a Unit 1 (1)
Due to Gaseous Radwaste Treatment System (Of fras).
Step 1 - If it is expected that the augmented offgas treatment system will be out of service during the month, go to Step 7.
Otherwise, continue with Steps 2 through 6.
Step 2 - Determine C'N = number of curies of noble gas released during the most recent month of operation from the atgmented offgas system.
1 Step 3 - Estimate R1 = ratio of expected full power offgas rate at the air ejector for the upcoming month compared to the reference month of Step 2.
Step 4 - Estimate R2 = ratio of expected unit production capacity for the upcoming month compared to the reference month of Step 2.
Step 5 - Determine DMG = estimated monthly gamma air dose. -
DMG (mrad) = 7.6.x10-5 Q'q R, R2 (Factor is from Appendix D) 1 Step 6 - Determine DMB = estimated monthly beta air dose.
D MB = 7.6 x 10-7 C'N RR2 (Factor is from Appendix D) 1 Step 7 - If the augmented offgas system is expected to be out of service during the month, determine the following:
Q=
Estimated curies /sec at the air ejector at the expected maximum power for the month.
R=
estimated curie reduction factor from air ejector to stack via the 30 minute (actual time is approximately 55 minutes) holdup line (in decimal fraction).
d=
estimated number of days the 30 minute holdup pipe will be used.
DbG = estimated monthly gamma air dose.
= 7.6 x 10-5 mrad /Ci x Q Ci/secx R x d (day) x 8.6 x 10 sec/ day.
4 E
DMG = 6.5 x Q x R x d DMB = estimated monthly beta air dose.
DbB = 0.065 x Q x R x d (2)
Due to Ventilation System Releases Step 1 - For the last quarter of operation, determine DQT or D o* as Q
determined per Section D.3.a.*
- D-10
Rev.1 Step 2 - Estimate Rj = expected ratio of primary coolant iodine level for the coming month as compared with the average level during the
- quarter used in Step 1.
s-Step 3 - Estimate R2 = expected ratio of primary leakage rate for the.
l coming month as compared with the average leakage rate during the quarter used in Step 1.
Step 4 - Determine DMO = estimated monthly dose to the maximum.
D o (or DQT)*
DMO = 1/3 R1 R2 Q
Whichever was greater Section D.3.b for Unit 2 s
=
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1 D-Il
Rev.I D.4.b Unit 2 (1)
Due to Gaseous Radwaste Treatment System Step 1 - Estimate Ch = the number of curies of noble gas to be released from the waste gas storage tanks during the next month.
Step 2 - Determine DhG = estimated monthly gamma air dose.
DhG (mrad) = 7.6 x 10-5 C%
(Factor is from Appendix D for the Unit I stack releases since the Unit 2 waste gas tanks are discharged via the Unit I stack. This factor should be conservative as the isotopic mix would only be the longer lived noble gases which would have lower dose conversion factors than the typical mix from Unit 1.)
Step 3 - Determine DhB = estimated monthly beta air dose.
DMB (mrad) = 7.6 x 10-7 Dh (2)
Due to Steam Generator Blowdown Tank Vents and Ventilation Releases Use the same method as given in Section D.4.a (2) for Unit 1.
D-12
Rev.1 D.4.c
. Unit 3 (1)
Due to Radioactive Gaseous Waste System, Steam Generator Blowdown Tank Vent.
Use the same method as given in Section D.4.b.(1).
(2). Due to Ventilation Releases
.Use the same method as given in Section D.4.a.(2).
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l D-13 L
-Rev.I D.5 ' Ouarterly Dose Calculations for Semlannual Report Detailed quarterly dose calculations required for the Semiannual Radioactive Effluent Report shall be done using the computer codes GASPAR and AIREM.
D-14
Rev.1 D.6 Compliance with 40 CFR190 The following sources should be considered in determining the total dose to a real individual from uranium fuel cycle sources:
a)
Gaseous Releases from units 1,2, and 3.
b).
Liquid Releases from units 1,2, and 3.
c)
Direct Radiation from the Site d)
Since all other uranium fuel cycle sources are greater than 5 miles away, they need not be considered.
D-15
Rev.1 E.
LIQUID MONITOR SETPOINTS E.1 Unit i Liquid Radwaste Effluent Line The trip / alarm setting on the Unit I liquid radwaste discharge line depends on dilution water flow, radwaste discharge flow, the isotopic composition of the liquid, the background count rate of the monitor and the efficiency of the monitor. Due to the variability these parameters, an alarm / trip setpoint will be determined prior to the release of each batch. The following methodology v;ill be used:
Step 1-From the tank isotopic analysis and the MPC values for each identified nuclide (including noble gases) determine the requin:d reduction factor, i.e.:
1 R = Reduction Factor = I/i uCi/mi of nuclide i MPC of nuclide i Step 2 -
Determine the existing dilution flow = D = circulating water pumps x 100,000 gpm + # service water pumps x 10,000 gpm.
Step 3 -
Determine the allowable discharge flow = F F = 0.1 x R x D Note that discharging at this flow rate would yield a discharge concentration 10% of the Technical Specification Limit due to the safety factor of 0.1.
Step 4 -
Determine the total uCi/mlin the tank.
Step 5 -
Using the latest monitor calibration curve, determine the " cps" corresponding to two times the total uCi/ml determined in Step 4.
This will be the trip setpoint.
Note:
If discharging at the allowable discharge rate as determined in Step 3, this would yield a discharge concentration corresponding to 20% of the Technical Specification limit.
Step 6 -
The allowable discharge flow rate calculated in Step 3 may be increased by up to a factor of 5 with appropriate administrative controls.
E-1
Rev.1 E.2 Unit 1 Service Water Effluent Line The MPl Reactor Building' Service Water Monitor Hi alarm setting is approximately 1.5 times the ambient background and the Hi-Hi Alarm is approximately 2 times the ambient background reading on the monitor in counts per second.'
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Rev.1 E.3 Unit 2 Clean Liquid Radwaste Effluent Line Same as Section E.1 of the MP1 Liquid Radwaste Monitor except for Step 2 where:
Dilution Flow = D = # circulating water pumps x 135,000 gpm + # service water pumps x 4,000 gpm.
E-3
Rev.1 E.4 Unit 2 Aerated Liquid Radwaste Effluent Line and Condensate Polishing Facility Waste Neut. Sump Effluent Line Same as E.3 for Clean Liquid Monitor, except that for the Condensate Polishing Facility Waste Neut. Sump, the monitor has a digital readout of uCi/ml and the alarm setpoint is set directly on uCi/mi and not the corresponding count rate.
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Rev.1 E.5 Unit 2 Steam Generator Blowdown Assumptions used in determining the Alarm setpoint for this monitor are:
a.
Maximum possible total S.G. blowdown flow rate = 500 gpm.
b.
Minimum possible circulating water dilution flow during periods c,!
blowdown = 270,000 gpm (2 pumps).
c.
Unidentified MPC for unrestricted areas = 1 x 10-7 uCi/ml*.
Therefore, the alarm setpoint should correspond to a concentration of:
Alarm (uCi/ml) = 270,000 x 1 x 10-7 = 5.4 x 10-5 uCi/ml 500 The latest monitor calibration curve should be used to determine the alarm setpoint in cpm corresponding to 1.1 x 10-4 uCi/ml.
This setpoint may be increased through proper administrative controls if the steam generator blowdown rate is maintained less than 500 gpm and/or more than 2 circulating water pumps are available.
The percent increase would correspond to the ratio of flows to those assumed above or:
Alarm (uCi/ml) = 5.4 x 10-5 uCi/ml x # Circ water pumps x 500 2
S/G Blowdown (gpm)
= 1.4 x '10-2 uCi/mi x # Circ water pumps total S/G Blowdown (gpm)
Note:The Steam Generator Blowdown alarm criteria is in practice based on setpoints required to detect allowable levels of primary to secondary leakage.
This alarm criteria is typically more restrictive than that required to meet discharge limits. This fact should be verified however whenever the alarm setpoint is recalculated.
unrestricted areas may be used.
E-5
=
Rev.1 E.6 Unit 2 Condenser Air Ejector This monitor is included as a liquid monitor since the reason it's in the Technical Specifications is for control of the Steam Generator Blowdown liquid activity. It can be used in conjunction with or in place of the blowdown monitor to ensure that the blowdown concentration is within 10CFR20 limits.
Gaseous release limits are not controlled by this monitor but rather by the monitor at the final discharge point.
A detailed study was performed to determine the equilibrium steam generator blowdown activity as a function of blowdown rate and primary to secondary leakage rate. It turns out that in order to reach 10CFR20 limits as determined in Section E.5 the minimum primary to secondary leakage rate required is 0.4 gpm.
The air ejector monitor is set to alarm at a level corresponding to approximately 0.2 gpm. leakage. Thus it ensures adequate control of blowdown.
The above values are for primary coolant activity level used at the time of the study. However, if the coolant activity increased such that the leakage rate required to reach 10CFR20 limits was less, there would be an equal increase in the sensitivity of the air ejector monitor.
4 e
s E-6
Rev.1 E.7 Unit 2 Reactor Building Closed Cooling Water The alarm setting is approximately 2 times the ambient background reading of the monitor.
4 E-P
1 Rev.1 E.8 Unit 3 Liquid Waste Monitor Similar to the Unit i liquid discharge line, the setpoints on the Unit 3 liquid waste monitor depend on dilution water flow, radwaste discharge flow, the isotopic composition of the liquid, the background count rate of the monitor and the efficiency of the monitor. Due to the variability these parameters, the alert and alarm setpoints will be determined prior to the release of each batch. The following methodology will be used:
Step 1 - From the tank isotopic and the MPC values for each identified nuclide (including noble gases) determine the required reduction i
factor, i.e.:
l R - Reduction Factor - 1/ uCi/mi of nuclide i i
MPC of nuclide i Step 2 - Determine the existing dilution flow = D = # circulating water pumps x 150,000 gpm + # service water pumps x 15,000 gpm.
Step 3 - Determine the allowable discharge flow = F F = 0.1 x R x D Note that discharging at this flow rate would yield a discharge concentration 10% of the Technical Specification Limit due to the safety factor of 0.1.
Step 4 - Determine the total uCi/ml in the tank.
Step 5 - Using the latest monitor calibration curve, determine the " cps" corresponding to 1.5 times the total uCi/ml determined in Step 4.
This will be the Alert setpoint.
Step 6 - Using the latest monitor calibration curve, determine the " cps" corresponding to two times the total uCi/mi determined in Step 4.
This will be the Alarm setpoint.
Note:
If discharging at the allowable discharge rate.as determined in Step 3,
this would yield a discharge concentration corresponding to 20 % of the Technical Specification limit.
Step 7 - The allowable discharge flow rate calculated in Step 3 may be increased by up to a factor of 5 with appropriate administrative controls.
E-8
.. - _ - ~ _ _. _, _ _ _
Rev.1 E.9 Unit 3 Regenerant Evaporator Effluent Line The MP3 Regenerant Evaporator Monitor alert setting is approximately 1.5 times the normal reading and the alarm setting is 2 times the normal reading.
1 4
s E-9 i
Rev.1 E.10 Unit 3 Waste Neutralization Sump Effluent Line Same as Section E.8.
E-10
Rev.1 E.ll Unit 3 Steam Generator Blowdown The Alarm setpoint for this monitor assumes:
a.
steam generator blowdown rate of 76 gpm for each steam generator for a total of 304 gpm.
b.
the release rate limit is conservatively set at 10% of the 10CFR Part 20 limit (0.1 times the unidentified MPC* for unrestricted areas which equals 0.1 x 1 x 10-7 uCi/mi-1 x 10-8 uCi/ml).
c.
minimum possible circulating and service water dilution flow during periods of blowdown = 456,000 gpm (3 circulating water pumps) +
30,000 gpm (2 service water pumps) = 486,000 gpm.
Therefore, the Alarm setpoint should correspond to a concentration of:
O Alarm (uCi/ml) = 486,000 x 1 x 10-8 = 1.6 x 10-5 uCi/mi 340 This setpoint may be increased through proper administrative controls if the steam generator blowdown rate is maintained less than 304 gpm and/or more than 3 circulating and 2 service water pumps are available. The amount of the increase would correspond to the ratio of flows to those assumed above or:
Alarm (uCi/ml) = 1.6 x 10-5 uCi/mi x circulating & service water flow (gpm) 486,000 gpm x
304 apm S/G Blowdown (gpm)
= 1 x 10-8 uCi/ml x circulating & service wate flow (gpm) total S/G Blowdown (gpm)
Note:The Steam Generator Blowdown alarm criteria is in practice based on setpoints required to detect allowable levels of primary to secondary leakage.
This alarm criteria is typically more restrictive than that required to meet discharge limits. This fact should be verified however whenever the alarm setpoint is recalculated.
- In lieu of using the unidentified MPC value, the identified MPC values for unrestricted areas may be used.
l l
E-Il l
l
~.
Rev.1 E.12 Unit 3 Turbine Building Floor Drains Effluent Line The Alarm setpoint for this monitor assumes:
a.
Drinking water is not a real pathway at this site. Therefore the NRC code, LADTAP, is used to calculate the dose to the maximum individual.
b.
The dilution flow is 5 gpm (1.11 x 10-2 3
ft /sec) c.
Near field dilution factor = 13,000.
Far field dilution factor = 32,000.
(
Reference:
Millstone 3 FSAR, Section 2.4.13) d.
Isotopic concentrations were taken from the Millstone 3 FSAR, Table 11.2-4 (See column under Turbine Building).
e.
Each concentration above was multiplied by the total annual flow (9.95 x 10 cm3, conservatively assuming 5 gpm continuous).
9 f.
The maximum individual organ dose is set equal to 0.1% of 1500 mrem. The limiting individual is the child; maximum organ is the thyroid.
The setpoint corresponding to 1.5 mrem to the child's thyroid is 7.6 x 10-5 uCi/ml.
E-12
V Rev.1 F.
GASEOUS MONITOR SETPOINTS F.1 Unit 1 Hydrogen Monitor Per Section 3.8.D.6 of the Technical Specifications, the alarm setpoint shall be less than or equal to 4% hydrogen by volume.
F-1
Rev.1 F.2 Unit 1 Steam Jet Air Elector Of fgas Monitor Per Section 3.8.D.7 of the Technical Specifications, the maximum allowed noble gas in-process activity rate shall not exceed 1.47 x 106 uCi/Sec. This value will be more limiting than the instantaneous stack release rate limit.
Using the latest offgas monitor calibration curve, determine the reading in 6
mR/HR corresponding to 1.47 x 10 uCi/sec. The alarm setpoint should be set at less than or equal to this value.
F-2
Rev.1 F.3 Unit i Stack Noble Gas Monitor Per Technical Specifications 3.8.D.1 and ODCM Section D.I.a, the instantaneous release rate limit from the site shall be:
Q1 Q2 Q3 41
+
+
790,000 217,000 217,000 where Q1 = noble gas release rate from MP1 stack (uCl/sec)
Q2 = noble gas release rate from MP2 vent (uCl/sec)
Q3 = noble gas release rate from MP3 vent (uC1/sec)
Assume 33% of the limit is from MP1 stack.
Therefore Q1 should be less than 260,000 uCi/sec.
The MP1 stack noble gas monitor calibration curve (given as uCi/sec per cps) is determined by assuming a maximum ventilation flow of 170,000.
Therefore, the alarm setpoint should be set at or below the " cps" corresponding to 260,000 uCl/sec from the calibration curve.
The alarm setpoint may be increased if the MP2 or MP3 vent setpoints are at levels corresponding to less than 33% of the site limit.
F-3
z --
Rev.1 i
F.4 Unit 1 Main Stack Sampler Flow Rate Monitor The MPl main stack sampler flow control alarms on low pressure indicating loss of flow, or on high pressure indicating restricted flow.
The alarm will occur with either:
a)
Pressure Switch #1 less than 2" Hg or b)
Pressure Switch #1 greater than 18" Hg and Pressure Switch #2 less than 20" Hg F-4
Rev.1 F.5 Unit 2 Vent - Noble Gas Monitor Per Section D.I.a of this manual, the instantaneous release rate limit from the site shall be:
Q1 Q2 Q3 f,
1
+
+
790,000 217,000 217,000 Assuming 33% of the limit is from the MP2 vent, the release rate limit for Unit 2 is 71,000 uCl/sec.
The MP2 vent noble gas monitor calibration curve (given as uCi/sec per cpm)is determined by assuming the maximum possible ventilation flow for various fan combinations. Curves for 3 different fan combinations are normally given.
The " cpm" corresponding to 71,000 uCi/sec should be determined from the appropriate curve. The alarm setpoint should be set at less than or equal to this
. value.
The alarm setpoint may be increased if the MP1 stack or MP3 vent setpoints are at levels corresponding to less than 33% of the site limit.
F-5
Rev.I s.4 F.6 Unit 2 Waste Gas Decay Tank Monitor Per Section D.I.a of this manual, the instantaneous release rate limit from the site shall be:
Q1
+
Q2
+
Q3 4 1 790,000 217,000 217,000 Administratively all waste gas decay tank releases are via the MP1 stack.
Assuming 33% of the limit is from the MP1 stack, the release rate limit for MPI is 260,000 uCl/sec.
Releases trom wa:te gas decay tanks are much lower than this limit and are based upon ventilation dilution, consetvative meteorology (X/Q = 10-3) and release flow rates to maintain off site concentration below MPC values.
The MP2 waste gas' decay tank monitor (given as uCi/cc per epm) calibration curve is used to assure that the concentration of gaseous activity being released from a waste gas decay tank is not greater than the concentration used in discharge permit calculations.
9 F-6
t i
Rev.I F.7 Unit 3 Vent Noble Gas Monitor t
Per Section D.l.a of this manual, the instantaneous release rate limit from the site shall be:
4 91 Q2 Q3 g
1
+
+
790,000 217,000 217,000 Assuming 33% of the limit is from the MP3 vent, the release rate limit for Unit 3 h 71,000 uCl/sec. Based on the maximum ventilation flow rate of 280,680 8
CFM (1.325 x 10 cc/sec, see Table 3.5-16 of MP3 FSAR) this converts to:
Alarm setpoint= 71,000 uCi/sec/1.325 x 108 cc/sec 5.3 x 10-4 uCl/sec
=
F-7
Rev.I F.8 Unit 3 Engineering Safeguards Building Monitor Per Section D.I.a of this manual, the instantaneous release rate limit from the site shall be:
31 3L 4
32
+
+
1 790;U00 217;U00 217I000 Assuming releases less than 10% of the MP3 FSAR design releases of noble gases (Table 11.3-11,1.4 x 104 Ci/ year which is equal to 450 uCi/sec) assures that less than 1% of the above instantaneous relea'se rate is added by this intermittent pathway (450/217,000 = 0.21%). Assuming a flow rate of 6,500 CFM (3.05 x 10-6 cc/sec) for this pathway translates this limit to:
0.1 x 450/3.05 x 106 = 1.5 x 10-5 uCi/cc The Alarm setpoint should be set at or below this value.
f 9
?
9 h
I t
F-8 r
F:
Rev.1 G.
EFFLUENT FLOW DIAGRAMS Figures G-1, G-2, G-3, G-4, G-5 and G-6 present simplified flow diagrams for the liquid and gaseous radwaste systems for Units 1, 2 and 3. They also indicate the
' location of the radiation monitors listed in the Technical Specifications.
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Figure G-3 Simplified Flow Diagram - Liquid - Millstone Unit #3 Containment Building Sump 40 GPD Auxiliary Building Sump 200 GPD High Level Waste Test Waste Waste Reactor Plant Samples Sinks Waste Drain Evaporator __
Task Pump Demineralizer Demineralizer 35 GPD Tank Filter 25,000 Gal 35 GPM 21,000 Gal Laboratory Wastes 400 GPD Misc. High-Level Waste 660 GPD Reactor Coolant Bleed to Chemical and Degas-Cesium Boron Boron Test Boron Boron Recovery Volume Control ifier Removal Tank Evaporator Tank Demin-Filter Recovery 1440 GPD System IX eralizer o
150,000 25 GPM 12,000 Gal Gal Plant Gaseous Drains 300 GPD Low-Level Effluent Misc. Low-Level Waste Waste Drain Pump Filter
-*~
40 GPD Tank Drain 50gpm Liquid h
Waste Monitor Regenerant Regenerant
'Regenerant Reactor Regenerant Chemicals Evaporator Regenerant Pump Demineralizer Deminealizer Discharge Tunnel
~*'
~*
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3400 GPD Feed Tank Evaporator' Filter OR 3,000 Gal 35 GPM Regenerant Evaporator Monitor Coodensate Polishing Sum 1 Monitor Facility Waste W
Nentralization Sump V
Flash Steam Generator Blowdown Tank Steam Generator Blowdown Monitor Turbine Building Drains m
72,000 GPD Turbine Building Floor A
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.i Figure G Simplified Flow Diagram - Gaseous - Millstone Unit #3 Auxiliary Atmosphere Building Filters Service Building n
Ventilation Auxiliary Building Monitors Ventilation Alterate Path From Gasous Waste System Fuel Unit #3 Building Filters Containment Ventilation Fuel Building Monitor Purge Vent C'ontainment Purge Monitor Waste Liquid Waste System Disposal Building Baron Recovery System Gaseous Waste System Degassifier Ventilation H
p Ventilation Vent Monitor Condensate Deminearlizer Liquid Waste System
- Containment Vacuum Pumps Exhaust Air Ejector Monitor Condensate Air Removal System V
W U
Reactor Plant Aerated Vent System Process Gas Charcoal Bed Adsorbers Radioactive Gaseous Waste System
~
n SLCRS Monitor Atmosphere Reactor Plant Gaseous Vent System W
4 Atmosphere Unit #1 ESF Monitor 4
Stack Engineered GR ESF Safety Features v
Building Exhaust I
Building Atmosphere Atmosphere Atmopphere (during startup) 4 f
f Turbine Building Roof Condenser Containment Turbine Gland Exhaust Vacuum Priming Vacuum Steam m
Seal Steam Condenser (during startup; Ejector Exhaust
Rev.1 APPENDIX A DERIVATION OF FACTORS FOR SECTION C.1 - LIQUID DOSES
- 1.
Section C.I.a - Step 3 Unit 1 - Liquid - Whole Body Doses DQT(F)/Cp DQT(H)/CH Year Qtr.
C_p_
QT(F)
(mrem /Ci)
C_H_
DQT(H)
(mrem /Ci)
D 1976 1
8.60 7.6(-2) 8.8(-3) 3.12 ND 2
0.053 1.3(-4) 2.5(-3) 9.19 2.l(-6) 2.3(-7) 3 0.48 6.8(-3) 1.4(-2) 1.33 ND 4
0.15 1.3(-3) 8.7(-3) 4.42 1.9(-6) 4.3(-7) 1977 1
0.12 1.l(-3) 9.2(-3) 3.11 7.3(-7) 2.3(-7) 2 0.36 4.6(-3) 1.3(-2) 0.64 1.3(-7) 2.0(-7) 3 0.012 1.1(-4) 9.2(-3) 0.002 8.0(-10) 3.5(-7) 4 0.028 1.5(-4) 5.4(-3) 0.66 2.3(-7) 3.5(-7) 1978 1'
O.119 1.3(-3) 1.l(-2) 0.98 3.9(-7) 3.9(-7) 2 0.049 5.2(-4) 1.1(-2) 1.29 2.9(-7) 2.2(-7) 3 0.002 2.l(-5) 1.l(-2) 0.93 4
0.005 5.8(-5) 1.2(-2) 0.0002 1979 1
0.045 4.4(-4) 1.0(-2) 1.78 2
0.146 1.5(-3) 1.0(-2) -
2.83 3
0.009 9.7(-5) 1.l(-2) 0.94 4
0.010 4.6(-5) 4.6(-3) 2.37 1980 1
0.013 6.2(-3) 4.8(-3) 2.40 3.04(-7) 1.27(-7) 2 0.014 1.6(-4) 1.1(-2) 4.96 1.54(-6) 3.10(-7) 3 0.011 1.2(-4) 1.l(-2)
~6.45 1.67(-6) 2.59(-7) 4 0.686 1.2(-2) 1.8(-2) 13.50 1981 1
0.314 5.8(-3) 1.9(-}
1.42 2
0.042 7.6(-4) 1.1(-2) 0.88 3
0.029 3.5(-4) 1.2(-2) 0.31 4
0.009 1.2(-4) 1.3(-2) 0.006
.982 1
0.008 1.2(-4) 1.5(-2) 0.12 2
0.030 1.8(-4) 6.0(-3) 0.12 3
0.577 7.4(-3) 1.3(-2) 3.88 l
4 0.538 6.l(-3) 1.1(-2) 2.08 4
1983 1
0.777 3.9(-3) 5.0(-3) 1.61 2
0.007 7.3(-5) 1.0(-2) 1.87 3.96(-7) 2.12(-7) 3 0.007 1.0(-4) 1.4(-2) 3.64 1.16(-6) 3.19(-7) 4 0.016 2.0(-4) 1.3(-2) 1.26 j-.
Rev.O APPENDIX A DERIVATION OF FACTORS FOR SECTION C.1 - LIQUID DOSES
- 1.
Section C.I.a - Step 3 Unit 2 - Liquid - Whole Body Doses DQT(F)/Cp DQT(H)/CH Year Qtr.
Cp_
QT(F)
(mrem /Ci)
C DQT(H)
(mrem /Ci)
D H_
1976 1
0.102 1.8(-4) 1.8(-3) 34.7 1.2(-5) 3.4(-7) 2 0.179 2.4(-4) 1.3(-3) 87.3 2.7(-5) 3.l(-7) 3 0.037 0.9(-4) 2.4(-3) 70.0 2.0(-5) 2.8(-7) 4 0.025 1.0(-4) 4.0(-3) 85.4 3.7(-5) 4.3(-7) 1977 1
0.217 7.0(-4) 3.2(-3) 60.1 2.l(-5) 3.4(-7) 2 0.802 6.l(-3) 7.6(-3) 73.3 3.0(-5) 4.l(-7) 3 0.037 1.6(-4) 1.6(-4) 42.1 1.5(-5) 3.5(-7) 4 0.509 1.9(-3) 3.7(-3) 35.0 1.1(-5) 3.3(-7) 1978 1
0.432' 5.2(-3) 1.2(-2) 1.8 8.9(-7) 4.9(-7) 2 1.27 6.6(-3) 5.2(-3) 43.6 1.2(-5) 2.7(-7) 3 0.715 4.8(-3) 6.7(-3) 91.3 4
0.372 1.8(-3) 4.8(-3) 72.0 1979 1
1.65 9.6(-3) 5.8(-3) 64.6 2
2.48
. 2.8(-2) 1.l(-2) 27.8 3
0.331 2.8(-3) 8.5(-3) 68.4 4
0.411 3.0(-3) 7.3(-3) 93.0 1980 1
0.635 4.0(-3) 6.3(-3) 97.7 2
0.285 1.7(-3) 6.0(-3) 57.0 1.09(-5) 1.91(-7) 3 1.17 7.9(-3) 6.8(-3) 48.8 4
0.723' 1.2(-2) 1.7(-2) 64.8 2.28(-5) 3.52(-7) 1981 1
0.435 6.8(-3) 1.6(-2) 55.3 2
0.343 5.8(-3) 1.7(-2) 149.0 541.(-5) 3.63(-7) 3 0.265 1.6(-3) 6.0(-3) 87.2 1.77(-5) 2.03(-7) 4 3.14 1.0(-2) 3.2(-3) 79.9 1982 1
1.65 1.0(-2) 6.1(-3) 7.4 2
9.94 8.4(-3) 8.5(-4) 88.3 491.(-5) 5.56(-7) 3 1.14 8.l(-3) 7.l(-3) 113.0 4
1.14 1.3(-2) 1.l(-2) 82.6 L --
Rev.1 APPENDIX A
-DERIVATION OF FACTORS FOR SECTION C.1 - LIQUID DOSES
- 1.
Section C.I.a - Step 3 Unit 2 - Liquid - Whole Body Doses y
DQT(F)/Cp DQT(H)/CH DQT(F)
(mrem /Ci)
C_H_
QT(H)
(mrem /Ci)
C D
Year -
Qtr.
4
- 1983 1
1.48 1.1(-2) 7.4(-3) 70.7 2
0.685 7.2(-3) 1.l(-2) 36.7 3
2.42 3.6(-2) 1.5(-2) 6.5 4
3.22 4.5(-2) 1.4(-2) 6.8 Unit 3 - Liquid Whole Body Doses Dose Projected Releases
- Ci/yr (mrem)
Dose /Ci Total Fission and 0.18 8.8(-4) 4.9(-3)
- Activation (ex.H-3)
H-3 730 1.6(-4) 2.2(-7)
Since the maximum values DQT(F)/Cp and DQT(H)/CH are not much different for Units 1 and 2, the same factor can be used for all three units (for simplicity).
Also,' the maximum values are less than four times the average values, this indicates that the dose per total curie does not fluctuate greatly; hence this
- - method is not overconservative.
- from Unit 3 ER Table 5.2-4.
- where, Cp = Curies of fission and activation products released during calendar quarter.
DQT(F) = Calculated total body dose to the maximum individual (mrem) due to fission and activation products. Dose calculated using computer code LADTAP.
CH = Curies of tritium released during calendar quarter. L
Rev.1 DQT(H) =
Calculated total body does to the maximum individual (mrem) due to tritium releases.
Dose calculated using computer code LADTAP.
Maximum Value of DQT(F)/Cp -
Unit 1 = 1.9 x 10-2 mrem /Ci Unit 2 = 1.7 x 10-2 mrem /Ci Unit 3 = unknown Average Value of DQT(F)/Cp -
Unit 1 = 1.1 x 10-2 mrem /Cl Unit 2 = 7.4 x 10-3 mrem /Ci Unit 3 = 4.9 x 10-3 mrem /Ci Maximum Value of DQT(H)/CH-Unit 1 = 4.3 x 10-7 mrem /Ci Unit 2 = 5.6 x 10-7 mrem /Ci Unit 3 = unknwon Average Value of DQT(H)/CH-Unit 1 = 2.8 x 10-7 mrem /Ci Unit 2 = 3.5 x 10-7 mrem /Ci Unit 3 = 2.2 x 10-7 mrem /Ci DQT(F)/Cp = 1.9 x 10-2 mrem /Ci DQT(H)/CH = 5.6 x 10-7 mrem /Cl
- Note: Although operation of Unit 3 increases the dilstion flow, the near field dilution factor is reduced from 5 to 3. Therefore, the net effect is to reduce the doses only by a factor of 0.86. For conservatism, this factor will be neglected.
-4 E
o Rev.1 APPENDIX B DERIVATION OF FACTORS FOR SECTION C2 - LIQUID DOSES 1.
Section C.2.a - Step 2 Unit 1 - Liquid Doses Max. Organ Dg D g/Cp_
Year Qtr.
C_p_
1976
-1 8.60 GI (LLI) 0.054 0.0062 2
0.053 GI (LLI) 0.0003 0.0056 3
0.48 GI (LLI) 0.059 0.123 4
0.15 GI (LLI) 0.0057 0.038 1977 1
0.12 GI (LLI) 0.0021 0.018 2
0.36 GI (LLI) 0.0041 0.011 3
0.012 Liver 0.00017 0.014 4
0.028 GI (LLI) 0.00086 0.031 1978 1
0.119 GI (LLI) 0.024 0.202 2
0.049 GI (LLi) 0.0031 0.063 3
0.002 GI (LLI) 4.0(-5) 0.02 4
0.005 GI (LLI) 1.3(-4) 0.026 1979 1
0.045 GI(LLI) 1.8(-3) 0.04 2
0.146 GI(LLI) 9.3(-3) 0.064 3
0.009 GI(LLI) 9.0(-4) 0.10 4
0.01 GI(LLI) 2.1(-4) 0.021 1980 1
0.013 GI(LLI) 1.7(-4) 0.013 2
0.014 GI(LLI) 5.5(-4) 0.039 3
0.011 GI(LLI) 3.0(-4) 0.027 4
0.686 Liver 1.7(-2) 0.025 1981.
1 0.314 GI(LLI) 9.75(-3) 0.031 2
0.042 GI(LLI) 1.88(-3) 0.045 3
0.029 GI(LLI) 7.94(-4) 0.027 4
0.009 GI(LLI) 2.58(-4) 0.029 1982 1
0.008 GI(LLI) 2.58(-4) 0.032 2
0.030 GI(LLI) 3.09(-4) 0.010
.3 0.577 Liver 1.24(-2) 0.021 Thyroid 1.42(-2) 0.025 4
0.538 GI(LLI)
'l.17(-2) 0.022 1983 1
0.777 GI(LLI) 1.26(-2) 0.016 2
0.007 GI(LLI) 1.73(-4) 0.025 3
0.007 GI(LLI) 2.15(-4) 0.031 4
0.016 GI(LLI) 4.12(-4) 0.026 L
Rev.1 APPENDIX B DERIVATION OF FACTORS FOR SECTION C2 - LIQUID DOSES
- 1. - Section C.2.a - Step 2 Unit 2 - Liquid Doses Year Qtr.
C_p,,
Max. Organ Dg D g/Q:,,
1976 1
0.102 GL (LLI) 0.0017 0.016 2
0.179 GI (LLI) 0.0051 0.028 3
0.037 GI (LLI) 0.0024 0.065 4
0.025 GI (LLI) 0.00075 0.030 1977 1
0.217 GI (LLI) 0.012 0.055 2
0.802 GI (LLI)'
O.036 0.045 3
0.035 GI (LLI) 0.0014 0.040 4
0.509 GI (LLI) 0.012 0.024 1978 1
0.432 GI (LLI) 0.039 0.090 2
1.27 GI (LLI) 0.13 0.120 3
0.715 GI (LLI) 4.2(-2) 0.059 4
0.372 GI (LLI) 9.0(-3) 0.024 1979 1
1.65 GI (LLI) 4.1(-2) 0.025 2
2.48 GI (LLI) 2.3(-1) 0.097 3
0.331 GI (LLI) 1.8(-2) 0.054 4
0.411 GI (LLI) 1.6(-2) 0.039 1980 1
0.635 GI (LLI) 1.1(-2) 0.017 2
0.285 GI (LLI) 3.9(-3) 0.014 3
1.17 GI(LLI) 1.0(-1) 0.085 4
0.723 GI (LLI) 7.4(-2) 0.102 1981 1
0.435-GI (LLI) 2.91(-2) 0.067 2
0.343 GI (LLI) 2.91(-2) 0.085 3
0.265 GI (LLI) 7.47(-3) 0.028 4
3.14 Liver 1.67(-2) 0.005 1982' 1
1.65 GI (LLI) 9.6(-2) 0.058 2
9.94 GI (LLI) 5.76(-2) 0.006 Thyroid 3.59(-1) 0.036 3
1.14 GI (LLI) 2.43(-2) 0.210 Thyroid 2.84(-2 0.025 4
1.14 Liver 1.09(-2) 0.010 1983 1
1.48 Liver 1.66(-2) 0.011 2
0.685 Liver 1.14(-2) 0.017 3
2.42 GI (LLI) 6.36(-2) 0.026 4
3.22 GI (LLI) 7.74(-2) 0.024 '
Rev.I Unit 3 - Liquid Doses Projected Releases Maximum Dose from ER Ci/yr Organ (mrem /yr)
Dose /Ci 0.18 Thyroid 6.3(-3) 0.035
- where, Cp Curies of fission and activation products released during
=
calendar quarter.
GI (LLI)
Gastro - Intestinal Tract - Lower Large Intestine.
=
Dgo Calculated critical organ dose to the maximum individual
=
(mrem) for the calendar quarter. Dose was calculated using the computer code LADTAP.
Note Tritium has never contributed more than 1% to the maximum
=
organ dose and thus is it not included in the calculation.
Maximum Value of Dqo/CF -Unit 1 - 0.202 mrem /Ci Unit 2 - 0.120 mrem /Cl Unit 3 - unknown Average Value of D o/Cp - Unit 1 - 0.038 mrem /Cl Q
Unit 2 - 0.044 mrem /Ci Unit 3 - 0.035 mrem /Cl Since the maximum value of Dqo/Cp is within a factor of two for Unit I and 2, the same factor can be used for all units for simplicity. Also, since the maximum value is within a fator of 6 of the average value, this indicates that the dose per total curie does not fluctual greatly, hence this method is not over-conservative.
Thus, Dgo/Cp = 0.2 mrem /Ci i
Rev.1 APPENDIX C LADTAP - LIQUID DOSE CALCULATIONS The LADTAP code was written by the NRC to compute doses from liquid releases using the models given in Regulatory Guide 1.109. There is no revision date on the copy of the code which was obtained, but it was purchased in March 1976. The only change made to the code since that time was a change in the ingestion dose factors from those given in Rev. O of Reg. Guide 1.109 to those in Rev.1.
For calculating the maximum individual dose at Millstone, the following options and parameters are used:
1.
Real time, measured dilution flow 2.-
Salt water site 3.
Reconcentration - cycle time - 12 hrs. (MP1 and 2 FES)
Recycle fraction = 0.025 (MP1 and 2 FES) 4.
'Shorewidth factor = 0.5 (Table A-9, Regulatory Guide 1.109) 5.
Dilution for Max. Individual Pathways = 3 (page 5.2-5 of MP3 Environmental Report) 6.
30 min. Discharge Transit Time - time to transit quarry; estimated from chloride study.
7.
Reg. Guide 1.109 usage factors for Max. Individual for fish, shellfish, shoreline, swimming and boating pathways.
8.
Zero usage for algae, drinking water, and irrigated food pathways.
t Rev.1 APPENDIX D DERIVATION OF FACTORS FOR SECTION D GASEOUS DOSES 1.
. X/Q's, D/Q's
- Unit 1 Stack Elevated X/Q's, D/Q's Quarterly Averages - Maximum Values 1976 1
2.7(-8) 1.3(-9) 2 2.8(-8) 2.1(-9) 3 4.7(-8) 5.5(-9) 4 2.6(-8) 7.9(-9) 1977 1
2.3(-8) 1.4(-9) 2 4.1(-8) 4.2(-10) 3 4.8(-8) 2.2(-9) 4 5.4(-8) 4.8(-9) 1978' 1
4.7(-8) 6.6(-9) 2 5.3(-8) 1.2(-9) 3 4.0(-8) 2.2(-9) 4 7.l(-8) 4.3(-9) 1979 1
4.2(-8) 5.1(-9) 2 5.2(-8) 1.5(-9) 3 3.2(-8) 2.4(-9) 4 5.7(-8) 4.9(-9) 1980 1
5.3(-8) 2.8(-9) 2 4.0(-8) 1.7(-9) 3 4.6(-8) 1.8(-9) 4 6.3(-8) 4.0(-9) 1981 1
4.5(-8) 4.8(-9) 2 1.6(-8) 9.1(-10) 3 6.3(-8) 1.6(-9) 4 4.9(-8) 6.2(-9) 1982 1
5.9(-8) 2.4(-9) 2 2.6(-8) 2.4(-9) 3 4.8(-8) 2.2(-9) 4 5.1(-8) 1.2(-9) <
Rev.1 Year Quarter Maximum X/Q Maximum D/Q 1983 1
3.7(-8) 3.3(-10) 2 6.0(-8) 3.9(-10) 3 4.4(-8) 5.5(-10) 4 6.0(-8) 1.8(-9)
Maximum Quarterly Average X/Q = 7.1 x 10-8 sec M3 Maximum Quarterly Average D/Q = 7.9 x 10-9 M-i
)
l l
l v
j l l
Rev.1 Unit 2 and Unit 3 - Vents
- Quarterly Average X/Q's - D/Q's Maximum Values Maximum X/Q M_gi'qum D/Q Year Qtr Continuous Batch Cont!. aous Batch 1976 1
5.0(-6)
ND 4.3(-8)
ND 2
1.3(-5)
ND 6.7(-8)
ND 3
4.4(-6) 8.1(-6) 4.5(-8) 8.0(-8) 4 2.2(-6) 5.9(-6) 2.5(-8) 6.5(-8) 1977 1
2.8(-6) 4.1(-6) 3.2(-8) 5.4(-8) 2 1.9(-6) 1.4(-6) 1.3(-8) 1.3(-8) 3 8.2(-6) 7.5(-6) 1.5(-7) 1.5(-7) 4 3.5(-6) 2.6(-6) 6.9(-8) 5.2(-8) 1978 1
2.5(-6)
ND 4.3(-8)
ND 2
5.3(-6) 1.6(-6) 8.7(-8) 2.9(-8) 3 9.1(-6) 8.2(-6) 1.4(-7) 1.1(-7) 4 3.3(-6) 4.2(-6) 8.7(-8) 8.0(-8) 1979 1
2.2(-6)
ND 3.8(-8)
ND 2
5.1(-6) 5.0(-6) 8.0(-8) 6.2(-8) 3 7.5(-6) 5.1(-6) 1.3(-7) 9.4(-8) 4 3.8(-6) 4.6(-6) 9.3(-8) 1.0(-7) 1980 1
2.3(-6) 9.5(-7) 5.1(-8) 6.5(-8) 2 6.9(-6) 6.8(-6) 1.1(-7) 1.3(-7) 3 7.3(-6)
ND 1.2(-7)
ND 4
3.2(-6)
ND 7.6(-8)
ND 1981 1
3.9(-6) 1.3(-7) 6.5(-8) 1.1(-8) 2 7.9(-6) 8.8(-9) 1.0(-7) 7.0(-10) 3 4.9(-6) 7.3(-8) 9.6(-8) 4.9(-9) 4 1.7(-6) 3.5(-8) 4.l(-8) 5.1(-9) 1982 1
2.9(-6) 5.4(-8) 4.5(-8) 2.1(-9) 2 6.5(-6)
ND 9.2(-8)
ND 3
6.7(-6) 4.5(-8) 1.2(.7) 2.1(-9) 4 4.2(-6) 2.9(-8) 1.0(-7) 1.4(-9) 1983 1
1.3(-6) 9.l(-8) 2.6(-8) 6.7(-10) 2 5.4(-6) 1.7(-7) 1.1(-7) 2.0(-9) 3 8.1(-6) 2.4(-7) 1.5(-7) 4.4(-9) 4 2.3(-6) 1.2(-7) 6.2(-8) 6.4(-9)
Maximum Quarterly Average = 1.3 x 10-5 ec/M3 S
Maximum Quarterly Average D/Q = 1.5x 10-7 M-2 t
m.
Rev.1 From the above data we can also see that the batch releases are of a random enough nature such that the batch release meteorology approximates the continuous meteorology as shown by the average of the above values:
Average Max. Qtr. X/Q - Continuous Release -
5.0 x 10-6 Average Max. Qtr. D/Q - Batch Releases -
2.7 x 10-6 Average Max. Qtr. D/Q - Continuous Releases -
7.8 x 10-8 Average Max. Qtr. D/Q - Batch Releases -
4.5 x 10-8 Therefore, the same X/Q's and D/Q's can be used for both batch and continuous releases.
Release heights for these two vents are approximately the same. Tables D-2a and D-2b of the NRC Draft Environmental Statement for Millstone 3 show that the average X/Q for Unit 3 to be less than Un*t 2 (because of location), however the D/Q's are equal.
Rev.1 -
2.
Section D.1.a - Noble Gas Release Rate Limits Unit 1 Stack Gaseous Releases - Curies vs. Dose Max. Individual mrem per Avg. Noble Gas Dose (Mrem) uCi/Sec Year Quarter Release Rate (uCi/Sec)
W. B.
Skin W.B. and Skin 1976 1
17,400 1.9 1.9 1.1 (-4) 2 25,600 4.2 4.3 1.6 (-4) 3 20,100 3.4 3.4 1.7 (-4) 4 2,600 0.3 0.3 1.0 (-4) 1-4 16,400 9.8 9.9 6.0 (-4) 1977 1
11,600 1.1 1.1 8.6 (-5) 2 13,000 1.9 1.9 1.5 (-4) 3 24,000 4.6 4.6 1.9 (-4) 4 29,700 2.2 2.2 7.4 (-5) <
l-4 19,600 9.8 9.8 5.0 (-4) 1978 1
50,800 4.4 4.4 8.7 (-5) 2 20,800 3.1 3.1 1.5 (-4) 3 350 0.04 0.04 1.3 (-4) 4 530 0.03 0.03 6.4 (-5) 1-4 18,100 7.6 7.6 4.2 (-4) 1979.
I 1,180 0.032 0.032 2.7 (-5) 2 380 0.024 0.024 6.3 (-5) 3 640 0.061 0.061 9.5 (-5) 4 420 0.024 0.024 5.7 (-5) 1-4 655 0.14 0.14 2.1 (-4) 1980 1
360 0.018 0.020 5.0 (-5) 2 230 0.019 0.019 8.2 (-5) 3 880 0.20 0.20 2.3 (-4) 4 40 6.4(-4) 6.4(-4) 1.6 (-5) 1-4 380 0.24 0.24 6.3 (-4) 1981 1
1.2 6.0 (-6) 6.0 (-6) 5.0 (-6) 2 25 0.004 0.004 1.6 (-4) 3 1580 0.19 0.19 1.2 (-4) 4 220 0.015 0.016 6.8 (-5) 1-4 460 0.21 0.21 4.6(-4) 1982 1
160 0.004 0.004 2.5 (-5) 2 140 0.042 0.042 3.0 (-4) 3 490 0.051 0.052 1.0 (-4) 4 240 0.002 0.002 8.3 (-6) 1-4 260 0.10 0.10 3.8 (-4) l i
Rev.1 i
Max. Individual mrem per Avg. Noble Gas Dose (Mrem) uCl/Sec Year Quarter Release Rate (uCl/Sec)
W. B.
Skin W.B. and Skin 1983 1
560 0.002 0.002 3.6 (-6) 2
-120 0.014 0.014 1.2 (-4) 3 74 0.012 0.012 1.6 (-4) 4 56 0.003 0.003 5.4 (-5) 1-4 200 0.031 0.031 1.6 (-4)
Unit 2 Stack-Gaseous Releases - Curies vs. Dose Max. Individual mrem per Avg. Noble Gas Dee (mrem) uCi/Sec.
Ratio Year Quarter Release Rate (uCi/Sec)
W. B.
Skin W. B.
Skin /W.B.
1976 1
0.63 0.00016 0.00047 2.5 (-4) 2.9 2
83 0.058 0.16 7.0 (-4) 2.8 l
3 54 0.015 0.055 2.8 (-4) 3.7 4
63 0.022 0.035 3.5 (-4) 1.6 1-4 50 0.095 0.25 1.9 (-3) 2.6 l
l 1977 1
134 0.023 0.058 1.7 (-4) 2.5 2
70 0.007 0.018 1.0 (-4) 2.8 3
39 0.019 0.056 4.9 (-4) 2.9 4
69 0.010 0.030 1.4 (-4) 3.0 1-4 78 0.059 0.162 7.6 (-4) 2.7 1978 1
10 0.0068 0.012 6.8 (-4) 1.8 2
91 0.019 0.058 2.1 (-4) 3.1 3
313 0.13 0.37 4.2 (-4) 2.8 4
_ 21 0.0054 0.011 2.6 (-4) 2.0 1-4 109 0.16 0.45 1.5 (-3) 2.8 1979 1
- 7. l
- 0.0081 0.019 1.1 (-3) 2.3 2
2.6 0.0066 0.0021 2.5 (-4) 3.2 3
38 0.013 0.037 3.4 (-4) 2.8 4
23 0.0052 0.015 2.3 (-4) 2.9 l-4 18 0.027 0.073 1.5 (-3) 2.7 1980 1
54 0.0086 0.022 1.7 (-4) 2.6 l
2 47 0.020 0.056 4.3 (-4) 2.8 3
67 0.066 0.13 9.9 (-4) 2.0 i
4 1.7 0.0028 0.0043 1.8 (-3) 1.5 I
l-4 42 0.098 0.212 2.3 (-3) 2.2 1981 1
16 0.0061 0.014 3.8 (-4) 2.3 L
2 124 0.075 0.20 6.0 (-4) 2.7 3
64 0.030 0.078 4.7 (-4) 2.6 4
74 0.013 0.033 1.6 (-4) 2.5 1-4 70 0.124 0.325 1.8(-3) 2.6 t
Rev.1 Max. Individual mrem per Avg. Noble Gas Dose (Mrem)
Ci/Sec Ratio Year Quarter Release Rate ( Ci/Sec)
W. B.
Skin W. B.
Skin /W.B.
1982 1
5.3**
0.013 0.022 2.5 (-3) 1.7 2
322 0.18 0.49 5.6 (-4) 2.7 3
205 0.13 0.34 6.3 (-4) 2.6 4
191 0.074 0.18 3.9 (-4) 2.4 1-4 180 0.397 1.032 2.2 (-3) 2.6 1983 1
464 0.041 0.11 8.8 (-5) 2.7 2
659 0.22 0.62 3.3 (-4) 2.8 3
0 0.0045 0.0053 1.2 4
0 0.0020 0.0023 1.2 1-4 280 0.268 0.737 9.6 (-4) 2.8 Only continuous ventilation (purge data leads to an unconservative value).
Beginning in 1982, purges are released through Unit I stack.
Unit 3 Vent - Gaseous Releases - Curles vs. Dose Max. Individual mrem per Noble Gas Dose (mrem) uCl/Sec Ratio Release Projection Release Rate (uCl/Sec)
W.B.
Skin W. B.
Skin /W. B.
Unit 3 FSAR and ER 14.2 0.16 0.29 1.1 (-2) 1.8 Design releases from Unit 3 FSAR Table 11.3-11 and Unit 3 ER Table 3.5-14:
14,141 C1/yr = 448 uCl/sec.
Expected releases from Table 11.3-1: 448 Ci/yr which equals 14.2 uCl/sec.
Maximum value of mrem / year per uC1/sec is for 1980 for Units 1 and 2. Since the average X/Q's are less for Unit 3 than for Unit 2, a conservative estimate for Unit 3 would be to assume its value would be the same as for Unit 2.
These values for whole body doses are:
Unit 1: 6.0 x 10-4 mrem /yr. per uCi/sec Unit 2: 2.3 x 10-3 mrem /yr. per uC1/Sec Unit 3: 2.3 x 10-3 mrem /yr per uCi/Sec.
Rev.1 The 10CFR20 limit is 500 mrem to the whole body and 3000 mrem to the skin.
Since the skin dose has never been as much a six times the whole body dose for Unit 1 or Unit 2 releases, we can use the 500 mrem as the limiting dose.
Therefore, the release rate limits would be:
Unit 1: 500/5.3 x 10-4 = 790,000 uCi/sec.
Unit 2: 500/2.3 x 10-3 = 217,000 uCl/sec.
Unit 3: 500/2.3 x 10-3 = 217,000 uCi/sec.
However,10CFR20 is a site limit, therefore the limit is:
Q1
+
O2
+
Q3 6
1 790,000 217,000 217,000
- where, Q1 = noble gas release rate from MP1 stack (uCl/sec)
Q2 = noble gas release rate from MP2 vent (uCl/sec)
Q3 = noble gas release rate from MP3 vent (uCl/sec)
Justification for Above Method The above method of determining instantaneous release rates will ensure compliance with 10CFR20 for the following reasons:
1.
The doses presented for Unit I were calculated using the EPA AIREM code, which uses a finite cloud model similar to that in Reg. Guide 1.109. This code has compared very favorable with data actually measured at the critical site boundary with a pressurized ion chamber.
Plant related quarterly doses measured by the ion chamber were calculated using a model developed by ERDA's Health and Safety Lab. These doses have always been within 30% of those calculated by AIREM. The average difference has been 14%, with the AIREM code calculating the higher dose. Thus, we are ensured that the AIREM code yields reasonable, if not slightly' conservative, estimates of the maximum individual whole body dose.
2.
The doses presented for Unit 2 were calculated usIng the NRC GASPAR code which uses the methodology of Reg. Guide 1.109.
3.
The dose per curie release can be seen from the tables not to vary significantly from one quarter to the next.
Unit 1: Minimum Value - 3.6 x 10-6 mrem /qtr. per uCl/sec Average Value - 1.0 x 10-4 Maximum Value - 3.0 x 10-4 mrem /qtr. per mrem
/qtr per uCl/sec Unit 2: Minimum Value - 8.8 x 10-5 mrem /qtr. per uCi/sec Average Value - 5.2 x 10-4 Maximum Value - 2.5 x 10-3 mrem /qtr. per mrem
/qtr. per uCl/sec Rev.1 It can be seen that the maximum value observed is only a factor of 3 greater than the average value even though there have been sig/or nificant changes in the' isotopic compositions of the releases and the meteorological frequencies.
The isotopic changes include significant operational changes such as:
a.
Operation with and without the recombiner-charcoal delay system on the Unit 1 off-gas.
b.
Period when a unit was down the entire quarter for refueling.
c.
Quarters with many MP2 containment purges and quarters with no purges.
d.
Quarters with relatively high and relatively low fuel leakage from MPl.
Thus, the dose per curie released is not that sensitive to operational changes such that a gross curie release ratio can be used. We have been conservative in taking the worst annual ratio abserved.
4.
It should also be recognized that there is a great deal of conservatism between this method and the actual requirements of 10CFR20 for the
~
following reasons:
a.
10CFR20 states that release rates may be averaged over a year, however we are using this as an instantaneous release rate limit.
b.
10CFR20 limits are gound level concentration limits, which for elevated releases from the Units 1 stack would be less restrictive than the use of the elevated finite cloud model as used here.
5.
It must also be recognized that the type of empircal method given above is the only practical operational method. The use of a method similar to that given in NUREG-0133 would be an operational nightmare, would be next to impossible to implement and could yield allowable release rates many times that given above.
For example, releases from the Unit i stack could include any of the following releases:
MP1 ventilation from radiological areas MP1 off-gass release from the off-gas treatment system MP1 off-gas releases via the 30 minute holdup pipe MP1 mechanical vacuum pump MP1 gland seal condenser MP2 waste gas tank discharge MP2 containment purges MP2 ventilation from radiological areas MP2 condenser air ejector MP2 mechanical vacuum pump 9
7-Rev.1 MP3 ventilation from radiological areas MP3 condenser air ejector MP3 reactor plant gaseous vents MP3 radioactive gaseous waste system MP3 containment vacuum pump MP3 reactor plant aerated vents MP3 steam generator blowdown tank vent These sources may exist in any possible combination and each has its own particular, but changing, nuclide mixtures. Thus, the ratio of nuclides being released is a constantly changing parameter.
It is impractical to recalculate a stack release rate based on isotope specific dose conversion factors each time a source stream is initiated or terminated or a new isotopic analysis is performed on any of the source streams. This could require 4 or 5 recalculations and monitor set point changes each day. The plant could not operate in this manner.
It would als be unnecessarily restrictive to assume the worst possible mixture and use that as the limit for all situations. The only practical solution is to use a conservatively determined empirical method as given above.
Rev.1 3.
Section D.1.b -Iodine. Particulate and Other Limits a.
Iodine Iodine Release vs. Dose - Unit 1 Thyroid Curies Dose Year Quarter I-131 mrem mrem /Cl 1976 1
0.58 0.6 1.0 2
0.75.
3.8 5.1 3
0.58 4.9 8.4 4
0.29 0.6 2.1 1-4 2.20 9.9 4.5 1977 1
0.39 0.3 0.8 2
0.59 1.2 2.0 3
1.57 5.4 3.4 4
2.1 4.6 2.2 1-4 4.65 11.5 2.5
~1978 1
1.70 8.7 5.1 2
1.15 3.1 2.7 3
0.18 0.6 3.3 4
0.16 0.3 1.9 l-4 3.19 12.7 4.0 1979 1
0.21 0.01 0.05 2
0.10 0.60 6.3 3
0.04 0.44-10.2 4
0.06 0.004 0.07 1-4 0.41 1.05 2.6 1980 1
0.021 0.004 0.19 2
0.048 0.32 6.7 3
0.111' O.59 5.3 4
0.034 0.002 0.06 1-4 0.214 0.916 4.3 1981 1
2.4 (-5) 1.9 (-5) 0.79 2
0.001 0.004 4.0 3
0.042 0.50 11.9 4
0.032 0.002 0.06 1-4 0.075 0.51 6.8 1982 1
0.032 0.002 0.06 2
0.027 0.23 8.5 3
0.038 0.52 13.7 4
0.002 1.2 (-4) 0.05 1-4 0.099 0.752 7.6 I
Rev.1 Iodine Release vs. Dose - Unit 1 Thyroid Curies Dose Year Quarter I-131 mrem mrem /Ci 1983 1
0.006 2.3 (-4) 0.04 2
0.007 0.054 7.7 3
0.010 0.10 10.0 4
0.007 5.7 (-4) 0.08 1-4 0.030 0.155 5.2 Iodine Release vs. Dose - Unit 2 Curies Dose Year Quarter I-131 mrem mrem /Ci 1976 1
3.3 (-3) 0.015 4.5 2
4.0 (-3) 0.076 19.0 3
1.8 (-3) 0.077 43.7 4
4.2 (-4) 0.023 54.8 1-4 9.5 (-3) 0.191 20.1 1977 1
2.6 (-4) 0.010 38.5 2
1.8 (-3) 0.047 26.1 3
6.9 (-4) 0.037 53.6 4
2.5 (-3) 0.064 25.6 1-4 5.2 (-3) 0.158 30.4 1978 1
6.9 (-4) 0.024 34.8 2
1.0 (-3) 0.051 51.0 3
5.7 (-3) 0.52 91.2 4
6.7 (-5) 0.017 253.8 1-4 7.5 (-3) 0.612 81.6 1979 1
1.2 (-2) 0.004 0.3 2
7.4 (-4) 0.054 73.0 3
9.1 (-4) 0.16 175.8 4
1.2 (-3) 0.006 6.0 1-4 1.5 (-2) 0.22 14.9 1980 1
6.4 (-4) 0.003 4.7 2
2.1 (-3) 0.21 80.8 3
3.2(-3) 0.30 93.8 4
3.3 (-4) 0.094 284.8 1-4 6.3 (-3) 0.61 96.8 1981 1
4.6 (-4) 0.007 15.2 2
7.8 (-4) 0.13 166.7 3
3.4 (-4) 0.041 120.6 4
1.0 (-1) 0.093 0.9 1-4 1.0 (-1) 0.27 2.7 o
7 Rev.1 Iodine Release vs. Dose - Unit 2 Curles Dose Year Quarter I-131 mrem mrem /Ci
-1982 1
4.8 (-3) 0.009 1.9 2
1.1 (-2) 0.677 61.5 3
3.2 (-2) 2.81 87.8 4
3.7 (-3) 0.022
. 2.5 1-4 5.7 (-2) 3.52 61.8 1983 1
1.1 (-2) 0.009 0.8 1
2 1.1 (-2) 0.83 75.5 3
1.3 (-3) 0.17 130.8 4
9.5 (-5) 0.003 31.6 1-4 2.3 (-2) 1.01 43.9 Iodine Release vs. Dose - Unit 3 Curles Release Projection
- I-131/ year mrem /yr mrem / Curie Unit 3 FSAR 0.065 3.6
-55.4
- Expected releases from Unit 3 FSAR Table 11.3-l and from Unit 3 ER Tr.ble 3.5-14.
/
Maximum Valhe for MP1 is for 1982 = 7.6 mrem /Cl I-131 Maximum Value for MP2 is for 1980 = 96.8 mrem /CiI-131 Since D/Q's for Unit 2 and Unit 3 are equal (See NRC Draf t Environmental' Statement for Unit 3) this value should be approximately equal to Unit 2's value.
~
Therefore, the Maximum Value for MP3 = 96.8 mrem /Ci1-131.
Lin$it is 15000 mrem /yr. to the thyroid E
' MP1 allowable release rate
= 1500 mrem /7.6 mrem x 106 uC1/Cl x 3.17 x 10-8 yr/sec = 6.26 uCl/sec MP2 and MP3 allowable release rate
= 1500 mrem /96.8 mrem x 106 x 3.17 x 10-8 = 0.49 uCl/sec Rev.I
~
Since' this is a site limit, the allowable release rate for I-131 is:
QIl ' + ' QI2 - + QI3 4,
1 6.26 0.49 0.49 where QIl = Release rate of I-131 from MP1 Stack (uCl/sec)
O
- 7..
QI2 = Release rate of I-131 from MP2 Vent (uC1/sec)
Q13 = Release rate of I-131 from MP3 Vent (uCi/sec)
- rk j.
b.
Particulates with Half Lives Greater Than 8 Days i
[,l
<f'
- Particulate Releases vs. Dose - Unit 1
'{
Total Curves Max. Organ Max. Organ Year Quarter Particulates Ex. Thyroid Dose mrem /Ci 1976 1
0.040 Bone 7.9 (-3) 0.20 2
0.043 Bone 2.1 (-2) 0.49 3
0.051 Bone 1.7 (-2) 0.33 4
0.014 Bone 1.1 (-2) 0.79 l-4 0.148 5.7 (-2) 0.39 1977 1
0.009 Bone 3.2 (-3) 0.36 2
0.014 Liver 4.3 (-3) 0.31 3
0.075 Bone 1.8 (-2) 0.24 4
0.103 Bone 5.0 (-2) 0.49 l-4 0.201 7.6 (-2) 0.38 l
1978 1
0.156 Bone 1.6 (-1) 1.02 i
2 0.963 Bone 9.5 (-2) 0.10 3
0.131 Bone 2.7 (-2) 0.21 4
0.105 Bone 2.8 (-2) 0.27 1-4 1.355 3.1 (-1) 0.23 1979 1
0.083 Bone 3.4 (-2) 0.41 2
0.038 Bone 3.5 (-3) 0.09 i
3 0.031 Bone 1.2 (-2) 0.39 i
4 0.037 Bone 1.1 (-2) 0.30 1-4 0.189 6.1 (-2) 0.32 q
>1980 1
0.028 Bone 1.6 (-2) 0.57 2
0.020 Bone 5.1 (-3) 0.26 i
3 0.063 Bone 3.0 (-2) 0.48 4
0.008 Bone 1.2 (-2) 1.50 1-4 0.119 6.3 (-2) 0.53
- -,., ~,
.,.,-,c
,.,+.,----.n
-,----n--,,,.,.,-n-e,.,.,
,,.,.,,,,_,_,,_,,,,,,,,,-~,nw_,,.,,
--n.,_n-,-c--w.--
s1 Rev.1 i
a Total Curves Max. Organ Max. Organ Year Quarter Particulates Ex. Thyroid Dose mrem /Cl 1981 1
0.002 Bone 1.2(-3) 0.60 2
0,00E Bone 1.7(-3) 0.21 3,.
0.24 Bone 6.3(-3) 0.26 4L 0.039 Bone 9.5(-2) 2.44
("
1-4 0.073 1.0(-1) 1.37 e' ;
f 1982 1
0,038 Bone 1.1(-2) 0.29 2
0.033 Bone 1.0(-2) 0.30 3
0.031 Bone 7.7(-3) 0.25 4
0.009 Bone 1.3(-3) 0.14
(",
.1-4 0.111 3.0(-2) 0.27
- 3 1983 1
'0'.007 Bone 4.4(-4) 0.06 O.006 Bone 8.2(-4) 0.14 2
.0.010 Bone 1.4(-3) 0.14 3
4
-0.010 Bone 4.0(-3) 0.40
,y-1-4 0.033 6.7(-3) 0.20 Particulate Releases vs. Dose - Unit 2 h
Total Curies Max. Organ Max. Organ Year Quarter Particulates Ex. Thyroid Dose mrem /Ci
/
,.. o\\
1976 1
3.2(-5)
Lung 3.3(-4) 10.2 7o 2
3.6(-5)
GI-Tract 5.4(-5) 1.5
! u 3
1.2(-5)
Bone 3.1(-4) 25.8 4
1.8(-4)
Bone 6.3(-4) 3.5 1-4 2.6(-4) 1.3(-3) 5.1 1977 1
1.6(-4)
Liver 1.0(-3) 6.5 2/
4.1(-7)
Bone 1.9(-4) 463.4*
'/ 3 1.3(-5)
GI-Tract 2.9(-5) 2.2 4
2.2(-4)
GI-Tract 7.1(-4) 3.2
'1-4 3.9(-4) 1.9(-3) 4.9 1978 1
2.5(-4)
GI Tract 8.9(-4) 3.6 2
4.1(-5)
Bone 1.8(-3) 44.0 3
1.0(-4)
Bone 2.0(-3) 20.1 4
6.4(-5)
Bone 5.5(-4) 8.6 1-4 4A(-4) 5.2(-3) 11.4
- Outlier 1 -' ;
l, t
-l
c.
Rev.1 Total Curies Max. Organ Max. Organ Year Quarter Particulates Ex. Thyroid Dose mrem /Cl 1979 '
1 9.8(-5)
Bone 1.5(-4) 1.5 2
1.3(-4)
Bone 4.6(-4) 3.5 3
9.4(-5)
Bone 8.5(-4) 9.1 4
5.5(-5)
Lung 1.8(-5) 0.3 1-4 3.8(-4) -
1.5(-3) 3.9 1980 1
5.4(-5)
Lung 1.3(-3) 0.24 2
6.9(-5)
Bone 5.6(-4) 8.2 3
7.9(-5)
Bone 7.6(-5) 1.0 4
4.0(-5)
Lung 8.9(-5) 2.2 1-4 2.4(-4) 7.4(-4) 3.1 1981 1
4.4(-5)
Lung 2.2(-5) 0.5 2
5.3(-5)
GI-Tract 1.7(-4) 3.2 3
3.2(-5)
Bone 8.8(-5) 2.8 4
3.6(-3)
GI-Tract 1.9(-5) 0.5 1-4' l.7(-4) 3.0(-4) 1.8 1982 1
3.5(-4)
Lung 1.2(-4) 0.3 2
5.4(-5)
Bone 1.0(-4) 1.9 3
1.7(-4)
Bone 1.4(-3) 8.1 4
3.6(-4)
Lung 3.0(-5) 0.08 1-4 9.3(-4) 1.7(-3) 1.8 1983 1
3.4(-4)
Bone 7.4(-6) 0.02 2
1.5(-4)
Bone 3.1(-3) 20.7 3
5.8(-5)
Bone 1.l(-3) 19.0 4
5.4(-5)
Lung 1.4(-5) 0.3 1-4 6.0(-4) 4.2(-3) 7.0 Particulate Releases vs. Dose - Unit 3 Maximum Total Organ Particulate Maximum Organ Dose Release Projection
- Curies Excluding Thyroid (mrem) mrem /Ci Unit 3 FSAR 0.16 Liver *
- 3.6 22.5 Expected releases - from Unit 3 FSAR Table 11.3-1 and from Unit 3 ER Table 3.5-14.
From Unit 3 ER Lee 5.2-10 (Note: some of the liver dose may be from H-3, however the bone dose is 3.2 mrem, all of which should be due to particulates).
Maximum Value for MP1 is for 1981 = 1.37 mrem /Ci Rev.1 Maximum Value for MP2 is for 1976 = 11.4 mrem /Cl Limit is 1500 mrem /yr to the maximum organ MP1 allowable release rate
= 1500 mrem /l.37 mrem /Cl x 106 uCl/Cl x 3.17 x 10-8 yr/sec = 35 uCl/sec MP2 allowable release rate
= 1500/11.4 x 106 x 3.17 x 10-8 = 4.2 uCl/sec MP3 allowabe release rate 6
= 1500/22.5 x 10 x 3.17 x 10-8 = 2.1 uCi/sec Since this is a site limit, the allowable release rate for particulates is:
Q3 6
1 Q1 Q2
+
+
35 4.2 2.1 where Release rate of total particulates with half lives greater than 8 days Q1
=
from the MP1 Stack (uCi/sec)
Q2 Release rate of total particulates with half lives greater than 8 days
=
from the MP2 Stack (uCi/sec)
Q3 Release rate of total particulates with half lives greater than 8 days
=
from the MP3 Stack (uCi/sec)
Rev.I c.
Tritium Unit 1 Tritium Releases - Curies vs. Dose Dose (mrem) Due Year Quarter Curies to Tritium mrem /Cl 1976 1
3.71 2.5(-5) 6.7(-6) 2 1.47 8.1(-6) 5.5(-6) 3' i1.4 8.2(-5) 7.2(-6) 4 12.1' 6.2(-5) 5.l(-6) 1-4 28.7 1.8(-4) 6.3(-6) 1977 1
7.17 3.2(-5) 4.5(-6) 2 9.24 7.5(-5) 8.l(-6) 3 19.3 1.8(-4) 9.4(-6) 4 29.5 1.9(-4) 6.3(-6) 1-4 65.2 4.8(-4) 7.4(-6) 1978 1
16.8 1.7(-4) 1.0(-5) 2 7.68 8.6(-5) 1.l(-5) 3 13.1 1.l(-4) 8.5(-6) 4 11.1 1.7(-4) 1.5(-5) 1-4 48.7 5.4(-4) 1.1(-5) 1978 1
14.1 4.4(-6) 3.1(-7) 2 11.8 7.8(-4) 6.6(-5) 3 24.2 2.3(-3) 9.5(-5) 4 9.22 2.8(-6) 3.0(-7) 1-4 59.3 3.l(-3) 5.2(-5) 1980 1
15.2 7.9(-6) 5.2(-7) 2 11.3 6.7(-4) 5.9(-5) 3 27.2 8.l(-4) 3.0(-5) 4 41.8 7.l(-4) 1.7(-5) 1-4 95.5 2.2(-3) 2.3(-5) 1981 1
9.96*
2 26.9 1.0(-4) 3.7(-6) 3 26.9*
4 30.9*
1-4 26.9 1.0(-4) 3.7(-6) 1982 1
18.6 6.0(-6) 3.2(-7) 2 11.6 1.2(-3) 1.0(-4) 3 12.5 8.2(-4) 6.6(-5) 4 11.1 1.8(-6) 1.6(-7) 1-4 53.8 2.0(-3) 3.8(-5) n
-l8-e
Rev.1 Dose (mrem) Due Year Quarter Curies to Tritium mrem /Ci 1983 1
15.6 1.8(-6) 1.2(-7) 2 17.0 5.l(-4) 3.0(-5) 3 20.7 1.2(-3) 5.8(-5) 4 22.6 6.9(-6) 3.1(-7) l-4 75.9 1.7(-3) 2.3(-5)
- Note:
These were, inadervertently left out of the GASPAR runs for these quarters (dose consequence is insignificant), therefore total is for 2nd
. quarter only.
Unit 2 Tritium Releases - Curies vs. Dose Dose (mrem) Due Year Quarter Curies to Tritium mrem /Cl 1976 1
0.16 2.6(-5) 1.6(-4) 2 2.15 1.8(-3) 8.4(-4) 3 4.34 1.7(-3) 3.9(-4) 4 1.79 6.2(-4) 3.5(-4) 1-4 8.4 4.l(-3) 4.9(-4) 1977 1
2 3
2.80 3.4(-3) 1.2(-3) 4 1.89 1.3(-3) 7.l(-4) 1.4 4.69 4.7(-3) 1.0(-3) 1978 1
2 3
16.9 2.6(-2) 1.5(-3) i 22.7 1.2(-2) 5.5(-4) 1-4 39.6 3.8(-2) 9.6(-4) 1979 1
20.5 7.3(-3) 3.6(-4) 2 12.4 1.l(-2) 8.9(-4) 3 57.4 7.1(-2) 1.2(-3) 4 13.5 2.l(-3) 1.5(-4) 1-4 103.8 9.l(-2) 8.8(-4) 1980 1
9.8 9.0(-4) 9.2(-5) 2 10.8 1.3(-2) 1.2(-3) 3 103.0 3.5(-2) 3.4(-4) 4 725.0 3.8(-1) 5.2(-4) 1-4 848.6 4.3(-1) 5.l(-4) l
[
i
Rev.1 Dose (mrem) Due Year Quarter Curies to Tritium mrem /Ci 1981 1
39.4 6.2(-3) 1.6(-4) 2 53.4 7.0(-2) 1.3(-3) 3 23.7 1.9(-2) 8.0(-4) 4 22.3 6.2(-3) 2.8(-4) 1-4 138.3 1.0(-1) 7.3(-4) 1982 1
13.8 1.6(-3) 1.2(-4) 2 9.1 1.0(-2) 1.l(-3) 3 20.8 3.l(-2) 1.5(-3) 4 24.1 4.l(-3) 1.7(-4) 1-4 67.8 4.7(-2) 6.9(-4) 1983 1
34.4 1.6(-3) 4.7(-5) 2 50.5 4.6(-2) 9.1(-4) 3 21.7 2.9(-2) 1.3(-3) 4 30.3 2.8(-3) 9.2(-5) 1-4 136.9 7.9(-2) 5.8(-4)
Unit 3 Tritium Releases - Curies vs. Dose The Unit 3 Environmental Report (ER) does not include an isotopic breakdown of the dose consequences. Therefore this cannot be calculated from the FSAR or ER. However, since Unit 2 has a similar release point as Unit 3, the Unit 2 value can be used here.
Maximum value for MP1 is for 1979 = 5.2 x 10-5 mrem / curie - H-3 Maximum Value for MP2 is for 1978 = 1.0 x 10-3 mrem / curie - H-3 Limit is 1500 mrem /yr to the maximum organ MP1 allowable release rate
= (1500 mrem /5.2 x 10-5 mrem /Ci) x 106 uCi/Ci x 3.17 x 10-8 yr/sec = 9.1 x 105 uCi/sec MP2 and MP3 allowable release rates
= (1500/1.0 x 10-3) x 106 x 3.17 x 10-8 = 4.0 x 10 uCi/sec 4
Since this is a site limit, the allowable release rate for tritium is:
QT1 QT2 + QT3
+
61 9.1x105 4.0x104 4x104 -,_ __
Rsv. I where QT1= Release rate of tritium from MP1 Stack -(uCi/sec)
QT2 = Release rate of tritium from MP2 Stack -(uCi/sec)
QT3 = Release rate of tritium from M3 Stack -(uCi/sec)
Since exposure to tritium produces whole body exposure, the release rate fraction for tritium must be added to the release rate for I-131 and particulates.
The combined release rate limits then are:
1-131 and tritium Q11 + QI2 + QI3 + QT1
+ QT2 + QT3 f
1 6.26 0.49 0.49 9.1 x 105 4.0x104 4.0x104 Particulates and tritium Q3T1 + QT2 +
QT3 dI Q1 + Q2 Q3
+
+
35 4.2 2.1 9.1x105 4.0x104 4.0x104 4.
Section D.2.a - Noble Gas - Ouarterly Air Dose Method 1 (1) Unit i From the table in Section D.I.a of this Appendix 4.the maximum quarterly value of mrem /qtr. per uCi/sec is 3.0 x 10 This value is mrem to the whole body.
To convert to mrad air dose we must multiply by 2 because there is a factor of 0.7 to go from mrad to whole body mrem (The Distribution of Absorbed Dose Rates in Humans From Exposure to Environmental Gamma Rays, Health Physics, January 1976) and also a factor of 0.7 for building shielding and occupancy (Regulatory Guide 1.109, Rev.1, Pg. 43) used to originally calculate the whole body results. Therefore, the conversion factor for the air dose is:
6.0 x 10-4 mrad /qtr. per uCi/sec or 6.0 x 10-4 mrad-sec x 106 uCi/Ci x 1.26 x 10-7 qtr./sec qtr. - uCi
= 7.6 x 10-5 mrad /Ci This is the gamma air dose at the critical location. Since the critical location is the site boundary and is only 0.5 miles from a 375 foot stack, the beta air dose at the critical location is near zero as the dose is from the overhead finite cloud (see earlier discussion in Section D.I.a).
The
=
Rsv.1-beta air dose at the critical location has always been less than 0.01 times the gamma dose. Thus, the beta dose can be recorded as:
less than 7.6 x 10-7 mrad /Cl (2) Unit 2 Likewise, for Unit 2 from Section D.I.a, the maximum quarterly value of mrem /qtr. per uCi/sec is 2.5 x 10-3 Converting to mrad /Cl we have 2.5 x 10-3 x 2 x 106 x 1.26 x 10-7 = 6.3 x 10-4 mrad /Cl This is the gamma air dose. The following is the ratio of the beta air dose to the gamma air dose at the critical location as calculated by the GASPAR code:
Ratio 1976 1977 1978 1979 1980 1st qtr.
2.9 3.1 6.9 3.1 2.8 2nd qtr.
2.9 3.0 2.8 3.3 2.7 3rd qtr.
3.5 2.5 3.0 3.1 1.7 4th qtr.
3.0 3.0 3.0 3.0 1.8 1981 1982 1983 ist qtr.
2.5 1.3 2.6 2nd qtr.
2.4 2.3 2.7 3rd qtr.
2.2 2.2 4th qtr.
2.2 2.4 The average ratio = 2.8 Beta air dose = 1.8 x 10-3 mrad /Ci
- No continuous releases these quarters (3) ' Unit 3 Again, as mentioned in Section D.1.a, since the average X/Q's are less for Unit 3 than for Unit 2, a conservative estimate for Unit 3 would be to assume its values would be the same as for Unit 2.
Rev.1 5.
Section D.2.b Unit 1 Finite Cloud Code Year Quarter Xe-138 Due to Xe-138 Dose / Curie 1976 1
2.4 (+4) 0.29 1.2 (-5) 2 3.9 (+4) 0.61 1.6 (-5) 3 3.3 (+4) 0.52 1.6 (-5) 4 7.5 (+3) 0.08 1.0 (-5) 1977 1
2.1 (+4) 0.19 8.9 (-6) 2 1.9 (+4) 0.22 1.2 (-5) 3 3.4 (+4) 0.52 1.5 (-5)
.4 3.4 (+4) 0.22 6.4 (-6) 1978 1
6.5 (+4) 0.31 4.8 (-6) 2 4.7 (+4) 0.57 1.2 (-5) 3 9.0 (+2) 0.019 2.1 (-5) 4 1.6 (+3) 0.015 9.2 (-6) 1979 1
1.98 (+3) 0.010 5.1 (-6) 2 8.42 (+2) 0.013 1.5 (-5) 3 1.05 (+3) 0.028 2.7 (-5) 4 1.06 (+3) 0.019 1.8 (-5) 1980 1
1.09 (+3) 0.011 1.0 (-5) 2 5.42 (+2) 0.013 2.4 (-5) 3 2.43 (+3) 0.052 2.1 (-5) 4 3.54 (+1) 4.0 (-4) 1.1 (-5) 1981 1
2 1.41 (+2) 2.7 (-3) 1.9 (-5) 3 3.77 (+3) 0.033 8.8 (-6) 4 8.48 (+2) 0.004 4.7 (-6) 1982 1
2.40 (+2) 2.3 (-3) 9.6 (-6) 2 3.59 (+1) 6.1 (-4) 1.7 (-5) 3 1.09 (+3) 0.012 1.1 (-5) 4 1983 1
8.89 (+1) 2.8 (-4) 3.1 (-6) 2 4.52 (+2) 7.8 (-3) 1.7 (-5) 3 3.55 (+2) 7.7 (-3) 2.2 (-5) 4 2.11 (+2) 2.1 (-3) 1.0 (-5).. - -
Rev.1 The above table normalizes the dose for each quarter to the same location from a particular radionuclide. Thus, the only variance in dose per curie should be due to the quarterly meteorology. Using this method, we can determine that the worst case meteorology occurred during the 3rd quarter-1979. Thus, the 3rd quarter joint frequencies should be used as input for the AIREM code.
6.
Section D.3 a.
Unit 1 The only significant contributor to the thyroid dose is I-131. If the particulates were significant a different organ would be limiting.
Tritium releases have never contributed more than 1% of the doses from Unit 1.
Thus,.to determine the quarterly thyroid dose we can use the maximum quarterly _value observed of mrem / curie of I-131 as presented in Section 3 of this appendix.
This maximum value is :
13.7 mrem / curie - I-131 The critical organ dose due to particulates with half lives greater than 8 days can also be determined from the maximum quarterly dose per cure given in Section 3 of this appendix.
This maximum value is:
2.4 mrem / curie of particulates b.
Unit 2 For Unit 2, we must consider tritium in both the calculation of the thyroid and other organ doses. The dose factor for all organs for tritium is the same.
l k
The maximum values of mrem per curie as presented in Section 3 of
('
the appendix are as follows:
l For I-131, 285 mrem /Ci - I-131 For Particulates,44 mrem /Ci-Particulates For Tritium,1.5 x 10-3 mrem /Ci-H-3 c.
Unit 3 i
l As previously discussed, for conservatism, assume the conversion factors for Unit 3 are the same as for Unit 2.
l l t l
L
Rev.1 APPENDIX E GASEOUS DOSE CALCULATIONS - GASPAR -
The GASPAR code was written by the NRC to compute doses from gaseous releases using the models given in Regulatory Guide 1.109. The revision date of the code which was purchased is February 20,1976. The only changes made to the code were to change the dose factors and inhalation rates from those given in Rev. O of Reg.~ Guide 1.109 to those in Rev.1.
For calculating the maximum individual dose at Millstone, the following options and parameters are used:
1.
Real time meteorology using a X/Q, D/Q model which incorporates the methodology of Reg. Guide 1.111. Meteorology is determined separately for continuous releases and batch releases and for elevated releases and vent releases.
2.
100% of vegetation grown locally,76% of vegetation intake from garden.
3.
Animals on pasture April through December - 100% pasture intake.
3 4.
Air water concentration equals 8 g/m.
5.
Maximum individual dose calculations are performed at the land location with maximum decayed X/Q, at the nearest vegetable garden (assumed to be nearest residence) with the maximum D/Q, and at the cow and goat f arms with maximum D/Q's.
Rev.1 APPENDIX F GASEOUS DOSE CALCULATIONS - AIREM The AIREM code was written by the EPA to compute doses from atmospheric emissions of radionuclides. The code is composed of two basic parts - a diffusion calculation and a dose calculation.
For the maximum individual dose at Millstone, cloud gamma doses are calculated using dose tables from a model which considers the finite extent of the cloud in the vertical direction. Beta doses are calculated assuming semi-infinite cloud concentrations which are based upon a standard sector averaged diffusion equation.
l 1
Rev.1 APPENDIX G ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS
.The following lists _the environmental sampling locations and the types of samples obtained at each location. Sampling locations are also shown on Figures G-1, G-2, and G-3.
l Direction &
Location Distance From Number Name Release Point **
Sample Types I-I*
Onsite - Old Millstone Rd.
0.6 Mi. - NNW TLD, Air Particulate, Iodine, Vegetation 2-I Onsite - Weather Shack 0.3 Mi. - SSE TLD, Air Particulate, Iodine 3-I Onsite - Bird Sanctuary 0.3 Mi - NE TLD, Air Particulate, Iodine 4-I Onsite - Albacore Drive 1.0 Mi. - N TLD, Air Particulate, Iodine 5-I Floating Barge 0.2 Mi. - SSE TLD 6-I Quarry Discharge 0.3 Mi. - SSE TLD 7-I Fox Island 0.3 Mi. - ESE TLD 8-I Environmental Lab 0.3 Mi. - SE TLD 9-I Bay Point Beach 0.4 Mi. - W TLD i
10-I Pleasure Beach 1.4 Mi. - E TLD, Air Particulate, Iodine 11-I New London Country Club 1.6 Mi. - ENE TLD, Air Particulate, Iodine 12-C Fisher's Island, NY 8.7 Mi. - ESE TLD 13-C Mystic, CT 12.0 Mi. - ENE TLD 14-C Ledyard, CT 12.0 Mi. - NE TLD 15-C Montville, CT 14.0 Mi. - N TLD, Air Particulate, Iodine 16-C Old Lyme, CT 8.5 Mi. - W TLD 17-I Site Boundary 0.5 Mi. - NE Vegetation 18-I New London Country Club 1.6 Mi. - ENE Vegetation 19-I Cow Location #1 6.0 Mi. - N Milk 20-I Cow Location #2 9.5 Mi. - NW Milk 21-1 Cow Location #3 -
11.5 Mi. - NE Milk 22-C Cow Location #4 16.0 Mi. - NNW Milk 23-I Goat Location #1 2.0 Mi. - ENE Milk 24-C Goat Location #2 14.0 Mi. - NE Milk 25-I Fruits & Vegetables Within 10 Miles Vegetation 26-C Fruits & Vegetables Byond 10 Miles Vegetation 27-I Niantic 1.7 Mi. - WNW TLD, Air Particulate, Iodine 28-I Two Tree Island 0.8 Mi. - SSE Mussels 29-I' Jordan Cove 0.4 Mi. - NNE Clams 30-C Golden Spur 4.7 Mi. - NNW Bottom Sediment 31-1 Niantic Shoals 1.8 Mi. - NW Bottom Sediment, Oysters 1.5 Mi. - NNW Mussels 32-1 Vicinity of Discharge Bottom Sediment Oysters, Lobster, Fish, Seawater 33-I Seaside Point 1.8 Mi. - ESE Bottom Sediment 34-1 Thames River Yacht Club 4.0 Mi, - ENE Bottom Sediment
.35-I Niantic Bay 0.3 M i. - W Lobster, Fish 36-I Black Point 3.0 Mi. - WSW Bottom Sediment, Oysters i L
7.-
Rev.1 Direction &
Location Distance From Number Name Release Point **
Sample Types 37-C Giant's Neck 3.5 Mi. - WSW Bottom Sediment, Oysters, Lobster, Seawater 38-I Waterford Shellfish Bed #1 1.5 Mi. - NNW Clams
- I = Indicator C - Control
- For terrestial locations, this is the MP1 stack, for aquatic it is the quarry cut.
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APPENDIX H METHODS FOR CALCULATING RELEASES FROM UNIT 3 "UNMONITORED" RELEASES - FOR SECTION D2 and D3 1.
Main Condenser Air Removal Mechanical Vacuum Pump Exhaust This system only operates during startup operation.
uCi of
- Grab Sample from*
! Condenser
- Grab sample from air Noble Gas ~ Air Ejection, uCi/ccj Volume, ccj ejector adjusted by monitor reading prior to shutdown and decay corrected from shutdown.
[
Iodines and-Mechanical Vacuum }[ Flow ratefrom Mech-}
' of(minutes ) [ units uCi of
, Grab Sample during conversion Particulates (Pump Exhaust, uCi/cgnical Pump) (operationj
((if necessary) 2.
Turbine Gland Sealing Systen Exhaust I r EjectorI I r EjectorI
[ Steam to Gland Seal I
Iminutes I uCi of Ai Ai 0*00l Noble Monitor Flow Rate Condenser of Gases (uCi/cc
) (cc/ min
]
(Steam to Main Condenser
)
(operation)
Io ines Generator
[l
) [ Steam to Gland \\ [DF for Gland
! minutes of uCi of Steam l
d and Blowdown carry-over Seal Condenser Seal Condenser operation (fraction * *;
(cc/ min.
(= 100
)
(
)
Parti-concen-culates tra tion
\\
/
uCi/cc
- carry-over fraction = 100 for Iodines and 1000 for particulates.