ML20206D107

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Rev 10 to ODCM for Hnp
ML20206D107
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 06/30/1997
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20206D089 List:
References
PROC-970630, NUDOCS 9905030302
Download: ML20206D107 (52)
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Text

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nam.u OFFSITE DOSE CALCULATION MANUAL FOR THE t

HADDAM NECK PLANT DOCKET NO. 50-213 I

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9905030302 990430 PDR R ADOCK 05000213 pg June 1997 wimwa Revision 10

6/27/97 Revision 10 NADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS SECTION PAGE NO, REV.NO. DAIE A. INTRODUCTION A-1 2 12/31/94 B. RESPONSIBILITIES B-1 2 12/31/94 C. LIQUID DOSE CALCULATIONS C.1 QUARTERLY DOSE CALCULATIONS

a. Whole Body Ciose C-1 2 12/31/94
b. Maximum Organ Dose C-1 2 12/31/94 C.2 ANNUAL DOSE CALCULATIONS
a. Whole Body Dose C-2 2 12/31/94
b. Maximum Organ Dose C-2 2 12/31/94 C.3 MONTHLY DOSE PROJECTIONS C-3 2 12/31/94 C-4 2 12/31/94 C.4 QUARTERLY DOSE CALCULATIONS FOR ANNUAL RADIOACTIVE EFFLUENT REPORT C-4 2 12/31/94 D. GASEOUS DOSE CALCULATIONS D.1 10CFR20 LIMITS (" INSTANTANEOUS *)
a. Noble Gas Release Rate Limit D-1 2 12/31/94
b. lodine & Particulate Release Rate Limit D2 3 4/15/95 D3 3 4/15/95 D.2 10CFR50 APPENDIX l- NOBLE GAS LIMITS

- a. Quarterly Air Dose Limit Due to Noble Gases D4 2 12/31/94 D-5 2 12/31/94

b. Annual Air Dose Limit Due to k Noble Gases D-5 2 12/31/94 o= = ooc T of C - 1

6/27/97 Revision 10

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HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Continued)

SECTION PAGE NO. REV. NO. DATE D.3 10CFR50 APPENDIX l-LODINE AND PARTICULATE DOSES

a. Quarterly Organ Dose Limit D-6 2 2/1/93 D-7 2 2/1/93
b. Annual Or9sn Dose Limit D-7 2 2/1!93 D.4 GASEOUS EFFLUENT MONTHLY DOSE PROJECTIONS
a. Gaseous Radwaste Treatment System D-8 1 1/1/90
b. Ventilation Releases D-8 1 1/1/90 D-9 2 12/31/94 D.5 QUARTERLY DOSE CALCULATIONS FOR ANNUAL RADIOACTIVE EFFLUENT REPORT D-9 2 12/31/94 D.6 COMPLIANCE WITH 40CFR190 LIMITS D9 2 12/31/94 E. LIQUID MONITOR SETPOINTS E.1 TEST TANK DISCHARGE LINE MONITOR E-1 3 6/27/97 E-2 2 6/27/97 E.2 STEAM GENERATOR BLOWDOWN MONITOR E-3 2 6/27/97 E.3 SERVICE WATER RADIATION MONITOR E-3 2 6/27/97 E4 0 6/27/97 F. GASEOUS MONITOR SETPOINTS F.1 STACK NOBLE GAS ACTIVITY MONITOR F-1 1 1/1/90 wxwooc T of C - 2

l 6/27/97 Revision 10

( HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES AND FIGURES l TABLE NO. TABLE NAME PAGE NO. REV.NO. DATE 1 DOSE FACTORS FOR NOBLE GASES D-10 1 1/1/90 2 DOSE FACTORS FOR IODINE &

PARTICULATES D-11 1 1/1/90 FIGURE NO. FIGURE NAME PAGE NO. REV NO. DATE G1 INNER TERRESTRIAL MONITORING STATIONS APP. G 3 4 5/30/97 G-2 AQUATIC AND WELL WATER SAMPLING STATIONS APP. G-4 2 5/30/97 G-3 ACCIDENT TLD SAMPLING I LOCATIONS APP.G 5 2 5/30/97 1

4 nexwooc T of C - 3

6/27/97 Revision 10

. _, NADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL ffffr$E/SluI REV.NO. DE APPENDIX A DERIVATION OF FACTORS FOR SECTION C.1.s 1 1/1/90 APPENDIX B DERIVATION OF FACTORS FOR SECTION C.1.b i 1/1/90 APPENDIX C LIQUID DOSE CALCULATIONS- LADTAP 1 1/1/90 ,

APPENDixD DERIVATION OF FACTORS FOR SECTION D.1 3 4/15/95 APPENDIX E GASEOUS DOSE CALCULATIONS-GASPAR 1 1/1/90 APPENDIX F DERIVATION OF FACTORS FOR SECTIONS D.2 & D.3 2 2/1/93 APPENDIX G ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS 6 5/30/97 APPENDIX H DERIVATION OF FACTORS FOR TABLE 2 1 1/1/90

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l noct e m T of C - 4

12/31/94 Revision 2 A. 94TRODUCTION

( -- The purpose of this manual is to provide the parameters and methods to be used in calculating offsite doses and effluent monitor setpoints at the Haddam Neck Plant.

Included are methods for determining maximum individual whole body and organ doses due to liquid and gaseous affluents to assure compliance with the dose limitations in the >

Technical Specifications. Also included are methods 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 Annual Radioactive Effluent Report. 5 Another section of this manual discusses the methods to be used in determining effluent monitor alarm / trip setpoints to be used to ensure compliance with the instantaneous .

release rate limits in the TechnicalSpecifications.

The bases for some of the factors used in this manual are included as appendices to this manual. Supplemental information on environmental sample locations is provided in an appendix.

This manual does not include surveillance procedures and forms required to document compliance with the surveillance requirements in the TechnicalSpecifications. All that is included here are the methods 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, Method 1, being the easiest but more conservative method. As long as releases remain low, one should be able to use Method f as a simple estimate of the dose. If release '

calculations approach the limit, however, more detailed and hence mnre realistic calculations may be used.

At any time, a more detailed calculation may be used in lieu of a simple calculation.

I A-1 oexw m I

I 12/31/94 R; vision 2

5. RESPONSIBILITIES All changes to this manual shall be reviewed by the Plant Operations Review Committee prior to implementation.

All changes and their rationale shall be documented in the subsequent Annual Radioactive EffluentReport. l It shall be the responsibility of the Station Vice President to ensure that this manual is used in performance of the surveillance requirements specified in the TechnicalSpecification.

D401XW.001 B-1 I

12/31/94 Revision 2 C. LIQUID DOSE CALCULATIONS C.1 Quarterly Dose Calculations

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a. Whole Body Dose (1) Method 1 TNs method may be used until the calculated total body dose exceeds 0.5 mrem for the calendar quarter.

E1921 Determine Cp which is the total curies of fission and activation products, excluding tritium and dissolved noble gases released during the calendar quarter.

Stan.2 Determine Cr which is the total curies of tritium released during the calendar quarter.

EitD 3 Determine Dow which is the quarterly dose to the whole body in mrem:

Dow = 5.4

  • C, + 1'10-5
  • C7 [See Appendix A]

1119 4. '

if Dow > 0.5 mrem, go to Method 2.

(2) Method 2 ,

if the calculated dose using Method 1 is greater than 0.5 mrem, use the methodology of NRC Regulatory Guide 1.109, Rev.1 to calculate the liquid doses. The use of this model and the input parameters discussed in Appendix C are given in Radiological Assessment Branch Procedure, Liquid Dose Calculations - LADTAP ll.

b. Maximum Oraan Dose (1) Method 1 This method to be used until the calculated dose to the maximum organ exceeds 2 millirem for the calendar quarter.

EltEl Determine Cr - as in C.1.a(1)- Step 1 1

D481XW.091 C1

12/31/94 RIvisi:n 2 AltiL2 De' ermine Cr - as in C.f.a(f)- Step 2 EltiL2 Determine Doo which is the quarterly dose to the maximum organ in mrom Doo = 8.0

  • C, + 1
  • 10-'
  • Cy [See Appendix B]

StenA If Doo > 2 mrem, go to Method 2 (2) Method 2 If the calculated dose using Method ? is greater than 2 mrem, use the methodology of NRC Regulatory Guide 1.109 Rev.1 to calculate the liquki doses. The use of this model and the input paramete.s are discussed in AppendixC and also given in Radiological Assessment Branch Procedure, Liquid Dose Calculations - LADTAP ll.

C.2 Annual Dose Calculations

a. Whole Body Dose Determine Dyw which is the dose to the whole body for the calendar year as follows:

Dyw - I Dow, where the sum is over the first quarter through the present quarter whole body doses The following should be used as Dow:

(f) If the detailed quarterly dose calculations required per Section C.4 for the Annual Radioactive Effluent Report are complete for any calendar l quarter, use thatiesult.

(2) If the detalled calculations are not complete for a particular quarter, use the results as determined in Section C.1.a.

(3) If Dyw > 3 mrem and any Dow determined as in Section C.f.a was not i calculated using Method 2 of that section, recalculate Dow using I Method 2.

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b. Maximum Oraan Dose Determine Dvo which is the dose to the maximum organ for the calendar year as foibws:

Dvo -I Doo The sum is over the first quarter through present quarter dose.

C-2 D481Xw.001 I ei lu

12/31/94 Revision 2 The following guidelines should be used:

(1) If the detailed quarterly dose calculations required per Section C.4 for i l ~'

the Annual Radioactive EMiuent Report are complete for any calendar l .\

quarter, use that result.

(2) If the detailed calculations are not complete for a particular quarter, use the results as determined in Section C.f.b.

(3) If different organs are the maximum for different quarters, they may be summed together and Dvo can be recorded as a less-than value as long as the value is less than 10 mram.

(4) If Dvo > 10 mrom and any value used in its determination was calculated as in Section C.f.b but not with Method 2, recalculate that value using Method 2.

C.3. Monthly Dose Projections This method ratios a previously calculated total body and maximum organ monthly dose based upon liquid release volumes, concentration, and fraction of release due to blowdown to project a monthly dose.

a. Monthly Doss Prolections to the Total Body and Maximum Oraan ESE1 Determine Duw which is the whole body dose from the previously i

completed month

  • as calculated per the method in Section C.f.a.

EER.2 Determine Duo which is the maximum organ dose from the previously completed month

  • as calculated per the methods in Section C.7.b.

i ERDJ '

Estimate Ri which equals the ratio of the total estimated volume of liquid batched to be released in the present month to the volume re; eased in the past month.

ERLi .

Estimate R which equals the ratio of the total estimated volume of  !

steam generator blowdown to be released in the present month to the volume releasedin the past month.

ERES Estimate F which equals the fraction of curies released last month i

coming from steam generator blowdown, i.e.:

4 i

,, curies from blowdown I curies from blowdown + curies from batch tanks 0481XW.001 i

12/31/94 Revisisn 2 SkRl

~ ~ ' Estimate R, which is the ratio of estimated secondary coolant activity for the present month to that for the past month.

IMDI Estimate R, which is the ratio of estimated primary coolant activity for the present month to that for the past month.

21811 Determine F, which is the factor to be applied to estimate ratio of final curie release if there are expected differences in treatment of liquid waste for the present month as opposed to the past month. NUREG-0017 or past experience should be used to determine the effect of each form of treatment. Set F,- 1 if there are no expected differences.

I18 9.2 Determine DL which is the estimated monthly whole body dose as follows:

DL = D. '(1 - F, ) R, R F, + F, R, R.,

B18R.19 DetermineDkwhich is the estimated monthly maximum organ dose as follows:

Dk = D '(1 - F, ) R, R, F, + F, R, R ,

  • 1f the past month is not typical of expected operations in the present month, go back to the last typical month. For example, if the plant was down for refueling the entire month of February and start-up is scheduled for March, use the last month of operation as the base month to estimate March's dose.

if the last typical month's doses were calculated using LADTAP 11 (or similar mGhtnAagy), also multiply last typical month's doses by Rs where Rs = last typical month's total dilution flow / estimated total dilution flow.

C.4. Qua[1grty Dona Calculations for Annual RM!sse*!ve Effluerii Rssort l Detailed quarterly dose calculations required for the Annual Radioact/ve Effluent Report shall be done using the NRC computer code LADTAP 11.

The use of this code and the input parameters are given in Radiological Assessment Branch Procedure, UqukiDose Calculations LADTAP ll.

D441XW.001 C-4

12/31/94 D. Revision 2 GASEOUS DOSE CALCULAMONS D.1. 10CFR20 Limits (" Instantaneous")

I ~~ a. Noble Gas Release Rate Limit UmitFor TotalBody:

0.39

  • 1.9 x 10
  • K
  • Qu < 500 mrem /yr Umit For Skin:

1.9 x 10'5

  • S
  • Qu < 3000 mrem /yr Where:

0.39 = gamma exposure rate finite cloud correction at 0.51 Km (nearest land site boundary) based upon 5-year joint frequency distribution average weighted stability class for 1975-1979 (See Appendix D).

5 1.9 x 10 - average of the quarterly average maximum X/0, sec/m' for a continuous mixed mode release (See Appendix D).

K = weighted average total body dose factor due to gamma emissions, mrem /yr per Cl/m*, as determined below.

S = weighted average skin dose factor due to beta and gamma emissions, mrem /yr per pCl/m*, as determined below.

Ou = release rate of noble gases in Ci/sec.

E.ltill Obtain results of the last analysis of the flashed gases from primary coolant, decay corrected to sample time. (In certain instances, e.g., high failed fuel fractions, the release rate may be based upon actual gas mixes present within the stack and not prompt flashed gas analyses. In these cases, the flashed gases analysis should only be calculated to determine the release rate limit for a prompt gas mixture release - Appendix D.)

3.18 9.2 For each noble gas radionuclide identified in Step f, determine Fi = fraction nuclide i is of the total noble gas activity.

E129 2 For each noble gas radionuclide identified in Step 1, determine K. (total body dose factor for noble gases) and Si (skin dose factor for noble gases) from Table 1.

Sten.4 l

DetermineK =I F; Kg i

D481XW.001 D1

10/15/95 l Revision 3 I i

ERS.E i- Determine S = I F, Sg i

ESE.1 Determine the release rate limit.

4 (pct /sec) < 500 ,,

0.39 x 1.9 x 104 x K 4 (pci/sec) < 3000 1.9 s 10*

  • S whicheveris lower.

d2.11 - See Appendix D forjustification of the method for determination of S and K (b) lodine and Particulate Release Rate Limit ,

Ng.it . See Appendix D for derivation of the following limits. All release rates are in pCi/sec.

(1) Method 1 The dose rate to the maximum organ will be less than 1500 mrom/yr provided:

(a) Release rate of l-131 + (2.4 x 10 x Release rate of I-133) + 8.5 4

x 10 x Release Rate of H 3 s 5 (b) Release rate of particulates + 8.2 x 104 x Release rate of H-3 <--

4.9 If limits are exceeded, go to Method 2.

(2) Mathgl.2 Above method assumes a conservative nuclide mix. If necessary, utilize the GASPAR code to determine the maximum organ dose. For the Special Locahon, enter 1.9 x 10* for the X/Os, 6.6 x 10* for the resident D/Q and 4.5 x 10* for the milk D/Q (or use actual X/Q and D/Q data for each criticallocation). Note that only the ventilation pathway needs consideration.

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  1. ^/15/95 R:visi n 3 INTENTIONALLY LEFT BLANK t~

t oeixwm, D3

r 12/31/94 Rsvisi:m 2 D.2 10CFR50 Annandir I- Noble r2== Limits

a. Quarterly Air Dose Limit Due to Noble Gases

(~ (1) Method 1 attal Determine Cu which equals the total curies from all sources of noble gases released during the calendar quarter.

2182.1 Determine Doao which is the quarterly air gamma dose (mrad):

DOAG = 9.8 x 10 *CN [See AppendixF)

Etta.I Determine Dans which is the quarterly air beta dose (mrad).

DQAB = 3.0 x10 *CN (See Appendix F)

E119 i If Dans exceeds 3 mrad, go to Method 2.

e (2) Method 2 This method to be used until the calculated gamma air dose exceeds 2.5 mrads or the beta air dose exceeds 5 mrads.

3189.1 Determine Ci which equals the total curies of each identified noble gas nuclide i released during the quarter from all sources, both continuous and batch.

Etta.1 Determine M which is the gamma air dose factor for each noble gas nuclide identified above. Values are given in Table f.

EttE.2 Determine N which is the beta air dose factor for each noble gas nuclide ,

identified above. Values are given in Table f.

i 1

E192i '

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Determine Doao which equals the quarterly air gamma dose (mrad):

D4 oneixw.oei

p 12/31/94 RGvision 2 DOAG = 2.7 x 104C*{(See g g M AppendixF)

(-- maa Determine Dans which equals the quarterly air beta dose (mrad):

1 Dg = 2.7 x 10 4 * { N gC;[See Appendix F]

I man.s if Dona > 2.5 mrad or Dona > 5 mrad, go to Method 3.

@) ninthod3 Use the GASPAR computer code to determine the critical site boundary air doses. For the Special Location, enter the following worst case quarterly average meteorology:

X/O = 3.2 x 10sec/m' D/Q = 1.1 x 10 m

If the calculated air dose exceeds one-half the Technical Specification limit, use real-time meteorology.

b. Annual Air Dose Limit Due to Noble rt..=.

Determine Dv4a and Dyas which equals the gamma air dose and beta air dose for the calendar year as follows:

Dyna = [ Dona and Dy4, = 1 Do ,

where the sum is over the first quarter through the present quarter doses.

The following should be used as Dora and Dore:

(f) If the detailed quarterly dose calculations required per Section D.5 for the Annual Radioactive 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 determined above in Section D.2.a.

p) If Dyxa > 10 mrad et Dyas > 20 mrad and any corresponding quarterly dose was not calculated using Method 3 of Section D.2.a., recalculate the quarterly dose using Method 3 If this could reduce the annual dose below the allowable limits.

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D-5 ode 1XW.001 1

2/1/93 Rsv.2 D.3. 10CFR50 ADDendix I - lodine and Particulate Doses

.a. Quarterly Oraan Dose Limit (1) Method 1 This method to be used until the calculated maximum organ dose exceeds 2.5 mrem.

11tEl Determine C.ist which equals the curies of I-131 and Ci-133 which equals the curies of I-133 released during the calendar quarter.

11tEl Determine CH which equals the curies of H 3 released during the calendar quarter.

1112 1 Determine Cp which equals the curies of all particulates with half-lives greater than 8 days released during the calendar quarter.

1.119.4_

i Determine DQT which is the quarterly thyroid dose as follows:

dot = 2.3 x 103 C.131 + 7.4 Ci.133 + 1.0 x 10-2 CH (See AppendixF) litEl Determine Doo which is the quarterly dose to maximum organ otherthan the thyroid:

Doo = 805 Cp + 1.0 x 10-2 Cu (See AppendixF) 1192 1 Maximum organ dose (Douo) equals the greater of dot or Doo. If either is greater than 2.5 mrem, go to Method 2.

(2) Method 2 Doses from vegetation consumption can be neglected during the 1st and 4th quarters and doses from milk consumption can be neglected during the first quarter. These time frames can be extended for short term releases (batch releases and weekly continuous,if necessary) if it can be verified that the milk animals were not on pasture and/or vegetation was not available for harvest. Therefore, calculate doses to the thyroid and maximum or

( when necessary. gan for pathways that actually exist. Sum pathways D-6

2/1/93 Rsv.2 b

Perform Steps 1 through 3 as in Method 1, then:

Et9.4 (See Appendix F forderivation of following factors)

1. InhalationPathway DQT = 16 Cpist + 4 Chiss + 1.3 x 10-3 CH l

Doo = 16 Cp + 1.3 x 10-3 CH

11. Vegetation Pathway DQT = 77 Chis1 + 1.4 Ci.133 + 4.1 x 10-3 C H l Doo = 91 Cp +4.1 x 10-3 CH iii. Milk Pathway DQT = 2200 Cp13; + 2 Chi 33 + 5.0 x 10-3 CH l Doo = 700 Cp + 5.0 x 10-3 CH Sum above is Method 1l pathways, as appropriatet (Ng_ti: sum of all three pathways Step 5 and Ste16 are the same as Method 1.

(3) Method 3 After reviewing the existing cow and goat farms,ifit can be determined

\ that the 1983 1987 D/Q data is acceptable (Note: if not, see guidance in Appendix F), then follow Method 2, above, except for lii, where:

Goat Milk Pathway Cow Milk Pathway DQT = 160 Ci.131 + 1.4 Cp:33 DQT = 134 Ci.131 + 1.2 Cp:33 +

+ 5.0 x 10-3 CH 2.4 x 10-3 CH '

Doo = 51 Cp + 5.0 x 10-3 CH Doo = 17 Cp + 2.4 x 10-3 CH (See Appendix F for derivation of above factors.)

N_p.tt: During the 2nd and 3rd quarters also add (to the above) the inhalation and Vegetation Pathways from Ste during the4th quarteraddInhalation pathway. p 4 of Method 2; (4) Method &

The GASPAR code can be used to determine the maximum quarterly organ dose. Real time meteorology should be used. (if not available, use worst-case quarter as discussed in Appendix F.) Specific curies for each iodine and particulate nuclide should be entered. Only those pathways which are actually in existence at the time should be used (for example - do not use milk pathway in 1st quarter). Vegetation and milk pathway doses should be calculated only at real locations.

b. Annual Oraan Dose 1.imit Determine Dyo which is the maximum organ dose for the calendar year as follows: -

Dyo = E Douo where the sum is over the first quarter through the present quarterdoses to the maximum organ.

D-7

1/1/90 Rsv.1 -

D.4. Gaseous Effluent Monthly Dose Projections * -

a. Gaseous Radwaste Treatment System EtEl I

Estimate c , which is the number of curies of gas to be discharged during the next month based upon the curies released in the present month assum-ing typical operation (i.e., not shut down for refueling, long maintenance, etc.).

Step 2 Determine D which is the estimated monthly gamma air dose for process gas:

MAG D,g = 9.8 z 10" ' C#y(mme Note - Factor from Appendix F, maximum gamma mrad per curie.

EtEl E

Determine D which is the estimated monthly beta air dose for process gas:

MAa D,y = 3.0 x 10-8

  • C,# (mma Note - Factor from Appendix F, maximum beta mrad per curie.
b. Ventilation Releases
i. Method 1 This method ratios a previously calculated organ dose (from D.3.a. -

Method f on ) based upon primary coolant levels and primary coolant losses due to akage.

5_ttal For the last quarter of operation, determine Douo as determined per Section D.3.a.(1). (Note: Use Method 1 only.)

ht91 Estimate R1 which is the expected ratio of primary coolant iodine level for the coming month as compared with the average level during the quarter used in Step f.

D-8 4

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12/31/94 l

Revislan 2 113R.2 {

Estimate R which is the expected ratio of primary leakage rate for the

(~' coming month as compared with the average leakage rate during the quarter used in Step f.

11RELi Determine Dk which is the estimated monthly dose to the maximum organ:

DL = 1/ 3 R, R, D.

QB '

fi. Alethod2 If necessary, estimate curies expected to be released for the next month and applicable method for dose calculation from Section D.3.a.

D.5 Quarterly Dome Calcu!stions for Annual Radioactive Effluent Reoort Detailed quarterly dose calculations required for the AnnualRadioactive Effluent Report shall l be done using the computer code GASPAR. The use of this code and required input parameters are given in Radiological Assessment Branch Procedure, Gaseous Dose Calculations - GASPAR.

D.6 Comollance with 40CFR190 Limits The following sources should be considered in determining the total dose to a realindividual from uranium fuel cycle sources:

a. CY gaseous doses - as calculated in Section Dabove.
b. CY liquid doses - as calculated in Section C above.

c.

CY - direct radiation from the site. Since conservative calculations indicate that yearly site boundary dose will be less than 0.026 mrem, dose from this pathway will be at most a very small fraction of the total dose and hence need not be considered.

d. Since all other uranium fuel cycle sources are greater than 20 mi!ss away, they need not be considered.

I D-9 D481XW.001

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  • 1/1/90 '

Rev.1 TABLE 1 DOSE FACTORS FOR NOBLE GASES (mrem /vr per uCi/m31 (mrad /vr per uCl/m31 Gamma Total Skin Gamma Air Beta Air Body Factor Factor Dose Factor Dose Factor Radionuclide K*** ,,,1l" ,, Mi*** Ni'*

  • Kr-83m 7.56 (-2)* 2.12 (1) 1.93 (1) 2.88 (2)

Kr-85m 1.17 (3) 2.81 (3) 1.23 (3) 1.97 (3)

Kr-85 1.61 (1) 1.36 (3) 1.72 (1) 1.95 (3)

Kr-87 5.92 (3) 1.65 (4) 6.17 (3) 1.03 (4)

Kr-88 1.47 (4) 1.91 (4) 1.52 (4) 2.93 (3)

Kr-89 1.66 (4) 2.91 (4) 1.73 (4) 1.06 (4)

Kr-90 1.56 (4) 2.52 (4) 1.63 (4) 7.83 (3)

  • Xe-131m 9.15 (1) 6.48 (2) 1.56 (2) 1.11 (3)

Xe-133m 2.51 (2) 1.35 (3) 3.27 (2) 1.48 (3) i Xe-133 2.94 (2) 6.94 (2) 3.53 (2) 1.05 (3)

Xe-135m 3.12 (3) 4.41 (3) 3.36 (3) 7.39 (2)

Xe-135 1.81 (3) 3.97 (3) 1.92 (3) 2.46 (3)

Xe-137 1.42 (3) 1.39 (4) 1.51 (3) 1.27 (4)

Xe-138 8.83 (3) 1.43 (4) 9.21 (3) 4.75 (3)

Ar-41 8.84 (3) 1.29 (4) 9.30 (3) 3.28 (3) 7.56 ( 2) = 7.56 x 10 2

/

    • Si = Li + 1.1 Mi from NRC proposed specifications, NUREG 0472, dated May 1978 where Li equals Seta Skin Dose Factor and Mi equals Gamma Air Oose Factor from Table B-1 of Regulatory Guide 1.109, October 1977, Rev.1.

1, using appropriate conversion factors. l l

D-10

' 1/1/90 '

R::v.1 TABLE 2

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DOSE FA CTORS FOR IODINES & PA RTICULA TES Pi*

(mregrger _ yf )r Per Radionuclide Inhalation Veaetables Goat Milk Cow Milk H-3 1.3(3) 4.0 (3)*

  • 4.9 (3)** 2.4 (3)*
  • Cr-51 2.1(4) 6.4 (6) l Mn-54 2.0(6) 3.0 (9)

Fe 59 1.5(6) 6.6 (8)

Co-58 1.3(6) 3.8 (8)

Co-60 8.7(6) 2.1 (9)

Zn 65 1.2(6) 2:2 (9) 1.9 (10)

Rb-86 2.0(5)

Sr-89 2.4(6) 3.7(10) 2.7(10) 1.3(10) )

Sr-90 1.1(S) 1.25(12) 2.6(11) 1.2 (11)

Y-91 2.9(6)

Zr 95 2.7(6)

Nb-95 7.5(5)

{

Ru-103 7.8(5) i Ru-106 1.6(7) 1.2(10)

Ag-110m 6.8(6) )

Te-127m 1.7(6) l

~

Te-129m 2.0(6)

Cs-134 1.1(6) 2.6(10) 2.0(11) 6.8(10)

Cs-136 1.9(5)

Cs-137 9.1(5) 2.4(10) 1.8(11) 6.0(10)

Ba-140 2.0(6)

Ce-141 6.1 (5) .

Ce-144 1.3(7) 1.0(10) 1-131 1.6(7) 2.2(10) 6.3(11) 5.3 (11) 1-133 3.9(6) 4.0 (8) 5.6 (9) 4.7 (9)

  • Pi are the inhalation and consumption factors derived from NRC Regulatory Guide f.109, Rev.1. For inhalation, the teen is the critical age group for all nuclides except Rb-86, Cs-137,1-131, and 1-133, which are for the child. For vegetables, th'e child is critical; for milk, the infant. Maximum organs are: whole body for H-3,  ;

bone for Sr-90 and thyroid for 1-131,133.

    • Same' units as for Inhalation for H 3, based on.NUREG 0133 assumptions.

D-11

06/27/g7 Rev.3 E. LlQUID MONITOR SETPOINTS E.1 Test Tank Discharae Line Monitor The trip / alarm setting on the test tank discharge line monitor depends on dilution water flow, test tank discharge flow, the isotopic composition of the liquid to be discharged, the background count rate of the monitor and the of5ciency of the monitor. Due to the variability of these parameters, an alarm / trip setpoint will be determined prior to the release of each batch The following method will be used:

3133,1 From the tank isotopic analysis and the MPC values for each identified nuclide, determine the required reduction factor:

. 1 R=

(C,IMPC,)

R = required reduction factor C, = concentration of nuclide I(pCL/ml)

MPC, = MPC value (10CFR20*, AppendixB, Table 2, Column 2 for all nuclides except d

noble gases. For noble gases, use 2 x 10 pCi/ml) for nuclide I (pCi/ml) l *10CFR20 version prior to January 1,1992.

Rigg2 Determine the existing dilution flow, D:

D = # of Cire. Pumps running x g3,000 gpm + # of service water pumps x 6,000 ppm I

D = existing dilution flow g3,000 gpm s flow from 1 circulating water pump l 6.000 gpm = flow from 1 service water pump (Note 1) l Riggj Determine the maximum allowable discharge flow F:

F = 0.1 x R x D (Note 2) 3133J Determine the total gamma concentration (A,) in the tank in pCi/ml:

A,(pCi/ml) = IC, ,

Where A, is the total concentration of gamma emitters in the tank and C,is the concentration of gamma emitterI(Note 3).

3333.5' Determine the monitor response, R. In cpm corresponding to two times the total concentration determined in Step 4 (Note 4):

R. = E x 2 x A, Where E is the current monitor ofRciency in cpm por pCiltnl.

E-1

F-06/27/g7 Rev.2

(_.

Sten 6 Determine the monitor response for worst case conditions, R,,, in epm (Note 5):

R., = E x (1 x 10i Ring.Z Determine the alarm trip setpoint, S, in cpm:

IF R. > R.,:

S = R. + B IF R,, > R. use either Option (1) or Option (2):

(1) S = R. + B, or (2)*S=R.,+B Where B = background of the monitor in epm. If background exceeds the monitor response (R or R,,) calculated prior to discharge, the monitor must be decontaminated prior to use.

  • lf option (2) is used for alarm trip setpoint, perform the following:
1. Independent valve verification;
2. controls to ensure that the allowable discharge flow is not exceeded, and
3. controls to ensure that the dilution flow is maintained.

Ng. tag:

1. The maximum capacity of the Service Water System is about 10,000 gpm for 2 or more pumps running. Although this could result in a potential non-conservative estimate of dilution Aow, this is justified since there is a factor of five conservatism in the overa:l calculation methdology.
2. Discharging at this flow rate would yield a discharge concentration corresponding to 10%

of the Technical Specification limit due to the safety factor of 0.1.

3. Monitor response to gamma emitters is used to verify representativeness of Chemistry sample. Compliance with 10CFR20 limits on non gamma emitters is ensured with Chemistry sample results and the maximum discharge flow of Step 3.
4. 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.
5. This value is based upon worst case conditions, assuming a maximum discharge flow (50 ppm), minimum dilution flow (186,000 ppm) and an assumed worst case mix of 4

nuclides (3 x 10 pCi/ml- Footnote 3.a Appendix B,10CFR20). If necessary, this value may be increased by factors to account for the actual discharge flow and actual dilution flow. Use of this value will assure that low level releases are not terminated due to small fluctuations in activity.

E- 2

06/37/97 Rev. 2

(-.

E.2 Steam Generator Blowdown Monitor Assumptions used in determining the Al. ARM setpoint for this monitor are:

a. Maximum possible liquid discharge rate = 43 GPM (rnaximum blowdown rate = 61 GPM of which 30% flashes to steam).
b. Minimum possible dilution flow rata = 279,000 GPM (minimum of 3 cire. pumps during periods of blowdown).
c. Unidentified MPC for unrestricted area (from Appendix B,10CFR20) = 1 x 10#pCi/ml.

Therefore, alarm /setpoint should be:

1 S (pC/ / ml) = 1 x 10-' x = 6.5 x 10" pCl / ml 43 Using the monitor calibration curve, determine the CPM corresponding to 6.5 x 10d pCl/mt. The monitor alarm setpoint should be set at less than this corresponding value plus the background count rate.

E.3 Service Water Radiation Monitor AttLi Maximum possible service water flow F., from potentially contaminated areas flowing past rnonitor =

6,000 GPM x # of service water pumps on.

F. = 6,000 GPM x # service water pumps on.

1192 2 Dilution flow Fo = # Cire. Pumps x 93,000 11923 Worst case MPC* for unrestricted area = 3 x 10 pCi/ml (Note 1)

  • 10CFR20 version prior to January 1,1992.

IlRL4 Therefore, the maximum allowable concentration (A) at the monitor should be:

'. A (pCi / ml) = 3 x 10-7 x "+ #

Fs E- 3

06/27/97 Rev.O

~*

mia Determine the maximum allowable monitor response, R,,, in epm:

R,,= E x A (pCi/mt)

Where E is the current monitor of5ciency in cpm per pCi/ml.

ERA.I Determine the alarm trip setpoint, S, in cpm:

IF cire water and service water systems are both in operation for tank discharges:

S = R,, + B At all other times:

S = 3 x B (Note 2)

Where B = background of the monitorin epm. For tank discharges,if the background exceeds the monitor response (R,,) calculated, the monitor must be decontaminated.

For all other times, if the background exceeds 400 cpm (Note 3) the monitor must be decontaminated.

Hetta:

1. Worst case MPC according to Footnote 3.a. Appendix B,10CFR20.
2. This setpoint will provide a margin of a factor of ten below MPC for gamma emitters with a background of 80 cpm. A worst case release (inadvertent Recycle Test Tank release) would cause tritium concentrations at 70% of the tritium MPC.
3. 400 cpm is about 20% of the MPC for Co 137 (2 x 10-'pCi/ml).

\

E-4

1/1/90

. Rsv.1 1..

F. GASEOUS MONITOR SETPOINTS F.1. Stack Noble Gas Activity Monitor .

Still As given in Section D.f.a. of this manual, determine the noble gas release rate limit Qn in pCi/sec.

1.192.1 Estimate maximum possible stack flow rate (Fs): ,

Fs (cdsec) = 1.2 x # purge fans x 52,000 CFM x 472 cdsedCFM.

Where 52,000 CFM = Flow from one purge flow and 1.2 = conservative factor for maximum possible flow.

Fs = 3 x 107 x # purge fans (cdsec)'

Step 3 Determine monitor alarm / trip setpoint S = Qs/Fs (pCi/cc)

Etn.4 Using the monitor calibration curve, determine the CPM corresponding to 5 (pCi/cc). The monitor alarm setpoint should be set at less than this corresponding  ;

value. l l

F-1

, 1/1/90 Riv.1 APPENDIX A DERIVATION OF LIQUID DOSE FACTORS FOR SECTION C.1.a

1. JUSTIFICATION FOR USING THE LAST FOUR YEARS OF DATA Dose Factors For Liould Releases Curies Dose (mrem)** Dose Per Curie Year Released
  • Whole Body Max. Oraan Whole Body Max. Oraan 1968 3.9 7.7 5.4 2.0 1.38 1969 12.8 4.1 2.99 0.32 0.23 1970 5.1 0.48 0.73 0.09 0.14 1971 5.85 2.7 4.3 ,0.46 0.74

. 1972 4.78 2.8 4.4 0.59 0.92 1973 3.04 4.5 7.2 1.48 2.37 1974 2.23 1.0 1.8 0.45 0.81 1975 1.24 0.81 1.2 0.65 0.97 j 1976 0.13 0.086 0.12 0.66 0.92 1977 1.95 0.56 1.32 0.29 0.68 1978 0.94 2.9 4.2 3.09 4.47 1979 0.87 0.58 '3.1 0.67 3.56 1980 0.28 1.0 1.4 3.57 5.00 ,

1981 0.71 0.61 1.4 0.86 1.97 1982 0.07 0.086 0.14 1.23 2.00 1983 0.48 0.71 1.0 1.48 2.08 1984 0.26 1.3 1.5 5.00 5.77 1985 0.08 0.13 0.18 1.62 2.25 1986 0.29 0.59 0.84 2.03 2.90 1987 0.43 0.93 1.28 2.16 2.98

  • Excepttritium and dissolved noble gases (Note: tritium doses are usually negligible).
    • Calculated using actual nuclide release data and dilution flow rates in the LADTAP computer program.

The worst case year is 1984. Therefore,it is acceptable to evaluate only 1984 - 1987 in detail. ,

1

' ~

. 1/1/90-

. RGv.1

2. METHOD (1) - STEP 3

(_

a. Whole Body Doses From Fission and Activation Products (Excluding Tritium)

Y E Quarter Cg Dgggj Dg /Cg  ;

1 0.010 2.14E-2 2.1 39g4 2 0.010 2.68E-2 2.7 3 0.100 5.40E-1 5.4 4 0.124 5.09E-1 4.1 1 0.024 2.6E-2 1.1 2 0.007 1.7E-2 2.4 1985 3.9 3 0.016 6.2 E-2 4 0.038 2.9E-2 0.8 1 0.017 7.46E-2 4.4 2 0.148 2.53E-1 1.7 1986 1.0 3 0.101 1.06E-1 4 0.044 1.60E-1 3.6 1 0.057 1.86E-1 3.3 2 0.097 3.25E-1 3.4 1987 0.7 3 0.194 1.40 E-1 4 0.079 2.74E-1 3.5 Cp - Curies of fission and activation products releases during calendar quarter.

Dow(r) - Calculated whole body dose (mrem) to maximum individual due to fission and activation products. Dose calculated using -

the computer code LADTAP.

Average value of Dow(r)over the period from 1978-1987 = 2.17 mrem /Ci Maximum value of Dow(r)/ Cr = 5.4 mrem /Ci Since the maximum is only 2.5 times the average, it is not overly conservative. Therefore, use the maximum value for C.I.a.(f) Step 3.

b. Whole Body Doses FromTritium ,

Cr - Curies of tritium released during calendar quarter.

DQw(T) - Calculated whole body dose (mrem) to maximum individual due to tritium.

Since only one nuclide is used here, we can use a method in NRCRegulatory Guide f.109 and estimated conservative dilution flows.

I t

2-

~

1/1/90 l Rev.1 i

( ~' D

  • I " " " * * "

""""*P""" I DilutionVolume

  • factorfor H-3 4W8T8 . rate  !

I 1

Does conversion k x

factorfortritium CI 8) 1012pCi

=

T x x 0.9 pCi/Kg x 21Kg V GiterWquarter) curie pCi/l yr .

yr l x x 1.05 x 10~7 mmm 4 quarters pCi C7(curies)

= 4.96 x 10 8 mrem V Oiters)

Assuming only one circulation pump is in operation for the whole quarter (worst case).

4.96 x 10 8

  • D = 1.07 x 10-8 (C.g3 mrem to Qwm " 4.64 x 10 U

Qwm

/. = 1 x 10-8 mrtm / curie T

l I

. 1 3-

1/1/90 Rsv.1 APPENDIX B

{'_ DERIVATION OF LIQUID DOSE FACTORS FOR SECTION C.1.b -

1. JUSTIFICATION FOR USING THE LAST FOUR YEARS OF DATA See Appendix A.
2. METHOD (1) - STEP 3
a. Maximum Organ Doses From Fission And Activation Products l I

Maximum Year ' Quarter Cg Oraan Dg Dg /Cg 1 0.010 liver 2.89E-2 2.9 .

39g4 2 0.010 liver 3.52 E-2 3.5 3 0.100 liver 7.85E-1 7.9 4 0.124 liver 6.81 E-1 5.5 1 0.024 liver 3.5E-2 1.5 1985 2 0.007 liver 2.3 E-2 3.3 3 0.016 liver 8.3 E-2 5.2 4 0.038 liver 3.9 E-2 1.0 1 0.017 liver 1.04E-1 6.1 1986 2 0.148 liver 3.55E-1 2.4 3 0.101 liver 1.49E-1 1.5 4 0.044 liver 2.31 E-1 5.3 1 1 0.057 liver 2.68E-1 4.7 2 0.097 liver 4.67E-1 4.8 1987 3 0.194 liver 1.94E-1 1.0 4 0.079 liver 3.47E-1 4.4 -

Cp - Curies of fission and activation products releases during calenoc quarter.

Dgo - Calculated dose (mrem) to the maximum adult organ; dose calculated using the computer code LADTAP.

Average value of Doo/Cp over the period from 19781987 = 3.3 mrem /Ci Maximum value of Dgo/Cp = 8.0 mrem /Ci or 2.4 x Average value Since the maximum is only 2.4 times the average, it is not overly conservative.

Therefore, use the maximum value for C.I.b.(T) Step 3.

. b. Maximum Organ Doses FromTritium According to the NRC Regulatory Guide 7.709, all organs (including whole body) receive the same dose from tritium (all dose conversion factors are the same). Therefore, use:

l l

r. -

. . 1/1/90 l . Rsv.1 i

I Der # C = r 1z10-5 m=m / curie

~

6s shown in Appendix A. .

l CT - Curies of tritium released during calendar quarter.

Doo(p - Calculated dose (mrem to the maximum organ due to tritium).

D l

l l

e I

l

WN7#8 Rsv.1 APPENDIX C g _.

. LIQUID DOSE CALCULATIONS- LADTAP The LADTAP code was written by the NRC to compute doses from liquid releases. The actual model used is LADTAP ll which performs calculations in accordance with Regulatory Guide 1.109, Revision 1.

For calculating the maximum individual dose from Haddam Neck, the following options and parameters are used:

1. Real time, measured dilution flow ,
2. Fresh water site, no reconcentration
3. Shorewidth factor = 0.1 for discharge canal
4. No dilution for maximum individual pathways
5. One hour discharge transit time - approximate time to reach 1/2 canal length
6. Regulatory Guide 1.109 usage factors for maximum individual for fish, shoreline, swimming and boating
7. Zero usage for shellfish, algae, drinking water, and irrigated food pathways D

m 1-

    1. /15/95 R:: vision 3 APPENDIX D DERIVATION OF FACTORS FOR SECTION D.1
1. SECTION a. - X/O VALUE ouartadv Averaae X/O's & D/O's Nearest Land Nearest Resident Cow or Goat Maximum X/Q Maximum D/Q Maximum D/Q Year /QTR. Continuous 38th Continuous Baish Continuous Ratsb 1983 - 1 1.1(5) 1.1 (-5) 6.0 (4) 6.2 (-8) 2 3.0 (-5) 5.8 (-5) 1.1 ( 7) 6.8 (4) 8.0 ( 9) 5.4 (-9) 3 2.4(5) 3.9 ( 5) 5.1 (4) 2.7 (4) 2.9 ( 9) 2.7 ( 9) 4 1.1 (-5) 1.4 (-5) 4.7 (4) 3.0 (4) 3.5 (-9) 3.0 (-9) 1984- 1 8.5 (4) 9.6 (4) 5.1 (4) 8.6 (4)

. 2 2.6 -(-5) 9.7 (-8) 7.3 (-9) 3 2.5 (-5) 4.8 ( 8) 3.9 (-9) 4 1.8 ( 5) 5.2 (-5) 5.3 (-8) 3.2 (-7) 4.0 ( 9) 2.4 (4) 1985- 1 1.5 ( 5) 8.5 ( 5) 6.9(4) 1.5 ( 7) 2 2.8 ( 5) 9.4 (-8) 6.8 (-9) 3 3.2 ( 5) 7.1 (-8) 5.0 ( 9) 4 1.3 ( 5) 3.7 (-8) 3.7 (-9) 1986 - 1 1.3 ( 5) 9.8 (4) 7.9 (-8) 4.9 (-8) 2 2.0 ( 5) 1.9 (-5) 9.1 (-8) 9.7 (4) 7.0 ( 9)- 4.1 (-10) 3 2.9 ( 5) 1.8 ( 5) 7.3 (4) 5.7 (4) 5.6(9) 4.0 (-9) 4 1.2 (-5) 1.2 (-5) 4.2 (4) 7.8 (4) 2.8 (-9) 4.3 (-9) 1987- 1 1.1 (-5) 7.6(4) 6.3 (-8) 7.1 (4) 2 1.7 (-5) 1.1 (-5) 7.3 (-8) 5.7 (-8) 2.1 (-9) 1.1 ( 9) 3 2.6 (-5) 4.1 (-5) 7.1 (-8) 1.2 ( 7) 3.0 (-9) 5.2 (-9) 4 1.6 ( 5) 4.7 (-8) 1.5 ( 9)

Maximum Quarterly Average X/Q - Continuous Releases = 3.2 x 10 4 Maximum Resident Quarterly Average D/Q - Continuous Releases = 1.1 x 10 #

Maximum Milk Animal Quarterly Average D/Q - Continuous Releases = 8.0 x 10*

Average Maximum Quarterly Average X/Q - Continuous Releases = 1.9 x 10 4 Avera9e Maximum Quarterly Average X/Q - Batch Releases = 2.8 x 104 Average Maximum Resident Quartedy Average D/Q - Continuous Releases = 6.6 x 10 4 Average Maximum Resident Quarterly Average D/Q - Batch Releases = 9.1 x 10 4 Average Maximum Milk Animal Quarterfy Average D/Q - Continuous Releases = 4.5 x 10*

Average Maximum Milk Animal Quarterly Average D/Q - Batch Releases = 5.6 x 10*

'(

~'-

70/15/95 R:visi:n 3 Although 10CFR20.106 allows averaging concentrations of radioactive material over a period not greater than one year, this does not suggest that the worst case year should be p

used for release rate determinations. NUREG -0733 recommends that the STS consider historical annual average atmospheric dispersion conditions. Therefore, average values from above are adequate for release rate calculations. This is conservative since the maximum quarter 1y averages are not typically at the same location.

2. SECTION a. . JUSTlFICATION FOR METHOD USED TO DETERMINE K & S There are many different sources contributing to the releases from the ventilation stack.

These include releases from the building ventilation, condenser air ejector, containment purges, flashed gases which occur while obtaining primary coolant samples, and discharges from the waste gas tanks. These sources may exist in any possible combination and each has its own particular, but changing, nuclide mixture. Thus, the ratio of nuclides being released is a constantly changing parameter.

It is impractical to change the value of K(S) and thus the release rate limit and monitor setpoints each time a source stream is initiated or terminated or an isotopic analysis is performed on any of the source streams, instead, we can choose a conservative value for K(S) such that whatever combination of source stream exists, the actual value of S or K will be less than that assumed.

Table 1 indicates that the highest values of K4 (Sn occur for the shorter half life noble gases.

Therefore, the highest value of K(S) would be obtained with a sample having the least amount of decay. Thus, if we determine K(S) us'ng the gas mixture in the primary coolant, we will be conservative because the mixture from any other source will be decayed from this value. (An actual isotopic mixture from the stack should be used to determine'K and S from normal releases during periods of high failed fuel fractions to prevent unnecessarily conservative limits. Any prompt releases should be based upon current primary flashed gas analyses however.)

3. SECTION a. - DERIVATION OF FINITE CLOUD CORRECTION FACTOR JOINT FREQUENCY DISTRIBUTION AT 196 FOOT LEVEL FRACTIONAL STABILITY CLASS Ygg A ,,3 , ,,,G_ D_ E., Ei,Q 1975 0.082 0.061 0.065 0.373 0.313 0.100 1976 0.102 0.057 0.066 0.364 0.306 0.102 1977 0.094 0.048 0.060 0.336 0.324 0.119 1978 0.090 0.053 0.057 0.374 0.315 0.105 1979 0.096 0.056 0.066 0.433 0.271 0.074 Avg. 0.093 0.055 0.063 0.376 0.306 0.100

(

. t. l DeSikWAl91

p/15/95 R:: vision 3 From " Meteorology and Atomic Enegy,"1968, Figures 7.16 and A.2 with a cloud gamma energy of 0.1 MeV, the finite cloud correchon factors at 0.51 Km (distance to nearest land site boundary) are:

Stability Class A 1 1 .jL 1 F Factor 0 0.51 Km 0.7 0.63 0.50 0.40 0.28 0.21 The weighted correchon factoris:

0.093(0.70) + 0.55(0.63) + .063(.50) + .376(0.40) + .306(0.28) + .100(0.21) = 0.39.

4. SECTION b. - DETERMINATION OF LODINE AND PARTICULATE RELEASE RATE LIMIT Doses are calculated using the methods of NUREG-of33 dated October 1978 and NRC Regulatory Guide 1.109, Revision 1. Note that the equation on page 27 of NUREG-0133 (for all radionuclides, except tritium) has been corrected for the elemental iodine fraction, as in Regulatory Guide f.109, Revision 1. For the instantaneous release rate limit, only the inhalation pathway needs to be considered.

Method 1 Dose formula for iodine (both I-131 and 1-133) is:

D r, . (X / Q x P, x Q,)

Inhalation where: DTi = thyroid dose rate from iodine releases (1-131 and 1-133)

Qi = release rate of each isotope of iodine, pCi/sec X/Q = meteorological dispersion factor, sec/m*

P. = values derived from NUREG-0133 and Regulatory Guide 1.109 (see Table 2).

Dose formula for tritium is:

DT, = [XI Q x R x Q,)

Inhalation where: DT, = thyroid (or any other organ) dose rate from tritium releases Qs = release rate of H-3, pCi/sec other parameters as described above.

Dose formula for particulates is:

DO, = lX / Q .R . Q,}

where: DO, = maximum organ dose rate from particulate releases Q, a release rate of particulates, pCi/sec other parameters as described for iodine, above.

(

3 omixw.ms

  1. N15/95

)

R; vision 3

a. Thyroid Doses Method 1 304Qwas + 74.1Q su + 0.0250s 51500 4

0.20 Q6n, + 0.049 Quin + 1.7 x 10 Qw 51 o-4 Quit + 0.24Qusu + 8.5 x 10 Qw 5 5

b. Oman Doses (other than thyroid)

Method 1 304Q, + 0.025 Qw 51500 '

O.2Q, + 1.7 x 104 Qs 51 or l

Q, + 8.2 x 104Qn 5 4.9 5.

SECTION b. - DETERMINATION OF RELEASE RATE LIMITS - METHOD 2 l

Method 2, by use of the GASPAR code, eliminates some of this conservatism by calculatij the dose to each organ using the dose factor for that particular organ for each nuclide, then the critical organ can be determined.  !

l l

(

DettXW.091 9

  • ~

1I1/90 Rsv.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 f.fo9. 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 Regulatory Guide f.109 to those in Rev. f.

For calculating the maximum individual dose from Haddam Neck, the following options and parameters are used:

1. Real time meteorology using a X/Q, D/Q model which incorporates the methodology of Regulatory Guide f.!f f. Meteorology is determined separately for continuous releases and batch releases 2.100%

seasonoffrom vegetation grownSeptem April through locally,ber76% of vegetation intake from garden, harvest

3. Animals on pasture April through December- 100% pasture intake
4. Air water concentration equals 8 g/m3
5. Maximum individual dose calculations are performed at the nearest land site boundary with maximum decayed X/Q, and at the nearest vegetable garden (assumed to be nearest residence) and cow and goat farms with maximum D/Q's t

[ - ~ wwes

.Rsv.1 APPENDIX F l(

l DERIVATION OF FACTORS FOR SECTIONS D.2 & D.3 *

  • l .

1

1. SECTION D.2.s (1) -

' Noble Gas Air Doses Curies of Air Dose (mrad)* mrad per curie l Xsar Quarter Noble Gas Gamma - Rita Gamma geta 1 825 0.087 O.251 1.1 (-4) 3.0 (-4) 2 48 0.022 0.141 4.6 (-4) 2.9 (-3) 1983 l 3 359 0.277 0.615 7.7 (-4) 1.7 (-3) 4 1530 0.353 0.866 2.3 (-4) 5.7 (-4) 1 1210 0.146 0.425 1.2 (-4) 3.5 (-4) l 3gg4 2 3770 1.51 3.66 4.0 (-4) 9.7 (-4) 3 2540 0.893 2.84 3.5 (-4) 1.1 (-3)

! 4 3 0.002 0.006 6.7 (-4) 2.0 (-3) i 1 172 , 0.169 0.511 9.8 (-4) 3.0 (-3)  !

2 1040 0.555 1.23 5.3 (-4) 1.2 (-3) l l 1985 752 3 0.657 1.14 8.7 (-4) 1.5 (-3) 4 799 0.210 0.481 2.6 (-4) 6.0 (-4) 1 1730 0.257 0.788 1.5 (-4) 4.6 (-4) l! 1986 2

3 62 393 0.012 0.113 0.044 0.333 1.9 (-4) 2.9 (-4) 7.1 (-4) 8.5 (-4) 4 150 .0.026 0.076 1.7 (-4) 5.1 (-4) 1 63 0.007 0.019 1.1 (-4) 3.0 (-4) ggg7 2 852 0.134 0.377 1.6 (-4) 4.4 (-4) l 3 2670 0.929 2.83 3.5 (-4) 1.1 (-3) '

4 0.2 5.9 (-6) 1.8 (-4) 3.0 (-5) 9.0 (-4)

Avg. = 3.6 (-4) 1.1 (-3) .

  • Calculated maximum tir dose ("mrad) due to noble gases calculated using NRC computer code GASPAR.

Average value of gamma air dose per curie = 3.6 x 10-4 mrad /Ci ,

Maximum value of gamma air dose per curie = 9.8 x 10-4 mrad /Ci Ratio Maximum / Average = 2.7 l Average value of beta air dose per curie = 1.1 x 10-3 mrad /Ci l .

Maximum value of beta air dose per curie = 3.0 x 10-3 mrad /Ci l Ratio Maximum / Average = 2.7 Therefore, use of the maximum observed values should only be a factor of three l conservative on the average.

    • All X/Q and D/Q values are based upon mixed mode release per Regulatory i Guide 1.111.

f 1/1/90

. Rcv.1 )

)

- 1 l

l

~

.. 2. SECTION D.2.s (2)

Appendix D lists the quarterly X/O and D/O factors for 1983-1987. However, unlike the instantaneous limits where averaging is acceptable, the worst casa quarter should be used. For the period 1983-1987, this occurred for batch releases dunng the first quarter 1985 (X/Q = 8.5 x 10-5).

(1) - STEP 4 DQAGi = Quarterly gamma air dose due to nuclide i )

= C, (Ci) M . (yr** -

z 8.5 x 10-8 mc/m3 z pCi 108pCi/Ci z 3.17 x 10-8 (yr/see)

As indicated above, the same X/Q can be used for both batch and continuous releases.

D = 2.7 x 10-8 M, C, Q4a4 Dq,g = E over all nucliden = 2.7 z 10-*

  • M, C; t (2) - STEP 5 Likewise for the beta air dose, all factors are the same except the dose conversion factor Mi should be replaced by Ni.

D9 , = 2.7 x 10-8 * [, N, C, e .

3. DERIVATION OF FACTORS FOR SECTION D.2.a (3)

X/Q = 3.2 x 10 5 sec/m3 D/Q = 1.1 x 10 7 m-2

4. DERIVATION OF FACTORS FOR SECTION D.3.a (1)

Doses are calculated using the methods of NUREG-Of33 dated October 1978 and NRC Regulatory Guide 1.109 Revision 1. Note that the equation on page 27 of NUREG-Of33 (for all radionuclides, except tritium) has been corrected for the elemental iodine fraction, as in Regulatory Guide 7.709, Revision 1. Since the locations of milk producing animals causes significant variations in the dose calculations (substantial variations in D/Q's), use 3 methods when performing these calculations.

Method 1 Assume worst case locations (i.e., milk animals located at maximum resident D/Q

! location), vegetables harvested throughout the year, and milk animals on pasture throughout the year.

2-

2/1/93

  • ~

R3v. 2 Method 3 Assume worst case quarterly X/Q and D/Q as above, however:

1. If the 1st quarter, neglect vegetation and milk doses.

ii. If the 4th quarter, neglect vegetation doses.

iii. For batch releases (including weekly continuous releases, if necessary) evaluate other periods of time where the above may apply.

Method 3 Determine if the maximum quarterly D/Q data from Appendix D.1 is acceptable to use -

(i.e., no milk animal likel:t to be more critical than the data for 1983-1987). If acceptable, use D/Q for mi k locations. If not, an acceptable D/Q for use is the worst case quarter of at least the past three years. Also determine if goat or cow dose factors are to be used (Hgtg: goat dose factors result in higher doses).

Dose formula forlodineis:

Dg7 = XIQ O + +

g C, DlQ

  • Og
  • C, DlQ O g C, inhalation Vegetation Milk where: Dor, = quarterly thyroid dose from iodine releases (for each l-131 and 1 133) l i Cl = curies of each isotope of iodine released X/Q = meteorologicaldispersion factor,sec/m3 D/Q = deposition factor,m 2 Oi = Pi x 3.17 x 10-2*, mrem . m3/Ci . see forinhalation and mrem . m2/Ci . sec for food consumption Pi a values derived from NUREG 0133 and Regulatory Guide 1.109 (see Table 2)
  • pCi/sec per Ci/yr conversion factor Dose formula fortritiumis:

D =

XIQ O Cy_, +

QTu g XIQ O Cy_,

g + .XIQ Og C_,

y inhalation Vegetation Milk {

where: DQTw3 = quarterly thyroid (or any other organ) dose rate from tritium releases CH-3 = Curies of tritium released other parameters as described above, except units for 0; and Pi. Since milk and vegetable doses from tritium are related to X/Q and not D/Q, use the l units for inhalation (see NUREG-0133 and/or Regulatory Guide 1.109, Revision 1 fordetails).

L .

l 3  !

2/1/93 Rsv.2 n

\ Dose formula for particulatesis:

Dgg , a XIQ P g* Cp + DlQ P, C, + DIQ P g C, inhalation Vegetation Milk where: Dgo, a quarterly maximum organ dose from particulate releases Cp = curies of particulates released other parameters as described for iodine, above.

i. Method 1 Using the worst case quarters as explained earlier and P/s (conservative mix *) l from Table 2 resultsin:

D g7 = 2.29 x 10+aCg ,gg + 24.9 Cl- m D = 1.0 z 10-8 Cy _,

erg D gg = 805 C,

,

  • For particulate doses use either Ru-106 or Cs-134 Pi values (whichever is greater). Review of the 1978 - 1988 effluent data shows that Sr-90 usually contributes to less than 2% of the total particulate curies (only 1st quarter 1987 exceeded this with 3.1% contribution by Sr-90). Therefore, this will usually result in a conservative calculation.

ii. Method 2 i Use same formulas as for Method 1, however, delete vegetation and/or milk when applicable.

iii. Method 3 After review of existing cow and goat farms,if the D/O for milk animals for i the 1983-1987 data is determined to be acceptabic, then:

Milk Pathway Doses-Goat:

Dg7 = 160 Cl-un+I4Ui- m D

erH-s = 5.0 x 10-s C,_,

D = 51 Cp g gg, f

2/1/93 Rev. 2 Milk Pathway Doses-Cow:

. Dy = 134 C g ,, + 1.1 C,,,

l i

l D, _ = 3.4:10-s g N-s l

D, = 17 C, t

l l

l l

0 l

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1

$ d 5-

5/30/97 Revision 6

(_ APPE!NDlX G ENYlRONMENTAL MONITORING PROGRAM Samnling 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, and G 2,,

Location Dirootton & Distance figunhat timma From Sample Types Relanas Point *"

1 l* On-she Mouth of Discharge Canal 1.1 Mi, ESE TLD 21 Haddam-Park Rd. 0.8 Mi, S TLD 31 Haddam-Jail Hill Rd. 0.4 Mi, W S W TLD 41 Haddam-Ranger Rd. 1.8 Mi, SW TLD, Air Paniculate 51 On site Injun Hollow Rd. 0.4 Mi, NW TLD, Air Particulate 61 On she Substation 0.5 Mi, NE TLD, Air Particulate, Vegetation 71 Haddam 1.8 MI, SE TLD, Air Particulate 81 East Haddam 3.1 Mi, ESE TLD, Air Particulate 9l Higganum 4.3 Mi, WNW TLD, Air Particulate 101 Hurd Park Rd. 2.8 Mi, NNW TLD 11 C" Middletown 9.0 Mi, NW TLD 12-C - Deep River 7.1 Mi, SSE TLD g 13-C North Madison 12.5 MI, SW TLD, Air Particulate 14 C Colchester 10.5 Mi, NE TLD 15 1 On site Wells 0.5 MI, ESE*"* WellWater 16 C Well State Highway Dept. E. Haddam 2.0 Mi, SE WellWater 17 C Fruns & Vegetables Beyond 10 Miles Y*getation 18-1 Site Boundary 0.4 Mi, NW Vegetation igl Cow Location #1 4.5 Mi, ENE Mik 20-1 Cow Location #2 8.0 Mi, NE Mik 21 1 Cow Location #3 11.0 Mi, SE Milk 22 C Cow Location #4 11.0 Mi, ENE Mik 23-C Goat Location #1 18.0 Mi, NNE Mik 24 1 Goat Location e2 3.8 MI, SSE Mik 25-l Fruits & Vegetables WRhin 10 Miles Vegetation 26-1 Conn. River Near intake 1.0 MI, WNW Fish l

27 C Conn. River Higganum Light 4.0 MI, WNW Shellfish 4 1

28 l Conn. River E. Haddam Bridge 1.8 Mi, SE Bottom Sediment, River Water 2g-1 Vicinity of Discharge Bottom Sed 6 ment, Fish

. .. {

30-C Conn. River Middiotown 9.0 MI, NW River Water, Bottom Sediment l 7.8 MI, NW Fish 31 1 Mouth of Salmon River 0.8 MI, ESE Shellfish i I

'l = Indicator "C = Controf

'"The release points are the stack for terrestial locations and the end of the discharge canal for squatic locations..

l

""New wells at 0.4 miles SE may be used as a replacement for this location.

(

APP. G 1 meim mt. ooc

5/30/97 Revision 6

(- The following lists the accident TLD sampling locations. Sampling locations are shown on Figure G-3.

ACCIDENT TLD SAMPLING LOCATIONS Direction andDistance Location Description (Town and Street) 0.8 Mi, N Haddam Neck, Cove Road 4.0 Mi, N East Haddam, Quitewood Road and Route 196 1 0.7 Mi, NNE Haddam Neck, Jenks Hill Road 2.6 Mi, NNE Leesville Substation, intersection of 151 and 196 j 4.8 Mi, NE Colchester, Waterhole Road 0.3 Mi, ENE Haddam Neck, Jenks Hill Road 4.4 Mi, ENE East Haddam, Falls Bashen Road 0.3 Mi, E Haddam Neck, Road to Canal 4.4 Mi, E East Haddam, Smith Road 2.8 Mi, SE East Haddam, Creamery Road (off Route 82)

( 0.9 Mi, SSE Haddam, Route 9A, Comer of Plains Road 3.2 Mi, SSE Haddam, Old Chester Road 3.1 Mi, S Haddam, Int. Turkey Hill and Dickinson Road 0.7 Mi, SSW Haddam. Route 9A, Parking Lot Agr. Building 5.2 Mi, SSW Killingworth, Parker Hill Road 0.7 Mi, SW Haddam, Route 9A, Quarry Hill Road 4.0 Mi, SW Haddam, Route 81, North of Woods Road 3.2 Mi, WSW Haddam, Route 81, after Route 9 Underpass 0.9 Mi, W Haddam, Route 9A, South End of Walkely Hill 1.1 Mi, W Haddam, Island Dock Road 4.6 MI, W Haddam, Spencer Road 1.2 Mi, WNW Haddam, Route 9A, North of Town Dump 0.7 Mi, NW Haddam Neck, injun Hollow Road 4.6 Mi, NW Middletown, Maromas Meteorological Tower 1.0 Mi, NNW Haddam Neck, Ague Spring Road

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. . 1/1/90

. RGv.1 APPENDlX H

]

l l DERIVATION OFFACTORS FOR TABLE 2*

  • j l ( ~~

4

1. Vegetation Factors )

l

a. H 3 , I 1

R,= K'K" U, f, + U# (, DFL , 0.75 0.5 / H From page 36 of NUREG-0133 l

K' = 10s DFLy_, = 2.03 x 10-7 K ' = 108 3

f, = 1.0

)

U,' = 26 (forchild) f, = 0.76 8

U," = 520 (forchild) H = 6 atm 8 8 8 R, = 10 - 10 26 (1.0 + 520f.76 2.03 x 10-7 (0.75 =x4.01 0.5x 10

/8

b. lodine-131,133

~

= K' O.5 R,Y DlQ DFL , Uf f, e v.(2, + x.)

From page 35 of NUREG-Of 33, except last term was deleted since it is negligible t

for iodine-131 and 133 and accounting for elemental iodine fraction. -

K' = 108 U, = 26 (child), 64 (adult) '

r = 1.0 f, = 1.0 l

Y, = 2 A, = 9.97 x 10~ 7 I-131 DFL = 5.72 x 10-8 f I-131 A, = 9.35 x 10-s I-133 DFL = 1.36 x 10-8 fI-133 s, = 8.6 x 10' see I

A, = 5.73 x 10 ~7 1 i R,=10*x _ DCF, 26 e -As')1 0.5) 2A+A j t - .. .

E '

1'/1/90 Rsv.1 APPENDIX H (C:nt'd.)

(~' for1-131:

l R, = 10' = 2.17 x 10' x 5.72 x 10-8 f 26 x 0.9178 (0.5 2(1.57 x 10-a for M 33:

R, = 10' x 1.36 x 10-s 26 x 0.4475 (0.5 2 f 9.92 x 10-s

= 3.99 x 108= 4.0 x 10 8

c. Sr 90 (r) - 1.* 4' - 1* ,k R[ DIQ = K' DFl., , U,' f, e +U (, e Y, f A j +A From page 35 of NUREG-0133 K I = 10 8 U, = 26 (child), 64 (adult) ,

r = 0.2 U,8 = 520 (child), 520 (adult)

Y, = 2 f, = 1.0

~

Ag + A, = 5.738 x 10-7 f, = 0.76 DFL3 ,,,, = 1.70 x 10-2 (child) Aj = 7.85 x 10-10 8

= 7.85 x 10-8 (adult) f, = 8.6 x 10 ase t g= 5.16 x 10s ,,,

, 's 'I ,

, ," At 'h DlQ = 10 8 1.7 x 10 - 2 1 x 26 R[ +f.76x520 2 f 5.738 x 10-7

= 2.06 x 10 s (2e . 3,5.2) = 1.25 x 10 2 2-l

. 1/1/90

Rsv.1 i

APPENDIX H (Cent'd.)

l I~ 2. Milk Factors .

a. H-3 P = K' K F, Q, U, DFL, g 0.75 0.5 /H From page 27 ofNUREG-0133 Kt= 10 s U, = 330 (brinAnt)

K '8 = 108 gm/Kg 8

DFL, = 3.08 x 10~7 F, = 0.17 (forgoat) H=8 Qf = 6 (forgoat) 8

  • P, = 10 -

10 8 ( 0.17 f f330 6' f 3.08 x 10-7

= 4860 (forgoat)

= 2400 (forcow - ase NUREG -0133 )

b. lodine-131,133 K' Q, U* rF

.n. I Pg = FL, e Y, k, + A.

From page 26 of NUREG-0133, however, multiply this by 0.5 elemental iodine  !

fraction per guidance in NRCRegulatory Guide 1.109, page26.

Y , = 0.7 F, = 0.06 )

I r = 1.0 for iodine . t y = 1.73 x 10' sec l

. 1, = 9.97 x 10~7 for I-131 DFLi- ut

= 1.39 x 10-2 1

Aj = 9.35 x 10~8 for.1- 133 DFL,,, = 3.31 x 10-8

~I A, = 5.73 x 10-7 sec and other factors as shown above.

l I-

11 'y1/90 R0v.1 ,

APPENDIX H (C:nt'd.)

4- for1-131: .

P, = 7.5 z 10" fe" / = 7.5 z 10" x 0.842 = 6.32 x 10"

~

for1133:

f -1 :

P, = 2.83 z 10 (e dI = 2.83 x 10 0.198 = 5.62 x 10' 30

c. Sr 90 Same equation as for lodines, except disregard elemental iodine fraction and:

A, = 7.85 z 10 ~ A, + A, = 5.738 z 10~7 ,

r = 0.2 DFLp,,, = 1.85 x 10-2 F, = 0.014 (forgoat) rF *

.a I d

Pd= 2.83 z 10' A, + A, DFL,e

-14

= 2.55 x 10 38 x(e* I = 2.6 z 10 '

3

  • Comparisons of calculations performed using these values with calculations from GASPAR (NRC computer code) verify these factors.

l

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