ML20211N330

Errata to Offsite Dose Calculation Manual Covering Apr 1979 - May 1981

ML20211N330
Person / Time
Site:	Seabrook
Issue date:	06/30/1986
From:	PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:
Shared Package
ML20211N322	List: ML20211N318 ML20211N330
References
SBN-1149, NUDOCS 8607030024
Download: ML20211N330 (21)

Text

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1 l3 . Attachment 2 lg .

SBN-1149

,I CHANGES TO PP.OPOSED SEABROOK ODCM June 30, 1986 List of Affected Fages Pages R6 place with new Pages l Cover Page Cover Page B.1-ll B.1-ll B.1-13 thru B.1-15 B.1-13 thru D.1-15 ]

B.3-8 B.3-8 B.5-9 thru B.5-r3 B.5-9 thru B.5-13 B.6-3 B.6-3 B.7-4 B.7-4 B.7-18 thru B.7-20 B.7-18 thru B.7-20 B.7-26 B.7-26 I B.8-7 thru B.8-9 B.8-7 thru B.8-9 i i

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ADOCK 05000443 PDR l 1 l

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I lI I SEABROOK STATION l

Orr-SITE 00SE CALCULATION MANUAL l

NEW HAMPSHIRE YANKEE .

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TABLE B.1-7 Summary of Methods for Setpoint Determinations I Equation Category Equation Number 5-1 Liquid Effluents:

Liquid Waste Test I

DF Tank Monitor setpoint ( " )" 1 DF min i (RM-6509)

I kghk$a - RCset(gph) = 1x108 , 3yp , pCC 1

l l

Gaseous Effluents:

Plant Vent Wide Range Gas I Honitors (RM-6520-1, 2, 3)

Total Body 5-5 1 tb (pCi/sec) = 806 DFB 5-6 Skin R 1

skin (uti/sec) = 3000 DF' I

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B .1 -11 I

TABLE B.1-8 (continued)

Sumary of Variables I Variable Definition Units

= Dose to the maximum organ mrem D,9 D = Dose to skin f rom beta and gama mrem

= Dose to the total body mrem l D

b

= Dilution factor ratio DF

= Minimum allowable dilution factor ratio DF min

= Composite skin dose factor mrem-sec DF' pCi-yr

• 3 "I'*~*

DFB = Total body gamma dose factor for nuclide "i" p -yr (Table B.1-10) 3 DFB = Composite total body dose factor C c

DFL g = Site-specific, total body dose factor for a mrem ,

liquid release of nuclide "i" (Table B.1-11) pCi

= Site-specific, maximum organ dose f actor for a mrem DFLi

• liquid release of nuclide "i" (Table B.1-11) pCi DFG 4c, = Site-specific, critical organ dose factor for a mrem {

gaseous release of nuclide "i" (Table B.1-12) pCi DFG' = Site-specific, critical organ dose rate f actor mrem-sec C

for a gaseous release of nuclide "i" pCi-yr (Table B.1-12) 3 mrem-m DFS = Beta skin dose factor for nuclide "i" pCi-yr (Table B.1-10) mrem-sec

= Combined skin dose factor for nuclide "i" I DF' I

(Table B.1-10) pCi-yr 3

nrad-m I DF T

I

= Gamma air dose f actor for nuclide "i" (Table B.1-10)

B .1 -13 pCi-yr

,I l

I )

TABLE B.1-B (continued)

Sununary of Variables I Lariable Definition Units 3

mrad-m 0

0F = Beta air dose f actor for nuclide "i" p -yr (Table B.1-10)

E = Critical organ dose rate due to iodines b F C

and particulates h = Skin dose rate due to noble gases r skin I b tb

= Total body dose rate due to noble gases yr D/Q = Deposition factor for dry deposition of 1 elemental radioiodines and other particulates ,2 F = Flow rate out of discharge tunnel gpm or d

ft /sec I F, = Flow rate past liquid waste test tank monitor gpm F = Flow rate past plant vent monitor cc sec I

Dimensionless I f); f3f2 3

= Fraction of total MPC associated with Paths 1, 2, and 3 F = Total fraction of MPC in liquid pathways Cimensionless (excluding noble gases)

I HPC,

= Maximum permissible concentration for uCi I radionuclide "i" (10CFR20, Appendix B, lable 2, Column 2) cc

= Release to the environment for curies, or I 0 9

radionuclide "i" pcuries

= Release rate to the environment for pCi/sec I Q 4

radionuclide "i" R = Liquid monitor response for the limiting pCi/ml i setpoint concentration at the point of discharge R = esp nse en e gas manhor at ne cpm, or skin limiting skin dose rate pCi/sec B .1 -14 I

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TABLE B.1-8 (continued)

Summary of Variables E Variable Definition Units R = Response of the noble gas monitor to cpm, or b

limiting total body dose rate pCi/sec Sp = Shielding factor Dimensionless 5 = Detector counting ef ficiency f rom the com mR/hr 9 gas monitor calibration pCi/cc or pCi/cc

= Detector counting efficiency for noble com mR/hr pCi/cc or pCi/cc S

gj gas "i" S

j = Detector counting ef ficiency f rom the cos liquid monitor calibration pCi/ml I S jg = Detector counting ef ficiency for cos radionuclide "i" pCi/ml I X/Q = Average undepleted atmospheric dispersion factor (Tables B.7-4 and 8.7-5) se m

3 B [X/Q]Y = Effective average gamma atmospheric dispersion f actor (Tables B.7-4 and B.7-5) m SWF = Service Water System flow rate gph uCi/ml I PCC = Primary c.omponent cooling water measured (decay corrected) gross radioactivity concentration E

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3.4 Method to Calculate the Total Body Dose Rate From Noble Gases Technical Specification 3.11.2.1 limits the dose rate at any time to the total body from noble gases at any location at or beyond the site boundary to 500 mrem / year. The Technical Specification indirectly limits peak release rates by limiting the dose rate that is predicted from continued release at the peak rate. By limiting D to a rate equivalent to no more than 500 tb mrem / year, we assure that the total body dose accrued in any one year by any I member of the general public is less than 500 mrem.

Use Method I first to calculate the Total Body Dose Rata from the peak release rate via the station vents . Method I applies at all release rates.

Use Method II if a more refined calculation of D tb is desired by the station (i.e., use of actual release point parameters with annual or actual meteorology to obtain release-specific X/Qs) or if Method I predicts a dose I rate greater than the Technical Specification limit to determine if it had actually been exceeded during a short time interval. See Section 7.2.1 for I basis.

Compliance with the dose rate limits for noble gases are continuously demonstrated when effluent release rates are below the plant vent noble gas activity monitor alarm setpoint by virtue of the fact that the alarm setpoint is based on a value which corresponds to the of f-site dose rate limit, or a value below it. Determinations of dose rate for compliance with Technical Specifications are performed when the effluent monitor alarm setpoint is exceeded, or as required by the Action Statement (Technical Specification 3.3.3.10 Table 3.3-10) when the monitor is inoperable.

I (I) The Turbine Building vent ground level release X/Os are used in the ODCM Method I equations. This is to conservatively account for the I station vent stack, and, any potential ground level releases.

I I B.3-8 I

5.2 Gaseous Effluent Instrumentation Setpoints l

Technical Specification 3.3.3.10 requires that the radioactive gaseous ef fluent instrumentation in Table 3.3-13 of the Technical Specifications have their alarm setpoints set to insure that Technical Specification 3.11.2.1 is not exceeded.

5.2.1 Plant Vent Wide-Range Gas Monitors (RM-6528-1.2 and 3)

I ,

The plant vent wide-range gas monitors are shown on Figure B.6-2.

5.2.1.1 Method to Determine the Setpoint of the Plant Vent Wide Range Gas Monitors (RM-6528-1.2 and 3)

The setpoint for the plant vent wide-range gas monitor (readout response in uti/sec) is set by limiting the off-site noble gas dose rate to l the total body or to the skin, and is denoted Rsetpoint' "setpoint 5 I lesser of:

I R tb

= 806 1

DFB C

(5-5) 3 pCi/sec (mrem-uti-m ) I pCi-vr}

-pCi- m 3 mrem-m and:

R = 3,000 (5-6) l skin 0F.

C I pCi/sec (mrem) yr uti-(mrem sec vr )

where:

R = Response of the monitor at the limiting total body dose g rate (pCi/sec) l lI I B.5-9 I

I 500 mrem-uCi-m

~ )

~E (lE+06) (6.2E-07)

I 500 - Limiting total body dose rate (mrem /yr)

= Number of pCi per pCi (pCi/pCi)

I 1E+06

= [X/Q)T, maximum annual average gama atmospheric dispersion I 6.2E-07 factor (sec/m )

DFB = Composhe Mal W h MW W @M c

I hgDFB j i

(5-7)

E6' i I

hg = The release rate of noble gas "i" in the mixture, for each noble gas identified in the off-gas (pci/sec)

I DFB 4

= Total body dose f actor (see Table B.1-10) (mrem-m /pCi-yr)

I R 5 "

= Response of the monitor at the limiting skin dose rate (pCi/sec) l I 3,000 = Limiting skin dose rate (mrem /yr)

I DF' = Composite skin dose factor (mrem-sec/pci-yr) hj OFj i

= (5-8)

I b3 i

I I B . 5-10 1 I

DF' i = Combined skin dose factor (see Table B.1-10)

(mrem-sec/pCi-yr)

5. 2.1. 2 Plant Vent Wide Range Gas Monitor Setooint Example The following setpoint example for the plant vent wide range gas I monitors demonstrates the use of equations 5-5 and 5-6 for determining setpoints.

This setpoint example is based on the following data (see Table B.1-10 for DFBg and DF ):

h3 DFB 3

DFj i (uti) s,c (mrem-m oci-vr I Imrem-sec}

uCi-vr Xe-138 1.03E+04 8.83E-03 1.21E-02 Kr-87 4.73E+02 5.92E-03 1.77E-02 Kr-88 2.57E+02 1.47E-02 1.38E-02 Kr-85m 1.20E+02 1.17E-03 2.86E-03 Xe -135 3.70E+02 1.81E-03 3.89E-03 Xe-133 1.97E+01 2.94E-04 6.66E-04 DFB g i

DFB c" .

(5-7) i i i hg DFB$ = (1.03E+04)(8.83E-03) + (4.73E+02)(5.92E-03)

+ (2.57E+02)(1.47E-02) + (1.20E+02)(1.17E-03)

+ (3.70E+02)(1.81E-03) + (1.97E+01)(2.94E-04)

= 9.83E+01 (uci-mrem-m /sec-pci-yr)

I h4 = 1.03E+04 + 4.73E+02 + 2.57E+02

!I B.5-11 l I

+ 1.20E+02 + 3.70E+02 + 1.97E+01 I = 1.15E+04 pCi/sec 9.83E+01 0FB c = 1.15E+04

= 8.52E-03 (mrem-m /pCi-yr)

Rtb = 806 DFB c

= (806) (8.52E-03)

I = 9.46E+04 pCi/sec and next; bg DFj DF' = - (5-8) l bbi j

h$DFj = (1.03E+04)(1.21E-02) + (4.73E+02)(1.77E-02) i

+ (2.57E+02)(1.38E-02) + (1.20E+02)(2.86E-03)

+ (3.70E+02)(3.89E-03) + (1.97E+01)(6.66E-04)

= 1.38E+02 (uci-mrem-sec/sec pci-yr)

DF' = 1.38E+02 c 1.15E+04

= 1.20E-02 (mrem-sec/pci-yr)

R skin *

• DF' lI c I B . 5-12 I

= (3,000)

(1.20E-02)

= 2.50E+05 uti/sec r %e The setpoint, R s ht, is the lesser of Rtb and R skin.

noble gas mixture in this example R b is less than R skin, n cadng dat the total body dose rate is more restrictive. Therefore, in this example the I plant vent wide-range gas monitors should each be set at 9.46E+04 pCi/sec above background, or at some administrative fraction of the above value.

l In the event that no activity is expected to be released, or can be measured in the system to be vented, the gaseous monitor setpoint should be based on Xe-133.

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MONITOR Figure B.6-2 Gaseous Effluent Streams, Radiation Monitors, and Radwaste Treatment System at Seabrook Station I B.6-3 E

M M M M M M M m e e a e e a g g g TABLE B.7-1 Usage Factors for Various Liquid Pathways at Seabrook Station ~ '

(From Reference A, Table E-5*, except as noted. Zero where no pathway exists)

MILK MEAT FISH INVERT. POTABLE SHORELINE SWIMMING *** BOATING ***

AGE VEG. LEAFY VEG. WATER (KG/YR) (KG/YR) (KG/YR) (LITER /YR) (HR/YR) (HR/YR) (HR/YR)

(KG/YR) (KG/YR) (LITER /YR) 0.00 0.00 21.00 5.00 0.00 334.00** 8.00 29.00 Adult 0.00 0.00 0.00 0.00 16.00 3.80 0.00 67.00 45.00 52.00 Teen 0.00 0.00 0.00 0.00 0.00 6.90 1.70 0.00 14.00 28.00 52.00 Child 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Infant 0.00 0.00 Y

z~

• Regulatory Guide 1.109

• • Regional shoreline use associated with mudflats - Maine Yankee Atomic Power Station Environmental Report

• • • HERMES; "A Digital Computer Code for Estimating Regional Radiological Ef fects f rom Nuclear Power Industry," l HEDL, December 1971 l 1 l

mmmm

where:

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D coE and D coR = the critical organ dose rates to an individual at the Education Center and the " Rocks", respectively.

Og = defined previously.

and DF'icoR = the critical organ dose rate factors for I

DF' coE radionuclide "i" for the Education Center and the " Rocks," respectively (see Table B.1-14.)

I 7.2.7.4 Garnma Dose to Air From Noble Gases Method I was derived f rom Equation (7-14):

T T Q DF (7-14 )

D = 3.17E+04 [X/Q]Y i i ir $

substituting

[X/Q]T = 2.0E-06 sec/m3 (Education Center)

= 5.9E-06 sec/m3 (The " Rocks")

I multiplying by 0F = 0.0014 (Education Center)

= 0.0076 (The " Rocks")

I and lE-06 Ci/pci I

I

.I B.7-18 I

gives I T (7-23)

Qi DF i D

aire

= 8.88E-H $

WaO T (7-24)

Qi DF i (mrad)

D}irR = 1.42E-09 g where:

= the gamma air doses to an individual at the D

aire and D airR Education Center and the " Rocks," respectively.

O g = total activity (pCi) released to the atmosphere via the station vents of each radionuclide "i".

DF} and DF} = defined previously.

7.2.7.5 Beta Dose to Air From Noble Gases I

Method I was derived f rom Equation (7-15):

I B Qi DF i ( 7-15)

Dair = 3.17E+04 X/Q g substituting X/Q = 6.7E-06 sec/m3 (Education Center)

= 2.3E-05 sec/m (The " Rocks")

multiplying by I 0F = 0.0014 (Education Center)

= 0.0076 (The " Rocks")

and lE-06 Ci/pci B.7-19 I

gives l

O Oi DF ( -25)

DairE = 2.97E-10 i (mrad) l l

0 0

= 5.54E-09 Oi DF (mrad)

( - 6) airR i where:

B 0 D

aire and 0airR = Center the beta air doses to an individual at the Education and the " Rocks," respectively.

Q4 = total activity (pCi) released to the atmosphere via the station vents of each radionuclide "i".

DF and DF = defined previously.

l 7.2.7.6 Critical Organ Dose From Iodines. Tritium and Particulates With l Half-Lives Greater Than Eight Days I Method I was derived in the same manner as Equation (3-8):

Q DFG O

co

=

i ico (3-8) multiplying by ,

OF = 0.0014 (Education Center) l

(

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= 0.0076 (The " Rocks")

JB . and lE-06 Ci/pCi; plus substituting the location specific DFGs fg gives l

0 DFG i g (mrem) (7-27) g D< < = 0.0014 i Oi DFG bR (mrem) (7-28)

DcoR = 0.0076 i B.7-20 l

7.3.2 Seabrook Station Atmospheric Dispersion Model I The time average atmospheric dispersion factors are computed for g

a routine (long-term) ground level releases using the AE0LUS Computer Code (Reference B). AE0LUS is based, in part, on the straight-line airflow model discussed in Regulatory Guide 1.111 (Reference C).

AE0LUS produces the following average atmospheric dispersion f actors for each location:

I 1. Undepleted X/Q dispersion factors for evaluating ground level l

i concentrations of noble gases; I

2. Depleted X/Q dispersion factors for evaluating ground level concentrations of iodines and particulates; l

l 3. Gamma X/Q dispersion factors for evaluating gamma dose rates f rom a sector averaged finite noble gas cloud (multiple energy undepleted source); and

4. D/0 deposition factors for evaluating dry deposition of elemental I radioiodines and other particulates.  ;

I Gamma dose rate is calculated throughout this ODCM using the finite cloud model presented in " Meteorology and Atomic Energy - 1968" (Reference E, j Section 7-5.2.5. That model is implemented through the definition of an effective gamma atmospheric dispersion factor, [X/Q ]T(Reference B, Section 6), and the replacement of X/Q in infinite cloud dose equations by the T '

[X/Q ].

7.3.3 Lona-Term Average Atmospheric Dispersion Factors for Receptors l

Actual measured meteorological data for a two-year period, April-1979 l through March-1980, and . lune-1980 through May-1981, were analyzed to determine l the locations of the maximum off-site average atmospheric dispersion factors.

Each dose and dose rate calculation incorporates the maximum applicable off-site long-term average atmospheric dispersion factor. The values used and their locations are summarized in Tables B.7-4 and B.7-5.

B.7-26

DFB

• c i i i i i mrem-m pCi-yr Iuti) sec Iuti) sec mrem-m pCi-yr )

Solving Equation 8-11 for DFB yields:

hj DFB 4

=

i (5-7) 0FB bg i

Technical Specification 3.11.2.1.a limits the dose rate to the total body from noble gases at any location at or beyond the site boundary to 500 g

mrem /yr. By setting D b equal to 500 mrem /yr and substituting DFB for DFB $

in Equation 3-3, one may solve for [ Q$ at the limiting whole body noble gas l I

dose rate:

h=4 806 DFB i C Iuti) sec "Imrem uCi-m ) IDCi-vr3) yr-pCi-sec mre n Substituting this result f or [ h in$Equation 8-10 yields Rtb, the response l of the monitor at the limiting noble i gas total body dose rate:

R tb

= 806 S g h DFB c

I ICPS) " Imrem yr-pCi-sec uCi-m ) Icom-cm pCi ) Isec) c ,3 I

DCi-vr mrem-m The skin dose rate due to noble gases is determined with Equation 3-4: l b "

i skin i i

mrem) , uCi) yr sec mrem-sec) pCi-yr B.8-7 I

where:

Og = Skin dose rate (mrem /yr) h3 = As defined above.

DF' = Combined skin dose factor (see Table B.1-10) (mrem-sec/pci-yr) i A composite combined skin dose factor, DF', may be defined such that:

I DF' hg = hg DFj (8-14) i i uCi) mrem-sec) g mrem-sec) pCi-yr uCi) sec set pCi-yr Solving Equation 8-14 for DF' yields:

bg DFj DF' = (5-8) bi i

Technical Specification 3.11.2.1.a limits the dose rate to the skin l f rom noble gases at any location at or beyond the site boundary to 3,000 mrem /yr.

By setting D skin equal to 3,000 mrem /yr and substituting DF' for DFj in Equation 3-4 one may solve for [Og at the limiting skin noble gas dose rate: l 1

h = 3,000 4 DF' i c uti-vr uCi) sec mrem) yr mrem-sec)

Substituting this result for [ h in Equation g 8-10 yields Rskin, the response of the monitor at the limiting noble i gas skin dose rate:

I B.8-8 I

j .

(8- W R skin = ,000 S g h DF, 3

uCi-vr (cpm) (mrem) Icom-cm pCi ) cIsec) Imrem-seh yr ,3 l

As with the liquid monitoring system, the gaseous monitoring system is ig E also designed to incorporate the detector efficiency, gS , into its software. The monitor also converts the response output to a release rate (pCi/sec) by using a real time stack flow rate measurement input. Therefore, multiplying by the stack flow rate measurement (F), the Equations 9-15 and 8-16 become:

R = 806 tb DFB c

I Iuti) sec " Imrem-uCi-m yr-pCi-sec ) I DCi-vr mrem-m 3

= 3000 (5-6)

R skin h',

I (pC1) ,{mremy sec yr uti-vr mrem-sec) 8.3 Basis for PCCW Head Tank Rate-of-Change Alarm Setpoint I The PCCW head tank rate-of-change alarm will work in conjunction with the PCCW radiation monitor to alert the operator in the Main Control Room of a leak to the Service Water System from the PCCW System. For the rate-of-change alarm, a setpoint based on detection of an activity level of 10~ pCi/cc in I the discharge of the Service Water System has been selected. This activity level was chosen because it is the minimum detectable level of a service water monitor if such a monitor were installed. The use of rate-of-change alarm with information obtained from the liquid sampling and analysis commitments described in Table A.3-1 of Part A ensure that potential releases f rom the Service Water System are known. Sampling and analysis requirements for the Service Water System extend over various operating ranges with increased 1 sampling and analysis at times when leakage from the PCCW to the service water l 13 occurring and/or the activity level in the PCCW is high.

l 1

B.8-9

_ _ _ _ _ _ _ _ .