ML17262A977

Rev 5 to ODCM for Ginna Station.

ML17262A977
Person / Time
Site:	Ginna
Issue date:	03/13/1992
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17262A975	List: ML17262A974 ML17262A976 ML17262A977 ML17262A978
References
PROC-920313, NUDOCS 9209030119
Download: ML17262A977 (40)

Text

Offsite Dose Calculation Manual for Ginna Station Rochester Gas and Electric Corporation Revision 5 March 13 1992 9209030119 920828 PDR ADOCK 05000244 R PDR

s Ginna Station Offsite Dose Calculation Manual TABLE OF CONTENTS .

Radiological Effluent Technical Specification Dose Calculation Section Manual Pa e 3.5.5 Z. Liquid Effluent Monitor Setpoints 4 '2 '

3.5.5 ZZ. Gaseous Effluent Monitor Setpoints 4.12 '

3.9. 1. 1 III. Liquid Effluent Concentrations Release 3 ~ 9~1~2 IV. Liquid Effluent Dose 10 3 ~ 9 ~ 1.3 V. Liquid and Gaseous Radwaste 14 3.9.2.3 Treatment and Operability 5.5 3.9 ~ 2 ~ 1 VZ. Gaseous Effluent Dose Rate 18 3 ' ' ' VZZ. Gaseous Effluent Doses 20 4 ~ 10 ~ 1 VZZZ. Environmental Monitor Sample 22 Locations 3.9 ' ' ZX. Preparation of Special Report to 35 Demonstrate Compliance with Environmental Radiation Protection Standards X. References 36

LIST OF TABLES AND FIGURES Pa<ac Table 1 Dose Parameters for Radioiodines and Radioactive Particulate, Gaseous Effluents Table 2 Dose Factors for Noble Gases and Daughters Table 3 Dispersion Parameter (X/Q) for Long Term Releases, 28 Plant Vent Table 4 Dispersion Parameter (D/Q) for Long Term Releases, 29 Plant Vent Table 5 Dispersion Parameter (X/Q) for Long Term Releases, 30 Containment Purge Table 6 Dispersion Parameter (D/Q) for Long Term Releases, 31 Containment Purge Table 7 Dispersion Parameter (X/Q) for Long Term Releases, 32 Ground .Vent Table 8 Dispersion Parameter (D/Q) for Long Term Releases, 33 Ground Vent Table 9 Pathway Dose Factors Due to Radionuclide Other Than Noble Gases S4

~

\

Figure 1 Ginna Station Liquid Waste Treatment System 16 Figure 2 Ginna Station Gaseous Waste Treatment and 17 Ventilation Exhaust Systems Figure 3 Location of Onsite Air Monitors and Post Accident TLDs 24 Figure 4 Location of Farms for Milk Samples and Ontario Water 25 District Intake Figure 5 Location of Offsite TLDs 26 Figure 6 Location of Offsite Air Monitors 27

I. Li id Effluent Monitor Set oints The Ginna Technical Specifications, Section 3.5.5, require alarm and/or trip setpoints for radiation monitors on each liquid effluent line (reference 1). Precautions, limitations and setpoints applicable to the operation of Ginna Station liquid effluent monitors are provided in plant procedures P-9 and RD-13.1. Setpoint values are calculated to assure that alarm and trip actions occur prior to exceeding the limits of 10 CFR 20 at the release point to the unrestricted area. For added con-servatism, liquid effluent release rates are administratively set so that only small fractions of the applicable 10 CFR 20 maximum permissible concentrations can be reached in the discharge canal.

The calculated alarm and trip action setpoints for each radioactive liquid effluent line monitor and flow determination. must satisfy the following equation:

Equation (1): cf < C F+f Where:

C the effluent concentration which implements the 10 CFR 20 limit for unrestricted areas, in uCi/ml.

c = the setpoint of the radioactivity monitor measuring the radioactivity concentration in the discharge line prior to dilution and subsequent release, in uCi/ml.

f= the flow as meas'ured at the radiation monitor location, in volume per unit time, in the same units as F below.

F ~ the dilution water flow as determined prior to the release point, in volume per unit time.

Liquid effluent batch releases from Ginna Station are discharged through a liquid waste disposal monitor. The liquid waste stream (f) is diluted (by F) in the plant discharge canal before it enters Lake Ontario.

The limiting batch release concentration (c) corresponding to the liquid waste monitor setpoint is calculated from the above ex-pression. Since the value of (f) is very small in comparison to, (F), the expression becomes:

Equation (2): c < CF f

Where:

C = the maximum permissible concentration of gross beta, gamma activity above background in the circulating water discharge at the unrestricted area boundary (1 x 10 7 uCi/ml).

F the dilution flow assuming operation. of only 1 circulating water pump (170,000 gpm).

f ~ thethe maximum waste effluent discharge rate through designated pathway.

The limiting release concentration (c) is then converted to a k

setpoint count rate by use of the monitor calibration factor determined per procedure RD-13.1. The expression becomes:

Equation (2a): Setpoint (cpm) ~ c uCi m Cal. Factor (uCi/ml per cpm)

~Exam le (Liquid Radwaste Monitor R-18):

Zf one assumes, for example, that the maximum pump effluent discharge rate (f) is 30 gpm, then the limiting batch release concentration (c) would be determined as follows:

</

30 (gpm) c < 5.7 x 10"4 (uCi/ml)

The monitor R-18 alarm and trip setpoint (in cpm) is then deter-mined utilizing the monitor calibration factor calculated in plant procedure RD-131. Assuming a calibration factor of 9.5 x 10 9 ~uol ml cpm j

limiting batch release concentration determined and a above the alarm and trip setpoint for monitor R-18 would be:

~

9.5 x

'Lx I I 18 9 ~udi ml 1 P cpm The setpoint values for the Containment Fan Cooler Monitor (R-16), Spent Fuel Pit Heat Exchanger Service Water Monitor (R-20),

Steam Generator Blowdown Monitor (R-19), the Retention Tank Monitor (R-21), and the All Volatile Treatment Waste Discharge Monitor (R-22) are calculated in a similar manner using Equation (2), substituting appropriate values of (f) and the corresponding calibration factor.

I

~l '%

~

rQ TZ. Gaseous Effluent Monitor Set pints The Ginna Technical Specifications (reference 1) require alarm

,and/or trip setpoints for specified radiation monitors on each

'noble gas effluent line. Precautions, limitations and setpoints applicable .to the operation of Ginna Station gaseous effluent monitors are provided in plant procedures P-9 and RD-13.1.

Setpoints are conservatively established for each ventilation noble gas monitor so that dose rates in unrestricted areas corresponding to 10 CFR Part 20 limits will not be exceeded.

Setpoints shall be determined so that dose rates from releases of noble gases will comply with the Technical Specification require-ments of 3.9.2.1.a(i), which 'stipulate that the dose, rate for noble gases shall be < 500 mrem/yr to the total body and < 3000 mrem/yr to the skin.

The calculated alarm and trip action setpoints for each radioactive gaseous effluent monitor must satisfy the following equation:

Equation (3).: c < ~iv f'k'K Where:

c ~ setpoint in cpm Qiv = release rate limit by specific nuclide in uCi/sec f ~ discharge flow rate in cfm k units conversion factor (cc/sec/cfm)

I K = calibration factor (uCi/cc/cpm)

The general methodology for establishing plant ventilation monitor setpoints is based upon a vent concentration limit (in uCi/cc) derived from site specific meteorology and vent release characteristics.

Additional radiation monitor alarm and/or trip setpoints are calculated for radiation monitors measuring radioiodines, radio-active materials in particulate form and radionuclides other than noble gases. Setpoints are determined to assure that dose rates from the release of these effluents shall comply with Technical Specification 3.9.2.l.a(ii), which requires that the dose rate for all radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days shall be < 1500 mrem/yr to any organ.

The release rate limit for noble gases shall be calculated by the following equation for total body dose:

Equation (4):

Qiv (uCi/sec) 500 mrem r Ki (mrem/yr per uCi/m ) ~

275v (sec/m )

and by the following equation for skin doses:

Equation (5):

Qiv (uCi/sec) 3000 mrem r (Li + 1.1Mi)(mrem/yr per uCi/m ) ~

~X Qv (sec/m )

Where:

Ki The total body dose factor due to gamma emissions for each identified noble gas radionuclide, (in mrem/yr per uCi/m ) from Table 2.

Li The skin dose factor due to beta emissions for each identified noble gas radionuclide, (in mrem/yr per uCi/m ) from Table 2.

Mi The air dose factor due to gamma emissions for each identified noble gas radionuclide, (in mrad/yr per uCi/m ) from Table 2 (unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose).

X/Qv The highest calculated annual average dispersion parameter for estimating the dose to the critical offsite, receptor from vent release point (v) (in sec/m ). The ~X Qv is calculated by the method described in Reg. Guide 1.111 (reference 6).

Qiv The release rate of radionuclide (i) from vent (v) which results in a dose rate of 500 mrem/yr to the whole body or 3000 mrem/yr to the skin of the critical receptor, (in uci/sec).

Historically, xenon-133 is the principal noble gas released from all vents and is appropriate for use*Theas whole the reference isotope for body dose will be establishing monitor setpoints.

limiting, and the Xe-133 release rate limit is(4)'. calculated by substituting the appropriate values in equation After the release rate limit for Xe-133 is determined for each vent, the corresponding vent concentration limits are calculated based on applicable vent flow rates. Annually-derived monitor calibration factors (uCi/cc per cpm) convert limiting vent concentrations to count rate.

Containment Plant. Vent and Air E ector Noble Gas Monitors Monitors R-12 R-14 and R-15 Monitor R-12 measures noble gas activity in containment when is isolated, or in the containment vent during purge releases.

it Noble gases being released via the plant vent are detected by R-14; Monitor R-15, on the air e)ector, normally indicates only background noble gas activity; however it serves as one of the first indicators o f primary-to-secondary leakage. 1 Additional noble gas monitoring capability'or the containment, plant and air e)ector vents is provided'y high-range effluent monitors R-12A, R-14A and R-15A, respectively.

J Noble gas monitor setpoints are conservatively set in Procedure P-9 to correspond to fractions of the applicable 10 CFR 20 maximum permissibleconcentrations (MPCs) for unrestricted areas.

Fractions are small enough to assure the timely detection of any simultaneous discharges from multiple'elease points before the combined downwind site boundary concentration could exceed MPC.

Additional conservatism is provided by basing these setpoints upon instantaneous downwind concentrations. Release rates during the remainder of a given year, combined with any infrequent releases at setpoint levels, are likely to result in only a very small fraction of the 10 CFR 20 annual limits.

~Eam le: (Plant vent monitor R-14).

Using Xe-.133 as the controlling isotope for the setpoint and assuming a measured activity at 2.66E>>4 uCi/cc, a ratemeter reading of 4750 cpm above background and a vent flow of 7.45 E4 cfm.

Xe-133 efficiency = Activit Net Ratemeter Reading Xe-133 efficiency 2.66E-4 ~ 5.6E-8 ~u 3~c 4750 cpm QA (Ki)(X/Qv)

Qiv = 500 ~ 6.3E5 uCi/sec (2. 94E2) (2 7E-6)

~

setpoint c ~ iv (f) (k) (K) 6.3E5 uCi sec 7.45E4 (cfm) 472 ~cc eec 5.6E-S ~uci cc cfm cpm c 3.2E5 cpm (R-14 is set at 1/20 of this value, per Procedure P-9 or 1.6E4 cpm for normal operation).

1. NOTE: Continuous radioiodine and particulate monitoring on the air ejector is not required. Calculations and plant measurements have indicated that the iodine and particulate source terms via the air ejector compared to other airborne release pathways, are negligible.

(See references 5,7, and 8)

DQSE PARAM.'rKRS FOR RADIOIODINES AND RADICACPIVE PARPICUGQR GASKX3S 1~IIJEHIS*

Pi Pi Pi Pi Radio- Inhalatian Pathwa Food & Ground Pathways Radio- Inhalatian Pathway Food & Grad Pathways nuclide uCi g +m2 uCi sec nuclide uCi Qm2 uCi sec H-3 6.5E+02 2.4E+03 Od-115m 7.0E+04 4.8E+07 C-14 8.9E+03 1.3E+09 Sn-126 1.2E+06 1.1E+09 Cr 51 3.6E+02 1.1E+07 Sb-125 1.5E+04 1.1E+09 Rn-54 2.5E+04 1.1E+09 Te-127m 3.8E+04 7.4E+10 Fe-59 2.4E+04 7.0E+08 Te-129m 3.2E+04 1.3E+09 Co-58 1.1E+04 5.7E+08 Te-132 1.0E+03 7.2E+07

~0 Zn-65 3.2E+04 6.3E+04 4.6E+09 1.7E+10 Cs-134 Cs-136 7.0E+05 1.3E+05 5.3E+10 5.4E+09 Rb-86 1.9E+05 1.6E+10 Cs-137 6.1E+05 4.7E+10 Sr-89 4.0E+05 1.0E+10 Ba-140 5.6E+04 2.4E+08 S~O 4.1E+07 9.5E+10 Ce-141 2.2E+04 8.7E+07 Y-91 7.0E+04 1.9E+09 Ce-144 1.5E+05 6.5E+08 Zr-95 2.2E+04 3.5E+08 Hp-239 2.5E+04 2.5E+06

~5

~9 1.3E+04 2.6E+02 3.6E+08 3.3E+08 I-131 I-133 1.5E+07 3.6E+06 1.1E+12 9.6E+09 Ru-103 1.6E+04 3.4E+10 V~mtified 4.1E+07 9.5E+10 Ru-106 1.6E+05 4.4E+ll Ag-llQm 3.3E+04 1.5E+10

• 'The listed dose parameters are for radianuclides that may be detected in gasecas effluents. 'Ihese and additianal dose parameters for isotopes not included in Table 1 may be calculated using the methodology described in NUR1H-0133, Section 5.2.1 (reference 2) .

TABLE 2 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*

Total Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor Ki Li Mi Ni Radionuclide mrem r uci m3J mr er uci m3> mrad r r uCi m3$ mrad r uCi m3$

Kr-83m 7.56E-02** 1.93E+Ol 2.88E+02 Kr-85m 1.17E+03 1. 46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+Ol 1.34E+03 1.72E+Ol 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

• The listed dose factors are for radionuclides that may be detected in gaseous effluents. These dose factors for noble gases and daughter nuclides are taken fram Table B-1 of Regulatory Guide 1.109 (reference 3). A semi-infinite cloud is assumed.

• • 7.56E-02 = 7.56 x 10

~ ~ 1 a III. Li id Effluent Release Concentrations Liquid batch releases are controlled individually and each batch release is authorized and based upon sample analysis and the existing dilution flow in the discharge canal. Plant procedures RD-7 and RD-8 establish the methods for sampling and analysis o' each batch prior to release. A release rate limit is'alculated for each batch based upon analysis', dilution 'flow and all procedural conditions being met before it is authorized for release. The waste effluent stream entering the discharge canal is continuously monitored and the release will be automatically terminated if the pre-selected monitor setpoint is exceeded.

(See Section I)

If lieu gross beta analysis is performed for each batch release in of gamma isotopic analysis, then a weekly composite for principal gamma emitters and I-131 is performed. Additional monthly and quarterly composite analyses are to be performed as specified in Table 4.12-1 of the Ginna Technical Specifications.

I The equations used to calculate activity're:

Ga a S ectromet uCi/cc Act.

eak area counts - bk d counts (Count Time)(Eff)(Vol)(T1/2 correction)(3.7E4)(Branching Fraction)

Gross Beta Gamma:

uCi/cc Act. total counts - bk d counts (Count Time) (Eff) (Vol) (T1/2 correction) (3.7E4) where: count time is in seconds; eff counting efficiency, in counts er sec disintegrations per sec vol volume, in milliliters; Tl/2 correction decay correction factor, dimensionless; 3.7E4 ~ conversion constant, in disinte rat ons er sec; uci Branching fraction is the fraction disintegrating by a particular decay mode, dimensionless.

ZV. Li id Effluent Dose The dose contribution received by the maximally exposed individual from the ingestion of Lake Ontario 'fish and drinking water is determined using the following methodology. These calculations will assume a near field dilution factor of 1.0 in evaluating the fish pathway dose, and a dilution factor of 20 between the plant discharge and the Ontario Water District drinking water intake located 1.1 miles away (Figure 4). .The dilution factor of 20 was derived from drift and dispersion studies documented in reference 4.

Dose contributions from shoreline recreation, boating and swimming have been shown to be negligible in the Appendix I dose analysis (reference 5) and do not need to be routinely evaluated. Also, there is no known human consumption of shellfish from Lake Ontario.

The dose contribution to an individual will be determined to ensure that it complie's with the Technical Specification require-ments of 3.9.1.2.a(i) and 3.9.1,2.a(ii). The dose or dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas shall be limited: (i)

During any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ, and, (ii) During any calendar year to <

3 mrem to the total body and to < 10 mrem to any organ. Offsite receptor doses will be determined for the limiting age group and organ, unless census data show that ~actua of fsite individuals are of a less limiting age group.'he following expression is used to calculate ingestion pathway dose contributions for the total release period 1

~tj from all radionuclides identified in liquid effluents released to unrestricted areas:

Equation (6): D< Z [A~ p 1

~tj Cij Fj]

where:

D< ~ the cumulative dose commitment to the total body or any organ, z, from the liquid effluents for the total time period (in mrem). m 1

&tjf

~tj = the length of the jth time period over, which Ciq and Fj are averaged for all liquid releases, (in hours).

10

Ci) the, average concentration of radionuclide, .i, in undiluted liquid effluent during time period ~t~ from any liquid release, (in uCi/ml).

Ai< the .site-related ingestion dose commitment factor to the total body or any organ 'C for each identified

,principal gamma and beta emitter (in mrem/hr per uCi/ml). See equation (7) ~

F) the discharge canal dilution factor for Ci during any liquid effluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the average flow from the site discharge structure to unrestricted 'receiving waters. The dilution factor will depend on the number of circulation pumps operating and, during icing conditions, the percentage opening of the recirculating gate. Reference curves are presented in plant procedure RD-7.

Equation (7): Aig = ko (Uw/Dw + UFBFi) DFi where:

Aig the site-related ingestion dose commitment factor to the total body or to any organ 'C for. each identified principal gamma and beta emitter, (in mrem/hr per Gci/ml) ~

ko units conversion factor, 1.14 x 10 10 pCi/uCi x 10 ml/kg + 8760 hr/yr.

Uw a receptor person's water consumption by age group from table E-5 of Regulatory Guide 1.109 (reference 3).

Dilution factor from the near field area of the release point to potable water intake. The site specific dilution factor is 20. This factor is assumed to be 1.0 for the fish ingestion pathway.

UF a receptor person's fish, consumption by age group fiom table E-5 of Regulatory Guide 1.109.

BFi Bioaccumulation factor for nuclide, i, (in fish pCi/kg per PCi/L), from Table A-1 of Regulatory Guide 1.109.

DFi Dose conversion factor for the ingestion of nuclide, for a receptor person in pre-selected organ, 7 , (in mrem/pCi), from Tables E-ll, E-12, E-13, E-14 of Regulatory Guide 1.109.

11

The monthly dose contribution from releases for which radionuclide concentrations are determined by periodic composite sample analysis may be approximated by assuming an average monthly concentration based on the previous monthly or quarterly composite analyses. However, in the radioactive effluent release report (submitted within 60 days of January 1 per Technical Specification 6.9.1.4) the calculated dose contributions from these radionuclides shall be based on the actual composite analyses.

Exam le wh ch llustrates how to com ute the dose to t e whole bod via the f sh and drinki water athwa s assumin an initial Cs-137 dischar e concentration of 3.0 -4 uCi ml:

Given the following discharge factors, where:

= 1 hour Ci) 3 ' E-4 uCi/ml 170,000 gpm 20 And, taking the following values from Regulatory Guide 1.109 which concern the receptor of interest, which we assume is the child in this case:

Uw 510 L/year UF 6.9 Kg/year

'BFi = 2000 pCi/kg per pCi/L DFi 4.62 E-5 mrem/pCi Then, the site-related ingestion dose commitment factor, Aig, is calculated as follows:

Agg m~rem hr Ko (Uw/Dw + UF BFg) DFg uCi/ml 1.14 E5 (510 + F 9 20

'000) 4 '2 E-5 Aig 7.28'4 mrem/hr per uCi/ml

And, the whole body'dose to the child is then:

D< mrem

~ (Aig) (~t~) (C~ ) (F~) '7

~ 28 E4) (1) (3 0

~ E-4) (1. 2 E-4)

Dg = 2.6E-3 mrem to the whole body from Cs-137 (The dose contribution from any other isotopes would then need to be calculated and summed.)

13

V. Li id and Gase'ous Radwaste Treatment and 0 erabilit An objective of the Ginna Technical Specifications'which implement the overall requirements of 10 CFR Part 50, Appendix I, is to ensure that the plant radwaste treatment equipment is used and maintained. This equipment is to be utilized to reduce radioactive discharges from nuclear plants to levels "as low as reasonably achievable" or ALARA. ALARA levels warranting equipment operabil-ity have been defined by the NRC in the form of monthly dose "trigger" values. The trigger values, which are provided below, correspond to approximately 1/48 of the annual design objective doses given by 10 CFR Part 50, Appendix I. If continued at this rate, these monthly doses would correspond to just under 1/4 of the Appendix I annual design objectives.

Liquid Gaseous Ventilation Radwaste S stem Radwaste S stem Exhaust 31-day 0.06 mrem (w. body) 0.2 mrad (gamma air)

Trigger 0. 3 mrem (any organ)

Values 0.2 mrem (any organ) 0.4 mrad (beta air)

Figures 1 and 2 show the components of, the R.E. Ginna liquid and gaseous waste/ventilation exhaust systems. These systems are normally in routine use at the plant. Because discharges are being ~teated, the trigger values in the Technical Specifications may be exceeded but compliance with the stated quarterly and annual dose limits is required.

If the liquid or gaseous radwaste/ventilation exhaust systems were to be inoperable in excess 'of 31 days, then effluents are considered "untreated" waste. Should, over a 31-day period, the plant discharges exceed the dose trigger values in con'unction with extended inoperability of a waste treatment system, then Technical Specifications 3.9.1.3.b and 3.9.2.3.c apply. In this case, a 30-day report must be submitted to the Commission which identifies the inoperable equipment and describes appropriate corrective actions (see Technical Specifications 3.9.1.3.b and 3.9.2.3.c).

~Exam le:

Assume a case where plant modifications were underway on the waste evaporator and demineralizer piping, and a reduction of the liquid waste volume contained in the waste holdup tank (WHUT) was needed. Assuming no other means of treatment were readily available, WHUT liquid (untreated) might be transferred to the waste condensate tanks, sampled and then discharged on a controlled basis.

In this case, assume also that a decision was made to proceed this way at the beginning of a given month, knowing that the waste evaporator and other portions of the liquid radwaste treatment system would be unavailable for the next 45 days.

The followin method would be used to determine the need or a 30-da re ort:

Using existing plant procedures, sample the concentration contained in the WHUT (Ci~). Decide a sample frequency (e.g. 1/day) since the tank concentration could change.

2 ~ Determine the permissible release rate to maintain the concentration in the discharge canal well within the appli-cable maximum permissible concentration (e.g. 1/100-1/10 MPC) for the mixture. (The discharge canal concentration is equal to Ci~ F~).

3 ~ Calculate the incremental dose from all identified isotopes via the drinking water and fish ingestion pathways for each receptor group. The critical receptor will probably be the child. Assume the release will be continuous and that doses will be evaluated each day, corresponding to the WHUT sampling frequency. (We thus compute D using Equations 6 and 7, taking ~t~ as the duration of each release; in this case, 24 hr/day. )

4 ~ The offsite receptor dose due to a control'led discharge of the WHUT contents is thus determined and cumulated over each daily release time interval. If the WHUT isotopic mixture and the discharge canal dilution factory Fgg are relatively constant, then each day's dose increment should be approxi-mately the same. One can then estimate the number of release days trigger value.

it will take to reach the applicable dose 5 ~ The 30-day reporting requirement applies system is inoperable ~a if a dose trigger values are radwaste'reatment exceeded. In the example, one reporting criterion is already met, since the treatment .systems will be out of service for more than 31 days. If we determine that the liquid pathway dose does not exceed the trigger values. in 31 days or less, then a 30-day report is not required. However, if a liquid pathway dose attains a trigger. level within 31 days, then a report submittal would be required.

6. In the last case, it would be prudent to avoid a situation requiring the 30-day report. First, a trigger level dose, when added to the calculated doses resulting from all other liquid release sources (e.g: high conductivity waste tank, blowdown, retention tank), may significantly impact upon the plant's "dose budget" for the calendar quarter treatment or the calendar year. Also, more realistically, other options would likely be available at the plant and could be utilized.

15

GIHNA STATIOH LIQUID WASTE TREATMENT SYSTEH FIGURE 1 ENT RESIN STORAGE TANKS REACTOR COOLAHT D IH NK r .LIHE BLOWDOWN SAHPLE CONTAIHHEHT SUHP "h" OHONITOR R-19 I CHEHICAL DRAIN TANK RECYCLE S/G BLOWDOWH LINQ TO llOTWELL~

LAUHORY 4 llOT SHOWER TANKS S/G BLOMDOMH VAHK DRAIN AUX. 4 INTEiNEDIATE BLDG. DRAIHS HIXEO BEO DI

'WASTE IlOLDUP TANK ASTE EVAPORATO HIXED BED DI I

llIGll I WASTE ONOUCTIVITY I CONDENSATE WASTE HONITOR R-22 grCIRCULATING WATER I TANK TANK DISCllARGE I'/

I

'WASTE TURBINE BLDG HONITOR'-21 HONITOR R-18 COHDEHSATE DRAINS TANK HONITOR R-20 SFP HX

~ SERVICE HATER HOHITOR R-16 CV PAN COOLER

G)HNA STATHiN GASEOUS WASTE TREATHEtlT AND,VENTItATION IXllhU'l'YSTEHS FIGURE 2 AUXILIARY BUILDING "G"FILTERS MONITORS R-108,13,1i,lih VEHTILATIOH SYSTEN "C"FILTERS PLANT VEHT "h"FILTERS I

l2 I.

I WASTE CASFOUS WASTE CVCS GAS DECAY TANKS p,l. To emNT GAS 'COHPRESSORS VENT HONITORS TRFATHEHT SYSTFA NONITORS R-lohtll 12 12A CONTAINMENT VER CONTAINHENT PURGE CONTAIHHENT C F NONITORS R-15 ~ R-15A COHDFNSER AIR EJECTOR OFFGAS VENT NOTE- h IIEPA FILTi'.RS C~CNARCOAL FILTERS F~FANS

yZ. Gaseous Effluent Dose Rate Gaseous effluent monitor setpoints as described in Section jZ of this'anual are established at. concentrations which permit some margin for corrective action to be taken before exceeding offsite dose rates corresponding to 10 CFR Part 20 limitations. Plant procedures RD-l.l, RD-1.2, RD-2, RD-3, RD-5 and RD-12 establish the methods for sampling and analysis for continuous ventilation releases and for containment purge releases. Plant procedure RD-6 establishes the methods for sampling and analysis prior to gas decay tank releases. The instantaneous dose rate in unrestricted areas due to unplanned releases of airborne radioactive materials may be averaged over a 24-hour period according to Technical Specification 3.9.2.1.b. Dose rate shall be determined using the following expressions:

For noble gases:

Equation (8): D P [Ki (X/Q)>> Qi>>] ( 500 mrem/yr (to total body)

Equation (9): D )f [(Li + l.l Mi) (X/Q)>> Qi>>] 5 3000 mrem/yr

( total gamma and beta dos'e to the skin)

For radioiodines, radioactive materials in particulate form, 'and radionuclides other than noble gases:

Equation (10): D p [Pi W>> Qi>>] 5 1500 mrem/yr (critical organ)

Ki The total body dose factor due to gamma emissions for each identified noble gas radionuclide, (in mrem/yr per uCi/m from Table 2).

Li = The skin dose factor due to beta emissions for each identified noble gas radionuclide, (in mrem/yr per uCi/m3 from Table 2).

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide, (in mrad/yr per uCi/m from Table 2), (unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose).

Pi The dose, parameter for radionuclides other than noble gases for the inhalation pathway, in mrem/yr per ucigm3 and for food and ground plane pathways, (in m mrem/yr per uci/sec) from Table 1. The dose factors are based on the critical individual organ and most restrictive age group.,

18

(~/0) v The highest calculated annual average relative concen-tration for any area at or beyond the unrestricted area boundary, (in sec/m ).

Wv = The highest annual. average dispersion parameter for estimating the dose to the critical receptor; (in sec/m for the inhalation pathway, and in m for the food and ground pathways).

<iv = The release rate of radionuclide uCi/sec),

i from vent (v), (in 19

VII. Gaseous Effluent Doses The air dose in unrestricted areas due to noble gases released in gaseous effluents from the site shall be determined using the following expressions:

During any calendhr year, for gamma radiation:

Equation (ll): D< 3.17 x 10 8 E i [Mi (X/Q) v Qiv] < 10 mrad, and During any calendar year for beta radiation:

Equation (12): = 3.17 x 10-8 Dp C i [Ni (X/Q)v Qiv] 20 mrad Where:

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide, (in mrad/yr per uCi/m from Table 2).

Ni The air dose factor due to beta emissions for each identif ied noble gas radionuclide, (in mrad/yr per uCi/m from Table 2).

(X/Q) v For vent releases. The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, including uninhabited areas, (in sec/m ).

The total gamma air dose from gaseous effluents, (in mrad).

Dp The total beta air dose from gaseous effluents, (in mrad) .

Qiv The release of noble gas radionuclides, i, in gaseous effluents from all vents, in uCi. Releases shall be cumulative over the time period.

3.17 x 10" = The inverse of the number of seconds in a year..

The dose to an individual from radioiodines and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released from the site to unrestricted areas shall be determined using the following expression:

During any calendar year:

Equation (13): DI 3.17 x 10 X.Ri [Wv Qiv], < 15 mrad i

20

Where:

~iv = The release of radioiodines, and radioactive materials in particulate form in gaseous effluents, i, with half-lives greater than 8 days, (in uCi). Releases shall be cumulative over the desired time period as appropriate.

Dz- The total dose from radioiodines and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents, (in mrem).,

Wv The annual average dispersion parameter for estimating the dose to an'ndividual at the critical location; (in sec/m for the inhalation pathway, and in m" for the food and ground pathways).

Ri ~ The dose factor for each identified radionuclide, i, (in m 'rem/yr per uCi/sec or mrem/yr per uCi/m from Table 9).

21

VIIX, Environmental Monitor Sam le Locations Figure 3 shows the onsite* indicator sample locations for airborne particulates, radioiodine and direct radiation. Respective sample locations are specified below. Also indicated on Figure 3 is the .onsite vegetable garden, as well as the placement of TLDs (locations 13-24). The onsite garden is located post,.-'ccident near the closest resident who is the maximally exposed individual.

Figure 4 gives the location of the only milk herds within 5 miles of the plant. On this map is also included the Ontario Water District intake pumping station where lake water is sampled prior

,to treatment.

Figure 5 shows the offsite control sample locations for airborne particulates, radioiodine and direct radiation. Sample stations 9 and ll are situated near population centers (Webster and Williamson) located approximately 7 miles from the Ginna site.

Ke to Fi ures 3 to 5:

~Te ~Locatio Radioiodine: 3 onsite ¹2, ¹4 and 7 3 offsite ¹9, ¹ll, and ¹12 Particulate: 7 onsite ¹2g3/4I 5@6I 7 and 13 5 offsite ¹8, 9, 10, ll and 12 Direct Radiation:

TLD 18 onsite 3r 4I 14( 15) 16I 17I 18I 19'0I and 24 21I 22 I 23 10 4-5 miles ¹31I 32I 33/ g34g 35~ 36I 37I 38I 39 and 40 ll > 5 miles ¹Sg 25'6~

9I 10I llew 12I 27I 28 I 29 and 30 Surface Water 1 control (Russell Station) 1 indicator (Ginna Condenser Hater Discharge)

• Note: "Onsite" refers to the area surrounding the Ginna plant bounded by RG&E property lines. "Offsite" refers to the area beyond the immediate RGGE property.

22

Drinking Water 1 indicator (Ontario Water District Intake)

Milk 1 control (N4) 3 indicator (Nl, 2, 3)

Fish 4 control (offshore at Russell) 4 indicator (offshore at Ginna)

Food Products 1 control 2 indicator (onsite) 23

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rALrL DISPERSION PARAMETER (D 0) FOR LONG TERM RELEASES > 500 JIR YR OR > 125 llR QTR Plant Vent Distance to the control location, in miles Sector* 0-0.5 0.5-1.0 1.0-1.5 1,5;2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 '4.5-5.0 8.3 E-8 1.7 E-8 6.1 E-9 2.5 E-.9 1.2 E-.9 7.3 E-10 5.1 E-10 4.1 E-.lo 2.9 E-10 2.5 E-10 JJYE 4.5 E-B 1.0 E-8 3.7 E-9 1.5 E-9 7.0 E-10 4.4 E-10 3.1 E-10 2.4 F..lo L.B L-10 l. 5 E-10 NE 6.5 E-& 1.5 E-8 5.4 E-9 2.2 E-9 1.0 E-9 6.5:E-10 4. 5 E 10 3. 6 E-lO 2. 6 E-10 2. 2 E-10 8.3 E-8 1.8 E-8 6.4 E-9 2.6 E-9 1.2 E-9 7.5 E-10 5.3 E>>10 4.1 E-lO 3.1 E-lO 2.6 E-10 1.4 E-7 2.9 E-8 1.0 E-8 4.2 E-9 1.9 E-9 1.2 E-9 8.6 E-10 6.7 E-10 4.8 E-10 4.1 E-10 ES" 1.4 E-7 3.0 E-8 1.1 C-8 4.3 E-9 1.9 E-9 1.2 E-9 8.7 E-10 6.7 E-10 5.2 E-10 4.5 E-10 1.3 E-7 2.7 E-8 9.3 E-9 3.7 E-9 1.7 E-9 1.0 E-9 7.7 E-10 6.1 E-10 4.6 E-10 4.0 E-10 SSE 5.8 E-8 1.4 E-B 4.7 E-9 1.9 E-9 8.9 E-10 5.6 E-10 4.1 E-10 3:5 E-10 2.7 E-10 2.3 E-10 2.8 E-& &.6 E-9 3.1 E-9 1.3 E-9 S.& E-10 3.8 E-lo 2.9 E-10 2.4 E-10 1.8 E-10 1.6 E-10 SSH 3.1 E-B 7.8 E-9 3.1 E-9 1.3 E-9 5.9 E-10 3.7 E-10 2.,7 E-10 2.2 E-10 1.8 E-10 l. 5 E-10 4.S E-B 1.0 E-B 3.6 E-9 1.5 E-9 6.8 E-10 4.4 E-10 3.1 E-10 2.5 E-10 1.9 E-10 l. 6 E-10 hSl4 5.6 E-B 1.3 E-8 4.6 E-9 1.8 E-9 8.4 E-10 5.3 E-10 3.7 E-10 2.9 E-10 2.1 E-10 l. 8 E-10 4.2 E-B 1.0 E-8 3.9 E-9 1.6 E-9 7 ' E-.10 4.7 E-10 3.3 E-10 2.6 E-10 1.9 E-10 l. 6 E-10 2.2 E-8 5.9 E-9 2.4 E-9 1.0 E-9 4.7 E 10 3.0 E-10 2.1 E-10 1.7 E-10 1.3 E-10 1. 0 E-10 h Ig 1.5 E-& 4.1 E-9 1.7 E-9 7.0 E-10 3.3 E-10 2.1 E-10 1.5 E-10 1.2 E-10 8.8 E-ll 7. 4 E-ll 4.0 E-8 9.2 E-9 3.5 E-9 1.4 E-9 6.6 E 10 4.2 E-10 2.9 E-10 2.3 E-10 1.7 E-10 l. 4 E-10

• Direction wind blows into

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TABLE 9 PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES*

Inhalation Meat Ground Plane Cow-Milk-Infant Leafy Vegetables Pathway Pathway Pathway Pathway Pathway Ri Ri .

Ri Ri Ri Radio- (mrem/yr (m2 mrem/yr (m2 mrem/yr (m2 mrem/yr (m2 mr em/yr nuclide er uCi sec H-3 1. 12E 03 2.33E 02 0. 2.38E 03 2.47E 02 CR-51 1. 70E 04 4.98E 05 5.31E 06 5.75E 06 1.63E 06 MN-54 1.57E 06 7.60E 06 1.56E 09 3.70E 07 5.38E 07 FE-59 1.27E 06 6.49E 08 3.09E 08 4.01E 08 1.10E 08 CO-58 1.10E 06 9.49E 07 4.27E 08 7.01E 07 4.55E 07 CO-60 7.06E 06 3.61E 08 2.44E 10 2.25E 08 1.54E 08 ZN-65 9.94E 05 1.05E 09 8.28E 08 1.99E 10 2.24E 08 SR-89 2 15E 06 4.89E 08 2.42E 04 1.28E 10 5.39E 09 SR-90 1.01E 08 1.01E 10 0 1.19E 10 9.85E 10 ZR-95 2.23E 6.09E 2.73E 8.76E 05 1.13E 08 I-131 I-133 1.62E 3 '4E 06 07 06 2.60E 6.45E 08 09 01 1.01E 1.43E 08 07 06 4.95E 4.62E ll 09 2.08E 3.88E 10 08 CS-134 1.01E 06 1.42E 09 7.70E 09 6.37E 10 1.96E 09 CS-136 1 71E 05 5.06E 07 1.64E 08 6.61E 09 1.60E 08 CS-137 9.05E 05 1.27E 09 1.15E 10 5.75E 10 1.80E 09 BA-140 1-74E 06 5 ~ OOE 07 2;26E 07 2.75E 08 2-03E 08 CE-141 5.43E 05 1.45E 07 1.48E 07 1.43E 07 8.99E 07

• Additional dose factors for isotopes not included in Table 9 may be calculated using the methodology described in NUREG-0133, Section 5.3.1 (reference 2).

~ g4

~ 'l ~

IX. Pre aration of S ecial Re ort to Demonstrate Com liance with Environmental Radiation protection Standards

/

Ginna Technical Specification 3.9 ' '.a requires the preparation and submittal of a Special Report to the Commission when calculated effluent release doses exceed twice the limits of Specifications 3.9.1.2.a, 3.9.2.2.a or 3.9.2.2.b. In addition, subsequent releases are to be* limited so that the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except the thyroid, which is limited to < 75 mrem) for the calendar year that includes

. the release(s) in the Special Report. This includes the dose contributions from the calendar quarter in which the limits were exceeded and the subsequent calendar quarters within the current calendar year. I The following general guidelines are presented for preparation of the Special Report:

1) The maximally exposed real member of the public will generally be the same individual considered in the Technical Specifi-cation.

2) Dose contributions to the maximally exposed individual need only be considered to be those resulting from the Ginna plant itself. All other uranium fuel cycle facilities or operations are of sufficient distance to contribute a negligible portion of the individual's dose.

3) For determining the total dose to the maximally exposed in".ividual from the ma)or gaseous and liquid effluent pa'hways and from direct radihtion, dose evaluation techniques used in preparing the Special Report may be those described in this manual or other applicable methods where appropriate.

4) The contribution from direct radiation may be estimated by effluent dispersion modelling or calculated from the results of the environmental monitoring program for direct radiation.

35

~ t X. References 1, R.E.'inna Nuclear power Plant Unit No.l, A endix A to 0 eratin License No. DPR"18 Technical S ecifications I Rochester Gas and Electric Corporation, Docket 50-244.

2 ~ USNRC, Pre aration of Radiolo ical. Effluent Technical S ecifications for Nuclear Power Plants, NUREG-0133 (October, 1978) ~

3 ~ USNRC, Calculatio of Annual Doses to Man from Routine Releases of Reactor Effluents for e ose of Evaluatin Com liance with 10 CFR Part 50 A end x , Regulatory Guide 1.109, Revision 1 (October, 1977).

4. R.E. Ginna Nuclear Power Plant, v onmental Re ort, Appendix B (August, 1972).

5. R.E. Ginna Nuclear Power Plant, Calcu ations to Demonstrate Co ia ce with the Desi Ob ect ves o 0 C R Part 50 1977) .

6 ~ USNRC, Methods for Estimatin Atmos he c Trans ort and Dis ersion of Gaseous Effluents n out e Releases from Li ht-Water-Cooled Reactors, Regulatory Guide 1.111, Revision 1 (July, 1977).

7. R.E. Ginna Nuclear Power Plant, Steam I de Generator Tube Failu e Inc dent Janua t va uation 25 Ginna 1982, Rochester'Gas and Electric Corporation, (April 12, 1982).

8. Pelletier, C.A, et. al., Sources of Radio odi e at Pressurized W ter Reactors, EPRI NP-939 (November, 1978).

36