Text

Semiannual Radioactive Effluent Release Rept,Jan-June 1985
	ML18038A171
Person / Time
Site:	Nine Mile Point
Issue date:	06/30/1985
From:	Lempges T; NIAGARA MOHAWK POWER CORP.
To:	Murley T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
	NUDOCS 8606190710
	Download: ML18038A171 (184)
	v • d • e

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NINE MILE POINT~NUCLEAR STATION SEMI-ANNUAL RADIOACTIVE/EFFLUENT RELEASE REPORT JANUARY= JUNE 1985' DOCKET NOo:

LICENSE NO.:

50-220 DPR-6 3 g(.01. (6 ()q (

NIAGARA MOHAWK POWER CORPORATION

NINE MILE POINT NUCLEAR STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY JUNE 1985 SUPPLEMENTAL INFORMATION Facility:

Nine Mile Point Unit /Il Licensee:

Niagara Mohawk Power Corporation 1.

Technical Specification Limits:

A)

Fission and activation gases:

1.

The dose rate limit of noble gases from the site to areas at and beyond the site boundary shall be less than or equal to 500 mrems/year to the total body and less than or equal to 3000 mrems/year to the skin.

2.

The air dose due to noble gases released in gaseous effluents from the Nine Mile Point 1 Station to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 milliroentgen for gamma radiation and less than or equal to 10 mrads for beta radiation

and, during any calendar year to less than or equal to 10 milliroentgen for gamma radiation and less than or equal to 20 mrads for beta radiation.

B&C) Tritium, Iodines and Particulates, half lives > 8 days:

1.

The dose rate limit of Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight

days, released to the environs as part of the gaseous wastes from the, site, shall be less than or equal to 1500 mrems/year to any organ.

2.

The dose to a member of the public from Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half lives greater than 8 days as part of gaseous effluents released from the Nine Mile Point 1 Station to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrems to any organ

and, during any calendar year to less than or equal to 15 mrems to any organ.

D)

Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B,

Table II, Column 2 for radionuclides other than dissolved or'ntrained noble gases.

For dissolved or entrained noble

gas, the concentration shall be limited to 2E 04 microcuries/ml total activity.

el

D.

Liquid Effluents (Cont.)

2.

The dose or dose commitment to a

member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 1 unrestricted areas shall be limited during any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5

mrems to any

organ, and during any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

2.

Maximum Permissible Concentrations A)

Fission and activation gases:

None specified B&C) Iodines and particulates, half lives > 8 days:

None specified D)

Liquid Effluents:

10CFR 20, Appendix B, Table II, Column 2.

Avg MPC ( Jan March

)

no discharges Avg MPC ( April June

)

~

no discharges 3 ~

Average Energy (Fission and Activation gases Mev)

Jan March: E0.433; E~ ~ 0.644 April June:

E>

~ 0.423; Q

~ 0.641 4.

Measurements and Approximations of Total Radioactivity Provide the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.

A)

Fission and activation gas:

On-line isotopic monitoring (intrinsic germanium crystal) or gross activity monitoring (calibrated against isotopic analysis of a 4.0L Marinelli sample) of an isokinetic sample stream.

B)

Iodines:

Isotopic analysis (at least weekly) of charcoal cartridges manually or automatically sampled from an isokinetic sample stream.

C)

Particulates:

Isotopic analysis (at least weekly) of particulate filters manually or automatically sampled from an isokinetic sample stream.

D)

Liquid Effluents:

Isotopic Analysis of a representative sample of each batch.

, C

~5.

Batch Releases Provide the following information relating to radioactive materials in liquid and gaseous effluents.

batch releases of A)

Liquid 1.

Number of batch releases:

0 2.

Total time period for batch releases:

0 3.

Maximum, time period for a batch release:

0 4.

Average time period for a batch release:

0 5.

'Minimum time period for a batch release:

0 6.

Average stream flow during period of release of effluent into a flowing stream:

7.

Total volume of water used to dilute the liquid effluent during release periods 8.

Total volume of water available to dilute the liquid effluent during reporting period hours 0

hours 0

Not Applicable Not Applicable 250 GL min..

min ~

min.

B)

Gaseous Not applicable 6.

Abnormal Releases A.

Liquids none B.

Gaseous none

C

TABLE 1A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION //1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY-JUNE A.

Fission

& Activation ases 1.

Total release 2.

Average release rate for period 3.

Percent of Technical Specification Limit E.

Zod1noo 1.

Total 1od1no-131 2.

Average release rate for period 3.

Percent of Technical Specification Limit C.

Particulates 1.

Particulates with half-lives >8 days 2.

Average release rate for period 3.

Percent of Technical

-Specification Limit 4.

Gross alpha radio-activity D.

Tritium 1.

Total release 2.

Average release rate for period 3.

Percent of Technical S pecification.Limit UNIT Ci u Ci/sec Ci uci/sec uCi/sec Ci Ci uCi/sec 1st 2nd EST.TOTAL QUARTER tlUARTER

ERROR, X

1.83E+02 2.27E+02 2.5E+01 2.35E+01 2.89E+01 1.94E-03 6.32E-03 2.0E+01 2.49E-04 8.04E-04

2. 24E-03 2.43E-03

2. OE+01 2.88E-04 3.09E-04 9.50E-06 1.42E-05 2.5E+01 6.13E+00 8.15E+00 2.0E+01 7.88E-01 1.04E+00

I

TABLE lA SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION 81 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY-JUNE (CONT'D)

UNIT 1st 2nd EST.TOTAL gUAR?ER

.QUARTER ERROR E.* Percent of Technical Specification Limits (NMP-1 Elevated Release )

Fission and Activation Gases:

1.

Percent of Quarterly Gamma Air Dose Limit 2.

Percent of Quarterly Beta Air Dose Limit 3.

Percent of Annual Gamma Air Dose Limit to Date 4.

Percent of Annual Beta Air Dose Limit to Date 5.

Percent of Whole Body Dose Rate.Limit 6.

Percent of Skin Dose Rate Limit 5.88E-01 7.16E-01 3.44E-01 4.23E-01 2.94E-01 6.52E-01 1.72E-01 3.84E-01 2.39E-02 2.87E-02 8.61E-03 1.04E-02 Tritium Iodines and Particulates (with half-lives reater than 8 da s):

2 ~

3 ~

Percent of Quarterly Dose Limit Percent of Annual Dose Limit to Date Percent of Organ Dose Rate Limit 8.91E-01 3.05E+00 4.49E-Ol 1.98E+00 1.81E-02 6.12E-02

TABLE 1B SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION //1 GASEOUS EFFLUENTS-ELEVATED RELEASE Nuclides Released 1.

Fission Gases CONTINUOUS MODE Argon-41 Krypton-85m Krypton-87 Krypton-88 Xenon-133 Xenon-135 Xenon-135m Xenon-137 Xenon-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci 3.42E+00 4.45E+00 2.46E-Ol 5.90E-01 5.66E+01 1.73E+01 1.16E+01 4.47E+Ol 4.43E+01 3.21E+00 5.91E+00 1.22E-01 6.07E-01 7.19E+01 1.78E+01 1.76E+01

5. 63E+01 5.40E+01 2.

Zodines Iodine-131 Iodine-133 Iodine-135 3.

Particulates Ci Ci Ci 1.94E-03 5.37E-03 (1.24E-02 6.32E-03 5.02E-O 2 7.59E-02 Strontium-89 Strontium-90 Cesium-134 Cesium-137 Cobalt-60 Cobalt-58 Manganese-54 Barium-Lanthanum-140 Antimony-125 Niobium-95 Cerium-141 Cerium-144 Iron-59 Cesium-136 Chromium-51 Zinc-65 Ci Ci Ci Ci Ci Ci Ci, Ci Ci Ci Ci Ci Ci Ci Ci Ci 4.57E-04 2.05E&6 3.08E-06 6.43E-04 6.16E-04 5.23E-04 5.62E-04 3.48E-06 4.70E-06 1.60E-04 5.83E-,04 9.56E-06 l.11E-0 3

7

TABLE 1C SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION k/1 GASEOUS EFFLUENTSWROUND LEVEL RELEASES JANUARY JUNE There were no ground-level releases from the Nine Mile Point Nuclear Station Unit

$31 during the period January June 1985.

4 t l

TABLE 2A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION 81 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY-JUNE There were no liquid effluent releases from the Nine Mile Point Nuclear Station Unit 81 during the period January-June 1985.

r

TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFIUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION 81 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.

Solid Waste Shipped Off-Site for Burial or Dis osal (Not irradiated fuel) 1.

Class of Waste Jan June Est.Total

Error, a.

Class A

Spent Resins m3 CiSolidification Agent Container Package Principle Isotopes Filter Media m3 Ci Solidification Agent Container Package Principle Isotopes Filter Media m3 CiSolidification Agent Container Package Principle Isotopes Filter Media m3 CiSolidification Agent Container Package Principle Isotopes

4. 98E+01 2.02E+02 Dewatering Plastic HIC Type A Co-60, Mn-54, 4.75E+00 1.38E+01 Dewatered Plastic HIC Type A Co-60, Mn-54, 1.51E+01 2.08E+01 Cement Steel Liner Type A Co-60, Mn-54, 2.12E+00 5.50E+00 Polymer (Dow)

Steel Drum Type A Co-60, Mn-54, 2.5E+01 Cs-134, Cs-137 Cs-134, Cs-137

3. OE+01 Cs-134, Cs-137 2.5E+01 Cs-134, Cs-137 Evaporator Bottoms 3

CiSolidification Agent Container Package Principle Isotopes

6. 78E+00 1.72E+00 Polymer (Dow)

Steel Drum Type A Co-60, Mn-54, 2.5E+01 Cs-134, Cs-137

r

TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION //1 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)

A.

Solid Waste Shi ed Off-Site for Burial or Dis osal (Not irradiated fuel )

1.

Class of Waste Jan June Est.Total

Error, a.

Class A (Coat'd)

Evaporator ottoms CiSolidification Agent Container Package Principle Isotopes Dry Compressible Waste 3

CiSolidification Agent Container Package Principle Isotopes Contaminated Components m3 CiSolidification Agent Container Package Principle Isotopes 5.54E+01 3.32E+01 Cement Steel Liner Type A Co-60, Mn-54, Cs-134, Cs-137 2.5E+01 1.72E+02 8.91E-01 None Strong Tight Box LSA Co-60, Mn-54, Cs-134, Cs-137 3.0E+01

3. OE+0 1 1.13E+01 2.30E+00 None Steel Liner Type A Co-60, Mn-54, Cs-134, Cs-137 B.

Class B

Filter Medig m

CiSolidification Agent Container Package Principle Isotopes 2.5E+0 1 2.37E+00 8.21E+Ol Dewatered Plastic HIC Type A Co-60, Mn-54, Cs-134, Cs-137

-10

TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION //1 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued) b.

Class B (Cont'd)

Jan-June Est. Total Error X

Filter Hedia m3 CiSolidification Agent Container Package Principle Isotopes Evaporator Bottoms m3 CiSolidification Agent Container Package Principle Isotopes c.

Class C

1.01E+01 6.67E+01 Cement Steel Liner Type A Co-60, Hn-54, Cs-134, Cs-137 2.5E+0 1 2.5E+0 1 1.01E+01 1.95E+Ol Cement Steel Liner.

Type A Co-60, Hn-54, Cs-134, Cs-137 Spent Resin m3 CiSolidification Agent Container Package Principle Isotopes 2.5E+01 1.34E+01 8.32E+Ol Dewatered Plastic HIC Type A Co-60, Mn-54, Cs-134, Cs-137

-11

e

TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION Pl SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued) 2.'stimate of Ma or Nuclide Com osition (b T

e of Waste )

a.

Evaporator Bottoms Resins Filter Media Cobalt-60 Cesium-137 Carbon-14 Lanthanum-140 Iodine-131 Chromium-51 Barium-140 Cobalt-58 Manganese-54 Nickel-63 Cesium-134 Other X

x X

X x

X X

x x

x X

x 4.52E+01 1.59E+01 6.60E+00 6.53E+00 5.70EWO 4.08E+00 3.40E+00 2.87E+00 2.80E+00 1.92E+00 1.80E+00 3.20E+00 b.

Dry Compressible Waste and Contaminated Components Cobalt-60 Cesium-137 Manganese-54 Cesium-134 Strontium-90 Cobalt-58 Chromium-51 Nickel-63 Other x

x x

X x

X X

X x

5.21E+01 3.50E+01 3.00E+00 2.20E+00 2.10E+00 2.00E+00 1.10E+00 1.20E+00 1.30E+00 c.

Irradiated Components None 3.

Solid Waste Dis osition Number of Shi ments 47 3

Mode Truck Truck Destination

Barnwell, SC

Hanford, WA B.

Irradiated Fuel Shi ments (Disposition)

Number of Shi ments Mode Destination None

-12

TABLE 4A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985 )

NINE MILE POINT NUCLEAR STATION 81 HOURS AT EACH WIND SPEED AND DIRECTION JANUARY JUNE In accordance with Amendment 66 of Nine Mile Point Unit 1

Technical Specifications, an annual summary of hourly meteorological data shall be included and submitted in the Semi-Annual Radioactive Effluent Release Report within 60 days after January 1 of each year.

Therefore, meteorological data has not been included in this report

~ and will henceforth appear only in the first Semi-Annual Radioactive Effluent Release Report submitted each year.

-13

e J

4 TABLE 5 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION 81

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY-JUNE In accordance with Section 6.9.1 of Amendment 66 to the Nine Mile Point 1

Technical Specifications, the Table below (a) describes and provides justification for recent changes to the Off-Site Dose Calculation Manual and (b) explains why these changes will not adversely affect the accuracy or reliability of off-site dose calculations or monitor alarm setpoint determinations.

Attachment 1 to this document provides copies of pertinent pages of Revision 0

and Revision 1

to Off-Site Dose Calculation Manual showing "before" and "after" changes.

All revisions to the Off-Site Dose Calculations were reviewed and accepted by authorized station personnel in accordance with applicable administrative procedures.

Review and approval documentation is affixed to the front side of Attachment l.

CHG.

ODCM, REVISION 0 NO.

SECTION CHANGED DESCRIPTION OF CHANGE (JUSTIFICATION)

AFFECT ON ACCURACY/

RELIABILITYOF DOSE CALCULATIONS/ALARSETPOINT DETERMINATIONS 1,

Introduction, Paragraph 2,

page 1

Paragraph was deleted since sections 3.2.1.1 and 3.2.1.2 of Revision 1 to the Offsite Dose Calculation Manual now define calculations (ie., the basis) used to establish offsite release limits.

This change will improve the accuracy and reliability of release rate limit and dose rate limit calculations since both meteorological information and dose to curie conversion factors are now considered.

2.

Section 2.1.1 Paragraph 1,

page 2

A quarterly monitor setpoint calculation requirement was established in Revision 1 to ensure 10CFR20 MPC concentra-tions are not exceeded for gamma emitters even with periodic changes in isotopic composition of probable release sources.

The efficiency of the service water monitor is dependent on the gamma emission energy of the isotopes released.

Thus, the monitor accuracy is improved if the setpoint calculation is periodically performed using an isotopic composition which most closely resembles the probable isotopic composition of the source of release

-14

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION 81

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY-JUNE (Continued)

CHG.

ODCM, REVISION 0 NO.

SECTION CHANGED DESCRIPTION OF CHANGE (JUSTIFICATION)

AFFECT ON ACCURACY/

RELIABILITYOF DOSE CALCULATIONS/ALARMSETPOINT DETERMINATIONS 3.

Section 2.1.1 Paragraph 2,

page 2

In conformance with Technical Specifications a provision was added to Revision 1 which permits Liquid Radwaste monitor inoperability during periods when the radwaste discharge line is isolated.

Reliability/accuracy of dose calculations are not affected by monitor status since doses are calculated based on sample analysis data.

Liquid Radwaste monitor alarm setpoint accuracy and reliability is not required when radwaste discharge line is isolated.

4.

Section 2.1.2 and 2.1.3, Equations, pages 2-5 Alarm setpoint equations were changed in order to correct minor calculational errors.

Accuracy of Setpoint Determina-has been improved by correcting calculational errors.

5.

Section 2.1.3 Paragraph was redundant with None

'last paragraph, section 2.1.1 and was page 5

therefore deleted.

6.

Section 2.2.1, Dose calculation equation

Equation, page 7

error was eliminated.

Accuracy of Dose Calculations has been improved by correcting calculational error.

l

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION 81

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY-JUNE (Continued)

CHG.

ODCM, REVISION 0 NO.

SECTION CHANGED DESCRIPTION OF CHANGE (JUSTIFICATION)

AFFECT ON ACCURACY/

RELIABILITYOF DOSE CALCULATIONS/AIdQR SETPOINT DETERMINATIONS 7.

Section 2.2.1, Paragraph 6,

page 10 An explanatory sentence was added to Revision 1 which states that if a factor of conservatism (ie.,l.05) is applied to the dose calcula-tion equation, dose contribu-tion from the drinking water pathway need not be con-sidered.

This assumption was applied to liquid dose calculation equations in both Revision 0 and 1 of the Offsite Dose Calculation Manual

since, based on historical data, the fish ingestion pathway contributes

>98X of the maximum doses to the total body and critical organ received from liquid released Accuracy and reliability of dose calculation is unaffected.-

-16

TABLE 5 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION 81

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY-JUNE (Continued)

CHG.

ODCM, REVISION 0 NO.

SECTION CHANGED DESCRIPTION OF CHANGE (JUSTIFICATION)

AFFECT ON ACCURACY/

RELIABILITYOF DOSE CALCULATIONS/ALARMSETPOINT DETERMINATIONS 8.

Section 3.1.1 Paragraph 1,

page 12 Paragraph 2 was added to Revision 1 which changed the frequency of monitor alarm setpoint determination from monthly to quarterly under normal release rate conditions.

This change was made so that frequency and performance of alarm setpoint readjustment (if required) would correspond to the time of detector calibration.

Station procedures require stack monitor alarm points be set conservatively during periods of normal release rate.

This fact increases the likelihood that that monitor alarms will sound if Technical Specification release limits are approached.

Thus, overall reliability is improved.

Paragraph 3 was added which requires more frequent alarm

,setpoint determinations under conditions of abnormal release rate.

Paragraph 4 was added (and the last paragraph of ODCM, Revision 0 deleted) since the isotopic composition of gaseous effluents cannot be determined during prolonged outages (when noble gases have decayed to less than detectable activities).

9.

Section 3.1.2, pages 12-14 The entire section was revised to require alarm setpoint determination using meteorol-ogical information and dose-to curie conversion factors rather than obsolete limits listed in the Environmental Technical Specifications for Nine Mile Point Nuclear Station Unit

$31 dated March 1, 1979.

This change will improve the accuracy and reliability of alarm setpoint determinations since both meteorological conditions and dose-to-curie conversion factors are now considered.

S.

TABLE 5 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION //1

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY-JUNE (Continued)

CHG.

ODCM, REVISION 0 NO.

SECTION CHANGED DESCRIPTION OF CHANGE (JUSTIFICATION)

AFFECT ON ACCURACY/

RELIABILITYOF DOSE CALCULATIONS/ALARMSETPOINT DETERMINATIONS

10. Section 3.1.3, page 14 Two effective changes were made to this section:

(a) factors of conservatism were removed from the set-point calculation and (b) allowable upper limits on hi hi and hi alarm set-points were increased to correspond to 1X and 1/2X the technical specification limit respectively. It was felt that the frequency of plant off gas sampling and analysis required by station procedures (generally five times per week) )ustified setting the off gas monitor alarms higher than originally intended by Revision 0

of the OCDM.

Accuracy and reliability of alarm setpoint determinations remains unchanged since, in both Revision 0 and Revision 1 to the Offsite Dose Calculation Manual, the alarm setpoint is a function of monitor efficiency which is in turn a function of the isotopic composition and concentration of the offgas.

By station procedure, alarm setpoint calculation is performed monthly to ensure isotopic composition and concen-tration do not appreciably change the monitor efficiency factor.

ll. Section 3.2, page 14 A description of the overall approach and assumptions used in dose and dose rate determina-tions for gaseous releases at Nine Mile Point Unit One was added.

Dose and dose rate calculation.methodology described in Revision 1 to the Offsite Dose Calculation Manual will improve the accuracy reliability of dose/dose rate estimates since real time meteorological data may (when available) be applied.

-18

r

~i

~

TABLE 5 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION //1

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY-JUNE (Continued)

CHG.

ODCM, REVISION 0 NO.

SECTION CHANGED DESCRIPTION OF CHANGE (JUSTIFICATION)

AFFECT ON ACCURACY/

RELIABILITYOF DOSE CALCULATIONS/ALARMSETPOINT DETERMINATIONS

12. Section 3.2.1.1 and 3 ~ 2 ~ 1 ~ 2 j pages 14-15 Reliability and accuracy of dose alarm setpoint calculations is unaffected.

Revision 1 to the Offsite Dose Calculation Manual defines the calculations used to compute total body, skin and organ dose rates received from noble gases, tritium, iodines and partic-ulate gaseous releases Justification for release rate limits above which dose rate calculations are performed, is also provided.

Revision 0 to the Offsite Dose Calculation Manual did not adequately supply this informa-tion.

13. Section 3.2.2.1 and 3 ~ 2 ~ 2 ~ 2 j page 17 X/Q and D/Q definitions vere changed to include the option of using real time meteorological data in lieu of maxiumum 5 year average annual meteorological data.

Same as noted in change

//11 above.

-19

t

TABLE 5 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION 81

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY-JUNE (Continued)

CHG.

ODCM, REVISION 0 NO.

SECTION CHANGED DESCRIPTION OF CHANGE (JUSTIFICATION)

AFFECT ON ACCURACY/

RELIABILITYOF DOSE CALCULATIONS/ALA1NSETPOINT DETERMINATIONS

14. Section 3 ~ 2 ~ 2 ~ 3 pages 18-19 The requirement to calcul-ate/sum doses due to tritium, iodine and particulates from each pathway separately was deleted from Revision 0.

Instead, doses due to tritium, iodines, partic-ulates are calculated/summed monthly for the "moving" critical receptor location (defined on page 18, Revision 1 to the Offsite Dose Calculation Manual-See Attachment 1) unless Technical Specification limits are approached.

This change was made in order to more rapidly calculate doses and to provide a degree of conservatism in the dose calculation.

Reliability (ie, the likelihood of identifying dose problems) of dose calculation is improved with this revision since meth'odology now effectively considers dose contri-butions from all critical receptor locations and pathways simultaneously.

Accuracy of dose calculation is unaffected under high release rate conditions since doses at all critical receptor locations are calculated separately.

Under low (normal) release rate conditions, doses may be conservatively over-estimated However, the relative error is negligible when compared to other assumptions made in the dose calculation (eg., meteorological assumptions.

~

The requirement to estimate infant thyroid doses monthly prior to receipt of all analysis data was added to Revision 1 to provide rapid identification of potential dose problems.

Paragraph 2 of Section 3.2.2.3, Revision 0 was deleted and applicable information about critical receptors was incorporated into Section 3.3.

-20

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION 81

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY-JUNE (Continued)

CHG.

ODCM, REVISION 0 NO.

SECTION CHANGED DESCRIPTION OF CHANGE (JUSTIFICATION)

AFFECT ON ACCURACY/

RELIABILITYOF DOSE CALCULATIONS/ALARMSETPOINT DETERMINATIONS

15. Section 3.3, pages 19-20 The critical receptor loca-tion for noble gas doses was changed from the great-est X/Q residence location to the maximum X/Q land sector site boundary loca-tion (when 5 year average meteorological conditions are

'assumed) since calculated doses are higher at the latter location, and, since Technical Specifications requires dose rate calcula-tion at the site boundary.

This change provides an accurate means of assessing site boundary dose rates due to noble gases.

16. Section 4.4, page 24 This section was added to Revision 1 of the Offsite Dose Manual in order to determine doses to members of the public within the Site Boundary.

Doses as a

. result of gaseous effluents are evaluated via inhalation and direct radiation compon-ents.

The direct radiation component is evaluated by environmental TLDs.

The in-halation component is eval-uated by a simple lung dose equation taken from Regulatory Guide 1.109.

This change provides an accurate means of assessing doses within the site boundary.

17. Section 5.2, last paragraph, page 26 The Interlaboratory Comparison Program required by the Technical Specifi-cations was detailed further by including the types of samples obtained from the EPA's Cross Check Program.

This change has no effect on accuracy or reliability of dose/alarm setpoint determinations and was, included for clarity only.

-21

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION 81

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY-JUNE (Continued' CHG.

ODCM, REVISION 0 NO.

SECTION CHANGED DESCRIPTION OF CHANGE (JUSTIFICATION)

AFFECT ON ACCURACY/

RELIABILITYOF DOSE CALCULATIONS/ALMNSETPOINT DETERMINATIONS

18. Table Numbering System.

The numbering sequence used Same as change 817.

for ODCM Tables was revised to a more orderly system.

19. Table 3.1, page 32 Ar-41, which was inadver-tantly not included in Table 3.1 of Revision 0, was added to Table 2-1 of Revision 1.

Accuracy and reliability of dose calculation has been improved with this change.

20. Table 3.2, page 33 Distances of receptor locations from the site were changed slightly to reflect data from a new Geological Survey Map used.

Same as change 819.

Site Boundary receptor location was added to Table 3.1 of Revision 1 for calculation of noble gas air dose at the si'te boundary.

(See Change 8 15 )

Table X/Q and D/Q values changed slightly to reflect values based on an actual five year average of site meteorological data.

Revision 0 values were estimates.

X/Q and D/Q values were also added for the new site boundary receptor location.

(See Change /i'5)

21. Table 3.3, page 34 Gamma air doae factors for Kr-88 and Xe-131m were corrected in Table 4-1 of Revision l.

Same as change 819.

-22

TABLE 5 SEMI-ANNUALRADIOACTIVE EFFLUENT RELEASE.REPORT (1985)

NINE MILE POINT NUCLEAR STATION 81

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY-JUNE (Continued)

CHG.

ODCM, REVISION 0 NO.

SECTION CHANGED DESCRIPTION OF CHANGE (JUSTIFICATION)

AFFECT ON ACCURACY/

RELIABILITYOF DOSE CALCULATIONS/ALARMSETPOINT DETERMINATIONS

22. Table 5.1, pages 54-56 Table 5.1 was revised to change some of the descrip-tions of the environmental sampling locations.

The direction in degrees and distance in miles was revised as a result of using a new Environmental Geological Survey Map to describe the sample locations.

Environmental air station (ODCM Location t/2 of Revision 0 or Location f/1 of Revision 1) as, located on Nine Mile Point Road instead of the site boundary as originally indicated.

The station could not be located at the site boundary area as originally indicated, because the area was inaccessible.

Same as t/19.

Environmental air station (ODCM location 84 of Revision 0 or Location 83 of Revision

1) was located on Co. Rt.

29 instead of the NE shoreline because the most recent meteorological study for X/Q and D/Q values showed the Co. Route 29 location had greater X/Q and D/Q values than the NE shoreline area, as originally proposed.

Environmental air stations (map locations 1-4) were assigned new map numbers.

Location 1 became.4; 2 became 1;

3 became 2; and 4 became 3.

The revised off-site ODCM map is included in Attachment 1 ~

r 1 ~

TABLE 5 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985 )

NINE MILE POINT NUCLEAR STATION 81

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY-JUNE (Continued)

CHG.

ODCM, REVISION 0 NO.

SECTION CHANGED DESCRIPTION OF CHANGE (JUSTIFICATION)

AFFECT ON ACCURACY/

RELIABILITYOF DOSE CALCULATIONS/ALAMSETPOINT DETERMINATIONS

22. Table 5.1 (Cont')

Same as //19.

The description for ODCM TLD location 810 was changed to JAF east boundary from Sunset Bay Road.

The actual location did not change.

The description for ODCM TLD location 828 was changed to Co. Rt. 1 from Mitchell Street.

The location moved slightly to the east to reduce the possibility of theft.

The description for ODCM sediment location 840 was changed to Sunset Bay instead of Nine Mile Point Unit (31 because the Sunset Bay location had a greater potential for recreational value than the former location.

The description for ODCM milk location 844 was changed from milk program location 845 to 850.

This change was a result of the most recent meteorological study and the associated D/Q values.

The most recent study showed milk program location

/$50 to have a greater D/Q value than location /345.

The other listed locations (milk program locations 87 and //16) also showed greater D/Q values; thus they remained unchanged.

-24

C.

~ )

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION 81

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY-JUNE (Continued)

CHG.

ODCM, REVISION 0 NO.

SECTION CHANGED DESCRIPTION OF CHANGE (JUSTIFICATION)

I AFFECT ON ACCURACY/

RELIABILITYOF DOSE CALCULATIONS/ALARMSETPOINT DETERMINATIONS

22. Table 5.1 (Cont'd)

The descriptions for food product locatons (ODCM Map

/148-55) were revised to show the property owners for each location.

This revision allows environmental personnel to more readily identify the locations.

The actual sample locations were not changed.

Same as //19.

~ 4 t ~

I

TABLE 6 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION 81 CAUSE AND CORRECTIVE ACTIONS REGARDING SERVICE WATER EFFLUENT MONITOR INOPERABILITY Amendment 66, Section 3.6.14a of the Nine Mile Point Station Unit 81 Technical Specifications requires ad)ustment of radioactive liquid effluent monitor alarm setpoints to ensure that 10 CFR 20, Appendix B,

Table II, Column 2 limits are not exceeded.

Inability to meet this criteria in the case of the service water effluent monitor requires (a) declaration of monitor inoperability (or cessation of the release) and (b) sampling and analysis of the affected effluent water at 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months intervals.

Furthermore, the cause of the monitor inoperability and a

description as to how the instrument will be restored to operable status must be reported in the next Semi-Annual Radioactive Effluent Release Report.

Prior to implementation of Amendment 66 of the Technical Specifications, it was determined that the sensitivity (ie, the capability of the monitor to respond to concentrations equal to 10 CFR 20 Appendix B, Table II, Column 2 limits) of Nine Mile Point 81 Service Water effluent monitor was questionable.

Therefore, the monitor was considered inoperable on January 1,

1985 and a

12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months service water sampling and analysis program was implemented.

Current plans call for re-establishment of service water monitor operability in 1986.

A new monitoring system has been purchased and is already on-site.

Required electrical modifications and

-procedure development/implementation should take place during the 1986 refuel outage.

In the interim

period, additional Technical Specific'ation surveillances required to maintain service water monitor operability, including periodic sensor checks, 'ource

checks, channel tests and calibrations are still being performed on the existing monitoring system despite its sensitivity limitations.

-26

t

ATTACHMENT 1 SEMI-ANNUAL RADIOACTIVE EFFIUENT RELEASE REPORT (1985)

NINE MILE POINT NUCLEAR STATION 81 ODCM REVISION 0 AND REVISION 1 PAGE CHANGES JANUARY - JUNE

-See Attached Pages-

-27

h e

f

~

f 0 DCM REVlelOM NIAGARA MOHAWK,POWER CORPORATION DOCUMENT REVIEW FORM SITE OPERATIONS REVIEW COMMITTEE Document Title r =S(

Document No ~

Cz c

Proposed Revision No

/

Date 2 g Periodic Revie~ Per Figure 4, APN-5y Revision Author, Name J f /'W~

Despcription of Revision Cwm

~c s~.

= n -v. u)

C~~~

4.)rP rysr P S

v. ~~~ M'-~

cr c wm~.~ 'nn

~ dvf" 6 n rr p./trey l7 C~

/+-Zsr r'3"%e-Reviewer Name Accepted As Presented Initials/Date Accepted As Revised Initials/Date

/~Z7 ~

4.

5.

First Presented to SORC by Accepted by SORC-As Submitted

/

on Date

.As Revised

', Reetang 6

Poll Vote Recorded by Safety Analysis Required Yes Date Analysis assigned to Sire/, Syr.

Sng. /

Date

.This procedure changed in accordance uith Section 6.3 Apll-1

/

initials/Date This has been reviewed by SORC for compliance with-Technical Specifications.

Initials/Dace APN-3

-7 December l983

0 DCM AEVISION Rev.

1 NINE MILE POINT NUCLEAR STATION NINE MILE P01NT UNIT 1 OFF-SITE DOSE CALCULATION MANUAL (ODCM)

DATE AhtD INITIALS APPROVALS SIGNATURES REVISION 1 REVISION 2 REVISION 3 Chemistry and Radiation Management Superintendent E.

W. Leach C

Station Superintenden NMPNS Unit 1 T.

W. Roman General Superintendent Nuclear Generation Chairman of S.O.R.C.

T. J. Perkins Summar of a es Revision 1

(Effective 3/28/85 PAGE DATE 1-90 August 1985 - Reissue This reissue reflects change in placement of revision NIAGARA MOHAWK P85$ C%$ 5RATION

'THIS PROCEDURE NOT TO BE USED AFTER MARCH 1987 SUBJECT TO PERIODIC REVIEW.

r

6 DCM REViStOM ODCM NINE MILE POINT UNIT 1 Page

1.0 INTRODUCTION

2.0 LIQUID EFFLUENTS 2.1 Setpoint Determinations 2.2 Dose Determinations 3.0 GASEOUS EFFLUENTS I

3.1 Setpoint Determinations 3.2 Dose and Dose Rate Determinations 3.3 Critical Receptors 4.0 40 CFR 190 REQUIREMENTS 4.1 Evaluation of Doses From Liquid Effluents 4.2 Evaluation of Doses From Gaseous Effluents 4.3 Evaluation of Doses 'From Direct Radiation 5.0 ENUIRONMENTAL MONITORING PROGRAM 12 25 26 28 28 29 33 5.1 Sampling Stations 5.2 Interlaboratory Comparison Program 33 33 5.3 Capabilities for Thermolumi'nescent Dosimeters Used for Environmenta1 Meesurements 34 TABLES APPENDIX A Dose Parameters for Iodine 131 and 133, Particulates and Tritium 67 B Diagrams of Liquids and Gaseous Radvaste Treatments Systems C -

Dispersion Calculation Tables 80 87

t'

6 DS.Q REV f SIQM

].

Rev.

1

1.0 INTRODUCTION

The Offsite Dose Calculation Manual (ODCM) provides the methodology to be used for demonstrating compliance with the Radiological Effluent Technical N

I Specifications (RETS),

10 CFR 20, 10 CFR 50, and 40 CFR 190.

The contents of the ODCM are based on Draft NUREG-0472, Revision 3, "Standard Radiological Effluent, Technical Specifications for Pressurized Water Reactors,"

September 1982; Draft NUREG-0473, Revision 2, "Radiological Effluent Technical Specifications for BWR's," July 1979; NUREG 0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978; the several-Regulatory Guides referenced in these documents;

and, communication with the NRC staff.

Section 5 contains a detailed description of the Radiological Environmental Monitoring (REM) samplin~ locations.

Should it be necessary to revise the ODCM, these revisions will be made in accordance with Technical Specifications.

O DCg aEV t SlObl Rev.

1 2.0 LIQUID EFFLUENTS 2.l Setpoint Determinations 2.l.l Basis Monitor setpoints will be established such that the concentration of radionuclides in the liquid effluent releases in the discharge canal will not exceed those concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2.

Setpoints for the Service Vater System Effluent Line will be calculated quarterly based on the radionuclides identified during the previous year's releases from the liquid radwaste system or the isotopes identified in t'e most recent radwaste release or identified probable source.

Setpoints for the Liquid Radwaste Effluent Line will be based on the radionuclides ident1fied in each batch of liquid waste prior to its release.

After release, the Liquid Radwaste monitor setpoiat may remain as set, or revert back to a setpoint based on a previous Semi-Annual Radioactive Effluent Release Report, or install blank flange in the discharge line and declare 1noperable in accordance with the technical specification.

2.1.2 Service Vater System Effluent Line Alarm Setpoint The detailed methods for establishing setpoints for the Service Vater System Effluent Line Monitor shall be contained in the Nine Mile Point Station Procedures.

These methods shall be in accordance w1th the following:

~

P

O DCM REV t810N Rev. l Setpoint (Hi-Hi alarm)<0.9 Z Ci TDF Fsw CF Cg MPCi

+ background where Ci concentration of isotope i in the sample (units uCi/ml)

TDF ~ Total Dilution Flow (units

~ gallons/min)

Fsw Service Water Flow (units gallons/min)

CF ~ monitor calibration factor (units net cps/uCi/ml)

MPCi liquid effluent radioactivity concentration limit for radionuclide i as specified in 10 CFR 20, Appendix 8, Table XE, Column 2, for those nuclides present in the previous batch release from the liquid radwaste effluent system or for those nuclides present in the last Semi"annual Radioactive Effluent Release Report (units uCi/ml) or for those nuclides present in the service water system.**

factor to account for the presence of pure beta emitters Required Dilution Factor TDF Actual Dilution Factor SW For, periods with known reactor water to RCLC system leakage, RCLC maximum permissible concentration may be prudently substituted for the above t

O OCV REVIBfOM Rev. l

+ background Satpoitt (Mi alatia)<0.7 g (Ci)

TDF CF Fsw pm<MPCi 2.1a3 Liquid Radwaste Effluent Line Alarm Setpoint The detailed methods for establishing setpoints for the Liquid Radwaste Effluent Line Monitor shall be contained in the Nine Mile Point Station Procedures.

These methods shall be in accordance with the following:

Setpoint (Hi-Hi alarm)<0.9(ZCi)

TDF Fre CF 1

+ background ZMP0lI where C

activity of isotope i in the sample (units uCi/ml)

TDF =

Total Dilution Flow (units ~ gallons/min)

F

~

Radwaste Effluen Flow (units gallons/min )

CF monitor calibration factor (units

~ net cps/uCi/ml)

MPCi liquid effluent radioactivity concentration limit for radionuclide i as specified in 10 CFR 20, Appendix B, Table II, Column 2, for those nuclides detected by spectral analysis. of the contents-of the. radwaste-tanks to be released (units

'uCi/ml )

0.9

'factor to account for pure beta emitters C

Required Dilution Factor MPGi

1 l

k o oc'v REVJSfOg Rev.

1 SetPoint (Hi alarm)

<0'7 ~(Ci)

TDF Fr CF

)MPCg

+ background Note:

If TDF "g

~C Fre CMPCi the discharge could not be made, since the monitor would be continuously in alarm.

To avoid this situation, F

will be reduced (normally by a factor of 2) to allow setting the alarm point at a

concentration higher than tank concentration.

This will also result in a discharge canal concentration at approximately 50K maximum permissible concentration.

2.2 Dose Determination 2.2.1 Maximum Dose Equivalent Pathway A dose assessment report was prepared for the Nine Mile Poin t Unit 1 facility by Charles T. Main, Inc., of Boston, MA.

This report presented the calculated dose equivalent rates to individuals as well as the population within a 5g-mile radius of the facility based on the radionuclides released in liquid and gaseous effluents during the time periods of 1 July 1980 through 31 December 1980 and from 1 Januar'y 19S1 through 31 December 19S1.

Utilizi'ng the effluent data contained in the

/

J

Rev.

1 R

1100U M

Z B D

(-X t )

apji ap p ip aipj exp i p Vhere R

i apji total annual dose (per Curie released) to organ "j" of individuals of age group "a" from all of the nuclides "i" in pathway "p" (units " mrem/year Ci )

Uap usage factor specifying the exposure time or intake rate for an individual of an age group "a" associated with pathway "p" (units kg/year) mixing rates (reciprocal of dilution factor) at the point of exposure or point of harvest (units dimensionless) flow rate of the liquid effluent (units ft /sec) 3 Bip equilibrium bioaccumulation factor for nuclide "i" in pathway "p" (units liters/kg)

ODCM BEY ISfOM'ev.

1 Daipj the dose factor, specific to a specific age group "a", radionuclide "i", pathway "p",

and organ "g", which can be utilized to calculate the radiation dose from an intake of a radionuclide (units

~ mrem/pCi) radioactive decay constant of nuclide "i"

-1 (units hours

)

P the average transit time required for nuclides to reach the point of exposure.

For internal dose, t is the total time P

elapsed between the release of the nuclides and the ingestion of the food and/or water

'units hours) 1100 am factor to convert from (Ci/year)/(ft /sec) to pCi/liger 3

Values for R are contained in Table l-l. All of these apdi values of R are on a per Curie basis for each of the sp5t nuclddes released.

Table 1-2 dndtcates those parameters used for selected factors of the formula.

Prior to each radioactive liquid discharge, each liquid waste tank to be discharged will be analyzed for isotope content utilizing a GeLi detector.

On the basis of this analysis, projected doses to an adult whole body and a teen liver will be calculated using the following relationships:

ODCM REViStOM Rev.

1 1.05

~

correction factor to account for 100K of

dose, assuming that 95K of dose received is delivered via the fish ingestion pathway.

The value of 1.05 is used in the equation as a conservative factor to incxease the projected dose from an anticipated xelease to 100/.

As long as the 1.05 factor is used, doses received via the drinking water pathway (eg, tritium) neea not be accounted for separately.

All projected doses calculated in this manner for each batch of liquid effluent will be summed for comparison with quarterly and annual limits, added to the doses accumulated from other releases in the quarter and year of interest.

In all cases, the following relationships will hold:

For a calendar quarter:

D

< 1.5 mrem total body D

5 mrem fox any organ rI

h v

ODC M

REViStON 1.

Rev.

1 3.0 GASEOUS EFPLUENTS 3.1 Setpoint Determinations 3.1.1 Basis Stack gas and off gas monitor setpoints will be established such that the instantaneous release rate of radioactive materials in gaseous effluents does not exceed the 10 CFR 20 limits for annual release rate.

The setpoints will be activated if the instantaneous dose rate at or beyond the (land) site boundary would exceed 500 mrem/yr to the whole body or 3000 mrem/yr to the skin from the continuous release of radioactive noble gas in the gaseous effluent.

Monitor setpoints will be determined once per quarter under normal release rate conditions and will be based on the isotopic composition of the release and/or a more conservative default composition specified in the pertinent procedure. If the calculated setpoint is higher than the existing setpoint, it is not mandatory that'he setpoint be changed Under abnormal site release rate conditions, monitor setpoints will be recalculated and, if necessary, reset at more frequent intervals as deemed necessary by CHIRP Supervision.

In particular, the JAP contribution shall be assessed During outages and until steady state power operation is again

realized, the last operating setpoint shall be used.

The skin dose rate limit is not used in setpoint calculations because it is never limiting.

ODCM BEY ISlON 1

Rev.

3.1.2 Stack Monitor Setpoints The detailed methods for establishing setpoints shall be contained in the station procedures.

These methods shall apply the following general criteria:

(1) Rationale for Stack monitor settings is based on the general equation:

release rate, actual corresponding dose rate, actual release rate, max. allowable corresponding dose rate, max.

allowable Q~

3/Q Z(QiM )

500 mr/yr where:

Qi vCi/sec released rate for each isotope, i X/Q highest land sector site boundary dispersion parameter equal to 1.5 E-6 Sec/m M

gamma air dose factor in units of mr/yr/Ci/sec release

rates, the following general formula shall be applied:
(C -B) K m
s uCi/sec release rate where:
C monitor gross count rate in cps or cpm B
" monitor background count rate K
stack monitor efficiency factor with units of s
uCi/sec-cps or uCi/sec-cpm.
I
ODC M
REY I SION Rev.
1 (5) Monitor K factors shall be determined using the general formula:
Ks
~Qi/(C -a) where
.'i individual radionuclide stack effluent release rate as determined by isotopic analysis<<
K factors more conservative than those calculated by the above methodology may be assumed.
3.1.3 Recombiner Discharge (Off Gas) Monitor (1)
T e hi hi alarm points shall activate with recombiner discharge rates equal to or less than 500,000 vCi/sec.
This alarm point may be set equal to or less than 1 Ci/sec for a period oi time not to exceed 60 days provided the offgas treatment system is in operation.
ODC M
R EV1SI Oh!
Rev.
1 (2)
The hi alarm points shall activate with recombiner.
discharge rates equal to or less than 500,000 >Ci/sec (3)
To convert monitor mR/hr readings to PCi/sec, the formula below shall be applied:
QR uCi/sec recombiner discharge release rate where
~
mR/hr monitor indicator K
efficiency factor in units of uCi/sec mR/hr determined prior to setting monitor alarm points (4)
Monitor KR factors shall be determined using the general formula:
I K
~
KQi/R where:
individual radionuclide recombiner discharge i
release rate as determined by isotopic analysis and flow rate monitor-K factors more conservative than those calculated by the above methodology may be assumed.
O~C M
~EVlSIOM Rev.
1 3.2 Dose and Dose Rate Determinations In accordance with..specification 4.6.15.b.(2) and 4.6.15.b.(3),
dose and dose rate determinations will be made monthly in order to determine:
(1)
Total body dose rates and gamma air doses at the maximum X/Q land sector site boundary interface and beyond.
(2)
Skin dose rates and beta air doses at the maximum X/Q land sector site boundary interface and beyond.
(3)
The critical organ dose and dose rate at the maximum X/Q land sector site boundary interface and at a critical receptor location beyond the site boundary.
Either maximum fiv~aa~nnual-average-or real time meteorologica'1'ata shall be utilized for dose and dose rate calculations.
Vihere maximum five year average annual meteorological data is assumed, dose and dose rates due to noble gases at locations beyond ahe site'oundary will be lower than equivalent site boundary dose and dose rates.
Therefore, under these conditions, calculation of noble gas dose and dose rates beyond the maximum X/Q land sector site boundary locations can be neglected.
The frequency of dose rate calculations will be upgraded when elevated release rate conditions specified in subsequent sections 3.2.1.1 and 3.2.1.2 are realized.
-17>>
~ +
ODC M
REVl SODOM Rev.
1 Critical organ doses and dose rates may be conservatively calculated by assuming the existence of a so-called "moving" critical receptor.
At this "moving" critical receptor location, it is assumed that all pathways are applicable and the highest X/A and/or D/Q value for actual pathways as noted in Table 3-1 are in effect.
A person's dose at the "moving" critical receptor location is equal to the same dose that person would receive if they were simultaneously subjected to the highest pathway dose at each critical receptor identified for each pathway.
If dose or dose rates calculated, using the assumptions noted above, reach Technical Specification limits, actual pathways will be evaluated, and doses/dose rates shall be calculated at separate critical receptor locations and compared with applicable limits.
Not all pathways need be considered in dose and dose rate calculations at each critical receptor location.
For example, when calculating land sector site boundary doses and dose rates for particulates, iodines'and tritium, only the ground deposition and inhalation pathways apply.
P
O D-C g REVlSlON Rev.
1 3.2.1 Dose Rate 3.2.1.1 Noble Gases In accordance with the provisions of 10 CFR 20 the dose rates from noble gas release from the site to unrestricted areas are to be limited to 500 mrem/yr to the total body and 3,000 mrem/yr to the skin.
Dose rate calculation will be performed monthly, or when the Hi Hi stack monitor alarm point is reached, using the, following equations:
For total body dose rates (in mr/yr):
DR~
3.17 x 10 g M (X/Q)Q /sec i
1 For skin dose rates:
K+ B
[3.17 x 10
$ N (X/Q)Q /sec]
+ DR>
i where:
-e M, N, X/Q, Q, 3.1? x 10 are as defined in section 3.2.2.1
~8
h
~
ODC lvl REVlSfOM 3.2.1.2 Tritium, Iodines and Particulates Rev.
1 (1)
The dose rate in unrestricted areas from the release of tritium, iodine-131, iodine-133 and all radionuclides in particulate form with half lives greater than 8 days is limited to 1500 mrem/year to any organ (2)
In order to ensure that the 1500 mrem/year dose rate limit is not exceeded, particulate> iodine and tritium off site dose rate calculations shall be performed monthly and whenever particulate and iodine release
-2 rates exceed 10 uCi/sec using the equation given in Section 3.2.2.2 with Q expressed in uCi/sec.
-2 Rhen the release rate exceeds 10 PCi/sec, the dose rate assessment shall also include JAP contribution.
-2 (3)
The use of the 10 PCi/sec release rate threshold to perform dose rate calculations is justified as follows:
The 1500 mrem/yr organ dose rate limit corresponds to a minimum release rate limit of 0.27 uCi/sec calculated using the equation:
1500
~
(Q/sec)
Z. ig 0 max r
4
~+
~I
~
ODC M
REVlSiag where:
1500
~
site boundary dose rate limit in mrem/year (Ri)W))
the maximum curie to dose conversion factor equal to 5500 mrem-sec/pCi-yr for Sr-90, child bone at the "moving" critical receptor location beyond the site boundary.
3.2.2 Dose Calculations will be performed monthly at a minimum, to demonstrate that, doses resulting from the release of noble
\\
gases, tritium, I-131, I-133 and particulates with half lives greater than 8 days are within the limits specified in 10 CFR 50, Appendix I.
These limits are:
Noble Gas Air Dose 5 mr gamma/calendar quarter 10 mrad beta/calendar quarter 10 mr gamma/calendar year 20 mrad beta/calendar year Radioiodines Tritium 6 Particulates 7.5 mrem to any organ/calendar quarter 15 mrem to any organ/calendar year
~ ~
~P
~y' ODC M
REVJSlOM 1
Rev.
1 3.2.2.1 Noble Gas Air Dose The air dose at the critical receptor due to noble gas releases is determined as follows:
For gamma radiation D
3.17 x 10 E Mi X/Q Qi For beta radiation Dg 3 17 " 1o
~ Ni
/Q Qj where M
air gamma dose factor in (mr/year per uCi/m ) for each isotope i (Table 4-1 )
3 air beta dose factor (nrad/year per uCi/m ) for each isotope i (Table 4-1 )
3 X/Q ~
the relative plume concentration (in units 3
of sec/m
) at the land sector site boundary or beyond.
Either maximum 5 year average annual values (Table 3-1 or Appendix C), or real time values may be assumed.
Q mi the total quantity of isotope i released during the period, (uCi)
-8 3.17 X 10 the inverse o'f the number oi seconds in a year
ODCM REV I SION Rev.
1 3.2.2.2 Radioiodine, Tritium & Particulates The doses to an individual from I-131, I-133, tritium, and particulates with half lives greater than 8 days will be calculated as follows:
Dose 3.17 X 10 E.
E R
W.Q j i ijak j i Where Wj dispersion parameter either X/Q (sec/m ) or D/Q (1/m ) depending on pathway and receptor 2
location assumed.
Either 5 year average annual values (Table 3-1, or Appendix C) or real time values may be assumed the total quantity of isotope 1 released during the period, (uCi)
Rij k the dose factor for each isotape i, pathway j, age group a, and organ k (Table 4-2, through 4-20)
-8 3.17 X 10
~ the inverse of the number of seconds in a year The R values contained in Tables 4-2 through 4-20 were calculated using the methodology defined in NUREG-0133 and Regulatory Guide 1.109, Revision 1.
'r J
oDCM R EV.lSf OM Rev.
1 3.2.2.3 Accumulating Doses Doses will be calculated monthly, at a minimum, for I
gamma air and beta air, the identified critical organ, and age group.
Results will be summed for each calendar quarter and year.
It has been historically demonstrated that the critical pathway is usually the grass-cow-milk pathway and the critical organ is the infant's thyroid.
For this reason, monthly infant thyroid dose estimates will normally be made prior to receipt of all analysis data (i.e., strontium and tritium).
The critical doses are based on the following pathways.
noble gas plume air dose ground plane dose (deposition) inhalation dose cow's milk dose goat's milk dose meat consumption dose vegetation (food crops) dose The quarterly and annual results shall be compared to the limits listed in paragraph 3.2.2. If the limits are exceeded, special reports, as required by Section 6.9.3 of the Technical Specification, shall be submitted.
~a r
ODCM REVlSlON Rev.
1 3.3 Critical Receptors In accordance with the provisions of 10 CFR 20 and 10 CFR 50, Appendix I, the critical receptors have been identified and are contained in Table 3-1.
For noble gas doses, one of two critical receptor locations will be assumed.
When maximum five year average annual X/Q values are used, the critical receptor is the maximum X/Q land sector site boundary interface.
When real time meteorological X/Q values are used, the critical receptor may either be the maximum X/Q land sector site boundary location, or the downwind location of greatest X/Q residence (e.g.,
1.5 miles east),
whichever is higher.
For I-133, I-131, tritium and particulate radionuclides with a half life of greater than eight days, the critical pathways are milk (cow and goat)',
meat, vegetation, inhalation and direct radiation (ground I
plane) as a result of ground deposition.
The cow milk and goat milk pathway will be baaed on the greatest D/Q milk cow and milk goat location as determined by technical specification 3.6.22.
The inhalation dose pathway wiU. be based on the greatest X/Q residence as determined by technical specification 3.6.22 since this location would have the greatest potential occupancy time.
The ground plane dose pathway will be calculated as the greatest D/Q residence because of the greatest potential occupancy time.
~ ~ I
ODCM REVtSlOM Rev.
1 3.3 Critical Receptors For'the meat consumption dose
pathway, the critical receptor is the greatest D/Q meat animal location.
This location has been determined in conjunction with the land use census (technical specification 3.6.22) and is subject to change.
The vegetation (food crop) dose is based on the greatest D/Q garden location from which samples are taken.
This location also may be modified as a result of vegetation sampling surveys.
4.0 40 CFR 190 REQUIREMENTS The "Uranium Fuel Cycle" is defined in 40 CFR Part 190.02 (b) as follows:
"Uranium fuel cycle means the operations of milling of uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium-fuel
, generatian-of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but excludes mining operations, operations at waste disposal sites, transportation of any radioactive material in support of these operations, and the reuse of recovered non-uranium special nuclear and-by-product materials from the cycle."
Section 3.6.15.d of the Technical Specifications requires than when the v'alculated doses associated with the effluent releases exceed twice the limits of sections 3.6.15.a.(2)(b),
3.6.15.b.(2)(b) and 3.6.15.b.(3)(b),
then calculations shall be made including direct radiation contributions from the reactor units and outside storage tanks (as applicable) to determine whether the above 40 CFR 190 dose limits have been exceeded.
I
oocv REVIS}ON Rev.
1 4.4
'Doses to Members of the Public Within the Site Boundary.
Section 6.9.1.e of the Nine Mile Point Unit 1 Technical Specifications requires that the Semiannual Effluent Release Report include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary as defined by Figure 5.1-1 of the specifications.
A member of the public, as defined by the Technical Specifications, would be represented by an individual who visits the sites'nergy Information Center for the purpose of observing the educational displays or for picnicing and associated activities. lt is assumed that an individual would spend four hours per week for twelve weeks at the Energy Information Center.
The time spent at the facility is assumed to occur from approximately July 1 to September 30 of each year."
Thus, the first Semiannual Effluent Release Report will not address this particular dose because the summer season is the period of concern.
The second report will address this dose based on forty eight ho~rs occupancy The pathways considered for the evaluation include the inhalation pathway with the resultant lung dose and the direct radiation dose pathway with the associated total body dose.
The direct radiation dose pathway, in actuality, include several pathways.
These include:
the direct radiation gamma dose to an individual froa. on overhead
plume, a submersion gamma plume dose, and a ground plane dose (deposition).
pther pathways, such as the ingestion pathway, are not applicable.
In addition, pathways associated with water related recreational activities are not applicable here.
These inlcude swimming and wading which are prohibited at the facility.
l
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ODC M
REVISIOM Rev.
1 The inhalation pathway is evaluated by identifying the applicable radionuclides (radioiodine, tritium and particulates) in the effluent for the appropriate time period.
The radionuclide concentrations are the'n multiplied by the appropriate X/Q value, inhalation dose factor, air intake rate, and the fractional portion of the year in question.
Thus, the inhalation pathway is evaluated using the following equation adapted from Regulatory Guide 1.109 '
$ <[c< F x/Q DPA R tl where R
~
the dose for the period in question to the lung (j) for all radionuclides (i) for the adult age group (a) in mrem per time period.
The average concentration in the stack release of radionuclide i in pCi/m for the period in question 3
F Unit 1 average stack flowrate in m /sec.
3 X/Q "
The plume dispersion parameter for a location 0.50 miles west of NHP-1 (The plume dispersion parameter is 1.176E-07 and was obtained from the C.T-Hain five year average grazing season X/Q tables.
4 X/Q value based on real time meteorology may also be utilized for the period in question).
~r
ObCM AQUIgfOM Rev.
1 DFAija the inhalation dose factor for radionuclide i the lung j, and adult age group a in mrem per pCi found on Table E-10 of Regulatory Guide 1.109.
Ra annual-.air intake for individuals in age group a in M
per year (this value is 8,000 m
per year and 3
3 was obtained from Table E-5 of Regulatory Guide 1.109).
fractional portion of the year for which radionuclide i was detected and for which a dose is to be calculated (equals 0.23 years).
The direct radiation gamma dose pathway includes any gamma doses from an overhead plume, submersion in the plume and ground plane dose (deposition).
This general pathway will be evaluated by average environmental TLD readings.
At least two environmental TLD locations will be utilized and located in the approximate area. of the Energy Information Center (EXC) and the facility picnic area.
These TLDs will be placed in the field on approximately July 1 and removed on approximately September 30 of each year (this time interval is composed of one quarterly TLD collection period).
The average TLD readings will be adjusted by the average control TLD readings-This is accomplished by subtracting the average quarterly control TLD value from the average EIC TLD value.
The applicable quarterly control TLD values will be utilized after adjusting for the appropriate time period (as applicable).
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O-D C M
R'EV1 sfoM Rev.
1 EPA Crosscheck Program.
Participation shall be only for those media, e.g., air, milk, water, etc., that are included in the Nine Mile Point Environmental Monitoring Program and for which cross check samples are available.
The site identification symbol or the actual Quality Control sample results shall be reported in the Annual Radiological Environmental Operating Report so that the Commission staff may evaluate the results.
Specific sample media for which EPA Cross Check Program samples are available include the following:
gross beta in air particulate filters gamma emitters in air particulate filters t
I-131 in milk gamma emitters in milk gamma emitters in food product gamma emitters in water tritium in water I-131 in water 5.3 Capabilities for Thermoluminescent Dosimeters Used for Environmental Measurements Required detection capabilities for thermoluminescent dosimeters used for environmental measurements required by Table 4.6.20-1, footnote b
of the Technical Specifications are based on ANSI Standard
N545, section 4.3.
Required detection capabilities are as follows.
TLDs are defined as phosphors packaged for field use.
In regard to the detection capabilities for thermoluminescent dosimeters, only one determination is required to evaluate the above capabilities per type of TLD.
Furthermore, the above capabilities may be determined by the vendor who supplies the TLDs.
ne C
0 DCM REV1SlON Rev.
1 TABLE 2-1 Average Energy Per Disintegration fSOTDPE Ar-41 Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Kr-89 Kr-90 Xe-131M Xe-133 Xe-133m Xe-135 Xe-135m Xe-137 Xe-138 E Ymev/dis l.294 0.00248 0.0022
0. 159 0.793 1.95 2.22 2.10 0.0201 0.0454 0.042 0.247 0.432 0.194 1-18 (Ref)
(3)
(2)
(2)
Efeev/die(~ )
(Ref )
0.464 0.0371 0.250 0.253 1.32 0.377 1.37 1.01 0.143
0. 135 0.19 0.317 0.095 1.64 0.611 (3)
(2)
(2)
(1)
ORNL-4923, Radioactive Atoms Supplement I,;M.S. Martin, November 19?3.
(2)
NED0-12037, "Summary of Gamma and Beta Emitters and Xntensity Data"; M.E.
Meek, R.S. Gilbert, January 1970.
('l'he average energy was computed from the maximum energy using the ICRP XX equation, not the 1/3 value assumption used in this reference).
(3)
NCRP Report No. 58, "A Handbook of Radioactivity Measurements Procedures";
1978 (4)
The average energy includes conversion electrons.
s ~
O DGM RE%I fSlON I
Rev.
1 TABLE 3-1 Critical Receptor Dispersion Parameters LOCATION Residences*
Dairy Cows""
Milk Goats*"
DIR ESE Gardens*"
Site Boundary**"
ENE Meat Animals*"
SSE MELEE 1.4 3.0 1.8 1.5 0,4 sec X/g m
1.4 E-07 4.3 E&8 1.6 E-08 2.1 E-08 1.2 E-07 1.5 E-06 1
D/Q m
4.8 E-09 1.5 E-09 4.6 E-10 7.7 E-10 3.9 E-09 3.5 E-08 Value based on 5 year annual meteorological data Value based on 5 year average grazing season meteorological data Site boundary value based on most restrictive X/Q land-based sector (ENE) and 5 year annual average meteorological data.
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0-DCM REVt SION Rev.
1 TABLE 4-1 DOSE FACTORS FOR NOBLE GASES Radionuclides Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Xe-139 Ar-41 Gamma Air Dose Factor Mi mr r rGi-yr 1.93E+01
1. 23E&3 1-72E+01 6.17E+03 1.52E+04 1.73E+04 1.63E+04 3.27K+02 3.27E+02 3.53E+02 3.36E+03 1.92E+03 1.51E+03 9.21E+03 5.28E+03 9.30E+03 Beta Air Dose Factor Ni mrad-m3 uCi-yr 2.88E+02 1.97E+03 1.95K+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.48E+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 e.52E+04 3.28E+03 Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," dated October 1977, page 1.109-21.
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0 DC,IIII REVISlON Rev.
1 Nine Mile Point Nuclear Station Unit 1 Radiological Environmental Monitoring Program Sampling Locations Table 5.1 Type of Sample Radioiodine and Particulates (air)
Radioiodine and Particulates (air)
Radioiodine and Particulates (air)
Map Location Collection Site Nine Mile Point Road north Co. Rt.
29
& Lake Road Co. Rt.
29 Location 1.8 mi 8 88' 1.1 mi C4 104'SE 1.5 mi 8 132 SE Radioiodine and Particulates (air)
Village of Lycoming, NY 1.8 mi 8 143'E Radioiodine and Particulates (air)
Montario Point Road 16.4 mi 8 42'h Direct Radiation (TLD) 6 Direct Radiation (TLD) 7 Direct Radiation (TLD) 8 Direct Radiation Direct Radiation (TLD) 9 (TLD) 10 Direct Radiation (TLD) ll Direct Radiation (TLD) 12 Direct Radiation (TLD) 13 Direct Radiation (TLD) 14 Direct Radiation (TLD) 15 Direct Radiation (TLD) 16 Direct Radiation (TLD) 17 Direct Radiation (TLD) 18 North Shoreline Area North Shoreline Area North Shoreline Area North Shoreline Area JAP east boundary Rt.
29 Rt. 29 Miner Road Miner Road Lakeview Road Lakeview Road
.0.1 mi 8 5' 0.1 mi 8 25'NE
, 0-2 mi 8 45'E 0.8 mi 8 70'NE 1.0 mi 8 90' 1.1 mi C'15'SE 1-4 mi 8 133 SE 1.6 mi C'59'SE 1;bmi8 181 S
1.2 mi 4 200'SW 1.1 mi 8 225'4 Site Meteorological Tower 0.7 mi 6 250'SW Energy Information Center 0.4 mi 8 265'
Map See Figures 5.1-1 and 5.1-2
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0 DGM AEVISlON l, Rev.
1 Nine Mile Point Nuclear Station Unit 1 Radiological Environmental Monitoring Program Sampling Locations Table 5.1 (Continued)
Type of Sample Map Location Collection Site Location Direct Radiation (TLD) 19 Direct Radiation (TLD) 20 Direct Radiation (TLD) 21 Direct Radiation (TLD) 22 Direct Radiation (TLD) 23 Direct Radiation (TLD) 24 Direct Radiation (TLD) 25 Direct Radiation (TLD) 26 North Shoreline North Shoreline North Shoreline Demster Beach Road Leavitt Road Rt. 104 Rt. 51A Maiden Lane Road Direct Radiation (TLD)
Direct Radiation (TLD) 28 Co. Rt.
1 Direct Radiation (TLD) 31 S.W.
Oswego, Control Direct Radiation (TLD) 32
Scriba, NY Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD) 33 Alcan Aluminum, Rt. 1A 34
Lycoming, NY 35 New Haven, NY 36 W. Boundary, Bible Camp Direct Radiation (TLD) 37 Lake Road Surface Water Surface Water 38 OSS inlet Canal 39 JAFNPP Inlet Canal
Map See Figures 5.1-1 and 5.1-2 Direct Radiation (TLD) 29 Lake Shoreline Direct Radiation (TLD) 30
Phoenix, NY Control 0.2 mi 6 294'hW 0.1 mi (a 315'W 0.1 mi 8 341'NW 4.8 10i C4 97' 4.1 mi 8 ill ESE 4.2 mi 8 135'E 4.8 mi C4 156'SE 4.4 mi C" 183' 4.,4 mi 8 205'SW 4.7 mi 6 223 SW 4-1 mi 8 237'SW 19.8 mi
('. 170'-SSE 12.6 mi 8 226'lv 3.6 mi 8 199'SW 3.1 mi 8 220'k 1.8 mi C" 143'E 5.3 mi 8 123'SE 0.9 mi 8 237'W-WSW 1.2 mi 8 101 E-ESE 7.6 mi 8 235 SW-WSW 0.5 mi 8 70'NE
~i
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0 DCM hEV~S~OM r
~
Rev.
1 Nine Mile Point Nuclear Station Unit 1 Radiological Environmental Monitoring Program Sampling Locations Table 5.1 (Continued)
Type of Sample
Map Location Collection Site Location Shoreline Sediment Fish Fish 40 41 42 Sunset Bay Shoreline 1 5 mi 8 80' NMP Site Discharge Area 0.3 mi 6 315'W and/or NMP Site Discharge Area '.6 mi 8 55'E Fish Milk Milk Milk Milk Food Produc t Food Product Food Product 44 46 47 48 49 50 Oswego Harbor Area Milk Location //50 Milk Location 87 Milk Location f/16 Milk Location 840 Produce Location 81~*
(O'onnor)
Produce Location 82~*
(J. Parkhurst)
Produce Location 83**
(Fox) 6.2 mi 8 235'S%
9.3 mi
('. 93'E 5.5 mi 8 107'SE 5.9 mi C" 190' 15.0 mi 8 223'h 1.3 mi 8 98' 1.8 mi 8 96'SE 1.9 mi
(~ 101 ESE F ood Product 51 Produce Location 84"* '.5 mi 8 114'k (C. Parkhurst)
Food Product Produce Location 85"*
-"(C-.-R. Parkhurst) 2.1 mi 8 111' Food Product Food Product 54 Produce Location //6"*
(J-Lawton)
Produce Location 87**
(Mc Millen) 2.2 mi 8 123'h 15.0 mi 8 223 ESE 12.6 mi 8 225 S4 Food Product 55 Produce Location 88"*
(Denman)
Map See Figures 5.1-1. and 5.1-2
Food Product samples need not necessarily be collected from all listed locations.
Collected samples will be of the highest calculated site average D/Q.
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Rev.
0 ODCM - NINE MILE POINT Page
1.0 INTRODUCTION
2.0 LIQUID EFFLUENTS 2.1 Setpoint Determinations 2.2 Dose Determinations 3.0 GASEOUS EFFLUENTS 12 3.1 Setpoint Determinations 3.2 Dose Determinations 3.3 Critical Receptor 4.0 40 CFR 19 REQUIREMENTS 12 14 19 20 4.1 Evaluation of Doses From Liquid Effluents 4.2 Evaluation of Doses From Gaseous Effluents 23 24 4.3 Evaluation of Doses From Direct Radiation 5.0 ENVIRONMENTAL MONITORING PROGRAM 24
~ 25 5.1 Sampling Stations 5.2 Interlaboratory Comparison Program 25 5.3 Capabilities for Thermoluminescent Dosimeters Used for Environmental Measurements 26 TABLES APPENDIX 30 A
Dose Parameters for Iodine 131 and 133, Particulates and Tritium B Diagrams of Liquids and Gaseous Raduaste Treatments Systems Dispersion Calculation, Tables 72 79
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0 DGM REViSiOX O
Rev.
0
1.0 INTRODUCTION
The Offsite Dose Calculation Manual (ODCM) provides the methodology to be used for demonstrating compliance with the Radiological Effluent Technical Specifications (RETS),
10 CFR 20, 10 CFR 50, and 40 CFR 190.
The contents of the ODCM are based on Draft NUREG-0472, Revision 3, "Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors,"
September 1982; Draft NUREG-0473, Revision 2, "Radiological Effluent Technical Specifications for BWR's," July 1979; NUREG 0133,
~IPreparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"
October 1978; the several Regulatory Guides referenced in these documents;
and, communication with the NRC staff.
Notwithstanding the above, rather than redefine the basis for an offsite dose limit or release limit, the limits listed in the Etocixaamn Technical Specifications for Nine Mile Point Nuclear Stati'on Unit 1 dated Harch 1
1979 have been utilized whenever possible.
In this manner a
minimum number of changes to the current implementing procedures are I
needed.
One of the major differences between the RETS and OIKM and the Environmental Technical Specification is that release limits and offsite dose limits in the latter are based on site releases while they are based on unit releases in the former.
This difference is compensated for in the ODCM b setting the releases from other units at the site equal to zero.
Section 5 contains a detailed description of the Radiological Environmental Monitoring (REH) sampling locations.
These locations are subject to change based on the results of the annual Land Use Census.
Should it be necessary to revise the ODCM, these revisions will be made in accordance with Technical Specifications.
I
0 DC@
REVlSION 0
2.0 LIQUID EFFLUENTS 2.l Setpoint Determinations 2.1.1 Basis Monitor setpoints will be established such that the concentration of radionuclides in the liquid effluent releases in the discharge canal will not exceed those concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2.
Setpoints for the Service Water System Effluent Line will be calculated basi-! on the radionuclides identified during the previous year's releases from the liquid radwaste system or the isotopes identified in the most recent radwaste release.
Setpoints for the Liquid Radwaste Effluent Line will be based on, the radionuclides identified in each batch of liquid waste prior to its release.
After release, Liquid Radwaste the monitor setpoint may remain as set, or revert back to a setpoint based on a previous Semi-Annual Radioactive Effluent Release Report.
2 2
.l.
Service Water System Effluent Line Alarm Setpoint The, detailed methods for establishing setpoints for the Service Water System Effluent Line Monitor shall be contained in the Nine Mile Point Station Procedures.
These methods shall be in accordance with the following:
I
o pcM REVISION 0
gerPoinr (Hl Hl alarm)<D.9$ (C() (TDF)
(~CF
+ background Fsw V Ci K MPCi where Ci concentration of isotope i in the sample (units
~ uCi/ml)
TDF = Total Dilution Flow (units gallons/min)
F Service Water Flow (units gallons/min)
CF monitor calibration factor (units net cps/uCi/ml)
MPCi liquid effluent radioactivity concentration limit for radionuclide i as specified in 10 CFR 20, Appendix B, Table El, Column 2, for those nuclides present in the previous batch release from the liquid radwaste effluent system or for those nuclides present in the last Semi-annual Radioactive Effluent Release Report (units uCi/ml) or for those nuclides prese99e'n the service water system.**
factor to account for the presence of P emitters~
Z C
Required Dilution Factor MPCi TDF Actual Dilution Factor SW For periods with known reactor water to RCLC system
leakage, RCLC maximum
a. e
0 Bc' EV I Sl ON 0.,
Setpoint (Hi alarm)(0.? Setpoint (Hi-Hi alarm) 2.1 3.3 Liquid Radwaste Effluent Line Alarm Setpoint The detailed methods for establishing setpoints for the Liquid Radwaste Effluent Line Monitor shall be contained in the Nine Mile Point Station Procedures.
These methods shall be in accordance with the following:
Setpoint (Hi-Hi alarm)<0.9(ECi)
(TDF) (CF
)+ background Fre y Ci MP Ci where Ci activity of isotope i in the sample (units uCi/ml)
TDF =
Total Dilution Flow (units
~ gallons/min)
F cs re Radwaste Effluent Flow (units
~ gallons/min)
CF monitor calibration factor (units net cps/uCi/ml)
MPCi liquid effluent radioactivity concentration limit for radionuclide i as specified in 10 CFR 20, Appendix B, Table Il, Column 2, for those nuclides detected by spectral analysis of the contents of.the radwaste
.tanks to be released (units
~ uCi/ml) 0.9 factor to account for P emitters Required Dilution Factor MPC
1 P
P
\\
~'4(
g ~
~
oC 0 DCM I:EVlSlOM 0
Setpoint (Hi alarm)
~ <0.7 Setpoint (Hi-Hi Alarm)
Note:
If TDF ~
Ci Frq MPCi the discharge could not be made, since the monitor would be continuously in alarm.
To avoid this situation, F
will be reduced (normally by a factor re of 2) to allow setting the alarm point at a
t concentration higher than tank concentration.
This will also result in discharge canal concentration at approximately 50X maximum permissible concentration.
After the batch rele
e has been made from the liquid radwaste effluent system, the setpoint may remain the same or be returned to a level based on the previous Semi-Annual Radioactive Effluent Release Report where an actual release was made.
2.2 Dose Determination 2.2.1 Maximum Dose Equivalent Pathway A dose assessment report was prepared for the Nine Mile Poin t Unit 1 facility by Charles T. Main, Inc., of Boston, MA.
This report presented the calculated dose equivalent rates to individuals as well as the population within a 50~lie radius of the facility based on the radionuclides released in liquid and gaseous effluents during the time periods of 1 July 1980 through 31 December 1980 and from 1 January 1981 through 31 December 1981.
Utilizing the effluent data contained in the
I
0 DCM REVISION O
Rev.
0 R
~ 1100U M
E Q
B D
t )
apji ~p-P i fp afpj exp
(-
%1 p F
Where Rapji total annual dose to organ "j" of individuals of age group "a" from all of the nuclides "i" in pathway "p" (units mrem/year Ci)
U a
ap usage factor specifying the exposure time or intake rate for an individual of an age group "a" associated with pathway "p
(units
~ kg/year) mixing rates (reciprocal o'ilution factor) at the point of exposure or point of harvest (units dimensionless) flow rate of the liquid effluent (units
~
3 ft /sec)
Q sm i
release rate of radionuclide "i" (units Ci/year
)
Bip equilibrium bioaccumulation factor for nuclide "i" in pathway "p" (units liters/kg)
ro
0 DCM REV I SlON 0
D
~R aipj the dose factor, specific to a specific age group "a"; radionuclide "i", pathway "p",
and organ "j", which can be utilized to calculate the radiation dose from an intake of a radionuclide (units
~ mrem/pCi )
radioactive decay constant of nuclide "i"
-1 (units
~ hours
)
t P
the average transit time required for nuclides to reach the point of exposure.
For inter'nal dose, t
is the total time P
elapsed between the release of the nuclides and the ingestion of the food and/or water (units
~ hours) 1100
~
factor to convert from (Ci/year)/(ft /sec) to pCi/lite r 3
Values for R are contained in Table 2-1.
All of these apji values of R
are on a per Curie basis for each of the
..apji nuclides released.
Table 2-2 indicates those parameters used for selected factors of the formula.
Prior to each radioactive liquid discharge, each liquid waste tank to be discharged will be analyzed for isotope content
.utilizing a GeLi detector.
On the basis of this analysis, projected doses to an adult whole body and a teen liver will be calculated using the following relationships-
1 P
1.05
~
0 DCM BEYS StON 0
E correcti,on factor to account for 100X of dose assuming that 95X of dose received is delivered via the fish ingestion pathway.
Rev.
0 The basis for the derivation of the above parameters is contained in the preceding pages 6,
7 and 8 and on page 10.
As stated, it has been determined that greater than 95X of the projected organ and whole body dose from the liquid pathway comes from ingestion of fish.
The value of 1.05 is used in the equation as a conservative factor to increase the projected dose from an anticpated release to 100X.
All ro 'jected doses calculated in this manner for each batch of li uid efflu n q
e t will be summed for comparison with quarterl y and annual limits, added to the doses accumulated from other releases in the quarter and year of interest.
In all cases, the following relationships will hold:
For a calendar quarter:
D
< l. 5 mrem total body D
5 mrem for any organ Nt g ~
C
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I
~ I O,D C
M REV lSlON 0
Rev.
0 For the calendar year:
D
< 3.0 mrem'otal body D
< 10 mrem for any organ where D
t'otal dose received due to liquid effluent releases If these limits are
exceeded, a special report will be submitted to the NRC identifying the cause and proposed corrective actions.
In addition, if these limits are exceeded by a factor of two, calculations shall be made to determine if the dose limits contained in 40 CFR 190 have been exceeded.
Dose limits, as contained in 40 CFR 190 are total body and org;:n doses of 25 mrem per year and a thyroid dose of 75 mrem per year.
These calculations will include doses as a result of liquid and gaseous pathways as well as doses from direct radiation.
Liquid, gaseous and direct radiation pathway dose s will consider the James A. FitzPatrick', facility's ~11 as Nine Mile Point Nuclear Station.
In the event the calculations demonstrate that the 40 CFR 190 dose limits, as defined above, have been exceeded, then a
report shall be prepared and submitted to the Commission within 30 days as specified in Section 3.6.15.d of the Technical Specifications Section 4.0 of the ODCM contains moie information'concerning calculations for an evaluation of whether 40 CFR 190 limit's have been exceeded.
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$4& C 0 DCM AEVISI Og O
3 r 0 GASEOUS EFFLUENTS 3.1 Setpoint Determinations 3.1.1 Basis The monitor setpoints will be established such that the instantaneous release rate of radioactive materials in gaseous effluents does not exceed the 10 CFR 20 limits for annual release.
The setpoints will be activated if the annual dose at or beyond the site boundary would exceed 500 mrem to the whole
'I body or 3000 mrem to the skin from the continuous release of radioactive noble a
ble gas in the gaseous effluent.
The Stack Gas Moni.tor set oints wi P
ill be determined once per month and will be based on the isotoopic composition of the release.
Ef the calculated set oint is P
less conservative than the existing setpoint it is not mandatory that the setpoint be changed During outages, the last operating setpoint shall be used.
Followi ollowing an outage of greater tha 30 an days the setpoints at the time of shutdown shall be utilized until such time as the current isotopic composition of the effluent has been determined this period may not exceed one month.
3.1.2 Stack Monitor Setpoint The detailed methods for establishin set oin g
p ts shall be contained in the station procedures.
These methods shall be in accordance with the following-'12-
l l
0 oem REVlSION 0
.Rev.
0
(
) The release rate limit for noble gases from Nine Mile Point (1) Th Unit 1 is:
Z fg (1.6E
+ 0.3 E
}J i8 vhere. i ~
an individual nuclide release rate from Nine Mile Point Unit 1 main stack in Ci/sec for isotope i i
the average gamma energy per disintegration the average beta energy,per disintegration Refer to Table 3-1 for E and E
values.
s (2) Vtilizin th g
e isotopic composition of noble gas releases, determine fi (the fraction of each noble gas isotope in the effluent}
f
~ ~
C i
E Ci the concentration in uCi/cc of isotope i in the gaseous effluent.
( )
ermine the maximum acceptable release rate Qnax (Ci/sec)
(3) Determi for the isotopic mixture of noble gases'.
Qmax 1
Zffi (1'6 Eig +
0 EiS}j
0 DCM REViSfON 0
Rev.
0 (4) Determine the Hi Hi alarm point value Hi Hi Alarm Point
[(Qmax)(CF) j CF Calibration Factor (net cps/Ci/sec)
(5) The Hi. aLarm point value is 1/2 the Hi Hi alarm point value.
3.1.3 Recombiner Discharge Monitor The release rate at the Recombiner Discharge Monitor is limited to 500,000 uCi/sec (1 Ci/sec for up to 60 days).
(1) The Hi Hi alarm point value is determined as follows:
Hi Hi alarm point ~ 3/4* X 500 000 uCi/sec
~ Ll,900 mr/hr
31. 5 uCi/sec/mr/hr**
(2) and, the Hi alarm point value i.s Hi alarm point
~ 1/4* X 500,000 uCi./sec 3,960 mr/hr 31.5 uCi sec mr hr
3/4 and 1/4 re r p esent factors of conservatism which may be set less conservative if is weekly.
sotopic analysis frequency is increased from onthly t s
m 0
T i yp cal value, as determined by isotopic analysis.
3.2 Dose Determination 3.2.1 Dose Rate 3.2.1.1 Noble Gases In accordance with the provisions of 10 CFR 20 the dose rates from noble gas release to unrestricted areas are to be limited to 500 mrem/yr to the total I
P
0 DCNI REVlSiOM O
Rev.
0 body and 3,000 mrem/yr to the skin.
The monitor alarm setpoint determinations in Section 3.1 are based on this limit and setting the alarm setpoints in the manner specified will assure that these limits are not exceeded.
3.2.1.2 Tritium, Iodines and Particulates The dose rate in unrestricted areas from the release of tritium, iodine-131, iodine-133 and all radionuclides in particulate form with half lives greater than 8 days is limited to 1500 mrem/year to 1
any i>rgan.
In order to assure that this limit is not exceeded the average annual release rate of tritium E-131, I-133 and particulates with half lives greate~
than 8 days shall be-12X10 Q <1 4
p where:
release rate from Unit 1 stack in P
Ci/sec or the maximum release rate (Qpmax) shall not exceed-'pmax 1
8.3X10 Ci/sec.
83 uCi/sec 1.2 X 10 3.2.2 Dose Calculations will be performed monthly to demonstrate that doses resuLting from the release of noble gases,
tritium, I-131, I-133 and particulates with half lives greater than 8
days are within the limits specified in 10 CFR 50, Appendix I.
These limits are:
~ f l
P
0 DC@
Rn~SiO~
O Rev.
0 Noble Gas 5 mr gamma/calendar quarter 10 mrad beta/calendar quarter 10 mr gamma/calendar year 20 mrad beta/calendar year Radioiodines Tritium 6 Particulates t
7.5 mrem to any organ/calendar quarter 15 mrem to any organ/calendar year 3.2.2.1 Noble Gas The air dose at the critical receptor due to noble gas releases is determined as follows:
For gamma radiation D
= 3.17 x 10 E M X/Q i
i For beta radiation D>~ 3.17 x 10 E N X/Q Q
i whe re Mi air gamma dose factor in (mr/year 3
per uCi/m ) for each isotope i (Table 3-3)
J P
0 DC M REViSiON O
P Rev.
0 air beta dose factor (mrad/year per uCi/m ) for each isotope i (Table 3-3) 3 X/Q the highest calculated 5 year annual average relative concentration for areas at or beyond the site boundary (sec/m
) (Table 3
3-2) the total quantity of isotope i released during the period, (uCi)
-8 3
~ 17 X 10 the inverse of the number of seconds in a year 3.2.2.2 Radioiodine, Tritium 6 Particulates The doses to an individual from I-131, I-133, tritium, and particulates with half lives greater than 8 days will be calculated monthly as follows:
-8 Dose 3.17X10 Z
E R
M Q
i ijak j i Where Wj dispersion parameter either X/Q or D/Q depending on pathway Q
asi the total quantity of isotope i released during the period, (uCi) t'7
~h WV 0 DCM REV}SION Rijak the-dose factor for each isotope i, pathway age group a, and organ k (Table 3>>4, through S)
-8 3.17 X 10
~ the inverse of the number of seconds in a year The R values contained in Table 3-4 were calculated using the methodology defined in NUREG-0133 and Regulatory Guide 1.109, Revision 1.
3.2.2.3 A: cumulating Doses Doses will be calculated, monthly for the identified critical organ, age group, and pathway, and the results will be summed for each calendar quarter ard year.
Et has been historically demonstrated that the critical pathway is usually the grass-cow~ilk pathway and the critical organ is the infant's thyroid.
The critical doses are based on the following pathways.
noble gas plume dose ground plane dose (deposition) inhalation dose cow's milk dose goat's milk dose meat consumption dose vegetation (food crops) dose
0 DC M
REVtaiON O
Rev.
0 Critical receptor locations have been identified for the purposes of evaluating each pathway.
These receptor locations are contained in Table 3-2.
For the noble gas plume dose and inhalation dose the critical X/Q residence is applicable.
For the milk, meat and vegetation
dose, the critical receptor locations are the critical D/Q milk cow location, milk goat location, meat animal location and critical D/Q garden location.
The quarterly and annual results shall be compared to I
the limits listed in paragraph 3.2.2.
If the limits are exceeded, special reports as required by Section 6.9.3 of the Technical Specification must be submitted.
3.3 Critical Receptors In accordance with the provisions of 10 CFR 20 and 10 CFR 50, Appendix I, the critical receptors will be identified.
For noble
gases, only the external noble gas plume dose pathway will be considered and the location of concern will be the greatest X/Q residence as determined in specification 3.6.22 of the Technical Specifications.
For I-133, I-131, tritium and particulate radionuclides with a half life of greater than eight days, the critical pathways are milk (cow and goat),
meat, vegetation, inhalation and direct radiation (ground plane) as a result of ground deposition.
l 4
0 ocM REV.lSION The cow milk and goat milk pathvay will be based on the greatest D/4 milk cow and milk goat location as determined in specification Rev.
0 3.6.22.
The inhalation dose pathway will be based on the greatest x/!Q residence as determined in specification 3.6.22 since this location w
ocation would have the greatest potential residence time.
This critical receptor location is the same as the location used for the noble as lume g
p ume dose pathway.
The ground plane dose pathway vill be calculated as ht e greatest D/Q residence because of the greatest sidence time.
For the meat consumption dose pathvay, the potential reside critical receptor is the greatest D/Q meat animal location.
This location is determined in conjunction with the land use census (specification 3.6.22).
The vegetation (food crop) dose is based on the greatest D/Q garden location.
This location, as the critical meat animal locat 'n, will be determined in conjunction with the land use.census.
~
C
~i1
0 DCM REVlgl()g Rev.
0 EPA Crosscheck Program.
Participation shall be only for those media, e.g., air, milk, water, etc., that are included in the Nine Mile Point oint environmental monitoring program and for which cross check samples are available.
The site identification symbol or the actual Quality Control sample resuLts shall be reported in the Annual Rad 1
adiological Environmental Operating Report so that the Commission staff may evaluate the results.
5.3 Ca abilities f r P
o Thermoluminescent Dosimeters Used for Environmental Measurements Required detection capabilities for thermoluminescent dosimeters used for environmental measurements required by Table 4.6.20-1, footnote b
of the Technical Specifications are based on ANSI Standard
N545, section 4.3.
Required detection capabilities are as follows.
TLDs are defined as phosphors packaged for field use.
In regard to the detection capabilities for thermoluminescent
~
0 dosimeters, only one determination is required to evaluate the above capabilities per type of TLD.
Furthermore, the above capabilities may be determined by the vendor who supplies the TLDs.
Uniformity shall be determined by giving TLDs from the same batch an exposure equal to that resulting from an exposure rate of 10 uR/hr during the field cycle.
The responses obtained shall have a relative standard deviation of less than 7.5Z.
A total of at least 5 TLDs shall be evaluated.
I I
4
0 DCM REVfStOM 0
~t Rev.
0 TABLE 3-1 Average Energy Per Disintegration ISOTOPE Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Kr-89 Kr-90 Xe-131M Xe-133 Xe-133m Xe-135 Xe-135m Xe-13?
Xe-138 E3 mev/dis
0. 00248 0.0022 0.159 0.793
1. 95 2.22
2. 10 0.0201 0.0454 0.042 0.247 0.432
0. 194 1.18 (Ref)
(2)
(2}
E P mev/dis(3) 0.0371
0. 250
0. 253 1.32 0.377 1.37 1.01
0. 143 E
0.135 0.19
0. 317
0. 095
1. 64
0. 611 Ref )
(2)
(2)
(1) 0RNL-4923, Radioactive Atoms - Su plement I, M.S. Martin, November 1973.
(2)
NED0-12037, "Summary of Gamma and Beta Emitters and Intensity Data"
> M.E.
Meek, R.S. Gilbert, January 1970.
(The average energy Mas computed from the maximum energy using the ICRP II equation, not the 1/3 value assumption used in this reference).
(3)
The average energy includes conversion electrons.
J C
0 DCM REV I SiON O
.Reve 0
TABLE 3-2 Critical Receptor Dispersion Parameters LOCATION Residences Dairy Cows Milk Goats Meat Animals Gardens DIR ESE SW ESE MILES 1.2 1.6 2.9 1.6 1.6 (sec)
~X/
~m 1.00E-OV*
5.00E-08**
1.25E-08**
5.00E-08**
8.00E-08**
( 1)
D/Q m~
6.00E-09*
2.00E-09**
2.00E-10~*
2.00E-09**
2.50E-09**
Estimated value (conservative) based on 5 year annual meteorological data Estimated value (conservative) based on 5 year average grazing seaso'n meteorological data 1
P l
0 DCM REV l SION 0
TABLE 3-3 DOSE FACTORS FOR NOBLE GASES Radionuclides Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Xe-139 Ar-41 Gamma Air Dose Factor Mi mr m-uC g-yr
1. 93E+Ol
l. 23E+03
l. 72E+01 6.17E+03 1.51E+04 1.73E+04 1.63E+04 1.56E+02 3.27E+02 3.53E+02 3.36E+03 1.92E+03 1.51E+03
9. 21E+03
5. 28E+03
9. 30E+03 Beta Air Dose Factor Ni mrad-m3 uCi-yr
2. 88E+02 1 97K+03 1.95E+03 1.038+04 2.93E+03 1.06E+04 7.83E+03 1.11E+03 1.48E+03 1.05K+03
7. 39E+02 2.46E+03 1.27E+04 4.75E+03 6.52E+04 3.28E+03 Regulator Guide 1
09 y
.1 9, "Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix T.," dated October 1977, page 1.109-21.
P I'
0 DC,V REV) 8)OZ G
Rev. 0 Nine Mile Point Nuclear Station Unit 1
Radiation Environmental Monitoring Program Sampling Locations Table 5.1 Type of Map Sample Location Collection Site Location Radioiodine and Particulates (air)
Vi1.1age of Lycoming, NY 1.9 mi 8 145 SE Radioiodine and Particulates (air)
Radioiodine and Particulates (air)
Radioiodine and Particulates (air)
Near East Property Boundary of JAFNPP Rt.
29 NE Shoreline Area 1.0 mi 8 85' 1.3 mi 8 115'SE 0.8 mi 8 68'NE Radioiodine and Particulates (air)
Montario Point Road 16 4 mi 8 42'E Direct Radiation (TLD) 6 Direct Radiation (TLD) 7 Direct Radiation (TLD) 8 Direct Radiation (TLD) 9 Direct Radiation (TLD) 10 Direct Radiation (TLD) 11 Direct Radiation (TLD) 12 Direct Radiation (TLD) 13 Direct Radiation (TLD) 14 Direct Radiation (TLD) 15 Direct Radiation (TLD) 16 Direct Radiation (TLD) 17 Direct Radiation (TLD) 18 North Shoreline Area North Shoreline Area North Shoreline Area North Shoreline Area Sunset Bay Road Rt.
29 Rt.
29 Miner Road Miner Road Lakeview Road Lakeview Road 0.1 mi C
0.1 mi C'5'NE O.R mi 6 45'E 0.9 mi 8 75 ENE 1.2 mi 8 90' 1.3 mi 8 115 ESE 1.5 mi 8 135'E 1.8 mi 8 160 SSE 1.7 mi 8 180' 1.1 mi 8 200'SW 0.7 mi 8 225 SW Site Meteorological Tower 0.7 mi 8 250'SW Energy Information Center 0.5 mi 8 268'
Map - See Figures 5.1-1 and 5.1-2
l I
Ooeg-REVISlON
- 0
'Rev.
0 Nine Mile Point Nuclear Station Unit 1 Radiation Environmental Monitoring Program
- Sampling Locations Table 5,1 (Continued )
Type of Sample Map Location Collection Site Location Direct Radiation (TLD) 19 Direct Radiation (TLD) 20 Direct Radiation (TLD) 21 Direct Radiation (TLD) 22 North Shoreline North Shoreline North Shoreline Demster Beach Road Direct Radiation (TLD) 23 Leavitt Road Direct Radiation (TLD) 24 Rt.
104 Direct Radiation (TLD) 25 Rt. 5IA
.Direct Radiation
('OLD) 26 Maiden Lane Road Direct Radiation (TLD) 27 Rt.
53 Direct Radiation (TLD) 28 Mitchell Street 0.2 mi 9 29G'NM 0 ~ 1 mi Co 315 NW O.l mi 8 335'NM 4.5 mi 8 100' 4.2 mi 8 115'SE
4. 2 mi 8 140'E 4.8 mi 8 160 SSE 4.4 mi C'90' 4.8 mi 8 205 SSM 4.8 mi 8 220'W Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD) 29 Lake Shoreline 30
Phoenix, NY Control 31 S.M. Oswego, Control 32
Scriba, NY 4.4 mi 6 240 WSM
-2Q-.O mi 8 165'-SSE 12.8 mi 8 225 SW 4.1 mi 8 195'SW Direct Radiation (TLD)
Direct Radiation (TLD) 33
'Alcan'luminum, Rt. 1A 34
Lycoming, NY Direct Radiation (TLD) 35 New Haven, NY Direct Radiation (TLD)
Direct Radiation (TLD)
Surface Mater Surface Mater 36 W. Boundary, Bible Camp 37 Lake Road 38 OSS Inlet Canal 39 JAFNPP Inlet Canal
+Map - See Figures 5.1-1 and 5.1-2 3.2 mC 8 220 SM 1.9 mi (9 145'E 5.4 mi 9 120 ESE 0.9 mi 8 238'W-WSW 1.1 mi 8 105 E-ESE --
7.7 mi 8 230'W-MSM
'.5 mi 9 70 ENE I
C
'r
0 DCM REV~ SODOM 0
Rev.
0 Nine Mile Point Nuclear Station Unit 1 Radiation Environmental Monitoring Program Sampling Locations Table 5.1 (Continued )
Type of Sample Shoreline Sediment Fish Fish Fish Milk Milk Milk Milk Food Product Food Product Food Product Food Product Food Product Food Product Food Product Food Product
Map Location 40 41 44 46 47 48 50 51 52 53 "54 55 Collection Site, NMPNS Shoreline NMP Site Discharge Area NMP Site Discharge Area Oswego Harbor Area Milk Location 845 Milk LocMion 87 Milk Location 816 Milk Location f340 Produce Location //1**
Produce Location 82**
Produce Location 83**
Produce Location 84**
Produce Location 85**
Produce Location /36**
Produce."Location b'7**
Produce Location t!8**
Location 1.3 mi 8 82' 0.3 mi 8 315'>NW and/or 0.6 mi 6 55'E 6.3 mi 8 235 WSW 8.0 mi 8 125'E 5.5 mi 6 107'SE 5.2 mi 8 190' 15.2 mi e 220'W 1.6 mi C'5' 1.6 mi 9 115'SE 2.0 mi
(': 103'SE.2 mi 8 220 SW 1.3 mi. 6 225' 1.6 mi 8 132'E 2.'3 mi 8 118 ESE 12.6 mi 8 225'W
Map - See Figures 5.1-1 and 5.1-2
Food Product samples need not necessarily be collected from all listed locations.
Collected samples will be of the highest calculated site average D/g.
4 I
I'l
August 30, 1985 Dr. Thomas E. Murley Regional Administrator United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Re:
Nine Mile Point Unit f/1 Docket No. 50-220 DPR-63
Dear Dr. Murley:
In conformance with Amendment 66, Sections 3.6.14a and 6.9.1 of the Nine Mile Point Nuclear Station Unit 81 Technical Specifications, we are enclosing the Semi-Annual Radioactive Effluent Release Re ort for the period January 1,
1985, through June 30, 19 5.
Include in this report is (a) a summary of
liquid, gaseous and solid effluents released from the station during the reporting period (Tables 1-3),
(b) a description of and justification for recent.
changes to the Offsite Dose Calculation Manual (Table 5) and (c) an explanation as to the cause and corrective actions regarding current inoperability of the Station's Service Water Effluent Monitor (Table 6).
The format used for the effluent data is as outlined in Appendix B of Regulatory Guide 1.21, Revision
'1.
Distribution is in accordance with Regulatory Guide 10.1, 10 CFR 50.36a (a)(2) and the Technical Specifications If you have any questions concerning the attached
report, please contact James N. Duell, Supervisor Chemistry and Radiation Protection, at Nine Mile Point (315) 349-2426.
Very truly yours, Thomas E. Lempges r Vice President Nuclear Generation Enclosures (3 copies)
CC:
Director, Office of Nuclear Reactor Regulation (1)
Director, Office of Inspection and Enforcement (1)
Document Control Desk, U.S. Nuclear Regulatory Commission Washington, D.C.
20555 (1)
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'

ML18038A171

Contents

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

1.0 INTRODUCTION

1.0 INTRODUCTION

1.0 INTRODUCTION

1.0 INTRODUCTION

Dear Dr. Murley:

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ML18038A171

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

1.0 INTRODUCTION

1.0 INTRODUCTION

1.0 INTRODUCTION

1.0 INTRODUCTION

Dear Dr. Murley:

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