ML18018B098

Semi-Annual Radioactive Effluent Release Report July - December 1993

ML18018B098
Person / Time
Site:	Nine Mile Point
Issue date:	01/18/2018
From:	Niagara Mohawk Power Corp
To:	Office of Nuclear Reactor Regulation
References
Download: ML18018B098 (290)

Text

NINE MILE POINT NUCLEAR STATION-UNIT 1 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1993-NIAGARA MOHAWK POWER CORPORA TION J<v t Page 1 of 3 NINE MILE POINT NUCLEAR STATION-UNIT 1 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY-DECEMBER 1993 SUPPLEMENTAL INFORMATION

~Fi~lli: Nine Mile Point Unit¹1~Li ennea: Niagara Mohawk Power Corporation 1.TE HNI AL PE IFI ATION LIMIT 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.

B8LC)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 eight 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.004443LL l l I Page 2 of 3 D)LIQUID EFFLUENTS 1~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 entrained noble gases.For dissolved or entrained noble gas, the concentration shall be limited to 2E-04 microcuries/ml total activity.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 to 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.MEA REMENT AND APPR XIMATI N F T TAL RADI A TIVITY Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents, A)FISSION AND ACTIVATION GASES Noble gas effluent activity is determined by on-line gamma spectroscopic monitoring (intrinsic germanium crystal)or gross activity monitoring (calibrated against gamma isotopic analysis of a 4.0L Marinelli grab sample)of an isokinetic stack sample stream.B)IOD INES Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly)of charcoal cartridges sampled from an isokinetic stack sample stream.C)PARTICULATES Activity released from main stack is determined by gamma spectroscopic analysis (at least weekly)of particulate filters sampled from an isokinetic sample stream.For emergency condenser vent batch releases, effluent curie quantities are estimated by subtracting activity remaining in the shell side of the emergency condenser after batch release from activity delivered to the shell from Make-up sources.Actual isotopic concentrations are found via gamma spectroscopy.

Batch release activities of Sr-89, Sr-90 and Fe-55 are estimated by applying scaling factors to activity concentrations of gamma emitters.The activity of Tritium released during normal operation or during batch releases is conservatively estimated by multiplying recent condensate storage tank H-3 activity by assumed steaming rates out the vents.D)TRITIUM Tritium effluent activity is estimated by liquid scintillation or gas proportional counting of monthly samples taken with an air sparging/water trap apparatus.

004443 LL w4ci.Ngt Page 3 of 3E)LIQUID EFFLUENTS Isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters.F)SOLID EFFLUENTS Isotopic contents of waste shipments are determined by gamma spectroscopy, gross alpha and water content analyses of a representative sample of each batch.Scaling factors-established from primary composite sample analyses conducted off-site are applied, where appropriate, to find estimated concentration of non-gamma emitters.For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.004443LL U'It'i$4 F ATTACHIVIENT 1 Summary Data Page 1 of 2 Unit 1 X Unit 2 Uquid Effluents:

Reporting Period Jul-December 1993 10CFR20, Appendix B, Table II, Column 2~NA~NA Average Energy (Fission and Activation gases-Mev): Qtr.3 Qtr.4 Ey~6.07E-02 Ep~1.41E-01 Ey~8.12E-02 E~~1.72E-01 Uquid: There ware no liquid releases during the reporting period.Number of batch releases 0 Total time period for batch releases (hrs)NIA Maximum time period for a batch release (hrs): N/A Average time period for a batch release (hrs):~NA Minimum time period for a batch release (hrs):~NA Total volume of water used to dilute tho liquid effluent during release period (L)NIA Total volume of water available to dilute tho liquid effluent during reporting period (L)2.63E+11 UNIT 1 (ONI.YJ Gaseous (Emergency Condenser Vent): There were no releases from the operation of the emergency condenser vent.Number of batch releases 0 Total time period for batch releases (hrs)~NA Maximum time period for a batch release (hrs):~NA Average time period for a batch release (hrs)NIA Minimum time period for a batch release (hrs): N/A Gaseous (Primary Containment Purge): Number of batch releases Total time period for batch releases (hrs)0~NA Maximum time period for a batch release (hrs):~NA Average time period for a batch release (hrs):~NA Minimum time period for a batch release (hrs):~NA 004443 LL A l~,1 ATTACHMENT 1 Summary Data Page 20f 2 Unit 1 X Unit 2 bnormal Releases: There were no abnormal releases during the reporting period.Uquids: Number of releases 0 Reporting Period Jul-December 1993 B.Gaseous: Total activity released~NA Ci Number of releases 0 Total ectivity released~NA Ci 004443LL 4'IP ATfACHMENT 21 Unit 1 X Unit 2 Reporting Period Jul-December 1993 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL A.Fission r/E Activation Gases 1.Total release 2.Average release rate Ci/ICI/sec 3'EST.TOTAL QUARTER QUARTER~ERROR 3.63E+01 2.91E+00 5.00E+01 4.57E+00 3.66E-01 B.Iodiness 1.Total iodine-131 2.Average release rate for period Ci/ICI/sec~Q~0~0~0 3.00E+01 C.Perticuletess 1~Particulates with half-lives

)8 days 2.Average release rate for period 3.Gross alpha radioactivity D.Tritiums 1.Total release 2.Average release rate for period E.Percent of Tech S ec Limits Fission and Activation Gases Percent of Quarterly Gemma Air Dose Umit (5 mrem)Percent of Quarterly Beta Air Dose Limit (10 mrem)Percent of Annual Gamma Air Dose Limit to Date (10 mrem)Percent of Annual Beta Air Dose Umit to Date (20 mrem)Percent of Whole Body Dose Rate Limit (500 mrem/yr)Percent of Skin Dose Rate Limit (3000 mrem/yr)Tritium lodines end Particulates with half-lives rester than 8 da s Percent of Quarterly Dose Limit (7.5 mrem)Percent of Annual Dose Limit (15 mrem)Percent of Organ Dose Rate Limit (1500 mrem/yr)Ci/rCI/sec Ci Ci/iCI/sec 7.19E+00 1.74E+01 5.00E+01 8.57E-01 2.21E+00 2.98E-02 4.16E-03 3.01E-02 2.97E-03 7.31E-02 7.52E-02 1.22E-01 1.23E-01 7.09E-04 1.05E-04 2.84E-04 4.11E-05 1.20E-02 7.63E-02 9.92E-01 9.98E-01 2.26E-04 1.53E-03 6.39E-05 4.25E-04 3.00E+01 7.62E-06 5.41E-05 5.42E-05 3.80E-05 2.50E+01 An independent technical evaluation of the off-site vendor analyses performed by Niagara Mohawk Power Corporation has indicated a potential for a discrepancy in the data results.The resident inspectors at Nine Mile Point have been informed and corrective actions initiated.

Future Semi-Annual Radioactive Effluent Release Reports will reflect any changes as a result of this technical evaluation.

Concentrations less than the lower limit of detection of 1.00E-04/rCI/ml for noble gases, 1.00E-11/JCI/ml for particulates, 1.00E-12 pCI/ml for lodines, and 1.00E-06/ICI/ml for Tritium as required by Technical Specifications, afe indicated with a double asterisk.Tritium, Iron-55, and Strontium results were not received from the off-site vendor at the time of this report.These numbers include estimates, and actual numbers will be provided in the next Semi-Annual Report.004443LL

~~~f 8 P<>EST.TOTAL QUARTER QUARTER~ERROR A.Fission&Activation Products 1.Total release (not including Tritium, gases, alpha)2.Average diluted concentration during reporting period B.Tritium 1.Total release 2.Average diluted concentration during reporting period Ci/ICI/ml Ci/ICI/ml No Releases No Releases No Releasee No Releasee No Releases No Releases No Releases No Releases 5.00E+01 5.00E+01 C.Dissolved and Entrained Gases 1.Total release 2.Average diluted concentration during reporting period Ci pCI/ml No Releases No Releases No Releases No Releases 5.00E+01 D.Gross Al ha Radioactivit 1.Total release Ci No Releases No Releases 5.00E+01 E.Volumes 1.Prior to dilution 2.Volume of dilution water used during release period 3.Volume of dilution water available during reporting period Liters Liters Uters No Releases No Releases 1.28E+11 No Releases No Releases 1.35E+11 5.00E+01 5.00E+01 5.00E+01 F.Percent of Technical S ecification Limits Percent of Quarterly Whole Body Dose Umit (1.5 mrem)Percent of Quarterly Organ Dose Limit (5 mrem)Percent of Annual Whole Body Dose Limit to Date (3 mrem)Percent of Annual Organ Dose Umit to Date (10 mrem)Percent of 10CFR20 Concentration Umit Percent of Dissolved or Entrained Noble Gas Limit (1.00E-5/ICI/ml)

%No Releases No Releases No Releases No Releases No Releases No Releases No Releasee No Releases No Releases No Releasee No Releases No Releasee 004443LL

.1'k AT1ACHIVIENT 5 Page 20f 2 Unit 1 X Unit 2 UQUID EFFLUENTS RELEASED Reporting Period Jul-December 1993 BATCH MODE Nuclides Released Strontium-89 Strontium-90 Cesium-134 Cesium-137 Iodine-131 Ci Ci Ci Ci Ci 3" QUARTER No Releases No Releases No Releases No Releases No Releases 4o QUARTER No Releases No Releases No Releases No Releases No Releases Cobalt-58 Cobalt-60 Iron-59 Zinc-65 Manganese-54 Chromium-51 Ci Ci Ci Ci Ci Ci No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases Zirconium-Niobium-95 MolyMenum-99 Technetium-99m Barium-Lanthanum-140 Cerium-141 Ci Ci Ci Ci Ci No Releases No Releases No Releases No Releases No Releases No Releases No Releasee No Releases No Releases No Releases Tungsten-187 Arsenic-76 Iodine-133 Iron-55 Ne ptunium-239 Praseodymium-144 Iodine-135 Ci Ci Ci Ci Ci Ci Ci No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases Dissolved or Entrained Gases Tritium Cl Ci No Releases No Releases No Releases No Releases 004443LL a~4 II i ATTACHMENT 6 Page 1 of 6 Unit 1 X Unit 2 Reporting Period Jul-December 1993 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.1 TYPE Volume (ms)~Activit (Ci)Class Class 1.Spent Resin 5.83E+00 0 0 8.08E+00 0 0 Filter Sludge 5.50E+00 0 0 1.27E+01 0 0 Concentrated Waste Evaporator Bottoms Total 0 1.13E+01 0 0 0 0 0 1.88E+01 0 0 0 0 2.Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) 0 0 0 0 0 0 3.Irradiated Components There were no irrldeted components shipped for burial during the reporting period.An independent technical evaluation of the off-site vendor analyses performed by Niagara Mohawk Power Corporation has indicated a potential for a discrepancy in the data results.The resident inspectors at Nine Mile Point have been informed and corrective actions initiated.

Future Semi-Annual Radioactive Effluent Release Reports will reflect any changes as a result of this technical evaluation.

The estimated total error is 5.00E+01%.

004443LL P~4" ATTACHMENT 6 Page 20f 6 Unit 1 X Unit 2 Reporting Period Jul-December 1993 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.l TYPE Container~Paaka a Solidification

~Aaat Spent Resin Filter Sludge Concentrated Waste 2.Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) 3.Irradiated Components HIC HIC TYPE A TYPE A~NA~NA NONE CEMENT~NA 004443LL

'4<W, W I~II'l~+'S.W ATTACHMENT 6 Page 3 of 6 Unit 1 X Unit 2 Reporting Period Jul-December 1993SOUD WASTE AND IRRADIATED FUEL SHIPMENTS A.2.ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)a.Spent Resins, Filter Sludpes, Concentrated Waste: Nuclide Percent (1)(2)(3)(4)(5)(6)Co-60 Cs-137 Fe-55 Mn-54 Cs-134 Other 3.80E+01 3.29E+01 1.74E+01 6.98E+00 3.10E+00 1.56E+00 b.Dry Compressible'Waste, Dry Non-Compressible Waste (C ontaminated Equipment):

There were no shipments.

Nuclide~Percen c.Irradiated Components:

There were no shipments.

Nuclide~percen d.Other: There were no shipments.

Nuclide~Percen 004443 LL

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ATTACHMENT 6 Page 4 of 6 Unit 1 X Unit 2 A.3.SOLID WASTE DISPOSITION Reporting Period JuI-December 199 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Number of Shi ments Mode of rans o ation Destination Truck B mwll SC B.IRRADIATED FUEL SHIPMENTS (DISPOSITION)

There ware no shipments.

Number of Shi ments Mode of Trans ortation Destination 0 NIA~NA 004443LL 4 I'I\+J 4$E" t'=I'54*7 H\Q 4 ATTACHMENT 61 Page 5 Of 6 Unit 1 X Unit 2 Reporting Period Jul-December 1993 SOUD WASTE AND IRRADIATED FUEL SHIPMENTS C.-SOLID WASTE SHIPPED OFF-SITE TO VENDORS FOR PROCESSING AND SUBSEQUENT BURIAL Below is a summary of Dry Active Waste that was shipped off-site for processing and burial by vendor facilities (i.e., ALARON, QUADREX, and/or SCIENTIFIC ECOLOGY GROUP)during Jul-December 1993.These totals were reported separately from"10CFR61 Solid Waste Shipped for Burial" since (a)waste classification and burial was performed by the vendors, and (b)Technical Specification B.9.1 requires reporting of"information for each class of solid waste (as~defined by 10CFR61)shipped off-site during the reporting period".The information provided in this section,,therefore, is in addition to that required by the Technical Specifications.

The following data represents the actual shipments made from the off-site vendors of our non-compacted commingled trash that was processed prior to burial.C.1.TYPE OF WASTE-noncompacted commingled trash and contaminated fuel pool equipment shipped to Oak Ridge, TN for processing prior to burial at Barnwell, SC Burial Volume~m Activity~CI Est.Total~Brror 1.77E+01 5.32E-01 5.00+01 C.2.ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide~Percen (1)Co-60 (2)Cs-137 (3)Mn-54 (4)Co-58 (5)Fe-55 (6)Fe-59 (7)Other B.17E+01 2.09E+01 8.09E+00 4.20E+00 1.83E+00 1.58E+00 1.65E+00 C.3.SOLID WASTE DISPOSITIONS Number of Shi monte Mode of Trans ortatio Destination Truck B roweB SB An independent technical evaluation of the off-site vendor analyses performed by Niagara Mohawk Power Corporation has indicated a potential for a discrepancy in the data results.The rosident inspectors at Nine Milo Point have boon informed and corrective actions initiated.

Future Semi-Annual Redioactivo Effluent Release Reports will reflect any changes as a result of this technical evaluation.

The number of shipments reported hero represents tho total number that was shipped from the off-site vendor for burial..This does not represent th'e number of shipments Niagara Mohawk sent to be processed.

004443LL i Ir~W-'%P ATTACHIVIENT 6 Page 6 of 6 Unit 1 X Unit 2 Reporting Period Jul-December 1993 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS D.SEWAGE SLUDGE SHIPPED TO A TREATMENT FACILITY CENTER FOR PROCESSING AND BURIAL There were no shipments of sewage sludge with detectable quantities of plant-related nuclldes from NMP to the treatment facilitY during the reporting period.0 004443LL 1~f (

ATTACHMENT 7 Unit 1 X Unit 2 Reporting Period Jul-December 1993

SUMMARY

OF CHANGES TO THE OFFWITE DOSE CALCULATION MANUAL There was one revision to the Unit 1 ODCM during the reporting period.Revision 13 is attached along with a summary of changes presented to and approved by the Station Operations Review Committee In December 1993.The summary also includes a Justlflciation for each change.004443LL 1 Ill(hg ummar f ni 1 9 M han~Di~m~n:~Ti le: Unit 1 Offsite Dose Calculation Manual Revision 13 to the Offsite Dose Calculation Manual k~k Revision 13 to the Unit 1 ODCM was completed to comply with a milk location addition to the environmental program.The Unit 1 ODCM contains the methodology and parameters to determine gaseous and liquid setpoints for effluent streams.In addition, the Unit 1 ODCM contains dose and dose rate equations and parameters for determining compliance with 10CFR20, 10CFR50 and 40CFR190, in accordance with the requirements of the Unit 1 Technical Specifications.

Description Change/:~K.~Piintn:

I)~Pa~f-Table 5.1 is being updated to reflect an addition of a milk location to the environmental program (memo from B.Zacharek to B.Thomas, dated August 20, 1993).2)~Pa~-Map location¹73 for the additional milk location is being added to Figure 5.1-2.The Unit 1 ODCM.T hni lR vi w: A Technical Review was completed by B.Zacharek and H.Flanagan, Environmental Group.004475LL F I~+'C kht I" Jl>>

ATTACHMENT 8 Page 1 Of 3 Unit 1 X Unit 2 Reporting Period Jul-December 1993

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM The Unit 1 PCP Revision 01 was implemented in December 1993.Cop)es of Revisions 00 and 01 are attached.The following changes were approved by the Station Operations Review Committee ISORC)in November 1993 and do not affect or Impact the safety of radwaste operations.

These changes were done to improve and/or reflect current radwaste operations.

/Old':Page pg:;i)IteW:Pigs',Itr!::;::,:.',:,:::::c.;-','Section p,:;:,,:,>>..,':,:.:';,:

Table of Contents Deleted reference to commitments as a section.;;:;::,':,,i;::,Reason,'for.';.Chs'n'gag,',:,g i:: No commitments.

1.0~Added reference to D.O.T.regulations and guidelines.

~Deleted reference to wet waste.Clarification.

2.1.2 Removed

reference to specific Tech Specs section 8.5.2.11, and state,"In accordance with the applicable Tech Spec." Administrative change.3.1 Removed all reference and specific procedural requirements for types of waste (wet radioactive waste, dewatered spent bead resins, activated carbon and dewatered filter sludge)and replaced with general waste processing procedural requirements for any type of radioactive waste including the capability to use vendor equipment and vendor procedures.

Deletes specific procedures and allows processing using approved vendor equipment and procedures including the capability of dehydrating liquid waste as a method of processing waste to meet shipping and burial requirements.

3.2.4 Deleted

reference to CNSI procedures.

Deleted reference to specific procedures N1-LWPP-4,"Waste Transfer to a Shipping Cask, and N1-WHP-4,"Cask Loading" procedure.

Allows use of more then one vendor.Administrative to take specific procedure numbers out of tho manual and broaden with a more generio statement.

3.3.2 Changed

the requirement that,"The Manager of Chemistry shall ensure the chemical and radionuclide content of each sample is determined in accordance with N1-CSP-14V,'Collection and Analysis of Waste Samples'" to"Tho Manager of Chemistry shall ensure the chemical and radionucllde content of waste is determined in accordance with the applicable chemistry procedures." Administrative to take specific procedure numbers out of the manual and broaden with a mors generio statement.

004443LL J It~l<A h O'I 4+*P P/~al f~Wg v'x goal f ATTACHMENT 8 Page'2 of 3 gOld Page>¹j/New~:P>agi',:¹j~

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3 3.3.3 3.4.1.a 3.4.l.c Deleted the reference to"applicable S-RPIP's" and state"applicable radiation protection procedures." Deleted reference to the specific Tech Spec section, 6.9.1, Routine Reports.Deleted section.Administrative to take specific procedure numbers out of the manual and broaden with a more generic statement.

Administrative.

Addressed in 3.4.1.b.3.4.1.d Deleted reference to the reference GAP-INV-O2,"Control of Material Storage Areas." Administrative to take specific procedure numbers out of the manual and broaden with a more generic statement.

3 3.4.2.a Deleted reference to specifio Technical Specification section.Administrative.

3.4.2.b There is a typing error that was inadvertently approved;this will be corrected in next rovision of PCP.Clerical.3.4.3 Added the statement that personnel are effectively trained in accordance with the"applicable training procedures"~..Clarification to encompass all procedures.

3.4.3.a Changed statement of Radwaste Operator inidal qualification requirement from satisfactory completion of the Radwaste Operations Unit 1 Plant Training Program to state satisfactory completion of the Radwaste Operations Unit 1 Initial Training Program".Clarification.

3.4.3.a.1-4

~Switched and renumbered 3.4.3.a.1 with 3.4.3.a.2 and rewrote 3.4.3.a.2 to delete the reference to classroom instruction and to specific intent of on-the-job training objectives.

Added the statement"in accordance with applicablo training procedures." Clarification to take specific training out of the manual and broaden with a more generic statement to ensure compliance with all procedure requirements.

3.4.3.b and c~Deleted sections and Incorporated 3.4.3.b.1 and 3.4.3.b.2 into sections 3.4.3.a.3 and 3.4.3.a.4 respectively.

Continued training on an annual basis is changed to a cyclical basis and deleted reference to requalification training.Clarification.

In addition, remedial training will now be as directed by NTP-TQS-503 instead of by the General Supervisor Radwaste.Clarification.

004443LL g~

ATTACHIVIENT 8 Page 3 of 3@::::<gy:%

'~wgxw:!::',:New".,:P'age,¹',";:.:

3.4.4 Deleted

reference to specific quality assurance procedures and reports and stated that,"Training records and waste management records are maintained in accordance with the applicable quality assurance procedures." Clarification to take specific procedures out of the manual and broaden with a more generic statement to ensure compliance with all procedural requirements.

4.1-4.3 Deleted specIFic definitions and stated,"The applicable Radwaste packaging, processing and transportation definitions will be used in accordance with 49CFR171.8 and 49CFR173A03.

Deleted specific definitions and included references to 49CFR171.8 and 49CFR173.403.

5.1.1 Usted

the LCO and surveillance requirements separately as Tech Spec sections 3.6.16.c and 4.6.16.c, respectively.

Clarification.

6 5.3 Deleted reference to AP-3.3,"Radiation Protection Program," AP-3.3.2,"Radiation Work Permit," AP-3.3.3,"Radiation Worker Conduct", and added GAP-RAP<1,"Radiation Protection Program," and GAP-RAP<2,"Radiation Work Permit." Updated to incorporate current references.

8,9 7,8 Attachment 1 Deleted reference to N1-WHP-05,"On-Sits Drum Handling." Updated to reflect current references.

Updated the title to N1-LWPP-14,"Sump and Tank Cleaning" procedure.

Deleted reference to S-RPIP-7.5,"Van end Bathed Shipments." Added chemistry procedure,"N1-CTP-V402,"Radioactive Solid Waste Composites.

Updated the quality assurance procedures with revised title and numbers.Deleted training procedure NTP-13,"Training and Continued Training of Radwaste Operators." 004443LL ta 0 ATTACHMENT 9 Unit 1 X Unit 2 Reporting Period Jul-December 1993

SUMMARY

OF INOPERABLE MONITORS Monitor Dates of Inoperability Cause snd Corrective Actions There were no inoperable monitors for a period greater than 30 days during the reporting period.004443LL 4*4 4.

ATTACHMENT 10~Page 1 of 3 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1993)'NINE IVIILE POINT NUCLEAR STATION UNIT 1 DOSES TO IVIEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY-DECEIVIBER 1993 Doses to members of the public (as defined by the Technical Specifications) from the operation of the NMP1 facility as a result of activity inside the site boundary are controlled by activities at the Energy Center.This facility is open to the public and offers educational information, summer picnicking activities and fishing.Any possible doses received by a member of the public by utilizing the private road that transverses the east and west site boundaries are not considered here since it takes a matter of minutes to travel the distance.The activity at the Energy Center that is used for the dose analysis is fishing because it is the most time consuming.

Although there is no specific survey information available, many of the same individuals have been observed to return again and again because of the access to salmonid and lake trout populations.

Dose pathways considered for this activity include direct radiation, inhalation and external ground (shoreline sediment or soil)doses.Other pathways, such as ingestion pathways, are not considered because they are either not applicable, insignificant, or are considered as part of the evaluation of the total dose to a member of the public located off-site.In addition, only releases from the NMP1 stack were evaluated for the inhalation pathway.The emergency condensers were not operated during 1993.The direct radiation pathway is evaluated in accordance with the methodology found in the Off-site Dose Calculation Manual (ODCM).This pathway considers three components:

direct radiation from the generating facilities, direct radiation from any possible overhead plume and direct radiation from plume submersion.

The direct radiation pathway is evaluated by the use of high sensitivity environmental TLD's.Since any significant fishing activity near the Energy Center occurs between April through December, environmental TLD data for the approximate period of April 1-December 31, 1993 were considered.

Data from two environmental TLD's from the approximate area where the fishing occurs were compared to control environmental TLD locations for the same time period.The average fishing area TLD dose rate was 7.0E-03 mRem per hour for the period.The average control TLD dose rate was 5.7E-03 mRem per hour for the period (approximate second, third and fourth calendar quarters of the year).The average increase in dose as a result of fishing in this area at a conservative frequency of eight hours per week for thirty-nine weeks is 4.1E-01 mRem from direct radiation for the period in question.The majority of the dose from this pathway is from the NMP1 facility because'of its proximity to the fishing area.A small portion may be due.to the NMP2 facility.The inhalation dose pathway is evaluated by utilizing the inhalation equation in the ODCM, as adapted from the Regulatory Guide 1.109.The equation basically gives a total inhalation dose in mRem for the time period in question (April-December).

The total dose equals the sum, for all applicable radionuclides, of the NMP1 stack release concentration, times the average NMP1 stack flowrate, times the applicable five-year average calculated X/0, times the inhalation dose factors from Regulatory Guide 1.109, Table E-7, times the Regulatory Guide 1.109 annual air intake, times the fractional portion of the year in question.In order to be slightly conservative, no radiological decay is assumed.An independent technical evaluation of the off-site vendor analyses performed by Niagara Mohawk Power Corporation has indicated a potential for a discrepancy in the data results.The resident inspectors at Nine Mile Point have been informed and corrective actions initiated.

Future Semi-annual Radioactive Effluent Release Reports will reflect any changes as a result of this technical evaluation.

004443LL k 0 ATTACHMENT 10 Page 2 of 3 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1993)NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY-DECEMBER 1993 The 1993 calculation utilized the following information:

NMP1 Stack: Unit 1 average stack flowrate=1.04+02 m'/sec X/Q value=8.9 E-06 (annual NWN sector, historical average)Inhalation dose factor=Table E-7 of Regulatory Guide 1.109 Annual air intake=8000 m'er year (adult)Fractional portion of the year=0.0356 (312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />)Co-60=2.91E-01 pCi/m'e-55

=1,16E-01 pCi/m'r-89

=1.97E-01 pCi/m'r-90

=2,33E-02 pCi/m'-3=1.03E+04 pCi/m'-131

=7,90E-02 pCi/m'-133

=7.90E-02 pCi/m'-135

=1.42E-02 pCi/m'he inhalation dose to a member of the public as a result of activities inside the site boundary is 5.03E-04 mRem to the lung (maximum organ dose)and 4.34E-04 mRem to the whole body, The dose from standing on the shoreline to fish is based on the methodology in the ODCM, as adapted from Regulatory Guide 1.109.During 1993, it was noted that fishing was performed from the shoreline on many occasions although waders were also utilized.In order to be conservative, it is assumed that the maximum exposed individual fished from the shoreline at all times.The use of waders, of course, would result in a dose of zero from this pathway.The shoreline sediment doses are not taken into consideration by environmental TLD data.The ODCM equation basically gives the total dose to the whole body and skin from the sum of all plant-related radionuclides detected in shoreline sediment samples.The plant-related radionuclide concentration is adjusted for background sample results, as applicable.

The equation, therefore, yields the whole body and skin dose by multiplying the radionuclide concentration adjusted for any background data (as applicable), times a usage factor, times the sediment or soil density in grams per square meter (to a depth of one centimeter), times the applicable shore width factor, times the regulatory guide dose factor, times the fractional portion of the year over which the dose is applicable.

In order to be conservative and to simplify the equation, no radiological decay is assumed since the applicable radionuclides are usually long lived.004443LL kg I,J ATTACHMENT 10 Page 3 of 3 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1993)NINE IVllLE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY-DECEMBER 1993 The calculation utilized the following information:

Usage factor=312 hours Density in grams per meter=40,000 Shore width factor=0.3 Whole body and skin dose factor for each radionuclide

=Regulatory Guide 1.109, Table E-6 Fractional portion of the year=1 (used average radionuclide concentration over total time period)Average Cs-137 concentration

=0.295 pCi/g Average Co-60 concentration

=0.031 pCi/g The total whole body and skin dose from standing on the shoreline to fish is 6.61E-03 mRem whole body and 7.73E-03 mRem skin dose for the period.Doses to members of the public relative to activities inside the site boundary from aquatic pathways other than ground dose from shoreline sediment/soil are not applicable.

In summary, the total dose to a member of the public as a result of activities inside the site boundary from the direct radiation, inhalation and shoreline dose pathways is 4.2E-01 mRem to the whole body and 5.03-04 mRem to the maximum exposed internal organ (lung).The dose to the skin of an adult is 7.73E-03 mRem.These doses are generally a result of the operation of NMP1~However, a portion of these doses for the direct radiation pathway may be attributable to the NMP2 facility.004443LL 4~~A{g'l 0 ATTACHMENT 11 Page 1 of 3 SEIVII-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1993)NINE MILE POINT NUCLEAR STATION UNIT 1 RADIATION DOSES TO THE LIKELY MOST EXPOSED MEMBER OF THE PUBLIC OUTSIDE THE SITE BOUNDARY JANUARY-DECEMBER 1993 Radiation doses to the likely most exposed member of the public outside of the site boundary are evaluated relative to 40CFR190 requirements.

The dose limits of 40CFR190 are 25 mRem (whole body or organ)per calendar year and 75 mRem (thyroid)per calendar year.The intent of 40CFR190 also requires that the effluents of NMP2 as well as other nearby uranium fuel cycle facilities be considered.

In this case, the effluents of NMP1, NMP2 and the James A.FitzPatrick (JAF)facilities must be considered.

Doses to the likely most exposed member of the public as a result of effluents from the site can be evaluated by using calculated dose modeling based on the accepted methodologies of the facilities'ff-site Dose Calculation Manuals (ODCM's)or may, in some cases, be calculated from the analysis results of actual environmental samples.Acceptable methods for calculating doses from environmental samples are also found in the facilities'DCM's.

These methods are based on Regulatory Guide 1.109 methodology.

Dose calculations from actual environmental samples are, at times, difficult to perform for some pathways.Some pathway doses should be estimated using calculational dose modeling.These pathways include noble gas air dose, inhalation dose, etc.Other pathway doses may be calculated directly from environmental sample concentrations using Regulatory Guide 1.109 methodology.

Since the effluents from the generating facilities are low, the resultant gaseous and liquid effluent doses are anticipated to be low.In view of this, doses can be based on calculated data.Doses are not based on actual environmental data for 1993 with the exception of doses from direct radiation, fish consumption and shoreline sediment.In addition, in order to be conservative and for the sake of simplicity, it is assumed in the dose calculations that the likely most exposed member of the public is positioned in the maximum receptor location for each pathway at the same time.This approach is utilized because the doses are very low and the computations are greatly simplified.

The following pathways are considered:

1.The inhalation dose is calculated at the critical residence because of the high occupancy factor, In order to be conservative, the maximum whole body and organ dose assumes no correction for residing inside a residence.

2.The milk ingestion dose is calculated utilizing the maximum milk cow location.As noted previously, in order to be conservative and for the sake of simplicity, the likely most exposed member of the public is assumed to be at all critical receptors at one time.In this case, the member of the public at the critical residence is assumed to consume milk from the critical milk location.3.The maximum dose from the milk ingestion pathway as a result of consuming goat's milk is based on the same criteria established for item"2", above (ingestion of cow's milk).An independent technical evaluation of the off-site vendor analyses performed by Niagara Mohawk Power Corporation has indicated a potential for a discrepancy in the data results.The resident inspectors at Nine Mile Point have been informed and corrective actions initiated.

Future Semi-annual Radioactive Effluent Release Reports will reflect any changes as a result of , this technical evaluation.

004443LL h")

ATTACHIVIENT 11 Page 2of 3 SEIVII-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1993)NINE MILE POINT NUCLEAR STATION UNIT 1 RADIATION DOSES TO THE LIKELY MOST EXPOSED MEIVIBER OF THE PUBLIC OUTSIDE THE SITE BOUNDARY JANUARY-DECEMBER 1993 4, The maximum dose associated from consuming meat is based on the critical meat animal.The likely most exposed member at the critical residence is assumed to consume meat from the critical meat animal location.6.The maximum site dose associated with the consumption of vegetables is calculated from the critical vegetable garden location.As noted previously, the likely most exposed member of the public is assumed to be located at the critical residence and is assumed to consume vegetables from the critical garden location.The dose, as a result of direct gamma radiation from the site, encompasses doses from direct"shine" from the generating facilities, direct radiation from any overhead gaseous plumes, plume submersion and from ground deposition.

This total dose is measured by environmental TLD.The critical location is based on the closest year-round residence from the generating facilities as well as the closest residence in the critical downwind sector in order to evaluate both direct radiation from the generating facilities and gaseous plumes as determined by the local meteorology.

During 1993, the closest residence and the critical downwind residence are at the same location.7.8.The measured average dose for 1993 at the critical residence was 54.2 mRem.The average control dose was 50.0 mRem.The average dose at the critical residence is slightly greater than the average control location dose.The net increase in dose is due to the differences between doses from naturally occurring radionuclides in the soil and rock at the different locations and due to the standard deviation in TLD measurements.

This difference in dose rate can be demonstrated by observing the 1993 average dose for an environmental TLD located near the critical residence TLD, but approximately 700 feet closer to the generating facilities.

The annual average dose for this TLD location was 51.3 mRem.The dose for this location is lower than the critical residence location even though they are close to one another and even though the TLD location with the lowest dose is closer to the generating facilities.

The dose, as a result of fish consumption, is considered as part of the aquatic pathway.The dose for 1993 is calculated from actual results of the analysis of environmental fish samples.For the sake of being conservative, the average plant-related radionuclide concentrations were utilized from fish samples taken near the site discharge points.Only Cs-137 was detected during 1993.Adjusting the average concentration of Cs-137 in indicator samples by subtracting the average concentration of Cs-137 in control sampes resulted in a net negative concentration.

Therefore, no dose was calculated and assumed to be zero for this pathway.The shoreline sediment pathway is considered relative to recreational activities.

The dose due to recreational activities from shoreline sediment is based on the methodology in the ODCM as adapted from Regulatory Guide 1.109.The ODCM gives the total dose to the whole body and skin from the sum of plant-related radionuclides detected in actual shoreline sediment samples.The plant-related radionuclide concentration is adjusted for background sample results, as applicable.

The total whole body and skin dose from shoreline recreational activities is 1.02E-03 mRem whole body and 1.19E-03 mRem skin dose for the period.004443LL

4)

ATTACHMENT 11 Page 3 of 3 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1993)NINE MILE POINT NUCLEAR STATION UNIT 1 RADIATION DOSES TO THE LIKELY IVIOST EXPOSED MEMBER OF THE PUBLIC OUTSIDE THE SITE BOUNDARY JANUARY-DECEIVIBER 1993 9.In summary, the maximum dose to the most likely exposed member of the public is 1.67E-01 mRem to the thyroid (maximum organ dose)and 3.97E-02 mRem to the whole body.It should be noted that the maximum organ dose and maximum whole body doses are based on the sum of the maximum doses observed for all three facilities regardless of age group.This results in some conservatism.

The maximum organ and whole body doses were a result of gaseous effluents.

Doses as a result of liquid effluents were secondary.

The total whole body and skin dose from shoreline recreational activities are 1.02E-03 mRem whole body and 1.19E-03 mRem skin dose for the period.The direct radiation dose to the critical residence from the generating facilities was insignificant or zero.The dose to an individual as a result of fish consumption was also zero.These maximum total doses are a result of operations at the Nine Mile Point Unit 1, Nine Mile Point Unit 2 and the James A, Fitzpatrick facilities.

The maximum organ dose and whole body dose are below the 40CRF190 criteria of 25 mRem per calendar year to the maximum exposed organ or the whole body, andbelow 75 mRem per calendar year to the thyroid.004443LL l'l UPDATE TO THE PREVIOUS REPORTS 004443LL tt 4 II 1'I f Unit 1 X Unit 2 Reporting Period Janus-Juno 1993 UPDATE OF RELEASE AND DOSE DATA FOR GASEOUS EFFLUENTS-ELEVATED AND GRODND LEVEL UGVID EFFLUENTS Update of date using actual results from the off-site vendors for Strontium, Tritium, and Iron-55 for the second quarter of 1993.Particulates Nuclidet Sr-89 Sr-90 K-3 Fe-55 1.Particulates with half-lives

)8 days 2.Average release rate for period GASEOUS 2 QUARTER AetidteCJt 4.48E-05 6.31E+00 2.08E-05 Ci pCI/sec UQUID 2 QUARTER 5.42E-05 LIQUID~NA DNA~AclMt Ci No Releases No Releases No Releases No Releases GASEOUS 3.98E-04 Tritium Tritium lodines ond Particulates with half-lives rester than 8 do 8 1.Total release 2.Average release rate for period Ci pCi/sec 6.31E+00 8.60E-01 GASEOUS~NA~NA LIQUID 1.Percent of Quarterly Dose Umlt 2.Percent of Annual Dose Limit to Date 3.Percent of Organ-Dose Rate Umit (Gaseous)(Quarterly)

-Dose Umit (Uquid)(Annual Ik Quarterly) 4.Percent of 1OCFR20 Concentration Umit (0 quid)5.Percent of Dissolved or Entrained Noble Gas (Liquid)1.06E-01 (Quarterly) 9.85E-01 (Annual)2.27E-03 (Quarterly)

~NA (Annual)N/A~A (Quarterly)

~NA (Annual)~NA (Quarterly)

~NA (Annual)Concentrations less than tho lower limit of detection, as required by Technical Specifications are indicated with a double asterisk.Tho dose is to tho maximally exposed organ for gaseous effluents.

004443LL

'k 1 IA ATTACHMENT Bt Page 5 of 6 Unit 1 X Unit 2 Reporting Period Janus-June 1993 SOUD WASTE AND IRRADIATED FUEL SHIPMENTS C.SOLID WASTE SHIPPED OFF-SITE TO VENDORS FOR PROCESSING AND SUBSEQUENT BURIAL Below is a summary of Dry Active Waste that was shipped off-site for processing and burial by vendor facilities (i.e., ALARON, QUADREX, and/or SCIENTIFIC ECOLOGY GROUP)during Janus-June 1993.These totals were reported separately from"10CFR61 Solid Waste Shipped for Burial" (i.e., Section A of Table 3A)since (a)waste ciassificat(on and burial was performed by the vendors, and (b)Technical Specification

6.9.1 requires

reporting of"information for each class of solid waste (as defined by 10CFR61)shipped off-site during the reporting period".The information provided in this section, therefore, is in addition to that required by the Technical Specifications.

The following data represents the actual shipments made from the off-site vendors of our non.compacted commingled trash that was processed prior to burial.C.1.TYPE OF WASTE-noncompacted commingled trash and contaminated fuel pool equipment shipped to Oak Ridge, TN for processing prior to burial at Barnwell, SC Burial Volume~m Activity~CI Est.Total~Emr 1 929+01 2.71E-01 9.00n01 C.2.ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent (1)C0-60 (2)Cs-137 (3)Mn-54 (4)C0-58 (5)Fe-59 (6)Other C.3.SOLID WASTE DISPOSITIONs 5.98E+01 2.27E+01 9.54E+00 5.10E+00 1.88E+00 9.34E-01 Number of Shi ments Mode of Trans ortation Truck Truck~0B 8 El h 8 I 0 9 nwlt 00 Rlnhl nd WA This Attachment 6 supersedes the information provided in the January-Juno 1993 Semi-Annual Radioactive Effluent Release Report for Nine Mile Point Nuclear Station Unit 1.The number of shipments reported here represents the total number that was shipped from the off-site vendor for burial.This does not represent the number of shipments Niagara Mohawk sent to be processed.

004443LL

NINE MILE POINT NUCLEAR STATION NINE MILE POINT UNIT 1 OFF-SITE DOSE CALCULATION MANUAL ODCM APPROVALS S IGNATURES~M DATE AND INITIALS REVISION 13 K.A.Dahlberg Plant Manager Unit 1 C.D.Terry V.P.Nuclear Engineering NIAGARA MOHAWK POWER CORPORATION 004152LL Unit 1 ODCM Revision 13 October 1993 I

SUMMARY

OP REVISIONS PAGE Revision 13 Effective 12/31/93 DATE lg 2i 5g 6g 8i 9i 11 13/15 18'1'4i 25/36 44i 47 49'2-81,86-116 3i 4/7g 10'4/19'0'2'3'6 35 45i 46f 50i 51~82 85*29*64(77(78 19~21i 22AJ 22Bg 124'5i 26i 112 i g ii, iii, 12-1 6, 1 8, 28-40, 45-47 52i 55'9 89J 92J 93'7 129'1-93, 95 3, 4, 21, 92, 95a-c 10, 16-20 5i 13'8'0'5 30'5'9 66, 69 February 1987 December 1987 January 1988 May 1988 (Reissue)May 27, 1988-(Reissue)

February 1990 June 1990 June 1992 February 1993 March 1993 June 1993 December 1993 004152LL Unit 1 ODCM Revision 13 December 1993 I L~1k k"i Vh ,fly+4 j ,A4'~'

ODCM-NINE MILE POINT UNIT 1 TABLE OF CONTENTS

1.0 INTRODUCTION

2'LIQUID EFFLUENTS Pacae 2.1 Setpoint Determinations

2.1.1 Basis

2.1.2 Service Water System Effluent Alarm Setpoint 2.1.3 Liquid Radwaste Effluent Alarm Setpoint 2.1.4 Discussion 2.1.4.1 Control of Liquid Effluent Batch Discharges 2.1.4.2 Simultaneous Discharges of Radioactive Liquids 2.1.4.3 Sample Representativeness 2.1.4.4.Liquid Radwaste System Operation 2.1.4.5 Service Water System Contamination 2.2 2.3 Liquid Effluent Concentration Calculation Dose Determinations

2.3.1 Maximum

Dose Equivalent Pathway 3.0 GASEOUS EFFLUENTS 10 3.1 3.1.1 3.1.2 3.1.3 3.1.4 3.1.5 3.1.5.1 3.1.5.2 3.1.5.3 Setpoint Determinations Basis j Stack Monitor Setpoints'ecombiner Discharge (Off Gas)Monitor Setpoints Emergency Condenser Vent Monitor Setpoint Discussion Stack Effluent Monitoring

System Description

Stack Sample Flow Path-HAGEMS Stack Sample Flow Path-OGESMS 10 10 10 12 13 13 13 13 14 004152LL Unit 1 ODCM Revision 13 December 1993 T Nt<<w ,I ODCM-NINE MILE POINT UNIT 1 TABLE OF CONTENTS (Cont'd)3.1.5.4 3.1.5.5 3.1.5.6 3.2 3.2.1 3.2.1.1 3.2.1.2 3.2.2 3.2.2.1 3.2.2.2 3.2.2.3 3.3 3.44.0 4.2 4.3 4.4 5.0 5.1 5.2 5.3 Sample Frequency/Sample Analysis I-133 Estimates Gaseous Radwaste Treatment System Operation Dose and Dose Rate Determination Dose Rate Noble Gases Tritium, Iodines and Particulates Dose Noble Gas Air Dose Tritium'Iodines and Particulates Accumulating Doses Critical Receptors Refinement of Offsite Doses Resulting From Emergency Condenser Vent Releases 40 CFR 190 REQUIREMENTS Evaluation of Doses From Liquid Effluents Evaluation of Doses From Gaseous Effluents Evaluation of Doses From Direct Radiation Doses to Members of the Public Within the Site Boundary ENVIRONMENTAL MONITORING PROGRAM Sampling Stations Interlaboratory Comparison Program Capabilities for Thermoluminescent Dosimeters Used for Environmental Measurements Pacae 14 14 15 15 16 16 18 19 19 20 21 21 22 23 24 25 26 26 29 29 29 30 004152LL Unit 1 ODCM Revision 13 December 1993 I, ,P~4 ODCM-NINE MILE POINT UNIT 1 TABLE OF CONTENTS (Cont')Table 1-1 Tables 2-1 to 2-8 Table 3-1 Table 3-2 Table 3-3 Average Energy Per Disintegration

~Values for the NMP-1 Facility Critical Receptor Dispersion Parameters for Ground I evel and Elevated Releases Gamma Air and Whole Body Plume Shine Dose Factors for Noble Gases (B, and V~)Immersion Dose Factors for Noble Gases Pacae 32 33 41 42 43 Tables 3-4 to 3-22 Table 3-23 Table 5.1 Figure 5.1-1 Figure 5.1-2 Organ Dose and Dose Rate Factors (R,)Parameters for the Evaluation of Doses to Real Members of the Public from Gaseous and Liquid Effluents NMP-1 Radiological Environmental Monitoring Program Sampling Locations Nine Mil'e Point On-Site Map Nine Mile Point Offsite Map 63 64 68 69 Figure 5.1.3-1 Site Boundaries 70 Appendix A Appendix B Appendix C Appendix D Liquid Dose Factor Derivation (A)Plume Shine Dose Factor Derivation (B, and V,)Organ Dose and Dose Rate Factors for Iodine-131 6 133, Particulates and Tritium (R;)Diagrams of Liquid and Gaseous Radwaste Treatment Systems 71 74 78 88 004152LL-iii-Unit 1 ODCM Revision 13 December 1993

'tS V JW V

1.0 INTRODUCTION

The Offsite Dose Calculation Manual (ODCM)provides the methodology to be used for demonstrating compliance with the Radiological 3'ffluent T).chnical 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)sampling locations.

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

004152LL Unit 1 ODCM Revision 13 December 1993 S~,~5 e lt Ill F~"

2.0 F 1 2.F 1 LIQUID EFFLUENTS Setpoint Determinations 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 quarterly based 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 or other identified probable source.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, the Liquid Radwaste monitor setpoint 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 inoperable in accordance with the technical specification.

2'.2 Since the Service Water System effluent monitor and Liquid Radwaste effluent monitor can only detect gamma radiation, the alarm setpoints are calculated by using the concentration of gamma emitting isotopes only (or the corresponding MPC values for the same isotopes, whichever are higher)in the Z,(pCi/ml)p expression (Section 2.1.2, 2.1.3).The Required Dilution Factor is calculated using concentrations of all isotopes present (or the corresponding MPC values for the same isotopes, whichever are higher)including tritium and other non-gamma emitters to ensure that all radionuclides in the discharge canal do not exceed 10 CFR 20 limits.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 followings

((pCi/mi)lr/MPCI)

I Setpoint (Alert alarm)(0.7 Z Ci ml CF TDF F+background

((pCi ml)n MPC))I (pCi/ml)+(pCi/ml)n TDF concentration of gamma emitting isotope i in the sample, or the corresponding MPC of gamma emitting isotope i (MPC)whichever is higher (units=pCi/ml).concentration of any radioactive isotope i in the sample including tritium and other non-gamma emitters or corresponding MPC of isotope i, MPCwhichever is higher (units~pCi/ml).Total Dilution Flow (units~gallons/minutes).

Service Water Flow (units=gallons/minutes).

004152LL Unit 1 ODCM Revision 13 December 1993 Jr't4+'I W~IV"" ,A

2.1.2 Service

Water System Effluent Line Alarm Setpoint (Cont'd)CF MPH monitor calibration factor (units net cpm/pCi/ml

).liquid effluent radioactivity concentrations limit for radionuclide i as specified in 10 CFR 20, Appendix B, Table II, Column 2.Sample (MPC)v Those nuclides present i.n the previous batch release from the liquid radwaste effluent system or those nuclides present i.n the last Semi-annual Radioactive Effluent Release Report (units~pCi/ml)or those nuclides present in the service water system.**same as MPC, but for gamma emitti.ng nuclides only.0.9 and 0.7 factors of conservatism to account for inaccuracies.

E,[(pCi/ml)z/MPC,]

=Required Dilution Factor.If MPC values are used in the (pCi/ml)+, they must also be used in calculating RDF (numerator).

TDF/F~Actual Dilution Factor 2'~3 Liquid Radwaste Effluent Li.ne Alarm Setpoint The detailed methods for establishing setpoints for the Li.quid Radwaste Effluent Line Monitor shall be contained in the Nine Mile Poi.nt Station Procedures.

These methods shall be in accordance with the followings E~[(pCi/ml)s'/MPCI)(pCi/ml)+,[(pCi/ml)z/MPC,]concentration of gamma emitting isotope i in the sample or the corresponding MPC of gamma emitting isotope i, (MPC), whichever is higher.(pCi/ml)~concentration of any radioactive isotope i in the sample including tritium and other non-gamma emitters or the corresponding MPC of isotope i MPC, whichever is higher.(uni.ts=pCi/ml).TDF CF Total Di.lution Flow (units=gallons/minutes).

Radwaste Effluent Flow (units=gallons/minutes).

monitor calibration factor (units=net cps/pCi/ml).

• • For periods with known reactor water to RCLC system leakage, RCLC maximum permissible concentration may be prudently substituted for the above.004152LL Unit 1 ODCM Revision 13 December 1993 Nt It gt g~g>lt+'

2Liquid Radwaste Effluent Line Alarm Setpoint (Cont'd)MPC)(MPC)I 0.9 and 0.7 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=pCi/ml)same as MPC, but for gamma emitting nuclide only.factors of conservatism to account for inaccuracies.

E ((pCi/ml)s/MPC,]=Required Dilution Factor.If MPC values are used in the (pCi/ml)+, they must also be used in calculating RDF (numerator).

Notes: (a)If TDF/F=Zi[(pCi/ml)s/MPC,]

the discharge could not be made, since the monitor would be continuously in alarm.To avoid this situation, Fwill 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 50%maximum permissible concentration.(b)The value used for TDF will be reduced by the fractional quantity (1-FT), where FT is tempering fraction (i.e., diversion of some fraction of discharge flow to the intake canal for the purpose of temperature control).2.1.4 Discussion

~~2.1.4.1 Control of Liquid Effluent Batch Discharges At Nine Mile Point Unit 1 Liquid Radwaste Effluents are released only on a batch mode.To prevent the inadvertent release of any liquid radwaste effluents, radwaste discharge is mechanically isolated (blank flange installed or discharge valve chain-locked closed)following the completion of a batch release or series of batch releases.2.1.4.2 This mechanical isolation remains in place and will only be removed prior to the next series of liquid radwaste discharges after all analyses required in station procedures and Technical Specification Table 4.6.15-1A are performed and monitor setpoints have been properly adjusted.Simultaneous Discharges of Radioactive Liquids.If during the discharge of any liquid radwaste batch, there is an indication that the service water canal has become contaminated (through a service water monitor alarm or through a grab sample analysis in the event that the service water monitor is inoperable) the discharge shall be terminated immediately.

The liquid radwaste discharge shall not be continued until the cause of the service water alarm (or high grab sample analysis result)has been determined and the appropriate corrective measures taken to ensure 10CFR20, Appendix B, Table II, Column 2 (Technical Specification Section 3.6.15.a(1))

limits are not exceeded.004152LL Unit 1 ODCM Revision 13 December 1993 vt,~-'9're Xy~~kjUWl~lri'~~ok p 11 2'.4.2 Simultaneous Discharges of Radioactive-Liquids (Cont'd)In accordance with Site Chemistry procedures, controls are in place to preclude a simultaneous release of liquid radwaste batch tanks.-I'n additioii," an independent verification of, the discharge valve line-up is performed prior to discharge to ensure that simultaneous discharges are prevented.

2.1.4.3 Sampling Representativeness This section covers Technical Specification Table 4.6.15-1 Note b concerning thoroughly mixing of each batch of liquid radwaste prior to sampling.Liquid Radwaste Tanks scheduled for discharge at Nine Mile Point Unit 1 are isolated (i.e.inlet valves marked up)and at least two tank volumes of entrained fluids are recirculated prior to sampling.Minimum recirculation time is calculated as follows: Minimum Recirculation Time=2.0(T/R)Where: 2.0~Plant established mixing factor, unitless T~Tank volume, gal R~Recirculation flow rate, gpm Additionally, the Hi Alarm setpoint of the Liquid Radwaste Effluent Radiation Monitor is set at a value corresponding to not more than 70%of its calculated response to the grab sample or corresponding MPC values.Thus, this radiation monitor will alarm if the grab sample, or corresponding MPC value, is significantly lower in activity than any part of the tank contents being discharged.

2.1.4'~~~Liquid Radwaste Systems Operation Technical Specification 3.6.16.a requires that the liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge, as necessary, to meet the concentration and dose requirements of Technical Specification 3.6.15.Utilization of the radwaste system will be based on the capability of the indicated components of each process system to process contents of the respective low conductivity and high conductivity collection tanks: 1)Low Conductivity (Equipment Drains): Radwaste Filter and Radwaste Demin.(See Fig.B-1)2)High Conductivity (Floor Drains): Waste Evaporator (See Fig.B-1)Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined as described in Section 2.3 of this manual prior to the release of each batch of liquid waste.This same dose projection of Section 2.3 will also be performed in the event that untreated liquid waste is discharged, to ensure that the dose limits of Technical Specification 3.6.15.a(2) are not exceeded.(Thereby implementing the requirements of 10CFR50.36a, General Design Criteria 60 of Appendix A and the Design Objective given in Section II-D of Appendix I to 10 CFR50).004152LL Unit 1 ODCM Revision 13 December 1993 hp V 4'.i~C\C U ,e, P+h$+1 2.1.4.4 Liquid Radwaste Systems Operation (Cont'd)For the purpose of dose pro)ection, the following assumptions shall be made with regard to concentrations of non-gamma emitting~radionuclides subsequently analyzed off-site: a)[H-3]5 H-3 Concentration found recent condensate storage tank analysis 2.1.4.5 b)[Sr-89]s 4 x Cs-137 Concentration c)[Sr-90]5 0.5 x Cs-137 Concentration d)[Fe-55]5 1 x Co-60 Concentration Assumed Scaling Factors used in b, c, and d above represent conservative estimates derived from analysis of historical data from process waste streams.'ollowing receipt of off-site H-3, Sr-89, Sr-90 and Fe-55 analysis information, dose estimates shall be revised using actual radionuclide concentrations and actual tank volumes discharged.

Service Water System Contamination Service water is normally non-radioactive.

If contamination is suspected, as indicated by a significant increase in service water effluent monitor response, grab samples will be obtained from the service water discharge lines and a gamma isotopic analysis meeting the LLD requirements of Technical Specification Table 4.6.15-1 completed.

If it is determined that an inadvertent radioactive discharge is occurring from the service water system, then: a)A 50.59 safety evaluation shall be performed (ref.ICE Bulletin 80-10), 2~2 b)daily service water effluent samples shall be taken and analyzed for principal gamma emitters until the release is terminated, c)an incident composite shall be prepared for H-3, gross alpha, Sr-89, Sr-90 and Fe-55 analyses and, d)dose pro)ections shall be performed in accordance with Section 2.3 of this manual (using estimated concentrations for H-3, Sr-89, Sr-90 and Fe-55 to be conservatively determined by supervision at the time of the incident).

Additionally, service water effluent monitor setpoints may be recalculated using the actual distribution of isotopes found from sample analysis.Liquid Effluent Concentration Calculation This calculation documents compliance with Technical Specification Section 3.6.1.5.a (1).The concentration of radioactive material released in liquid effluents to unrestricted areas (see Figure B-7)shall be limited to the concentrations specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases.For dissolved or entrained noble gases, the concentration shall be limited to 2 E-4 microcurie/milliliter (pCi/ml)total activity.004152LL Unit 1 ODCM Revision 13 December 1993 lb*

2~2 Liquid Effluent Concentration Calculation (Cont'd)The concentration of radioactivity from Liquid Radwaste batch releases and, if applicable, Service Water System and emergency condenser+tart-up vent discharges are included in the calculation The calculation is performed for a specific period of time.No credit taken for averaging over the calendar year as permitted by 10CFR20.106.

The limiting concentration is calculated as follows: MPC Fraction~E<[(E, CF,)/(MPC; E, F,)]Where: MPC Fraction The limiting concentration of 10 CFR 20, Appendix B~Table II, for radionuclides other than dissolved or entrained noble gases.For noble gases, the concentration shall be limited to 2 E-4 microcurie/ml total activity.C~(pCi/ml)

~The concentration of nuclide i in particular effluent stream s, pCi/ml.F,"MPCi The flow rate of a particular effluent stream s, gpm.The limiting concentration of a specific nuclide i from 10CFR20, Appendix B, Table II, Column 2 (noble gas limit is 2E-4 pCi/ml).Z,(pCi/ml)F,)

=The total activity rate of nuclide i, in all effluent streams s.2~3 2.3~1 The total flow rate of all effluent streams s, gpm (including those streams which do not contain radioactivity)

.A value of less than one for MPC fraction is considered acceptable for compliance with Technical Specification Section 3.6.15.a.(1).

Dose Determination Maximum Dose Equivalent Pathway A dose assessment report was prepared for the Nine Mile Point 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-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 January 1981 through 31 December 1981.The radwaste liquid releases are based on a canal discharge rate of 590 ft~/sec which affects near field and far field dilution;therefore, this report is specific to this situation.

Utilizing the effluent data contained in the Semi-Annual Radioactive Effluent Release Reports as source terms, dose equivalent rates were determined using the environmental pathway models specified in Regulatory Guides 1.109 and 1.111 as incorporated in the NRC computer codes LADTAP for liquid pathways, and XOQDOQ and GASPAR for gaseous effluent pathways.Dose equivalent rates were calculated for'the total body as well as seven organs and/or tissues for the adult, teen, child, and infant age groups.From the standpoint of liquid effluents, the pathways evaluated included fish and drinking water ingestion, and external exposure to water and sediment.004152LL Unit 1 ODCM Revision 13 December 1993

, l fm I'

2.3.1 Maximum

Dose Equivalent Pathway (Cont'd)The ma)ority of the dose for a radwaste liquid batch release was received via the fish pathway.However, to comply with Technical Specifications for dose pro)ections, the drinking water and sediment pathways are included.Therefore, all doses due to liquid effluents are calculated monthly for the fish and drinking water ingestion pathways and the sediment external pathway from all detected nuclides in liquid effluents released to the unrestricted areas to each organ.The dose projection for liquid batch releases will also include discharges from the emergency condenser vent as applicable, for all pathways.Each age group dose factori~i is given in Tables 1-1 to 1-8.To expedite time the dose is calculated for a maximum individual instead of each age group.This maximum individual will be a composite of the highest dose factor of each age group for each organ, hence A.The following expression from NUREG 0133, Section 4.3 is used to calculate doses i (ASi(r.a.i))Where: D, The cumulative dose commitment to the total body or any organ, from the liquid effluents for the total time period (dT), mrem.hT~The length of the L th time period over which C~and Fz are averaged for all liquid releases, hours.Cz=The average concentration of radionuclide, i, in undiluted liquid effluents during time period hTfrom any liquid release, pCi/ml.The site related ingestion dose commitment factor to the total body or any organ t for each identified principal gamma or beta emitter for a maximum individual, mrem/hr per pCi/ml.The near field average dilution factor for Ca during any liquid effluent release.Defined as the ratio of the maximum undiluted liquid waste flow during release to the average flow from the site discharge structure to unrestricted receiving waters, unitless.A values for radwaste liquid batch releases at a discharge rate"of 295 ft~/sec (one circulating water pump in operation) are presented in tables 1-1 to 1-4.A values for an emergency condenser vent release are presented in tables 1-5 to 1-8.The emergency condenser vent releases are assumed to travel to the perimeter drain system and released from the discharge structure at a rate of.33 ft/sec.See Appendix A for the dose factor Q, derivation.

To expedite time the dose is calculated to a maximum individual.

This maximum individual is a composite of the highest dose factor A of each age group a for each organ t and each nuclide i.If a nuclide is detected for which a factor is not listed, then it will be calculated and included in a revision to the ODCM.All 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: 004152LL Unit 1 ODCM Revision 13 December 1993 Jk Q't fq n I'l I nfl~i~4"

2.3.1 XaxisLua

Dose Equivalent Pathway (Cont'd)For a calendar quarters D,<1.5 mrem total body D,<5 mrem for any organ For the calendar year: D,<3.0 mrem total body D,<10 mrem for any organ Where: D, total dose received to the total body or any organ 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 organ 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.

The liquid pathway analysis will only include the fish and sediment pathways since the drinking water pathway is insignificant.

This pathway is only included in the station's effluent dose projections to comply with Technical Specifications.

Liquid, gaseous and direct radiation pathway doses will consider the James A.FitzPatrick and Nine Mile Point Unit II facilities as well as Nine Mile Point Unit I 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 more information concerning calculations for an evaluation of whether 40 CFR 190 limits have been exceeded.004152LL Unit 1 ODCM Revision 13 December 1993

~I gl~~'I Q.J-it~(Tf"A~a jgQ),"y, qV I~II V'~I%II I'llew I 3~0 GiLSEOUS EFFLUENTS F 1 Satpoiat Determinations 3'.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.Emergency condenser vent monitor setpoints will be established such that the release rate for radioactive materials in gaseous effluents do not exceed the 10 CFR 20 limits for annual release rate over the pro)ected longest period of release.Monitor setpoints from continuous release points will be determined once per quarter under normal release rate conditions and will be based on the isotopic composition of the actual release in progress, or an offgas isotopic distribution 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 the setpoint be changed.Monitor setpoints for emergency condenser vent monitors are conservatively fixed at 5 mr/hr for reasons described in Sections 3.1.4 and therefore do not require periodic recalculations.

Under abnormal site release rate conditions, monitor alarm Betpoints from continuous release points will be recalculated and, if necessary, reset at more frequent intervals as deemed necessary by CORM Supervision.

In particular, contributions from both JAF and NMP-2 and the Emergency Condenser Vents shall be assessed.During outages and until power operation is again realized, the last operating stack and off gas monitor alarm setpoints shall be used~Since monitors respond to noble gases only, monitor alarm points are set to alarm prior to=exceeding the corresponding total body dose rates.3~1~2 The skin dose rate limit is not used in setpoint calculations because it is never limiting.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',=release rate max.allowable corresp.dose rate, actual corresp.dose rate, max.allowable E iQi(%+(SF)

W(~/Q).)500 mrem/yr 004152LL 10 Unit 1 ODCM Revision 13 December 1993

<<4 P 4~4'i).>

3.1.2 Stack

Monitor Setpoints (Cont'd)Where: releaae"rate for each isotope i, pCi/sec.V)gamma whole body dose factor in units of mrem/yr per pCi/sec.(See Table 3-2).(Q)=instantaneous release rate limit pCi/sec.(2)To ensure that 10 CFR 20 and Technical Specifications dose rate limits are not exceeded, the Hi Hi alarms on the stack monitors shall be set lower than or equal to (0.9)(Q).Hi alarms shall be set lower than or equal to (0.5)(Q)(3)(4)Based on the above conservatism, the dose contribution from JAF and NMP-2 can usually be ignored.During Emergency Classifications at JAF or NMP-2 due to airborne effluent, or after emergency condenser vent releases of significant proportions, the 500 mrem/yr value may be reduced accordingly.

To convert monitor gross count rates to pCi/sec release rates, the following general formula shall be applied: (C-B)K,~Q~pCi/sec, release rate Where: C~B monitor gross count rate in cps or cpm monitor background count rate stack monitor efficiency factor with units of pCi/sec-cps or pCi/sec-cpm (5)Monitor K, factors shall be determined using the general formula:~LQl/(C"B)Where: Q,~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.Alternatively, when stack release rates are near the lower limit of detection, the following general formula may be used to calculate k,: 1/K,=E~Z F E Y 3.7E4da f f Sec.-pCi Where: stack flow in cc/sec.efficiency in units of cpm-cc/pCi or cps-cc/pCi (cpm~counts per minute;cps~counts per second).E~cpm-cc/bps or cps-cc/@ps.

.From energy calibration curve produced during NZST traceable primary gas calibration or transfer source calibration (bps=beta per second;Yps=gammas per second).004152LL Unit 1 ODCM Revision 13 December 1993 IR pa~e peal 3'.2 Stack Monitor Setpoints (Cont'd)Y~b/d (betas/disintegration) or y/d (gammas/disintegration).

P,~Activity fraction of nuclide i in the mixture.i=nuclide counter.k=discrete energy beta or gamma emitter per nuclide counter.s=seconds.This monitor calibration method assumes a noble gas distribution typical of a recoil release mechanism.

To ensure that the calculated efficiency is conservative, beta or gamma emissions whose energy is above the range of calibration of the detector are not included in the calculation.

3.1~3 Recombiner Discharge (Off Gas)Monitor Setpoints (1)The Hi-Hi alarm points shall activate with recombiner discharge rates equal to or less than 500,000 pCi/sec.This alarm point may be set equal to or less than 1 Ci/sec for a period of time not to exceed 60 days provided the offgas treatment system is in operation.

(2)'The Hi alarm points shall activate with recombiner discharge rates equal to or less than 500,000 pCi/sec.According to the Unit 1 Technical Specifications, Note (C)to Table 4.6.14-2, the channel functional test of the condenser air ejector radioactivity monitor shall demonstrate that automatic isolation of this pathway occurs if either of the following conditions exist: i)Instruments indicate two channels above the Hi-Hi alarm setpoint, ii)Instruments indicate one channel above Hi-Hi alarm setpoint and one channel downscale.

This automatic isolation function is tested once per operating cycle in accordance with station procedures.

(3)To convert monitor mR/hr readings to pCi/sec, the formula below shall be applied: (R)(KR)=Qg pCi/sec recombiner discharge release rate Where: R=mR/hr monitor indicator.

K=efficiency factor in units of pCi/sec/mR/hr determined prior to setting monitor alarm points.(4)Monitor KR factors shall be determined using the general foimula: KR=EiQ(/R Where: Q,~individual radionuclide recombiner discharge release rate as determined by isotopic analysis and flow rate monitor.Kfactors more conservative than those calculated by the above methodology may be assumed.004152LL 12 Unit 1 ODCM Revision 13 December 1993 I~I5 3Recombiner Di.scharge (Off Gas)Monitor Setpoints (Cont'd)(5)The setpoints chosen provide assurance that the total body exposure to an indivi.dual at the exclusion area boundary will not excead a very small fraction of the limits of 10CFR Part 100-in the event this effluent is inadvertently discharged directly to the environment without treatment (thereby implementing the requirements of General Design Cri.teria 60 and 64 of Appendix A to 10CFR Part 50).Additionally, these setpoints serve to limit bui.ldup of fission product activity within the station systems which would result if high fuel leakage were to be permitted over extended periods.3 1'Emergency Condenser Vent Moni.tor Setpoi.nt The monitor setpoint was established by calculation

(" Emergency Condenser Vent Monitor Alarm Setpoint", January 13, 1986, NMPC File Code f16199).Assuming a hypothetical case with (1)reactor water iodine concentrations higher than the Technical Specificati.on Limit@(2)reactor water noble gas concentrations higher than would be expected at Technical Specification iodine levels, and (3)leakage of reactor steam into the emergency condenser shell at 300%of rated flow (or 1.3 E6 lbs/hr), the calculation predi.cts an emergency condenser vent monitor response of 20 mR/hr.Such a release would result in less than 10 CFR 20 dose rate values at the site boundary and beyond for typi.cal emergency condenser cooldown periods.Since a 20 mR/hr monitor response can, in theory, be achievable only when reactor water iodi.nes are higher than permitted by Technical Specifications, a conservative monitor setpoint of 5 mr/hr has been adopted.3~1~5 3.1~5.1 Discussion Stack Effluent Monitoring System Descripti.on The NMP-1 Stack Effluent Monitoring System consists of two subsystems; the Radioactive Gaseous Effluent Monitoring System (RAGEMS)and the old General Electric Stack Monitoring System (OGESMS).During normal operation, the OGESMS shall be used to monitor station noble gas effluents and collect particulates and iodine samples in compliance with Technical Specification requirements.

The RAGEMS is designed to be promptly activated from the Main Control Room for use i.n high range monitoring during accident situations in compliance with NUREG 0737 criteria.Overall system schematic for the OGESMS and RAGEMS are shown on Figure B-9.A simplified view of RAGEMS Showi.ng Unit 0, 1, 2, 3 and 4 can be found on Figure B-S.The RAGEMS can provide continuous accident monitoring and on-line isotopic analysis of NMP-1 stack effluent noble gases at Lower Levels of Detection less than Technical Specification Table 4.6.15-2 limits.Activities as low as 5.0E-S and as high as 2.0ES pCi/cc for noble gases are detectable by the system.3~1~5+2 Stack Sample Flow Path-RAGEMS The effluent sample is obtained inside the stack at elevation 530'sing an isokinetic probe with four orifices.The sample line then bends radially out and back into the stack;descends down the stack and out of the stack at approximately elevation 257';runs horizontally (enclosed in heat tracing)some 270'long the off gas tunnel;and enters the RAGEMS located on the Turbine Building 250'Dilution cabinet-Unit 0)and Off Gas Building 247'Particulate, Iodine, Noble Gas stations-Units 1-3).004152LL 13 Unit 1 ODCM Revision 13 December 1993 lg t A t 3.1.5.2 Stack Sample Flow Path-RAGEMS (Cont'd)In the Di.lution cabinet of the RAGEMS, the stack gas may be diluted during accident situations approximately 100-200X (first stage)or 10000-40000"X (first and second stage)with,gaseous nitrogen supplied from an on-site liquid nitrogen storage tank (see Figure B-9).From Unit 0, the sample gas enters Unit 1-3 of RAGEMS and flows thru in-line particulate and iodine cartridges and then thru either a 6 liter (low range)or 30 cc (hi.gh range)noble.gas chamber.The sample gas next flows back thru Unit 0 and the off gas tunnel;and back into the stack.3~1~5.3 Stack Sample Flow Path-OGESMS The OGESMS sample i.s obtained from the same stack sample probe as the RAGEMS.From the exi.t of the stack at elevation 257', the sample line runs east approximately 20'nd then vertically approximately 8'o the OGESMS skid.In the OGESMS, sample flows thru a particulate/iodi.ne cartridge housing and four noble gas scintillation detectors (i.e., 07 and 08 low range beta detectors and RN-03A and RN-03B high range gamma detectors)

.From OGESMS, the stack sample flows back into the stack at approximately elevation 257'.All OGESMS detector outputs are monitored and recorded remotely in the Main Control Room.Alarming capabilities are provided to alert Operators of high release rate conditions prior to exceeding Technical Specification 3.6.15.b (1)a dose rate limits.Stack particulate and iodine samples are retrieved manually from the OGESMS and analyzed in the laboratory using gamma spectroscopy at frequenciea and LLDs specified in Table 4.6.15-2 of the Technical Speci.ficationa.

3'.5.4~~~Sampling Frequency/Sample Analysis Regardless of which stack monitoring subsystem is utilized, radioactive gaseous wastes shall be sampled and analyzed in accordance with the sampling and analysis program specified in Technical Specification Table 4.6.15-2.Particulate samples are saved and analyzed for principal gamma emitters, gross alpha, Fe-55, Sr-89, Sr-90 at monthly intervals minimally.

The latter three analyses are performed off-site from a composite sample.Sample analysis frequencies are increased ,during elevated release rate conditions, following startup, shutdown and in con)unction with each drywell purge.Consistent with Technical Specification Table 4.6.15-2, stack effluent tri.tium is sampled monthly, during each drywell purge, and weekly when fuel is off loaded until stable release rates are demonstrated.

Samples are analyzed off-site.3,1~5.5 Line loss correction factors are applied to all particulate and iodine~results.Correction factors of 2.0 and 1.5 are used for data obtained from RAGEMS and OGESMS respectively.

These correction factors are based on empirical data from sampling conducted at NMP-1 in 1985 (memo from J.Blasiak to RAGEMS File, 1/6/86,"Stack Sample Repreaentativeness Study: RAGEMS versus In-Stack Auxiliary Probe Samples").I-133 Estimates Monthly, the stack effluent shall be sampled for iodines over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and the I-135/I-131 and the I-133/I-131 ratios calculated.

These ratios shall be used to calculate I-133, I-135 release for longer acquisition samples collected during the month.004152LL Unit 1 ODCM Revision 13 December 1993 p 4 64.<<I"<<I l<<'t<<1 I'4 4 3~1~5~5 F 1.5.6 I-133 Estimates (Cont'd)Additionally, the I-135/I-131 and I-133/I-131 ratios should also be determined after a significant change in the ratio is suspected (eg, plant stadia changes from prolonged shutdown to power operation or fuel damage has occurred).

Gaseous Radwaste Treatment System Operation Technical Specification 3.6.16.b requires that the gaseous radwaste treatment system shall be operable and shall be used to reduce radioactive materials in gaseous waste prior to their discharge as necessary to meet the requirements of Technical Specification 3.6.15.b.To ensure Technical Specification 3.6.15.b limits are not exceeded, and to confirm proper radwaste treatment system operation as applicable, cumulative dose contributions for the current calendar quarter and current calendar year shall be determined monthly in accordance with section 3.2 of this manual.Initial dose calculations shall incorporate the following assumptions with regard to release rates of non-gamma emitting radionuclides subsequently analyzed off-site: a)H-3 release rate b)Sr-89 release rate c)Sr-90 release rate d)Fe-55'release"rate 5 4 pCi/sec 5 4 x Cs-137 release rate 5 0.5 x Cs-137 release rate S 1 x Co-60 release rate Assumed release rates represent conservative estimates derived from analysis of historical data from effluent releases and process waste streams (See NMP 34023, C.Ware to J.Blasiak, April 29, 1988,"Dose Estimates for Beta-Emitting Isotopes").Following receipt of off-site H-3i Sr-89, Sr-90, Fe-55 analysis information, dose estimates shall be revised using actual radionuclide concentrations.

Dose and Dose Rate Determinations In accordance with specifications 4.6.15.b.(1), 4.6.15.b.(2), and 4.6.15.b.(3) dose and dose rate determinations will be made monthly 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.Average meteorological data (ie, maximum five year annual average X/Q and D/Q values in the case of elevated releases or 1985 annual average X/Q and D/Q values, in the case of ground level releases)shall be utilized for dose and dose rate calculations.

Where average meteorological data is assumed, dose and dose rates due to noble gases at locations beyond the site boundary will be lower than equivalent site boundary dose and dose rates.Therefore, under these conditions, calculations 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.004152LL 15 Unit 1 ODOM Revision 13 December 1993 4 I~I 8~4 t I 3~2 Dose and Dose Rate Determinations (Cont'd)Emergency condenser vent release contributions to the monthly dose and dose rate determinations will be considered only when the emergency condenser return isolation valves have been opened for reactor cooldown or if Emergency Condenser tube leaks develop with or without the system's return isolation valve opened.Without tube leakage or opening of the return isolation valves, releases from this system are negligible and the corresponding dose contributions do not have to be included.When releases from the emergency condenser have occurred, dose rate and dose determinations shall be performed using methodology in 3.2.1 and 3.2.2.Furthermore, environmental sampling may also be initiated to refine any actual contribution to doses.See Section 3.4.Critical organ doses and dose rates may be conservatively calculated by assuming the existence of a maximum individual.

This individual is a composite of the highest dose factor of each age group, for each organ and total body, and each nuclide.It is assumed that all pathways are applicable and the highest X/g and/or D/Q value for actual pathways as noted in Table 3-1 are in effect.The maximum individual's dose 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.The pathways include grass-(cow and goat)-milk, grass-cow-meat, vegetation, ground plane and inhalation.

To comply with Technical Specifications we will calculate the maximum individual dose rate at the site boundary and beyond at the critical residence.

~~3.2~1 If dose or dose rates calculated, using the assumptions noted above, reach Technical Specification limits, actual pathways will be evaluated, and dose/dose rates shall be calculated at separate critical receptor locations and compared with applicable limits.Dose Rate Dose rates will be calculated monthly, at a minimum, or when the Hi-Hi stack monitor alarm setpoint is reached, to demonstrate that dose rates resulting from the release of noble gases, tritium, iodines, and particulates with half lives greater than 8 days are within the limits specified in 10CFR.20.These limits are: Noble Gases Whole Body Dose Rate: 500 mrem/yr Skin Dose Rate: 3000 mrem/yr Tritium Iodinee and Particulates Organ Dose Rate: '500 mrem/yr 3.2.F 1 Noble Gases The following noble gas dose rate equation includes the contribution from the stack (s)elevated release and the emergency condenser vent (v)ground level release when applicable (See section 3.2).To ensure that the site noble gas dose rate limits are not exceeded, the following procedural actions are taken if the offsite dose rates from Unit 1 exceed 10%of the limits: 1)Notify the Unit 1 SSS (Station Shift Supervisor) and Unit 1 Supervisor Chemistry.

004152LL 16 Unit 1 ODOM Revision 13 December 1993

3.2.1.1 Noble Gases (Cont'd)2)Notify the Unit 2 SSS and Unit 2 Supervisor Chemistry and request the Unit 2 contribution to offsite dose.3)Notify the SSS of the James A.Fitzpatrick Nuclear Plant and request the Fitzpatrick contribution to offsite dose.4)Increase the frequency of performing noble gas dose calculations, if necessary, to ensure Site (Nine Mile Point Units 1 and 2 and Fitzpatrick) limits are not exceeded.Additionally, alarm setpoints are set at 50%of the dose rate limit to ensure that site limits are not exceeded.This alarm setpoint is ad)usted if the noble gas dose rate from Unit 1 is greater than 10%of the limit.For total body dose rates (mrem/sec):

DR, (mrem/sec)

=3.17E-8E,[(V,+(SF)g(X/Q),)Q

+(SF)g (X/Q)Q)For skin dose rates (mrem/sec):

DR+>(mrem/sec)=

3.17E-SE,[(L,(X/Q),+1.11(SF)(B,'

g(X/Q),))Q.

+..~(L)+1~11(SF)g)(X/Q)Q~]Where: DR DR+p V, total body gamma dose rate (mrem/sec).

skin dose rate from gamma and beta radiation (mrem/sec)

.the constant accounting for the gamma whole body dose rate from stack radiation for an elevated finite plume releases for each identified noble gas nuclide, i.Listed on Table 3-2 in mrem/yr per pCi/sec.the constant accounting for the gamma whole body dose rate from immersion in the semi-infinite cloud for each identified noble pas nuclide, i.Listed in Table 3-3 in mrem/yr per pCi/m (from Reg.Guide 1.109)SF X/Q the release rate of isotope i from the stack(s)or vent(v);(pCi/sec)structural shielding factor.the relative plume concentration (in units of sec/m~)at the land sector site boundary or beyond.Average meteorological data (Table 3-1)is used."Elevated" X/Q values are used for stack releases (s=stack)g"Ground" X/Q values are used for Emergency Condenser Vent releases (v=vent).L)the constant accounting for the beta skin dose rate from immersion in the semi-infinite cloud for each identified noble gas nuclide, i.Listed in Table 3-3 in mrem/yr per pCi/m~(from Reg.Guide 1.109)B, the constant accounting for the air gamma radiation from the elevated Finite plume resulting from stack releases for each identified noble gas nuclide, i.Listed in Table 3-2 in mrad/yr per pCi/sec.004152LL 17 Unit 1 ODCM Revision 13 December 1993 J tq).}

3.2.1.1 Noble Oases (Cont'd)the constant accounting for the gamma air dose rate from immersion in the semi-infinite cloud for each identified"noble gas nuclide, i.Listed in, Table 3-3 in mrem/yr per pCi/m'from Reg.Guide 1.109)See Appendix B for derivation of B, and V<.1 3.2.1.2 Tritium, Zodines and Particulates To ensure that the 1500 mrem/year site dose rate limit is not exceeded, offsite dose rates for tritium, iodine and particulates with half lives greater than 8 days shall be calculated monthly and when release rates (Q)exceed 0.34 pCi/sec using the following equation.D~(mrem/sec)

=3.17E-SZj[Z,~[W, Q+WQ])Where: Wj Total dose rate to each organ k of an individual in age group a (mrem/sec).

dispersion parameter either X/Q (sec/m')or D/Q (1/m~)depending on pathway and receptor location assumed.Average meteorological data is used (Table 3-1)."Elevated" Wj values are used for stack releases (s~stack);"Ground" W>values are used for Emergency Condenser Vent releases (v=vent).the release rate of isotope i, from the stack (s)or vent(v);(pCi/sec).

the dose factor for each isotope i, pathway j, age group a, and organ k (Table 3-4, through 3-22'-mrem/yr per pCi/sec for all pathways except inhalation, mrem/yr per pCi/m'.The R values contained in Tables 3-4 through 3-22 were calculated using the methodology defined in NUREG-0133 and parameters from Regulatory Guide 1.109, Revision 1;as presented in Appendix C.3.17E-S~the inverse of the number of seconds in a year.When the release rate exceeds 0.34 pCi/sec, the dose rate assessment shall also include JAF and NMP-2 contribution.

The use of the 0.34 pCi/sec release rate threshold to perform dose rate calculations is justified as follows: (a)The 1500 mrem/yr organ dose rate limit corresponds to a minimum release rate limit of 0.34 pCi/sec calculated using the equation: 1500~(Q, pCi/sec)x (RWj)Where: 1500 (RgWj)site boundary dose rate limit (mrem/year).

the maximum curie-to-dose conversion factor equal to 4.45E3 mrem-sec/pCi-yr for Sr-90, child bone at the critical residence receptor location beyond the site boundary.004152LL 18 Unit 1 ODCM Revision 13 December 1993 1 Ci>>y 3.2.1.2 Tritium, Zodines and Particulates (Cont'd)(b)The use of 0.34 pCi/sec release rate threshold and the 4.45E3 mrem-sec/pCi-yr curie-to-dose conversion factor is conservative since curie-to-dose conversion factors for other isotopes likely to be present are significantly lower.Zn addition, if the organ dose rate exceeds 5%of the annual limit, the following procedural actions will be taken: 1)Notify the Unit 1 SSS (Station Shift Supervisor) and Unit 1 Supervisor Chemistry.

2)Notify the Unit 2 SSS and Unit 2 Supervisor Chemistry and request the Unit 2 contribution to offsite dose.3)Notify the SSS of the James A.Fitzpatrick contribution to offsite dose.4)Zncrease the frequency of performing dose calculations if necessary to ensure site (Nine Mile Point Units 1 and 2 and Fitzpatrick) limits are not exceeded.3~2~2 Dose Calculations will be performed monthly at a minimum, to demonstrate that doses resulting from the release of noble gases, tritium, iodines, and particulates with half lives greater than 8 days are within the limits specified in 10 CFR 50, Appendix Z.These limits are: Noble Gases 5 mR gamma/calendar quarter 10 mrad beta/calendar quarter 10 mR gamma/calendar year 20 mrad beta/calendar year Tritium Zodines and Particulates 7.5 mrem to any organ/calendar quarter 15 mrem to any organ/calendar year 3.2.2.1 Noble Gas Air Dose The following Noble Gas air dose equation includes contributions from the stack (s)elevated release and the emergency condenser vent (v)ground level release when applicable (see section 3.2): For gamma radiation'mrad):

Dy(mrad)=3.17E-8Z<(M;(X/Q)Q+(Bi

+g(X/Q),)Q]

~t For beta radiation (mrad): Du(mrad)=3~17E-8EiN~[(X/Q)>>

Q~+(X/Q), Q,)~Where: D gamma air dose (mrad).Dp beta air dose (mrad).Note that the units for the gamma air dose are in mrad compared to the units for the limits are in mR.The NRC recognizes that 1 mR=1 mrad, for gamma radiation.

004152LL 19 Unit 1 ODCM Revision 13 December 1993 1 t~J+pC'1~')tl e 3.2.2.1 Noble Gas Air Dose (Cont'd)B)N)the constant accounting for the air gamma radiation from the elevated finite plume resulting from stack releases for each identified.

noble gas nuclide, i.--Listed in Table 3-2 in mrad/yr per pCi/sec.The constant accounting for the air beta dose from immersion in the semi.-infinite cloud for each identified noble gas nuclide, i.Listed on Table 3-3 in mrad/yr per pCi/m'from Reg.Guide 1.109).Q g Q=the release rate of isotope i, f rom the stack (s)or vent (v)i (pCi/sec).

3.17E-8 the inverse of the number of seconds in a year.the constant accounting for the air gamma dose from immersion in the semi-infinite cloud for each identified noble gas nuclide, i.Listed on Table 3-3 in mrad/yr per pCi/m~(from Reg.Guide 1.109).total time during release periodi sec.342 All other parameters are as defined in section 3.'2.1.1.Tritium, Zodines and Particulates To ensure that the 15 mrem/yr facility dose limit is not exceeded, offsite doses for tritium, iodines, and particulates with half lives greater than 8 days shall be calculated monthly using the following equations D~(mrem)=3.17E-SZ>[Z,~[W, Q+WQ])~t Where: WJ Q i'otal dose to each organ k of an individual in age group a(mrem).dispersion parameter either X/Q (sec/m')or D/Q (1/m~)depending on pathway and receptor location assumed.Average meteorological data is used (Table 3-1)."Elevated" W>values are used for stack releases (s=stack)p"Ground" W>values are used for Emergency Condenser Vent releases (v~vent).the release rate of isotope i from stack(s)or vent (v)i (pCi/sec).

3.17E-S the dose factor for each isotope i, pathway j, age group a, and organ k (Tables 3-4, through 3-22;m~-mrem/yr per pCi/sec).R values contained in Tables 3-4 through 3-22 were calculated using the methodology defined in NUREG-0133 and parameters from Regulatory Guide 1.109, Revision 1;as presented in Appendix C.the inverse of the number of seconds in a year.total time during the release period, sec.004152LL 20 Unit 1 ODCM Revision 13 December 1993 4~a 4 J jan(\t t I~R II w ve 3.2.2.3 Accumulating Doses Doses will be calculated monthly, at a minimum, for gamma air, beta air, and the critical organ for each age group.Dose estimates.

will, also" be calculated monthly prior to receipt of any offsite-analysis data i.e., strontium, tritium, and iron-55.Results will be summed for each calendar quarter and year.The critical doses are based on the following!

3~3 noble gas plume air dose-direct radiation from ground plane deposition inhalation dose cow milk ingestion dose-goat milk ingestion dose cow meat ingestion dose-vegetation (food crops)ingestion 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.

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 elevated noble gas releases the critical receptor is the site boundary.When 1985 average annual X/Q values are used for ground level noble gas releases, the critical receptor is the maximum X/Q land sector site boundary interface.

For tritium, iodines, and particulates with half lives greater than eight days, the critical'athways are grass-(cow and goat)-milk, grass-cow meat, vegetation, inhalation and direct radiation (ground plane)as a result of ground deposition.

The grass-(cow and goat)-milk, and grass-cow-meat pathways will be based on the greatest D/Q 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)pathway is based on the greatest D/Q garden location from which samples are taken.This location may also be modified as a result of vegetation sampling surveys.The inhalation and ground plane dose pathways will be calculated at the critical residence.

Because the Technical Specifications state to calculate"at the site boundary and beyond", the doses and/or dose rates must be calculated for a maximum individual who is exposed to all pathways at the site boundary and at the critical residence.

The maximum individual is a composite of the highest dose factor of each age group, for each organ and total body, and each nuclide.Since the critical residence location has the greatest occupancy time, the resultant dose at the residence including all pathways is limiting.However, due to the Technical Specification wording, the inhalation and ground plane dose at the site boundary along with all other pathways, will be calculated assuming a continuous occupancy time.004152LL 21 Unit 1 ODCM Revision 13 December 1993 4~'I hf 14'4 C E'r gyes 4 V 3'Critical Receptors (Cont'd)In lieu of correcting land site boundary ground plane and inhalation dose factors for occupancy time, a Technical Specificat3;on change will be.submitted to change the requirement from calculating"at the site boundary and beyond" to"at the site boundary or beyond".Unit 1 will then calculate at the critical residence since this should be the limiting dose.Until this change is effective, the dose and/or dose rate calculations for tritium, iodines, and particulates with half lives greater than 8 days will conservatively assume that the ground plane and inhalation pathway critical receptors are at the site boundary, i.e., X/Q and D/Q, respectively, are calculated at the site boundary.3.4 Refinement of Offsite Doses Resulting from Emergency Condenser Vent Releases The doses resulting from the operation of the emergency condensers and calculated in accordance with 3.2.2 may be refined using data from actual environmental samples.Ground deposition samples will be obtained from an area or areas of maximum projected deposition.

These areas are anticipated to be at or near the site boundary and near projected plume centerline.

Using the methodology found in Regulatory Guide 1.109, the dose will be calculated to the maximum exposed individual.

This dose will then be compared to the dose calculated in accordance with 3.2.2.The comparison will result in an adjustment factor of less than or greater than one which will be used to adjust the other doses from other pathways.Other environmental samples may also be collected and the resultant calculated doses to the maximum exposed individual compared to the dose calculated per 3.2.2.Other environmental sample media may include milk, vegetation (such as garden broadleaf vegetables), etc.The adjustment factors from these pathways may be applied to the doses calculated per 3.2.2 on a pathway by pathway basis or several pathway adjustment factors may be averaged and used to adjust calculated doses.Doses calculated.

from actual environmental sample media will be based on the methodology presented in Regulatory Guide 1.109.The regulatory guide equations may be slightly modified to account for short intervals of time (less than one year)or modified for simplicity purposes by deleting decay factors.Deletion of decay factors would yield more conservative results.004152LL 22 Unit 1 ODCM Revision 13 December 1993 I'V sv'A p.~'/if f e L'4a.~" g'l EP A'.L S~'Q""t'4'I~>

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, generation 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 that when the calculated doses associated with the effluent releases exceed twice the applicable quarter or annual limits, the licensee shall evaluate the calendar year doses and, if required, submit a Special Report to the NRC and limit subsequent releases such that the dose commitment to a real individual from all uranium fuel cycle sources is limited to 25 mrem to the total body or any organ (except the thyroid, which is limited to 75 mrem).This report is to demonstrate that radiation exposures to all real individuals from all uranium fuel cycle sources (including all liquid and gaseous effluent pathways and direct radiation) are less than the limits in 40 CFR Part 190.If releases that result in doses exceeding the 40 CFR 190 limits have occurred, then a variance from the NRC to permit such releases will be requested and if possible, action will be taken to reduce subsequent releases.The report to the NRC shall contain: 1)Identification of all uranium fuel cycle facilities or operations within 5 miles of the nuclear power reactor units at the site that contribute to the annual dose of the maximum exposed member of the public.2)Identification of the maximum exposed member of the public and a determination of the total annual dose to this person from existing pathways and sources of radioactive effluents and direct radiation.

The total body and organ doses resulting from radioactive material in liquid effluents from Nine Mile Point Unit 1 will be summed with the maximum doses resulting from the releases of noble gases, radioiodines, and particulates for the other calendar quarters (as applicable) and from the calendar quarter in which twice the limit was exceeded.The direct dose components will'be determined by either calculation or actual measurement.

Actual measurements will utilize environmental TLD dosimetry.

Calculated measurements will utilize engineering calculations to determine a projected direct dose component.

In the event calculations are used, the methodology will be detailed as required in Section 6.9.1.e of the Technical Specifications.

004152LL 23 Unit 1 ODCM Revision 13 December 1993 4L 41 J 4L~-~Hw, Ai*~'t~>" e P 1 s4e.

4.0 40 CFR 190 REQUIREMENTS (Cont'd)The doses from Nine Mile Point Unit 1 will be added to the doses to the maximum exposed individual that are contributed from other uranium fuel cycle operations within 5 miles of the site.Other uranium fuel cycle facilities within 5 miles of the Site include Nine Mile Point Nuclear Station Unit 2 and the James A.Fitzpatrick Nuclear Power Plant.Doses from other facilities will be calculated in accordance with each facilities'DCM.

For the purpose of calculating doses, the results of the Radiological Environmental Monitoring Program may be included for providing more refined estimates of doses to a real maximum exposed individual.

Estimated doses, as calculated from station effluents, may be replaced by doses calculated from actual environmental sample results.Reports will include all significant details of the dose determination if radiological sampling and analyses are used to determine if the dose limits of 40CFR190 are exceeded.4'Evaluation of Doses From Liquid Effluents For the evaluation of doses to real members of the public from liquid effluents, the fish consumption and shoreline sediment ground dose will be considered.

Since the doses from other aquatic pathways are insignificant, fish consumption and shoreline sediment are the only two pathways that will be considered.

The dose associated with fish consumption may be calculated using effluent data and Regulatory Guide 1.109 methodology or by calculating a dose to man based on actual fish sample analysis data.Because of the nature of the receptor location and the extensive fishing in the area, the critical individual may be a teenager or an adult.The dose associated with shoreline sediment is based on the assumption that the shoreline would be utilized as a recreational area.This dose may be derived from liquid effluent data and Regulatory Guide 1.109 methodology or from actual shoreline sediment sample analysis data.Equations used to evaluate doses from actual fish and shoreline sediment samples are based on Regulatory Guide 1.109 methodology.

Because of the sample medium type and the half-lives of the radionuclides historically observed, the decay corrected portions of the equations are deleted.This does not reduce the conservatism of the calculated doses but increases the simplicity from an evaluation point of view.Table 3-23 presents the parameters used for calculating doses from liquid effluents.

The dose from fish sample media is calculated as: Zl[Cu (U)(D~)f](1E+3)Where: The total annual dose to organ j, of an individual of age group a, from nuclide i, via fish pathway p, in mrem per year.The concentration of radionuclide i in fish samples in pCi/gram.U~The consumption rate of fish in kg/yr.1E+3~Grams per kilogram.004152LL 24 Unit 1 ODCM Revision 13 December 1993 I 4 e>'L HN ,~g'4 I~i+sSV~W+~I~.,

4.1 Evaluation

of Doses From Liquid Effluents (Cont'd)(D~J.~The ingestion dose factor for age group a, nuclide i, fish pathway p, and organ j, (Reg.Guide 1.109, Table E-11)(mrem/pCi).

~The fractional portion of the year over which the dose is applicable.

The dose from shoreline sediment sample media is calculated as: Z<[Cl, (U)(4E+4)(0.3)(D~)f)Where: Cg=The total annual dose to organ j, of an individual of age group a, from nuclide i, via the sediment pathway p, in mrem per year.~The concentration of radionuclide i in shoreline sediment in pCi/gram.'U~The usage factor, (hr/yr)(Reg.Guide 1.109).4E+4~The product of the assumed density of shoreline sediment (40 kilogram per square meter to a depth of 2.5 cm)times the number of grams per kilogram.0.3~The shore width factor for a lake.D~~The dose factor for age group a, nuclide i, sediment pathway s, and organ j.(Rep.Guide 1.109, Table E-6)(mrem/hr per pCi/m).~The fractional portion of the year over which the dose is applicable.

4'Evaluation of Doses Prom Gaseous Effluents For the evaluation of doses to real members of the public from gaseous effluents, the pathways contained in section 3.2.2.3 of the ODCM will be considered.

These include the deposition, inhalation cows milk, goats milk, meat, and food products (vegetation).

However, any updated field data may be utilized that concerns locations of real individuals, real time meteorological data, location of critical receptors, etc.Data from the most recent census and sample location surveys should be utilized.Doses may also be calculated from actual environmental sample media, as available.

Environmental sample media data such as TLD, air sample, milk sample and vegetable (food crop)sample data may be utilized in lieu of effluent calculational data.Doses to member of the public from the pathways contained in ODCM section 3.2.2.3 as a result of gaseous effluents will be calculated using the dose factors of Regulatory Guide 1.109 or the methodology of the ODCM, as applicable.

Doses calculated from environmental sample media will be based on the methodologies found in Regulatory Guide 1.109.004152LL 25 Unit 1 ODCM Revision 13 December 1993 4A V~~~V I.V P~V r, kt, VVL I 4'V 4'Evaluation of Doses Prom Direct Radiation The dose contribution as a result of direct radiation shall be considered when evaluating whether the dose limitations of 40 CFR 190 have been exceeded.4.4 Direct radiation doses as a result of the reactor, turbine and radwaste buildings and outside radioactive storage"tanks (as applicable) may be evaluated by engineering calculations or by evaluating environmental TLD results at critical receptor locations, site boundary or other special interest locations.

For the evaluation of direct radiation doses utilizing environmental TLDs, the critical receptor in question, such as the critical residence, etc., will be compared to the control locations.

The comparison involves the difference in environmental TLD results between the receptor location and the average control location result.Doses to Members of.the Public Within the Site Boundary The Semi.-Annual Radioactive Effluent Release Report shall 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 Center for the purpose of observing the educational displays or for picnicking and associated activities.

Fishing is a major recreational activity in the area and on the Site as a result of the salmonoid and trout populations in Lake Ontario.Fishermen have been observed fishing at the shoreline near the Energy Center from April through December in all weather conditions.

Thus, fishing is the ma)or activity performed by members of the public within the site boundary.Based on the nature of the fishermen and undocumented observations, it is conservatively assumed that the maximum exposed individual spends an average of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per week fishing from the shoreline at a location between the Energy Center and the Unit 1 facility.This estimate is considered conservative but not necessarily excessive and accounts for occasions where individuals may fish more on weekends or on a few days in March of the year.The pathways considered for the evaluation include the inhalation pathway, the ground dose pathway with the resultant whole body and skin dose and the direct radiation dose pathway with the associated whole body dose.The direct radiation dose pathway, in actuality, includes several pathways.These include: the direct radiation gamma dose to an individual from an overhead plume, a gamma submersion plume dose (as applicable), possible direct radiation dose from the facility and a giound plane dose (deposition).

Because the location is in close proximity to the site, any beta plume submersion dose is felt to be insignificant.

Other pathways, such as the ingestion pathway, are not applicable since these doses are included under calculations for doses to members of the public outside of the site boundary.In addition, pathways associated with water related recreational activities, other than fishing, are not applicable here.These include swimming, boating and wading which are prohibited at the facility.004152LL 26 Unit 1 ODCM Revision 13 December 1993

'~!t ll P

4.4 Doses

to Members of the Public Within the Site Boundary (Cont'd)The.inhalatien pathway is evaluated by identifying the applicable radionuclides (radioiodine, tritium and particulates) in the effluent for the appropriate time period.The radionuclide concentrations are then 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.Table 3-23 presents the reference for the parameters used in the following equation.NOTEt Dp The following equation is adapted from equations C-3 and C-4 of Regulatory Guide 1.109.Since many of the factors are in units of pCi/m', m~/sec., etc., and since the radionuclide decay expressions have been deleted because of the short distance to the receptor location, the equation presented here is not identical to the Regulatory Guide equations.

Zi[(Ci)F (X/Q)(DFA)-(BR)at]Where:.Dp C, The maximum dose from all nuclides to the organ j and age group (a)in mrem/yr.The average concentration in the stack release of nuclide i for the period in pCi/m~.Unit 1 average stack flowrate in m~/sec.X/Q The plume dispersion parameter for a location approximately 0.50 miles west of NMP-1;the plume dispersion parameter is 8.9E-06 (stack)and was obtained from the C.T.Main five year average annual X/Q tables.The stack (elevated)

X/Q is conservative when based on 0.50 miles because of the close proximity of the stack and the receptor location.(DFA)U, (BR), The dose factor for nuclide i, organ j, and age group a in mrem per pCi (Reg.Guide 1.109, Table E-7)~Annual air intake for individuals in age group a in m~per year (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 (in years).004152LL 27 Unit 1 ODCM Revision 13 December 1993 F<4

4.4 Doses

to Members of the Public Within the Site Boundary (Cont'd)The ground dose pathway (deposition) will be evaluated by obtaining at least one soil or shoreline sediment sample in the area where fishing occurs.The dose will then be calculated using the sample results, the time period in question, and the methodology based on Regulatory Guide 1.109 as presented in Section 4.1.The resultant dose may be adjusted for a background dose by subtracting the applicable off-site control soil or shoreline sediment sample radionuclide activities.

In the event it is noted that fishing is not performed from the shoreline, but is instead performed in the water (i.e., the use of waders), then the ground dose pathway (deposition) may not be evaluated.

1 The direct radiation gamma dose pathway includes any gamma doses from an overhead plume, potential submersion in the plume, possible direct radiation from the facility and ground plane dose (deposition).

This general pathway will be evaluated by average environmental TLD readings.At least two environmental TLDs will be utilized at one location in the approximate area~here fishing occurs.The TLDs will be placed in the field on approximately the beginning of a calendar quarter and removed on approximately the end of the calendar quarter.For the purposes of this evaluation, TLD data from quarters 2, 3, and 4 will be utilized.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 fishing location TLD value.The applicable quarterly control TLD values will be utilized after adjusting for the appropriate time period (as applicable).

In the event of loss or theft of the TLDs, results from a TLD or TLDs in a nearby area may be utilized.004152LL 28 Unit 1 ODCM Revision 13 December 1993

5~0 ENVIRONMENTAL MONITORING PROGRAM 5.1-Sampling Stations The current sampling locations are specified in Table 5-1 and Figures 5.1-1, 5.1-2.The meteorological tower is shown in Figure 5.1-1.The location is shown as TLD location 17.The Radiological Environmental Monitoring Program is a joint effort between the Niagara Mohawk Power Corporation and the New York Power Authority, the owners and operators of the Nine Mile Point Unit 1 and the James A.FitzPatrick Nuclear Power Plant, respectively.

Sampling locations are chosen on the basis of historical average dispersion or deposition parameters from both units.The environmental sampling location coordinates shown on Table 5-1 are based on the NMP-2 reactor centerline.

The average dispersion and deposition parameters have been calculated for a 5 year period, 1978 through 1982.These dispersion calculations are attached as Appendix E.The calculated dispersion or deposition parameters will be compared to the results of the annual land use census.If it is determined that a milk sampling location exists at a location that yields a significantly higher (e.g.50%)calculated D/Q rate, the new milk sampling location will be added to the monitoring program within 30 days'f a new location is added, the old location that yields the lowest calculated D/Q may be dropped from the program after October 31 of that year.Interlaboratory Comparison Program Analyses shall be performed on samples containing known quantities of radioactive materials that are supplied as part of a Commission approved or sponsored Interlaboratory Comparison Program, such as the 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 crosscheck samples are available.

An attempt will be made to obtain a QC sample to program sample ratio of 5%or better.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 followings

-gross beta in air particulate filters-gamma emitters in air particulate filters-gamma emitters in milk-gamma emitters in water-tritium in water-I-131 in water 004152LL 29 Unit 1 ODCM Revision 13 December 1993 4"4 4'+I 8'i.C E'1 5'Capabilities for Thermoluni.nescent Dosimeters Used for Envi.ronmental Measurements Required detection capabi.lities 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.TLDs are defined as phosphors packaged for field use.In regard to the detection capabilities for thermolumi.nescent dosimeters, only one determination is required to evaluate the above capabi.lities per type of TLD.Furthermore, the above capabilities may be determined by the vendor who supplies the TLDs.Required detection capabilities arq as follows: 5.3.1 Uniformity shall be determined by giving TLDs from the same batch an exposure equal to that resulti.ng from an exposure rate of 10 mR/hr during the field cycle.The responses obtained shall have a relative standard deviation of less than 7.5%.A total of at least 5 TLDs shall be evaluated.

5.3'Reproducibility shall be determined by giving TLDs repeated exposures equal to that resulting from an exposure rate of 10 uR/hr during the field cycle.The average of the relative standard deviations of the responses shall be less than 3.0%.A total of at least 4 TLDs shall be evaluated.

5~3.3 Dependence of exposure interpretation on the length of a field cycle shall be exami.ned by placing TLDs for a period equal to at least a field.cycle and a period equal to half the same field cycle i.n an area where the exposure rate is known to be constant.This test shall be conducted under approximate average winter temperatures and approximate average summer temperatures.

For these tests, the ratio of the response obtained in the field cycle to twice that obtained for half the field cycle shall not be less than 0.85.At least 6 TLDs shall be evaluated.

5.3.4 Energy

dependence shall be evaluated by the response of TLDs to photons for several energies between approximately 30 keV and 3 MeV.The response shall not differ from that obtained with the calibration source by more than 25%for photons with energi.es greater than 80 keV and shall not be enhanced by more than a factor of two for photons-with energies less than 80 keV.A total of at least 8 TLDs shall be evaluated.

5,3.5 5.3.6 The directional dependence of the TLD response shall be determined by comparing the response of the TLD exposed in the routine orientation with respect to the calibration source with the response obtained for different orientations.

To accomplish this, the TLD shall be rotated through at least two perpendicular planes.The response averaged over all directions shall not differ from the response obtained in the standard calibration position by more than 10%.A total of at least 4 TLDs shall be evaluated.

Light dependence shall be determined by placing TLDs in the field for a period equal to the field cycle under the four conditions found in ANSI N545, section 4.3.6.The results obtained for the unwrapped TLDs shall not differ from those obtained for the TLDs wrapped in aluminum foil by more than 10%.'A total of at least 4 TLDs shall be evaluated for each of the four conditions.

004152LL 30 Unit 1 ODCM Revision 13 December 1993 L a l' Moisture dependence shall be determined by placing TLDs (that is, the phosphors packaged for field use)for a period equal to the field cycle in an~'rea where the exposure rate is known to be constant.The TLDs shall be exposed under two conditions:

(1)packaged in a thin, sealed plastic bag, and (2)packaged in a thin, sealed plastic bag with sufficient water to yield observable moisture throughout the field cycle.The TLD or phosphor, as appropriate, shall be dried before readout.The response of the TLD exposed in the plastic bag containing water shall not differ from that exposed in the regular plastic bag by more than 10%.A total of at least 4 TLDs shall be evaluated for each condition.

5',8 Self irradiation shall be determined by placing TLDs for a period equal to the field cycle in an area where the exposure rate is less than 10 uR/hr and the exposure during the field cycle is known.If necessary, corrections shall be applied for the dependence of exposure interpretation on the length of the field cycle (ANSI N545, section 4.3.3).The average exposure inferred from the responses of the TLDs shall not differ from the known exposure by more than an exposure equal to that resulting from an exposure rate of 10 uR/hr during the field cycle.A total of at least 3 TLDs shall be evaluated.

004152LL 31 Unit 1 ODCM Revision 13 December 1993 V4 it TABLE l-l Average Energy Per Disintegration ISOTOPE 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 1.294 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)E~av dis<" 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~Ref (3)(2)(2)(2)(3)(4)ORNL-4923, Radioactive Atoms-Su lement I, M.S.Martin, November 1973.NEDO-12037,"Summary of Gamma and Beta Emitters and Intensity Data";M.E.Meek, R.S.Gilbert, January 1970.(The average energy was computed from the maximum energy using the ICRP II equation, not the 1/3 value assumption used in this reference).

NCRP Report No.58,"A Handbook of Radioactivity Measurements Procedures";

1978 The average energy includes conversion electrons.

004152LL 32 Unit 1 ODCM Revision 13 December 1993 t 4 1J<gs.h'I 0 NUCLIDE BONE LIVER Mn 56 Mo 99-2.40E-4 2.34E+1 Na 24 2.37 2.37 I 131 3.03E+1 3.54E+1 I 133 4.22 6.15 Ni 65 1.33E-3 1.51E-4 I 132 1.58E-4 3.21E-4 Cs 134 3.54E+2 6.60E+2 Cs 136 Cs 137 Ba 140 Ce 141 Nb 95 La 140 Ce 144 4.05E+1 1.19E+2 4.91E+2 5.75E+2 1.50E+2 1.50E-1 7.21E-2 4.40E-2 3.85E-2 1.59E-2 1.18E-2 4.67E-3 2.79 1.14 H3 2.90E-1 Cr 51 Cu 64-'.13E-1 Mn 54 1 87E+1 FE 55 1.31E+1 8.44 Fe 59 2 84E+1 4.96E+1 Co 58 3.34 Co 60 1 02E+1 Zn 65 1.72E+1.5.91E+1 Sr 89 2.32E+3 Sr 90 1.74E+4 Zr 95 1.91E-1 4.66E-2 5.23E-2 4.23 2.26 1.96E+1 8.34 2.40E+1 2'3E+1 6.66E+1 4.43E+3 3.30E-2 4.15E-5 4.57 2.37 2.37 1.91E-l 4.14 2 87E+1 5'2E-2 2.07E>>4 3.50E+1 2.37 1.57E+1 1.17E+4 4.17E+1 1.80 6.85E-S 1-12E+3 7.23 1.14E-4 1.50E-2 3.58E-4 6.67E+1 4.45E+1 4.07E+1 7.74 5.17E-3 9.18E-3 1.20E-3 1.57E-1 1.70E+2 4.75E+1 1.54E+2 3.57E-2 1.36E-2 1.14E-2 4.62E-1 TABLE 2-1 A VALUES-LIQUID*RADWASTE TANK INFANT mrem-ml hr-pCi T BODY THYROID KIDNEY 2.90E-1 2.90E-1 2 90E-1 1.29E-2 8.39E-3 1.83E-3 LUNG GI-TRACT 4.13 1.07 1.47E+1 2.37E+1 8.33 2.37 2.42E+1 5'OE+1 4.77E+1 2.17E+2 2.32E+1 2.18E-2 7.71 2'7 1.28 1.04 1.15E-2 2.60E-4 6.97E+1 1.79 9.71E+1 1.81 6.24E+1 1.80 9.23E-2 3.69E+1 2.27E+1 1.34E+1 5.48E+1 1.60E+2 2.90E-1 2.90E-1 1.63E-2 3.75E-1 2.32 6.86*Calculated in accordance with NUREG 0133, Section 4.3.1;and Regulatory Guide 1.109, Regulatory position C, Section 1.004152LL 33 Unit 1 ODCM Revision 13 December 1993 44 t 7A" y~Wml NUCLIDE BONE LIVER H3 4.39E-1 Cr 51 2.13E-2 2.13E>>2 Cu 64 2.51E-6 2.70 Mn 54 6.92 3.38E+3 Fe 55 9.21E+2 4.88E+2 Fe 59 1.30E+3 2.11E+3 Co 58 1.89 7.46E+1 Co 60 1.12E+2 3.28E+2 Zn 65 2.15E+4 5.73E+4 Sr 89 3.26E+4 1.10E-4 Sr 90 4.26E+5 Zr 95 1.70 1.33 Mn 56 1.65E-1 Mo 99 5.35E-3 9.57E+1 Na 24 1.52E+2 1.52E+2 I 131 2.09E+2 2.10E+2 I 133 3.39E+1 4.19E+1 Ni 65 I 132 Cs 134 2.67E-1 2.51E-2 6.13E-3 1.13E-2 3.68E+5 6.04E+5 Ce 144 5.00 1.81 Cs 136 3.52E+4 9.67E+4 Cs 137 5.15E+5 4.93E+5 Ba 140 3.61E+2 3.96E-l Ce 141 1.50E-1 1.07E-1 Nb 95 5.21E+2 2.03E+2 La 140 1.50E-1 5.93E-2 1.40 1.63 7'6E-1 2.30E-1 2.51E-6 6.52 9.06E+2 6.92 1.51E+2 1.05E+3 1.34 2.24E+2 1.89 9.53E+2 1.34 1.89 7.48E+2 1.12E+2 1.12E+2 3.56E+4 3.85 3.61E+4 9.32E+2 1.10E-4 1.10E-4 1.08E+5 1.32 3.73E-2 1.23 1.38 2.00E-1 2.37E+1 5.35E-3 2.04E+2 1.52E+2 1.52E+2 1.52E+2 1.19E+2 6.94E+4 3.45E+2 1.59E+1 7.78E+3 6.98E+1 1.47E-2 5.18E-3 5.22E-1 1.72E-2 1.27E+5 3.54E+1 1.87E+5 6.26E+4 6.21E-1 5.15E+4 7.28E+4 ,5.37E+1 1.61E+5 2.11E+1 7.96E-2 1.82E-1 6.99E-2 6.34E-2 8.24E-2 1.45E+2 6.39E-1 1.91E+2 2.68E-2.1.03E-2 1.03E-2 6.06E-1 3.58E-1 1.16 TABLE 2-2 A, VALUES-LIQUID*RADWASTE TANK CHILD mrem<<ml hr-pCi T BODY THYROID KIDNEY 4.39E-1 4.39E-l 4.39E-1 LUNG GI-TRACT 4.39E-l 4.39E-l 1.42 7.31E+1 2.51E-6 1.27E+2 6.92 2.84E+3 2.76E+2 9.05E+1 6.12E+2 2.19E+3 1.89 4.26E+2 1.12E+2 1.31E+3 3.85 1.01E+4 1~10E-4 1.26E+3 1.23 5.74E+3 1.08E+2 2.39E+1 5.35E-3 7.91E+1 1.52E+2 1.52E+2 5.60E-2.1.38E-4 1.87E+1 1.69E+1 3.08 1.32E-2 6.72E+4 3.29E+3 7.68E+3 3.40E+3 5.78E+4 3.14E+3 2.68E-1 1.83E+2 6.34E-2 5.40E+1 6.39E-1 3.75E+5 1.03E-2 1.36E+3 3.58E-1 3.80E+2*Calculated in accordance with NUREG 0133, Section 4.3.1;and Regulatory Guide 1.109, Regulatory position C, Section 1.004152LL 34 Unit 1 ODCM Revision 13 December 1993

\'5 s6':

NUCLIDE BONE LIVER H3 3.28E-1 Cr 51 1.02E-1 1.02E-1 Cu 64 1.20E-5 2.89 Mn 54 3.31E+1 4.34E+3 Fe 55 6.94E+2 4.92E+2 Fe 59 1.07E+3 2.49E+3 Co 58 9.03 9.82E+1 Co 60 5.36E+2 7.96E+2 Zn 65 2.10E+4 7.28E+4 Sr 89 2.44E+4 5.24E-4 Sr 90 4.66E+5 Zr 95 6.20 6.00 Mn 56 1.81E-1 Mo 99 2.56E-2 9.22E+1 Na 24 1.39E+2 1.39E+2 I 131 1.55E+2 2.17E+2 I 133 2.53E+1 4.29E+1 Ni 65 2.08E-1 2.66E-2 I 132 4.90E-2 1.28E-2 Cs 134 3.05E+5 7.18E+5 Cs 136 2.98E+4 1.17E+5 Cs 137 4.09E+5 5.44E+5 Ba 140 2.35E+2 4.10E-1 Ce 141 3.46E-1 3.32E-1 1.39 1.36 8.16E-1 3.84E-1 1.20E-5 7.32 8.87E+2 3.31E+1 1.32E+3 1.15E+2 9.64E+2 6.41 2.15E+2 9.03 6.41 9.03 1.12E+3 5.36E+2 5.36E+2 3.40E+4 1.84E+1 4 66E+4 6.98E+2 5.24E-4 5.24E-4 1.15E+5 5.97 3.22E-2 5.90 6.04 2.29E-1 1.76E+1 2.56E-2 2.11E+2 1.39E+2 1.39E+2 1.39E+2 1.16E+2 6.31E+4 3.73E+2 1.31E+1 5.99E+3 7.52E+1 1.21E-2 4.60E-3 4.32E-1 2.02E-2 3.33E+5 1.69E+2 2.28E+5 7.88E+4 2.97 6.38E+4 1.90E+5 2.57E+2 1.85E+5 1.55E+1 3.81E-1 4.79E-1 3.07E-1 3.04E-1 3.17E-1 TABLE 2-3~VALUES-LIQUID~RADWASTE TANK TEEN mrem-ml hr-pCi T BODY THYROID KIDNEY 3.28E-1 3.28E-1 3 28E-1 LUNG GI-TRACT 3.28E-1 3.28E-1 1.94 2.16E+2 1.20E-5 2.24E+2 3.31E+1 8'86E+3 3.12E+2 2.13E+2 7.89E+2 5'7E+3 9.03 1.24E+3 5.36E+2 3.93E+3 1.84E+1 3.08E+4 5.24E-4 2.90E+3 5.90 1.31E+4 2.28E+2 1.19E+1 2.56E-2 1.65E+2 1.39E+2 1.39E+2 2.68E-1 4.30E+1 6 60E-4 3.25E+1 1.44 5.59E-3 8.73E+4 9.10E+3 1.01E+4 9.44E+3 7.21E+4 7.99E+3 5.75E-1 3.63E+2 3.04E-1 8.16E+1 Nb 95 La 140 4.44E+2 2.48E+2 1.57E-1 1.02E-1 1.18E+2 3.06 2.40E+2 6.35E-2 4.94E-2 4.94E-2 3.06 1.05E+6 4.94E-2 3.05E+3 Ce 144 3.99 2.65 1.83 1.71 2.27 1.71 5.74E+2*Calculated in accordance with NUREG 0133, Section 4.3.1;and Regulatory Guide 1.109, Regulatory position C, Section 1.004152LL 35 Unit 1 ODCM Revision 13 December 1993 ee II N L I 5"4'e'i,W LIVER 4.45E-1 NUCLIDE BONE H3 Cr 51 CQ 64 Mn 54 5.94 2'5 4.38E+3 1.82E-2 1-82E-2 1.27 7.64E-1 2.93E-1 1.29 8.41E+2 5.94 6.94 1.31E+3 TABLE 2-4 A VALUES-LIQUID*RADWASTE TANK ADULT prem-ml hr-pCi T BODY THYROID KIDNEY 4.45E-1 4.45E-1 4.45E-1 LUNG GI-TRACT 1.67 5.94 3.14E+2 2.35E+2 1.34E+4 4.45E-1 4.45E-1 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Mn 56 Mo 99 Na 24 I 131 I 133 Ni 65 I 132 Cs 134 Cs 136 Cs 137 Ba 140 ce 141 Nb 95 La 140 Ce 144 6.64E+2 4.58E+2 1.03E+3 2.43E+3 l.62 9.15E+1 9.60E+1 2.57E+2 2.31E4 7.36E+4 2.25E+4 9.39E-S 5.60E+5 1.36 1.15E 1.73E-1 2.48 1.22 4.58E-3 8.70E+1 1.35E+2 1.35E+2 1.45E+2 2.07E+2 2.35E+1 4.09E+1 1.93E-1 2.51E-2 4.68E-3 1.25E-2 2.98E+5 7.08E+5 2.96E+4 1.17E+5 3.82E+5 5.22E+5 2.24E+2 3.49E-1 9.53E-2 8.20E-2 4.39E+2 2.44E+2 1.11E-1 6.03E-2 1.07E+2 9.31E+2 1~15 2.03E+2 1.62 1.15 1.62 6.71E+2 9.60E+1 9.60E+1 3 32E+4 3.30 4.92E+4 6.45E+2 9.39E-S 9.39E-S 1.37E+5 1.12 3.07E-2 1.06 1.21 2.20E-1 1.32E+2 2.24E-2 5.47E-1 2.41E+2 8.84E-3 8.84E-3 4.24E-1 3.07E-1 8.47E-1 1.66E+1 4 58E-3 1.97E+2 1.35E+2 1.35E+2 1.35E+2 1.19E+2 6.79E+4 3.55E+2 1.25E+1 6'2E+3 7.14E+1 1.14E-2 4.38E-3 4.38E-1 2.00E-2 5.79E+5 3.03E+1 2.29E+5 8.42E+4 5.32E-1 6.51E+4 3.42E+5 4.60E+1 1.77E+5 1.47E+1 6.83E-2 1.64E-1 5.75E-2 5.44E-2 6.72E-2 2.56E+2 2.63E+2 6.79E+2 8.09E+3 1.62 1.82E+3 9.60E+1 4.99E+3 3.30 4.63E+4 9.39E-5 3.60E+3 1.06 1.62E+4 3.06E+2 5.52 4-58E-3 2.02E+2 1.35E+2 1.35E+2 4.80E-2 5.47E+1 1 18E-4 3.68E+1 6.36E-1 2.35E-3 7.61E+4 1.24E+4 8.93E+3 1.33E+4 5.90E+4 1.02E+4 2.29E-l 4.61E+2 5.44E-2 1.06E+2 5.47E-1 1.48E+6 8.84E-3 3.78E+3 3.07E-1 7.37E+2*Calculated in accordance with NUREG 0133, Section 4.3.1;and Regulatory Guide 1.109, Regulatory position C, Section 1.004152LL 36 Unit 1 ODCM Revision 13 December 1993 1s.

NUCLIDE BONE LIVER Cs 136 Cs 137 1.04E-1 3.06E-1 1.26 1.47 Ba 140 3.85E-1 3.85E-4 Ce 141 1.85E-4 1.13E-4 Nb 95 La 140 9.88E-5 4.07E-S 3.03E-S 1.20E-S Ce 144 7.16E-3 2.93E-3 H3 7.43E-4 Cr 51 Cu 64 2.89E-4 Mn 54 4.79E-2 Fe 55 3.35E-2 2.16E-2 Fe 59 7.29E-2 1.27E-1 Co 58 8.58E-3 Co 60 2.60E-2 Zn 65 4.42E-2 1.52E-1 Sr 89 5.95 Sr 90 4.46E+1 Zr 95 4.90E-4 1.19E-4 Mn 56 ,6.17E-7 Mo 99 6.00E-2 Na 24 6.07E-3 6.07E-3 I 131 7.77E-2 9.16E-2 I 133 1.08E-2 1.58E-2 Ni 65 3.41E-6 3.86E-7 I 132 4.05E-7 8.22E-7 Cs 134 9.08E-1 1.69 TABLE 2-5 VALUES-LI{}UID*EMERGENCY CONDENSER VENT INFANT mrem-ml hr-pci T BODY THYROID 7.43E-4 7.43E-4 KIDNEY 7.43E-4 1.34E-4 1 08E-2 5.78E-3 5.02E-2 2.14E-2 6.15E-2 6'9E-2 1.71E-1 1.14E+1 8.47E-5 1.06E-7 1.17E-2 4.89E-4 1.06E-2 7.35E-2 1.29E-4 5.30E-7 8.97E-2 6.07E-3 6.07E-3 6.07E-3 4.03E-2 3'1E+1 1.07E-1 4.62E-3 2.87 1.76E-7 1.85E-2 2.93E-7 3.85E-S 9.17E-7 1.71E-1 1.14E-1 1.04E-1 1.99E-2 1.33E-5 2.35E-S 3.08E-6 4.02E-4 4.36E-1 1.22E-l 3.95E-1 9.15E-S 3.48E-S 2.92E-5 1.19E-3 3.30E-S 2.15E-S 4.70E-6 LUNG GI-TRACT 7.43E-4 7.43E-4 4.18E-S 9.61E-4 5.94E-3 1~76E-2'1~06E-2 2.75E-3 3.76E-2 6.08E-2 2'4E-2 6.19E-2 1.28E-1 1.22E-1 5.57E-1 5.95E-2 5,60E-5 1.98E-2 6.07E-3 6.07E-3 3.27E-3 2.67E-3 2.94E-5 6.66E-7 1.79E-1 4.60E-3 2.49E-2 4.64E-3 1.60E-1 4.61E-3 2.37E-4 9.47E-2 5.82E-2 3.43E-2 1.41E-1 4.11E-1*Calculated in accordance with NUREG 0133, Section 4.3.1;and Regulatory Guide 1.109, Regulatory position C, Section 1.004152LL 37 Unit 1 ODCM Revision 13 December 1993

~e'I I I I I ir'A>,

LIVER 1.44E-1 NUCLIDE BONE H3 Cr 51 3.78E-S 3 78E-5 Cu 64 2.63 Mn 54 1.23E-2 3.36E+3 Fe 55 9.04E+2 4.79E+2 Fe 59 1.28E+3 2.07E+3 Co 58 3.36E-3 7.01E+1 Co 60 1.99E-l 2.08E+2 Zn 65 2.15E+4 5.73E+4 Sr 89 3.07E+4 sr 90 4.01E+5 Zr 95 3.01E-l 6.78E-2 Mn 56-1.65E-l Mo 99 8.16E+1 Na 24 1.50E+2 1.50E+2 I 131 1.86E+2 1 87E+2 I 133 3.08E+1 3.81E+1 Ni 65 2.66E-1 2.50E-2 I 132 6.01E-3 1.10E-2 Cs 134 3.68E+5 6.04E+5 Cs 136 3.51E+4 9.66E+4 Cs 137 5.14E+5 4.92E+5 Ba 140 Ce 141 2.48E+2 2.17E-1 3.08E-2 1.54E-2 Ce 144 1.64 5.15E-l Nb 95 5'1E+2 2.03E+2 La 140 1.31E-1 4.59E-2 1.37 1.59 7.58E-1 2'7E-1 6.35 8.95E+2 1.23E-2 9.42E+2 1.49E+2 1.03E+3 2.38E-3 2.38E-3 2.15E+2 3.36E-3 3.36E-3 6.14E+2 1.99E-1 1.99E-1 3.56E+4 6.84E-3 3.61E+4 8.78E+2 1~02E+5 6.06E-2 2.19E-3 9.61E-2 3.73E-2 2.02E+1.2.00E-1 1.74E+2 1.50E+2 1.50E+2 1.50E+2 1.06E+2 6.19E+4 3.08E+2 1.44E+1 7+07E+3 6.35E+1 1.46E-2 5.08E-3 5.12E-1 1.69E-2 1.27E+5 6.29E-2 1.87E+5 6.25E+4 7.27E+4 1.10E-3 9.55E-2 5.14E+4 1.60E+5 1.45E+1 1.42E-4 7.09E-2 2.39E-3 1.13E-4 6.83E-3 1.45E+2 1.14E-3 1.90E+2 1.55E-2 1.83E-5 1.83E-S 8.81E-2 6.36E-4 2.85E-1 TABLE 2-6~VALUES-LIQUID*EMERGENCY CONDENSER VENT CHILD mrem-ml hr-pCi'I T BODY THYROID KIDNEY 1.44E-1 1.44E-1 1.44E-1 LUNG GI-TRACT 1.44E-1 1.44E-1 1.38 7'4E+1 1.23E+2 1.23E-2 2.82E+3 2.71E+2 8.88E+1 6.00E+2 2.15E+3 3.36E-3 4.09E+2 1.99E-1 1.15E+3 6.84E-3 1.01E+4 1.19E+3 5.40E+3 2.19E-3 6.84E+1 2.39E+1 6.75E+1 1.50E+2 1.50E+2 1.67E+1 1.53E+1 3.07 1.30E-2 6.71E+4 3.25E+3 7.67E+3 3.40E+3 5.77E+4 3.08E+3 1.30E-1 1.26E+2 1.13E-4 1.91E+1 1.14E-3 3.75E+5 1.83E-5 1.28E+3 6.36E-4 1.34E+2*Calculated in accordance with NUREG 0133, Section 4.3.1;and Regulatory Guide 1.109, Regulatory position C, Section 1.004152LL 38 Unit 1 ODCM.Revision 13 December 1993 t, A, V lb e g1~.'gC'll

'NUCLIDE BONE H3 LIVER 1.74E-1 TABLE 2-7~VALUES-LIQUID*EMERGENCY CONDENSER VENT TEEN mrem-ml hr-pCi T BODY THYROID KIDNEY 1.74E-1 1.74E-1 1.74E-1 LUNG GI-TRACT 1.74E-1 1.74E-1 Cu 64 2.86 Cr 51 1.81E-4 1.81E-4 1.28 1.35 7.12E-1 2.81E-1 7.24 1.83 2.15E+2 2.22E+2 Fe 55 6.89E+2 Fe 59 1.05E+3 4.88E+2 2.46E+3 Co 58 1.61E-2 8.78E+1 Co 60 9.53E-1 2'7E+2 Zn 65 2.10E+4 Sr 89 2.38E+4 Sr 90 4.54E+5 7.28E+4 Zr 95 2.56E-1 8.80E-2 Mn 54 5.89E-2 4.29E+3 8.52E+2 5.89E-2 1.28E+3 1.14E+2 9.50E+2 1.14E-2 1.14E-2 2.02E+2 1.61E-2 1.61E-2 5.78E+2 9.53E-1 9.53E-1 3.39E+4 3.28E-2 4.66E+4 6 81E+2 1.12E+5 6.38E-2 1.05E-2 1.24E-1 5.89E-2 8.81E+3 3.10E+2 2.11E+2 7.76E2 5.82E+3 1.61E-2 1.21E+3 9.53E-l 3.34E+3 3-28E-2 3.08E+4 2.83E+3 1.27E+4 1.05E-2 1.79E+2 Mn 56 Mo 99 1~81E-1 8.57E+1 3.22E-'2 1.63E+1 2.29E-1 1.96E+2 1.19E+1 1.54E+2 Na 24 1.38E+2 1.38E+2 I 131 1.47E+2 2.06E+2 I 133 2.42E+1 4.11E+1 Ni 65 2.08E-1 I 132 4.86E-3 Cs 134 3.05E+5 2.66E-2 1.27E-2 7.18E+5 Ce 144 1.27 5.28E-1 Cs 136 2.98E+4 1.17E+5 Cs 137 4.09E+5 5.44E+5 Ba 140 1.96E+2 2.47E-2 Ce 141 2.43E-2 1.64E-2 Nb 95 4.41E+2 ,2.45E+2 La 140 1.05E-1 5.17E>>2 1.38E+2 1.38E+2 1.38E+2 1.10E+2 6.00E+4 3.54E+2 1.25E+1 5.74E+3 7.21E+1 1.21E-2 4.56E-3 4.29E-1 2.00E-2 3.33E+5 3.01E-1 2.28E+5 7.87E+4 5.28E-3 6.38E+4 1.89E+5 4.57E-1 1.85E+5 1.27E+1 6.77E-4 8.23E-2 2.36E-3 5.40E-4 8.02E-3 1.15E+2 5.43E-3 2.37E+2 1.38E-2 8.78E-S 8.78E-5 7.12E-2 3.04E-3 3.17E-1 1.38E+2 1.38E+2 4.77E-4 4.07E+1 3.11E+1 1.44 5.54E-3 8.71E+4 8.93E+3 1.01E+4 9.43E+3 7.19E+4 7.73E+3 1.62E-1 3.03E+2 5.40E-4 4.54E+1 5.43E-3 1.05E+6 8.78E-5 2.96E+3 3.04E-3 3.19E+2*Calculated in accordance with NUREG 0133, Section 4.3.1;and Regulatory

'uide 1.109, Regulatory position C, Section 1.004152LL 39 Unit 1 ODCM Revision 13 December 1993

\4+S I 1 I'~Ital NUCLIDE BONE LIVER H3 2 27E-1 Cs 136 Cs 137 Ba 140 Ce 141 Nb 95 La 140 Ce 144 2.96E+4 1.17E+5 3.82E+5 5.22E+5 1.84E+2 2.32E-1.2'1E-2 ,1.50E-2 4.38E+2 2.44E+2 9.90E-2 4.99E-2 1.17 4.89E-1 Cr 51 3.24E-S 3.24E-5 Cu 64 2.72 Mn 54 1.06E-2 4.37E+3 Fe 55 6.58E+2 4.55E+2 Fe 59 1.02E+3 2.41E+3 Co 58 2.88E-3 8.83E+1 Co 60 1.71E-1 2.56E+2 Zn 65 2.31E+4 7.36E+4 Sr 89 2.18E+4 Sr 90 5.44E+5 Zr 95 2.40E-1 7.-81E-2 Mn 56 1.73E-1 Mo 99 8.04E+1 Na 24 1.34E+2 1.34E+2 I 131 1.37E+2 1.96E+2 I 133 2.25E+1 3.91E+1 Ni 65 1.93E-1 2.50E-2 I 132 4.64E-3 1.24E-2 Cs 134 2.98E+5 7.08E+5 TABLE 2-8 A VALUES-LIQUID*EMERGENCY CONDENSER VENT ADULT mrem-ml hr-pCi T BODY THYROID KIDNEY 2.27E-l 2 27E-1 2.27E-1 1.24 1.28 7.43E-1 2.74E-1 6.86 8.33E+2 1.06E-2 1.30E+3 1.06E+2 9.22E+2 2.04E-3 2.04E-3 1.98E+2 2.88E-3 2.88E-3 5.65E+2 1.71E-1 1.71E-1 3.32E+4 Si87E-3 4.92E+4 6.27E+2 1.34E+5 5.35E-2 1.88E-3 1.22E-1 3.07E-2 1.53E+1 2.20E-1 1.82E+2 1.34E+2 1.34E+2 1.34E+2 1.12E+2 6.43E+4 3.36E+2 1.19E+1 5.75E+3 6.82E+1 1 14E-2 4.34E-3 4.34E-1 1.98E-2 5.79E+5 5.39E-2 2.29E+5 8.42E+4 9.46E-4 6.51E+4 3.42E+5 8.19E-2 1.77E+5 1.21E+1 1.21E-4 7.88E-2 1.78E-3 9.67E-5 7.00E-3 1.31E+2 9.73E-4 2.41E+2 LUNG GI-TRACT 2.27E-1 2.27E-l 1.65 3'2E+2 2.32E+2 1.06E-2 1.34E+4 2.54E+2 2.61E+2 6.72E+2 8.02E+3 2.88E-3 1.79E+3 1.71E-1 4.81E+3 5.87E-3 4.63E+4 3.50E+3 1.57E+4 1.88E-3 2.42E+2 5.52 1.86E+2 1.34E+2 1.34E+2 5.17E+1 3.51E+1 6'6E-1 2.33E-3 7.61E+4 1.24E+4 8.92E+3 1.33E+4 5.89E+4 1.01E+4 1.33E-1 3.79E+2 9.67E-S 5.68E+1 9.73E-4 1.48E+6 6.33E-2 5.45E-4 2.90E-1 5.45E-4 3.95E+2 1.32E-2 1.57E-5 1.57E-5 1.57E-5 3.66E+3*Calculated in accordance with NUREG 0133, Section 4.3.1;and Regulatory Guide 1.109, Regulatory position C, Section 1.004152LL 40 Unit 1 ODCM Revision 13 December 1993 L 1 TABLE 3-1 Critical Receptor Dispersion Parameters'or Ground Level and Elevated Releases ELEVATED ELEVATED GROUNDo GROUNDo LOCATION Residences Dairy Cows'ilk Goats'eat Animals Gardens Site Boundary DIR E (980)SE (1300)SE (1300)ESE (1154)E (974)ENE (674)MILES 1.4 2.6 2.6 1.8 1.8 0.4 1.8 E-07'.2 E-08'.2 E-08'.1 E-OS'.0 E-07'.4 E-06~5.2 E-09~7'E-10'.0 E-10'.7 E-09'.5 E-09'.4 E-08~~Xsec m'i~D~m'i~Xsec ms+4.02 E-07 6.00 E-08 6.00 E-OS 1.16 E-07 2.53 E-07 6.63 E-06+D~m 8.58 E-09 1.64 E-09 1.64 Ei..09 3.54 E-09 5.55 E-09 6.35 E-08 a.These values will be used in dose calculations beginning in April 1986 but may be revised periodically to account for changes in locations of farms, gardens or critical residences.

b.Values based on 5 year annual meteorological data (C.T.Main, Rev.2)c.Values based on 5 year average grazing season meteorological data (C.T.Main Rev.2)d.Value are based on most restrictive X/Q land-based sector (ENE).(C.T.Main, Rev.2)e.Values are based on average annual meteorological data for the year 1985.f.Conservative location based on past dairy cow and goat milk history.004152LL 41 Unit 1 ObCM Revision 13 December 1993

,~vr.~

TABLE 3-2 Gamma Air and Whole Body Plume Shine Dose Factors*For Noble Gases Nuclide Kr-85 Kr-85m Kr-87 Kr-88 Kr-89 Kr-83m Xe-'133 Xe-133m Xe-135 Xe-135m Xe-137 Xe-138 Xe-131m Ar-41 Gamma Air B, mead r Ci sec 2.23E-6 1.75E-3 1.02E-2.2.23E-2 2.50E-2 2.26E-6 2.80E-4 2.27E-4 2.62E-3 5.20E-3 2.30E-3 1.32E-2 1.74E-5 1.64E-2 Gamma Whole Body V, m~rem~ei aec 1.68E-3 9.65E-3 2.17E-2 1.71E-2 2.41E-4 1.87E-4 2.50E-3 4.89E-3 2.20E-3 1.26E-2 1.47E-6 1.57E-2*Calculated in accordance with Regulatory Guide 1.109.(See Appendix B.)004152LL 42 Unit 1 ODCM Revision 13 December 1993 h A\P V TABLE 3-3 IMMERSION DOSE FACTORS*Nuclide 1~B~od*"~L-Skin**~~Air***~NA-ir<<<<<<Kr 83m 7.56E-02 Kr 85m 1.17E3 Kr 85 1.61E1 Kr 87 5.92E3 Kr 88 1.47E4 Kr 89 1.66E4 Kr 90 1.56E4 Xe 131m 9.15E1 Xe 133m 2.51E2 Xe 133 2.94E2 Xe 135m 3.12E3 Xe 135 1.81E3 Xe 137 1.42E3 Xe 138 8.83E3 Ar 41 8.84E3 1.46E3 1.34E3 9.73E3 2 37E3 1.01E4 7.29E3 4.76E2 9.94E2 3.06E2 7.11E2 1.86E3 1.22E4 4.13E3 2.69E3 l.93E1 1.23E3 1.72E1 6.17E3 1.52E4 1.73E4 1.63E4 1.56E2 3'7E2 3.53E2 3.36E3 1.92E3 1.51E3 9.21E3 9.30E3 2.88E2 1.97E3 1.95E3 1.03E4 2.93E3 1.06E4 7.83E3 1.11E3.1.48E3 1.05E3 7.39E2 2.46E3 1.27E4 4.75E3 3.28E3*From, Table B-l.Regulatory Guide 1.109 Rev.1**mrem/yr per pci/mi.***mrad/yr per pCi/m~.004152LL 43 Unit 1 ODCM Revision 13 December 1993 th'i 4'1 I%w ll TABLE 3-4 DOSE AND DOSE RATE Q VALUES INHALATION INFANTl~rem~r pci/m NUCLIDE H 3*C 14*Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I-131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE',65E4 1.97E4 1.36E4 1.93E4 3.98E5 4.09E7 1.15ES 1.57E4 3.79E4 1.32E4 3.96ES 5.49E5 5.60E4 5.05E2 2.77E4 3.19E6 7.94E3 LIVER 6.47E2 5.31E3 2.53E4 1.17E4 2.35E4 1.22E3 8.02E3 6.26E4 2.79E4 6.43E3 1.65E2 4.44E4 1.92E4 7.03ES 6.12E5 5.60E1 2.00E2 1.67E4 1.21E6 8.13E3 6.47E2 5.31E3 8.95E1 4.98E3 3.33E3 9.48E3 1.82E3 1.18E4 3.11E4 1.14E4 2.59E6 2.03E4 3.78E3 3.23E1 1.96E4 5.60E3 7.45E4 4.55E4 2.90E3 5.15E1 1.99E3 1.76ES 5.00E2 6.47E2 5.31E3 5.75E1 1.48E7 3.56E6 T.BODY" THYROID KIDNEY 6.47E2 5.31E3 1.32E1 4.98E3 3.25E4 3.11E4 4.72E3 2.65E2 5.18E4 2.24E4 1.90E5 1.72ES 1.34E1 5.25E3 5.38ES 3.15E3 LUNG 6.47E2 5.31E3 1.28E4 GI-LLI 6.47E2 5.31E3 3.57E2 1'OE6 7 06E3 8.69E4 1.02E6 7.77E5 4.51E6 6.47E5 2 03E6 1.12E7 1.75E6 4.79ES 1.35ES 7.97E4 7.13E4 1.60E6 1.09E3 2.48E4 1.11E4 3.19E4 5.14E4 6.40E4 1.31ES 2.17E4 1.27E4 4.87E4 1.06E3 2.16E3 1.33E3 1.33E3 3.84E4 5.17ES 9.84E6 3.22ES 2.16E4 1.48ES 3.12E4 1.68E5 8.48E4*mrem/yr per pci/m~.'his and following g Tables Calculated in accordance with NUREG 0133, Section 5.3.1, except C 14 values in accordance with Regulatory Guide 1.109 Equation C-8.004152LL 44 Unit 1 ODOM Revision 13 December 1993 J aA ,F TABLE 3-5 DOSE AND DOSE RATE Q VALUES-INHALATION mrem r pCi/m CHILD NUCLIDE H 3*C 14*Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE'.59E4 4.74E4 2.07E4 4.26E4 5.99E5 1.01E8 1.90E5 2.35E4 4.81E4 1.66E4'.51E5 9.07ES 7.40E4 6.44E2 3.92E4 6.77E6 1.08E4 LIVER 1.12E3 6.73E3 4.29E4 2.52E4 3'4E4 1.77E3 1.31E4 1.13ES 4.18E4 9.18E3 1.72E2 4.81E4 2.03E4 1.01E6 8.25E5 6.48E1 2.25E2 1.95E4 2'2E6 8.73E3 T.BODY 1.12E3 6.73E3 1.54E2 9.51E3 7 77E3 1.67E4 3.16E3 2.26E4 7 03E4 1.72E4 6.44E6 3.70E4 6.55E3 4.26E1 2.73E4 7.70E3 2.25E5 1.28E5 4.33E3 7.55El 2.90E3 3.61E5 6.81E2 1.12E3 6.73E3 8.55E1 1.12E3 6.73E3 2.43El 1.00E4'7.14E4 1.62E7 3.85E6 5.96E4 8.62E3 3.92E2 7.88E4 3.38E4 3.30E5 2.82ES 2.11E1 8.55E3 1~17E6 4.81E3 THYROID KIDNEY LUNG 1.12E3 GI-LL'I 1.12E3 1~27E6 7.07E4 1.11E6 3.44E4 7.07E6 9.95ES 9.62E4 1.63E4 2.16E6 1.67ES 1.48E7 3.43ES 2.23E6 6.11E4 6.14ES 3.70E4 1.35ES 1.21ES 1~27ES 2.84E3 5.48E3 3 85E3 1.04ES 3.62E3 1.74E6 1.02E5 1.83ES 2.26ES 5.44ES 1.20E7 3.28ES 5.66E4 3.89E5 8.21E4 6.73E3 6.73E3 1.70E4 1.08E3 1.58E6 2.29E4 1.11E5 2.87E3*mrem/yr per pci/m~.004152LL 45 Unit 1 ODCM Revision 13 December 1993 l r t I j I N I'~l P NUCLIDE H 3*C 14*Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147'BONE'.60E4 3.34E4 1.59E4 3.86E4 4.34E5 1.08E8 1.46E5 1.86E4 3.54E4 1.22E4 5.02E5 6.70ES 5.47E4 4.79E2 2.84E4 4.89E6 7.86E3 LIVER 1.27E3 4.87E3 5.11E4 2.38E4 3.70E4 2.07E3 1.51E4 1.34ES 4.58E4 1.03E4 1.69E2 4.91E4 2.05E4 1.13E6 8.48ES 6.70E1 2.36E2 1.90E4 2.02E6 8.56E3 1.27E3 4.87E3 1~35E2 8.40E3 5.54E3 1.43E4 2.78E3 1.98E4 6.24E4 1.25E4 6.68E6 3.15E4 5.66E3 3.22E1 2.64E4 6.22E3 5.49E5 3.11E5 3.52E3 6.26E1 2.17E3 2.62E5 5.13E2 1.27E3 4'7E3 7.50E1 1.46E7 2'2E6 TABLE 3-6 DOSE AND DOSE RATE Q VALUES-INHALATION mrem r pCi/m T.BODY THYROID TEEN KIDNEY 1.27E3 4.87E3 3.07E1 1.27E4 8.64E4 6.74E4 1.00E4 4.11E2 8.40E4 3.59E4 3.75E5 3.04E5 2.28E1 8.88E3 1~21E6 5.02E3 LUNG 1+27E3 GI-LLI 1.27E3 4.87E3 4.87E3 2.10E4 3.00E3 8'2E6 1.24E6 2.59E5 4.66E4 2.42E6 3.71E5 1.65E7 7.65ES 2.69E6 1.49ES 7.51E5 9.68E4 1.54ES 2.69E5 1.46ES 1.21E5 2.03E6 2.14E5 6.14E5 6.49E3 1.03E4 9.76E3 8'8E3 2.29ES 4.87E5 1.26ES 1.34E7 8.64E5 3.72E5 1.82E5 1.98E6 6.68E4 1.24E5 6.39E3 1.53E6 1.78E5 1.34E6 9.52E4*mrem/yr per pci/m~.004152LL 46 Unit 1 ODCM Revision 13 December 1993 i',>>

NUCLIDE H 3*C 14+Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE 1.82E4 2.46E4 1.18E4 3.24E4 3.04ES 9.92E7 1.07E5 1.41E4 2.52E4 8.64E3 3.73E5 4.78ES 3.90E4 3.44E2 1.99E4 3.43E6 5.27E3 LIVER 1.26E3 3.41E3 3.96E4 1.70E4 2.78E4 1.58E3 1.15E4 1.03ES 3.44E4 7.82E3 1.21E2 3.58E4 1.48E4 8.48ES 6.21ES 4.90E1 1.74E2 1.35E4 1.43E6 6.10E3 1.26E3 3.41E3 1.00E2 6.30E3 3.94E3 1.06E4 2.07E3 1.48E4 4.66E4 8.72E3 6.10E6 2.33E4 4.21E3 2.30E1 2.05E4 4.52E3 7.28E5 4 28ES 2.57E3 4.58E1 1.53E3 1.84E5 3.65E2 1.26E3 3.41E3 5.95E1 1.19E7 2.15E6 TABLE 3-7 DOSE AND DOSE RATE Q VALUES-INHALATION mrem r pCi/m T.BODY'HYROID ADULT KIDNEY 1.26E3 3.41E3 2.28E1 9.84E3 6.90E4 5.42E4 7.74E3 2.91E2 6.13E4 2.58E4 2.87ES 2.22ES 1.67E1 6.26E3 8.48ES 3.56E3 LUNG 1'26E3 GI-LL'I 1.26E3 1.02E6 9.28ES 5.97E6 1.88E5 1.06E5 2.85E5 8.64E5 5.34E4 1.40E6 3.50ES 9.60E6 7.22E5 1.77E6 5.05ES 1.50ES 1.04ES 9.12E4 2.48ES 9.76E4 7.52E4 1.27E6 1.36E5 3.62ES 6.28E3 8.88E3 1.04E4 8.40E3 2.18ES 4 58E5 1.20E5 7.78E6 8.16ES 2.21ES 1.73ES 3.41E3 3.41E3 1.44E4 3.32E3 1.40E6 7.74E4 7.21E4 6.03E3*mrem/yr per pci/m~.004152LL 47 Unit 1 ODCM Revision 13 December 1993 g l

~UCLI DE H 3 C 14 Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 TABLE 3-8 DOSE AND DOSE RATE Q VALUES-GROUND PLANE ALL AGE GROUPS mi-mremlrr pci/sec TOTAL BODY 4.65E6 1.40E9 2.73E8 3.80E8 2.15E10 7 46ES 2.16E4 2.45E8 1.36E8 3.99E6 1.72E7 2.39E6 6.83E9 1.03E10 2.05E7 1.92E7 1.37E7 6.96E7 8.46E6 S IN 5 50E6 1.64E9 3'0E8 4'5E8 2'3E10 8'7E8 2.51E4 2.85E8 1.61E8 4.63E6 2.09E7 2.91E6 7.97E9 1.20E10 2.35E7 2.18E7 1.54E7 8.07E7 1.01E7 004152LL 48 Unit 1 ODCM Revision 13 December 1993

~l I' TABLE 3-9 DOSE AND DOSE RATE VALUES-COW MILK-INFANT md~mr em r pci/sec NUCLIDE H 3 C 14'r 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE 3.23E6~LI VR 2.38E3 6.89ES 8.43E7 1.22E8 3.53E9 6.93E9 8.19E10 3.85E3 4.21E5 6~81ES 8.52E6 2.51E7 5.44E7 2'3ES 1.39E7 5'0E7 1.21E10 9.39E2 1.64ES 1.04ES 8.02ES 1.24E7 1.21E8 2.03E1 2.28E4 1.49E6 4.43E2 1.21E5 7.99 1.39E4 6 10E5 4.55E2 2.41E10 4.49E10 3.47E10 4.06E10 2.38E3 6'9E5 8.35E4 5.68E6 1.45E7 8.38E7 3.46E7 1.39ES 5 58E9 1.99E8 2.09E10 6.66E2 1.17ES 2.03E7 3.53E8 3.63E6 4.54E9 2.88E9 6.22E6 2.06 1.64E3 8.34E4 2.79El 2.38E3 6.89ES 5.45E4 2.64E11 2.26E9 T.BODY'HYROID KIDNEY 2.38E3 6.89E5 1.19E4 5.56E6 5.87E9 1.01E3 1.54ES 1.55E8 9.37E8 1.46E7 1.16E10 1.09E10 2.87E4 4.28E3 2.46E5 1.76E2 LUNG 2.38E3 6.89E5 1.06E5 2.66E7 GI-LDI 2.38E3 6.89E5 2.43E6 9.21E6 6.91E6 4.74E9 4.41E9 7.42E4 3.46E7 1.40ES 1.02E10 1.42E8 1.02E9 4.68E5 3.03E8 3.43E7 2.86E7 2.10E6 1.22ES 1.27ES 2.97E7 9.39E4 7.18E6 8.54E7 2.89E5 6.29E7 1.02ES mrem/yr per pci/m~.004152LL 49 Unit 1 ODCM Revision 13 December 1993 1'h l~Iy.kr NUCLIDE H 3 C 14 Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE'.65E6 L~IVE 1.57E3 3.29E5 6.97E7 6.52E7 2.63E9 3.64E9 7.53E10 2.17E3 1.86ES 3.26ES 4.04E6 1.35E7 3.07E7 1.06ES 6.94E6 2.89E7 7.00E9 4.77E2 1.03E4 4.07E7 3.28ES 4.99E6 5.87E7 9.70 1.15E4 1.04E6 2.24E2 5.14E4 3.39 5.73E3 3.26E5 1.81E2 1.50E10 2.45E10 2.17E10 2.08E10 T.BODY THYROID KIDNEY 1.57E3 1.57E3 3.29ES'.29E5 5.27E4 3.59E6 1.15E7" 5.26E7'2.13E7 8.52E7 4.35E9 1.04ES 1.91E10 4.25E2 5.69E4 1.01E7 1.86ES 1.89E6 5.18E9 3.07E9 3.43E6 1.14 8.51E2 5.55E4 1.40E1 2.93E4 1.08E11 9.27E8 1.57E3 3.29E5 7.99E3 3.78E6 4.41E9 6.83E2 1.00ES 8.69E7 5.39ES 8.32E6 7.61E9 6.78E9 1.67E4 2.51E3 1.80ES 9.94E1 TABLE 3-10 DOSE AND DOSE RATE Q VALUES-COW MILK-CHILD mi~mrem r pCi/sec LUNG 1.57E3 GI-LLI 1'7E3 3.06E7 2.73E9 2.44E9 3.07E4 1.10E8 4.05E7 1.60ES 1.23E9 1.41ES 1.01E9 4.98E5 4.42ES 3.37E7 2.92E7 2.01E6 1.32ES 1.30ES 2.97E7 9.45E4 7.15E6 8.49E7 2.87ES 3.29ES 3.29ES 5.34E4 2.80E6 1.13E7 2.09E7 6.85E6 mrem/yr per pci/m~.004152LL 50 Unit 1 ODCM Revt.sion 13 December 1993 gtl TABLE 3-11 DOSE AND DOSE RATE Q VALUES-COW MILK-TEEN gj~mrem r pCi/sec NUCLIDE H 3 C 14 Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE'.70E5 2.78E7 2.81E7 1.34E9 1.47E9 4.45E10 9.34E2 1.86E5 1.34E8 1.66E6 6.49E9 9.02E9 2.43E7 4.05 4.67E3 4.22ES 9.12E1 LIVER 9.94E2 1.34E5 9 01E6 1.97E7 6.57E7 4.55E6 1.86E7 4.65E9 2.95E2 1.03E5 2.24E7 1.88E8 2.82E6 1.53E10 1.20E10 2.98E4 1.99 3.12E3 1.74ES 9.91E1 T.BODY 9.94E2 1.34ES 2.58E4 1'9E6 4.59E6 2.54E7 1.05E7 4.19E7 2.17E9 4.21E7 1.10E10 2.03E2 5.69E4 4.27E6 1.01E8 8.59ES 7.08E9 4.18E9 1.57E6 5.30E-1 3.58E2 2.27E4 5.94EO THYROID KIDNEY 9.94E2 1.34E5 1.44E4 9.94E2 1.34ES 5.66E3 2.69E6 2.97E9 1.47E3 1.04ES 5.82E1 4.33E2 1.00E5 5.12E7 5.49E10 3.24E8 3.93E8 4.94E6 4.85E9 4.08E9 1.01E4 LUNG GI-LLI 1.35E5 1.34E5 3.69E4 4.34E6 1.25E7 2.07E7 1.85E9 1 59E9 2.00E4 1.85E7 8.52E6 1.55E8 6.27E7 2.42E8 1.97E9 1.75E8 1.25E9 6.80E5 4.42E8 4.01E7 3.72E7 2.13E6 1.90E8 1.71E8 3.75E7 1.14E5 8'1E6 1.06E8 3.58ES 9.94E2 9.94E2 mrem/yr per pci/m~.004152LL 51 Unit 1 ODCM Revision 13 December 1993 r V4 J I Yl'J I[

TABLE 3-12 DOSE AND DOSE RATE Q VALUES-COW MILK-ADULT me~mrem r pCi/sec NUCLIDE H 3 C 14 Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE 3.63E5 1.57E7 1.61E7 8.71ES 7.99ES 3.15E10 5.34E2 1.09E5 7.41E7 9.09E5 3.74E9 4.97E9 1.35E7 2.26 2.54E3 2.29ES 4.74E1 LIVER 7.63E2 7.26E4 5.41E6 1~OBE7 3.79E7 2.70E6 1.10E7 2.77E9 1.71E2 6.07E4 1.24E7 1.06ES 1~58E6 8.89E9 6.80E9 1.69E4 1.14 1.72E3 9.58E4 5.48E1 T.BODY 7.63E2 7.26E4 1.48E4 1.03E6 2.52E6 1.45E7 6.05E6 2.42E7 1.25E9 2.29E7 7.74E9 1.16E2 3.27E4 2.36E6 6.08E7 4.82ES 7.27E9 4.46E9 8.83E5 3.01E-1 1.95E2 1.23E4 3.28EO THYROID KIDNEY 7.63E2 7.63E2~LUN GI-LII 7.63E2 7.63E2 7'6E4 8.85E3 3.26E3 1 61E6 1.96E4 3.72E6 1.66E7 6.04E6 6.21E6 3.47E10 2.32ES 1.85E9 2.69E2 6.00E4 2.81E7 1.82ES2.76E6 2.88E9 2.31E9 5.75E3 7.99E2 5.68E4 3.20E1 1.06E7 9.55ES 7.68ES 9.69E3 1.26EB 5.47E7 2.06EB 1.75E9 1.28EB 9.11EB 5.43ES 3.69ES 2.87E7 2 SOE7 1.42E6 1.56ES 1.32EB 2 77E7 8.35E4 6.58E6 7.74E7 2.63E5 7.26E4'.26E4 7.26E4 mrem/yr per pci/m~.004152LL 52 Unit 1 ODCM Revision 13 December 1993

NUCLIDE H 3 C 14 Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE 3.23E6 1.10E6 1.59E6 4.24ES 1.48E10 1.72E11 4.66E2 9.42E4 8.17ES 1.02E7 7.23E10 1.04E11 1.45E7 2.430 2.74E3 1.79ES 5.32E1 LIVER 6.33E3 6.89ES 3'1E6 7.08E5 2.78E6 1.67E6 7.08E6 1.45E9 1.13E2 3.88E4 1.27E7 9.63ES 1.49E7 1.35E11 1.22E11 1.45E4 9.59E-l 1.67E3 7.32E4 5.47E1 GI-LLI KIDNEY T.BODY THYROID LUNG 6.33E3 6.89E5 6.33E3 6'9E5 1~43E3 6.67E5 6.33E3 6.89E5 1.00E4 6.82E5 1.89E5 1.09E6 4.16E6 1.67E7 6.70ES 4.24E8 4.38E10 8.04E1 2.24E4 2.47E6 4.23E8 4.36E6 1.36E10 8.63E9 7.48ES 2.47E-1 1.96E2 1.00E4 3.35EO 6.33E3 6.89ES 6.56E3 6.33E3 6.89E5 1.28E4 2.93E5 1.11E6 8.98E4 3.46ES 8.21E5 1.33E6 4.16E6 1.68E7 1.23E9 3'4ES 2.15E9 5.65E4 3'7E7 4.17E6 3.44E7 2.52E6 7.04ES 1.22E2 2.78E4 1.89E7 3.16E11 1.12E9 2.71E9 1.75E7 3.47E10 1.42E10 3.66ES 3.27E10 1.32E10 3.81ES 3.44E3 8.91E3 3.56E6 1.13E4 8.62E5 5.14E2 2.96E4 2.11El 1.03E7 3.46E4 TABLE 3-13 DOSE AND DOSE RATE VALUES-GOAT MILK-INFANT m'mremlrr pCi/sec mrem/yr per pci/m3.004152LL 53 Unit 1 ODCM Revision 13 December 1993 M WW t J TABLE 3-14 DOSE AND DOSE RATE R;VALUES-GOAT MILK-CHILD mi~mrem r pCi/sec NUCLIDE H 3 C 14'r 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE 1.65E6 LIVER 4.17E3 3.29E5 9 06E5 8'2ES 3.15ES 7.77E9 1.58E11 2.62E2 5.05E4 3.91ES 4.84E6 1.62E6 4.81E5 1.38E6 8.35E5 3.47E6 8.40ES 5.76E1 1.96E4 4.95E6 3.94E8 5.99E6 6.52E10 7.05E6 1.16 1.38E3 1.25ES 2.68E1 6.24E10 6.18E3 4.07E-1 6.88E2 3.91E4 2.17El 4.49E10 7.37E10 T.BODY 4.17E3 3.29E5 6.34E3 4.31ES 1.49E5 6.86E5 2.56E6 1.02E7 5.23ES 2.22ES 4.01E10 5.13E1 1.40E4 1.22E6 2.24ES 2'7E6 1.55E10 9.21E9 4.12ES 1.37E-1 1.02E2 6.66E3 1.68EO THYROID 4.17E3 3.29E5 3.52E3 KIDNEY 4.17E3 3.29E5 9.62E2 4.54E5 5.29ES LUNG 4.17E3 GI-LLI 4.17E3 3.29E5 3.29E5 6.43E3 2.72E5 3.99E5 3.36ES 1.36E6 8.91E4 1.43E6 4.87E6 1.92E7 1.48ES 3.01ES 2.13E9 6.01E4 3.63E7 4.09E6 3.50E7 1.11E9 9.98E6 2.28E10 5 8.19E9 2.03E10 7.32E9 2.01E3 3.68E3 3.02E2 2.16E4 1.19E1 2.41E6 3.97E8 3.91ES 3.57E6 1.13E4 8.59E5 1.02E7 3.44E4 8.25E1 1.85E4 1.06E7 1.30E11 6.46ES mrem/yr per pci/m~.004152LL 54 Unit 1 ODCM Revision 13 December 1993

~~

TABLE 3-15 DOSE AND DOSE RATE Q VALUES-GOAT MILK-me~mrem r pci/sec TEEN NUCLIDE H 3 C 14'r 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE'.70ES LIVER 2.64E3 1.34E5 3.61E5 3.67E5 1~61ES 3.14E9 9.36E10 1.13E2 2.23E4 1.61E8 1.99E6 1.08E6 2.56E5 8.57ES 5.46E5 2.23E6 5 SSES 3.56E1 1.24E4 2.72E6 2.26E8 3.38E6 2.92E6 4.86E-1 5.60E2 5.06E4 1.09E1 3.58E3 2.39E-l 3.74E2 2.09E4 1.19E1 1.95E10 4.58E10 2.71E10 3.60E10 T.BODY THYROID KIDNEY 2.64E3 1.34ES 3.11E3 2.15ES 5.97E4 3.31E5 1.26E6 5.03E6 2.60ES 8.99E7 2.31E10 2.45E1 6.82E3 5.19ES 1.21ES 1.03E6 2.13E10 1.25E10 1.88E5 6 36E-2 4.30E1 2.72E3 7.13E-1 2.64E3 1.34ES 1.73E3 2.64E3 1.34E5 6'2E2 3.23E5 3.57E8 4.72ES 5.93E6 1.46E10 1.23E10 1.21E3 1.76E2 1.25E4 6.99EO 5.23El 1.20E4 6.23E6 6.59E10 3.89ES I UNG GI-LLI 2.64E3 2.64E3 1~35ES 1.34ES 4.44E3 5.23ES 1.62ES 2.22E6 1.11ES 2'0E5 2.03E6 5.56E9 4.76E9 7.53E6 2.91E7 2.36ES 3.74ES 2.63E9 8.22E4 5.30E7 4.87E6 4.47E7 2.56E6 5.70ES 5.12ES 2.41E3 4.50E6 1.37E4 1.07E6 1.27E7 4.29E4 mrem/yr per pci/m~.004152LL 55 Unit 1 ODCM Revision 13 December 1993 C'(1 gS 0~l TABLE 3-16 DOSE AND DOSE RATE Q VALUES-GOAT MILK-ADULT m'~modem r pci/sec ,NUCLIDE H 3 C 14'r 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 ,Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE'.63E5 LIVER 2.03E3 7.26E4 2'4ES 2.10ES 1 05EB 1.70E9 6.62E10 6.45E1 1.31E4 8.89E7 1.09E6 6.50E5 1.41E5 4.95E5 3.25E5 1.32E6 3.33EB 2.07E1 7.29E3 1.51E6 1.27EB 1.90E6 1.62E6 2.71E-1 3.06E2 2.75E4 5,69EO 2.03E3 1.36E-l 2.07E2 1.15E4 6.57EO 1.12E10 2.67E10 1.49E10 2.04E10 T.BODY 2.03E3 7.26E4 1.78E3 1.24E5 3.28E4 1.90E5 7.27ES 2.91E6 1.51EB 4.89E7 1.63E10 1.40E1 3.92E3 2.87E5 7.29E7 5.79E5 2.18E10 1.34E10 1.06E5 3.61E-2 2.34E1 1.48E3 3.93E-1 THYROID KIDNEY 2.03E3 7.26E4 1.06E3 2.03E3 7.26E4 3.92E2 1.93ES 2.23EB 2.79EB 3.31E6 8.63E9 6.93E9 6.91E2 9.60E1 6.82E3 3.84EO 3.25E1 7.21E3 3.41E6 4.17E10 2.18EB LUNG GI-LLI 2.36E3 7.85E4 1.38ES 4.48E5 1~99E6 8.07E4 1.65E6 6.58E6 2.48E7 2.10EB 2.73EB 1.91E9 6.56E4 4.42E7 3.49E6 3.36E7 1.71E6 2.86E9 4.67EB 2.30E9 1.16E3 3.95EB 3.33E6 1,00E4 7.90E5 9.30E6 3.15E4 2.03E3 2'3E3 7.26E4 7'6E4 mrem/yr per pci/m~.004152LL 56 Unit 1 ODCM Revision 13 December 1993

TABLE 3-17 DOSE AND DOSE RATE Q VALUES-COW MEAT-CHILD m~~mrem r pci/sec NUCLIDE H 3 C 14 Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE 5.29ES 2.89ES 2.04ES 2.38ES 2.65ES 7.01E9 1.51E6 4.10E6 4.15E6 9.38E-2 6.09ES 8.99ES 2.20E7 2.80E-2 1.17E4 1.48E6 5.93E3 LIVER 2.34E2 1'6ES 5.15E6 1.53ES 3.30EB 9.41E6 4.64E7 6.35ES 3.32ES 1.59E6 5.42E4 4.18E6 1.16E-1 1.00E9 8.60EB 1.93E4 9.78E-3 5.82E3 4.65ES 4.80E3 T.BODY 2.34E2 1.06ES 4;55E3 1.37E6 4.74E7 1.65ES 2.88E7 1.37ES 3.95ES 7.57E6 1.78E9 2.95E5 1.14E6 1.34E4 2.37E6 4.39E-2 2.11ES 1.27ES 1.28E6 3.30E-3 8.64E2 7.91E4 3.72E2 2.34E2 1.06ES 2.52E3 2.34E2 1.06ES 6.90E2 1.44E6 4.00ES 1.38E9 2.15E1 4.75E5 1.50E6 1.16E5 6.86E6 1.93E-1 3.10ES 2.80EB 6.27E3 2.55E3 2.57E5 2.64E3 THYROID KIDNEY LUN GI-LL'I 2.34E2 2.34E2 1.06E5 1'6E5 9.58E7 1.11EB 1.01EB 3.44ES 5.49E7 2.57EB 1.12EB 1.03E7 9.44E7 3.46EB 2.95E9 4.48E4 3.72E5 4.67E-2 5.39E6 5.39E6 1.15E4 1.11E7 2.73E2 7.26E6 1.21EB 7.61E6 4'1E3 2'1ES 4.32E6 8.66E7 2.84E7 mrem/yr per pci/m~.004152LL 57 Unit 1 ODCM Revision 13 December 1993 A

TABLE 3-18 DOSE AND DOSE RATE Q VALUES-COW MEAT-TEEN me~mr em r pCi/sec NUCLIDE H 3 C 14 Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr.89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE'.81ES 1.50ES 1.15ES 1~59ES 1.40EB 5.42E9 8.50E5 2.37E6 2.24E6 5.05E-2 3.46ES 4.88ES 1.19E7 1.53E-2 6.19E3 7'7ES 3.16E3 LIVER 1.94E2 5.62E4 4 50E6 1.07ES 2.69ES 8.05E6 3.90E7 5'2EB 2.68E5 1.32E6 3.90E4 3.13E6 8.57E-2 8.13ES 6.49EB 1.46E4 7.51E-3 4.'14E3 3.26ES 3.44E3 T.BODY 1.94E2 5.62E4 2.93E3 8.93ES 2.49E7 1.04ES 1.86E7 S.SOE7 2.57EB 4.01E6 1.34E9 1.84ES 7.24ES 7.43E3 1.68E6 2.61E-2 3.77ES 2.26ES 7.68ES 2.00E-3 4 75E2 4.23E4 2.06E2 1.94E2 5.62E4 1.62E3 1.94E2 5.62E4 6.39E2 1.34E6 3.53ES 9.15EB 1.20E1 3.94ES 1.28E6 8.92E4 5.40E6" 1.50E-1 2.58ES 2.21EB 4.95E3 1~95E3 1.94E5 2.02E3 THYROID KIDNEY LUNG 1.94E2 5.62E4 GI-LL'I 1.94E2 5.62E4 8.47E7 6.36ES 1.11ES 5-09EB 2'4ES 1.67E7 1.52ES 6.19EB 5'3E9 6.98E4 6.20E5 6.48E-2 9.87E7 , 1.01E7 8.58E7 9.81E3 9.24E6 1.84E7 4.31E2 1.18E7 1.98EB 1.24E7 4.16E3 4.90ES 9.24E6 6.77E7 4.62E7 mrem/yr per pci/m~.004152LI 58 Unit 1 ODCM Revision 13 December 1993 8 V.~r, TABLE 3-19 DOSE AND DOSE RATE g VALUES-COW MEAT-ADULT'icr em r pci/sec NUCLIDE H 3 C 14 Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE 3.33E5 LIVER 3 25E2 6.66E4 5.90E6 1.28E8 3.39ES 1.04E7 5.03E7 7.19ES 1.85ES 1.44ES 2.26ES 1.66ES 8.38E9 1.06E6 3.04E6 3.40E5 1.69E6 4.71E4 3.85E6 1.05E-1 1.03E9 8.04ES 1.81E4 9.37E-3 4.99E3 3.90ES 2.69E6 6.04E-2 4.35ES 5.88ES 1.44E7 1~86E-2 7.38E3 9.33E5 3.59E3 4.15E3 3.25E2 6.66E4 3.65E3 1.13E6 2.98E7 1.30ES 2.34E7 1.11E8 3.25E8 4.76E6 2.06E9 2.30ES 9.08E5 8.97E3 2.21E6 3.20E-2 8.45ES 5.26ES 9.44E5 2.48E-3 5.66E2 5.01E4 2.48E2 3.25E2 6.66E4 2.18E3 1.26E9 1.54E1 T.BODY THYROID KIDNEY 3'5E2 6.66E4 8.03E2 1.76E6 4.81ES 5.34E5 1~67E6 1.07ES 6.61E6 1.83E-1 3.35ES 2.73ES.6.15E3 2'2E3 2.31ES 2.42E3 LUNG GI-LBI 4.84E3 9.17E5 1.81E7 7.14E7 7.34E7 9.46E7 1.11ES 9.07E7 1.04E4 1.13E9 2.12ES 9.45ES 4.53ES 2.66E7 2.42ES 1.08E9 1.03E10 1.09E5 1.02E6 9.44E-2 1.81E7 1.56E7 2.97E7 6.88E2 1.91E7 3.16ES 1.99E7 3.25E2 3.25E2 6.66E4 6.66E4 mrem/yr per pci/m~.004152LL 59, Unit 1 ODCM Revision 13 December 1993

TABLE 3-20 DOSE AND DOSE RATE VALUES-VEGETATION me~mrem r pci/sec CHILD NUCLIDE H 3 C 14'r 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE 3.50E6 7'3ES 3.97ES 8.12ES 3.59E10 1.24E12 3.86E6 1.02E6 7.16E7 1.69E6 1.60E10 2.39E10 2.77ES 3.25E3 6.56E5 1.27ES 7.23E4 LIVER 4.01E3 7.01ES 6.65ES 4.05E8 6.42E8 6 45E7 3.78ES 2'6E9 8.50E5 3.99E5 7.70E6 7.20E7 2.09E6 2.63E10 2 29E10 2.43ES 1.13E3 3.27E5 3.98E7 5 86E4 T.BODY 4.01E3 7.01E5 1.17E5 1.77ES 1.25ES 3.20E8 1.97ES 1.12E9 1.35E9 1.03E9 3.15E11 7.56E5 2.85E5 1.91E6 4.09E7 7.92E5 5.55E9 3.38E9 1.62E7 3.83E2 4,85E4 6.78E6 4.54E3 THYROID KIDNEY 4.01E3 7.01E5 6.49E4 4'1E3 7.01ES 1.77E4 1.86ES 1.36E9 3.89ES 3.49E6 8.15E9 7.46E9 7.90E4 1.43E5 2.21E7 3.22E4 1.22E6 3.75ES 1.65E7 2.38E10 1.18ES LUNG GI-LLI 1.86E8 2.93E9 2.68E9 1.45ES 6.69ES 3.76ES 2.10E9 3.80E8 1.39E9 1.67E10 8.86ES 7.37ES 6.37E6 6.41E6 8.44E5 1.42ES 1.43ES 1'0ES 3.16E7 4.08ES 1.04E10 9.28E7 4.01E3 4.01E3 7.01E5 7.01ES 1.18E5 6.20E6 5.58ES 2.29E8 7.50E7 mrem/yr per pci/m~.004152LL 60 Unit 1 ODOM Revision 13 December 1993 I A 1 I.~l TABLE 3-21 DOSE AND DOSE RATE Q VALUES-VEGETATION-mi~mrem r pCi/sec TEEN NUCLIDE H 3 CD 14 Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147'BONE 1.45E6 LIVER 2.59E3 2.91E5 3.10ES 1.79EB 4 24EB 1.51E10 7e51E11 1.72E6 4.80E5 3.85E7 9.29E5 7.10E9 4.54EB 2.20ES 4.18ES 4.37E7 2.49ES 1.47E9 5.44E5 2.66ES 5.64E6 5.39E7 1.58E6 1.67E10 1.38ES 1.81E3 2.83ES 5.27E7 3.66E4 1.69ES S.SSE2 1.89E5 2.18E7 3.98E4 1.01E10 1.35E10 2.59E3 2.91E5 6.16E4 9,01E7 5.13E7 1.61ES 1.01ES 5.60ES 6.86ES 4.33EB 1'SE11 2.59E3 2.91ES 3.42E4 KIDNEY 2.59E3 2.91E5 1.35E4 1.36ES 9.41ES 3e74E5 1'6ES 1'SE6 2.89E7 4.80ES 7.75E9 4.69E9 8.91E6 2'6E2 2.17E4 2.83E6 2.3863 7.99ES 2.58E5 1.29E7 1.57E10 9.28E7 2.20EB 2.76E6 5.31E9 4.59E9 5.74E4 8.89E4 1.30E7 2.34E4 T.BODY THYROID LUNG GI-LTI 2.59E3 2.59E3 2.91ES 8.79E4 1.40EB 2.91E5 1.03E7 9'2ES 9.53E7 2.03E9 1.78E9 1.14ES 1 SOE9 2'1E10 1'6E9 1.14E9 1'1E7 1.07E7 1.19E6 2.08EB 1.92EB 2.13EB 5.10E7 5.40EB 1.33E10 1.44ES 1'2ES 9.89ES 6'2ES 3.24E9 6.23EB mrem/yr per pci/m~004152LL 61 Unit 1 ODCM Revision 13 December 1993 i"'qp'h 1I~

NUCLIDE H 3 C 14 Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE'.97ES 2.00ES 1'6ES 3.17E8 9.96E9 6.05E11 1.18E6 3.55E5 4 04E7 1,00E6 4.67E9 6.36E9 1.29E8 1.98E3 1.97E5 3.29E7 3.36E4~IIVR 2.26E3 1.79E5 3.13ES 1.38ES 2.96ES 3'SE7 1.67ES 1.01E9 3.77E5 1.98E5 6.14E6 5.78E7 1.74E6 1.11E10 8.70E9 1.61E5 9.97E2 1.33E5 1.38E7 3.88E4 2.26E3 1.79E5 4.64E4 5.97E7 3~22E7 1.13ES 6.90E7 3.69E8 4.56E8 2.86E8 1.48E11 2.55E5 1.06E5 1'7E6 3.31E7 5.30ES 9.08E9 5.70E9 8.42E6 2.63E2 1.51E4 1.77E6 2.32E3 2.26E3 1.79E5 2.77E4 1.90E10 2.56ES TABLE 3-22 DOSE AND DOSE RATE VALUES-VEGETATION m'~modem e pci/sec T.BODY'HYROID ADULT KIDNEY 2.26E3 1.79ES 1.02E4 9.31E7 6.75E8 5.92E5 1.95E5 1.39E7 9.91E7 3.03E6 3.59E9 2.95E9 5.49E4 6.19E4 8.16E6 2.27E4 LUNG 2.26E3 GI-LLX 2'6E3 1.79E5 1.79E5 6.15E4 7.69E7 1.17E7 9.58ES 7.91E7 8 27E7 1.02E9 1.19E9 9.81E8 6.24E8 3.14E9 6'6ES 1.60E9 1.75E10 1.20E9 1.20E9 1.42E7 1.53E7 1.56E6 1.94E8 1.68E8 9.25E4 2 65E8 7.32E7 5.09ES 1.11E10 1.86ES mrem/yr per pci/m~004152LL 62 Unit 1 ODOM Revision 13 December 1993 l

TABLE 3-23 PARAMETERS FOR THE EVALUATION OF DOSES TO REAL MEMBERS OF THE PUBLIC FROM GASEOUS AND LIQUID EFFLUENTS~Pathwa..Paraeetera Fish U (kg/yr)-adult Value 21 Reference Reg.Guide 1.109 Table E-5 Fish Shoreline D~(mrem/pCi)

U (hr/yr)-adult-teen Each Radionuclide 67 67 Reg.Guide 1.109 Table E-11 Reg.Guide 1.09 Assumed to be same as Adult Shoreline Each Radionuclide (mrem/hr per pCi/mi)Reg.Guide 1.109 Table E-6 Inhalation DFA Each Radionuclide Reg.Guide 1.109 Table E-7 004152LL 63 Unit 1 ODCM Revision 13 December 1993 eg 1I NINE MILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAIVlPLING LOCATIONS TABLE 5.1 Type of Sam le Radioiodine and Particulates (air)Radioiodine and Particulates (air)Radioiodine and Particulates (air)Radioiodine and Particulates (air)Radioiodine and Particulates (air)*Map Location Collection Site Env.Pro ram No.1 Nine Mile Point Road North (R-1)Co.Rt.29 5 Lake Road (R-2)Co.Rt.29 (R-3)Village of Lycoming, NY (R-4)Montario Point Road (R-5)L tion 1.8mi I 88'1,1 mi I 104o ESE 1.5 mi I 132'E 1.8mi I 143~SE 16.4 mi I 42o NE Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)10 12 13 14 15 16 17 18 North Shoreline Area (75)North Shoreline Area (76)North Shoreline Area (77)North Shoreline Area (23)JAF East Boundary (78)Rt.29 (79)Rt.29 (80)Miner Road (81)Miner Road (82)Lakeview Road (83)Lakeview Road (84)Site Meteorological Tower (7)Energy Information Center (18)0.1mi@5~N 0.1 mi I 25o NNE 0.2 mi I 45o NE 0.8 mi I 70~ENE 1.0 mi I 90o E 1.1 mi I 115~ESE 1.4 mi I 133~SE 1.6 mi I 159o SSE 1.6 mi I 181~S 1.2 mi I 200~SSW 1.1 mi I 225o SW 0.7 mi I 250o WSW 0.4 mi I 265~W*Map=See Figures 5.1-1 and 5.1-2 004152LL 64 Unit 1 ODCM Revision 13 December 1993 k 4 if 0 Y i~k'r NINE IVIILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS TABLE 5.1 (Continued)

Type of am le*Map Location Collec ion Site Env.Pro ram No.L ation Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation,(TLD)

Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Surface Water Surface Water 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 North Shoreline (85)North Shoreline (86)North Shoreline (87)Hickory Grove (88)Leavitt Road (89)Rt.104 (90)Rt.51A (91)Maiden Lane Road (92)Co.Rt.53 (93)Co.Rt.1 (94)Lake Shoreline (95)Phoenix, NY Control (49)S.W, Oswego, Control (14)Scriba, NY (96)Alcan Aluminum, Rt.1A (58)Lycoming, NY (97)New Haven, NY (56)W.Boundary, Bible Camp (15)Lake Road (98)OSS Inlet Canal (NA)JAFNPP Inlet Canal (NA)0.2 mi I 294~WNW 0.1 mi I 315'W 0.1 mi I 341 o NNW 4.5 mi I 97~E 4.1 mi I 111 ESE 4.2 mi I 135o SE 4.8 mi I 156 SSE 4.4 mi I 183o S 4 4 mi I 205o SSW 4.7 mi I 223~SW 4.1 mi I 237~WSW 19.8 mi I 163~S 12.6 mi I 226o SW 3.6 mi I 199'SW 3.1 mi I 220~SW 1.8 mi I 143'E 5.3 mi I 123~ESE 0.9 mi I 237~WSW 1.2 mi I 101~E 7.6 mi I 235o SW 0.5 mi I 70o ENE (NA)=Not applicable

• Map=See Figures 5.1-1 and 5.1-2 004152LL 65 Unit 1 ODCM Revision 13 December 1993

NINE MILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS TABLE 5.1 (Continued)

Type of Sam le*Map Lo a i n Collec ion Si e Env.Pr ram No.Lo ai n Shoreline Sediment Fish Fish Fish Milk Milk Milk Milk Milk Milk Milk (CR)Food Product Food Product Food Product Food Product Food Product 40 41 42 43 44 45 0 47 64 65 66 73 48 49 50 51 52 Sunset Bay Shoreline (NA)NMP Site Discharge Area (NA)NMP Site Discharge Area (NA)Oswego Harbor Area (NA)Milk Location¹50 Milk Location¹7 Milk Location¹65 Milk Location¹55 Milk Location¹60 Milk Location¹4 Milk Location (Woodworth)

Produce Location¹6++(Bergenstock)(NA)Produce Location¹1++(Culeton)(NA)Produce Location¹2++(Vitullo)(NA)Produce Location¹5++(C.S.Parkhurst)(NA)Produce Location¹3++(C.Narewski)(NA)1.5 mi 5 80~E 0.3 mi 5 315'W (and/or)0.6 mi 5 55~NE 6 2 ml y 235o SW 8.2 mi 5 934 E 5.5 mi 5 107~ESE 17.0 mi 5 220~SW 9.0 mi 5 95~E 9.5 mi 5 90~E 7.8 mi 5 113~ESE 13.9 mi 5 234~SW 1.9 mi 5 141~SE 1.7 mi@96~E 1.9 mi 5 101~E 1.5 mi y 114o ESE 1.6 mi@84o E*Map=(NA)The Jones milk location has been deleted due to the herd being sold.(Map location¹46.)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.Not applicable Control Result (location) 004152LL 66 Unit 1 ODOM Revision 13 December 1993

NINE IVIILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONIVIENTAL MONITORING PROGRAIVI SAMPLING LOCATIONS TABLE 5.1 (Continued)

Type of am I*Map Loca ion Collec ion i Env.Pr ram No.L ion Food Product Food Product (CR)Food Product (CR)Food Product Food Product Food Product Food Product Food Product (CR)Food Product Food Product Food Product 53 54 55 56 57 58 59 60 61 62 63 Produce Location¹4++(P.Parkhurst)(NA)Produce Location¹7++(Mc Millen)(NA)Produce Location¹8'Denman)(NA)Produce Location¹9 (O'onnor)(NA)Produce Location¹10 (C.Lawton)(NA)Produce Location¹11 (C.R.Parkhurst)(NA)Produce Location¹12 (Barton)(NA)Produce Location¹13 (Flack)(NA)Produce Location¹14 (Koeneke)(NA)Produce Location¹15 (Whaley)(NA)Produce Location¹16 (Murray)(NA)2.1 mi I 110~ESE 15.0 mi I 223 SW 12.6 mi I 225 SW 1.6 mi I 171~S 2.2 mi I 123 ESE 2.0 mi I 112~ESE 1.9 mi I 115 ESE 15.6 mi I 225 SW 1.9 mi I 95o E 1.7 mi I 136'E 1.2 mi I 207 SSW*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.(NA)=Not applicable CR=Control Result (location) 004152LL 67 Unit 1 ODCM Revision 13 December 1993

FIGURE 5.1-1 004152LL 68 Unit 1 ODCM Revision 13 December 1993

FIGURE 5.1-2 004152LL 69 Unit 1 ODCM Revision 13 December 1993 E 4t

~saldteFI IISI 24 SCALE OF hlILES LEGEND t e.tt III Courtly Lltloe..Tees Llsal..Cky A VNale Uaea..................

hei leoode..ENVI~NTAL~K...........Q LOCA II OSS FIGURE 5.1-2 NINE MILE POINT OFF-SITE MAP (1 2/'93)laldvde d F28'll.lated vde 16'Xr w~\Os<<odd Ca<<ass ead6.Ol<<WS4 S S.Sat<<a stoa Sdd Stat<<e ledea 61 Seder 4 Steel States Sleet i<<a L AEE ONT ARIO 42 2 Al 5l I 63 3 4 44 33 laae asset~4 4~Il ssellaas avs devel Ot lsl Seassl S g 5 See<<e Total 41 4Attavv Sle IS sv<<tv 34 ll 48 l~I 5'g 4 g t<<v<<<<l eltt<<es~4 I<<~'v~tttl 4 I~III lee I<<<<4 v Ie I<<~I gatv>>Yeast~~~eve SI Od'dCO I%I II IIII<<\I 4 ee 4~<<~OS+QGgO 5%l<<<<l~'i<<.C Is II I wtIITIOed l N E loess St<<W<<tl B A I Wed~v S I~ealvee n~.s Ovate~4~<<I~Sf Ygsa A Y-6 N 66 I l.M<<d llleslcd~<<II II~l.i c X I~a 44 la C , I A JJ sP,f II II, 7p'

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FIGURE 5.1.3-1 004152LL 70 Unit 1 ODCM Revision 13 December 1993

APPENDIX A LIQUID DOSE FACTOR DERIVATION 004152LL 71 Unit 1 ODCM Revision 13 December 1993 f')V;" ff~g Appendix A Liquid Effluent Dose Factor Derivation, A~A (mrem/hr per pCi/ml)which embodies the dose conversion factors, pathway transfer factors (e.g , bioaccumulation factors)g pathway usage factors, and dilution'factors for the points of pathway origin takes into account the dose from ingestion of fish and drinking water and the sediment.The total body and organ dose conversion factors for each radionuclide will be used from Table E-11 of Regulatory Guide 1.109.To expedite time, the dose is calculated for a maximum individual instead of each age group.The maximum individual dose factor is a composite of the highest dose factor A of each nuclide i age group a, and organ t, hence A,.It should be noted that the fish ingestion pathway is the most significant pathway for dose from liquid effluents.

The water consumption pathway is included for consistency with NUREG 0133.The equation for calculating dose contributions given in section 1.3 requires the use of the composite dose factor A;, for each nuclide, i.The dose factor equation for a fresh water site is: Kit-l,t~](DFL)~+o~~Dw+69.3 UW e~(1-e)(DFS),)-ii<(>.>(4)Where: Ko U Is the dose factor for nuclide i, age group af total body or organ t, for all appropriate pathways, (mrem/hr per pCi/ml).Is the unit conversion factor, 1.14E5=1E6pC1/pCi x 1E3 ml/kg-:-8760 hr/yr.Water consumption (1/yr)i from Table E-5 of Reg.Guide 1.109.Ug Fish consumption (Kg/yr);from Table E-5 of Reg.Guide 1.109.U, (BF)i Sediment Shoreline Usage (hr/yr);from Table E-5 of Reg.Guide 1.109.Bioaccumulation factor for nuclide, i, in fish, (pCi/kg, per pCi/1), from Table A-1 of Reg.Guide 1.109.(DFL)hl (DFS))Dose conversion factor for age, nuclidei ii group a, total body or organ t, (mrem/pCi);

from Table E-ll of Reg.Guide 1.109.Dose conversion factor for nuclide i and total body, from standing on contaminated ground (mern/hr per pCi/m');from Table E-6 of Reg.Guide 1.109.D Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake for the adult water consumption.

This is the Metropolitan Water Board, Onondaga County intake structure located west of the City of Oswego;(unitless).

004152LL 72 Unit 1 ODCM Revision 13 December 1993 4%ps vent, D, 69.3 Appendix A (Cont'd)Dilution factor fx'om the near field area within one quarter mile of the release point to the shoreline deposit (taken at the same point where we take environmental samples 1.5 miles;unitless).

conversion factor.693 x 100, 100 K, (L/kg-hr)*40*24 hr/day/.693 in L/m~-d, and K,=transfer coefficient from water to sediment in L/kg per hour.Average transit time required for each nuclide to reach the point of exposure for internal dose, it is the total time elapsed from release of the nuclides to either ingestion for water (w)and fish (f)or shoreline deposit (s), (hr).tb Length of time the sediment is exposed to the contaminated water, nominally 15 yrs (approximate midpoint of facility operating life), (hrs).decay constant for nuclide i (hr').Example Calculation Shore width factor (unitless) from Table A-2 of Reg.Guide 1.109.r~For I-131 Thyroid Dose Factor for an Adult from a Radwaste liquid effluents release: (DFS))(DFL)L, BF)Ur D D,'U, W 2.80E-9 1.95E-3 15 21 40 12 12 0.3 5.5 mrem/hr per pCi/m~mrem/pci t~pCi/Kg per pCi/L t<Kg/yr tb 30 hrs.(w=water)24 hrs.(f=fish)1.314E5 hrs.(5.48E3 days)unxtless U=730 L/yr unitless Ko=1.14E5 Ci Ci ml k hr/yr (hr/yr)3.61E-3hr'rs (s=Shoreline Sediment)These values will yield an A, Factor of 6.79E4 mrem-ml per pCi-hr as listed in Table 2-4.It should be noted that only a limited number of nuclides are listed on Tables 2-1 to 2-8.These are the most common nuclides encountered in effluents.

If a nuclide is detected for which a factor is not listed, then it will be calculated and included in a revision to the ODOM.0 In addition, not all dose factors are used for the dose calculations.

A maximum individual is used, which is a composite of the maximum dose factor of each age group for each organ as reflected in the applicable chemistry procedures.

004152LL 73 Unit 1 ODCM Revision 13 December 1993 0 I APPENDIX B PLUME SHINE DOSE FACTOR DERIVATION 004152LL 74 Unit 1 ODCM Revision 13 December 1993 P!

APPENDIX B For elevated releases the plume shine dose factors for gamma air (B,)and whole body (V,), are calculated using the finite plume model with an elevation above ground equal to the stack height.To calculate the plume shine factor for gamma whole body..doses, the gamma air dose factor is adjusted for the attenuation of tissue, and the ratio of mass absorption coefficients between-tissue and air.The equations are as follows: Gamma Air B,=,E,~KE I Re V, Where: K'onversion factor (see below for actual value).mass absorption coefficient (cm/gK air for B<<ti.ssue for V,)V, Energy of gamma ray per disintegration (Mev)average wind speed for each stability class (s), IE downwind distance (site boundary, m)sector width (radians)subscript for stability class I function=I,+k?i for each stability class.(unitless, see Regulatory Guide 1.109)Fraction of the attenuated energy that is actually absorbed in air (see Regulatory Guide 1.109, see below for equation)Whole Bod Vi 1.11SB;e PEta Where: t~=tissue depth (g/cd)SF shielding factor from structures (unitless) 1.11=Ratio of mass absorption coefficients between tissue and ai r.Where all other parameters are defined above,.'K=conversion factor[3.7 E10 midis 1.6 E-6 erq]Ci-sec[1293 g]Mev[100~er]g-rad.46~k~~PE Where: p=mass attenuation coefficient (cd/g;air for B<<tissue for V<)p,=defined above 004152LL 75 Unit 1 ODCM Revision 13 December 1993

<S APPENDIX B (Cont'd)There are seven stability classes, A thru F.The percentage of the year that each stability class occurs is taken from the U-2 FSAR.From this data, a plume shine dose factor is calculated for each stability class and each nuclide, mgltiplied by its respective fraction and then summed.The wind speeds corresponding to each stability class are, also, taken from the U-2 FSAR.To confirm the accuracy of these values, an average of the 12 month wind speeds for 1985, 1986, 1987 and 1988 was compared to the average of the FSAR values.The average wind speed of the actual data is equal to 6.78 m/s, which compared favorably to the FSAR average wind speed equal to 6.77 m/s.The average gamma energies were calculated using a weighted average of all gamma energies emitted from the nuclide.These energies were taken from the handbook"Radioactive Decay Data Tables", David C.Kocher.The mass absorption (p,)and attenuation (p)coefficients were calculated by multiplying the mass absorption (p,/p)and mass attenuation (p/p)coefficients given in the Radiation Health Handbook by the air density equal to 1.293 E-3 g/cc or the tissue density of 1 g/cc where applicable.

The tissue depth is 5g/cm~for, the whole body.The downwind distance is the site boundary.004152LL 76 Unit 1 ODCM Revision 13 December 1993 c)~'4.4,e(,~ll SAMPLE CALCULATION APPENDIX B (Cont'd)Ex.Kr-89 F STABILITY CLASS ONLY-Gamma Air-DATA E p p e cr,~2.22MeV k~~=.871 K~.46 2 943 E-3m pa V=5.55 m/sec 5.5064E-3m'

=644m.39 19m.......vertical plume spread taken from"Introduction to Nuclear Engineering", John R.LaMarsh'-I Function Uc, Ii Ig a B<.06.33.45 I,+kIq.33+(.871)(.45)=-72 dis~0.46 Ci-sec Mev er s 2.943E-3m'.22Mev

.72 (sQ)(g/m~)(ercro)(5.55 m/s)(.39)(644m)(g-rad)1.55(-6)rad s 3600 s hr 24 h d 365 d Ci/s (~1E6 C1)Ci 1E3mrad rad 2.76 (-2)mead r pCi/sec-(.0253 cm~/g)(5g/cd)1.11 (.7)2.76(-2)mrad rI[e)pci/secJ 1.89(-2)mead r pCi/sec NOTE: The above calculation is for the F stability class only.For Table 3-2 and procedure values, a weighted fraction of each stability class was used to determine the B>and V, values.004152LL 77 Unit 1 ODCM Revision 13 December 1993

APPENDIX C DOSE PARAMETERS FOR IODINE 131 and 133, PARTICULATES AND TRITIUM 004152LL 78 Unit 1 ODCM Revision 13 December 1993 k~~~C APPENDIX C DOSE PARAMETERS FOR IODINE-131 AND-133i PARTICULATES AND TRITIUM This appendix contains the methodology which was used to calculate the organ dose factors for Z-131, I-133, particulates, and tritium.The dose factori Rwas.calculated uaCng the methodology outlined in NUREG-0133.

The radioiodine and particulate Technical Specification (Section 3.6.15)is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure occurs, i.e., the critical receptor.Washout was calculated and determined to be negligible.

g values have been calculated for the adult, teen, child and infant age groups for all pathways.However, for dose compliance calculations, a maximum individual is assumed that is a composite of highest dose factor of each age group for each organ and pathway.The methodology used to calculate these values follows: C.1 Inhalation Pathwa Q(I)where: K'BR)~(DFA)g, Q(Z)dose factor for each identified radionuclide i of the organ of interest (units=mrem/yr per pCi/m~)g K'constant of unit conversion, 1E6 pCi/pCi (BR)~(DFA)1F Breathing rate of the receptor of age group a, (units=m~/yr);The inhalation dose factor for nuclide i, organ j and age group a, and organ t (units=mrem/pci).The breathing rates (BR)~for the various age groups, as given in Table E-5 of Regulatory Guide 1.109 Revision 1, are tabulated below.A e Grou a Breathin Rate m~r Infant;Child Teen Adult 1400 3700 8000 8000 Inhalation dose factors (DFA)>for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109 Revision 1.004152LL 79 Unit 1 ODCM Revision 13 December 1993 1 V Eo+<

C.2 Ground Plane Pathwa APPENDIX C (Cont'd)W(G)K'KSF DFG-l,t 1-e Where: Q(G)K'Dose factor for the ground plane pathway for each identified radionuclide i for the organ of interest (units=m~-mrem/yr per pCi/sec)A constant of unit conversion, lE6 pCi/pCi A constant of unit conversion, 8760 hr/year The radiological decay'onstant for radionuclide i, (units~sec')t The exposure time, sec, 4.73E8 sec (15 years)(DFG)~~The ground plane dose conversion factor for radionuclide i;(units=mrem/hr per pci/m~)SF The shielding factor (dimensionless)

A shielding factor of 0.7 is discussed in Table E-15 of Regulatory Guide 1.109 Revision 1.A tabulation of DFG, values is presented in Table E-6 of Regulatory Guide 1.109 Revision l.004152LL 80 Unit 1 ODCM Revision 13 December 1993 i'I lk APPENDIX C (Cont'd)C.3 Grass-Cow or Goat-Milk Pathwa Q(C)~K'F r D.L~ff+(~1-f f)(e e-l,,t~-l,t, Yz Y, Where: Q(C)K'ose factor for the cow milk or goat milk pathway, for each identified radionuclide i for the organ of interest, (units m2-mrem/yr per pCi/sec)A constant of unit conversion, 1E6 pCi/pCi The cow's or goat's feed consumption rate, (units~Kg/day-wet weight), The receptor's milk consumption rate for age group a, (units liters/yr)

Y, The agricultural productivity by unit area of pasture feed grassy (units~kg/m2)The agricultural productivity by unit area of stored feed, (units~kg/m2)The stable element transfer coefficients, (units=pCi/liter.

per pCi/day)Fraction of deposited activity retained on cow's feed grass (DFL)LLThe ingestion dose factor for nuclide i, age group a, and total body or organ t (units=mrem/pCi)The radiological decay constant for radionuclide i, (units sec-1)The decay constant for removal of activity on leaf and plant surfaces by weathering equal to 5.73E>>7 sec-1 (corresponding to a 14 day half-life)

The transport time from pasture to cow or goat, to milk, to receptor, (units=sec)The transport time from pasture, to harvest, to cow or goat, to milk, to receptor (units=sec)004152LL 81 Unit 1 ODCM Revisi.on 13 December 1993

'4,~p I i Hg J'k P t.44~~t APPENDIX C (Cont'd)0'raction of the year that the cow or goat is on pasture (dimensionless)

Fraction of the cow feed that is pasture grass while the cow is on~asture (dimensionless)

Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds;Following the development in Regulatory Guide 1.109 Revision 1, the value of f, is considered unity in lieu of site specific information.

The value of f~is 0.5 based on 6 month grazing period.This value for f, was obtained from the environmental group.Table C-1 contains the appropriate values and their source in Regulatory Guide 1.109 Revision 1.The concentration of tritium in milk is based on the airborne concentration rather than the deposition.

Therefore, the Rz(C)is based on X/Q: Rp(C)K K F~QP~(DFL)

~0~75 (0~5/H)Where: Rg(C)H 0.75 Dose factor for the cow or goat milk pathway for tritium for the organ of interest, (units=mrem/yr per pci/m~)A constant of unit conversion, 1E3 g/kg Absolute humidity of the atmosphere, (units g/m~)The fract ion of total feed that is water 0.5 The ratio of the specific activity of the feed grass water to the atmospheric water Other values are given previously.

A site specific value of H equal to 6.14 g/m~is used.This value was obtained from the environmental group using actual site data.004152LL 82 Unit 1 ODCM Revision 13 December 1993 8'*I~9 Jt la l(c a Jfp ,~

C.4 Grass-Cow-Meat Pathwa APPENDIX C (Cont'd)-litr g(C)=K'F r DFL[~f1+(~1-f f)(e e: (1)+1~)[Yp ,Y, Q(M)Dose factor for the meat ingestion pathway for radionuclide i for any organ of interest, (units~m~-mrem/yr per pci/sec)Fr The stable element transfer coefficients, (units pCi/kg per pCi/day)The receptor's meat consumption rate for age group a, (units~kg/year)The transport time from harvest, to cow, to receptor, (units=sec)The transport time from pasture, to cow, to receptor, (units=sec)All other terms remain the same as defined for the milk pathway.Table C-2 contains the values which were used in calculating g(M).The concentration of tritium in meat is based on airborne concentration rather than deposition.

Therefore, the R~(M)is based on X/Q.Rg(M)=K'KFQP~(DFL)~

[0.75(0.5/H)

)Where: R~(M)~Dose factor for the meat ingestion pathway for tritium for any organ of interest, (units~mrem/yr per pCi/m')All other terms are defined above.C.S Ve etation Pathwa The integrated concentration in vegetation consumed by man follows the expression developed for milk.Man is considered to consume two types of vegetation (fresh and stored)that differ only in the time period between harvest and consumption, therefore:

R(V)=K'(l,+1.)-A,t-l,t(DFL)~U",Fe+U',F,e 004152LL 83 Unit 1 ODCM Revision 13 December 1993 Nl'V N I'Xi' APPENDIX C (Cont'd)Where: Q(V)K'L Us Fg Fq Yv Dose factor for vegetable pathway for radionuclide i for the organ.af interest, (units=m~-mrem/yr per pCi/sec)A constant of unit conversion, 1E6 pCi/pCi The consumption rate of fresh leafy vegetation by the receptor in age group a, (units kg/yr)The consumption rate of stored vegetation by the receptor in age group a (units kg/yr)The fraction of the annual intake of fresh leafy vegetation grown locally The fraction of the annual intake of stored vegetation grown locally The average time between harvest of leafy vegetation and its consumption, (units=sec)The average time between harvest of stored vegetation and its consumption, (units~sec)The vegetation areal P density, (units=kg/m~)All other factors have been defined previously.

Table C-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109 Revision 1.In lieu of site-specific data, values for Fz and F, of, 1.0 and 0.76, respectively, were used in the calculation.

These values were obtained from Table E-15 of Regulatory Guide 1.109 Revision 1.The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition.

Therefore, the Rz(V)is based on X/Q:+(V)=K K[U~sfa+U~fi](DFL)w 0~75(0~5/H)Where: Rg (V)dose factor for the vegetable pathway for tritium for any organ of interest, (units=mrem/yr per pCi/m).All other terms are defined in preceeding sections.004152LL 84 Unit 1 ODCM Revision 13 December 1993

TABLE C-1 Parameters for Grass-(Cow or Goat)-Milk Pathways Parameter a<(kg/day)(DFL)>(mrem/pCi)

F (pCi/liter per pCi/day)Y, (kg/m~)Y~(kg/m)Value 50 (cow)6 (goat)1.0 (radioiodines) 0.2 (particulates)

Each radionuclide Each stable element 2.0 0.7 Reference Re.Guide 1.109 Rev.1 Table E-3 Table E-3 Table E-15 Table E-15 Tables E-11 to E-14 Table E-1 (cow)Table E-2 (goat)Table E-15 Table E-15 t~(seconds)t~(seconds)U (liters/yr) 1.73 x 10'2 days)330 infant 330 child 400 teen 310 adult Table E-15 Table E-5 Table E-5 Table E-5 Table E-5 7.78 x 10~(90 days)Table E-15 004152LL 85 Unit 1 ODCM Revision 13 December 1993

TABLE C-2 Parameters for the Grass-Cow-Meat Pathway Parameter F, (pCi/Kg per pCi/day)U (Kg/yr)(DFL)@(mrem/pCi)

Y (kg/mi)Y, (kg/m)tb (seconds)tf (seconds)Qr (kg/day)Value 1.0 (radioiodines) 0.2 (particulates)

Each stable element 0 infant 41 child 65 teen 110 adult Each radionuclide 0.7 2.0 7.78E6 (90 days)1.73E6 (20 days)50 Reference Re.Guide 1.109 Rev.1 Table E-15 Table E-15'I Table E-1 Table E-5 Table E-5 Table E-5 Table E-5 Tables E-11 to E-14 Table E-15 Table E-15 Table E-15 Table E-15 Table E-3 004152LL 86 Unit 1 ODCM Revision 13 December 1993

TABLE C-3 Parameters for the Vegetable Pathway Parameter r (dimensionless)(DFL)>(mrem/pCi)

U"), (kg/yr)-infant-child-teen-adult U')~(kg/yr)-infant-child-teen-adult t(seconds)t(seconds)Y(kg/m~)Value 1.0 (radioiodines) 0.2 (particulates)

Each radionuclide 0 26 42 64 0 520 630 520 8.6E4 (1 day)5.18E6 (60 days)2.0 Reference Re.Guide 1.109 Rev.1 Table E-1 Table E-1 Tables E-11 to E-14 Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-15 Table E-15 Table E-15 004152LL 87 Unit 1 ODCM Revision 13 December 1993

APPENDIX D DIAGRAMS OF LIQUID AND GASEOUS TREATMENT SYSTEMS AND MONITORING SYSTEMS 004152LL 88 Unit 1 ODOM Revision 13 December 1993

~'l~*r<>,tp yg'ted%w C PIPING INSTRUHENT ANO EOUIPHENT SYHBOLS V~AV~YQQ~WL~asl i<<sees na nial D teat I I so I~~sH t>>K~LD<<Dates<<I IIOS<<Dao<<lowe oss~I<<all~>>IC awl~Ke<<D ts>>D 0 eel~~<<s~<<>>Ia IK 0>>K k~SK~IC L LK I IC~SK th I IK IK e<<}el~l K Ke LC SCt K ete ste~I I I[~8 CI~I ta tl~I oLI a<I}I K!Is~tl~I IO Lt~I~s I 0 Kt Ks~I I~~I~f~I W St<<CI~CI>>I Otl~K~I~II~I~II tl~os I II I~>>%~~t~~I I IIL~I s~IL<a Data ossa<<a~lessee lotto leil (KCS Lect CKCL FS I atoll<<lf ICallll H>>I-SKI<<<oe KKK~st<le a Kaw Sal>>e~00 sse/teal ths l>>ca taai chs)Sa<<eai Cha ess<<t<<cs e<<K LIWSSL lsn ICCW>>e loco lssl<<stol le%11%al~.I IKI<<OK calla aoo lal<<tcsf DCCI~ll<<h IK<<<KK t>>ala<Isow COSCC I lee Calls lee s<<<<tsl tcscfailoo sso cal I Isas OIKCII<<o KIIIO LIKI QS 011 Shel+Olatsssa II<<SPEC I A NOI<<S4 sssase<<IL SKS<

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atn~)oes<<<l>>SO (A~to>>et Sae Ks<<.<<>>sl K~I K C>>K 00<<CC.IKKsha E XPANss I ON JOINTS KS%<<S<<0 tie<<C~SKO sss~ea see<<tscsslosll ~~OK 110'sl~Ial oac Ksse<<sei I Lj LQtIIBOL VllLYESKBAUOK ~s sas~.V,-.T:~--~-g~l 0~tsossl 0 LSLL'steps<<~KL cowl Se~Isl~4 sess<cote%0 sea~assi al II ce<<sso<<<<s<<L D sw st ses I~tel I 4"~fo<<C.FIGURE PIP INC, IMSTINHEMT lUI0 OQIPIIIMT SYM80LS I~lashl S<<I Ital a B.~Ill Ksee ff a<<s~lo<<LSSD e<<K le'<<he<>>t<<sl I-A I OLJO I I selt stool It<At At<A aottsesw<c <owtH Co<<<oct<<<%<<oft NINE MILE I'OINT-UNIT 1 OFFSITE DOSE CALC.MANUAL 8 J RADIOA.IIVL WA~It III;I OSAI.;V.;II N to ooeet coot oov ooe Ieetl tees eV<<le,l~teltl ovtt lett ev<<le.let lo coeoeelc ltoea~ea Ieewel Wh No'w~CI~aoOO OLOOOel<<t~Itlte~vt et~tllooe tee ltlee ot clett<<ID tocteDIIo wtl Mice Iee tw ott Iccetl r-~\DIV O<<'LCN'4~I oe glels eel\I le)lceo a<<etc@I tl lite Cocle OL eo Oaf to Io loo,ve IOCIVtet<<Wtl lee el a+a//ta.Isle eoovotto wtl eve<<teel<<ttee oev oet eooooo teel Oltl LIC~I Decl tnt~~Iteo ow<<e~O Dt Wtl COV Octet et ltte~<<etc etIID Iee~e ooL~Leos octo IM<<4L VVI~COICCIV~ee~CO<<OIV Ito tve CIVCVOICO WIC~<<tate lite!cocle'tellto ~ettl IW elt oao wt te<<cc Vttl CttttCIOI tee osw tet Ie<<OI W IOCI e~tW eeI I lie IOIIC tote~oe etL Coo cello~I I eol tello I~Catt<<<<ISO eetlt tteot Ccctol Iee tello tee o<<ao wt octt Itlo lee ow oet~ettl evee IIV<<te~Sw oet~Ioel DV IIIitttIS Iee~L~e ett FIGURE D RADIOACTIVE MASTE DISPOSAL SYSTEH~CCOGAAA uOSCOSNÃCCOWKII CORCIOCCATCOCO NINE MILE POINT-UNIT 1 OFFSITE DOSE CALC.MAKUAL D-1 'g~V MAIN CONDENSER AIR REMOVAL AND OFF CAS SYSTEM II-=), g l~~>II'a.adeem I AIIA\~~IA I0%AI~IAI~A~t~~I A WAA~&IAAA IA%IA~Q IgŽII I~~AI~Il.~~\WW I A~l~I A lj o~I I AI AA~.~~~A%II 1~, II%AA tAI~I K I A I I~~~wa IAM f IGUAE D-1 SIEAH PACKING EKHAUSTER AHO RECOHBIHER SYSTEH MAOIAAA MOHAWIC POWtH CONPOHA'IIOM NINE MILF POINT-UNIT l OFFSIDE DOSE CALC.MANUAL A' REACTOR BUILDING VENTILATION SYSTEM C7 I LL)~ra ac~a I I Qt a eNSS gee a<<rises O:-.4:pg)-) --ta)-ty-)erl.)~~)P<Qn)-Qo(-@-~--Q+)=a=.m.)")I>>el~E>><<C rill~I>>ac Elree ae awr We 4<<te e'era 0~a~ea oa N alr<<area~eaes I e lre~l<<e~IN'r lre LQ~l<<e.I>>'<<Ira II<<g~<<'1 e w 1 rr<<II w Isa>>a Il<<ll w'eos e<<elena'ere II ee a>>ae<<~lweala Ec a (I.))).=.))3 El~<<e~<<e~~~~~~~y 4.~~~~~~~~b a rl aa ra~er waaaa~ease Ie)e)ii'1eil 1 ra 1>>Liaaw 1 a)Ir V~e>>I I~<<T r EL c<<e,>>I'roe e<<c.nr sees OEI I<<se wl I<<er I<<elae I see aee hg r<<e eeL~Walla'aaa~eel J<<I~Iae.ace c, IN'I>><<e r%El'ee<<aa<<rr~'i.P.~~sa I 1~I sae le aea<<<<<<'<<o oa o es F)GU))E I)-7 I REACTOR BUILDING VERT ILAT ION STSTEH 0-3)IIAi)A)lA LJOHJWK)IOW))1 1 OIZ)I@HA)IQ)J NINE MILE POINT-UNIT 1 OI'F SITE DOSE CALC.MANUAL \I+'I WASTE DISPOSAL BUILDING VENTILATION SYSTEM~eke Igf akke~A ke k k Pl~tk>>eat I&I'<<L kk&I ket 4--~V>>l I)~.'III t.e e 3".744Pk kk It taa t)~ek<<t 3~k Ie-e-3 3 ke~I e e I~k<<at~~k~Ikitek~~J I kae ak Lk lkaklkt Ql>>>>k>>~ke k II I~IF/Q 0 3 h l,eg YAAI I~I'k@e~(t>>a kt>>taa k Att Q>>,......~Qt~tea I~A>><<~k k kk~lt'Ak~~r Q>>~~I~I~akk eit f>><<kkt I>>vC 4'~u~Vrp~J Lh+.Q f I+A~ktk.'&gf Ik I>>~~I>>Ill Itt<<1+1'<<t att I>>akk iat F~~ekki H kl~, te>>t>>tklk tkkkt~I~Iet~tk keg k~A>>t Ik tikke tk I~L k.'II<<i.>>kt~kk~gK stk tkakk kk.Ia ka tk k Ik~~~l h Tll V.----S 0----'IWIk kkl FIGURE p-J IIASTE 0ISPOSAL BVILOING VENTILATION SYSILH HIAtiAAA AIOI<<AWK VOr<<LH C041'OHAlK)H NINE MILE POINT-UNIT 1 0 F F S I T E D 0 S E C A L C I1 A NU A I.0-4 ,C'I J a 4 ft STACK-PLAN AND ELEVATION h,AM CLRYATIO4 GRAPHIC PLATfoN4~LLfRX, I, I'I I I I I.(I PLAT1CRM~~4RRQ.Ieo III N CTIC PROaf PLATPORM I PLLTTG R LI coIc.twrelopa fLa50'4'rc tL.aaJO'OPP OL'5 LPCa oI~g~gLaeTIO<JlilL'0~TOP ae Qo I OVATION LOOKING+OATH 0-5 FIGURE D-5 SI I Stack NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 1 OFFSITR DON@CALCo MANUAL l OFF GAS BUILDING VENTILATION SYSTEM~tte Ws~etYI~K we h et~~ss ee~~~~q e~~~~Klltll~~le~Otl K'~stl~ott'e'tts ee la es~Is<<I e Jtl e'lOOC I e IIOOIK OslIOIte~<<LItte A&I 4'a es ketle~sett tg<>&t~les 4'IIAQAAA MOHOWOO OIOWLQ CG4OVVHAO<OOO NINE MILE POINT-UNIT 1 OFFSITE DOSE CALO.MANUAL 0-6 PRINTER CRT PARTCUl.ATE INPUT/DILUTION STATION IODINE DETECTOR8 (3)MAIN FRAME INSTRUMENTATION CABINET FIGURE 0-7 SImpIIfIed VIew of Hodel 400 Stacks Honltor NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 1 OFFSITE DOSE CALC.MANUAm.
• ISOKINETIC PROBE RN 21 11241 RAGEMS Dilutian RAG EMS Samph Return 112-52 112-13t Stack Sam 112-55 11243 3 112-132 112-57 112-56 OGESMS Intet 3 112-133 OGESMS Ou5el 112-30 J, P Figure D-8 Stack Sample and Sample Return NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 1 OFFSITE DOSE CALC.MANUAL 0-8 C-A il RAG EMS Inlttt OV5 112-173 OV3 112-169 OV2 112-167 PGV 112-106 112-110%Supply OV8 112-178 OV7 1 2-1 PI 112-21 OV4'l12-171 OFS1 112-101A L 112-130 112-51 OV1 OV13 112-165 112&RAG EMS Dilu Son Inlet OFC4 112-104 OFS4 112-04A PGV 112-107 OFG1 112-101 112-111 Pl 11.122 OFC3 112-103 OFS3 112-103A 112-116 OCF2 11-102 OFS2 112-102A 112-151 OV16 112-150 112-112 Pl'l1-23 OV12 Scunpte 112+7 Return RAG EMS Ou5et 112-113 Pl 112-124 112-117 112-118 Opl OV8 112143 Figure D-9 RAGEMS Dilution Schematic 11-44 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 1 OFFSITE DOSE CALC.MANUAL D-9 Pi'}
Pl 112-125 112-114 1FS1 112-129 1V3 1V4 112-183 112-185 2V3 112-199 2V4 112-201 3V16 1'12-218 11246 RahuQ Ttitium 112-73 112-72 112.74 3FS1 112-105A 1V1 1Q.1 12.181 2V1 112-1 3V3 112.7 Pl 3V1 3V5 g g 112-126 112-197 11245 11249 3CVI 112-105 1VS 112.186 1V6 2VS 112-187 112-202 2V6 112-203 2V11 112-208 11-76 1-78 3 3V4 11248 112-11 3V6 3V7 112-100 112-211 Pl 11247 1V11 112-192 Pl 11244 1V17 11219 3V11 112-215 3V1 112-217 108 112-%3P1 3V10 112-214 3V12 112-109 112-216 Fi ure D-10 RAGEMS Schematic NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 1 OFFSITE DOSE CALC.MANUAL 0-10 'EQ)t V' 11242 FS 11-93 112-10 11249 RN43A 67 11246 112-11 Inlet 112-146 112-147 112-59 FL1 112-58 112-148 12-149 11261 11260 112-152 P 1'l2-137 Pl 112-u u 112-62 63 112-153'l1264 1'l245 u u 112-154 112-161 11248 11244 FCV 112-91 112-137 112-163 112-134 PS2 11 44 11-35.112-135 112-139 112-138 1'l2-140 FS 112-94 Fl 11246 V/PI 11245 12-158 11 w 112-156 112-155 112-142 112-141 112-22 112-20 112-21 11240 112-159 112-13 112-157 112-19 112-1 12 112 14 11249 112-70 112-15 12-71 11207 11248 Fi ure D-11 112-12 OGESMS Schematic NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT'I OFFSITE DOSE CALC.MANUAL e Qh pl 4>>4 ATTACHNENT 2 7 NlAGARA'"'@;.;::",wxegg~e,~e;i'.;;.;.m~~t~),','~>-;..~~;~,.'.y~rt~g)r,;.;n~:~<<o'"'.g;:,>~@:No.-';I iver~jQCENSNG!DQCUMBgjCHANGEREQUEST'" p.UMQHA A'K'."~.',vg@",~@~;gym >;<g:-:.~,rg~j~~qw~ymj~yw:.~~~~~,>>, I<<4(D'.':".;0 g:"",:!.0 0 IN PArrr 1-/Nr77A7toN A.Affected Doc OPL Plans If Programs Page~of~g Unit 1 Q Unit2 Q Facitity Operating Ucense Q UFSAR Q Ste Emergency Phn (SEP)Q Technical Specifications Q QuaRy Assur Program d Q Secunty Phns (SPS)0 Environmental Prot Phn Q Rre Prot Program Otfsite Dose Cato Manual (ODM)Q IS Program Ran (ISI)Q IST Program Phn (IS7)Q Core Operating Umits Rept (COL)B.Descnpiion @permanent Q Tanporary, Errpectrrd Duratfo(L d rttt.d w~~enn~d We.$gZ 7-/OOCN, Pago h3 Section, Figure, Table D.Soutce of Change/References gas',r~f yy,to~r9, P'~~+it/I~~+.f~, MOM(.r~,~P~~/'s na~~cn(otl (rro~~Ž1 tdnrt/tn~d(~/r/g 7/p (n A d, (.(n 6(dDcitr.)'. NIP4EV41 Review g progninly eratuat fortrgahrty Rn(/rnrr ttacfred F Otiginato Q 0 gi/Q.PAR7'-RaVraW/APPROVAt. Date///4 9/y g 4SME(Prfnmacy Q NA Date B.ReSp Oig BranCh Manager (Pkeh5a/I ud,'3 Date C.Effectfvoness Reviow D.SORCQ NN E SRAB ea Q hN Q Attached hftghttL: MgDat>>:/g P/NgHo F.Phnt Mgr Q hat Q Obra/nod per MWRG41 G.NRC p&IRM1 Submitta/Require(9 NN Obta/ned per Doc Cotrersheot Q Obta/nod por MP4EV4f tartar NMlate: Q NRC AppTDate: PART~LZQEVTA77ON 4 OPL Only: Affected D ocuments Updated Q B.UFS Only: Need'Askuilt'r Affoct Documont Q C.Othen r 8 Q llrd SAR~-g/r Jqg PAR7'4-Ct.crlrRz tt.p tnooto'd into potont Doo,+R B.Q Not Yot tnooot'd into ontont Close Chango Tracfong Doc, App'd for Rtnr.C.Chsodby (Petrfretta() z I 77lG/7l.d.s &VI;,kicoip'.d;Rev:

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~"'"~"-'ev o I Q UFSAR A.Qualify As surrnce Program~Does the change(s)cease to satisfy the criteria of 10CFR50 Appendix 8 or educe SAR program commitments previously accepted by the NRC?Page~a S Q Yos QNo 8 Fire Prof@Son Program~Does the change(s)adversely affect the ability to acheve and maintain safe shutdownin the event of a lief QYoo QNo Q SITE FNERGENC Y PLAN~Does the change(s)decrease effectiveness of the SEP7~Does the SEP, as changed, cease to meet the standards of 10CFR50.47(b) and 10CFR50 Appendix E?Q Yos QNo Q Yes QNo Q SECURITY PLANS~Document~Does the change(s)decrease the effectiveness of the Physical Security Ran or Security Personnel Training and Quafiffcathn Plan prepared pursuant to 10CFR50.34(c) or 10CFR73't Does the change(s)decrease the effectiveness of the first four categories af informational Background, Generic Ranning Base, Licensee Planning Base, andlar responsibility matrix of the Safeguaids Contingency Plan prepared pursuant to 10CFR50.34(d) or 10CFR737 QYes QNo Q Yos QM~Q PROCESS CONTROL PROGRAM~Does the change(s)reduce Ihe overall conformance of the solidified waste product to existing criteria for solid wastes in accordance with Technical Specifications? Q Yos QNo gj ODCN~Does the change(s)reduce the accuracy of reliably of lhe dose cafcuhtions or setpoint determinations in accordance with Technical Speti5catfons7 Q Yes Q No BASIS~rA~v".i'rt'E'S 7 ere 0 diaz~.7.S.PaEPmea (Printltnitfal) ~liZMM>.Won~Page 12 NIP-LPP-01 Rev 02 4" lg.zf If No.~M U'!J R J!I apt I oi+FR.PRELIMINARY EVAL ATI N TlTLE: Revision 13 to the Unit 1 Offsite Dose Calculation Manual DESCRIPTION OF PROPOSED CHANGE:~Pennanen or Temporary 1 An wT hni I ifi i nmilkl i nw h R il i IEnvirnmn I M ni rin Pr r m.DOCUIVIENTS REVIEWED: 1 M m fr m B.Z h r k B.Th m A 2 1 AFETY IM A VAL ATI N A.Is the SAR affected?1.Does the proposal change the facility or procedures from their description in the SAR?(Yes(No)Thi h n n finf rm'n m i n w'hNRCR I i n nd7 hnical cifica nR uir n n doesn t v ri i f f iT r r in AR.a.Does the proposed change alter the design, function, or method of performing the function or a component, system, or structure described in the SAR?(YeslNo)Th han n u a finf rma ion ed n m ian e w h R R ulai n a Technical S'fic tion R irement a n inv lv an m nn m r ures describedin he SAR.b.Does the proposed change alter procedures discussed in the initial operations and organizational chapters of the FSAR or the other procedural-type commitments, such as the emergency plan and modes and sequences of plant operation described in the SARt Iyes~N~Th h n e n a finf rma'nba on om ian w h NRC R I T hni al fi'R ir en n r niza n ha mm nt u in in i FAR r o'n o ural-0041 58LL NIP-SEV%1 Rev 0 g" No, (-20 I NMP U RJ R Jl Page 2 of 4 FR.PRELIIVIINA Y EVAL (Cont'd)2.Does the proposal involve a test or experiment not described in the SAR?(Yes/~N)Th ch n eIs n finf rm n a n m I n w h R R uia ns a T hni I fi'R uir n nv Iv rex im n b in AR.3.Could the proposal affect nuclear safety in a way not previously evaluated in the SAR?(Yes/~N)h n n f in rm n as n I n w'hNR R I i IP ir n m wh IINR r ir n in w ff n r f If the answer to all the above questions is"NO", a safety evaluation is not required.If the answer is"YES" to any items in A, a detailed Safety Evaluation is required to determine if an Unreviewed Safety Question exists, B.Is a change to the Technical Specifications necessary?(Yes')If Yes, go to NIP-LPP-01. DETAILED SAFETY EVALUATION IS REQUIRED?YES XNO 0041 58LL NIP-SEV%1 Rev 0 t+fi J Co" II v A I~ No.NMPM'J R Page 3 of 4 FR.PRELIMINARY EVAL ATI N (Cont'd)NV NTA IMP T EVAL ATI N A.Will the change, test or experiment: '1.Result in a significant increase in any adverse environmental impact previously reviewed and evaluated in the NMP2 Final Environmental Statement-Operating License Stage (FES-OL)and other NRC Environmental impact assessments? YES NO 2.Result in a significant change in the effluents or power level?"3.Result in an activity not confined to on-site areas previously disturbed during site preparation and plant construction? YES.N~YES NO 4.Concern a matter not previously reviewed and evaluated in the documents specified in question"1" above, which may have a significant adverse environmental impact?YES NO'5.Constitute a decrease in the effectiveness of the NIVIP2 Environmental Protection Plan (EPP)?YES NO B.Is a change to the Environmental Protection Plan necessary? YES NO If the answer to all the above questions is"NO", the Environmental Evaluation is complete and no further action is required.If the answer is"YES" to any items in II.A or II,B above, a detailed Environmental Evaluation is required to determine if an Unreviewed Environmental Question exits, Contact Supervisor Environmental Protection. DETAILED ENVIRONMENTAL EVALUATION IS REQUIRED?YES N~0041 58LL NIP-SEV-01 Rev 0 Al E No.NMP Un R.J!FR PRELI I R EVAL ATl (Cont'd)Page 4 of 4 III.)DENTI ATI N F AR HAN E A.Are SAR changes required?(Yesl~N)LDCR No.Affected figures, tables, text sections (also indicate sheets for tables and figures and pages for text)IV.ID NTIFI ATI N F IMPA N PREVI MMTM A, Excluding statements made in the SAR, does this change impact any commitments made to the NRC?(YesINo)If yes, list commitment, agency.2.agency agency V.B.Does commitment(s) need to be changed?(Yes')If yes, notify the NRC Program Director.I NAT RE Preparer: Respo ble Individual Date Approver: Approver/Title Date Contact the NMP Supervisor Environmental Protection for assistance in answering these questions, if necessary. ~N: There is an ODCM change which requires an LDCR No.1-93-ODM-004, but this is not considered a SAR change.0041 58LL NIP-SEVZ1 Rev 0