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 MOHAWKPOWER CORPORA TION

J

<v t

Page 1 of 3 NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUALRADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1993 SUPPLEMENTAL INFORMATION

~Fi~lli: Nine Mile Point Unit ¹1 ~Li ennea: Niagara Mohawk Power Corporation

1. TE HNI AL PE IFI ATION LIMIT A) FISSION AND ACTIVATIONGASES 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 lI 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 ACTIVATIONGASES 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 3 E) 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

ATTACHIVIENT1 Page 1 of 2 Summary Data Unit 1 X Unit 2 Reporting Period Jul - December 1993 Uquid Effluents:

10CFR20, Appendix B, Table II, Column 2

~NA

~NA Average Energy (Fission and Activation gases- Mev):

Qtr. 3 Ey ~ 6.07E-02 Ep ~ 1.41E-01 Qtr. 4 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 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): ~NA Minimum time period for a batch release (hrs): ~NA 004443 LL

A l

~,1

ATTACHMENT 1 Page 20f 2 Summary Data Unit 1 X Unit 2 Reporting Period Jul - December 1993 bnormal Releases: There were no abnormal releases during the reporting period.

Uquids:

Number of releases 0 Total activity released ~NA Ci B. Gaseous:

Number of releases 0 Total ectivity released ~NA Ci 004443LL

4' IP

ATfACHMENT21 Unit 1 X Unit 2 Reporting Period Jul - December 1993 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL 3' EST. TOTAL QUARTER QUARTER ~ERROR A. Fission r/E Activation Gases

1. Total release Ci 3.63E+01 2.91E+00 5.00E+01

2. Average release rate /ICI/sec 4.57E+ 00 3.66E-01 B. Iodiness

1. Total iodine-131 Ci ~Q ~0 3.00E+01

2. Average release rate for period /ICI/sec ~0 ~0 C. Perticuletess 1 ~ )

Particulates with half-lives 8 days Ci 6.39E-05 4.25E-04 3.00E+01

2. Average release rate for period /rCI/sec 7.62E-06 5.41E-05

3. Gross alpha radioactivity Ci 5.42E-05 3.80E-05 2.50E+01 D. Tritiums

1. Total release Ci 7.19E+00 1.74E+01 5.00E+01

2. Average release rate for period /iCI/sec 8.57E-01 2.21E+ 00 E. Percent of Tech S ec Limits Fission and Activation Gases Percent of Quarterly Gemma Air Dose Umit (5 mrem) 2.98E-02 4.16E-03 Percent of Quarterly Beta Air Dose Limit (10 mrem) 3.01E-02 2.97E-03 Percent of Annual Gamma Air Dose Limit to Date (10 mrem) 7.31E-02 7.52E-02 Percent of Annual Beta Air Dose Umit to Date (20 mrem) 1.22E-01 1.23E-01 Percent of Whole Body Dose Rate Limit (500 mrem/yr) 7.09E-04 1.05E-04 Percent of Skin Dose Rate Limit (3000 mrem/yr) 2.84E-04 4.11E-05 Tritium lodines end Particulates with half-lives rester than 8 da s Percent of Quarterly Dose Limit (7.5 mrem) 1.20E- 02 7.63E- 02 Percent of Annual Dose Limit (15 mrem) 9.92E-01 9.98E-01 Percent of Organ Dose Rate Limit (1500 mrem/yr) 2.26E-04 1.53E-03 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

~ ~~

f8 P

<> EST. TOTAL QUARTER QUARTER ~ERROR A. Fission & Activation Products

1. Total release (not including Tritium, gases, alpha) Ci No Releases No Releases 5.00E+01

2. Average diluted concentration during reporting period /ICI/ml No Releases No Releases B. Tritium

1. Total release Ci No Releasee No Releases 5.00E+01

2. Average diluted concentration during reporting period /ICI/ml No Releasee No Releases C. Dissolved and Entrained Gases

1. Total release Ci No Releases No Releases 5.00E+01

2. Average diluted concentration during reporting period pCI/ml No Releases No Releases D. Gross Al ha Radioactivit

1. Total release Ci No Releases No Releases 5.00E+01 E. Volumes

1. Prior to dilution Liters No Releases No Releases 5.00E+01

2. Volume of dilution water used during release period Liters No Releases No Releases 5.00E+01

3. Volume of dilution water available during reporting period Uters 1.28E+ 11 1.35E+ 11 5.00E+01 F. Percent of Technical S ecification Limits Percent of Quarterly Whole Body Dose Umit (1.5 mrem) No Releases No Releasee Percent of Quarterly Organ Dose Limit (5 mrem) No Releases No Releases Percent of Annual Whole Body Dose Limit to Date (3 mrem) No Releases No Releases Percent of Annual Organ Dose Umit to Date (10 mrem) No Releases No Releasee Percent of 10CFR20 Concentration Umit No Releases No Releases Percent of Dissolved or Entrained Noble Gas Limit (1.00E-5/ICI/ml) % No Releases No Releasee 004443LL

. 1

'k

AT1ACHIVIENT5 Page 20f 2 Unit 1 X Unit 2 Reporting Period Jul - December 1993 UQUID EFFLUENTS RELEASED BATCH MODE 3" 4o Nuclides Released QUARTER QUARTER Strontium-89 Ci No Releases No Releases Strontium-90 Ci No Releases No Releases Cesium-134 Ci No Releases No Releases Cesium-137 Ci No Releases No Releases Iodine-131 Ci No Releases No Releases Cobalt-58 Ci No Releases No Releases Cobalt-60 Ci No Releases No Releases Iron-59 Ci No Releases No Releases Zinc-65 Ci No Releases No Releases Manganese-54 Ci No Releases No Releases Chromium-51 Ci No Releases No Releases Zirconium-Niobium-95 Ci No Releases No Releases MolyMenum-99 Ci No Releases No Releasee Technetium-99m Ci No Releases No Releases Barium-Lanthanum-140 Ci No Releases No Releases Cerium-141 Ci No Releases No Releases Tungsten-187 Ci No Releases No Releases Arsenic-76 Ci No Releases No Releases Iodine-133 Ci No Releases No Releases Iron-55 Ci No Releases No Releases Ne ptunium-239 Ci No Releases No Releases Praseodymium-144 Ci No Releases No Releases Iodine-135 Ci No Releases No Releases Dissolved or Entrained Gases Cl No Releases No Releases Tritium Ci No Releases No Releases 004443LL

a ~

4 II i

ATTACHMENT6 Page 1 of 6 Unit 1 X Unit 2 Reporting Period Jul - December 1993 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. 1 TYPE Volume ~Activit (ms) (Ci)

Class Class 5.83E+ 00 0 0 8.08E+ 00 0 0

1. Spent Resin Filter Sludge 5.50E+ 00 0 0 1.27E+01 0 0 Concentrated Waste 0 0 0 0 0 0 Evaporator Bottoms Total 1.13E+01 0 0 1.88E+01 0 0

2. Dry Compressible Waste, Dry 0 0 0 0 0 0 Non-Compressible Waste (Contaminated Equipment)

There were no irrldeted components shipped for burial during the reporting period.

3. Irradiated Components 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"

ATTACHMENT6 Page 20f 6 Unit 1 X Unit 2 Reporting Period Jul - December 1993 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.l TYPE Solidification Container ~Paaka a ~Aaat Spent Resin HIC TYPE A NONE Filter Sludge HIC TYPE A CEMENT Concentrated Waste ~NA

2. Dry Compressible Waste, ~NA ~NA Dry Non-Compressible Waste (Contaminated Equipment)

3. Irradiated Components 004443LL

'4 < W, W I ~

II

'l~

+'S.

W

ATTACHMENT6 Page 3 of 6 Unit 1 X Unit 2 Reporting Period Jul - December 1993 SOUD 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) Co-60 3.80E+01 (2) Cs-137 3.29E+01 (3) Fe-55 1.74E+01 (4) Mn-54 6.98E+00 (5) Cs-134 3.10E+00 (6) Other 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

~+ >

~ ~

ATTACHMENT 6 Page 4 of 6 Unit 1 X Unit 2 Reporting Period JuI - December 199 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.3. SOLID WASTE DISPOSITION 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

ATTACHMENT61 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 Burial Volume Activity Est. Total processing prior to burial at Barnwell, SC ~m ~CI ~Brror 1.77E+01 5.32E-01 5.00+01 C.2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide ~Percen (1) Co-60 B.17E+01 (2) Cs-137 2.09E+01 (3) Mn-54 8.09E+00 (4) Co-58 4.20E+00 (5) Fe-55 1.83E+00 (6) Fe-59 1.58E+00 (7) Other 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

ATTACHIVIENT6 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 (

ATTACHMENT7 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: Unit 1 Offsite Dose Calculation Manual

~Ti le: 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 of a

~f - Table 5.1 is being updated to reflect addition an milk location to the environmental program (memo from B. Zacharek to B. Thomas, dated August 20, 1993).

2) ~Pa ~ - Map location ¹73 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,:;:,,:,>>..,':,:.:';,:  ;;:;::,':,,i;::,Reason,'for.';.Chs'n'gag,',:,g i::

Table of Contents Deleted reference to No commitments.

commitments as a section.

1.0 ~ Added reference to D.O.T. Clarification.

regulations and guidelines.

~ Deleted reference to wet waste.

2.1.2 Removed reference to specific Administrative change.

Tech Specs section 8.5.2.11, and state, "In accordance with the applicable Tech Spec."

3.1 Removed all reference and Deletes specific procedures and specific procedural allows processing using requirements for types of approved vendor equipment and waste (wet radioactive procedures including the waste, dewatered spent capability of dehydrating liquid bead resins, activated waste as a method of carbon and dewatered filter processing waste to meet sludge) and replaced with shipping and burial general waste processing requirements.

procedural requirements for any type of radioactive waste including the capability to use vendor equipment and vendor procedures.

Deleted reference to CNSI Allows use of more then one procedures. vendor.

3.2.4 Deleted reference to specific Administrative to take specific procedures N1-LWPP-4, "Waste procedure numbers out of tho Transfer to a Shipping Cask, manual and broaden with a and N1-WHP-4, "Cask Loading" more generio statement.

procedure.

3.3.2 Changed the requirement that, Administrative to take specific "The Manager of Chemistry shall procedure numbers out of the ensure the chemical and manual and broaden with a radionuclide content of each mors generio statement.

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."

004443LL

J It

~ l

<A h O'I 4 +

• P P /~al f ~ Wg v'

goal x

f

ATTACHMENT 8 Page'2 of 3 gOld Page> ¹j /New~:P>agi',:¹j~ :i::';,'g'~i:,~l Ch'i'ng'e':.>'rg;"':>,';.',::.r'j'i>gg>.:':

.';.,".;.:;i. ,'!Bijou>.;':i';iIHeil'e'ori'for':.",C'h'in'gal::;!',;:::'.:::::i"':,.'.'.

3.3.3 Deleted the reference to Administrative to take specific "applicable S-RPIP's" and state procedure numbers out of the "applicable radiation protection manual and broaden with a procedures." more generic statement.

3 3.4.1.a Deleted reference to the specific Administrative.

Tech Spec section, 6.9.1, Routine Reports.

3.4.l.c Deleted section. Addressed in 3.4.1.b.

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

3 3.4.2.a Deleted reference to specifio Administrative.

Technical Specification section.

3.4.2.b There is a typing error that was Clerical.

inadvertently approved; this will be corrected in next rovision of PCP.

3.4.3 Added the statement that Clarification to encompass all personnel are effectively trained procedures.

in accordance with the "applicable training procedures" .. ~

3.4.3.a Changed statement of Radwaste Clarification.

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".

3.4.3.a.1-4 ~ Switched and renumbered Clarification to take specific 3.4.3.a.1 with 3.4.3.a.2 training out of the manual and and rewrote 3.4.3.a.2 to broaden with a more generic delete the reference to statement to ensure compliance classroom instruction and to with all procedure requirements.

specific intent of on-the-job training objectives. Added the statement "in accordance with applicablo training procedures."

3.4.3.b and c ~ Deleted sections and Clarification.

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.

In addition, remedial training Clarification.

will now be as directed by NTP-TQS-503 instead of by the General Supervisor Radwaste.

004443LL

g ~

ATTACHIVIENT8 Page 3 of 3

@::::<gy:% '~wgxw:

!::',:New".,:P'age,¹',";:.:

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

the applicable quality assurance procedures."

4.1-4.3 Deleted specIFic definitions and Deleted specific definitions and stated, "The applicable included references to Radwaste packaging, processing 49CFR171.8 and and transportation definitions 49CFR173.403.

will be used in accordance with 49CFR171.8 and 49CFR173A03.

5.1.1 Usted the LCO and surveillance Clarification.

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

6 5.3 Deleted reference to AP-3.3, Updated to incorporate current "Radiation Protection Program," references.

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."

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

Handling."

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

ATTACHMENT9 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-ANNUALRADIOACTIVE 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-ANNUALRADIOACTIVE 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

= 1,16E-01 pCi/m'e-55

= 1.97E-01 pCi/m'r-89

= 2,33E-02 pCi/m'r-90 pCi/m'-3

= 1.03E+04

= 7,90E-02 pCi/m'-131

= 7.90E-02 pCi/m'-133

= 1.42E-02 pCi/m'-135 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

ATTACHMENT10 Page 3 of 3 SEMI-ANNUALRADIOACTIVE 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 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> 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-ANNUALRADIOACTIVE 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"

)

ATTACHIVIENT11 Page 2of 3 SEIVII-ANNUALRADIOACTIVE EFFLUENT RELEASE REPORT (1993)

NINE MILE POINT NUCLEAR STATION UNIT 1 RADIATION DOSES TO THE LIKELYMOST 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.

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.

6. 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.

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.

7. 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.

8. 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-ANNUALRADIOACTIVE 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.

GASEOUS UQUID 2 QUARTER 2 QUARTER Nuclidet AetidteCJt ~AclMt Ci Sr-89 4.48E-05 No Releases Sr-90 No Releases K-3 6.31E+00 No Releases Fe-55 2.08E-05 No Releases Particulates GASEOUS LIQUID

1. Particulates with Ci 3.98E-04 ~NA

)

half-lives 8 days 5.42E-05

2. Average release rate pCI/sec DNA for period Tritium

1. Total release Ci 6.31E+ 00 ~NA

2. Average release rate pCi/sec 8.60E-01 ~NA for period Tritium lodines ond GASEOUS LIQUID Particulates with half-lives rester than 8 do 8

1. Percent of Quarterly 1.06E-01 ~A Dose Umlt (Quarterly) (Quarterly)

2. Percent of Annual 9.85E-01 ~NA Dose Limit to Date (Annual) (Annual)

3. Percent of Organ 2.27E-03 ~NA

- Dose Rate Umit (Quarterly) (Quarterly)

(Gaseous)(Quarterly) ~NA ~NA

- Dose Umit (Uquid) (Annual) (Annual)

(Annual Ik Quarterly)

4. Percent of 10CFR20 Concentration Umit (0 quid)

5. Percent of Dissolved N/A or Entrained Noble Gas (Liquid)

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 Burial Volume Activity Est. Total processing prior to burial at Barnwell, SC ~m ~CI ~Emr 1 929+01 2.71E-01 9.00n01 C.2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent (1) C0-60 5.98E+01 (2) Cs-137 2.27E+01 (3) Mn-54 9.54E+00 (4) C0-58 5.10E+00 (5) Fe-59 1.88E+00 (6) Other 9.34E-01 C.3. SOLID WASTE DISPOSITIONs Number of Shi ments Mode of Trans ortation ~0B 8 El h 8 I0 Truck 9 nwlt 00 Truck 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 DATE AND INITIALS APPROVALS S IGNATURES~M REVISION 13 K. A. Dahlberg Plant Manager Unit 1 C. D. Terry V. P. Nuclear Engineering NIAGARA MOHAWK POWER CORPORATION Unit 1 ODCM Revision 13 004152LL October 1993

I

SUMMARY

OP REVISIONS Revision 13 Effective 12/31/93 PAGE DATE lg 2i 5g 6g 8i 9i 11 13/15 February 1987 25/ 36 44i 47 18'1'4i 86-116 49'2-81, 3i 4/ 7g 10'4/ 19'0'2'3'6 35 December 1987 45i 46f 50i 51~ 82 85 January 1988

• 29 May 1988 (Reissue)

• 64( 77( 78 May 27, 1988 -(Reissue) 22Bg 124'5i 26i 112 February 1990 i ii, 21i g

19~

iii,22AJ 12-1 6, 8, 28-40, 1 45-47 52i 55'9 89J 92J 93'7 June 1990 129'1-93, 95 June 1992 3, 4, 21, 92, 95a-c February 1993 10, 16-20 March 1993 5i 13'8'0'5 30'5'9 June 1993 66, 69 December 1993 Unit 1 ODCM Revision 13 004152LL December 1993

I L1k

~

k "i Vh

,A4 '~',fly+ 4 j

ODCM - NINE MILE POINT UNIT 1 TABLE OF CONTENTS Pacae

1.0 INTRODUCTION

2' LIQUID EFFLUENTS 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 Liquid Effluent Concentration Calculation 2.3 Dose Determinations 2.3.1 Maximum Dose Equivalent Pathway 3.0 GASEOUS EFFLUENTS 10 3.1 Setpoint Determinations 10 3.1.1 Basis 10 j

3.1.2 Stack Monitor Setpoints 10 3.1.3 'ecombiner Discharge (Off Gas) Monitor Setpoints 12 3.1.4 Emergency Condenser Vent Monitor Setpoint 13 3.1.5 Discussion 13 3.1.5.1 Stack Effluent Monitoring System Description 13 3.1.5.2 Stack Sample Flow Path HAGEMS 13 3.1.5.3 Stack Sample Flow Path OGESMS 14 Unit 1 ODCM Revision 13 004152LL December 1993

T Nt

<<w

,I

ODCM - NINE MILE POINT UNIT 1 TABLE OF CONTENTS (Cont'd)

Pacae 3.1.5.4 Sample Frequency/Sample Analysis 14 3.1.5.5 I-133 Estimates 14 3.1.5.6 Gaseous Radwaste Treatment System Operation 15 3.2 Dose and Dose Rate Determination 15 3.2.1 Dose Rate 16 3.2.1.1 Noble Gases 16 3.2.1.2 Tritium, Iodines and Particulates 18 3.2.2 Dose 19 3.2.2.1 Noble Gas Air Dose 19 3.2.2.2 Tritium'Iodines and Particulates 20 3.2.2.3 Accumulating Doses 21 3.3 Critical Receptors 21 3.4 Refinement of Offsite Doses Resulting From Emergency Condenser Vent Releases 22 4.0 40 CFR 190 REQUIREMENTS 23 Evaluation of Doses From Liquid Effluents 24 4.2 Evaluation of Doses From Gaseous Effluents 25 4.3 Evaluation of Doses From Direct Radiation 26 4.4 Doses to Members of the Public Within the Site Boundary 26 5.0 ENVIRONMENTAL MONITORING PROGRAM 29 5.1 Sampling Stations 29 5.2 Interlaboratory Comparison Program 29 5.3 Capabilities for Thermoluminescent Dosimeters Used for Environmental Measurements 30 Unit 1 ODCM Revision 13 004152LL December 1993

I,

,P

~ 4

ODCM - NINE MILE POINT UNIT 1

')

TABLE OF CONTENTS (Cont Pacae Table 1-1 Average Energy Per Disintegration 32 Tables 2-1 to 2-8

~ Values for the NMP-1 Facility 33 Table 3-1 Critical Receptor Dispersion Parameters for Ground I evel and Elevated Releases 41 Table 3-2 Gamma Air and Whole Body Plume Shine Dose Factors for Noble Gases (B, and V~) 42 Table 3-3 Immersion Dose Factors for Noble Gases 43 Tables 3-4 to 3-22 Organ Dose and Dose Rate Factors (R,)

Table 3-23 Parameters for the Evaluation of Doses to Real Members of the Public from Gaseous and Liquid Effluents 63 Table 5.1 NMP-1 Radiological Environmental Monitoring Program Sampling Locations 64 Figure 5.1-1 Nine Mil'e Point On-Site Map 68 Figure 5.1-2 Nine Mile Point Offsite Map 69 Figure 5.1.3-1 Site Boundaries 70 Appendix A Liquid Dose Factor Derivation (A ) 71 Appendix B Plume Shine Dose Factor Derivation (B, and V,) 74 Appendix C Organ Dose and Dose Rate Factors for Iodine 131 6 133, Particulates and Tritium (R;) 78 Appendix D Diagrams of Liquid and Gaseous Radwaste Treatment Systems 88 Unit 1 ODCM Revision 13 004152LL -iii- 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 made it be necessary to revise the ODCM, these revisions will be in accordance with Technical Specifications.

Unit 1 ODCM Revision 13 004152LL December 1993

S~,

~5 e

lt Ill F ~"

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

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.

2 '.2 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 I

((pCi/mi)lr/MPCI)

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

((pCi ml)n MPC))

(pCi/ml) + concentration of gamma emitting isotope the sample, or the corresponding MPC of gamma i in emitting isotope (units = pCi/ml).

i (MPC) whichever is higher (pCi/ml) n concentration of any radioactive isotope the sample including tritium and other i in non-gamma emitters or corresponding MPC of isotope i, MPC whichever is higher (units ~

pCi/ml ) .

TDF Total Dilution Flow (units ~ gallons/minutes).

Service Water Flow (units = gallons/minutes).

Unit 1 ODCM Revision 13 004152LL December 1993

Jr '

t4

+ 'I W

~IV ""

,A

2.1.2 Service Water System Effluent Line Alarm Setpoint (Cont'd)

CF monitor calibration factor (units net cpm/pCi/ml ) .

liquid effluent radioactivity concentrations MPH limit for radionuclide i as specified in 10 CFR 20, Appendix B, Table II, Column 2.

Sample 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.**

(MPC)v 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) z/MPC,]

(pCi/ml)+ concentration of gamma emitting isotope sample or the corresponding MPC of gamma emitting i in the isotope i, (MPC), whichever is higher.

(pCi/ml) ~ concentration of any radioactive isotope sample including tritium and other non-gamma i in the emitters or the corresponding MPC of isotope whichever is higher. (uni.ts = pCi/ml).

i MPC, TDF Total Di.lution Flow (units = gallons/minutes).

Radwaste Effluent Flow (units = gallons/minutes).

CF 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.

Unit 1 ODCM Revision 13 004152LL December 1993

Nt It gt g ~

'

g>lt+

2' ' Liquid Radwaste Effluent Line Alarm Setpoint (Cont'd) liquid effluent radioactivity concentration MPC) i limit for radionuclide 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)

(MPC) I same as MPC, but for gamma emitting nuclide only.

0.9 and 0.7 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, F will be reduced (normally by a factor of

2) to allow setting the alarm point at a concentration higher than tank concentration. This will also result in a discharge canal concentration at approximately 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.

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.

2.1.4.2 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.

Unit 1 ODCM Revision 13 004152LL 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 sample, or corresponding MPC value, is significantly lower in the grab 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).

Unit 1 ODCM Revision 13 004152LL December 1993

hp V

4'.i~

C

\

C U

,e, $ +1 P

+h

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 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.

2.1.4.5 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),

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.

2 ~2 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.

Unit 1 ODCM Revision 13 004152LL 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 effluent stream s, pCi/ml.

i in particular F, The flow rate of a particular effluent stream s, gpm.

"MPCi 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.

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).

2 ~3 Dose Determination 2.3 ~ 1 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.

Unit 1 ODCM Revision 13 004152LL 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 emergencydosecondenser vent as factori ~i is applicable, for all pathways. Each age group 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 hT from 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 calculated and included in a revision to the ODCM.

it will be 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:

Unit 1 ODCM Revision 13 004152LL December 1993

Jk Q't fq n

I'l I

nfl4"

~

~i

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.

Unit 1 ODCM Revision 13 004152LL 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, mandatory that the setpoint be changed.

it is not 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.

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

3 ~1~2 Stack Monitor Setpoints The detailed methods for establishing setpoints shall be contained in the station procedures. These methods shall apply the following general criteria:

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

release rate actual ', = release rate max. allowable corresp. dose rate, actual corresp. dose rate, max. allowable E

iQi(%+(SF) W(~/Q).) 500 mrem/yr Unit 1 ODCM Revision 13 004152LL 10 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) 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.

(4) 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~ monitor gross count rate in cps or cpm B 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 ~ ZF 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).

Unit 1 ODCM Revision 13 004152LL December 1993

IR pa

~e peal

3 '.2 Stack Monitor Setpoints (Cont'd)

Y ~ b/d (betas/disintegration) or y/d (gammas/disintegration).

P, ~ i Activity fraction of nuclide 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.

K factors more conservative than those calculated by the above methodology may be assumed.

Unit 1 ODCM Revision 13 004152LL 12 December 1993

I~

I5

3 ' ' Recombiner 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 extended periods.

if high fuel leakage were to be permitted over 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 Discussion 3.1 5.1

~ 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).

Unit 1 ODCM Revision 13 004152LL 13 December 1993

lg t

t A

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 the exi.t of the stack at elevation 257', the sample line RAGEMS. From runs east approximately 20'nd then vertically approximately OGESMS 8'o skid. In the OGESMS, sample flows thru a particulate/iodi.ne the 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.

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" ).

3,1 5.5

~ 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.

Unit 1 ODCM Revision 13 004152LL December 1993

p4 64.

<< I

"<< I 1 l <<'t<<

I' 4

4

3 ~1~5 ~5 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).

F 1.5.6 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 5 4 pCi/sec b) Sr-89 release rate 5 4 x Cs-137 release rate c) Sr-90 release rate 5 0.5 x Cs-137 release rate d) Fe-55 '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.

Unit 1 ODOM Revision 13 004152LL 15 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.

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.

3.2

~ ~ 1 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 from Unit 1 exceed 10% of the limits:

if the offsite dose rates

1) Notify the Unit 1 SSS (Station Shift Supervisor) and Unit 1 Supervisor Chemistry.

Unit 1 ODOM Revision 13 004152LL 16 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 total body gamma dose rate (mrem/sec).

DR +p skin dose rate from gamma and beta radiation (mrem/sec) .

V, 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) the release rate of isotope vent(v); (pCi/sec) i from the stack(s) or SF structural shielding factor.

X/Q 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.

Unit 1 ODCM Revision 13 004152LL 17 December 1993

tq ) . }

J

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 + W Q])

Where:

Total dose rate to each organ k of an individual in age group a (mrem/sec).

Wj 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 site boundary dose rate limit (mrem/year).

(RgWj) 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.

Unit 1 ODCM Revision 13 004152LL 18 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 and necessary to ensure 2 and site (Nine Mile Point Units 1 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.

Unit 1 ODCM Revision 13 004152LL 19 December 1993

1 t

~J

+pC'1

~

')tl e

3.2.2.1 Noble Gas Air Dose (Cont'd)

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.

N) 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, from 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.

All other parameters are as defined in section 3.'2.1.1.

3 ' '42 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:

dose to each organ k of an individual in age WJ i'otal 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" values are used for stack releases W>

(s = stack)p "Ground" W> values are used for Emergency Condenser Vent releases (v ~ vent).

Q the release rate of isotope vent (v)i (pCi/sec).

i from stack(s) or 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.

3.17E-S the inverse of the number of seconds in a year.

total time during the release period, sec.

Unit 1 ODCM Revision 13 004152LL 20 December 1993

~ a4 4

J jan(

I

\t~

t 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!

noble gas plume direct air dose 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.

3 ~3 Critical Receptors In accordance with the provisions of 10 CFR 20 and 10 CFR 50, Appendix I, the critical receptors have been identified and are contained in Table 3-1.

For 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.

Unit 1 ODCM Revision 13 004152LL 21 December 1993

4

~ 'I hf 14 '4 C

E'r 4

gyes 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.

Unit 1 ODCM Revision 13 004152LL 22 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 be taken to reduce subsequent releases.

if possible, action will 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.

Unit 1 ODCM Revision 13 004152LL 23 December 1993

4L 41 J 4L ~

-~

Hw, Ai * ~

't~>" e s4e

.

1 P

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 if if the dose determination used to determine radiological sampling and analyses are 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:

i, j,via fish The total annual dose to organ of an individual of age group a, from nuclide pathway p, in mrem per year.

The concentration of radionuclide in pCi/gram.

i in fish samples U ~ The consumption rate of fish in kg/yr.

1E+3 ~ Grams per kilogram.

Unit 1 ODCM Revision 13 004152LL 24 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 Table E-11) (mrem/pCi).

j, (Reg. Guide 1.109,

~ 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:

= 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.

Cg ~ The concentration of radionuclide sediment in pCi/gram.

i in shoreline

'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.

Unit 1 ODCM Revision 13 004152LL 25 December 1993

4A V

~ ~

~V I.

r, kt, VVL V

P

~V 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.

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.

4.4 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.

Unit 1 ODCM Revision 13 004152LL 26 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 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.

Dp Zi [ (Ci) F (X/Q) (DFA)- (BR)at]

Where:

.Dp 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 C,

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, The dose factor for nuclide i, organ j, and age group a in mrem per pCi (Reg. Guide 1.109, Table E-7) ~

(BR), 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).

Unit 1 ODCM Revision 13 004152LL 27 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.

Unit 1 ODCM Revision 13 004152LL 28 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 Unit 1 ODCM Revision 13 004152LL 29 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 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.

5.3.6 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.

Unit 1 ODCM Revision 13 004152LL 30 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.

Unit 1 ODCM Revision 13 004152LL 31 December 1993

V4 it

TABLE l-l Average Energy Per Disintegration ISOTOPE ~Ref E~av dis<" ~Ref Ar-41 1.294 (3) 0.464 (3)

Kr-83m 0.00248 0.0371 Kr-85 0.0022 0.250 Kr-85m 0.159 0.253 Kr-87 0.793 1.32 Kr-88 1.95 0.377 Kr-89 2.22 (2) 1.37 (2)

Kr-90 2. 10 (2) 1.01 (2)

Xe-131M 0.0201 0.143 Xe-133 0.0454 0.135 Xe-133m 0.042 0.19 Xe-135 0.247 0.317 Xe-135m 0.432 0.095 Xe-137 0.194 1.64 Xe-138 1.18 0.611 ORNL-4923, Radioactive Atoms Su lement I, M.S. Martin, November 1973.

(2) 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).

(3) NCRP Report No. 58, "A Handbook of Radioactivity Measurements Procedures"; 1978 (4) The average energy includes conversion electrons.

Unit 1 ODCM Revision 13 004152LL 32 December 1993

t 4

1J <

gs.h'I 0

TABLE 2-1 A VALUES - LIQUID*

RADWASTE TANK INFANT mrem ml hr - pCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 2.90E-1 2.90E-1 2.90E-1 2 90E-1 2.90E-1 2.90E-1 Cr 51 1.29E-2 8.39E-3 1.83E-3 1.63E-2 3.75E-1 Cu 64 '.13E-1 5.23E-2 1.91E-l 2.32 Mn 54 1 87E+1 4.23 4.14 6.86 FE 55 1.31E+1 8.44 2.26 4.13 1.07 Fe 59 2 84E+1 4.96E+1 1.96E+1 1.47E+1 2.37E+1 Co 58 3.34 8.34 8.33 Co 60 1 02E+1 2.40E+1 2.42E+1 Zn 65 1.72E+1 . 5.91E+1 2 '3E+1 2 87E+1 5 'OE+1 Sr 89 2.32E+3 6.66E+1 4.77E+1 Sr 90 1.74E+4 4.43E+3 2.17E+2 Zr 95 1.91E-1 4.66E-2 3.30E-2 5 '2E-2 2.32E+1 Mn 56 -2. 40E-4 4.15E-5 2.07E>>4 2.18E-2 Mo 99 2.34E+1 4.57 3.50E+1 7.71 Na 24 2.37 2.37 2.37 2.37 2.37 2.37 2 '7 I 131 3.03E+1 3.54E+1 1.57E+1 1.17E+4 4.17E+1 1.28 I 133 4.22 6.15 1. 80 1-12E+3 7.23 1.04 Ni 65 1.33E-3 1.51E-4 6.85E-S 1.15E-2 I 132 1.58E-4 3.21E-4 1.14E-4 1.50E-2 3.58E-4 2.60E-4 Cs 134 3.54E+2 6.60E+2 6.67E+1 1.70E+2 6.97E+1 1.79 Cs 136 4.05E+1 1.19E+2 4.45E+1 4.75E+1 9.71E+1 1.81 Cs 137 4.91E+2 5.75E+2 4.07E+1 1.54E+2 6.24E+1 1.80 Ba 140 1.50E+2 1.50E-1 7.74 3.57E-2 9.23E-2 3.69E+1 Ce 141 7.21E-2 4.40E-2 5.17E-3 1.36E-2 2.27E+1 Nb 95 3.85E-2 1.59E-2 9.18E-3 1.14E-2 1.34E+1 La 140 1.18E-2 4.67E-3 1.20E-3 5.48E+1 Ce 144 2.79 1.14 1.57E-1 4.62E-1 1.60E+2

• Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section 1.

Unit 1 ODCM Revision 13 004152LL 33 December 1993

44 t

7A" y~Wml

TABLE 2-2 A, VALUES - LIQUID*

RADWASTE TANK CHILD mrem << ml hr pCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 4.39E-1 4.39E-1 4.39E-l 4.39E-1 4.39E-l 4.39E-l Cr 51 2.13E-2 2.13E>>2 1.40 7 '6E-1 2.30E-1 1.42 7.31E+1 Cu 64 2.51E-6 2.70 1.63 2.51E-6 6.52 2.51E-6 1.27E+2 Mn 54 6.92 3.38E+3 9.06E+2 6.92 9.53E+2 6.92 2.84E+3 Fe 55 9.21E+2 4.88E+2 1.51E+2 2.76E+2 9.05E+1 Fe 59 1.30E+3 2.11E+3 1.05E+3 1.34 1.34 6.12E+2 2.19E+3 Co 58 1.89 7.46E+1 2.24E+2 1.89 1.89 1.89 4.26E+2 Co 60 1.12E+2 3.28E+2 7.48E+2 1.12E+2 1.12E+2 1.12E+2 1.31E+3 Zn 65 2.15E+4 5.73E+4 3.56E+4 3.85 3.61E+4 3.85 1.01E+4 Sr 89 3.26E+4 1.10E-4 9.32E+2 1.10E-4 1.10E-4 1~ 10E-4 1.26E+3 Sr 90 4.26E+5 1. 08E+5 5.74E+3 Zr 95 1.70 1.33 1.32 1.23 1.38 1.23 1.08E+2 Mn 56 1.65E-1 3.73E-2 2.00E-1 2.39E+1 Mo 99 5.35E-3 9.57E+1 2.37E+1 5.35E-3 2.04E+2 5.35E-3 7.91E+1 Na 24 1.52E+2 1.52E+2 1.52E+2 1.52E+2 1.52E+2 1.52E+2 1.52E+2 I 131 2.09E+2 2.10E+2 1. 19E+2 6. 94E+4 3. 45E+2 5.60E-2. 1.87E+1 I 133 3.39E+1 4.19E+1 1.59E+1 7.78E+3 6.98E+1 1.38E-4 1.69E+1 Ni 65 2.67E-1 2.51E-2 1.47E-2 3.08 I 132 6.13E-3 1.13E-2 5.18E-3 5.22E-1 1.72E-2 1.32E-2 Cs 134 3.68E+5 6.04E+5 1.27E+5 3.54E+1 1.87E+5 6.72E+4 3.29E+3 Cs 136 3.52E+4 9.67E+4 6.26E+4 6.21E-1 5.15E+4 7.68E+3 3.40E+3 Cs 137 5.15E+5 4.93E+5 7.28E+4 ,5.37E+1 1.61E+5 5.78E+4 3.14E+3 Ba 140 3.61E+2 3.96E-l 2.11E+1 7.96E-2 1.82E-1 2.68E-1 1.83E+2 Ce 141 1.50E-1 1.07E-1 6.99E-2 6.34E-2 8.24E-2 6.34E-2 5.40E+1 Nb 95 5.21E+2 2.03E+2 1.45E+2 6.39E-1 1.91E+2 6.39E-1 3.75E+5 La 140 1.50E-1 5.93E-2 2.68E-2 . 1.03E-2 1.03E-2 1.03E-2 1.36E+3 Ce 144 5.00 1.81 6.06E-1 3.58E-1 1.16 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.

Unit 1 ODCM Revision 13 004152LL 34 December 1993

\'

5 s6':

TABLE 2-3

~ VALUES LIQUID~

RADWASTE TANK TEEN mrem - ml hr - pCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 3.28E-1 3.28E-1 3.28E-1 3 28E-1 3.28E-1 3.28E-1 Cr 51 1.02E-1 1.02E-1 1.39 8. 16E-1 3. 84E-1 1.94 2.16E+2 Cu 64 1.20E-5 2.89 1. 36 1.20E-5 7.32 1.20E-5 2.24E+2 Mn 54 3.31E+1 4.34E+3 8.87E+2 3.31E+1 1.32E+3 3.31E+1 8 '86E+3 Fe 55 6.94E+2 4.92E+2 1.15E+2 3.12E+2 2.13E+2 Fe 59 1.07E+3 2.49E+3 9.64E+2 6.41 6.41 7.89E+2 5 '7E+3 Co 58 9.03 9.82E+1 2.15E+2 9.03 9.03 9.03 1.24E+3 Co 60 5.36E+2 7.96E+2 1.12E+3 5.36E+2 5.36E+2 5.36E+2 3.93E+3 Zn 65 2.10E+4 7.28E+4 3.40E+4 1.84E+1 4 66E+4 1.84E+1 3.08E+4 Sr 89 2.44E+4 5.24E-4 6.98E+2 5.24E-4 5.24E-4 5.24E-4 2.90E+3 Sr 90 4.66E+5 1.15E+5 1.31E+4 Zr 95 6.20 6.00 5.97 5.90 6.04 5.90 2.28E+2 Mn 56 1.81E-1 3.22E-2 2.29E-1 1.19E+1 Mo 99 2.56E-2 9.22E+1 1.76E+1 2.56E-2 2.11E+2 2.56E-2 1.65E+2 Na 24 1.39E+2 1.39E+2 1.39E+2 1.39E+2 1.39E+2 1.39E+2 1.39E+2 I 131 1.55E+2 2.17E+2 1.16E+2 6.31E+4 3.73E+2 2.68E-1 4.30E+1 I 133 2.53E+1 4.29E+1 1.31E+1 5.99E+3 7.52E+1 6 60E-4 3.25E+1 Ni 65 2.08E-1 2.66E-2 1.21E-2 1.44 I 132 4.90E-2 1.28E-2 4.60E-3 4.32E-1 2.02E-2 5.59E-3 Cs 134 3.05E+5 7.18E+5 3.33E+5 1.69E+2 2.28E+5 8.73E+4 9.10E+3 Cs 136 2.98E+4 1.17E+5 7.88E+4 2.97 6.38E+4 1.01E+4 9.44E+3 Cs 137 4.09E+5 5.44E+5 1.90E+5 2.57E+2 1.85E+5 7.21E+4 7.99E+3 Ba 140 2.35E+2 4.10E-1 1.55E+1 3.81E-1 4.79E-1 5.75E-1 3.63E+2 Ce 141 3.46E-1 3.32E-1 3.07E-1 3.04E-1 3.17E-1 3.04E-1 8.16E+1 Nb 95 4.44E+2 2.48E+2 1.18E+2 3.06 2.40E+2 3.06 1.05E+6 La 140 1.57E-1 1.02E-1 6.35E-2 4.94E-2 4.94E-2 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.

Unit 1 ODCM Revision 13 004152LL 35 December 1993

ee N

L I II 5"4 ' e'i,W

TABLE 2-4 A VALUES LIQUID*

RADWASTE TANK ADULT prem-ml

-

hr pCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 4.45E-1 4.45E-1 4.45E-1 4.45E-1 4.45E-1 4.45E-1 Cr 51 1.82E-2 1-82E-2 1.27 7.64E-1 2.93E-1 1. 67 3.14E+2 CQ 64 2 '5 1.29 6.94 2.35E+2 Mn 54 5.94 4.38E+3 8.41E+2 5.94 1.31E+3 5.94 1.34E+4 Fe 55 6.64E+2 4.58E+2 1.07E+2 2.56E+2 2.63E+2 Fe 59 1.03E+3 2.43E+3 9.31E+2 1 ~ 15 1.15 6.79E+2 8.09E+3 Co 58 l. 62 9.15E+1 2.03E+2 1.62 1.62 1. 62 1.82E+3 Co 60 9.60E+1 2.57E+2 6.71E+2 9.60E+1 9.60E+1 9.60E+1 4.99E+3 Zn 65 2.31E4 7.36E+4 3 32E+4 3.30 4.92E+4 3.30 4.63E+4 Sr 89 2.25E+4 9.39E-S 6.45E+2 9.39E-S 9.39E-S 9.39E-5 3.60E+3 Sr 90 5.60E+5 1.37E+5 1.62E+4 Zr 95 1.36 1.15E 1.12 1.06 1.21 1.06 3.06E+2 Mn 56 1.73E-1 3.07E-2 2.20E-1 5.52 Mo 99 4.58E-3 8.70E+1 1.66E+1 4 58E-3 1.97E+2 4-58E-3 2.02E+2 Na 24 1.35E+2 1.35E+2 1.35E+2 1.35E+2 1.35E+2 1.35E+2 1.35E+2 I 131 1.45E+2 2.07E+2 1.19E+2 6.79E+4 3.55E+2 4.80E-2 5.47E+1 I 133 2.35E+1 4.09E+1 1.25E+1 6 '2E+3 7.14E+1 1 18E-4 3.68E+1 Ni 65 1.93E-1 2.51E-2 1.14E-2 6. 36E-1 I 132 4.68E-3 1.25E-2 4.38E-3 4.38E-1 2.00E-2 2.35E-3 Cs 134 2.98E+5 7.08E+5 5.79E+5 3.03E+1 2.29E+5 7.61E+4 1.24E+4 Cs 136 2.96E+4 1.17E+5 8.42E+4 5.32E-1 6.51E+4 8.93E+3 1.33E+4 Cs 137 3.82E+5 5.22E+5 3.42E+5 4.60E+1 1.77E+5 5.90E+4 1.02E+4 Ba 140 2.24E+2 3.49E-1 1.47E+1 6.83E-2 1.64E-1 2.29E-l 4.61E+2 ce 141 9.53E-2 8.20E-2 5.75E-2 5.44E-2 6.72E-2 5.44E-2 1.06E+2 Nb 95 4.39E+2 2.44E+2 1.32E+2 5.47E-1 2.41E+2 5.47E-1 1.48E+6 La 140 1.11E-1 6.03E-2 2.24E-2 8.84E-3 8.84E-3 8.84E-3 3.78E+3 Ce 144 2.48 1.22 4.24E-1 3.07E-1 8.47E-1 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.

Unit 1 ODCM Revision 13 004152LL 36 December 1993

1

s.

TABLE 2-5 VALUES - LI{}UID*

EMERGENCY CONDENSER VENT INFANT mrem - ml hr pci NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 7.43E-4 7.43E-4 7.43E-4 7.43E-4 7.43E-4 7.43E-4 Cr 51 3.30E-S 2.15E-S 4.70E-6 4.18E-S 9.61E-4 Cu 64 2.89E-4 1.34E-4 4.89E-4 5.94E-3 Mn 54 4.79E-2 1 08E-2 1.06E-2 1 ~ 76E-2 Fe 55 3.35E-2 2.16E-2 5.78E-3 '1 ~ 06E-2 2.75E-3 Fe 59 7.29E-2 1.27E-1 5.02E-2 3.76E-2 6.08E-2 Co 58 8.58E-3 2.14E-2 2 '4E-2 Co 60 2.60E-2 6.15E-2 6.19E-2 Zn 65 4.42E-2 1.52E-1 6 '9E-2 7.35E-2 1.28E-1 Sr 89 5.95 1.71E-1 1.22E-1 Sr 90 4.46E+1 1.14E+1 5.57E-1 Zr 95 4.90E-4 1.19E-4 8.47E-5 1.29E-4 5.95E-2 Mn 56 ,6. 17E-7 1.06E-7 5.30E-7 5,60E-5 Mo 99 6.00E-2 1.17E-2 8.97E-2 1.98E-2 Na 24 6.07E-3 6.07E-3 6.07E-3 6.07E-3 6.07E-3 6.07E-3 6.07E-3 I 131 7.77E-2 9.16E-2 4.03E-2 3 '1E+1 1.07E-1 3.27E-3 I 133 1.08E-2 1.58E-2 4.62E-3 2.87 1.85E-2 2.67E-3 Ni 65 3.41E-6 3.86E-7 1.76E-7 2.94E-5 I 132 4.05E-7 8.22E-7 2.93E-7 3.85E-S 9.17E-7 6.66E-7 Cs 134 9.08E-1 1.69 1.71E-1 4.36E-1 1.79E-1 4.60E-3 Cs 136 1.04E-1 3.06E-1 1.14E-1 1.22E-l 2.49E-2 4.64E-3 Cs 137 1.26 1.47 1.04E-1 3.95E-1 1.60E-1 4.61E-3 Ba 140 3.85E-1 3.85E-4 1.99E-2 9.15E-S 2.37E-4 9.47E-2 Ce 141 1.85E-4 1.13E-4 1.33E-5 3.48E-S 5.82E-2 Nb 95 9.88E-5 4.07E-S 2.35E-S 2.92E-5 3.43E-2 La 140 3.03E-S 1.20E-S 3.08E-6 1.41E-1 Ce 144 7.16E-3 2.93E-3 4.02E-4 1. 19E-3 4.11E-1

• Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section 1.

Unit 1 ODCM Revision 13 004152LL 37 December 1993

~ e

' I I

I I I ir'A >,

TABLE 2-6

~ VALUES - LIQUID*

EMERGENCY CONDENSER VENT CHILD mrem ml hr pCi 'I NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 1. 44E-1 1.44E-1 1.44E-1 1.44E-1 1.44E-1 1.44E-1 Cr 51 3.78E-S 3 78E-5 1.37 7.58E-1 2 '7E-1 1.38 7 '4E+1 Cu 64 2. 63 1.59 6.35 1.23E+2 Mn 54 1.23E-2 3.36E+3 8.95E+2 1.23E-2 9.42E+2 1.23E-2 2.82E+3 Fe 55 9.04E+2 4.79E+2 1.49E+2 2.71E+2 8.88E+1 Fe 59 1.28E+3 2.07E+3 1.03E+3 2.38E-3 2.38E-3 6.00E+2 2.15E+3 Co 58 3.36E-3 7.01E+1 2.15E+2 3.36E-3 3.36E-3 3.36E-3 4.09E+2 Co 60 1.99E-l 2.08E+2 6.14E+2 1.99E-1 1.99E-1 1.99E-1 1.15E+3 Zn 65 2.15E+4 5.73E+4 3.56E+4 6.84E-3 3.61E+4 6.84E-3 1.01E+4 Sr 89 3.07E+4 8.78E+2 1.19E+3 sr 90 4.01E+5 1 ~ 02E+5 5.40E+3 Zr 95 3.01E-l 6.78E-2 6.06E-2 2.19E-3 9.61E-2 2.19E-3 6.84E+1 Mn 56 1.65E-l 3.73E-2 .2.00E-1 2.39E+1 Mo 99 8.16E+1 2.02E+1 1.74E+2 6.75E+1 Na 24 1.50E+2 1.50E+2 1.50E+2 1.50E+2 1.50E+2 1.50E+2 1.50E+2 I 131 1.86E+2 1 87E+2 1.06E+2 6.19E+4 3.08E+2 1.67E+1 I 133 3.08E+1 3.81E+1 1.44E+1 7+07E+3 6.35E+1 1.53E+1 Ni 65 2.66E-1 2.50E-2 1.46E-2 3.07 I 132 6.01E-3 1.10E-2 5.08E-3 5.12E-1 1.69E-2 1.30E-2 Cs 134 3.68E+5 6.04E+5 1.27E+5 6.29E-2 1.87E+5 6.71E+4 3.25E+3 Cs 136 3.51E+4 9.66E+4 6.25E+4 1.10E-3 5.14E+4 7.67E+3 3.40E+3 Cs 137 5.14E+5 4.92E+5 7.27E+4 9.55E-2 1.60E+5 5.77E+4 3.08E+3 Ba 140 2.48E+2 2.17E-1 1.45E+1 1.42E-4 7.09E-2 1.30E-1 1.26E+2 Ce 141 3.08E-2 1.54E-2 2.39E-3 1.13E-4 6.83E-3 1.13E-4 1.91E+1 Nb 95 5 '1E+2 2.03E+2 1.45E+2 1.14E-3 1.90E+2 1.14E-3 3.75E+5 La 140 1.31E-1 4.59E-2 1.55E-2 1.83E-5 1.83E-S 1.83E-5 1.28E+3 Ce 144 1.64 5.15E-l 8.81E-2 6.36E-4 2.85E-1 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.

Unit 1 ODCM

.Revision 13 004152LL 38 December 1993

t, A,

V lb e

g1 ~ .'gC'll

TABLE 2-7

~ VALUES LIQUID*

EMERGENCY CONDENSER VENT TEEN mrem ml hr pCi

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

• Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory 1.109, Regulatory position C, Section 1. 'uide Unit 1 ODCM Revision 13 004152LL 39 December 1993

\4

+S I 1 I'

~ Ital

TABLE 2-8 A VALUES - LIQUID*

EMERGENCY CONDENSER VENT ADULT mrem - ml hr pCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 2 27E-1 2.27E-l 2 27E-1 2.27E-1 2.27E-1 2.27E-l Cr 51 3.24E-S 3.24E-5 1.24 7.43E-1 2.74E-1 1.65 3 '2E+2 Cu 64 2.72 1.28 6.86 2.32E+2 Mn 54 1.06E-2 4.37E+3 8.33E+2 1.06E-2 1.30E+3 1.06E-2 1.34E+4 Fe 55 6.58E+2 4.55E+2 1.06E+2 2.54E+2 2.61E+2 Fe 59 1.02E+3 2.41E+3 9.22E+2 2.04E-3 2.04E-3 6.72E+2 8.02E+3 Co 58 2.88E-3 8.83E+1 1.98E+2 2.88E-3 2.88E-3 2.88E-3 1.79E+3 Co 60 1.71E-1 2.56E+2 5.65E+2 1.71E-1 1.71E-1 1.71E-1 4.81E+3 Zn 65 2.31E+4 7.36E+4 3.32E+4 Si87E-3 4.92E+4 5.87E-3 4.63E+4 Sr 89 2.18E+4 6.27E+2 3.50E+3 Sr 90 5.44E+5 1.34E+5 1.57E+4 Zr 95 2.40E-1 7.-81E-2 5.35E-2 1.88E-3 1.22E-1 1.88E-3 2.42E+2 Mn 56 1.73E-1 3.07E-2 2.20E-1 5.52 Mo 99 8.04E+1 1.53E+1 1.82E+2 1.86E+2 Na 24 1.34E+2 1.34E+2 1.34E+2 1.34E+2 1.34E+2 1.34E+2 1.34E+2 I 131 1.37E+2 1.96E+2 1.12E+2 6.43E+4 3.36E+2 5.17E+1 I 133 2.25E+1 3.91E+1 1.19E+1 5.75E+3 6.82E+1 3.51E+1 Ni 65 1.93E-1 2.50E-2 1 14E-2 6 '6E-1 I 132 4.64E-3 1.24E-2 4.34E-3 4.34E-1 1.98E-2 2.33E-3 Cs 134 2.98E+5 7.08E+5 5.79E+5 5.39E-2 2.29E+5 7.61E+4 1.24E+4 Cs 136 2.96E+4 1.17E+5 8.42E+4 9.46E-4 6.51E+4 8.92E+3 1.33E+4 Cs 137 3.82E+5 5.22E+5 3.42E+5 8.19E-2 1.77E+5 5.89E+4 1.01E+4 Ba 140 1.84E+2 2.32E-1 1.21E+1 1.21E-4 7.88E-2 1.33E-1 3.79E+2 Ce 141 .2 '1E-2 ,1.50E-2 1.78E-3 9.67E-5 7.00E-3 9.67E-S 5.68E+1 Nb 95 4.38E+2 2.44E+2 1.31E+2 9.73E-4 2.41E+2 9.73E-4 1.48E+6 La 140 9.90E-2 4.99E-2 1.32E-2 1.57E-5 1.57E-5 1.57E-5 3.66E+3 Ce 144 1.17 4.89E-1 6.33E-2 5.45E-4 2.90E-1 5.45E-4 3.95E+2

• Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section 1.

Unit 1 ODCM Revision 13 004152LL 40 December 1993

L 1

TABLE 3-1 Critical Receptor Dispersion Parameters'or Ground Level and Elevated Releases ELEVATED ELEVATED GROUNDo GROUNDo LOCATION DIR MILES ~Xsec m'i ~D~m'i ~Xsec ms+ +D~m Residences E (980) 1.4 1.8 E-07'.2 5.2 E-09~ 4.02 E-07 8.58 E-09 Dairy SE (1300) 2.6 E-08'.2 7 ' E-10'.0 6.00 E-08 1.64 E-09 Cows'ilk SE (1300) 2.6 E-08'.1 E-10'.7 6.00 E-OS 1.64 Ei..09 Goats'eat Animals ESE (1154) 1.8 E-OS'.0 E-09'.5 1.16 E-07 3.54 E-09 Gardens E (974) 1.8 E-07'.4 E-09'.4 2.53 E-07 5.55 E-09 Site Boundary ENE (674) 0.4 E-06~ E-08~ 6.63 E-06 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.

Unit 1 ObCM Revision 13 004152LL 41 December 1993

,

~

vr.~

TABLE 3-2 Gamma Air and Whole Body Plume Shine Dose Factors*

For Noble Gases Gamma Whole Gamma Air B, Body V, Nuclide meadr Ci sec m~rem

~ei aec Kr-85 2.23E-6 Kr-85m 1.75E-3 1.68E-3 Kr-87 1.02E-2 . 9.65E-3 Kr-88 2.23E-2 2.17E-2 Kr-89 2.50E-2 1.71E-2 Kr-83m 2.26E-6 Xe-'133 2.80E-4 2.41E-4 Xe-133m 2.27E-4 1.87E-4 Xe-135 2.62E-3 2.50E-3 Xe-135m 5.20E-3 4.89E-3 Xe-137 2.30E-3 2.20E-3 Xe-138 1.32E-2 1.26E-2 Xe-131m 1.74E-5 1.47E-6 Ar-41 1.64E-2 1.57E-2

• Calculated in accordance with Regulatory Guide 1.109. (See Appendix B.)

Unit 1 ODCM Revision 13 004152LL 42 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 l. 93E1 2.88E2 Kr 85m 1.17E3 1.46E3 1.23E3 1.97E3 Kr 85 1.61E1 1.34E3 1.72E1 1.95E3 Kr 87 5.92E3 9.73E3 6.17E3 1.03E4 Kr 88 1.47E4 2 37E3 1.52E4 2.93E3 Kr 89 1.66E4 1.01E4 1.73E4 1.06E4 Kr 90 1.56E4 7.29E3 1.63E4 7.83E3 Xe 131m 9.15E1 4.76E2 1.56E2 1.11E3 Xe 133m 2.51E2 9.94E2 3 '7E2 .1.48E3 Xe 133 2.94E2 3.06E2 3.53E2 1.05E3 Xe 135m 3. 12E3 7.11E2 3.36E3 7.39E2 Xe 135 1.81E3 1.86E3 1.92E3 2.46E3 Xe 137 1.42E3 1.22E4 1.51E3 1.27E4 Xe 138 8.83E3 4.13E3 9.21E3 4.75E3 Ar 41 8.84E3 2.69E3 9.30E3 3.28E3

• From, Table B-l.Regulatory Guide 1.109 Rev. 1

• • mrem/yr per pci/mi.

• • • mrad/yr per pCi/m~.

Unit 1 ODCM Revision 13 004152LL 43 December 1993

4'1 th

'i Iw% ll

TABLE 3-4 DOSE AND DOSE RATE Q VALUES INHALATION INFANTl

~rem~r pci/m NUCLIDE LIVER T. BODY

"

THYROID KIDNEY LUNG GI-LLI H 3* BONE',65E4 6.47E2 6.47E2 6.47E2 6.47E2 6.47E2 6.47E2 C 14* 5.31E3 5.31E3 5.31E3 5.31E3 5.31E3 5.31E3 Cr 51 8.95E1 5.75E1 1.32E1 1.28E4 3.57E2 Mn 54 2.53E4 4.98E3 4.98E3 1 'OE6 7 06E3 Fe 55 1.97E4 1.17E4 3.33E3 8.69E4 1.09E3 Fe 59 1.36E4 2.35E4 9.48E3 1.02E6 2.48E4 Co 58 1.22E3 1.82E3 7.77E5 1.11E4 Co 60 8.02E3 1.18E4 4.51E6 3.19E4 Zn 65 1.93E4 6.26E4 3.11E4 3.25E4 6.47E5 5.14E4 Sr 89 3.98E5 1.14E4 2 03E6 6.40E4 Sr 90 4.09E7 2.59E6 1.12E7 1.31ES Zr 95 1.15ES 2.79E4 2.03E4 3.11E4 1.75E6 2.17E4 Nb 95 1.57E4 6.43E3 3.78E3 4.72E3 4.79ES 1.27E4 Mo 99 1.65E2 3.23E1 2.65E2 1.35ES 4.87E4 I-131 3.79E4 4.44E4 1.96E4 1.48E7 5.18E4 1.06E3 I 133 1.32E4 1.92E4 5.60E3 3.56E6 2.24E4 2.16E3 Cs 134 3.96ES 7.03ES 7.45E4 1.90E5 7.97E4 1.33E3 Cs 137 5.49E5 6.12E5 4.55E4 1.72ES 7.13E4 1.33E3 Ba 140 5.60E4 5.60E1 2.90E3 1.34E1 1.60E6 3.84E4 La 140 5.05E2 2.00E2 5.15E1 1.68E5 8.48E4 Ce 141 2.77E4 1.67E4 1.99E3 5.25E3 5.17ES 2.16E4 Ce 144 3.19E6 1.21E6 1.76ES 5.38ES 9.84E6 1.48ES Nd 147 7.94E3 8.13E3 5.00E2 3.15E3 3.22ES 3.12E4

• mrem/yr per pci/m~.

'his and following g Tables Calculated in accordance with Section 5.3.1, except C 14 values in accordance with Regulatory NUREG 0133, Guide 1.109 Equation C-8.

Unit 1 ODOM Revision 13 004152LL 44 December 1993

J aA

,F

TABLE 3-5 DOSE AND DOSE RATE Q VALUES INHALATION CHILD mrem r pCi/m NUCLIDE LIVER T. BODY THYROID KIDNEY LUNG GI-LL'I H 3* BONE'.59E4 1.12E3 1.12E3 1. 12E3 1.12E3 1.12E3 1.12E3 C 14* 6.73E3 6.73E3 6.73E3 6.73E3 6.73E3 6.73E3 Cr 51 1.54E2 8.55E1 2.43El 1.70E4 1.08E3 Mn 54 4.29E4 9.51E3 1.00E4 1.58E6 2.29E4 Fe 55 4.74E4 2.52E4 7 77E3 1.11E5 2.87E3 Fe 59 2.07E4 3 '4E4 1.67E4 1 ~ 27E6 7.07E4 Co 58 1.77E3 3.16E3 1.11E6 3.44E4 Co 60 1.31E4 2.26E4 7.07E6 9.62E4 Zn 65 4.26E4 1.13ES 7 03E4 '7.14E4 9.95ES 1.63E4 Sr 89 5.99E5 1.72E4 2.16E6 1.67ES Sr 90 1.01E8 6.44E6 1.48E7 3.43ES Zr 95 1.90E5 4.18E4 3.70E4 5.96E4 2.23E6 6.11E4 Nb 95 2.35E4 9.18E3 6.55E3 8.62E3 6.14ES 3.70E4 Mo 99 1.72E2 4.26E1 3.92E2 1.35ES 1 ~ 27ES I 131 4.81E4 4.81E4 2.73E4 1.62E7 7.88E4 2.84E3 I 133 1.66E4'.51E5 2.03E4 7.70E3 3.85E6 3.38E4 5.48E3 Cs 134 1.01E6 2.25E5 3.30E5 1.21ES 3 85E3 Cs 137 9.07ES 8.25E5 1.28E5 2.82ES 1.04ES 3.62E3 Ba 140 7.40E4 6.48E1 4.33E3 2.11E1 1.74E6 1.02E5 La 140 6.44E2 2.25E2 7.55El 1.83ES 2.26ES Ce 141 3.92E4 1.95E4 2.90E3 8.55E3 5.44ES 5.66E4 Ce 144 6.77E6 2 '2E6 3.61E5 1 ~ 17E6 1.20E7 3.89E5 Nd 147 1.08E4 8.73E3 6.81E2 4.81E3 3.28ES 8.21E4

• mrem/yr per pci/m~.

Unit 1 ODCM Revision 13 004152LL 45 December 1993

l r

t I

j I

N I'

~l P

TABLE 3-6 DOSE AND DOSE RATE Q VALUES INHALATION TEEN mrem r pCi/m NUCLIDE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI

'BONE'.60E4 H 3* 1.27E3 1.27E3 1.27E3 1.27E3 1+27E3 1.27E3 C 14* 4.87E3 4.87E3 4 '7E3 4.87E3 4.87E3 4.87E3 Cr 51 1 ~ 35E2 7.50E1 3.07E1 2.10E4 3.00E3 Mn 54 5.11E4 8.40E3 1.27E4 1.98E6 6.68E4 Fe 55 3.34E4 2.38E4 5.54E3 1.24E5 6.39E3 Fe 59 1.59E4 3.70E4 1.43E4 1.53E6 1.78E5 Co 58 2.07E3 2.78E3 1.34E6 9.52E4 Co 60 1.51E4 1.98E4 8 '2E6 2.59E5 Zn 65 3.86E4 1.34ES 6.24E4 8.64E4 1.24E6 4.66E4 Sr 89 4.34E5 1.25E4 2.42E6 3.71E5 Sr 90 1.08E8 6.68E6 1.65E7 7.65ES Zr 95 1.46E5 4.58E4 3.15E4 6.74E4 2.69E6 1.49ES Nb 95 1.86E4 1.03E4 5.66E3 1.00E4 7.51E5 9.68E4 Mo 99 1.69E2 3.22E1 4.11E2 1.54ES 2.69E5 I 131 3.54E4 4.91E4 2.64E4 1. 46E7 8.40E4 6.49E3 I 133 1.22E4 2.05E4 6.22E3 2 '2E6 3.59E4 1.03E4 Cs 134 5.02E5 1.13E6 5.49E5 3.75E5 1.46ES 9.76E3 Cs 137 6.70ES 8.48ES 3.11E5 3.04E5 1.21E5 8 '8E3 Ba 140 5.47E4 6.70E1 3.52E3 2.28E1 2.03E6 2.29ES La 140 4.79E2 2.36E2 6.26E1 2.14E5 4.87E5 Ce 141 2.84E4 1.90E4 2.17E3 8.88E3 6.14E5 1.26ES Ce 144 4.89E6 2.02E6 2.62E5 1 ~ 21E6 1.34E7 8.64E5 Nd 147 7.86E3 8.56E3 5.13E2 5.02E3 3.72E5 1.82E5

• mrem/yr per pci/m~.

Unit 1 ODCM Revision 13 004152LL 46 December 1993

i',>>

TABLE 3-7 DOSE AND DOSE RATE Q VALUES - INHALATION ADULT mrem r pCi/m NUCLIDE BONE LIVER T. BODY 'HYROID KIDNEY LUNG GI-LL'I H 3* 1.26E3 1.26E3 1.26E3 1.26E3 1' 26E3 1.26E3 C 14+ 1.82E4 3.41E3 3.41E3 3.41E3 3.41E3 3.41E3 3.41E3 Cr 51 1.00E2 5.95E1 2.28E1 1.44E4 3.32E3 Mn 54 3.96E4 6.30E3 9.84E3 1.40E6 7.74E4 Fe 55 2.46E4 1.70E4 3.94E3 7.21E4 6.03E3 Fe 59 1.18E4 2.78E4 1.06E4 1.02E6 1.88E5 Co 58 1.58E3 2.07E3 9.28ES 1.06E5 Co 60 1.15E4 1.48E4 5.97E6 2.85E5 Zn 65 3.24E4 1.03ES 4.66E4 6.90E4 8.64E5 5.34E4 Sr 89 3.04ES 8.72E3 1.40E6 3.50ES Sr 90 9.92E7 6.10E6 9.60E6 7.22E5 Zr 95 1.07E5 3.44E4 2.33E4 5.42E4 1.77E6 1.50ES Nb 95 1.41E4 7.82E3 4.21E3 7.74E3 5.05ES 1.04ES Mo 99 1.21E2 2.30E1 2.91E2 9.12E4 2.48ES I 131 2.52E4 3.58E4 2.05E4 1. 19E7 6.13E4 6.28E3 I 133 8.64E3 1.48E4 4.52E3 2.15E6 2.58E4 8.88E3 Cs 134 3.73E5 8.48ES 7.28E5 2.87ES 9.76E4 1.04E4 Cs 137 4.78ES 6.21ES 4 28ES 2.22ES 7.52E4 8.40E3 Ba 140 3.90E4 4.90E1 2.57E3 1.67E1 1.27E6 2.18ES La 140 3.44E2 1.74E2 4.58E1 1.36E5 4 58E5 Ce 141 1.99E4 1.35E4 1.53E3 6.26E3 3.62ES 1.20E5 Ce 144 3.43E6 1.43E6 1.84E5 8.48ES 7.78E6 8.16ES Nd 147 5.27E3 6.10E3 3.65E2 3.56E3 2.21ES 1.73ES

• mrem/yr per pci/m~.

Unit 1 ODCM Revision 13 004152LL 47 December 1993

g l TABLE 3-8 DOSE AND DOSE RATE Q VALUES GROUND PLANE ALL AGE GROUPS mi-mremlrr pci/sec

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

~ l I'

TABLE 3-9 DOSE AND DOSE RATE VALUES COW MILK INFANT md~mr em r pci/sec NUCLIDE BONE ~LI VR T. BODY 'HYROID KIDNEY LUNG GI-LDI H 3 2.38E3 2.38E3 2.38E3 2.38E3 2.38E3 2.38E3 C 14'r 3.23E6 6.89ES 6 '9E5 6.89ES 6.89E5 6.89E5 6.89E5 51 8.35E4 5.45E4 1.19E4 1.06E5 2.43E6 Mn 54 2.51E7 5.68E6 5.56E6 9.21E6 Fe 55 8.43E7 5.44E7 1.45E7 2.66E7 6.91E6 Fe 59 1.22E8 2 '3ES 8.38E7 6.29E7 1.02ES Co 58 1.39E7 3.46E7 3.46E7 Co 60 5 '0E7 1.39ES 1.40ES Zn 65 3.53E9 1.21E10 5 58E9 5.87E9 1.02E10 Sr 89 6.93E9 1.99E8 1.42E8 Sr 90 8.19E10 2.09E10 1.02E9 Zr 95 3.85E3 9.39E2 6.66E2 1.01E3 4.68E5 Nb 95 4.21E5 1.64ES 1.17ES 1.54ES 3.03E8 Mo 99 1.04ES 2.03E7 1.55E8 3.43E7 I 131 6 ~ 81ES 8.02ES 3.53E8 2.64E11 9.37E8 2.86E7 I 133 8.52E6 1.24E7 3.63E6 2.26E9 1.46E7 2.10E6 Cs 134 2.41E10 4.49E10 4.54E9 1.16E10 4.74E9 1.22ES Cs 137 3.47E10 4.06E10 2.88E9 1.09E10 4.41E9 1.27ES Ba 140 1.21E8 1.21E5 6.22E6 2.87E4 7.42E4 2.97E7 La 140 2.03E1 7.99 2.06 9.39E4 Ce 141 2.28E4 1.39E4 1.64E3 4.28E3 7.18E6 Ce 144 1.49E6 6 10E5 8.34E4 2.46E5 8.54E7 Nd 147 4.43E2 4.55E2 2.79El 1.76E2 2.89E5 mrem/yr per pci/m~.

Unit 1 ODCM Revision 13 004152LL 49 December 1993

1

'h l ~

Iy

.kr

TABLE 3-10 DOSE AND DOSE RATE Q VALUES COW MILK CHILD mi~mrem r pCi/sec NUCLIDE L~IVE T. BODY THYROID KIDNEY LUNG GI-LLI H 3 BONE'.65E6 1.57E3 1.57E3 1.57E3 1.57E3 1.57E3 1 '7E3 C 14 3.29E5 3.29ES '.29E5 3.29E5 3.29ES 3.29ES Cr 51 5.27E4 2.93E4 7.99E3 5.34E4 2.80E6 Mn 54 1.35E7 3.59E6 3.78E6 1.13E7 Fe 55 6.97E7 3.07E7 1.15E7 " 2.09E7 6.85E6 Fe 59 6.52E7 1.06ES 5.26E7 3.06E7 1.10E8 Co 58 6.94E6 '2.13E7 4.05E7 Co 60 2.89E7 8.52E7 1.60ES Zn 65 2.63E9 7.00E9 4.35E9 4.41E9 1.23E9 Sr 89 3.64E9 1.04ES 1.41ES Sr 90 7.53E10 1.91E10 1.01E9 Zr 95 2.17E3 4.77E2 4.25E2 6.83E2 4.98E5 Nb 95 1.86ES 1.03E4 5.69E4 1.00ES 4.42ES Mo 99 4.07E7 1.01E7 8.69E7 3.37E7 I 131 3.26ES 3.28ES 1.86ES 1.08E11 5.39ES 2.92E7 I 133 4.04E6 4.99E6 1.89E6 9.27E8 8.32E6 2.01E6 Cs 134 1.50E10 2.45E10 5.18E9 7.61E9 2.73E9 1.32ES Cs 137 2.17E10 2.08E10 3.07E9 6.78E9 2.44E9 1.30ES Ba 140 5.87E7 5.14E4 3.43E6 1.67E4 3.07E4 2.97E7 La 140 9.70 3.39 1.14 9.45E4 Ce 141 1.15E4 5.73E3 8.51E2 2.51E3 7.15E6 Ce 144 1.04E6 3.26E5 5.55E4 1.80ES 8.49E7 Nd 147 2.24E2 1.81E2 1.40E1 9.94E1 2.87ES mrem/yr per pci/m~.

Unit 1 ODCM Revt.sion 13 004152LL 50 December 1993

gtl TABLE 3-11 DOSE AND DOSE RATE Q VALUES COW MILK TEEN gj~mrem r pCi/sec NUCLIDE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 BONE'.70E5 9.94E2 9.94E2 9.94E2 9.94E2 9.94E2 9.94E2 C 14 1.34E5 1.34ES 1.34E5 1.34ES 1.35E5 1.34E5 Cr 51 2.58E4 1.44E4 5.66E3 3.69E4 4.34E6 Mn 54 9 01E6 1 '9E6 2.69E6 1.85E7 Fe 55 2.78E7 1.97E7 4.59E6 1.25E7 8.52E6 Fe 59 2.81E7 6.57E7 2.54E7 2.07E7 1.55E8 Co 58 4.55E6 1.05E7 6.27E7 Co 60 1.86E7 4.19E7 2.42E8 Zn 65 1.34E9 4.65E9 2.17E9 2.97E9 1.97E9 Sr 89 1.47E9 4.21E7 1.75E8 Sr 90 4.45E10 1.10E10 1.25E9 Zr 95 9.34E2 2.95E2 2.03E2 4.33E2 6.80E5 Nb 95 1.86E5 1.03E5 5.69E4 1.00E5 4.42E8 Mo 99 2.24E7 4.27E6 5.12E7 4.01E7 I 131 1.34E8 1.88E8 1.01E8 5.49E10 3.24E8 3.72E7 I 133 1.66E6 2.82E6 8.59ES 3.93E8 4.94E6 2.13E6 Cs 134 6.49E9 1.53E10 7.08E9 4.85E9 1.85E9 1.90E8 Cs 137 9.02E9 1.20E10 4.18E9 4.08E9 1 59E9 1.71E8 Ba 140 2.43E7 2.98E4 1.57E6 1.01E4 2.00E4 3.75E7 La 140 4.05 1.99 5.30E-1 1.14E5 Ce 141 4.67E3 3.12E3 3.58E2 1.47E3 8 '1E6 Ce 144 4.22ES 1.74ES 2.27E4 1.04ES 1.06E8 Nd 147 9.12E1 9.91E1 5.94EO 5.82E1 3.58ES mrem/yr per pci/m~.

Unit 1 ODCM Revision 13 004152LL 51 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 BONE LIVER T. BODY THYROID KIDNEY ~LUN GI-LII H 3 7.63E2 7.63E2 7.63E2 7.63E2 7.63E2 7.63E2 C 14 3.63E5 7.26E4 7.26E4 7 '6E4 7.26E4 '.26E4 7.26E4 Cr 51 1.48E4 8.85E3 3.26E3 1.96E4 3.72E6 Mn 54 5.41E6 1.03E6 1 61E6 1.66E7 Fe 55 1.57E7 1 ~ OBE7 2.52E6 6.04E6 6.21E6 Fe 59 1.61E7 3.79E7 1.45E7 1.06E7 1.26EB Co 58 2.70E6 6.05E6 5.47E7 Co 60 1.10E7 2.42E7 2.06EB Zn 65 8.71ES 2.77E9 1.25E9 1.85E9 1.75E9 Sr 89 7.99ES 2.29E7 1.28EB Sr 90 3.15E10 7.74E9 9.11EB Zr 95 5.34E2 1.71E2 1.16E2 2.69E2 5.43ES Nb 95 1.09E5 6.07E4 3.27E4 6.00E4 3.69ES Mo 99 1.24E7 2.36E6 2.81E7 2.87E7 I 131 7.41E7 1.06ES 6.08E7 3.47E10 1.82ES 2 SOE7 I 133 9.09E5 1 ~ 58E6 4.82ES 2.32ES 2.76E6 1.42E6 Cs 134 3.74E9 8.89E9 7.27E9 2.88E9 9.55ES 1.56ES Cs 137 4.97E9 6.80E9 4.46E9 2.31E9 7.68ES 1.32EB Ba 140 1.35E7 1.69E4 8.83E5 5.75E3 9.69E3 2 77E7 La 140 2.26 1.14 3.01E-1 8.35E4 Ce 141 2.54E3 1.72E3 1.95E2 7.99E2 6.58E6 Ce 144 2.29ES 9.58E4 1.23E4 5.68E4 7.74E7 Nd 147 4.74E1 5.48E1 3.28EO 3.20E1 2.63E5 mrem/yr per pci/m~.

Unit 1 ODCM Revision 13 004152LL 52 December 1993

TABLE 3-13 DOSE AND DOSE RATE VALUES GOAT MILK INFANT m'mremlrr pCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 6.33E3 6.33E3 6.33E3 6.33E3 6.33E3 6.33E3 C 14 3.23E6 6.89ES 6.89E5 6.89ES 6 '9E5 6.89E5 6.89E5 Cr 51 1.00E4 6.56E3 1 ~ 43E3 1.28E4 2.93E5 Mn 54 3 '1E6 6.82E5 6.67E5 1.11E6 Fe 55 1.10E6 7.08E5 1.89E5 3. 46ES 8.98E4 Fe 59 1.59E6 2.78E6 1.09E6 8. 21E5 1.33E6 Co 58 1.67E6 4.16E6 4.16E6 Co 60 7.08E6 1.67E7 1.68E7 Zn 65 4.24ES 1.45E9 6.70ES 7.04ES 1.23E9 Sr 89 1.48E10 4.24E8 3 '4ES Sr 90 1.72E11 4.38E10 2.15E9 Zr 95 4.66E2 1.13E2 8.04E1 1.22E2 5.65E4 Nb 95 9.42E4 3.88E4 2.24E4 2.78E4 3 '7E7 Mo 99 1.27E7 2.47E6 1.89E7 4.17E6 I 131 8.17ES 9.63ES 4.23E8 3.16E11 1.12E9 3.44E7 I 133 1.02E7 1.49E7 4.36E6 2.71E9 1.75E7 2.52E6 Cs 134 7.23E10 1.35E11 1.36E10 3.47E10 1.42E10 3.66ES Cs 137 1.04E11 1.22E11 8.63E9 3.27E10 1.32E10 3.81ES Ba 140 1.45E7 1.45E4 7.48ES 3.44E3 8.91E3 3.56E6 La 140 2.430 9.59E-l 2.47E-1 1.13E4 Ce 141 2.74E3 1.67E3 1.96E2 5.14E2 8.62E5 Ce 144 1.79ES 7.32E4 1.00E4 2.96E4 1.03E7 Nd 147 5.32E1 5.47E1 3.35EO 2.11El 3.46E4 mrem/yr per pci/m3.

Unit 1 ODCM Revision 13 004152LL 53 December 1993

M WW t

J

TABLE 3-14 DOSE AND DOSE RATE R; VALUES GOAT MILK CHILD mi~mrem r pCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 4.17E3 4.17E3 4.17E3 4.17E3 4.17E3 4.17E3 C 14'r 1.65E6 3.29E5 3.29E5 3.29E5 3.29E5 3.29E5 3.29E5 51 6.34E3 3.52E3 9.62E2 6.43E3 3.36ES Mn 54 1.62E6 4.31ES 4.54E5 1.36E6 Fe 55 9 06E5 4.81E5 1.49E5 2.72E5 8.91E4 Fe 59 8 '2ES 1.38E6 6. 86E5 3.99E5 1.43E6 Co 58 8.35E5 2.56E6 4.87E6 Co 60 3.47E6 1.02E7 1.92E7 Zn 65 3.15ES 8.40ES 5.23ES 5.29ES 1.48ES Sr 89 7.77E9 2.22ES 3.01ES Sr 90 1.58E11 4.01E10 2.13E9 Zr 95 2.62E2 5.76E1 5.13E1 8.25E1 6.01E4 Nb 95 5.05E4 1.96E4 1.40E4 1.85E4 3.63E7 Mo 99 4.95E6 1.22E6 1.06E7 4.09E6 I 131 3.91ES 3.94E8 2.24ES 1.30E11 6.46ES 3.50E7 I 133 4.84E6 5.99E6 2 '7E6 1.11E9 9.98E6 2.41E6 Cs 134 4.49E10 7.37E10 1.55E10 2.28E10 5 8.19E9 3.97E8 Cs 137 6.52E10 6.24E10 9.21E9 2.03E10 7.32E9 3.91ES Ba 140 7.05E6 6.18E3 4.12ES 2.01E3 3.68E3 3.57E6 La 140 1.16 4.07E-1 1.37E-1 1.13E4 Ce 141 1.38E3 6.88E2 1.02E2 3.02E2 8.59E5 Ce 144 1.25ES 3. 91E4 6.66E3 2.16E4 1.02E7 Nd 147 2.68E1 2.17El 1.68EO 1.19E1 3.44E4 mrem/yr per pci/m~.

Unit 1 ODCM Revision 13 004152LL 54 December 1993

~ ~

TABLE 3-15 DOSE AND DOSE RATE Q VALUES - GOAT MILK- TEEN me~mrem r pci/sec NUCLIDE LIVER T. BODY THYROID KIDNEY I UNG GI-LLI H 3 BONE'.70ES 2.64E3 2.64E3 2.64E3 2.64E3 2.64E3 2.64E3 C 14'r 1.34E5 1.34ES 1.34ES 1.34E5 1 ~ 35ES 1.34ES 51 3.11E3 1.73E3 6 '2E2 4.44E3 5.23ES Mn 54 1.08E6 2.15ES 3.23E5 2.22E6 Fe 55 3.61E5 2.56E5 5.97E4 1.62ES 1.11ES Fe 59 3.67E5 8.57ES 3.31E5 2 '0E5 2.03E6 Co 58 5.46E5 1.26E6 7.53E6 Co 60 2.23E6 5.03E6 2.91E7 Zn 65 1 ~ 61ES 5 SSES 2.60ES 3.57E8 2.36ES Sr 89 3.14E9 8.99E7 3.74ES Sr 90 9.36E10 2.31E10 2.63E9 Zr 95 1.13E2 3.56E1 2.45E1 5.23El 8.22E4 Nb 95 2.23E4 1.24E4 6.82E3 1.20E4 5.30E7 Mo 99 2.72E6 5.19ES 6.23E6 4.87E6 I 131 1.61E8 2.26E8 1.21ES 6.59E10 3.89ES 4.47E7 I 133 1.99E6 3.38E6 1.03E6 4.72ES 5.93E6 2.56E6 Cs 134 1.95E10 4.58E10 2.13E10 1.46E10 5.56E9 5.70ES Cs 137 2.71E10 3.60E10 1.25E10 1.23E10 4.76E9 5.12ES Ba 140 2.92E6 3.58E3 1.88E5 1.21E3 2.41E3 4.50E6 La 140 4.86E-1 2.39E-l 6 36E-2 1.37E4 Ce 141 5.60E2 3.74E2 4.30E1 1.76E2 1.07E6 Ce 144 5.06E4 2.09E4 2.72E3 1.25E4 1.27E7 Nd 147 1.09E1 1.19E1 7.13E-1 6.99EO 4.29E4 mrem/yr per pci/m~.

Unit 1 ODCM Revision 13 004152LL 55 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 LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 BONE'.63E5 2.03E3 2.03E3 2.03E3 2.03E3 2.03E3 2 '3E3 C 14'r 7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 7 '6E4 51 1.78E3 1.06E3 3.92E2 2.36E3 4.48E5 Mn 54 6.50E5 1.24E5 1.93ES 1 ~ 99E6 Fe 55 2 '4ES 1.41E5 3.28E4 7.85E4 8.07E4 Fe 59 2.10ES 4.95E5 1.90E5 1.38ES 1.65E6 Co 58 3.25E5 7.27ES 6.58E6 Co 60 1.32E6 2.91E6 2.48E7 Zn 65 1 05EB 3.33EB 1.51EB 2.23EB 2.10EB Sr 89 1.70E9 4.89E7 2.73EB Sr 90 6.62E10 1.63E10 1.91E9 Zr 95 6.45E1 2.07E1 1.40E1 3.25E1 6.56E4

,Nb 95 1.31E4 7.29E3 3.92E3 7.21E3 4.42E7 Mo 99 1.51E6 2.87E5 3.41E6 3.49E6 I 131 8.89E7 1.27EB 7.29E7 4.17E10 2.18EB 3.36E7 I 133 1.09E6 1.90E6 5.79E5 2.79EB 3.31E6 1.71E6 Cs 134 1.12E10 2.67E10 2.18E10 8.63E9 2.86E9 4.67EB Cs 137 1.49E10 2.04E10 1.34E10 6.93E9 2.30E9 3.95EB Ba 140 1.62E6 2.03E3 1.06E5 6.91E2 1.16E3 3.33E6 La 140 2.71E-1 1.36E-l 3.61E-2 1,00E4 Ce 141 3.06E2 2.07E2 2.34E1 9.60E1 7.90E5 Ce 144 2.75E4 1.15E4 1.48E3 6.82E3 9.30E6 Nd 147 5,69EO 6.57EO 3.93E-1 3.84EO 3.15E4 mrem/yr per pci/m~.

Unit 1 ODCM Revision 13 004152LL 56 December 1993

TABLE 3-17 DOSE AND DOSE RATE Q VALUES COW MEAT CHILD m~~mrem r pci/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUN GI-LL'I H 3 2.34E2 2.34E2 2.34E2 2.34E2 2.34E2 2.34E2 C 14 5.29ES 1 '6ES 1.06ES 1.06ES 1.06ES 1.06E5 1 '6E5 Cr 51 4;55E3 2.52E3 6.90E2 4 '1E3 2 '1ES Mn 54 5.15E6 1.37E6 1.44E6 4.32E6 Fe 55 2.89ES 1.53ES 4.74E7 8.66E7 2.84E7 Fe 59 2.04ES 3.30EB 1.65ES 9.58E7 3.44ES Co 58 9.41E6 2.88E7 5.49E7 Co 60 4.64E7 1.37ES 2.57EB Zn 65 2.38ES 6.35ES 3.95ES 4.00ES 1. 12EB Sr 89 2.65ES 7.57E6 1.03E7 Sr 90 7.01E9 1.78E9 9.44E7 Zr 95 1.51E6 3.32ES 2.95E5 4.75E5 3.46EB Nb 95 4.10E6 1.59E6 1.14E6 1.50E6 2.95E9 Mo 99 5.42E4 1.34E4 1.16E5 4.48E4 I 131 4.15E6 4.18E6 2.37E6 1.38E9 6.86E6 3.72E5 I 133 9.38E-2 1.16E-1 4.39E-2 2.15E1 1.93E-1 4.67E-2 Cs 134 6.09ES 1.00E9 2.11ES 3.10ES 1.11EB 5.39E6 Cs 137 8.99ES 8.60EB 1.27ES 2.80EB 1.01EB 5.39E6 Ba 140 2.20E7 1.93E4 1.28E6 6.27E3 1.15E4 1.11E7 La 140 2.80E-2 9.78E-3 3.30E-3 2.73E2 Ce 141 1.17E4 5.82E3 8.64E2 2.55E3 7.26E6 Ce 144 1.48E6 4.65ES 7.91E4 2.57E5 1.21EB Nd 147 5.93E3 4.80E3 3.72E2 2.64E3 7.61E6 mrem/yr per pci/m~.

Unit 1 ODCM Revision 13 004152LL 57 December 1993

A TABLE 3-18 DOSE AND DOSE RATE Q VALUES - COW MEAT - TEEN me~mr emr pCi/sec NUCLIDE LIVER T. BODY THYROID KIDNEY LUNG GI-LL'I H 3 BONE'.81ES 1.94E2 1.94E2 1.94E2 1.94E2 1.94E2 1.94E2 C 14 5.62E4 5.62E4 5.62E4 5.62E4 5.62E4 5.62E4 Cr 51 2.93E3 1.62E3 6.39E2 4.16E3 4.90ES Mn 54 4 50E6 8.93ES 1.34E6 9.24E6 Fe 55 1. 50ES 1.07ES 2.49E7 6.77E7 4.62E7 Fe 59 1. 15ES 2.69ES 1.04ES 8.47E7 6.36ES Co 58 8.05E6 1.86E7 1.11ES Co 60 3.90E7 S.SOE7 5-09EB Zn 65 1 ~ 59ES 5 '2EB 2.57EB 3.53ES 2 '4ES Sr. 89 1. 40EB 4.01E6 1.67E7 Sr 90 5.42E9 1.34E9 1.52ES Zr 95 8.50E5 2.68E5 1.84ES 3.94ES 6.19EB Nb 95 2.37E6 1.32E6 7.24ES 1.28E6 5 '3E9 Mo 99 3.90E4 7.43E3 8.92E4 6.98E4 I 131 2.24E6 3.13E6 1.68E6 9. 15EB 5.40E6 6.20E5 I 133 5.05E-2 8.57E-2 2.61E-2 1.20E1 " 1.50E-1 6.48E-2 Cs 134 3.46ES 8.13ES 3.77ES 2.58ES 9.87E7 , 1.01E7 Cs 137 4.88ES 6.49EB 2.26ES 2.21EB 8.58E7 9.24E6 Ba 140 1.19E7 1.46E4 7.68ES 4.95E3 9.81E3 1.84E7 La 140 1.53E-2 7.51E-3 2.00E-3 4.31E2 Ce 141 6.19E3 4.'14E3 4 75E2 1 ~ 95E3 1.18E7 Ce 144 7 '7ES 3.26ES 4.23E4 1.94E5 1.98EB Nd 147 3.16E3 3.44E3 2.06E2 2.02E3 1.24E7 mrem/yr per pci/m~.

Unit 1 ODCM Revision 13 004152LI 58 December 1993

8 V

. ~

r,

TABLE 3-19 DOSE AND DOSE RATE g

'icr VALUES COW MEAT ADULT pci/sec emr NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LBI H 3 3 25E2 3.25E2 3.25E2 3 '5E2 3.25E2 3.25E2 C 14 3.33E5 6.66E4 6.66E4 6.66E4 6.66E4 6.66E4 6.66E4 Cr 51 3.65E3 2.18E3 8.03E2 4.84E3 9.17E5 Mn 54 5.90E6 1.13E6 1.76E6 1.81E7 Fe 55 1.85ES 1.28E8 2.98E7 7. 14E7 7. 34E7 Fe 59 1.44ES 3.39ES 1.30ES 9.46E7 1.13E9 Co 58 1.04E7 2.34E7 2. 12ES Co 60 5.03E7 1.11E8 9.45ES Zn 65 2.26ES 7.19ES 3.25E8 4. 81ES 4.53ES Sr 89 1.66ES 4.76E6 2.66E7 Sr 90 8.38E9 2.06E9 2.42ES Zr 95 1.06E6 3.40E5 2.30ES 5.34E5 1.08E9 Nb 95 3.04E6 1.69E6 9.08E5 1 ~ 67E6 1.03E10 Mo 99 4.71E4 8.97E3 1.07ES 1.09E5 I 131 2.69E6 3.85E6 2.21E6 1.26E9 6.61E6 1.02E6 I 133 6.04E-2 1.05E-1 3.20E-2 1.54E1 1.83E-1 9.44E-2 Cs 134 4.35ES 1.03E9 8.45ES 3.35ES 1.11ES 1.81E7 Cs 137 5.88ES 8.04ES 5.26ES 2.73ES 9.07E7 1.56E7 Ba 140 1.44E7 1.81E4 9.44E5 .6.15E3 1.04E4 2.97E7 La 140 1 ~ 86E-2 9.37E-3 2.48E-3 6.88E2 Ce 141 7.38E3 4.99E3 5.66E2 2 '2E3 1.91E7 Ce 144 9.33E5 3.90ES 5.01E4 2.31ES 3.16ES Nd 147 3.59E3 4.15E3 2.48E2 2.42E3 1.99E7 mrem/yr per pci/m~.

Unit 1 ODCM Revision 13 004152LL 59, December 1993

TABLE 3-20 DOSE AND DOSE RATE VALUES VEGETATION CHILD me~mrem r pci/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 4.01E3 4.01E3 4.01E3 4 '1E3 4.01E3 4.01E3 C 14'r 3.50E6 7.01ES 7.01E5 7.01E5 7.01ES 7.01E5 7.01ES 51 1.17E5 6.49E4 1.77E4 1.18E5 6.20E6 Mn 54 6.65ES 1.77ES 1.86ES 5.58ES Fe 55 7 '3ES 4.05E8 1.25ES 2.29E8 7.50E7 Fe 59 3.97ES 6.42E8 3.20E8 1. 86E8 6.69ES Co 58 6 45E7 1.97ES 3.76ES Co 60 3.78ES 1.12E9 2.10E9 Zn 65 8.12ES 2 '6E9 1.35E9 1.36E9 3.80E8 Sr 89 3.59E10 1.03E9 1.39E9 Sr 90 1.24E12 3.15E11 1.67E10 Zr 95 3.86E6 8.50E5 7.56E5 1.22E6 8.86ES Nb 95 1.02E6 3.99E5 2.85E5 3.75ES 7.37ES Mo 99 7.70E6 1.91E6 1.65E7 6.37E6 I 131 7.16E7 7.20E7 4.09E7 2.38E10 1.18ES 6.41E6 I 133 1.69E6 2.09E6 7.92E5 3.89ES 3.49E6 8.44E5 Cs 134 1.60E10 2.63E10 5.55E9 8.15E9 2.93E9 1.42ES Cs 137 2.39E10 2 29E10 3.38E9 7.46E9 2.68E9 1.43ES Ba 140 2.77ES 2.43ES 1.62E7 7.90E4 1.45ES 1 '0ES La 140 3.25E3 1.13E3 3.83E2 3.16E7 Ce 141 6.56E5 3.27E5 4,85E4 1.43E5 4.08ES Ce 144 1.27ES 3.98E7 6.78E6 2.21E7 1.04E10 Nd 147 7.23E4 5 86E4 4.54E3 3.22E4 9.28E7 mrem/yr per pci/m~.

Unit 1 ODOM Revision 13 004152LL 60 December 1993

I A

1 I

. ~

l

TABLE 3-21 DOSE AND DOSE RATE Q VALUES - VEGETATIONTEEN mi~mrem r pCi/sec NUCLIDE 'BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LTI H 3 2.59E3 2.59E3 2.59E3 2.59E3 2.59E3 2.59E3 CD 14 1.45E6 2.91E5 2.91E5 2.91ES 2.91E5 2.91ES 2.91E5 Cr 51 6.16E4 3.42E4 1.35E4 8.79E4 1.03E7 Mn 54 4.54EB 9,01E7 1.36ES 9 '2ES Fe 55 3.10ES 2.20ES 5.13E7 1.40EB 9.53E7 Fe 59 1. 79EB 4.18ES 1.61ES 1 '2ES 9.89ES Co 58 4.37E7 1.01ES 6 '2ES Co 60 2.49ES 5.60ES 3.24E9 Zn 65 4 24EB 1.47E9 6.86ES 9.41ES 6.23EB Sr 89 1.51E10 4.33EB 1 SOE9 Sr 90 7e51E11 1 'SE11 2 '1E10 Zr 95 1.72E6 5.44E5 3e74E5 7.99ES 1 '6E9 Nb 95 4.80E5 2.66ES 1 '6ES 2.58E5 1.14E9 Mo 99 5.64E6 1 'SE6 1.29E7 1 '1E7 I 131 3.85E7 5.39E7 2.89E7 1.57E10 9.28E7 1.07E7 I 133 9.29E5 1.58E6 4.80ES 2.20EB 2.76E6 1.19E6 Cs 134 7.10E9 1.67E10 7.75E9 5.31E9 2.03E9 2.08EB Cs 137 1.01E10 1.35E10 4.69E9 4.59E9 1.78E9 1.92EB Ba 140 1.38ES 1.69ES 8.91E6 5.74E4 1.14ES 2. 13EB La 140 1.81E3 S.SSE2 2 '6E2 5.10E7 Ce 141 2.83ES 1.89E5 2.17E4 8.89E4 5.40EB Ce 144 5.27E7 2.18E7 2.83E6 1.30E7 1.33E10 Nd 147 3.66E4 3.98E4 2.3863 2.34E4 1.44ES mrem/yr per pci/m~

Unit 1 ODCM Revision 13 004152LL 61 December 1993

i

"'qp' h

1I ~

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

Unit 1 ODOM Revision 13 004152LL 62 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 Value Reference Fish U (kg/yr) adult 21 Reg. Guide 1.109 Table E-5 Fish D~ (mrem/pCi) Each Radionuclide Reg. Guide 1.109 Table E-11 Shoreline U

- (hr/yr) adult 67 67 Assumed Reg. Guide 1.09 to be same as Adult teen Shoreline Each Radionuclide Reg. Guide 1.109 (mrem/hr per pCi/mi) Table E-6 Inhalation DFA Each Radionuclide Reg. Guide 1.109 Table E-7 Unit 1 ODCM Revision 13 004152LL 63 December 1993

eg 1I

NINE MILE POINT NUCLEAR STATION RADIOLOGICALENVIRONMENTALMONITORING PROGRAM SAIVlPLING LOCATIONS TABLE 5.1 Type of

• Map Sam le Location Collection Site Env. Pro ram No. L tion Radioiodine and Particulates (air) 1 Nine Mile Point Road North (R-1) 1.8mi I 88' Radioiodine and Particulates (air)

Co. Rt. 29 5 Lake Road (R-2) 1,1 mi I 104o ESE Radioiodine and Particulates (air)

Co. Rt. 29 (R-3) 1.5 mi I 132'E Radioiodine and Particulates (air)

Village of Lycoming, NY (R-4) 1.8mi I 143~ SE Radioiodine and Particulates (air)

Montario Point Road (R-5) 16.4 mi I 42o NE Direct Radiation (TLD) North Shoreline Area (75) 0.1mi@5~ N Direct Radiation (TLD) North Shoreline Area (76) 0.1 mi I 25o NNE Direct Radiation (TLD) North Shoreline Area (77) 0.2 mi I 45o NE Direct Radiation (TLD) North Shoreline Area (23) 0.8 mi I 70~ ENE Direct Radiation (TLD) 10 JAF East Boundary (78) 1.0 mi I 90o E Direct Radiation (TLD) Rt. 29 (79) 1.1 mi I 115~ ESE Direct Radiation (TLD) 12 Rt. 29 (80) 1.4 mi I 133~ SE Direct Radiation (TLD) 13 Miner Road (81) 1.6 mi I 159o SSE Direct Radiation (TLD) 14 Miner Road (82) 1.6 mi I 181~ S Direct Radiation (TLD) 15 Lakeview Road (83) 1.2 mi I 200~ SSW Direct Radiation (TLD) 16 Lakeview Road (84) 1.1 mi I 225o SW Direct Radiation (TLD) 17 Site Meteorological Tower (7) 0.7 mi I 250o WSW Direct Radiation (TLD) 18 Energy Information Center (18) 0.4 mi I 265~ W

• Map = See Figures 5.1-1 and 5.1-2 Unit 1 ODCM Revision 13 004152LL 64 December 1993

k 4

if 0

Yi ~k

'r

NINE IVIILE POINT NUCLEAR STATION RADIOLOGICALENVIRONMENTALMONITORING PROGRAM SAMPLING LOCATIONS TABLE 5.1 (Continued)

Type of *Map am le Location Collec ion Site Env. Pro ram No. L ation Direct Radiation (TLD) 19 North Shoreline (85) 0.2 mi I 294~ WNW Direct Radiation (TLD) 20 North Shoreline (86) 0.1 mi I 315'W Direct Radiation (TLD) 21 North Shoreline (87) 0.1 mi I 341 o NNW Direct Radiation (TLD) 22 Hickory Grove (88) 4.5 mi I 97~ E Direct Radiation (TLD) 23 Leavitt Road (89) 4.1 mi I 111 ESE Direct Radiation (TLD) 24 Rt. 104 (90) 4.2 mi I 135o SE Direct Radiation,(TLD) 25 Rt. 51A (91) 4.8 mi I 156 SSE Direct Radiation (TLD) 26 Maiden Lane Road (92) 4.4 mi I 183o S Direct Radiation (TLD) 27 Co. Rt. 53 (93) 4 4 mi I 205o SSW Direct Radiation (TLD) 28 Co. Rt. 1 (94) 4.7 mi I 223~ SW Direct Radiation (TLD) 29 Lake Shoreline (95) 4.1 mi I 237~ WSW Direct Radiation (TLD) 30 Phoenix, NY Control (49) 19.8 mi I 163~ S Direct Radiation (TLD) 31 S. W, Oswego, Control (14) 12.6 mi I 226o SW Direct Radiation (TLD) 32 Scriba, NY (96) 3.6 mi I 199'SW Direct Radiation (TLD) 33 Alcan Aluminum, Rt. 1A (58) 3.1 mi I 220~ SW Direct Radiation (TLD) 34 Lycoming, NY (97) 1.8 mi I 143'E Direct Radiation (TLD) 35 New Haven, NY (56) 5.3 mi I 123~ ESE Direct Radiation (TLD) 36 W. Boundary, Bible Camp (15) 0.9 mi I 237~ WSW Direct Radiation (TLD) 37 Lake Road (98) 1.2 mi I 101~ E Surface Water 38 OSS Inlet Canal (NA) 7.6 mi I 235o SW Surface Water 39 JAFNPP Inlet Canal (NA) 0.5 mi I 70o ENE (NA) = Not applicable

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

NINE MILE POINT NUCLEAR STATION RADIOLOGICALENVIRONMENTALMONITORING PROGRAM SAMPLING LOCATIONS TABLE 5.1 (Continued)

Type of *Map Sam le Lo a i n Collec ion Si e Env. Pr ram No. Lo ai n Shoreline Sediment 40 Sunset Bay Shoreline (NA) 1.5 mi 5 80~ E Fish 41 NMP Site Discharge Area (NA) 0.3 mi 5 315'W (and/or)

Fish 42 NMP Site Discharge Area (NA) 0.6 mi 5 55~ NE Fish 43 Oswego Harbor Area (NA) 6 2 ml y 235o SW Milk 44 Milk Location ¹50 8.2 mi 5 934 E Milk 45 Milk Location ¹7 5.5 mi 5 107~ ESE 0

Milk 47 Milk Location ¹65 17.0 mi 5 220~ SW Milk 64 Milk Location ¹55 9.0 mi 5 95~ E Milk 65 Milk Location ¹60 9.5 mi 5 90~ E Milk 66 Milk Location ¹4 7.8 mi 5 113~ ESE Milk (CR) 73 Milk Location 13.9 mi 5 234~ SW (Woodworth)

Food Product 48 Produce Location ¹6++ 1.9 mi 5 141~ SE (Bergenstock) (NA)

Food Product 49 Produce Location ¹1++ 1.7 mi@96~ E (Culeton) (NA)

Food Product 50 Produce Location ¹2++ 1.9 mi 5 101~ E (Vitullo) (NA)

Food Product 51 Produce Location ¹5++ 1.5 mi y 114o ESE (C.S. Parkhurst) (NA)

Food Product 52 Produce Location ¹3++ 1.6 mi@ 84o E (C. Narewski) (NA)

The Jones milk location has been deleted due to the herd being sold. (Map location ¹46.)

• 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 Control Result (location)

Unit 1 ODOM Revision 13 004152LL 66 December 1993

NINE IVIILE POINT NUCLEAR STATION RADIOLOGICALENVIRONIVIENTALMONITORING PROGRAIVI SAMPLING LOCATIONS TABLE 5.1 (Continued)

Type of

• Map am I Loca ion Collec ion i Env. Pr ram No. L ion Food Product 53 Produce Location ¹4++

(P. Parkhurst) (NA) 2.1 mi I 110~ ESE Food Product (CR) 54 Produce Location ¹7++

(Mc Millen) (NA) 15.0 mi I 223 SW Food Product (CR) 55 Produce Location (NA)

¹8

'Denman) 12.6 mi I 225 SW Food Product 56 Produce Location (O'onnor) (NA)

¹9 1.6 mi I 171~ S Food Product 57 Produce Location (C. Lawton) (NA)

¹10 2.2 mi I 123 ESE Food Product 58 Produce Location ¹11 (C. R. Parkhurst) (NA) 2.0 mi I 112~ ESE Food Product 59 Produce Location (Barton) (NA)

¹12 1.9 mi I 115 ESE Food Product (CR) 60 Produce Location (Flack) (NA)

¹13 15.6 mi I 225 SW Food Product 61 Produce Location (Koeneke) (NA)

¹14 1.9 mi I 95o E Food Product 62 Produce Location (Whaley) (NA)

¹15 1.7 mi I 136'E Food Product 63 Produce Location (Murray) (NA)

¹16 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)

Unit 1 ODCM Revision 13 004152LL 67 December 1993

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

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

E 4t

~ saldteFI IISI 24 FIGURE 5.1-2 SCALE OF hlILES t

e.tt LEGEND NINE MILE POINT Courtly Lltloe..

III OFF-SITE MAP Tees Llsal..

Cky A VNale Uaea..................

hei leoode ..

ENVI~NTAL ~K...........Q

( 1 2/'93)

LOCA IIOSS 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 42 2 L AEE Al 5l 44 ONT ARIO I 63 3 4

33 ~ Il ssellaas avs laae asset devel Ot lsl Seassl Total See<<e

~ 4 S

g5 4

4Attavv 41 gatv>>

Sle sv<< tv 34 ll 48 5 'g IS l~ I

~ <<I Sf

~ 66 I%I IIIIII Ygsa

<<\

~ <<

I 4 ee

~

wtIITIOed l N E A Y -6 N d

4 S ~ ealvee llleslcd

<<l4 eltt <<es I<< ~ 'v I

~

~ tttl 4 I loess <<II II

~ III lee I<< OS+QGgO St<<W<<tl I

~

l.

<<4 v Ie SI 5 C Is II I B A I

n

~.s M

<<

l.

~

c X i I Ovate ~ a 44 la Od Wed ~4 I<<~ I %l<<<<l ~

'dCO 'i<<.

4 Yeast ~ v g t<<v<< ~~ ~ eve

C

, I A

J J

sP, f

II II, 7p'

P" ki I

~ Ml 'll 33 (y/'$ 'i~: t 3

3/'-

err r. tonne ~

~ os' vtfwsn r

I h too /

pell Se>>p )1-j '/'::.

neo Oelr,

)

CMOM

"=- V~'i '(~~

I

,i3l 0

I S L,~Y/ qq P hsl

~3 ~ \

H t)est);R I I>>

~1 I

IOPI'I Co wu ~ )lentor Co ness 1

r '>>

i

~

MWO I ~

~ AX

>>~/ltt

~ a

~e

)e re ms>>I ,Pres>>O ost'5 Cs nord 5I rr a Pwca

)

~1 Corners I. E It M 0

~ >> le )5 se

'M Rws St>>5 M Stos CIISRJ rrveer A. IWWM ~1 ll Oon SS wm ol l)sl Pelenno I rrr

~ I 5 ~1

%~~I0 45 0 5/

Cancel tosl V ~ I~ h

- 'e.

Poloemo 3

re rnwl ~ IM Olhtr p pest corhtr5 I

/ Corners

,'5'r h~s <<E aool nein I I Comers

~ I I I oeooso I Deoln C

6 Hannibal )

~

I

.I ~ C I FULTOM Can 3

I 5\Is I'I I L .ÃItrtlaohm i

N ON. 8 I

r 3

R Iss N  ;,8M l nnehosoe It ~ I

>>>>W Center hah>> oe ~r

~ nao So

) $ P new i

"~ l( Ioo eoo es Mlo n ROWeVS Irma aI' ~

Corhtrs ,i>>>>I M

lro 5Mlo>>l ~

(3

>>mela, 0

~ I ~

Is I 5$ I>> >>,ee>> M

Ã0 COUNTY I~ >>I>>re oa. 1 nwI MW Po IC P. sole ~

CAYUGA neer P)reel>>M oh

>>I ~

>> al Ih t ~ Watn IL IV ~

WM eel ~

at ~>>M>>a u re)o>>KI IE Soot hsw>>oa M Po Solos net h~ ONONI)AGA

'4 I ~ \e M l s)

RIY+

Pe Seen>>su 20 M 79

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

APPENDIX A LIQUID DOSE FACTOR DERIVATION Unit 1 ODCM Revision 13 004152LL 71 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

-ii<~ (1-e

+ ) (DFS),)

(>.> (4)

Where:

Is the dose factor for nuclide i, age group af total body or organ t, for all appropriate pathways, (mrem/hr per pCi/ml) .

Ko Is the unit conversion factor, 1.14E5=1E6pC1/pCi x 1E3 ml/kg : 8760 hr/yr.

U 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, Sediment Shoreline Usage (hr/yr); from Table E-5 of Reg. Guide 1.109.

(BF)i Bioaccumulation factor for nuclide, i, in fish, (pCi/kg, per pCi/1), from Table A-1 of Reg. Guide 1.109.

(DFL)hl Dose conversion factor for age, nuclidei group a, total body or organ t, (mrem/pCi); from ii Table E-ll of Reg. Guide 1.109.

(DFS) ) 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).

Unit 1 ODCM Revision 13 004152LL 72 December 1993

4 vent,

%ps

Appendix A (Cont'd)

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).

69.3 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').

Shore width factor (unitless) from Table A-2 of Reg.

Guide 1.109.

r~

Example Calculation For I-131 Thyroid Dose Factor for an Adult from a Radwaste liquid effluents release:

(DFS) ) 2.80E-9 mrem/hr per pCi/m~

(DFL)L, 1.95E-3 mrem/pci t~ 30 hrs. (w = water)

BF) 15 pCi/Kg per pCi/L t< 24 hrs. (f = fish)

Ur 21 Kg/yr tb 1.314E5 hrs. (5.48E3 days)

D 40 unxtless U = 730 L/yr D, 12 unitless Ko = 1.14E5 Ci Ci ml k

'U, 12 hr/yr (hr/yr)

W 0.3 3.61E-3hr'rs 5.5 (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 included in a revision to the ODOM.

it will be calculated and In addition, not all dose factors are used for the dose calculations. A maximum 0

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.

Unit 1 ODCM Revision 13 004152LL 73 December 1993

0 I

APPENDIX B PLUME SHINE DOSE FACTOR DERIVATION Unit 1 ODCM Revision 13 004152LL 74 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:

Air Gamma 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,)

Energy of gamma ray per disintegration (Mev)

V, average wind speed for each stability class (s),

downwind distance (site boundary, m) sector width (radians) subscript for stability class IE 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 PEta Vi 1. 11SB;e 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 Mev .46

[1293 g ] [100 ~er ]

g-rad

~k~~ Where: = mass attenuation coefficient PE p (cd/g; air for B<< tissue for V<)

p, = defined above Unit 1 ODCM Revision 13 004152LL 75 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.

Unit 1 ODCM Revision 13 004152LL 76 December 1993

c)~

'4.4,e

(, ~

ll

APPENDIX B (Cont'd)

SAMPLE CALCULATION Ex. Kr-89 F STABILITY CLASS ONLY Gamma Air

-DATA E

p 2.22MeV 2 943 E-3m 5.5064E-3m' k ~

=

~ pa 644m

= .871 K ~

V =

.46 5.55 m/sec p

e .39 cr, ~ 19m.......vertical plume spread taken from "Introduction to Nuclear Engineering", John R. LaMarsh

'

-I Function Uc, .06 Ii .33 Ig .45 a I, + kIq .33 + (.871) (.45) = -72 dis ~

B< 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 1E3mrad rad Ci/s (~1E6 C1)

Ci

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) meadr 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.

Unit 1 ODCM Revision 13 004152LL 77 December 1993

APPENDIX C DOSE PARAMETERS FOR IODINE 131 and 133, PARTICULATES AND TRITIUM Unit 1 ODCM Revision 13 004152LL 78 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 R was. 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) K'BR) ~ (DFA) g, where:

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) ~ Breathing rate of the receptor of age group a, (units = m~/yr);

(DFA) 1F 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; 1400 Child 3700 Teen 8000 Adult 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.

Unit 1 ODCM Revision 13 004152LL 79 December 1993

1 V

Eo +<

APPENDIX C (Cont'd)

C.2 Ground Plane Pathwa K'K SF DFG 1-e

-l,t W(G)

Where:

Dose factor for the ground plane pathway for each identified radionuclide i for the organ of interest Q(G)

(units = m~-mrem/yr per pCi/sec)

A constant of unit conversion, lE6 pCi/pCi K

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.

Unit 1 ODCM Revision 13 004152LL 80 December 1993

i' I

lk

APPENDIX C (Cont'd)

C.3 Grass- Cow or Goat -Milk Pathwa

~ K' F r D.L ~ff + (~1-f f)(e-l,,t~ e

-l,t, Q(C)

Yz Y, Where:

K'ose Q(C) 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)

The agricultural productivity by unit area of pasture feed grassy (units ~ kg/m2)

Y, 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) LL The 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)

Unit 1 ODCM Revisi.on 13 004152LL 81 December 1993

'4, ~

p I i Hg J

'k P

t. 44

~

~

t

(Cont'd) 0'raction APPENDIX C 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) 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 H Absolute humidity of the atmosphere, (units g/m~)

0.75 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.

Unit 1 ODCM Revision 13 004152LL 82 December 1993

8'*

I ~

9la Jt l(c a Jfp

~

,

APPENDIX C (Cont'd)

C.4 Grass-Cow-Meat Pathwa

= K' r DFL + (~1-f f ) (e e

-litr g(C) F [~f1

(1) + 1~) [ Yp ,Y, Q(M) Dose factor for the meat ingestion pathway for radionuclide for any organ of interest, (units ~ m~-mrem/yr per pci/sec) i 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'K' 'FQP~(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:

-A,t-l,t R(V) =

K'(l, + 1.)

(DFL)~ U",Fe + U',F,e Unit 1 ODCM Revision 13 004152LL 83 December 1993

Nl

'V N

I

'Xi '

APPENDIX C (Cont'd)

Where:

Q(V) Dose factor for vegetable pathway for radionuclide i for the organ .af interest, (units = m~-mrem/yr per pCi/sec)

K'L 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)

Us The consumption rate of stored vegetation by the receptor in age group a (units kg/yr)

Fg The fraction of the annual intake of fresh leafy vegetation grown locally Fq 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)

Yv 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.

Unit 1 ODCM Revision 13 004152LL 84 December 1993

TABLE C-1 Parameters for Grass-(Cow or Goat)-Milk Pathways Reference Parameter Value Re . Guide 1.109 Rev. 1 a< (kg/day) 50 (cow) Table E-3 6 (goat) Table E-3 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 (DFL)> (mrem/pCi) Each radionuclide Tables E-11 to E-14 F (pCi/liter per pCi/day) Each stable element Table E-1 (cow)

Table E-2 (goat)

Y, (kg/m~) 2.0 Table E-15 Y~ (kg/m ) 0.7 Table E-15 t~ (seconds) 7.78 x 10~ (90 days) Table E-15 t~ (seconds) 1.73 x 10'2 days) Table E-15 U (liters/yr) 330 infant Table E-5 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 Unit 1 ODCM Revision 13 004152LL 85 December 1993

TABLE C-2 Parameters for the Grass-Cow-Meat Pathway Reference Parameter Value Re . Guide 1.109 Rev. 1 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15

'I F, (pCi/Kg per pCi/day) Each stable element Table E-1 U (Kg/yr) 0 infant Table E-5 41 child Table E-5 65 teen Table E-5 110 adult Table E-5 (DFL)@ (mrem/pCi) Each radionuclide Tables E-11 to E-14 Y (kg/mi) 0.7 Table E-15 Y, (kg/m ) 2.0 Table E-15 tb (seconds) 7.78E6 (90 days) Table E-15 tf ( seconds ) 1.73E6 (20 days) Table E-15 Qr (kg/day) 50 Table E-3 Unit 1 ODCM Revision 13 004152LL 86 December 1993

TABLE C-3 Parameters for the Vegetable Pathway Reference Parameter Value Re . Guide 1.109 Rev. 1 r (dimensionless) 1.0 (radioiodines) Table E-1 0.2 (particulates) Table E-1 (DFL) > (mrem/pCi) Each radionuclide Tables E-11 to E-14 U"), (kg/yr) infant 0 Table E-5

- child 26 Table E-5 teen 42 Table E-5 adult 64 Table E-5 U') ~ (kg/yr ) infant 0 Table E-5 child 520 Table E-5 teen 630 Table E-5

- adult 520 Table E-5 t (seconds) 8.6E4 (1 day) Table E-15 t (seconds) 5.18E6 (60 days) Table E-15 Y(kg/m~) 2.0 Table E-15 Unit 1 ODCM Revision 13 004152LL 87 December 1993

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

~'l

~

• r <>,tp yg 'ted%

w C

V~AV ~YQQ~

WL i<<sees na PIPING INSTRUHENT ANO EOUIPHENT SYHBOLS ~ asl ICCW>>e loco W St<<

IL<a lssl<<stol le%11% al ~ .I Data ossa<<a ~ lessee lotto IKI<<OK calla aoo lal<<tcsf DCCI ll<<h ~

nialD leil (KCS IK<<<KK t>>ala< Isow I Lect CKCL COSCC I lee I[ FS I H>>I-atoll<<lf ICallll SKI<<<oe KKK Calls lee s<<<<tsl tcscfailoo K Ke I 0 Kt Ks teat I I so I~ Ia IK CI CI ~ CI sso cal I

~ sH t>>K 0>>K k >>I Otl Isas OIKCII<<o

~ LD ~ SK ~ IC ~I ~I ta tl ~s ~ I I~ ~ K ~ I ~ I I ~ st<le a Kaw KIIIOLIKI

<<Dates QS I II ~ I Sal >>e L LK I IC LC SCt ~ I IO Lt ~ ~ IIL 011 Shel II tl

<<I IIOS

<<Dao <<

~ SK I IK IK K th ete

~I

~ I

~f

~ I

~

~ os I II I~

~ ~ t~

~ I s~

~ 00 sse + Olatsssa II<<

lowe oss /teal ths SPEC I A NOI oLI

~ I<<all ~ l>>ca taai chs <<S4 sssase<<IL SKS<

>i< <<e>>se<<coocts lssl>>sas >>IC awl L,a s<<os<<ss>> ~ ~, <<SosD fl<< Ke<<D ts>> ~ K >>% ) Sa<< eai Cha ~ 0, ecs ssesaes ~ A.~ <<<<la t>>flCIla I lh D0 eel ~ e<<}el ste ~ 8 a<I }I !Is ~ tl ess<< t<<cs e<<K vii ~ 1>> 0. a e oee K >>casse%a CLOaaos ~ <<s ~ <<>> ~ l LIWSSL lsn It<'t<lit<It<I ~ I <<L<(ll < Itt~ ll<IM. yt<Lyj QIJ',RAIIQII stol ~ eel ~ ~ ss 00 ' ' 'ea '\ <<Os le c esses, Coo<<a ~PP NZ~QLS..YLIIIILAI.IQILQ8MPEI6 !F==. ~ IK<oc ~ ~ 0 I I~ 0<<o 01 I>>of Is I ~ B. ~ ~ Ill Ksee Ital a lashl S<<I ff a<<s lo<<LSSD e<<K le '<<he<>> t<<sl ~ ~ t, >>sa>>lease%os< a ccl ~ Ke a>>I I-F ON EV ICE S la>> Q~aYaa. II<I I'I ~ ~ eee<< t<<0>>. LD <LCKK WICI +<< V+A VE fleets<a% POSU~ON sess<<es<<<<. 818. LQtIIBOL VllLYESKBAUOK ~ ttttlJC<htlUtdh eslK ss<<s clos(i RC~Lsa.ttaLRBt<I<<t Q 0<<o toss De51Iw I ~ -. <<I ~ <<e>>e s<<0 0 ~dl-. -lb~ ~s sas ~ ~-- ~- ee<<sl >>a nD IOIKSI seilst Ole I<<ss Y RXMYrkR Ioc<< tiL AVclsw -Ill- .V,- .T: Q ~ M till< sa KOCI ~ sss atn ~ )Ks<<. oes <<<l>>SO 0 cowl Se Isl ~ o>>>>oa a<<atilt (A~to>>et K I K C>>K ~ Sae <<>>sl 00<<CC.IKKsha g~l tsossl 0 LSLL 'steps<< ~KL ~ ~ I Se tao lie%a l<<L~~I F>> c>> Pttt<PS ANO FANS O'.S<<<mS<<t<tttm %CKKO t>> XPANss I ON JOINTS ~AZL halosla <<ol <lssasssa<< esse scone I>> E KS %<<S<<0 tie <<C ~ SKO ~4 sess< sss ea see<< tscsslosll ~ assi al II K~'JR ~ II nte cote% 0 sea Kcsssssssl>> 4"~fo<<C. ~ D swtel YK 5 ~ ~ ~ e>>oo <<<<CO co<<toss <<ees shtl <<>>SI ~ OSCDIK o<<L Cecal Isle G' S<<\0 ss Kal t>><<saa ~ Le<<IS IteLtolol ~ OK 110'sl FIGURE ce <<sso<< <<s<<L ses I ~ st I SLOC ~ Ial oac ~ittt~isa ~ K>>ol <<S<< ts<<SSS Qsl lessee<<<<sss ~ PIP INC, IMSTINHEMT lUI0 OQIPIIIMT ~ SL<<o <<s ss sss ~ 8 0 es ~ I et<< oee ~ SSS OS <<so A I IS<< oll Lj Ksse<<sei I SYM80LS I I selt stool It<At At<A aottsesw<c < owtH Co<<<oct<<<%<<oft NINE MILE I'OINT-UNIT 1 AI OLJO I OFFSITE DOSE CALC. MANUAL 8 J RADIOA.IIVL WA~It III;I OSAI .;V.;II N lo coeoeelc ltoea ~ ea Ieewel ooveV<< ooe Ieetl tees teltl ovtt lett to ooeet coot le,l ~ ev<< le.let Wh No'w ~ aoOO OLOOOel<<t vt et ~ottllooe tee ~ CI ~ Itlte ~ ltlee clett<<ID tocteDIIo wtl Mice Iee tw ott Iccetl r-~ DIV O ~ I oe glels eel\I le)lceo a<<etc@I tllite Cocle OL eo Oaf to <<'LCN '4 \ Io loo,ve IOCIVtet<< Wtl lee el // ~ O Dt Wtl Oltl a+a << ttee LIC COV Octet et ltte oev oet ~ ~ IIteo Decl tnt ~ ow <<e ta.Isle eooooo teel eve << teelwtl eoovotto ~ <<etc etIID Iee CIVCVOICO WIC Ito tve ~ <<tate lite ~ e ooL ~ Leos octo te<<cc IM VVI~ COICCIV cocle'tellto ettl IW elt oao wt ~ ~ ee  ! <<4L ~ CO<<OIV ~ eeI IOCIe~tW Ilie Ie<<OI W IOIIC tote I I eol tello I~ Catt<<<<ISO eetlt tteot oe etL Coo Iee tello tee o Vttl tee CttttCIOI ~ cello Ccctol <<ao wt osw tet octt Itlo lee ow oet ~ ettl evee IIV ~ Ioel DV FIGURE D <<te ~ Sw oet IIIitttIS Iee ~ L~e ett RADIOACTIVE MASTE DISPOSAL SYSTEH ~ CCOGAAA uOSCOSNÃ CCOWKII 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 Ig'II I~~ AI ~ Il. ~ lj o ~ I I AIAA ~ \ I AWW~ l ~ I A ~ . ~ ~ ~ A %II ~, II %AA tAI 1 ~ IKIAI I ~ ~ ~ wa IAM fIGUAE D-1 SIEAH PACKING EKHAUSTER AHO RECOHBIHER SYSTEH MAOIAAAMOHAWIC POWtH CONPOHA'IIOM NINE MILF POINT-UNIT l OFFSIDE DOSE CALC. MANUAL A' REACTOR BUILDING VENTILATION SYSTEM )P< Qn ) ~--=a=.m Qo( -@- II ) Q+.)") ( ee a>>ae<< lweala Ec a ~ I.) ~ We te4<<e' e lre rr<<II w Isa>>a )).=.) )3 <<e El ~ra I>>el E>> era 0 ~ <<e ~ ~ ~ ~ ~ ~ y 4. ~a ~ ~ ~ ea oa N ac~a <<C rill ~ l<< e lre ~ IN'r Il<<ll w'eos ~ ~ ~ ~ ~ ~ I I ~ ~ Qt a gee a<<rises O eNSS LQ~ l<<e.IraI>>' << e<<elena'ere

-.4:pg)-)

-- ta)- ty-)erl.) C7 I LL) ~ ~ ~ I>>ac Elree ae awr ~ alr <<areaeaes I e II<<g~<<'1 w 1 b aa ra a rl ~ er waaaa ~ <<T r EL ~ ease Ie)e 1>> Liaaw 1 c<<e, >>I'roe a) Ir )ii'1eil 1 ra IV~e>> I e<<c. nr sees elae I<< r<<e I<<er I seeeeL aee ace c, IN' I>> <<e r %El'ee<<aa <<rr ~ OEI I<<se wl hg ~ Walla 'aaa ~ eel J<< ~ Iae. I 'i.P. <<<<<<o ~ ~ sa I '<< o oa es I sae 1 le aea ~ F)GU))E I)-7 I REACTOR BUILDING VERT ILATION STSTEH )IIAi)A)lALJOHJWK )IOW) )1 1 OIZ)I@HA)IQ)J NINE MILE POINT-UNIT 1 OI'F SITE DOSE CALC. MANUAL 0-3 \ I +'I WASTE DISPOSAL BUILDING VENTILATION SYSTEM ~ >>taa(t>>a kt k Att Q>>,...... kk &I ket <<L taa t)~ek ~ ke k III ~ ~ ~ Qt ~ eke Igf akke 4- -~V>> <<t 3 ~ Ikitek ke ~ Ie 3 IF/ Q l I) ke ~ I 3 tea I~ ~ lt' A>><< ~ .'III t. e ~ k kk~ kAk e e e I ~ r Q>> 3 ~~ J ~ ~ I ~ ".744 ~ k<<at ~ Pk kk It kae ak ~ k 0 I >>eat I& Lk lkaklkt I' YAAI I ~ I'k@ e ~ A ke k ktkPl h l,eg ~ Ql>>>>k>> 3 I ~Vrp~J Ik I>> ~~I>> akk eit ~ ekki H kl ~ F~ Ill Itt f >><<kkt I>> Lh+. Q <<1+1'<<t f I+A ~ ktk. att I>> akk iat ~, te>> t>>tklk vC 4'~u '& gf tkkkt ~ Iet ~ ~ A>>t Ik tikke tk ~ I tk keg k k.'II<< i. I~ L >> kt ~ gK ~ kk stk tkakk kk. Ia ka tk k Ik ~ ~ ~ .----S 0----'IWIk kkl FIGURE p- J l h Tll V IIASTE 0ISPOSAL BVILOING VENTILATION SYSILH HIAtiAAAAIOI<<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 PLAT1CRM ~ ~4RRQ. h,AM CLRYATIO4 GRAPHIC I,' I I I I PLATfoN4 Ieo IIIN CTIC LLfRX, ~ PROaf I I . ( I PLATPORM I PLLTTGR LI coIc.twrelopa fLa50'4'rc tL.aaJO' OPP OL'5 LPCa oI ~ g ~ gLaeTIO < ae JlilL'0~ TOP FIGURE D-5 Qo I OVATION LOOKING +OATH SI I Stack NIAGARA MOHAWK POWER CORPORATION 0-5 NINE MILE POINT-UNIT 1 OFFSITR DON@ CALCo MANUAL l OFF GAS BUILDING VENTILATION SYSTEM ~ tte Ws we h et ~ ~ ~ ~ ~ q e ~ ~ ~ ss ee ~ etYI~K ~ ~ Klltll ~le ~ ~ Otl K' ~stl ~Is <<I ~ ott'e'tts la es ee e Jtl e'lOOC ~ <<LItte I e A&I IIOOIK OslIOIte 4'a es ~ sett tg <<I ketle e w'K'IGURE te es OFFGAS BUILOING VEIITILATION SYSTEN IIAQAAAMOHOWOO OIOWLQ CG4OVVHAO<OOO NINE MILE POINT-UNIT 1 e~t w>> &t ~ OFFSITE DOSE CALO. MANUAL ~ les 4' 0-6 PRINTER CRT PARTCUl.ATE INSTRUMENTATION IODINE CABINET INPUT/DILUTION DETECTOR8 STATION (3) MAIN FRAME FIGURE SImpIIfIed VIew of Hodel 400 Stacks Honltor NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 1 0-7 OFFSITE DOSE CALC. MANUAm.
• RAGEMS RAG EMS Dilutian Samph 11241 Return ISOKINETIC PROBE RN 21 112-13t 112-52 Stack Sam 112-55 3 112-30 112-132 OGESMS Intet 11243 112-57 3
112-133 OGESMS Ou5el 112-56 J, P Figure D- 8 Stack Sample and Sample Return NIAGARAMOHAWK POWER CORPORATION NINE MILE POINT - UNIT 1 OFFSITE DOSE CALC. MANUAL 0-8 C -A il OV3 OV1 OV13 RAGEMS 112-169 112-165 112& RAG EMS Inlttt DiluSon %Supply Inlet OV5 OV8 112-173 L 112-178 OV4 112-130 OV7 OFS1 1 2-1 'l12-171 112-101A 112-51 OV2 PI 112-167 PGV 112-21 112-106 112-110 OFS4 112- 04A OFG1 112-101 OFC4 PGV 112-104 112-107 112-111 Pl 11 .122 112-116 OFS2 OFC3 OCF2 112-102A 112-103 OFS3 11 -102 112-103A 112-151 OV12 OV16 Scunpte 112+7 RAG EMS 112-150 Return Ou5et 112-112 Pl 112-124 Pl 112-113 'l1 - 23 112-118 112-117 Opl OV8 11 - 44 112143 Figure D- 9 RAGEMS Dilution Schematic NIAGARAMOHAWK POWER CORPORATION NINE MILE POINT - UNIT 1 OFFSITE DOSE CALC. MANUAL D-9 Pi' } RahuQ Ttitium 3V16 1'12-218 112-73 112.74 Pl 112-125 112-72 1V3 1V4 2V3 2V4 112-183 112-185 112-199 112-201 3FS1 1FS1 112-105A 112-129 11246 112-114 3V3 112. 7 Pl 1V1 2V1 3V1 3V5 112-126 g g 1Q.1 12.181 112-1 112-197 11245 11249 3CVI 112-105 -76 112-11 1VS 1V6 2VS 2V6 11 1 -78 112-187 112-202 112-203 3 112.186 3V4 3V6 3V7 2V11 11248 112-100 112-211 112-208 1V11 112-192 Pl 11244 Pl 11247 3P1 112-% 108 1V17 11219 3V11 112-215 3V10 112-214 Fi ure D-10 3V1 112-217 3V12 112-216 RAGEMS Schematic 112-109 NIAGARAMOHAWKPOWER CORPORATION NINE MILE POINT - UNIT 1 OFFSITE DOSE CALC. MANUAL 0-10 'EQ ) t V' 11242 112-10 RN43A FS 11249 11246 112-11 67 11 -93 112-147 112-59 FL1 112-58 112-148 12-149 'l1264 1'l245 Inlet 112-146 112-u u 112- u u 11261 11260 62 63 112-112-152 1'l2-137 153 112-154 Pl P 11248 FCV 112-137 112-91 112-161 11244 112-163 112-134 112-138 Fl PS2 112-139 1'l2-140 11246 11 - 35 11 44 .112-FS 135 112-94 112-22 112-21 112-155 V/PI 11245 12-158 11 w 112-156 112-20 112-142 112-141 11240 112-159 112-157 112-13 112-19 112-1 112 14 112-15 12 11249 112-70 12-71 11207 11248 Fi ure D-11 OGESMS Schematic 112-12 NIAGARAMOHAWK POWER CORPORATION NINE MILE POINT - UNIT 'I OFFSITE DOSE CALC. MANUAL e Qh pl 4>> 4 ATTACHNENT 2 '"'@;.;::",wxegg~e,~e;i'.;;.;.m~~t~),','~>-;..~~;~,.'.y~rt~g)r,;.;n~:~<<o'"'.g;:, >~@:No. -';I 7 NlAGARA iver ~jQCENSNG!DQCUMBgjCHANGEREQUEST'" UMQHAA'K '."~.',vg@",~@~;gym >;<g:-:. ~,rg~j~~qw~ymj~yw:.~~~~~,>>, I <<4(p. D 0 g:"",:!. 0 0 '.':".; IN PArrr 1 /Nr77A7toN Page ~of ~ A. Affected Doc OPL Plans If Programs g Unit 1 Q Facitity Operating Ucense Q UFSAR Q Ste Emergency Phn (SEP) Q IS Program Ran (ISI) Q Q Secunty Phns (SPS) Q IST Program Phn (IS7) Q Unit2 Q Technical Specifications QuaRy Assur Program d Q Core Operating Umits Rept 0 Environmental Prot Phn Q Rre Prot Program Otfsite Dose Cato Manual (ODM) (COL) B. Descnpiion permanent Q Tanporary, Errpectrrd Duratfo(L @ d rttt.d w ~ ~enn~d We. $ gZ 7- / OOCN, Pago Section, Figure, Table h3 / References ~ D. Soutce of Change ~~ gas ',r~f yy,to r9, P'~~+it/I ~ ~ +. f~, MOM(.r~, ~ P /'s na ~~cn(otl (rro~~ '1tdnrt /tn ~d(~ /r/g 7/p (n A d, (.(n 6( dDcitr.)'. NIP4EV41 Review gQ progninly eratuat fortrgahrty Rn(/rnrr ttacfred 0 F Otiginato gi /Q. Date ///4 9/y g PAR7' RaVraW/APPROVAt. 4SME(Prfnmacy Q NA Date ud, '3 B. ReSp Oig BranCh Manager (Pkeh5a/I 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&IRM1Submitta/Require( 9 NN Obta/ned per Doc Cotrersheot Q Obta/nod por MP4EV4f tartar NMlate: Q NRC AppTDate: llrd SAR~ -g/r Jqg PART ~LZQEVTA77ON PAR7'4-Ct.crlrRz 4 OPL Only: Affected D ocuments Updated Q tt. p tnooto'd into potont Doo, +R B. Q Not Yot tnooot'd into ontont  ;,kicoip'.d;Rev:

,'gy'

" g~:,.".tg Close Chango Tracfong Doc, App'd for Rtnr. B. UFS Only: Need'Askuilt'r Affoct Documont Q C. Chsodby (Petrfretta() Date C. Othen r 8 Q z I 77lG/7l.d.s &VI /.> Qo Page ll NIP-LPP-01 Rev 02 6$ %J 1OI 5M' ATTACHNEHT 3 R No """':""<-~~~"'"~"- 'ev o I Q UFSAR Page~a S 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? 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 Q Yos QNo ~ Does the SEP, as changed, cease to meet the standards of 10CFR50.47(b) and 10CFR50 Appendix E? 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 QYes QNo 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 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". 7 ere i'rt'E'S 0 diaz~. 7.S. PaEPmea (Printltnitfal) ~liZMM >. Won~ Page 12 NIP-LPP-01 Rev 02 4" lg. zf If No. I apt I oi + ~ M U'!J R J! 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 in w'hNRCR I n nd7 hnical i 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 nu 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 u in in i 'n r niza n ha FAR r o o ural-mm nt NIP-SEV%1 0041 58LL Rev 0

g" No, ( -20 I Page 2 of 4 NMP U RJ R Jl 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 In 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 EVALUATIONIS REQUIRED? YES XNO NIP-SEV%1 0041 58LL Rev 0 t+ fi J Co" II v A I~ No. Page 3 of 4 NMPM'J R 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? YES. N~

"3. Result in an activity not confined to on-site areas previously disturbed during site preparation and plant construction? 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 ENVIRONMENTALEVALUATIONIS REQUIRED? YES N~ NIP-SEV-01 0041 58LL Rev 0 Al E No. Page 4 of 4 NMP Un R .J! FR PRELI I R EVAL ATl (Cont'd) 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. agency

2. agency B. Does commitment(s) need to be changed? (Yes')

If yes, notify the NRC Program Director. V. 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. NIP-SEVZ1 0041 58LL Rev 0