ML20196C599

Forwards Rev 4 to Part a of Offsite Dose Calculation Manual (Odcm),Adding ODCM Rev 4 to Bottom of Each Page.Changes to Odcm,Part B Will Be Submitted Upon NRC Approval of Changes to Part a

ML20196C599
Person / Time
Site:	Seabrook
Issue date:	02/04/1988
From:	George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NYN-88014, NUDOCS 8802160184
Download: ML20196C599 (26)

Text

.

-e I-George S. Thomas V6ce Presiderd Nucleo: Production NYN-88014 Put2C h W h @

New Hampshire Yankee Division February 4, 1983 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:

Document Control Desk

References:

(a) Facility Operating License NPF-56, Docket No. 50-443 (b) USNRC Letter dated May 20, 1986, "Seabrook Station Technical Specification Improvement Program', T. M. Novak to R. J. Harrison (c)

PSNH Letter (SBN-1122) dated June 17, 1986, 'Seabrook Station Offsite Dose Calculation Manual (ODCM): Revised Manual', G. S. Thomas to V. S. Noonan (d) NUREG-0896 "Safety Evaluation Report Related to the Operation of Seabrook Station, Units 1 and 2'

Subject:

Seabrook Station Offsite Dose Calculation Manual (ODCM): Proposed Revision Gentlemen In Reference (b) the NRC Staff advised that specific information and tables could be removed from the Seabrook Station Technical Specifications and included in the ODCM.

Reference (c) submitted the ODCM for Staff review with the specific information stipulated in Reference (b) included as Part A.

Supplement 6 to Reference (d) dated October 1986 approved the Seabrook Station ODCM submitted by Reference (c).

The Seabrook Station ODCM is a controlled document and as such, adminis-trative procedures require that each page of the manual have a revision number at the bottom of each page.

The document revision numbers were not indicated at the bottom of each page.

The ODCM which was transmitted via Reference (c) for the Staff's review was in fact Revision 3, though this was not indicated at the bottom of each page.

Section 6.13.2(a) of the Seabrook Station Technical Specifications requires that changes to Part A of the ODCM be submitted to and approved by the NRC Staff prior to implementation.

In accordance with that requirement, enclosed please find all of Part A of the Seabrook Station ODCH. The only change is the addition of '0DCM Rev. 4' to the bottom of each page.

No other changes to Part A have been made.

8802160184 880204 PDR ADOCK 05000443 I

l P

PDR P.O. Box 300. Seabrook. NH 03874. Telephone (603) 474 9574

United States Nuclear Regulatory Commission February 4,-1988 Attention:

Document Control Desk Page 2

.Accordingly, changes to Part B of the ODCH, to reflect the addition of

'0DCM Rev. 4' to the bottom of ea'ch page, will be made in accordance with Section 6.13.2(b) of the Seabrook Station Technical Specifications once NRC approval is received to make the requested changes to Part A.

It is requested that the Staff inform us of their concurrence regarding the proposed ODCM change as soon as possible to facilitate our administrative controls and distribution.

Should you have any questions regarding this matter, please contact Mr. Warren J. Hall.at (603) 474-9574, extension 4046.

Very truly yours, George /C h S. Thomas Enclosure cci Mr. Victor Nerses. Project Manager Project Directorate I-3 Division of Reactor Projects United States Nuclear Regulatory Commission Washington, DC 20555 Mr. Antone C. Cerne NRC Senior Resident Inspector Seabrook Station Seabrook, NH 03874

ENCLOSURE TO NYN-88014 SEABROOK STATION OFFSITE DOSE CALCULATION MANUAL PART A i

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Pnet A RADIOLOGICAL EFFLUENT MONITORING PROGRAMS

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1.0 INTRODUCTION

The purpose of Part A of the ODCM (Of f-Site Dose Calculation Manual) is to describe the sampling and analysis programs conducted by the Station which provide input to the models in Part B for calculating liquid and gaseous ef fluent concentrations, monitor setpoints, and of f-site doses.

The results of Part B calculations are used to determine compliance with the concentration and dose requirements of Technical Specification 3/4.11.

The Radiological Environmental Monitoring Program required as a minimum to be conducted (per Technical Specification 3/4.12) is described in Part A, with the identification of current locations of sampling stations being utilized to meet the program requirements listed in Part B.

The information obtained from the conduct of the Radiological Environmental Monitoring Program provides data on measurable levels of radiation and radioactive materials in the environment necessary to evaluate the relationship between quantities of radioactive materials released in ef fluents and resultant radiation doses to individuals from principal pathways of exposure. The data developed in the surveillance and monitoring programs described in Part A to the ODCM provide a means to confirm that measurable concentrations of radioactive materials released as a result of Seabrook Station operations are not significantly higher than expected based on the dose models in Part B.

1.

Pending review and resolution of the staff's concerns regarding applied dispersion parameters for Method I gaseous dose calculations, the limits shall be reduced by a factor of 10.

This restriction will ensure compliance with 10CFR20 Appendix B and 10CFR50 Appendix I.

Upon satisfactory review and resolution of the concerns regarding dispersion parameters with the staf f, this restriction will be deleted from the ODCM.

2.

Method II gaseous and liquid dose calculations shall not be implemented until additional information is provided describing in sufficient detail the methodology used in Method II gaseous and liquid dose calculations.

Upon review, approval and incorporation of this methodology detail in Part B of the ODCM, this restriction will be deleted from the ODCM.

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A.1-1 ODCM Rev. 4 i

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2.0 RESPONSIBILITIES FOR PART A i

All changes to Part A of the ODCM shall be reviewed and approved by the l

Station Operations Review Committee (SORC) and the Nuclear Regulatory j

Countsston prior to implementation.

It shall be the responsibility of the Station Manager to ensure that the ODCM is used in the performance of the surveillancs requirements and j

administrative controls.of the appropriate portions of the Technical l

-Specifications.

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L 3.0 LIQUID EFFLUENT SAMPLING AND ANALYSES PROGRAM 4

Radioactive liquid wastes shall be sampled and analysed in accordance-with the program specified in Table A.3-1 for Seabrook Unit 1.

The results of the radioactive analysis'shall be used as appropriate with the methodology of Part B of the ODCM to assure that the concentrations of liquid effluents at the point of release from the multiport diffuser of the circulating water j

i system are maintained within the limits of Technical Specification 3.11.1.1 for Unit 1.

Radioactive effluent information for liquids obtained from this I

sampling and analysis program shall also be used in conjunction with the methodologies in Part B to demonstrate compliance with the dose objectives and surveillance requirements of Technical Specifications 3/4.11.1.2, 3/4.11.1.3, i

and 3/4.11.4.

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TABLE A.3-1 Radioactive Liquid Waste Sampling and Analysis Program 1

i Minimum Type of Liquid 8'"E

""E Release Analysis Activity l

Frequency (LLD) (1)

Type Frequency Analyss. s

, ;7, )

A.

Liquid P

P Principag3 gamma

,7 Radwaste Each Batch Each Batch Emitters 5x 10 Test Tanks

-6 1-131 1 x 10 i

(Batch Release)

P M

Dissolved and I x 10-Each Batch /M Entrained Cases (Camma Emitters)

-5 P

M H-3 1 x 10 Each Batch Composite Cross Alpha

'l x I&~

-8 P

Q Sr-89, Sr-90 5x 10 Each Batch Composite

-6 Fe-55 1 x 10 Effluent (g9

?rincipag3 gamma i

B.

Turbine Build W

W

,7 Grab Sample Emitters 5x 10 Sump 2

-6 1-131 1 x 10 (Continuoug

-5 Release)

W M

Dissolved and I x 10 Grab Sample Entrained Cases q.

(Gamma Emitters)

A.3-2 ODCM Rev. 4

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TABLE A.3-1 Radioactive Liquid Waste Sangling and Analysis Program (continued)

Lower Limit Li uid MI"I"""

Type of S

Pling of Detection Re case Analys s Activity Frequency (LLD) (1)

Frequency Analysis

(,c;f,g)

W M

H-3 1 x 10~

1 Grab Sample Cross Alpha 1 x 10~

-8 W

Q Sr-89, Sr-90 5x 10 Grab Sample

-6 Fe-55 1 x 10 4

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W Principal Gamma Blowdown Flash Emitters ( )

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Crab Sample 5x 10 Tank (6)(8)

-0 I-131 1 x 10 (Continuoul5)

-5 Release)

W M

Dissolved and 1 x 10 Grab Sample Entrained Cases (Camma Emitters)

-5 W

M H-3 1 x 10 Grab Sample s

Cross Alpha 1 x 10-

-8 W

Q Sr-89,-Sr-90 5x 10 Grab Sample

-6 Fe-55 1 x 10 4

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A.3-3 ODCM Rev. 4 4

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Lower Limit Liquid M a. nsmum g,

Typg of of Detection Release Analysis Activity p

, p (LLD) (1)

Type Frequency Analysis

j, )

D.

Service Water (7)

Principak3h*""*

W W

-7 Crab Sample Emitters 5 x-10

-0 I-131 1 x 10 W

M Dissolved and 1 x 10-Crab Sample Entrained Cases (Gamma Emitters)

-5 W

M H-2 1 x 10 Crab Sample Gross Alpha 1x 10-

-8 W

Q Sr-89, Sr-90 5x 10 Crab Sample

-6 Fe-55 1 x 10 P - Prior to Discharge W - Weekly M - Monthly Q - Quarterly r

A.3-4 ODCM Rev. 4

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TABLEA[3-1 Radioactive Liquid Waste Sampi ng and Analysis Progg (continued)

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Notations (1)The LLD is defined, for purposes of these specifications, as the smallest l

concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent

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probability with only 5' pere'ent probability of falsely concluding that a i

blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical F

separation:

t 4.66 s b

LLD =

[

E x v x 2.22 x 10 x Y x exp (-

t) i i

Where:

LLD = the "a priori" lower limit of detection (microcurie per unit mass i

or volume),

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s = the standard deviation of the background counting rate or of the f

b counting rate of a blank sample as appropriate (counts per minute),

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E = the counting efficiency (ccunts per rtisintegration),

V = the sample size (units of mass or volume),

i 2.22 x 10-6 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, j

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= the racioactive decay constant for the particular radionuclide (s g), and t = the elapsed time between the midpoint of sample collection and the time of counting (s).

Typical values of E, V, Y, and t s,hould be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the j

fact) limit representing the capability of a measurement system and not as an a,posteriori (af ter the fact) limit for a particular measurement.

(2)A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then j

thoroughly mixed to assure representr.tive sampling.

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TABLE A.3,.

Rcdionctiva Liquid Weste Snrpling end Anolysis Progrom (con t inued-)

Notations.

(3)The principal gamma emitters for which the LLD specification applies includes the following radionuclides:

Mn-54, Fe-59, Co-58, co-60, zn-65, l

4 Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be i

analyzed and reported in the Semiannual Radioactive Effluent Release Report in accordance with Technical Specification 6.8.1.4.

Isotopes which are not detected should be repo:ted as "not detected." Values determined to be below detectable levels are not used in dose calculations.

(4)A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the

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method of sampling employed results in a specimen that is representative of the liquids released.

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A continuous release is the discharge of liquid wastes of a nondiscrete

volume, e.g., from a volume of a system that has an input flow during the continuous release.

(0 Sampling and analysis is only required when Steam Generator Blowdown is directed to the discharge transition structure.

(7) Principal gamma emitters shall be analyzed weekly in Service Water.

Sample and analysis requirements for dissolved and entrained gases,

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tritium, gross alpha, strontium 89 and 90, and Iron 55 shall only be required when analysis for principal gamma emitters exceeds the LLD.

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a.

PCCW sampled and analyzed weekly for principal gamma emitters.

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b.

Sauple Service Water Systen (SWS) daily for principal gamma emitters whene3erprimarycomponentcoolingwater(PCCW)activityexceeds 4

1x10 uC/cc.

c.

With the PCCW System radiation monitor inoperable, sample PCCW and SWS daily for principal gamma emitters, d.

With a confirmed PCCW/SWS leak and PCCW activity in excess of 1x10" uC/ce, sample SWS every 12, hours for principal gamma emitters.

e.

The setpoint on the PCCW head tank liquid rate-of-change alarm will be set to ensure that its sensitivity :o detect a PCCW/SWS leak ir equal to or greater than that of an SWS radiation monitor located in the unit's combined SWS discharge, with an LLD of 1x10"3 uC/ce.

If tnis sensitivity cannot be achieved, the SWS will be sampled once every 12 j

hours.

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(8)If the Turbine Building Sump (Steam Generator Blowdown Flash Tank) isolate due to high concentration of radioactivity, that liquid stream will be j

sampled and analyzed for lodine-131 and principal gamma emitters prior to release.

A.3-6 ODCM Rev. 4 i

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i 4.0 GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM t

I Radioactive gaseous vastes shall;be esmpled.ind analyzed in accordance I

with the program specified in Table A.4-1 'for Seabrook Unit 1.

The results of the radioactive analysen-shall be used as appropriate with the methodologies l

of Part B of the ODCM to assure that the dose rates due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary are within the limits of Technical _ Specification 3.11.2.1 l

for Unit 1.

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Radioactive effluent information for gaseous wastes obtained from this sampling and analysis program shall also be used in conjunction with the methodologies in Part B to demenstrate compliance with the dose objectives and i

surveillance requirements of Technical Specifications 3/4.11.2.2, 3/4.11.2.3, 3/4.11.2.4, and 3/4.11.4.

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TABLE A.4-1 Radioactive Caseous Waste Sampling and Analysis Program Gaseous Lower Limit-l Sampling YPe f of Detection snamum 4

Release Analysts Actsvaty 7

(LLD)'(1)

J Type Frequency Analysas (uCi N )

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M(3)(4)

Pr.incspa 1.

Plant Vent M

Emitters {famma Crab Sample 1 x 10 l

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H-3 1 x 10 Continuous W

1-131 1 x 10-Charcoal Sample Continuous (5)

W(6)

-11 Principak2 gamma 1 x 10 Particulate Emitters i

Sample s

Continuous M

Gross Alpha 1 x _10-I composite Particulate Sample Continuous (5)

Q Sr-89, Sr-90 1 x 10-II

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Composite Particulate Sample 2.

Condenser Air M( }

M Principal Camma 1 x.10' Removal Exhaust Crab Sample Emitters

-0 H-3 1 x 10 l

A.4-2 ODCM Rev. 4 i

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TABLE A.4-1 Radioactive Gaseous Waste Samding and Analysis Program (contInuedT aseous Minimum Type of

""E

'"E Release Analysis Activity Frequency (LLD) (1)

Type Frequency Analysts y

3.

Cland steam continuous W

Principa Emitters {famma

~ I Packing Particulate 1 x 10 Exhauster Sample

-12 Continuous W

I-131 1 x 10 Charcoal Sample

~II Continuous M

Gross Alpha 1 x 10 Composite Particulate Sample s

Continuous

-II Q

Sr-89, Sr-90 1 x 10 composite Particulate Sam de Principa 1 x 10~

4.

Containment P

P Emitters {famma Purge Each Purge Each Purge Grab Sample

-6 11-3 (oxide) 1 x 10 A.4-3 ODCM Rev. 4

TABLE A.4-1 Radioactive Gaseous Waste Sampling and Anaiysis Program (continued)

Notations I The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95-piecent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD =

D E x V x 2.22 x 10 x Y x exp (-

t)

Where:

LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume),

the standard deviation of the background counting. rate or of the s =

b counting rate of a blank sample as appropriate (counts per minute),

E = the counting ef ficiency (counts per disintegration),

V = the sample size (units of mass or volume),

-6 2.22 x 10

= the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, the radioactive decay constant for the particular radionuclide

=

(s~g), and t = the elapsed time between the midpoint of sample collection and the time of counting (s).

Typical values of E, V, Y, and t should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (af ter the fact) limit for a particular measurement.

4 A.4-4 ODCM Rev. 4 4

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TABLE A.4-1 Radioactive Caseous Waste Sampling and Analysis Program (continued)

Notations

(

The principal gamma emitters for which the LLD specification applies includes the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54. Fe-59, co-58, C -60, 3

Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, and Cc-144, in iodine and particulate releases. This list does not mean that'only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report in accordance with Technical Specification 6.8.1.4.

Isotopes which are not detected should be reported as "not detected." Values determined to be below detectable levels are not used in dose calculations.

(3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within a one hour period unless; 1) analysis shows that the DOSE EQUIVALENT I-131 concentrations in the primary coolant has not increased more than a factor of 3; 2) the noble gas activity monitor for the plant vent has not increased by more than a factor of 3.

For containment purge, requirements apply only when purge is in operation.

(4) Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.

(5)The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Technical Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.

(6) Samples shall be changed at least once per seven (7) days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.

Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least seven (7) days following each thutdown, startup, or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within a one-hour period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10.

This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more 'than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

(7) Samples shall be taken prior to start-up of condenser air removal system when there have been indications of a primary to secondary leak.

4 A.4-5 ODCM Rev. 4

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4 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 Sampling and Analysis Program The' Radiological Environmental Monitoring Program (REMP) provides representative measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides that lead to the-highest potential radiation exposure of members of the public resulting from station operation. This monitoring program is required by Technical Specification 3.12.1.

The monitoring program implementsSection IV.B.2 of Appendix I to 10CFR, Part-50, and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than' expected on the b' asis of ef fluent measuremer.ts and the modeling of the environmental exposure pathways i

I which have been incorporated into Part B of the ODCM.

i The initially specified nonitoring program will be ef fective for at least the first three years of commercial operation.

Following this period, program changes any be initiated based on operational experience.

In accordance with Technical Specification surveillance requirements, 4.12.1, sampling and analyses shall be conducted as specified in Table A.5-1 for locations.shown in Section 4 of Part B to the ODCM.

Detection capability requirements, and reporting levels for radioactivity concentrations in environmental samples are shown on Tables A.5-2 and A.5-3, respectively.-

It should be noted that Technical Specification 3.12.1.C requires that if milk or fresh leafy vegetable samples are unavailable from one or more sample locations required by the REMP, new specific locations for. obtaining replacement samples (if available) shall be added to the REMP within 30 days, and the specific locations, from which the samples are unavailable may then be deleted from the monitoring program.

In this context, the term unavailable means that smaples are no longer available to be collected now or in the future for reasons such as the permission from the owner to collect the samples has been withdrawn or he has gone out of business, thus causing the permanent lose of the sample location.

A.5-1 ODCM Rev. 4

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5.2 Land Use census As part of the Radiological Environmental Monitoring Program, Technical Specification 3/4.12.2 requires that a land use census be conducted annually 1,

during growing season to identify within a distance of 8 km the location in eachofthe16meteorologicalsectorsofthenearestm{lkanimal,thenearest residence, and the nearest garden of greater than 50 m prodiscing broad leaf vegetation.

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The land use census ensures that changes in the use of area beyond the site boundary are identified, and appropriate modifications to the monitoring I

program and dose assessment models are made, if necessary.

This census satisfies the requirem nts of Section IV.3.3 of Appendix I to 10CFR Part 50.

For the purpose of conducting the land use census as required by l

Technical Specification 4.12.2, station personnel should determine what survey j

methods will provide the necessary results considering the type of information l

to be collected and the use to which it will be put, such as the location of potential milk animal pathway for use in routine dose calculations.

Land use census results shall be obtained by using a survey method, or combination of methods, which may include, but are not limited to, door-to-door surveys (i.e., roadside identification of locations), aerial surveys, or by consulting

. local agricultural authorities.

Technical Specification 3.12.2.b requires that new locations identified from the census that yield a calculated dose of dose commitment 20 percent greater than at the location from which samples are currently being obtained be added within 30 days to the REMP.

These new locations requried to be added I

to the sampling program shall only be those from which permission from the owner to collect samples can be obtained and sufficient sample volume is available.

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4 A.5-2 ODCM Rev. 4

TABLE A.5-1 I

Radiological Environmental Monitoring Program Exposure Pathway Number of Representative Sam Sampling and Type and Frequency and/or Sample and Sample Locations

• ples Collection Frequency of Analysis b

1.

DIRECT RADIATION 40 routine monitoring stations Quarterly Gamma dose quarterly, with two or more dosimeters placed as follows:

An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY; An outer ring of stations, one in each meteorological sector, generally in the 6 to 8-km range from the site; The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and control

'loca t ions.

2.

AIRBORNE d

Radioiodine and Samples from five' locations :

Coatinuous sampler Radioiodine Cannister:

j Particulates operation with sample Three samples from'close to the collection weekly, or I-131 analysis weekly.

three SITE BOUNDARY locations, more frequently if-in dif ferent sectors, of high required by dust.

Particulate Sampler:

calculated long-term average

loading, ground-level D/Q.

Cross beta radioactivity.

i analysis following filter One sample ' from the vicini ty of change ;

C a communitu having the highest Gamma isotopic analysis

• calculated long-term average of' composite (by location) ground-Level D/Q..

quarterly.'

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~ODCM Rev. 4 e

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TABLE A.5-1 Radiological Environmental Monitoring Program (Continued)

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Exposure Pathway Number of Representative Samples Sampling and Type and Frequency and/or Sample and Sample Locations

• Collection Frequency of Analysis One sample from a control location, as for example 15-30 km distant and in the least prevalent wind direction.

3.

WATERBORNE a.

Surface One sample in the discharge area.

Monthly grab sample.

Camma isotopic analysis

• One sample from a control location.

monthly. Composite for tritium analysis quarterly.

b.

Sediment from One sample from area with existing Semiannually.

Camma isotopic analysis

• from or paiential recreational value.

semiannually, shoreline 4.

INGESTION i

a.

Milk Sampleo from milking animals in Semimonthly when Gamma isotopic" and I-131 three locations within 5 km milking animals are on analysis'on each sample.

distance having the highest dose pasture, monthly at potential.

If there are none, other times.

then, one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr.g One sample from milking animals at a control location, as for example, 15-30 km distant and in the least prevalent wind

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direction.

A.5-4 ODCM Rev. 4

t TABLE-A.5-1 Radiological Environmental Monitoring Program (Continued)

Exposure Pathway Number of Representative Samples Sampling and.

-Type and Frequency-and/or Sample and Sample Locations

• Collection Frequency of Analysis b.

Fish and One sample of three commercially Sample in season, or Gamma isotopic analysis

• Invertebrates and recreationally important semiannually if they on edible portions.

species in vicinity of plant are not seasonal.

discharge area.

One sample of similar species in areas not influenced by plant discharge.

c.

Food Products Samples of three (if practical)

Monthly, when Gamma isotopic

• aied I-131 di f ferent kinds of broad leaf available.

' analysis.

E vegetation grown nearest each of two dif ferent of f-site locations of highest predicted long-term

'I average ground-level D/Q if milk l

sampling is not pe r formed.

One sample of each of the similar Monthly, when Gamma isotopic

• and I-131 8

broad leaf vegetation grown at.

available.

analysis, a control location, as for example 15-30 km distant in the.least

~!

prevalent wind direction, if milk j

sampling is not performed.

A.5-5 ODCM Rev. 4

TABLE A. 5-4 Radiological Environmental Monitoring Program (Continued) q i

Table Notation 1

(a) Specific parameters of' distance and direction sector from the centerline of the Unit I reactor, and additional description where pertinent, shall be i

I provided for each and every sample location in Table B.4-1 in the ODCM, Part B.

Deviations are permitted from the required sampling schedule if specimens are unobtain.;)1e due to circumstances such as hazardous con-ditions, seasonal unavailability and malfunction of automatic sampling equipment.

If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period.

All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report.

If it recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.

In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program.

Identify the-cause of the unavailability of samples for that pathway and identify the new location (s), if available, for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).

(b)A thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.

l (c) Airborne particulate sample filters shall be analyzed for gross beta l

radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay.

If gross beta activity in air particulate samples is I

greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(d) Optimal air sampling locations are based not only on D/Q but on factors such as population in the area, year-round access to the site, and availa-bility of power.

(e) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuelides that may le at tributable to the ef fluents from the facility.

(f)The dose shall be calculated for the maximum organ and age group, using the

{

methodology and parameters in the ODCM, Part B.

(g)If broad leaf vegetation is unavailab1'e, other vegetation will be sampled.

A.5-5 ODCM Rev. 4

~

TABLE A.5-2 Detection Capabilities for Environmental Sample Analysisa,f,g Lower Limit of Detection (LLD)b Fish and Water Airborne Particulate Invertebrates Milk Food Products Sedi me'n t Analysis (pCi/kg) or Cas (pCi/m3)

(pci/kg, wet)

(pei/kg)

(pci/kg, wet)

(pCi/kg, dry)

Cross Beta 4

0.01 H-3 3,000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130.

Zn-65 30' 260

--' ' ~

Zr-Nb-95 ISC I-131 15 0.07 1

60e Cs-134 15 0.05 130 15

~6'O 150-l l

Cs-137 18 0.06 150 18 80

'180 j

.i Ba-La-140 15Ced 15C d i

l i

l i

A.5-7 ODCM Rev. 4

TABLE.A.5-2 (Continued)

Table Notation

.1, a) This list does not mean that only these nuclides are to be considered.

Other peaks that are identifiable, together with_those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

b) The LLD is defined, for purposes of these specifications, as the smallest -

concentration of radioactive material in a. sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66 sb LLD =

E*V*

2.22

• Y

• exp(-

t)

Where:

l LLD is. the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume; 4.66 is a constant derived from the Kalpha and Kbeta values for the 95%

confidence level; Sb is the standard deviatio background counting rate or of the counting rate of a blank s appropriate, as counts per minute;

'.: se E is the counting efficiency, as counts per disintegration; V is the sample size in units of mass or volume; 2.22 is the number of disintegrations per minute per picoeurie; Y is the fractional radiochemical yield, when applicable; l

is the radioactive decay constant for the particular radionuclide as per second; and t for environmental samples is ~the elapsed time between sampic collection and time of counting, as seconds.

Typical values of E, V, Y, and t should be used in the calculation.

In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., Potassium-40 in milk semples).

A.5-8 ODCM Rev. 4 e

7m-r-

TABLE

.5-2 (Continued)

It should be recognized t6h'at'the LLD is defined as an a priori (before the fact) limit; representing the capability of a measurement system and not as an a posteriori (af ter the fact) limit for a particular measurement. This does.not preclude the calculation of an a posteriori LLD for a particular measurement based upon the actual parameters for the sample in question and appropriate decay correction parameters'such as decay while sampling and during analysis. Analyses shall be performed in such a manner that the-stated LLDs.will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such' cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

c) Parent only.

d) The Ba-140 LLD and concentration can be determined by the analysis of its short-lived daughter product La-140 subsequent to an eight-day period-following collection. The calculation shall be predicated on the normal ingrowth equations for a parent-daughter situation and the assumption that any unsupported La-140 in the sample.would have decayed to an insignificant amount (at least 3.6% of its original value). The ingrowth equations will assume that the supported La-140 activity at the time of collection is ~ zero, e) Broad leaf vegetation only.

f)

If the measured concentration minus the three standard deviation uncertainty is found to exceed the specified LLD, the sample does not have to be analyzed to meet the specified LLD.

g) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with recommendations of Regulatory Guide 4.13, Revision 1, July 1977.

1 A.5-9 ODCM Rev. 4

~

e.

.t-TABLE A.5-3 e

i Reporting Levels for Radioactivity Concentrations in Environmental Samples J

a Fish and Water Airborne Particulate Invertebrates Milk Food Products-Analysis (pCi/kg) or Gas (pCi/m3)

(pci/kg, wet)

(pCi/kg)

(pCi/kg, wet)

H-3 30,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 zn-65 300 20,000 Zr-Nb-95 40b*

g 1-131 100 0.9 3

100** -

Cs-134 30 10 1,000 60 1,000 Cs-137-50 20 2,000 70 2,000 Ba-La-140 200*

300*

Parent only.

• • Broad leaf vegetation only.

.A.5-10 c

4 5

.