ML20203H750

Rev 10 to Radiological Environ Monitoring Program Manual

ML20203H750
Person / Time
Site:	Rancho Seco
Issue date:	08/19/1997
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20203H704	List: ML20203H700 ML20203H713 ML20203H723 ML20203H735 ML20203H750
References
PROC-970819, NUDOCS 9803030316
Download: ML20203H750 (31)

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t MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER: CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE: OFF-SITE DOSE CALCULATION MANUAL PAGE: 74 of 74 ODCM REVISION REVIEW REOUIREMENTS QDCM REVISION REVIEW REQUIREMENTS Whenever the ODChi is revised, no matter what the changes arc. iescral rniews must be perfornwd Rese reviews must also be docunented. He documenlahon is often included as an attaclanent to the 50 59 Safety Determmation nas form hsts the maiunum rniews and documentatum requred for each change Imtal cach requeement as it is compkted Sign 11w bottcnn of the form wtwn all resiew requrements are completed laihall

1. fktermmation that the kvel of control of radkucthe ellluents is bemg inauitaried his determination is made by review of the folk) wing docunwnts-

• 10 CI'R 20.1301 and 20.1302 + 10 CFR 5036a

• Appenda I to 10 CFR 50

• 40 CFR 190

11. Determinaton that the change (s) will not adscrsely affect the accuracy or rehabdity of c(!!uent done cakulatumn or effluet nonitor setpunt determinatums nas determuution is nude by drectly reviewmg each change to the ODCN! Although each change must be es aluated, changes that drectiv unohe 'culatui i should N more care Aally consulered

!!!. Supportog infonnatm Full justification includmg anaines ard es alu ns ti pport the change (s) must be included in the review and approval packa IV, Notification of NRC.

De NRC is notified of all changes _ h5 1CM by includsig a compkte, kgible copy as part oC or concurrent with, the < .nu ta Ine E!!1uent Rekase Report ( ARERR). To ensure inclusion in the ARER a ' item s iuki be unhated wheneser the ODCM is reused.

V. Impkmentag De following docu - nts shouki resiewed for impact wheneser the ODCM is reused

• CAP 000ft, a kases of Radioactnity m Lulunt Elliuents e CAP 0009 Otfute Re ses of Radnuctiuty m Lulun! Ellluents

• CAP.0013. Preparatnin of the Annual Radioactne E!! bent Release Report

• CllM 5107. Composiimg of Liquki Samples a CllM 5109, Elliuent Momtor Alarm Response Iwedure VI. Multidiscipime Review Ensure all areas that may be alTected by the revisum, or have an interest m the changes made in the revision, are included in the muttahsciphne reuew Areas that are affected by the ODCM and coukt he included in this review are Technical Services Sunedlance Scheduler, Quahty Assurance, Lammng, and Operations.

All Reviews Complete:

Reuewer Signature Date CHM 122 (Rev,0) Page 1 of 1 Attachment 19 9003030316 980225 Page1of1 PDR ADOCK 050003 2 R

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R$NGS ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 1997 ATTACHMENT 3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 1 OF 31 LEAD DEPARTMENT: EFFECTIVE DATE:

RP/ CHEMISTRY . 08-19-97 REVISION

SUMMARY

1. Changed number of monthly composite water samples from one (1) to two (2)in Table 1, section 3.a. (Waterbome Pathway, Surfaca Water)

, TlilS PROCEDURE IS ISSUED POR liiFORMATION ONLY AND 311Al.L fiOT DE USED FOR WORK OR DESIGN.

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I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 2 OF 31 TABLE OF CONTENTS SECTION TITLE PAGE 0.0 POLICY ----- --- - - -- -

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4 1.0 BADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM BASES--------------4 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM QEECRIPTIQN---------5 2.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PAR 3!QsRS-------5 2.2 ANALYSIS OF EXPOSURE PATHWAYS - ------ -- ------ 7 3.0 R ADIOLOGIC AL ENVIRON MENTAL MONITORING---~~---------------------------8 4.0 LAND UF'E CENSUS --- -- ---------------------------------10 5.0 FUEL CYCLE DOSE----- - - ---- - - - - - - - - - - --- ------------- 1 1 6.0 INTERLABORATORY COMPARISON PROGRAM------- - - - - - - - - - - ----- 12 7.0 DEFINITIONS-- - -- - - - - - - - - - -------- 13 8.0 R A DIOLOGIC A L R EPORT R EQUIR EMENTS ---------------------------- 13 8.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR)---------13 8.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR)----- ------------- 14

9.0 REFERENCES

--- - - - - - - - - - - - - - - - - - - ---- 14 10.0 IDENTIFICATION CONVENTION FOR TABLE 6 SAMPLE LOCATIONS----- ------------ 1 6 11.0 REPORTING RESULTS OF RADIOLOGICAL ENVIRONMENTAL DATA-- -------- 17 12.0 SELECTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS------17 13.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) MANUAL CHANGES - - ----------- ----- -

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i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 3 OF 31 LIST OF TABLES TABLE ILT1E A P_ADE 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM---------20 2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION, LLD------22 3 REPORTING LEVELS FOR REMP MEASUREMENTS- --: ---- 2 5 4 TWO LETTER DESIGNATION TO IDENTIFY THE TYPE OF SAMPLE - 26 S SECTOR LETTER DESIGNATIONS USED IN SAMPLE IDENTIFICATION --27 6 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS- -------28 4

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 4 OF 31 0.0 POLICY The Sacramento Municipal Utility Distnct (SMUD) and the Rancho Seco Nuclear Station recognize their responsibility to comply with the Technical Specifications and the applicable regulations, codes, standards and industry-wide criteria for establishing and maintaining a viable Radiological Environmental Monitoring Program. We are committed to operating the Rancho Seco Nuclear Station in such a manner that will assure proper radiation protection to all employees, contractors and the general public. To this end, we have committed to performing an environmental sampling program which meets the intent of the applicable regulations while providing an accurate assessment of the radiological environment in and around the environs of the Rancho Seco site.

1.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM BASES The Sacramento Municipal Utility District and the Rancho Seco Nuclear Station have instituted a Radiological Environmental Monitoring Program (REMP) which this manual serves to implement. The REMP is based upon the information contained in Title 10 of the Code of Federal Regulations, Part 20, Section 1302 (10 CFR 20.1302). That Regulatory basis and associated guidelines have been the foundation of the REMP and its programmatic elements which:

1. Provide the technological basis of, and the instruction for, monitoring the site and environs for radioactivity of all sources, including:

a. naturally occurring background

b. releases during normal operations

c. operational occurrences and postulated accidents

d. weapons testing and major nuclear accidents which contribute to detectable radioactivity in the environs,

2. Provide the means to verify the radiological effluent control program of the Rancho Seco Nuclear Station.

3. Meet minimum limits for detecting radioactive isotopes in samples collected from the environs or direct measurements in the field.

4. Provide measurements of radiation and radioactive materials in those exposure pathways, (i.e., liquid, gaseous, and direct radiation), and for those radienuclides, (i.e.,

cesi'im, and cobalt), which lead to the highest potential radiation exposure of individuals resulting from station operation.

i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 5 OF 31

- This Manual contains the minimum requirements for tne conduct of the Rancho Seco Radiological Environmental Monitoring Program (REMP). The requirements are consistent with USNRC regulations, the Branch Technical Position (BTP), Radiological Effluent Technical -

Specifications (RETS) for PWRs (NUREG-0472), and the Rancho Seco Permanently Defueled Technical Specifications (PDTS) as Administrative Controls.

2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DESCRIPTION The Radiological Environmental Monitoring Program is under :he cognizance of the Nuclear

- Plant Closure Manager, with the responsibility for the administration and oversight of the program assigned to the Radiation Protection / Chemistry Superintendent (RP/ Chem Superintendent).

The design of the program is consistent with the intent of Title 10 Code of Federal Regulations,

' Part 20. " Standards for Protection Against Radiation" Section 1302. To implement these requirements, the Permanently Defueled Technical Specifications, Off site Dose Calculation Manual Health Physics Implementing Procedures, and Surveillance Procedures have been developed. The implementing procedures address specific areas in the program that require direct attention for completion.

2.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PARAMETERS The monitorinn and sampling aspects of the program are:

. Identificu, w v me effluent release pathways, e= identification of the human exposure pathways,

. - Identification of the land usage parameters by the population within a two mile radius of the site.

Three principal release pathways at Rancho Seco Nuclear Station, are:

Gasegu_s EffluentE Discharges from the Reactor Building Stack, Auxiliary Building Stack, and the Auxiliary Grade Level Vent.

Liould Effluents:

Dischargas which are released from the retention basins via the waste water disposal system (Regenerant Hold Up Tanks (RHUT) A and B).

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._ I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL l REVISION 10 PAGE 6 0F 31 l Direct Radiation:

Radiation that c.T,anates from systems or radioactive material contained within tanks or other containers which are within the site boundary to humans outside of the site boundary.

The pathways to human exposure to radioactive materials in the affluent release pathways from Rancho Seco are:

Gaseous e Inhalation of airbome radioactive material by humans, or by animals that inhale and retsin the materialin animal products that are consumed by humans, i.e.,

meat or milk.

. Con:iumption of radioactive particulate material which, although carried by air currents, is deposited onto or is taken up by water sources or plants consumed by humans, or by animals that provide products that are consumed by humans, i.e., milk or meat.

• Exposure from being immersed in air containing radioactive materials as a gas and/ or particulates.

• Exposure to the direct radiation from radioactive materials that have been deposited onto surfaces from airbome releases.

Liaujd e Drinking of water from the release pathway by humans, or by animals that are a food source fcr humans.

. The consumption of fish or other animals that have eaten fish or shellfish taken from water within the liquid release pathway.

. The consumption of products of animals that have eaten vegetation that have been irngated witn water from the release pathway.

. The consumption by humans of fruit or vegetation grown in soil irrigateu with water from the release pathway.

Direct Radiation

. The exposure to radiation emitted frora radioactive materials within the Rancho Seco site boundary. Sources include, but are not limited to, the Borated Water Storage Tank, Demineralized Reactor Coolant **orage Tank, the Interim Onsite Storage Building (IOSB), and the Independent Sr ,nt Fuel Storage Installation (ISFSI).

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 7 OF 31

. - The exposure from being immersed in the release pathway water, to radiation emanating from material contained in the water.

2.2 ANALYSIS OF EXPOSURE PATHWAYS Exposure pathways are analyzed through a systematic process which identifies a sample medium or organism that is found in the effluent pathways. Usage factors are determined that will suitably represent biological concentration, retention or uptake which may ultimately represent a contribution to human exposure. The pathways to human exposure are evaluated through the analysis of data obtained from the performance of a land use census. The pedormance of the land use census is required by the Permanently Defueled Technical Specifications Section D6.8.3b.2. The analysis of the effluent and exposure pathways enables

-- the selection of sampling and monitoring locations that fallinto one of two classes, those which are, and those which are not, influenced by effluent pathways. Those in the pathways are referred to as indicator locations. Several of the unaffected locations are selected to represent baseline or controllocations.

Indicator locations provide data from the surrounding environment that may be influenced by the operation of the plant because they are nearby, drenwind or downstream in the release pathway. Such data can be used to calculate doses to verify compliance with 40 CFR 190, using methodology contained in the ODCM. (This is referred to as the MEMBER OF THE PUBLIC, The MEMBER OF THE PUBLIC is defined as any individual except when that individualis receiving an occupational dose. A MEMBER OF THE PUBLIC who, based upon the land use census, is expected to receive the maximum off site dose to realindividuals, may be used to calculate doses to demonstrate compliance with 40 CFR 190.]

Control sample locations are to provide data that should not be influenced by the operations of Rancho Seco. These locations are selected based upon the distance from the plant, being upwind, or upstream of the release pathways. Data from these locations help discriminate between Rancho Seco releases and other natural or manmade events that may impact human exposure.

At Rancho Seco, potentially radioactive liquid effluent is discharged into Clay Creek. A continuous flow of Folsom South Canal water is released above the discharge point. The ccatinuous minimum flow and the liquid effluent release are the major effluent release pathway, and thus the exposure pathway for the station during normal operations. Prior to the minimum release rate being established, Clay Creek was a seasonal stream, formed as the confluence of three and one half square miles of drainage runoff upstream of the site. The now continuous flow of Clay Creek intersects Hadselville Creek north and west of Califomia State Highway 104. Hadselville Creek intersects Laguna Creek just east of the Folsom South Canal. Laguna Creek flows into the Cosumnes River approximately 20 miles from Rancho Seco. .

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- PAGE 8 OF 31 Hadselville and Laguna Creeks are also seasonal streams and also receive irrigation' runoff

' during periods when irrigation is used. These streams are the major release pathway for liquid effluents from the site.

The gaseous pathway _ analysis is related to the land use census. This pathway is not confined 4 i- by creek banks, but is subject to the meteorological conditions during the time of the release.

While not a significant release nor exposure pathway, weekly air sampling is performed to determine the dose due to radioactive gaseous releases.

The direct radiation exposure pathway is the least likely pathway for the exposure to plant radiation by humans. It is the most easily measured with the use of thermoluminesence

- dosimeters, which monitor continuously and passively. The dose is integratoo over three

? months to accumulate a statistically significant exposure. The vast majority of the dose .

Integrated by that,e detectors is delivered from primordial elements in the geological surface of

- the Earth, which contain naturally radioactive elements. A smaller fraction of the dose is delivered by cosmic radiation which has penetrated the Earth's atmosphere.

3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING The REMP shall be conducted AT ALL TIMES as specified in Table.1

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3.1 With the REMP not being conducted as specified in Table 1, prepare and submit to the Commis lon, in the Annual Radiological Environmental Operating Report (AREOR)

required by Section 8.1, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. Deviations are permitted from the required samplinc schedule if specimens are unobtainable due to hazardous conditions or seasonal unavailability.

3.2 With the level of radioactivity in an environmental sampling medium exceeding the Reporting Level of Table 3 when averaged over any calendar quarter, in addition to

_ complying with the requirements of Section 5.0, FUEL CYCLE DOSE, prepare and

. submit to the Commission within 30 days after the level of radioactivity has been determinedia Special Report which includes an evaluation of any release conditions,

- ' environmental factors or other aspects which caused the Reporting Levels to be-exceeded. This report will define correctivo actions to reduce emissions such that

-potential exposures will meet the 10 CFR 50, Appendix l dose guidelines. When more -

than one of the radionuclides in Table 3 are detected in the sampling medium, the

.Special Report shall be submitted if the Reporting Level fraction summation equals or exceeds unity (1.0).

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i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 9 OF 31 When radionuclides other than those in Table 3 are detected and are the result of plant effluents, this Special Report shall be submitted if the potential annual dose to an

individual is greater than or eaual to the calendar year guidelines of 10 CFR 50, Appendix l. This Special Report is not required if the measured level of radioactivity v/as not the result of plant effluents; however, the condition shall be reported and described in the AREOR.

3.3 With fresh vegetation samples unavailable from any of the sample locations required by Table 1, identify the cause of the unavailability of samples and the locations for obtaining replacement samples in the next AREOR. The locations from which samples wers unavailable may then be deleted from Table 6 provided the locations from which

the replacement samples were obtained are added to Table 6 as replacement locations,if available.

3.4 The radiological environmental monitoring samples shall be collected per Table 1 from the locations shown in Table 6. These samples shall be analyzed to the requirements t

of Table 1 and Table 2.

3.5 The flow measuring devices or, the environmental air monitors used for sampling the Table 1 AIRBORNE EXPOSURE PATHWAY shall be subjact to a MONTHLY function check and shall be calibrated ONCE EVERY 12 MONTHS.

3.6 The REMP required by Section 1.0 provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the Station operation. This monitoring program thereby implementsSection IV.B.2 of Appendix l to 10 CFR 50 and supplements the REMP by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and Off-site Dose Calculation Manual (ODCM) modeling of the environmental exposure pathways.

Guidance for Section 3.0 was provided by References 9.12 and 9.29. REMP changes may be initiated based on operational experience and changes in the regional population or agricultural practices. The detection capabilities required by Table 2 are state of the art for routine environmental measurements in industriallaboratories. The LLDs for drinking water meet the requirements of 40 CFR 141.

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I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 'i0 OF 31 4.0 LAND USE CENSUS A Land Use Census shall be conducted biennially and shallidentify the location of the nearest milk animal, the nearest residence and the nearest garden of greater than 500 square feet producing fresh leafy vegetation in each of the 16 meteorological sectors within a distance of two (2) miles. The location of the nearest miik animalis not required if the Offsite Dose Calculation Manual (ODCM) dose calculations are using conservative dose factort, which assume the presence of milk animals within the vicinity of Rancho Seco Nuclear Station. Vegetation sampling may be performed at the Station Site Boundary in lieu of the garden census.

The Land Use Census shall also include information relevant to the liquid effluent pathway and gaseous effluent pathway such that the ODCM and the REMP Manual can be kept current with existing environmental and societal use of land surrounding Rancho Seco.

4.1 The Land Use Centus shall be conducted biennially by using methods that will provide the best results, such as coor to-door survey, aerial survey, or by consulting local agriculture authorities The Land Use Census, or portions thereof, shall be conducted during the appropriate time of the year to provide the best results. The results of the Land Use Census shall be included in the AREOR covering the census year as required by Section 8.1.2.

4.2 With the Land Use Census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in the ODCM for compliance with 10 CFR 50, Appendix 1, identify the new location (s) in the next AREOR.

4.3 With the Land Use Census identifying a Incation(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Section 3.0, Radiological Environmental Monitoring, add the new location (s) to Table 6 within 30 days or submit a Special Report to the Commission that identifies the cause(s) for exceeding these requirements and the proposed corrective actions for precluding recurrence.

The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s) (via the same exposure pathway) may be deleted from Table 6 after October 31 of the census year. Identify the new location (s) in the next AREOR including a revised figure (s) and table for the REMP Manual reflecting the new location (s).

4.4 The Section 4.0 requirements are provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the REMP and the ODCM are made if required by the results of the Land Use Census. These requirements also satisfy the requirements of Section IV.B.3 of Appendix I to 10 CFR 50.

e RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 11 OF 31 Restricting the Land Use Census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetation consumption will be i identified and monitored. Gardens of this size are the minimum required to produce the quantity (26 kg/ year) of leafy vegetation assumed (reference 9.14) to be consumed by a child. In specifying this minimum garden size, it was further assumed that 20 percent of the garden was used for growing broad leaf vegetation (e.gliettuce or cabbage) and 2

that the productivity was two (2) kg/m ,

1 in addition, by gathering information on the liquid effluent pathway and the gaseous effluent pathway, the Land Use Census provides assurance that proper radiological environmental monitoring and radioactive effluent controls are in place for the adequate protection of the health and safety of the general public.

5.0 EUEL CYCLE DOSE

The dose or dose commitment to any real MEMBER OF THE PUBLIC due to releases of radioactive materialin gaseous and liquid effluents and to direct radiation from uranium fuel cycle sources shall AT ALL TIMES be limited to less than or equel to 25 mrem (total body or any orgen), and 75 mrem (thyroid), in a calendar year.

5.1 With any of the Reporting Levels of Table 3 being exceeded, calculations shall be n ade to determine whether the Section 5.0 fuel cycle dose / dose commitment limits

' have been exceeded. Contributions from direct radiation sources (including outside storage tanks, etc.) shall be included in this calculation.

5.2 If the Section 5.0 limits have been exceeded, prepare and submit to the Commission within 30 days a Special Report that defines the corrective action to be taken to reduce sut: sequent releases to prevent recurrence of exceeding the Section 5.0 limits. This Special Report shall also include a schedule for achieving conformance with the Section 5.0 limits.

This Special Report, as defined in 10 CFR 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, in a calendar year that includes the release (s) covered by this Special Report. This Special Report shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

5.3 If the estimated dose (s) exceeds Section 5.0 limits, and if the release condition resulting in the violation of 40 CFR 190 has not already been corrected, the Special Report shall also include a request for a variance in accordance with the provision of 40 CFR 190 Submittal of the Special Report is considered a timely request, and a variance is granted until USNRC staff action on the request is complete.

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 12 OF 31 5.4 .The Section 5.0 requirements are provided, in part, to meet the dose limitations of 40 -

CFR 190 that have been incorporated into 10 CFR 20. For the Rancho Seco site, it is unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the Station remains within twice the numerical guides for design objectives of 10 CFR 50, Appendix l and if direct radiation is kept small.

The Special Report will describe a course of action which should result in the limitation of the dose to a MEMBER OF THE PUBLIC for a calendar yeario within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of five (5) miles must be considered.

If the dose to any MEMBER OF THE PUBLIC is evaluated to exceed the requirements of 40 CFR 190, the Special Report along with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected)is considered to be a timely request and fulfills the requirements of 40 CFR 190 until USNRC staff action is completed.

An individual is not considered a MEMBER OF THE FUBLIC during any period in which he/she receives an occupational dose.

6.0 INTERLABORATORY COMPARISON PROGRAM The laboratory performing analyses of Table 6 samples pursuant to the requirements of Table 1 shall AT ALL TIMES participate in an intertaboratory Comparison Program (ICP) approved by the Commission. The ICP approved by the Commission may not always supply tests for the analyses required by Table 6.

Since no Commission approved ICP exists for TLDs, the laboratory performing analyses of the REMP environmental TLDs shall AT ALL TIMES participate in a licensee approved comparison program.

6.1 With ICP analyses not being performed as required in Section 6.0, report the corrective acDons taken to prevent a recurrence to the Commission in the AREOR as required by Section 8.1. i 6.2 A summary of the results obtained as a participant in the ICP shall be included in the AREOR as required by Section 8.1.

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL

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6.3 The requirement to participate in an ICP is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materialin-environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR 50, 7,0 DEFINITIONS 7.1 FORTNIGHTLY Once per fourteen (14) days 7.2 INDUSTRIAL AREA - That portion of the Station property, access to which is controlled as described in the NRC approved Security Plan by security fencing, equipment and personnel.

7.3 SITE EOUNDARY - That line beyond which the lanc' is neither owned, nor leased, nor otherwise controlled by the licensee.

7.4 RESTRICTED AREA - An so, access to which is limited by the licensen for the purpose of protecting indivioL c.s against undue risks from exposure to radiation and radioactive materials. Restncted area does not include areas used as residential-quarters, but separate rooms in a residential building may be set apart as a restricted area.

7.5 CONTROLLED AREA - An area, outside of a restricted area but inside the site boundary, access to which can be limited by the licensee for any reason.

7.6 UNRESTRICTED AREA An area, access to which is neither limited nor controlled by the licensee.

7.7 MEMBER (S) OF THE PUBLIC - Any individual except when that individua! is receiving an occupational dose.

8.0 RADIOLOGICAL REPORT REQUIREMENTS 8.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR) 8.1.1 An AREOR covering the operation of the Station during the previous calendar year shall be submitted to the USNRC prior to May 1 of each year in accordance with Permanently Defueled Technical Specification D6.9.2.3.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 14 OF 31 8.1.2 The AREOR shallinclude summaries end statistical evaluations of the results of the radiological environmental surveillance activities for the report period, including (as appropriate) a comparison with operatiorial controls. The AREOR shall also include the results of the Land Uw Census required by Section 4.0, LAND USE CENSUS. In the event a radionuclide concentration should be confirmed in excess of the Reporting Levelin Table 3 'oy environmental measurements, the AREOR shall describe a planned course of corrective action.

8.1.3 The AREOR shallinclude summarized and tabulated results of all radiological environmental samples taken during the AREOR period. In the event that some results are not available for inclusion, the AREOR shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

8.1.4 The AREOR shallinclude a summary description of the REMP (including a map of all sampling locatic.is keyed to a table giving distances and directions from the Reactor Building) and the results of participation in the Interlaboratory Comparison Program required by Section 6.0. The AREOR shall also include information related to Section 5.0, Fuel Cycle Dose.

8.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR)

Any changes made to the REMP MANUAL during the ARERR reporting period shCI be included in that ARERR. The complete REMP manual, in its revised form, shall be submitted with the ARERR.

9.0 REFERENCES

The following documents pertain to the design and conduct of radiological environmental monitoring programs:

9.1 American National Standards Institute (ANSI), Performance Testino and Procedural Specifications for Thermoluminesence Dosimetry (Environmental Acolications), ANSI Standard N545 (1975).

9.2 American Nuclear Insurers and Mutual Atomic Energy Liability Underwriters (ANI/MAELU), Environmental Monitorino Proarams, Information Bulletin 86-1 (1986).

9.3 ANI/MAELU, Enaineerino inspection Criteria for Radioloaical Environmental Monitorino, Section 5.2, Revision 2.

9.4 ANI/MAELU, Nuclear Liability Insurance Records Reten' on, Information Bulletin 80-1 A.

Rev. 2 (1986).

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 15 OF 31 9.5 Committee on the Biological Effects of lonizing Radiations (BEIR), The Effects on Populations of Exposure to Low Levels of lonizino Radiation: BEIR V heport (1990).

9.6 National Council on Radiation Protection (NCRP), A Handbook of Radioactivity Measurements Procedures, NCRP Report No. 58, Second Edition (1985).

9.7 NCRP, Radioloaical Assessment: Predictina the Transport. Bioaccumulation and Uotake by Man of Radionuclides Released to the Environment. NCRP Report No. 76 (1984).

9,8 USEPA, Environmental Standards for the Uranium Fuel Cycle. 40 CFR 190, Subpart B (1993).

9.9 USEPA, Uoaradina Environmental Radiation Data, Health Physics Society Committee Report HPSR 1, EPA 520/180-012 (1980).

9.10 USNRC, Criterion 64 Monitorina Radioactive Releases,10 CFR 50, Appendix A (1993).

9.11 USNRC, Numerical Guides for Desian Obiectives and Limitina Conditions for Operation to Meet the Criterion 'As Low As is Reasonab!v Achievable' for Radioactive Material in Llaht Water QAqljlLd Nuclear Power Reactor Effluents,10 CFR 50, Appendix I (1993).

9.12 USNRC, An Acceotable Radioloaical Environmental Monitorina Proaram. Branch Technical Position, Rev.1 (November 1979).

9.13 USNRC, implementation of Procrammatic Controls for Radioloaical Effluent Technical Spfeificat;ons in the Administrative Controls Section of the Technical, Specifications and the Relocation of Procedural Details of RETS to the Off-site Dose Calculation Manual or the Process Control Proaram, Generic Letter 89 01 (January 31,1989).

9.14 USNRC, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluatina Compliance with 10 CFR 50, Appendix 1, Regulatory Guide 1.109 (1977).

9.15 USNRC, Estimatina Acuatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Imolementina Appendix 1, Regulatory Guide 1.113 (1977).

9.16 USNRC, Measurina and Reportina of Radioactivity in the Environs of Nuclear Power Plants. Regulatory Guide 4.1 (1973).

9.17 USNRC, Preparation of Environmental Reports for Nuclear Power Stations. Regulatory Guide 4.2, Rev. 2 (1976).

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 16 OF 31 9.18 USNRC, Performance. Testina and Procedural Specifications for Thermoluminesence Do_simetry: Environmental Apolications," Regulatory Guide 4.13.

9.19 USNRC, Quality Assurance for Radioloalcal Monitos.o Proarams (Normal Operations) -

Eff. fluent Streams and the Environment, Regulatory Guide 4.15, Rev.1 (1979).

9.20 USNRC, Radioloaical Assessment: A Textbook on Environmental Do_s.jt NUREG/CR-4 3332 (1983).

9.21 USNRC, Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radioloaical Effluent and Environmental Measurements, NUREG/CR-4007 (1984).

9.22 USNRC, Radiobaical Effluent Technical Specifications for PWRs, NidEG 0472, Rev.

2 (July 1979).

9.23 USNRC, Radioloaical Monitorina by NRC Licensees for Routine Operations of Nuclear Facilitle.ji, NUREG-0475 (1978).

9.24 USNRC, Methods for Demonstratina LWR Comoliance With the EPA Uranium Fuel Cycle Standard (40 CFR 190), NUREG 0543 (1980).

9.25 USNRC, Dose Limits for individual members of the oublic,10 CFR 20.1301 (1993).

9.28 USNRC, Reports of exposures radiation levels. and concentrations of radioactive material exceedina the limits,10 CFR 20.2203 (1993).

. 9.27 Merril Eisenbud, Environmental Radioactivity From, Natural. Industrial. and Military Scurces, Third Edition (1987).

9.28 Rancho Seco Permanently Defueled Technical Specifications.

9.29 USNRC, Technoloav. Safety and Costs of Decommissionina a Reference Pressurized Water Reactor Power Station. NUREG/CR-0130 (June 1978) 9.30 USNRC, Air Samolina in the Workolate, Regulatory Guide 8.25, Rev.1 (June 1992) 10.0 IDENTIFICATION CONVEW.ON FOR TABLE 6 SAMPLE LOCATIONS Sampling and monitoring sites designated in Table 6 are identified using the following convention:

10.1 To establish the fact that the Table 6 samples originate from the Rancho Seco REMP, the letter "R" precedes every sample site designator.

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R RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 ,

4 PAGE 17 0F 31 i

10.2 The next two (2) letters are selected to identify SAMPLE TYPE. Refer to Table 4 for a listing of the SAMPLE TYPES and the associated two letter abbreviation.

i 10.3 The numbers following the SAMPLE TYPE abbreviation reflect the straight line distance (miles) to the sample site, ref ~enced to the center of the Reactor Buildinc 10.4 Following the distance, a SECTOR DESIGNATOR letter is included to specify which of j the 16 meteorological sectors the sample site is encompassed. Refer to Table 5 for a listing of the sector designators.

10.5 The final character in the sample site designation is the letter "0" or the letter "P". The i letter "O" designates the sample as one being added to the REMP following Station

initial criticality. The letter "P" designates the sample as one being added during the j post operational period following the issuance of the Possession Only License.

10.6 The present identification convention has been selected in preference to the system originally used to identify samples and sites. Since it is desirable to retain the ability to identify, and continue to use data from, previously collected samples, the former identification convention is also shown parenthetically in Table 6.

11.0 REPORTING RESULTS OF RADIOLOGICAL ENVIRONMENTAL DATA The requirements for reporting radiological environmental data are specified in Section 8.0 of this manual. Those subsections which rwquire supporting data from the Radiological Environmental Monitoring Program address the Annual Radiological

!~

Environmental Operating Report and the Anrual Radios rive Effluent Release Report.

Special Reports are made specific in HPIP 2050, Radiological Environmental Monitoring Program Reports. Specified therein are conditions requiring special reports, and rer -ing requirements in days for submittal. This includes those calculations to i provide rapid assurance of the degree of compliance with 10 CFR 50 Appendix 1, and 40 CFR 190 calculations after releases of any origin.

j 12.0 SELECTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATION,S In conjunction .vith the (2ata base established from the land use census, the requirements of the Permanently Defueled Technical Specifications, and the guidance desenbod in Section 2.0 of this Manual, the selection of sampling and monitoring sites is performed. These selected locations provide at least the minimum number of locations specified in Table 1.

o - - , , - . . - - . _ - -___.___m___ ____,__ ___,_ , _

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 18 0F 31 Data was gathered from the land use census, Lawrence Livermore National Laboratory Rancho Seco Study Reports, Oak Ridge National Laboratory Study Reports, and from additional sampling sites from which materials have been collected. The information gathered was used to determine indicator sites. Presently, a number of control sites have been selected and are not anticipated to be increased in number.

The second column of Table 6 identifies the Sample Class of a particular sample as either an Indicator (IND) or a Control (CON) Sample. Additional sample locations designated as Special (Spec) are used to perform initial radiological evaluations.

Environmental thermolumia: tence dosimeters are placed in the environs around the site. These devices passlO rnonitor radiation in the immediate environs. Data from TLDs is trended to establish variations which are influenced by seasonal, meteorological, local and global sources. TLDs will also respond to radiation in the effluents of the plant if they pass in near proximity. The data is included in each quarterly environmental report.

Sample locations for the collection of the flora and fauna are concentrated in the liquid effluent pathway to the West. Representative samples of all the pathways and suitable locations are established in all directions. Air samplers are distributed to achieve a sampling of air from major wind directions across the site.

The Radiological Environmental Monitoring Program maintains at least those minimum sampling locations and type of :: amp les to meet the requirements listed in Table 1.

A site has been established for a vegetable garden. The garden is at the site boundary alongside Clay Creek, and irrigated with water from the effluent stream. Th!s data is considered essential for comparisons to vegetation not irrigated with effluent stream water for determination of bioaccumulation for soil types common to the environs.

All of the environmental sample locations required for the Radiological Environmental Monitoring Program are designated in Tablo 6. Adfoonal sampling locations are listed in HPIP.2070, REMP Routes and Sample Locations.

13.0 Radiolooical Environmental Monitorino Prooram (REMP) Manual Chanoes As required by the Permanentiy Defueled Technical Specifications (PDTS) section D6.14.3, changes to the REMP manual shall be documented and the records of the reviews performed for the changes shall be retained as required by the PDTS section D6.10.2.o. Tha documentation shall contain sufficient information to support the change together with the appropriate analyses or evaluations justifying the change.

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i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 19 OF 31 The documentation shall also contLin a determination that the change will maintain the '

level of radioactive effluent control that is required by 10 CFR 20.1302,40CFR190,10 CFR 50.36a, and Appendix l to 10CFR50 and not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.

i Changes to the REMP manual shall become

• Factive after review and acceptance by the PRC and approval by the Plant Managre Changes to the REMP manuel shall be submitted to the Nuclear Regulatory Commission in the form of a complete, legible copy of the entire REMP Manual as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the REMP Manual was made. Each change shall be identified by markinpt in the margin of the affected pages, clearly indicatirg the area of the page that was changes, and shallindicate the date (e.g.,

month / year) the change was implemented.

3 i

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RADIOLOG! CAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 20 OF 31 l Table 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samphng and Type and Frequency of Analysis andt or Sample Samples

• Collectma Frequency

1. AIRBORNE 3 Continuous opstuon Partculate sampier. Analyze for Gross Beta of samplerwith rachoactnntf at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> follounng filter change.

sample collechon as Perform gamma isotopic analysis on each sample required by dust where gross beta activity is greater than 10 trnes the loading but at least year 1y mean of control samples for the same sample once per week penoct Perform gamma isotopic analysis on composde (by locahon) sample at least once per quarter

2. DIRECT Atleast 24 locabons Atleast once per Gamma dose. Atleast once per quarter RADIATION with 2 dosimeters at quarter each beabon

3. WATERBORNE

a. Surface 2 Composite sample Gamma isciopi.and tnbum analysis of each compos:te l collected monthly 3 Grab sample collected Gamma isotopc and tntium analys s of each sample monthly

b. Runoff 1 Grab sample collected Gamma isotopc and tnbum analysis of each sample fortnightly Sample locations are shown in Table 6

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 .

. PAGE 21 OF 31 Table 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4

i E=aa=m Pathway Number of Samping and Type and Frequency of Analyses I

^

andf orSample Samples

• Collection Frequency

3. WATERBORNE 2 Grab sample collected Gross Beta Gamma is-Mopic, and Tnbum analysts of ,

c.- Ground quarterly each sample l

d. Dnnlung 2 Grab sample collected Gross Beta, Gamma isotopic, and Tnbum analysis of ,

iri.a diJy each sample

, e. Mud and 2 Atleast quartedy. Gamma isotopc analysis of each sample. >

Silt Sample co!iected of the top 3 of material 2

] ft. from shoreline j 4. INGESTION l

a. Fish At least se6%cinidy. Gamma isotopc analysis of the edible porbon c' each 1  !

At least one sample sample. i of eitherof the speces j listed in Table 6 j i

b. Food 1 At least semsarnually. Gamma isotope analysis of the edbie porbon of each  ;

l One sample of sample.

vegetable (s) as shown in Table 6  !

Sample locations are shown in Table 6 i

i i.

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 - i PAGE 22 OF 31 Table 2  !

MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION, LLD *#

Airtmme Analyses water Particulate or F:sh Food Products IAud and Silt [

(pCW I) Gases (pCWm*) (pCime-wet) (pCW kg-wet) LC4 2)

Gross Beta 6 0.01 4 i r

H-3 2000 D

(1000 ) ,

Mn-54 15 130 -

Co-60 15 130 150W Zn 30 260  !

Cs-134 6 8 15(10 ) 0.01 130 60 150 Cs-137 D 8 18(10 ) 0.01 l 130 60 150 I

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 l l

PAGE 23 0F 31

. Table 2 4

MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION, LLD

• The Low Umit of Detection (LLD) values for the radionuclides presented in Table 2 are those recommended in Reference 9.12 (BTP)and Reference 9.22 (RETS). ,

The LLD of a radioanalysis system is that value which willindicate the presence or absence of '

radioactivity in a sample when the probability of a falso position and of a falso negative determination is stated. The probabilities of the false positive and falso negative i determinations are taken es equal to 0.05. The equation for estimating the maximum LLD is given by ths following equation:

2.71/t, + 3.29S. 8 LLD = '

3.7E- 2(YEl')exp(-AI,), pCl/1, pCl/kg wet, or pCi/M where:

2.71 = factor to account for Polsson statistics at very low background count rate 3.29 = twice the constant used to establish the one sided 0.95 confidence interval j = standard deviation of the background count rate Sb

" 2 (B / (tb t ) + B /13)05

, B = background counts

= background count interval, sec to ,

= sample count interval, sec t.

3.7E 2 = conversion factor, dis / sec/ pCl Y = radiochemical process yield (product of all factors such as abundance, chemical yield, etc.)

E = . counting efficiency, cts / dis V- = sample volume or mass, I or kg

-A = radioactive decay constant for the associate nuclide  :

-ec, , , ,.,..-v . - - . . - ,w..e,., -._.___,s-- , y r- . _ . , w -.-,-,,-,4 y-- . , - , ~ , - , y y

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RADIOLOGICAL ENNIRONMENTAL MONITORINO PROGRAM MANUAL  ;

REVISION 10 PAGE 24 OF 31 i

Table 2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION, LLD d

= elapsed time from the midpoint of sample collection to the midpoint of te counting, sec The LLD is defined as an g gdg.d (before the fact) estimate and is not to be calculated for each sample analyzed on an a posteriori(stter the fact) basis.

Occasionally, unavoidably small sample sizes or other uncontroliable circumstances may result in a priorf LLD values not being met, in such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

b LLD for Drinking Water samples from Reference 9.22 (RETS).

• Other peaks which are measurable and identifiable, together with the nuclides in Table 2, shall be identifiert and reported, d

Composite analysis LLD from Reference 9.22 (RETS) is shown; individual sample LLD 3 8 is 0.05 pCi/m , This LLD (0.05 pCi/m )is a site specific value.

LLD for Mud and Silt Co-60 is not required by Reference 9.22 (RETS). This value is consistent with the RETS required LLD for Cs 134 and Cs 137, 4:

ap - . , . . - - - . , , , - ,

. ~ ,, . _ m . . _._ _ _ . _ _ _ _ . . . _ _ .. _ .__ ._ _ _ _ _ .

J t

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i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 l PAGE 25 OF 31 l Table 3 t s

1- i REPORTING LEVELS FOR REMP MEASUF<EMENTS t 1

i  ;

Analysis Water Airtsorne Par *ieth or Fish Food Products I 4 (pcw g tw (pcum*) L<n r) (pcv e, wet) ,

j H-3 20000*  ;

s t

Mn-54 1000 30000 i

i-Co-60 300 10000 I ,

, Zn-65 300 20000 i l i Cs-134 30 10 1000 1000 1 Cs-137 50 20 2000 2000 Gross Beta 40' 8

2" 1

t i

!~ Applies to water samples utilized for human consumpton only. This value is as spec 6ed in 40 CFR 141.

1 i D

. Gross Beta actnnty in water of ten times the yearly mean of the control samples is indicated as Sie level that gamma iK46  !

analysis should be performed on the indnndual sample [ Reference 9.12 (BTP)]. Gamma iso 6pic analysts on each water sample l

. is reoutred by Table 1 and therefore this sepvim rg requireirsd does not apply i c Gross Beta acimty in air of ten (10) times the yearly mean of the control sampies is indicated as the level that Gamma Isotopic  !

l analysis should be pc,1viined on the indnndual sample. The value irdcated is site spedic

! P

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i ,

f

. - ~ . __ _ _ _ _ . _ _ _ _ . . _ _ . . _ _ _ _ _ _ . -. _. . .. .__ . . . _ ___

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL '

REVISION 10 PAGE 26 0F 31 ,

l Table 4 >

! TWO LETTER DESIGNATION TO IDENTIFY THE TYPE OF SAMPLE '

i Letter Deslanation Ivos of Samole Represented l '

AG Algae Sample AS Air Sample FS Fish Sample  :

i LV Garden Vegetation MS Mud & Silt (Sedimei.t)

RW Runoff Water

' b SW Surface Water 4

TL Direct Radiation (TLD) ,

2 WW Ground (Well) Water

- DW Drinking Water SL Soil

• Additionalletter designation may be added as sample designators if additional sample

! types are collected for analysis, b

The portion of precipitation on the land that ultimately reaches streams is considered to be surface water.

i 4

+

w e> w. p ,mr- q.w...--y----g--, vs w. e-. r=m-,- m. -v--#. n y , ,,_y -

y --.-r-.,,i, -

t *w-e-,- ,r-y,.- r y ,r.y- y- ---r rn , w -we

I I

RADIOLOGICAL ENVIRONMENTAL MONITORING FROGRAM MANUAL '

REVISION 10 PAGE 27 OF 31 4

Table S ,

SECTOR LETTER DESIGNATIONS USED IN SAMPLE IDENT'FICATION i

True North Compass

! Sector Sector Degrees Sector I

A 348.75 to 11.25 N B 11.25 to 33.75 NNE j C 33.75 to 56.25 NE I O 56 25 to 78.75 ENE l E 78.75 to 101.25 E F 101.25 to 123.75 ESE G 123.75 to 146.25 SE H 148.25 to 168.75 SSE J 168.75 to 191.25 S K 191.25 to 213.75 SSW L 213.75 to 236.25 SW i

M 236.25 to 258.75 WSW N 258.75 to 281.25 W P 281.25 to 303.75 WNW Q 303.75 to 326.25 NW R 326.25 to 348.75 NNW 1

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10

- PAGE 28 0F 31 Table O RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS 1

Sample Identification Sample Collection Location identification

+

(Former 10) Class Frwouency 6]H (Particulatec)

RASO.1CO IND Weekly On Site (PAP Building Carport)

(RAHO)

RASO,3MO IND Weekly On Site (Effluent Discharge) i RASO,7EO IND Weekly Meteorological Tower RUNOFF WATER RRWO.6MO IND Biweekly Site Boundary SURFACE WATER I

RSWO.7NO IND Monthly Water Sump RSW1.3F0 IND Monthly Rancho Seco Reservoir (RSWCO)

RSW3.7NO CON Monthly Folsom South Canal (Composite Sample)

(RSWBO)

RSW1.8NO IND Monthly Confluence of Clay and Hadselville Creeks RSWO.3MO IND Monthly Effluent Discharge (Composite Sample)

E

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 29 OF 31 Table 6 (continued)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Sample IdentWication Sample Collection Location Identification (Former 10) Class Frequency GROUND (Well)

WATER' RWWO.3E0 IND Quarterly Site Well (RWWAO)

RWWO.8DO CON Quarterly Marclel Ranch DRINKING WATER R W DO.1 G O IND Monthly Industrial Area Drinking Water Source RDW1.8FP CON Monthly Rancho Seco Lake Drinking Water Source MUD AND SILT (Sediment)

RMSO.3MO IND Quarterly Effluent Olscharge RMSO.6MO IND Quarterly Site Boundary (P.MSEO)

EIS11*

RFSO.6MO IND Semlannually Clay Creek near the Site Boundary NOTE: Include predator (o.g., bass, sunfish) or scavenger (e.g., catfish, sucker) species, as available, Other downstream locations may be substituted to meet sampling requirements.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 10 PAGE 30 OF 3t, i I

Table 6 (Continued)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Sample Identification Sample Collection Location Identification (Former ID) Class Frequency GARDEN VEGETABLES RLVO.6MO IND Se:nlannually Site Boundary Vegetable irrigation Garden (vegetable samples, depending on availability)

RLVXX.XX CON Semlannually Truck Farm, outside 5 mile radius. (locally (RLVFO) grown vegetable samples, depending on availability)

ILQ RTLO.3RO IND Quarterly #1 Rancho Seco Site RTLO.3CO IND Quarterly #2 Rancho Seco Parking Lot RTLO.3NO IND Quarterly #3 Rancho Seco Site RTLO.3LO IND Quarterly #4 Rancho Seco Site RTLO.3HO IND Quarterly #$ Rancho Seco Site RTLO.4FO IND Quarterly #6 SMUD Photovoltaic Facility RTLO.5CO IND Quarterly #7 Rancho Seco Entrance RTLO.6KO IND Quarterly #11 Tokay Substation / Clay East Rd.

RTL2.7MO IND Quarterly #16 Tipling Residence RTLB.2KO CON Quarterly #17 Elliot Cemetery RTL7.8CO CON Quarterly #18 Sam Jabor Residence a

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVIS!ON 10  :

PAGE 31 OF 31 Table 6 (Continued)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Sample identification Sample Collection Location Identification (Former ID) Class Frequency -

IkQ RTL1.8FO IND Quarterly #19 Rancho Seco Lake Clay East Road & Kirkwood RTL1.5MO IND Quarterly #20 RTL3.9KO IND Quarterly #26 Borden Rohd RTL7.4MO CON Quarterly #30 Herald Fire Department RTL3.7NO IND Quarterly #31 Hobay Road .

RTL3.8MO IND Quarterly #33 Folsom South Canal Pumping Station RTL1.9NO IND Quarterly #35 Hadselville Creek and Plant i Effluent Water RTL1.7FO IND Quarterly #43 Rancho Seco Reservoir RTL1.4DO IND Quarterly #46 Twin Cities Road (Highway 104)

RTL8.0PO CON Quarterly #55 Colony Road RTLO.8DO IND Quarterly #63 Marciel Ranch RTLO.6MO IND Quarterly #65 Site Boundary irrigated Garden RTLO.3PO IND Quarterly #68 West Fence, adjacent to ISFSI RTLO.3NP IND Quarterly #88 ISFSI outer Security fence, near inactive West Garden RTLO.4NP IND Quarterly #89 ISFSI outer Security fence, SW comer RTLO.5NP IND Quarterly #90 ISFSI outer Security fence, ITN comer RTLO.3QP IND Quarterly #91 ISFSI outer Security fence, NE ,

comer

- - - - , . . , - , -, - .- . . , . . . . - . .