ML20203H723
| ML20203H723 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/21/1997 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20203H704 | List: |
| References | |
| PROC-970121, NUDOCS 9803030310 | |
| Download: ML20203H723 (30) | |
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_(RSNGSANf.dALRADIO.;CTIVELTFLUENTRELEASEREPORT JANUARY-DECEMBER 1997
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 9
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PAGE 1 OF 31 LEAD DEPARTMENT: EFFECfiviDATEi RP/ CHEMISTRY , _ _ , . ,_ _ ot:2129L ,
8,EVISION_
SUMMARY
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- 1. Change radius of Land Use Consus from five (5) miles to two (2) rniles
- 2. Change fl3quency of Land Use Census from Annually to Dionnially
- 3. Cha'nged wording in section 4.0 to indicato that the ODCM uso c)nservativo dose factors which assume the presence of milk animals %ithin 5 miles" to "within the vicinity of Rancha Soco"
- 4. Editorial changes n
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RAD:OLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL y ;- REVISION O
- - PAGE 2 OF 31 TABLE OF CONTENTS l
SECTION. TITLE , , PAGE 0.0 P_OLICY ----- - - - - - - --
--~~~~~~---------~~~~~4 1.0 RADIOLOGICAL ENV!RONMENTAL MONITORING PROGRAM BASE 3---- -~~- 4 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DESCRIPTION.------- S
. 2,1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM P ARAMETERS-~~---S
' 2.2 ANALYSIS OF EXPOSURE PATHWAYS --------------------------------7
- 3.0 RADIOLOGICAL ENVIR_OMMENTAL MONITORING ---------- ----- - - ---- --- - -- 8 4.0 LA N D U S E C E N S U S ------------ --- -
~~-----------------------------10 5 0 EI)C:L CYCLE DOSE --------------~~ -----------------------------------11 6.0 INTERLABOR ATORY COMPARISON PROGR AM ---- ----- ------ -- - --------- -- 12 7.0 D E F I N ITI Qt1S ------~ ~-- ~~ ~--- ---- --- ---- - - -- -- --------------- ------ 1 3
. 8.0 RAQl,Ql,QOlQAL REPORT REQUIREMENTS ~~ - ~~ - - -- -- -- -- 13 0.1 ANNUAL RA70 LOGICAL ENVIRONMENTAt. OPJRATING REPORT (AREOR' ---- - 13
.- 8.2 ANNUffjM_pDACTIVE EFFLUENT RELEASE RFPORT (ARERR)----- -- - ------- 14
- 9. 0 R E F E R E N C E S -- ------------- -----~~---------------~~ --- --- ------~~~ - --- 14 10.0 IDEN1 tFIC ATIQtLCONVENTION FOR TABLmF 6_ SAMPLE L.QCATIONS.---- -- ----- - 16 11.0 REPORTING RESULTS_QF R ADIOLOGICAL ENVIR__QNMENTAL _DA_T,4 --- - - --~~ 17
- 12.0 SELE.QTIGN QF RADIOLQGICAL ENVIRONMENTAL MONITORING LQQ_ATION_S- -17 13.0 RADIOLOJICAQNVIRONMENTAL MONITORING PROGRAM (REMP) MANUAL QHANGES- ----- ------ -~~------------------------- - ---- --- -------- -- ---- ----- 1 8
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F L RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 9 PAGE 3 0F 31 LIST OF TABLES TABLE TITLE PAGE 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM-- 20 2 MAXIMUM VALUES FOR THE LOWER LIMIT OF OETECTION, LLD -22
- 3- REPOPTING LEVELS FOR REMP MEASUREMENTS 25 4 TWO LETTER DESIGNATION TO IDENTIFY THE TYPE OF SAMPLE -26 5 SECTOR LETTER DESIGNATIONS USED IN SAMPLE IDENTIFICATION --27 6 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS--------28
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL
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REVISION O PAGE 4 OF 31 0.0 POLICY -
The Sacramento Municipal Utility District (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 malntaining 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 ta performlng 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 RADIOL OGICAL ENVIRONMENTAL MONITORING PROGR6M C ' SES The Sacramento Municipal Utnity 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 q associated guidelines have been the foundation of the REMP and It:, programmatic elements
-i 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.
l 2, Provide the means to verify the radiological effluent control program of the Rancho Seco Nuclear Statiort.
I 3. Moet minimum limits for detecting radioactive isotopes in samples collected from the l evirons or direct measurements in t' e field.
- 4. Provide measurements of radiation and rddioactive materials in those exposure pathways, (i.e., liquid, gaseous, and direct radiation), and for those radionuclides, (i.e.,
cesium, and cobalt), v.lich lead to the highest potential radiation exposure of individuals resulting frc,en station operation.
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL v/
REVISION 9 PAGE 5 OF 31 This Manual contains the minirsum requirt,ments for the conduct of the Rancho Seco Radiological Environmental Mon!!aring Program (REMP). The requirements are consistent with USNRC regulations, the Branch Technical Position (BTP), Radiological Effluent Technica!
Specifications (RETS) for PWRs (NUREG-0472), and the Rancho Soco Pormanently Dofuelod Technical Specifications (PDTS) as Administrative Controls.
2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM D_ESCRIPTlQM The Radiological Envirenmental Monitoring Program is under the cognizance of the Nuclear !
Plant Closure Manager, with the responsibility for the administration and oversight of the progam 1:ssigned to tho Radiation ProtectiorJ Chemistry SuperinterMent (RP/ Chem Superintendent).
The design o the program is consistent wi'h the intent of Titio 10 CoJo of Federal Regulations, Part 20, " Standards for Protection Against Radiation" Section 1302. To in.plomont those requirements, the Permanently Defueled Technical Specifications, Oll sito Doso Calculation Manual, Health Physics Implementing Proceduros, and Surveillance Procedures have boon voveloped. The implementing proceduros address spcific areas in the program that requi to direct attention for completion.
] l 2.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PARAMETERS The monitoring and sampling aspects of the program are:
Identification of the effluent release pathways, Identification of the human exposure pathways, l e identification of the land usat,e parameters by the population within a two mile radius of the site.
Three principal release pathways at Rancno Soco Nuclear Station are:
gLaseous Effluents:
Discharges from the Reactor Duilding Stack, Auxiliary Building Stack, and the Auxiliary Grade Level Vent.
L._iauid Effluent ,
Discharges which are released from the retention basins via the waste water disposal system (Rogonerant Hold Up Tanks (RHUT) A and 8].
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- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL RSVISION 9 PAGE G OF 31 Direci t'adiation
Racietbn that emanates from systems or radioactive material contained within tanks or other containers which are within the site boundary to humans outside of T~,e site boundary, The pathways to human exposure to iadioactive materi'Is in the effluent release pathways l from Rancho Seco are: l Gaseous
. Inhalation of airoomo radioactive material by humans, or by animals that inhalo l end retain the materialin animal products that are consumed by humans, i.e.,
moat or milk.
. Consumption of radioactivo particulate material which, although carried by air currents, is deposited onto or is taken up by water sourcos or plants consumed by humans, or by e ilmsis that provide products that are consumed by humans, i.e., milk or meat.
(~N = Exposure from being immersed in air containing radioactive matorials as a gas C/ and/ or particulates.
. Exposure to the direct radiation from radioactivo materials that have been deposited onto surfaces from airborno releases.
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. Drinking of water from the release pathway by humans, or by aninials that are a food source for humans.
. The t.onsumption of fish or other animals shat 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 irrigated with water from the release pathway.
The consump' ion by humans of fruit or vegetation grown ',1 soil imgated with water from the release pathway.
Direct Radiation
. The exposure to radiation emitted from raoicactive materials within the Rancho m Seco site boundary, Sources include, but are not limited to, the Borated Water I
," Storago Tank, Domineralized Reactor Coolant Storage Tank, the interim Onsito Sturage Building (IOSB), and the independent Spent Fuel Storage Installation (ISFSI).
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. The exposure from being immersed in the release pathway water, to radiation emanating from material contained in the water.
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- 2.2 ANALYSIS OF EXPOSURE PATHWAYS r
Exposure pathways are analyzed through a systematic process which identifies a sample medium or organism that is found in the effluent pathways. Usage factors a!e determined that
- will suitably represent biological concentration, retention or uptake which may ultimately represent a contribution te human exposure. The pathways to human exposure are evaluated I through the analysis of data obtained from the performance of a land use census, The !
pc 1 rmance of the land use census is required by the Permanently Defueled Technical l Sps ,fications Section D6,8.3b.2. The analysis of the effluent and exposure pathways enables <
I the selection of sampling and monitoring locations tht fallinto one of two classes, those which are, and those which are not, influenced by effluent pathways. Those in the pathways are i referred to as indicator locations Several of the unaffected locatior,s are selected to represent I baseline or controllocations. j indicator locations provide data from the surrourkding environment that may t'e influenced by the operation of the plant because they are nearby, downwind or downstreatu .1 the release !
i pathway, Such data can be used to calculate doses to verify compliance with .M 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 wnan 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 realindividucts, may ba used to calculate dosos 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 those locations help discriminate
- between Rancho Seco releasns and other natural or manmade events that may impact human exposure.
At Rancho Seco, potentially radioartaiiquid efiluent is discharged into Clay Creek. A continuous flow of Folsom South Canalwateris released above the discharge point. TM continuous minimum flow and the liquid efnuent release are the major effluent release pathway, end thus the exposure pathway for the station during normal operations. Prior to the minimum release rato being retablished, Clay Creek was a seasonal stream, formed as tne confluence of three and one half square miles of drainage runoff upstream of the site. The now continuous flow of Clay Creek intersects Hadsciville Creek north and west of Califomia State Highway 104; Hadselville Crack intersects Laguna Creek just east of the Folsom South Canal.. Laguna Creek flows into the Cosumnes River approximately 20 niles from Rancho Soco.
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O RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL J REVISION 9 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 . elated to the land use cansus. This pathway is not confined by creek banks, but is subject to the meteorological conoiilons during the time of the release.
While not a significant release nor exposure pathway, weekly air sampling is performed to determme the dose due fo 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 thermoluminosonce dosimeters, which monitor continuously and passively. The dose is integrated ovor three months to accumulate a statistically significant exposure. The vast majority of the dose integrated by these 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 radiution which has penetrated the Earth's atmosphere.
3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING O
G The REMP shall be conducted AT ALL TIMES as specified iri Table 1 3.1 With the REMP not being conducted as specified in Table 1, prepare and submit to the Commission, in the Annual Rad:ological 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, DevlP"*ns are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions or seasonal unavailability.
3.2 With the level of radioactivity in an environmental samr'ing medium exceedir.g the Reporting Level of Table 3 when averaged over any calendar quartor, 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 detemmed, a Special Report which includet an evaluation of any rolosse conditions, environmental factors or other aspects which caused the Reporting Levels to be exceeded. This report will define corrective actions to reduce emissions such that potential exposures will meet the 10 CFR 50, Appendix I dose guidelines. When more than one of the radionuclides in Table 3 are ootected 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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V RADIOLOGICAL ENVIRONMENTAL MOf41TORING PROGRAM MANUAL REVISION 9 PAGE 9 OF 31 When radionucJidos other tfan those in Tablo 3 are detected and are the result of plant offluents, this Special Report shall be submitted if the potential annual doso to an Individual 13 Orcator than or equal to the calendar year guidelinos of 10 CFR.50, Appendix 1. This Spochel Reportis not required if the measured lovel of radioactivity was not the 'osult of plant offluents; however, the condition shall be reported and dosenbod in the AREOR.
1.3 With fresh vagotation samplos unavailablo from any of tho samplo locations required by Table 1, Identify the cause of the unavailability of samplos end the locations for obtaining replacement samples in the next AREOR. Tho locatice from which samplos woro unavailablo may then be deleted from Table 6 provided the locations from which the replacement samplos woro obtained are addcJ to Tablo 0 as replacomorit locations,if available.
3.4 The radiological environmental monitoring samplos shall bo collected por Tablo 1 frorr the locations showa in Table 6. Those samplos shall be analyzed to 'ho toquiromonts of Tablo 1 and Tablo 2.
3.5 The flow measuring devices on the environmental air monitors used for samphng the Tablo 1 Al3DORNE EXPOSURE PATHWAY shall be subject to a MONTHLY function h) v chock and shall be calibrated ONCE EVERY 12 MONTHS.
3.0 Tho REMP royulrod by Soction 1.0 providos moasuromonts of radiation and of radioactive matarials in those exposure pathways and fcr those ta .;onuclidos which lorJ to the highost potential radiation exposures of individualb resulting from the Station operation. This monitoring program thotoby implomonts SectioiIV.B.2 of Appendix I to 10 CFR 50 and supplomonts the REMP by verifying that tho morsurablo concentrations of radioactive motorials and lovels of radiation are not higher than expected on the basis of the offluent measutomonts and Off site Closo Calculation Manual (ODCM) modeling of the environmental exposure pathways.
Guidance for Soction 3.0 was provided by References 9.12 and 9 29 REMP changes may be initiated based on operational experianco and changes in tho regional population or agncultural practicos. Tho detoction capabilitins required by IaD;o 2 nro stato of the art for routino environmental measuremc its in industnallaboratones The LLDs for donking water moot thn requiroments of 40 CFR 141.
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( M t RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL PAGE 10 OF 31 4.0 LAND USE CENSUS l A Land Use Consus shall be cos,tiucted blonnially and shallidentify the location of tno noarost milk animal, the nearest residence and the nearost gordon of greater than 500 square feet producing fresh leafy vogotation in each of the 10 motoorological sectors l within a distance of two (2) miles. The locatlon of the noarest milk animalls not required if the Offsite Dose Calculation Manual (ODCM) dose calculations are using conservative dose factors which assume the presence of milk animals within the vicinity of Rancho Seco Nuclear Station. Vecctation sampling may bo performed at the Station Site Boundary In lieu of the garden census.
The Land Use Consus shah also include information rolovant to the liquid offluent 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 Soco, l 4.1 The Land Uso Consus shat; be conducted biorialally by using methods that will provide the best results, such as door to-door survey, aerial survey, or by consulting local
- agriculture authonties The Land Use Consus, or portions thoroof, shall he conducted during tho appropriate time of the year to provide the best results. The results of the O Land Uso Consus shall be included in the AREOR covering the consus yoor as required by Section 8.1.2, 4.2 With the Land Uso Censua identifying a locatio7(s) which yields a calculated dosn or doso commitment greator 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 Uso Consus identifying u location (s) that yields a ca:culated doso or doso commitmont (via the same exposure pathway) 20 percent greater than at a location from which samples are currontly being obtained in accordan* with Soe'~ n 3 0, Radiological Environrnental Monitoring, add the new location (s' bio 0 within 30 days or semit a Special Report to the Commission that identifies me cause(s) for excooding those requirements ar;d the proposed corrective actions for precluding recurrence. 5 The sampling location (s), excluding the control station location, haw ig the m *.t calculated dose or dose commitment (s)(via the same exposure pathway] may be doloted from Tablo 6 after October 31 of the consus year. Identify the nowlocation(s) in the next AREOR including a revised figuro(s) and table for the REMP Manual reflecting the now locatsun(s).
4.4 The Section 4.0 requirements are orovided to ensure that changes in the use of unrestricted areas are identified and that modifications to the REMo and the ODCM are mado if required by the results of the Land Uso Census. Those requirements also satisfy the requirements of Section IV.B.3 of Appendix ! to 10 CFR 50.
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( RADIOLOGICAL ENVIRONMENTAL MOf41TORING PROGRAM MANUAL REVISION 0 PAGE 11 OF 31 Rostricting the Land Uso Consus to gardons of greater than 500 square foot providos assuranco that significant exposure pathways via loafy vogotation consumption will be identified and monitored. Gardens of this size are the minimum required to produce the quantity (26 kg/ year) of loafy vogotation assumed (reforoco 9.14) to be consumed by l a child, in specifying this minimum garden size,it was further assumod that 20 porcent 1 of tho gardan was used for growing broad laaf vagotation (e.g./ lettuco or cahongo) a1d 2
that the productivity was two (2) kg/m ,
ln addition, by gathering information on the liquid offluent pathway 2nd the gaseous offluent pathway, tho Land Uso Consus providos assurance that propor radiol 4 cal environmental monitoring and radioactivo offluent controls are in place for the adequato protection of the health and safety of the gonoral public.
5.0 EVEL CYCLE DOjig The doso or doso commitment to any real MEMBER OF THE PUDLIC duo to releases of radioactivo matorialin gaseous and liquid offluents and to direct radiation from uranium fuoi cyclo sources shall AT ALL TIMES be limited to 13ss than or equal to 25 mi 'm (total body or any organ), and 75 mrem (thytold), in a colondar year.
5.1 With any of the Reporting Lovels of Table 3 being exceeded, calculations shall be made to determine whether the DJction 5.0 fuol cyclo dosoldoso commitment limits have boon excoodod. Contributions frorn direct radiation sources (including outsido storage tanks, etc.) shall be includod in this calculation.
5.2 If the Section 5.0 limits have boon exceeded, prepara and :ubmit to the Commission within 30 days a Soccial Report that defines the correctivo action to be taken to reduce sut,soquent refonses to prnvent recurronce of exceeding the Section 5.0 limits. This Special Report shall also .. cludo a schodule for achieving conformance with the Section 5.0 limits, This Speciai Report, as defined in 10 CFR 20 2203 shallinclude an analysis that est;rMtos the radiation exposure (doso) to a MEMBER OF THE PUBLIC from uranium feel cycle sources, including all effluent pathways and direct radiation, in a calendar year that includos the relouso(s) covered by this Spei!al Report This Special Repon shall also describo tovolt of radiation and concentrations of radioactive material involved, and the cat.so of tho exposuro levels or cencontratica,s.
5.3 If the estimated doso(s) oxceeds Section 5.0 limits, and if the release condition resulting in the violation of 40 CFR 190 has not already been correcteo. the Special Report shall also includo a request for a vanance in accord ance with the provision of 40 CFR 190. Submittal of the Special Repoit is considered a timely request, and a vananco is c. nted until USNRC staff action on the request is complete.
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C] REVISION 9 PAGE 12 OF 31 5.4 The Soction 5.0 roqulromonts are nenvided,in part, to moet the doso limitations of 40 ;
CFR 100 that have boon incorpor. , J into 10 CFR 20. For the Rancho Seco site,it is )
unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exccod the doso limits of 40 CFR 190 if the Station remains within twice the numerical guides for oosign objec0ves of 10 CFR 50, Appendix i and if direct radiaUon is kept small.
The Spedal Report will describe a course of aedon which should tosuit in the limitatlun of the doso to a MEMBER OF THE PUBLIC for a calendar year to within tho 40 CFR 100 limits, For the purposes of the Special Report,it may be assumed that the doso commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sou;cos is nogligible, with the exception that dose contributions from other nudoor fuel cyde facilitios at the same site or within a radius of fivo (5) miles must be considorod.
If the dose to any MEMDER OF THE PUDLIC is ovaluated to excoed the requirements of 40 CFR 100, the Spedal Report along eth a request for a variance (provided the rolosse conditions resulting in violation of 40 CFR 100 have not already been corrected)is considered to be a timely request and fulfills the requirements of 40 CFR 100 until USNRC staff action is completed.
- An individualis not considered a MEMBER OF THE PUBLIC during any period in which ho/she recolves an occupational dose.
6.0 INTERLADORATORY COMPARISON PROGRAM The laboratory performing analyses of Tablo a samplos pursuant to the requirements of Table 1 shall AT ALL TIMES partidpate in an Intertaboratory Comparison Program (ICP) approved by the Commission. The ICP approved by the Commission may not always supply tests for the analysos required by Table 0.
Since no Commission appro"9d ICP exists for TLDs, the laboratory performing analysob of the REMP onvhunmental TLDs shall AT ALL TIMES parbeipato in a licensoo approved comparison program.
0.1 With ICP ana'yses nct being performed as required in Section 6 0, repon the correctiva actions taken to provent a recurronce to the Commission in the AREOR as required b)
Soction 8.1.
6.2 A summaiy of the results obtained as a participant in the ICP nall be indudod in the AREOR as required by Section 8.1.
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1 0.3 The requirement to particJpato In s' CP is provided to ensu:o that ' r. Anw e : '
on the procision and accuracy of the monsuromonts of radioactivt i :.eds) % l environmental sample matrices are performed as part of the qual.rj ammtna 5 7. r l for environmental monitoring In order to demonstrate that the resuhs e i W.riaky l valid for the purposes of SectJon IV.D.2 of Appendix l to 10 CFR 50. j DEFINITIONS 7.0 7,1 i ORTNIGHTLY Onco por fourtoon (14) days 7.2 INDUSTRIAL AREA That portion of the Station property, access to which is controlled as doscribed in the NRC approved Security Plan by security foncing, equipment and personnel.
7.3 SITE DOUNDARY That line beyond which the land is neither owned, nor learod, nor otherwise controlled by the licensoo.
7.4 RESTRICTED AREA An area, access to which is limited by the licensoo for the purposo of protecting individuals against unduo risks from exposure to radic!1on and radioactivo materials. Restricted area does not includo areas used as residential a) quarters, but separate rooms in a tosidential building may bo set apart as a restrictad area.
7.5 CONTROLLED AREA An area, outside of a rostricted area but insido the site boundary, access to which can be limited by the licensoo for any reason.
7.0 UNRESTRICTED AREA An area, access to which is neither limited nor controlled by the licensoo.
i .7 MEMBER (S) OF THE PUBLIC - Any individual except when that individual is recolving an occupational doso.
8.0 {MWQiQGICALREP_Q[LTREQUIREMENJJ 81 ANNUAL RADIOt,QGiCAL ENVIRONMENTAL OPERATING REPORT (AREQJ3) 8.1.1 An AREOR covering the operation of the Station dunng the previous calendar year shalt be submittod to the USNRC prior to May 1 of each year in accordanco with Permanently Defuelod Technical Specification D8 9.2.3.
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REVISION 9 PAGE 14 OF 31 8.1.2 The APEC,R shallincluda summaries and stausucal evaluations of the results of the radiological environmental surveillance acuvities for the report period, including (as uppropriate) a comparison with operationst controls. The AREOR shsil also include the rebulls of the Land Use Census requirnd by Section 4.0, LAND USE CENSUS. In the event a redlonuclide concentrauon should be confirm 1d in excess of th9 Reporting Levelin Table 3 by environmental measuiements, the AREOR shall describe a planned course of corrective action. ,
8.1.3 The AREOR shallinclude summarized and tabulated resu!!s of all radelogical environmental samples taken dur(ng the AREOR period. In the event that some results are not available forinclusion, 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 locations keyed to a tablo giving distances and directioris from the Reactor Building) and the results of participation in the interiaboratory Comparison Program required by Section 6.0. The AREOR shall also includo infonna"on related to Secuon 5.0, Fuel Cycle Dose.
O 82 ANNUAL RADIOACTIVE EFFLUENT REW6SE REPORT (ARERR)
Any changes made to the REMP MANUAL during the ARERR reporting period bhall be included in that ARERR. The complete REMP manual, in its revisec 'orm, sht.li be submitted with the ARERR. ,
l 9.0 BEEEBENCES The following documents portain to the design and conduct of radiological environmental mcnitoring programs:
1 9.1 Amencan National Standxds insti'u.9 (ANSI), Eerformance.12gn,q3nd Procedu,rpt j Ssecifications for Thermoluming.gg Qgtimetry (En,yironmentgl, Applications), ANSI '
Standard N545 (1075).
9.2 American Nuclear insurers and Mutual Atomic Energy LiaWiity Underwnters (AN!/MAELU), Environmental Monitorina Proarams, Information Bulletin 861 (1988).
9.3 ant /MAELU, Enaineerina Insocetion Cnteria for Ra,gioloalcel Envirgnmental Monitorina.
Section 5.2, Revision 2.
9.4 ANI/MAELU, Nuclear Liabihty Insurance Records Retenqqr), It formation Bulletin 801 A, Rev. 2 (1986).
l l
4
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)- -,nr _
m v.w.w,mwgw.
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL PAGE 15 OF 31 9.5 Commit'oe on the Biolo0lcal Effects of lonizing Radiations (DEIR),Ihg Effects on Pooulations of Exoosure to Low Lovels of lonizina Radiation: DEIR V Report (1990).
k 9.6 Nauonal Council on RadlaUon Protection (NCRP), A Handbook gh13dioactivlty MfAsurements Proceduren. NCRP Report No,68, Second Edition (1985).
9,7 NCRP. Radioloalcal Assessment: Predictino the TransoqIt Blosecumulati20.gnd Volske by Man of Radionuclides Released to the Eny!ronment, NCRP Report No. 76 .
l (1984),
9.8 USEPA, linykonmental Standards for the Uranium F631;,40 CFR 190, Subpart B (1993),
9.9 USEPA, Up3radina Environmental Radiation Data, Health Physics Society Committee Report HPSR 1, EPA 520/180-012 (1980).
9.10 USNRC, Cfiterion 64 Monitorina Radioac1!ve Relettg),10 CFR 50, Appendix A (1993).
9.11 USNRC, Numerical Guldes for Dggian Obitstives and Limiting Conditions for 02g1D.189.0 O to Meet the Criterion 'As low Atta Reasonably Aenlevable' for Radioactive MatgI!3 LID Llaht V.{ tiff Coofed Nuclear PcwE, Reactor Effluent 1,10 CFR 50, Appendix I(1993).
9.12 USNRC, An Accepigble Radiolooical Enyiftpnmental Monitorina &pgr a n), Branch Technical Position Rr'v,1 (November 1979),
9.13 USNRC,[mpinmentation of Proarammatic Controls for RadiolgalGij Effluent Technieg!
Spoesfications in the Administrative Controts S.p.gtlon of the Technical Specifications an.fi,l!!e Reloepjigns! Ep.codura! Detalls of RETS to the Gif.sle Dose Cpjqulgil0D Manual or the Process Control Pronram. Genanc Letter 89 01 (January 31,1989).
9 14 USNRC, Calculation of Ar.nu.atppigs to Man f lom Routino Rplag191 pf_Rg.agiqi (iffjpgnts f for the Purqq1g of Evaluatina Comoliance with 10 CFR 50. Appendix l, Regulatory Guide 1.109 (1977).
9.15 USNRC, Eltimatitio Aqug.tj.g_Q!)ngf} ion of Eff!p_qnt),f tgm Aes!QQntial png Routino
[lg. actor RolegJtgs for the Purooje of Imptqn)qnitng Apponden 1. Regulatory Guido 1.113 (1977).
9.10 USNRC, Measunna and Reportina of Radioactivity in the En,iront of Nuqlear Poggf Planti, Regulatory Gu:de 4.1 (1973),
9.17 USNRC, $pparation of dnvironmental Reports for Nucigar PowgL$tations, Regulatory Guido 4 2, Rev. 2 (1976).
-- "a'r~-er
~
t' i RADIOLOGICAL ElMRONMENTAL MONITORING PROGRAM MANUAL
/ REVISION 9 PAGE 10 OF 31 _
9.18 USNRC, Performance. Testina and Procedural Specifications for ,TJ1ermoluminosengg posimetry: Environmental Applications," Regulatory Guido 4.13.
9.19 USNRC, Quality Assurance for Radiofonical Monitonna Proaragg (Normalhperation}h Effluent SMams and the Environment, Regulatory Guido 4.15. Rev.1 (1979).
9.20 USNRC, Epdloloalcal Assessment: A Textbook on Environmental Dos? NUREG/CR-3332 (1983).
9.21 UGNRC, Lg. wor Limit of Detection: Definition and Elaboration of a ELgposed Po1))!gg for Redioloulcal Effluent and Environmentel Measuremenu, NUREG/CR 4007 (1984).
9 22 USNRC, Radiotoolcol Effluent Technical Sp_qpifications for PWRs, NUREG-0472, Rov.
2 (July 1979),
'+ .3 USNRC, Redig 19alcol.Monitorina by NRC Licensees for Routine Qperations of Nuclear Facilitics, NUREG 0475 (1978).
9.24 USNRC, Methods for Demonstratino LWR Compliance With the EPA Uraniun FJej Qycle Stendard (40 CFR 100), NUREG 0543 (1980).
9.25 USNRC, Qq;e Limits for individual members of the p@lig.10 CFR 201301 (199'). a 9.20 USNRC, Reporis of exposures. rac.Jtjpn, levels. and.concentrptions of radjpagtjye mpjg.rlpi exceedino the limits,10 CFR 20.2203 (1993).
9.27 Morni Eisenbud rayironmental Radioactivity From Natura.L Industrial,and Military Sourcet Third ' <.stion (1937).
9.28 Rancho Seco Permanently Defueled Technical Specificativns.
9.29 USNRC, TechngjpayJafety and Costa of Decommlpyjq,nina a fjf ference Pressunze;I Wat
.,_ ff Reacjor Power Station. NUREG/CR-0130 ( ano 1978) 9.30 USNRC. 6JrJamp.ung tn,2q Wpr}plaqq. Regulatory Guide 8 25. Rev 1 (June 1992) 10.0 !QENTIFICA1QN CONVENTION FOR TABWJ SAMPLE t.OQA,_T[QL{S Sampling and monitoring sites des.gnated in Table 6 are identified using the following convention:
10.1 To establish the fact ihat the Table 6 samples onginate from the Rancho Seco REMP, g ~, the letter "R" precedes overy samplo sito designator.
U/
- * - - --- - r. . , y . w. ,,i- = w w wmessen_ _ . , ,, . . . , - ,y;yfy
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 9 PAGE 17 OF 31 10.2 Thi 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.
10.3 The numbers following the SAMDLE TYPE abbreviation reflect the straight line distanco l (miles) to the sample site, referenced to the center of the Reactor Building. l 10.4 Following the distance, a SECTOR DESIGNATOR letter is included to specify which of the 16 meteorological sectors the sample site is encompassed. Refer to Tr' le 5 for a 4 listing of the sector designators.
10.5 The final character in the sample site designation is the letter *O" or the letter *P". The 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 post operational period fcilowing the issuance of the Possession Only License.
4 10.0 The present identification convention has been selected in proforence 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 require supporting data from the Radiological Environmental Monitoring Program address the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report.
Special Repwts are made specJfic in HPIP 2050, RadiclogWat Environmental Monitoring Program Reports. Specified therein are conditions requiring special reports.
Lnd reporting requirements in days for submittal. This includes those calculations to provide rapid assurance of the degree of compliance with 10 CFR 50 Appendix 1, and 40 CFR 100 calculations after releases of any origin.
1 12 0 SEECTION OF B@lOLOGICAL ENVIRONMENTAL MONITORING t.OC ATIONS in conjunction with the data base established from the land use consus, the requiroments of the Pelmanently Defueled Technical Specifications, and the guidance described in Section 2 0 of this Manual, the selection of sampling and monitoring sitos is perforrnod. These selected locations provide at least the minimum number of locations specified in Table 1.
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( RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL I
\ REVISION 9 PAGE 18 OF 31 Data was gathored from the land uso consus, Lawrence Livormoro National Laboratory Rancho Seco Study Reports, Oak Ridge National Laboratory Study Reports, and from additional sampling sitos from which materials have boon collected. The information gathored was usod to determino Indicator sitos. Presently, a number of control sitos havo boon selected and are not anticipated to bo Increased in number.
The second column of Table 6 identifies the Samplo Class of a particular sample as either an Indicator (IND) or a Control (CON) Samplo. Additional sample locations designated as Special (Spoc) are used to perform inillal radiological evaluations.
Environmontal thormoluminosence dosimeters are placed in the envirens around tho site. These dovices passively monitor radiation in the immodlate e nvirons. Data from TLDs is trended to establish variations which are influenced by sonsor'sl, metoorological, local and global sources. TLDs will also respond to racVion in the offluents of the plant if they pass in non proximity, The data is included th ooch quartorly environmental roport.
Sample locations for the collection of the flora and fauna aro concentrated in the liquid offluent pathway to the West. Representativo samplos of all the pathways and suitable locations are established in all direct,ons. / sir samplers are distnbuted to achlove a p sampling of air from major wind directions across the site.
Q The Radiological Environmental Monitoring Program maintains at least those minimum sampling locations and type of samples to meet the requirements listed in Table 1.
A sito has been establishod for a vegott olo gardon. The gordon is at the sito boundary alongsids Clay Crook, and irrigated witf. water from the offluent strosm. This data is considered essential for comparisons to vogotation not irngated with effluent stream water for determination of bloaccumulation for soil types common to the environs.
All of the environmental samplo locations required for the Radiological Environmental Monitonng Program are designated in Table 6 Additional sampling locations are hstad in HPIP 2070. REMP Routes and Sample Locations.
13 0 B@ /onical Environmental Monitorina Pgaram (REMP) ManuaLQhannes As required by the Permanontly Dcfuoled Technical Soccifications (PDTS) section DG.14 3, enanges to the REMP manual shall be documented and the records of the reviews performod for the changes shall be retained as roquired by the PDTS section D0.10,2.o. The documentation shall contain sufficiern information to support the change together with the appropriato analysos or ovaluations justifying the chango 9
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N RADIOLOGICAL Et4VIRONMEf4TAL mot 41TORit4G PROGRAM mat 4UAL
'd REVISION 9 l PAGE 19 OF 31 l
The documentation shall also contain a dolormination that the chango will malntain the lovel of radioactivo effluent control that Is required by 10 CFR 20.1302,40CFR100,10 CFR 50.30a, and Appendir.1 to 10CFR50 and not adversoly impact the accuracy or reliability of offluent dose or sotpoint calculations.
Changos to the REMP manual shall becomo effoetivo afttr roslew and acceptanco t 1 the PRC and approval by the Plant Manager.
Changes to the REMP manual shall be submitted to the b'edaai Hoc A , -
Commission in the form of e compkte,logibio copy of the out.re RD,iP ? ' ..i a:i ',s a part of or concurrent with the Annual Radioactivo Etti . nt Refus<> "el. ort fc o porlod of the report in which any chango to the RfAP Unr oal wa: rnado. We ,
chango shall bo identified by markings in the marg:
sff scied pan us, clo4ily indicating the aron of the pago that was changes, tait ..I indicatts tho d2to (.c g.,
month / year) the change was implomontod.
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! RADIOL OGICAL EfMRONMENTAL MONITORING PROGRAM MMiUAL REVISION 9 1
PAGE 20 OF 31 I
Tab!e 1 RADIOLOGICAL EtMRONMENTAL VONITORING PROGRAM Sampling and Type and Frequency of Analysis Exposure Pathway Number of andt or Sample Samples
- CoIIection Frequency Particulate sampier. Anaiyze forGross Beta l 3 Continuous operation
- 1. AIRBORNE radioactmty at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> foDowing filter change. g l of samplerwith i sample co!Iection as Perform gamma iso *@ analysis on each sample g required by dust where gross beta actmty is greater than 10 times the -
loading but atleast yeariy mean of control samples for the same sample once per week period. Puform gamma isotopic analysis on composite (by Io.ation) sample at least once per cuarter.
Atleast once per Gamma dese. Atleastonce perqueer
- 2. DIRECT At least 24 locations RADIATION vath 2 dosimeters at quarter i
y each location i 3. WATERBORNE Gamma isotopic and tritium ana!ysis of each composite a Surface 1 Composite sample co!!ected monthly 3 Grab sample cettected Gamma isotopic and tritium aca!ysis of each sample l monthly 1 Grab sample cosected Gamma isotopic and tritium analysis of each sample
- b. Runoff fortnichtiv
- Sampie locations are shown in Tabte 6
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J *R.J v RAD'OLOGICAL ErMRONMENTAL MONITORING PROGRAM MAN'UAL REVISION 9 PAGE 21 OF 31 Taote 1 RAD'OLOG: CAL ENVIRONfENTAL MONITORING PROGRAM 8
Opcsu.m Pathway Number of Sampling and Type and Frequency of Analysis _
and/ or Sample Samples
- Co!!ection Frequency
- 3. WATERBORNE 2 Grab sampie conected Gross Beta Gamma isotopec, and Tntium analysis of
- c. Grour.d cuarterfy each sample g
- d. Dnnkrng 2 Grab sample couected Gross Beta. Gamma isotopic, and Trcum ana!ysis of a monthly ' each sampie.
- e. Mud and 2 At least quarter + Gamma isotopic analysis of each sample.
Sitt Sample conected of the top 3* of materia! 2 f*_ from shorerine.
- 4. INGESTION
- a. Fish 1 At least semiannua!!y. Gamma isotopic analysis of the edble portion of each
. At least one sample sample.
of eitherof the species
. listed in TaNe 6 4
~
.j b. Food 1 At least semiannua!!y. Gamma isotop.c anafysis of the ed:ble port;on of each l
1 One samp!e of sample.
vegetable (s) as shown
! I in Table 6 Sampie locations are shown in Tabte 6 3
5 4
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RADIOLOGICAL EfNIRONMENTAL MONITORING PROGRAM MANUAL REVLSION 9
. P/.GE 22 OF 31 Table 2 MAXtMUM VALUES FOR THE LOYER LIMIT OF DETECTION. LLD *
Airborne -
Analysis Water Particu! ate or Fish Food Products Mud and SCt I (pCi/ !) Gases (pCi/m*) (pCikg-wet) (pcil kg-wet) (pCi5cg-wet) 6 Gross Beta 4 0.01 l g H-3 2000 C D
(1000 )
Mn-54 15 130 Co-60 15 130 150"I Zn-65 30 260 6 ' d 130 60 150 1 Cs-134 15(10 ) O.01 l l Cs-137 6 8 130 60 150 18(10 ) u 0.01 l l l O
m a
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O RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 9 PAGE 23 OF 31 Table 2 MAXIMUM VALUES FOR THE LOWER LIMI( OF DETECTION, LLO *=
- The Low Limit of Detection (LLD) values for the radionuclides presented in Tcble 2 are those recommended in Reference 9.12 (DTP)and Reference 0.22 (RETS).
The LLD of a radionnalysis system is that value which willindicate the presence or absence of radioactivity in a sample when the probability of a f also position and of a false negative determination is stated. The probabilities of the falso positive and falso negative determinations are taken as equal to 0.05. The equation for estimating the maximum LLD is given by the following equation:
!J,D = -
3.7E- 2(TEl')cxp(-A/,), pct /1, pCi/kg wet, or pCil.W whore:
2.71 = f actoi to account for Poisson statistics at very low background count rato 3.29 = twice the constant used to establish the one sided 0 95 confidonen interval
= standard deviation of the background count rato Sb (D / (tot ) + B / to#) 0 0 0 = background counts a background count interval, see to e samplo cour.t interval, soc is 3.7E 2 = conversion f actor, dis / soc / pCI Y = radiochemical process yielJ (product of all factors such as abundance, chemical yield, etc.)
E = counting officioney, ets/ dis V = sample volume or mass,I or kg
). = radioactivo decay constant for the associato nuclido
IL ( O (
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL 3 REVISION 9 PAGE 24 OF 31 Table 2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION, LLD d
= elapsed time from the midpoint of samplo collottion to the midpoint of te counting, see The LLb is defined as an a pMpj(before the fact) est! male and is not to be calculated for each sample analyzed on an a posterforf (after the f act) basis.
Occasionally, unavoldably small sample sizes or other uncontrollabla circumstancos may result in a Morf LLD values not being mot. In such cases, the contributing f actors will be identified and described in the Annual Radiological Environmontal Operatirig Report.
b LLD for Drinking Water samplos from Reference 9.22 (RETS).
Other peaks which are measurable and identifiable, toriother with the nuclidos in TaL'e 2, shall be Identified and reported, d
Composite analysis LLD from Reference 9.22 (RETS) is a hown; individual sample LLD 3 3 is 0.05 pCl/m This LLD (0.05 pCl/m )is a site specific value.
LLD for Mud and Sitt Co-60 is not required by Reference 9.22 (RETS). This value is consistent with the RETS requirod LLD for Cs 134 and Cs 137.
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U RADIOLOGICAL EtMRONMENTAL MONITORING PROGRAM MANUAL REVISION 9 PAGE 25 OF 31 Table 3 REPORTING t WELS FOR REMP MEASUREMENTS i
Analysh Water Aistorne Particulate or Fish Food Products (pCilI) Gases (pClim*) (pCilkg-wet) (pCil kg-wet) y H-3 20000* W Mn-54 1000 30000 <
Co-60 300 10000
, Zn-65 300 20000 Cs-134 30 10 1000 1000 ;
Cs-137 50 j 20 2000 2000 t Gross Beta b 4c 2*
- ~
Applies to vater samples utilced for human consumption only. This valut s as specified in 40 CFR 141. ,
[,
Grcss Beta activ:ty in wa:er cf ten times the yearly mean of the control samptes is indicated as the level that gamma isotopic analycis should be performed on the indtv dual sample [ Reference 9.12 (BTP)}. Gamma isotopic ana!ysis on each water sample ,
is required by Table 1 and therefore this reporting requirement does not apply.
l,!
c Gross Beta activity in air of ten (10) times the yearty mean of the control samples is indica'st as the level thaf Gamma Isotopic i analysis should be performed on the indmduat sampie The value indicate d is site specfc' l' i
h
I
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') RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL s _./ REVISION 9 PAGE 20 OF 31 Tobio4 TWO LETTER DESIGNATION TO IDENTIFY THE TYPE OF SAMPLE '.
Letter Dostanotion Type of Sample Reprojented AG Algao Sarroio AS Air Sample FS Fish Sample LV Gardon Vogotation MS Mud & Silt (Sodiment)
RW Runoff Water b
SW Surface Water TL Dirnet Radiation (TLD)
WW Ground (Well) Water DW Drinking Water
(~')'
Soil SL Additionallottor designatio ey be added as samplo designators if additional sample types are collected for analysis.
D The portion of procipitation on the land that ultimately reachos streams is considered to be surface water.
7m l
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL ,
1 PAGE 27 OF 31 Table 5 SECTOR LETTER DESIGNATIONS USED IN SAMPLE IDENTIFICAT.Obl True North Compass Sector Sector Degrees Sector
~
A 348,75 to 11.25 N
~
O 11.25 to 33.75 NNE
' ~
C 33.75 tt $6.25 NE D 50.25 to 78.75 ENE
~
E 78.75 to 101.25 E
~
F 101.25 to 123.75 ESE G 123,75 to 140.25 SE H 146.25 to 108.75 SSE J 168.75 to 191.25 S K 191.25 to 213.75 SSW L 213.75 to 236.25 SW
~
M 230.25 to 258.75 WSW N 258.75 to 281.25 W P 281.25 to 303.75 WNW Q 303.75 to 320.25 NW R 320.25 to 348.75 NNW
~
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t
( kh ( l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL L REVISION O PAGE 28 OF Si j Table 6 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS ,
i Sample identification Samp!, Collection Location Identification
. (Former ID) Class Frequency 6!B (Particulates)
RASO,1CO IND Weekly On Site (PAP Building Carport)
(RAHO) i RAEO.3MO IND Weekly On Site (E' fluent Dischargo)
RASO,7EO IND Weekly Meteorological Tower f
RUNOFF WATER RRWO.6MO IND Biweekly Site Boundary SURFACE WATEil RSWO,7NO IND Monthly Water Sump 2 RSW1.3F0 IND Monthly Rancho Soco Reservoir (RSWCO)
RSW3.7NO CON Monthly Folsom South Canal (Composito Samplo)
(RSWBO)
RSW1.8NO IND Monthly Confluence of Clay and Hadselvillo Crooks RSWO.3MO IND Monthly Effluent Discharge (Composite Sample) l ___ . - . . . . _ - _ . . ._ . , _ , . . , . . . _ _ _ . - . - . . _ _ - - _ - . . . - . , , _ .
1
) s
( kl I O RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 9 PAGE 29 0F 31 >
Table 6 (continued) i RADIOLOGICAL ENVIRONMENTAL SAMPLING L'JCATIONS .
l Sample ldentification Sample Collection Location identification
, (Former 10) Class Frequency GROUND (Well)
W81}i8 RWWo.3E0 IND Quarterly Site Well (RWWAO)
RWWO.800 CON Quarterly Marciel Ranch DRINKING WATER RWDO 1GO IND Monthly industrial Atou Drinking Wator Sourco
, RDW1,8Fr CON Monthly Rancho Soco Lake Dnnking Water Source >
MUD AND SILT (Sediment)
RMSO.3MO IND Quartody Elfluent Discharge RM50.6MO IND Quartoriy Sito Doundary (RMSEO)
FISH
- RFSO.0MO IND Semlannual;y Clay Crook near the dito Boundary NOTE: Include predator (e.g., bass, sunfish) or scavenger (o g., catfish, sucker) species, as
- available.
Other downstream locations may be substituted to meet sampling requirements.
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( 49 66 49 s 7 s RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAPA MANUAL
('") REVISION 9 PAGE 31 OF 31 TAbhtQ (Continued)
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS ,
Samplo identification Samplo Collection Location identincation (Former ID) Class Frequency __
lLQ .
RTL1.0F0 IND Quartoriy #19 Rancho Soco Lake RTL1.5MO IND Quarterly #20 Clay East Road & Kirkwood RTL3.9KO IND Quarterly #26 Dordun Road RTL7.4MO CON Quartoriy #30 Herald Firo Department RTL3.7NO IND Quartoriy #31 Hobay Road RTL3.8MO Ira Quartoriy #33 Folsom South Canal Pump ng -
Station
- RTL1.9NO IND Quartoriy #35 Hadsolvillo Crook and Plant i
(') RTL1.7FO IND Quartoriy #43 Effluent Water Rancho Seco Reservoir 7
RTL1.4DO IND Quarterly #46 Twin Cith.s Road (Highway 104)
RTLO.0PO CON Quartoriy #55 Colony Road RTLO,8DO IND Quarterly #63 Marclol Ranch RTLO.6MO IND Quarterly #65 Site Boundary irrigated Gardon RTLO.3PO IND Quarterly #68 West Fonce, adjacent to ISFSI RTLO.3NP IND Quarterly #88 ISFSI outer Security fonco, near inactive West Gardon RTLO4NP IND Quarterly #89 ISFSI outer Secunty fence, SW corner RTLOSNP IND Quartoriy #D0 ISFSI ouer Secunty fence. NW corner RTLO.30P IND Quarterly #01 ISFSI outor Secunty fonco. NE comer n
./
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