ML20004F553
| ML20004F553 | |
| Person / Time | |
|---|---|
| Issue date: | 06/08/1981 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20004F549 | List: |
| References | |
| FOIA-81-93 NUDOCS 8106190065 | |
| Download: ML20004F553 (3) | |
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- h, RESP 0.15E TO F0IA REQUEST F01A-81-93 SUB-PART A: MONITORING OR SAMPLING OF RADI0 ACTIVE EFFLUENTS FROM NUCLEAR POWER' PLANTS IN ILLIN0IS
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ItemA(1)
Monitoring or sampling of radioactive effluents from nuclear power plants in Illinois.
Response
Each plant is required to submit a Semi-Annual Effluent Release Report to the NRC Regional Office.
Requestor is referred to the pub',:c document rooms for the subject ~ reports for each operatir.c plant located in Illinois.
See also general informa-tion summary below.
Item A(2)
Data obtained from any such monitoring or sampling.
Response
See Semi-Annual Effluent Release Reports.
ItemA(3)
The location, time, and manner of any such monitoring or sampling.
Response
See Semi-Annual Effluent Release Reports and generic informa-tion in Standard Review Plan 11.5 and Regulatory Guide 1.21 (located in Public Document Rooms).
Item A(4)
The basis for the agency's determination that such data should be collected in the manner and at the time and place so collected.
Response
See Regulatory Guide 1.21 and the specific references to Title 10 of the Code of Federal Regulations (located in Public Document Rooms) given in the general information summary below.
ItemA(5)
Evaluation or analysis of such data.
Response
The data provided by each licensee are reviewed by staff of the Regional Office of Inspection and Enforcement and by the staff of the Office of Nuclear Reactor Regulation (Bethesda, MD).
The data are compared to typical plant values based on extensive l.
operating history. Unless the data exhibits substantial devia-tion from the norm, no specific evaluation or analysis of the data is performed. NUREG reports are published by the NRC which summarize data from all plants contained in the semi-annual release reports.
The most recent report, NUREG-0521, summarizes data for 1977.
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. y-gel;ERAL INFORIMTIOW
SUMMARY
ON
. REGULATORY REQUIREMENT FOR MONITORING OF RADI0 ACTIVE PLANT EFFLUENTS.
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-Each nuclear power plant is required-to monitor or sample releases of radio-
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activity to-the' environment which may be contained in plant liquid and gaseo'.i, effluent streams. The basic requirements-are summarized below.
10 CFR 20.106(b)(2) requires licensees to demonstrate that it is not likely that radioactive material discharged 'in the effluent would result in the
. exposure of an-individual to concentrations of radioactive material in air t-l or water exceeding the limits in Appendix B, Table II of '0 CFR 20.
10 CFR 20.106(d)(e) provides that "...the Contnission may limit quantities of radioactive materials in air or water during a specified period of time if 4
it appears that the daily intake of radioactive material from air, water or food by a suitable sample of an exposed popule..on group, averaged over a period of one year, would otherwise exceed the daily intake resulting from continuous exposure to air or water containing one-third the concentration of radioactive materials specified in Appendix "B", Table II of 10 CFR Part 20.
l 10CFR20.201(b),requireseachlicenseetomakeorcausetobemadesuchsur-veys as.may be necessary for~him to comply with the regulations of 10 CFR Part 20. A " survey" means evaluation of the radiation hazards incident to the
...reler u, (or) disposal... of radioactive materials... including... measurements t
of levels of radiation or concentrations of radioactive material present.
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10 CFR 50.34a requires, for power plants licensed under applications filed on or after January 2, 1971, that licensees identify design objectives for keeping
'?vels of radicactive material in effluents to' unrestricted areas as low as reasonably achievable. Appendix I of 10 CFR Part 50 provides numerical guidance on design objectives to meet "ALARA" requirements.
10 CFR 50.36 requires that each plant shall operate in accordance with certain Technical Specifications, which include, among other factors, limiting condi-tions for operation relative to limits on radioactive materials in liquid and gaseous effluents, specifications for the monitoring and sampling of plant effluents, and periodic reporting requirements for plant radioactive effluents.
In particular, Section 50.36a(a)(2) requires that each licensee submit a report to the appropriate NRC Regional Office within 60 days after January 1 and July 1 of each year specifying the quanti,ty of each of the principal radionuclides released to unrestricted areas in liquid and gaseous effluents during the previous 6 months of operation, and such other information as may be required by the Commission to estimate maximum potential annual radiation doses to the public resulting from such effluent releases (Note:
For specifics on monitoring or sampling of radioactive effluents from specific plants, see the Semi-Annual Effluent Release Reports for each plant).
Appendix A to 10 CFR Part 50 -- The General Design Criteria. Appendix A to 10 CFR Part 50 contains a number of very important criteria which all plants must meet. The criteria pertaining to release of radioactive material to the t
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r-r environment and to the monitoring of such release; are:
General Dasign Criterion 60 - Control of releases of radioactive materials to the environment.
General Design Criterion 61 - Fuel storage and handling and radioactivity control.
General Design Criterion 63 - Monitoring fuei and waste storage.
Gr aeral Design Criterion 64 - Monitoring radioactivity releases.
Regu_1_atory Guide 1.21: Measuring, Evaluating, and Reporting Radioactivit,g in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants Regulatory Guiae 1.21 provides guidance on programs acceptable to the NRC staff for measuring, evaluating and reporting releases of radioactive materials in liquid and gaseaus effluents.
Other than the regulations of Title 10 of the Code of Federal Regulations previously cited -- and which Regulatory Guide 1.21 implements -- Regulatory Guide 1.21 is the NRC staff's principal guide on what constitutes acceptable monitoring of plant radioactive releases.
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MEMORAf100M FOR: 1.co liigginbotham, Chief Radiological Safety Branch, IE:HQ FROM:
Thomas D. Murphy, Chief Radiological Asressment Branch, DSI
SUBJECT:
YOUR MEM0 0F JAt;UARY 22, 1981 - REQUEST FOR ACTION - GROUT 1D WATER M0tilTORIflG The questions raised in your memo of January 22, 1981 and the accompanying memo of A. B. Davis of Region III dated January 7, 1981 are already covered by current standard Radiological Effluent Technical Specifications (RETS) and the Radiological Assessment Branch Technical Position (BTP).
There are now no " Standard Environmental Technical Specifications." All radiological environmental technical specifications are now included in the RETS.
Copics of the appropriate sections of the RETS and the BTP for waterborne environmental monitoring are attached, liote that these current regulations do require monitoring of the water sources referred to in the Davis letter i.e. where
" wells are as important as private and public water supplies" and "where all public and private water sources are ground water." This is exactly the type of ground water monitoring Duane Arnold has incorporated in their Technical Specifications (see attachment).
However, we do not require ground water monitoring when the wells are up-gradient from the facility. This position is consistent with our overall approach of monitoring real and potential significant pathways to human beings.
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hy, hief Radiological Assessment Branch Division of Systems Integration
Attachment:
As stated cc:
D. Ross W. Kreger
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TABLE 3.12-1 (Continued) 2
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
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Number of Samples Exposure Pathway and Sampling and Ty;>e and Frequency and/or Sample Sample Locations **
Collection Frequency of Analysis 3.
WATERBORNE a.
Surface (Locations 46 and 47)
Composite
- sample collected Gamma isotopic analysis over a period of 3 31 days.
of each composite sample.
Tritium analysis of com-posite sample at least once per 92 days.
b.
Ground (Locations 16 and 49)
At least once per 92 days.
Gamma isotopic and tritium analyses of each w
sample.
h c.
Drinking (Locations 50-52)
Composite
- sample collected I-131 analysis of each over a period of < 14 dcys, composite sample; if I-131 analysis is and performed; or Composite
- sample collected Gross beta and Gamma over a period nf 1 31 days.
isotopic analysis of each composite sample.
Tritium analysis of composite sample at least once per 92 days, d.
Sediment from (Locations 53)
At least once por 184 days.
Gamma isotopic analysi<.
Shoreline of each sample.
- Composite samples shall be collected by collectin0 an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- Sample locations ase shown on the figure in the ODCM.
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'I TABLE 1 (Continued)
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Exposure Pathway Number of. Samples
- Collection Frequency" of Analysis Sampling and Type and Frequency and/or Sample and Locations WAlttD0!mE Sur t.sce9 1 sample upstream Composite sampleh yer Gamma is t pic analysis 1 sample downstream one month period monthly.
Composite for tritium analyses qur.rterly Grouual Samplesfrom1or2sourgesonly Quarterly Gamma isotopic and if likely to be affected tritium analysis quarterly Urinking i sample of each of 1 to 3 of Composite sample I-131 analysis on each j
the nearest water supplies over two-week period composite when the dose could be affected by its if I-131 anlysis is calculated for the con-discharge performed, monthly sumption of the water composite otherwise is greateg than 1 mrem i sample from a control location per year.
Composite for Gross p and gamma isotopic y
analyses monthly.
Cumpo-site for tritium analysis quarterly Sediment from 1 sample from downstream area Semiannually Gamm:i isotopic analyses Shoreline with existing or potential semiannually recreational value Ufha " upstream sample" should be taken at a distance beyond significant influence of the discharge.
The "down-sticam" saw,)le should be taken in an area beyond but near the mixing zone.
" Upstream" samples in an estuary must bn taken far enough upstream to beyond the plant influence.
hGunerally, salt water is not sampied except when the receiving water is utilized for recreational activities.
I Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly).
IGroundwater samples should be taken when this source is tapped for drinkin0 or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
l TA3LE 4.3-1 (Continu2d) l ENVIRONMF.NTAL RADI0 ACTIVITY MONITORING PROGRAM FOR THE DUMTE An!OLD ENERGY CENTER
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SAMPLING DESCRIPTION SAMPLE FREQUENCY ANALYSIS RDL\\RKS Type of Sample Sampling Point Operational Sarple Point Descrip tion Program Surface 89 90 Ferformed if gross 8#'
8#
Vater 49-52 bets activity exceeds (Cont'd.)
10.pci/1 and on a quarterly basis.
Ground 53 Treated Municipsi Monthly Vater Vater Cross bets 54 Inle t to Municipsi Canns isotopic Vater Tresteent Sys, snalysis Caens isotopic analyd sis vill be performeq 57-60 4 off-site wells on each sample in (in vicinity of site) which the gross betu '
activity exceeds
,_,37 10 pCi/1.
cgg Ds11y grab s.inple of.
E-untreated munleLp.il i
'#8 vste r is conposited
((,E-for montiily analysts;
" t-Two hour gra'a sa sple
~ ' E' of t reated r.uo le i;.il vster is cunpu.i ted n3 for nonthly analysiso Tritius Monthly ss=ples Cround vill be composited l Vater quarterly for l (Cont'd.)
t ri ciu's.
89 90 Perforced if grqss ?
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bets activity Y
"execeds 10 pCi/1 t,
and on a quarterly 4
basis.
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