ML15238A832
| ML15238A832 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba, McGuire, Perkins, Cherokee  |
| Issue date: | 11/09/1978 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 7811210306 | |
| Download: ML15238A832 (31) | |
Text
pNC REGLA UNITED STATES 0
NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTA STREET, N.W.
ATLANTA, GEORGIA 30303 NOV 9 1978 In Reply Refer To:
RII:SCEwald Duke Power Company ATTN:
Mr. William 0. Parker, Jr.
Vice President, Steam Production Post Office Box 33189 422 South Church Street Charlotte, North Carolina 28242 Gentlemen:
The U.S. Nuclear Regulatory Commission will conduct a one-day seminar in Atlanta on December 5, 1978, to discuss new Model Radiological Effluent Technical Specifications for Nuclear Power Plants. Representatives from the Office of Nuclear Reactor Regulation will make presentations on background, development, and implementation of the effluent technical specifications and will discuss the major changes from existing specifi cations. A question and answer period will follow the prepared presentations.
All utilities which hold operating licenses or have applied for licenses to operate nuclear power reactors are invited to attend. We encourage you to send those members of your staff most closely involved in your radiological effluent program.
Information on time, location, accommoda tions, and an attendance registration form are enclosed. A copy of the agenda is also enclosed.
If you have questions beyond the scope of the agenda, please submit them with your registration forms so that the speakers will be able to provide answers to those questions that apply to the entire audience.
We will attempt to answer any questions pertaining to radiological effluents and environmental monitoring; however, if the problem is only specific to your case and not of general interest to the entire audience, we will communicate with you directly, rather than at this seminar.
Sincerely, ames P. O'Reilly D'rector
Enclosures:
Seminar Information Sheet Registration Form 0 S Proposed Agenda
Duke Power Company NOV 91978 cc w/enclosures:
Mr. M. D. McIntosh, Plant Manager McGuire Nuclear Station Post Office Box 488 Cornelius, North Carolina 28031 Mr. J. C. Rogers, Project Manager McGuire Nuclear Station Post Office Box 33189 Charlotte, North Carolina 28242 Mr. J. E. Smith, Station Manager Oconee Nuclear Plant Post Office Box 1175 Seneca, South Carolina 29678
SEMINAR INFORMATION SHEET SUBJECT Model Radiological Effluent Technical Specifications and Environmental Monitoring DATE December 5, 1978 TIME 8:00 a.m. to 5:00 p.m.
LOCATION Stadium Hotel, Braves Room 450 Capitol Avenue, S.E.
Atlanta, Georgia 30312 TRANSPORTATION Limousine service to and from the Atlanta airport is available.
ACCOMMODATIONS A number of rooms have been set aside for seminar participants at the Stadium Hotel for the night of December 4, 1978. Rates for seminar participants are $20.00 per night (single), and $26.00 per night (double),
plus 4% sales tax.
Reservations are the responsibility of the attendee(s) and should be made no later than November 22, 1978.
LUNCHEON A buffet luncheon has been arranged for participants at a charge of
$6.00 per person (includes tax and gratuity).
In addition, coffee will be served during morning and afternoon breaks at a charge of $1.00 per person. Money for lunch and coffee will be collected during registration on December 5.
NRC CONTACT S. C. Ewald 404/221-4181
SEMINAR REGISTRATION Please submit the following information for each representative planning to attend:
NAME TITLE REPRESENTING Do you plan to take advantage of:
LUNCHEON ($6.00)
Yes:
No:
COFFEE SERVICE ($1.00)
Yes:
No:
To assist us in making preparations for the seminar, please return all registration forms by November 27, 1978, to:
S. C. Ewald U.S. Nuclear Regulatory Commission Region II 101 Marietta Street Suite 3100 Atlanta, Georgia 30303
AGENDA FOR REGIONAL SEMINAR ON RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS I.
INTRODUCTION AND BACKGROUND A.
Standard Technical Specifications B.
Appendix A vs. Appendix B C.
Implementation of Appropriate Regulations
- 1.
- 2.
- 3.
40 CFR Part 190 II.
SCHEDULE FOR IMPLEMENTATION A.
OL Applications B.
Operating Reactors III.
INTERFACES WITH NRR IV.
DEVELOPMENT OF STANDARD TECHNICAL SPECIFICATIONS A.
NRC Task Force B.
AIF Task ForcS C.
Approval by R C D.
Deviations from Standard Technical Specifications V.
METHOD OF IMPLEMENTATION A.
Amendment to Operating License B.
Amendment to FSAR VI.
MAJOR CHANGES FROM PRESENT TECHNICAL SPECIFICATIONS A.
40 CFR Part 190 C.
Maintenance and Use of Equipment D.
Solidification -
Special Reports (40 CFR Part 141)
F.
Environmental Monitoring VII.
DISCUSSION OF NUREG-0133 VIII.
DISCUSSION OF TECHNICAL SPECIFICATIONS A.
LCO B.
Action C.
Surveillance IX.
QUESTION AND ANSWER-PEIOD
DISTRIBUTION' Docket File (3)
UNITED STATES.
ORB#4 Rdg NUCLEAR REGULATORY COMMISSION RIngram WASHINGTON; D.C. 20555 September 13 1978
Docket No.5:
0 70/297 Addressees: See next page'
Subject:
OCONEE UNITS NOS. 1 2, AND 3 The following documents concerning our review of the subject facility are transmitted for your information:
L0 Notice of Receipt of Application.
Draft/Final Environmental Statement, dated D-1 Safety Evaluation, or Supplement No.
, dated ED Notice of Hearing on Application for Construction Permit.
El Notice of Consideration of Issuance of. Facility Operating License.'
Application and Safety Analysis Report, Vol.
Amendment No.
to Application/SAR, dated DJ Construction Permit No. CPPR-dated L
Facility Operating License No. DPR- _
, NPF dated Amendment No.
to CPPR -
or DRR -
, dated Other:
Semiannual Rpt -
Radioactive Effluent Release and Environmental Monitoring covAng the period of 1/1/78 thru 6/30/78 Division of Operatina Reactors, ORB#4 Office of Nuclear Reactor Regulation
Enclosures:
As stated
-.- cc:
ORB#4:DOR OFFICEI------------------------
RIngram:rm.
SURNAME
.9/ 78 DATE p 9_
1/78 NRC-21 (6-76)
- 2 Chief Division of Ecological Services Bureau of Sport Fisheries & Wildlife U. S. Department of the Interior Washington, D. C. 20240 Director National Oceanographic Data Center Environmental Data Service National Oceanic & Atmospheric Administration U. S. Department of Commerce Washington, D. C. 20235 Dr. James T. Tanner National Bureau of Standards Reactor Building 235 Washington, D.C.
20234 Chief, Energy Systems Analyses Branch (AW-459)
Office of Radiation Programs U. S. Environmental Protection Agency Room 645, East Tower 401 M Street, S. W.
Washington, D. C. 20460 U. S. Environmental Protection Agency Region IV Office ATTN:
EIS COORDINATOR 345 Courtland Street, NE Atlanta, Georgia 30308
'DISTRIBUTIOI*.
- Docket FI Ie (3)~~
NRC,:PDR:(3)'
L. PDR (3)"
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- ,Will~iam 0 Pak.. -DEise nhut AT~h Mm Wl~lan 0.Parkr,~r!.TBAbern~thy
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Production
.ftACRS41,6) 0.-. BOX.2178'~-.K~ra 422' South Church. Stret Charlotte,-.North-CarOlina'???-~
Gray.Fii,e Gentlemen:
In -order. to. complete our review
.- yorsubmittai.o Deb~ r,17 inregard to the deletio of~
no-aI1gc~otos the~
Appendix B.Technical S ecif1 tati ono,o the.Q-P_
find that we pieed additional, oa.Jnw.~
IIs re quested.that you preyf ethPi, $rmtin1dnfednje enclosure to. enable us!+ tocomp !tep.Qur.,revle, Kindly, subu,hO signed-originals-and -37 addijtjraL.cois
.7 Sincerely,...
Roer.1 Reid, Chief O perating Reactors Branch: #A.
Enclsur: *
.. Division of-Operating Reactor~;~
Reques for-Additional
- I.~~..
-cc w/enclosure:- See next pagp,,,
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NRC FORM 318 (9-76)
NRQC1 0240,
- U.S.
GOVSRNMENT PRIN4TING OFFICK.
Duke Power Company cc: Mr. William L. Porter Duke Power Company P. 0. Box 2178 422 South Church Street Charlotte, North Carolina 28242 J. Michael McGarry, III, Esquire DeBevoise & Liberman 700 Shoreham Building 806-15th Street, NW.,
Washington, D.C.. 20005 Oconee Public Library 201 South Spring Street Walhalla, South Carolina 29691
ADDITIONAL INFORMATION TO BE INCLUDED IN THE LICENSEE'S ASSESSMENTS SUPPORTING THE TERMINATION OF NON-RADIOLOGICAL SPECIAL STUDIES AND ENVIRONMENTAL SURVEILLANCE PROGRAMS OCONEE STATION
- 1. On an annual basis, compare the fish impingement and entrainment rate to the studies of fishing catch rates for all age classes and important species defined by the Final Environmental Statement (FES) to determine whether the plant is killing an amount of fish comparable to that killed by fishing.
(e.g., see Reference 1)
- 2. Regarding fisheries studies, on page 117 of the FES, it is stated that: "It is clear that to determine ecological significance of condenser effluents, the observed effects must be related to the population density, dynamics, and regeneration times of the aquatic organisms present in the affected areas. Additional information is needed before expanded, detailed assessments of impacts on terrestrial and aquatic biota in and around Keowee Lake and Hartwell Reservoir can be made."
The effects of both condenser effluents and intake effects should be compared to the population density determined in these studies.
- 3. In discussing population dynamics of young-of-the-year fish in a reservoir receiving heated effluent, page 492 of your submittal, you conclude that, "Because changes from the fish populations resulting from heated effluents from the Oconee Nuclear Station are still occurring in the Keowee Reservoir, the total impact of the plant's operation on young fish stocks cannot yet be assessed The decline appears to be due to heated water."
Elaborate on this conclusion and describe whether or not it is premature to draw conclusions as to the impact of operation of the plant.
Reference:
- 1. Mathur, D., Heisey, P. G., Magnusson, N. C., Impingement of Fishes at Peach Bottom Atomic Power Station, Pennsylvania. Trans. Amer.
Fisheries Soc. Vol. 106, No. 3, May 1977.
D S IBUTION:
ITDSTAES OR Reading NUCLEAR REGULATORY COMMISSION Rlngram 6, 1978m WASHINGTON, D.C. 20555 June-6, '1978 Docket No.y1 6 0/287 Addressees:
See next page Subject OCONEE UNITS NOS. L, 2 AND 3 The following documents concerning our review of the subject facility are transmitted for your information:
L Notice of Receipt of Application.
L. -Draft/Final Environmental Statement, dated Safety Evaluation, or Supplement-No.
, dated ElI Notice of Hearing on Application for Construction Permit.
L Notice of Consideration of Issuance-of Facility Operating License.
pplication aid Safety Analysis Report,. Vo.
Amendment No.
to ApplicationSAR, dated Construction Permit No..CPPR-dated',
pertigicerse No DPR-da Amendment No.
to CPR or DRR dated orat endbna Decemer 31ng 1977.
Enclosures:
As stated cc:
oFFCE -
ORB4 RIngrn 75 NR.C.2i (8 7 5),-
Duke Power Company
- 2 Chief Division of Ecological Services Bureau of Sport Fisheries & Wildlife U. S. Department of the Interior Washington, D. C. 20240 Director National Oceanographic Data Center Environmental Data Service National Oceanic & Atmospheric Administration U. S. Department of Commerce Washington, D. C. 20235 Dr. James T. Tanner National Bureau of Standards Reactor Building 235 Washington, D.C.
20234 Chief, Energy Systems Analyses Branch (AW-459)
Office of Radiation Programs U. S. Environmental Protection Agency Rpom 645, East Tower 401 M Street, S. W.
Washington, D. C. 20460 U. S. Environmental Protection Agency Region IV Office ATTN:
EIS COORDINATOR 345 Courtland Street, N.E.
Atlanta, Georgia 30308
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 April 11, 1978 viockets Nos.: 50-269/270/287 To All Power Reactor Licensees Gentlemen:
Enclosed for your information and possible future use is the current NRC guidance on radiological environmental monitoring for nuclear power plants.
10 CFR Parts 20 and 50 require that radiological environmental monitoring programs be established to provide data on measurable levels of radiation and radioactive materials in the site environs. In addition, Appendix I to 10 CFR Part 50 requires that the relationship between quantities of radioactive material released in effluents during normal operation, includ ing anticipated operational occurrences, and resultant radiation doses to individuals from principal pathways of exposure be evaluated.
Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants, was issued for comment in December 1975. The enclosed tech nical position on the radiological portion of environmental monitoring was formulated by an NRC working group which considered the comments received on Regulatory Guide 4.8. This position sets forth guidance for developing an acceptable minimum radiological monitoring program to meet the regula tory requirements of 10 CFR Parts 20 and 50. Local site characteristics need to be examined to determine if pathways not covered by this guide may significantly contribute to an individual's dose and shouldbe included in the sampling program. The acceptability of changes to radiological environ mental monitoring programs at operating reactors will be-evaluated based on this guidance as well as on a review of past operating data.
We are developing technical specifications which incorporate the Appendix I guidance set forth in the enclosed position. These specifications will be implemented on all operating reactors in the future. This position is be ing provided to you at the present time for information only and no action is required on your part. More specific guidance on technical specifications relating to the implementation of Appendix I to 10 CFR 50 will be provided to you in the future.
Karl R. Goller, Assistant Director for Operating Reactors Division of Operating Reactors Office of Nuclear Reactor Regulation
March 1978 Branch Technical Position
Background
Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants, issued for comment in December 1975, is being revised based on comments received. The Radiological Assessment Branch has developed the following Branch Position on the radiological portion of the environ mental monitoring program. The position was formulated by an NRC working group which considered comments received after the issuance of the Regulatory Guide 4.8.
10 CFR Parts 20 and 50 require that radiological environmental monitoring programs be established to provide data on measurable levels of radiation and radioactive materials in the site environs. In addition, Appendix I to 10 CFR Part 50 requires that the relationship between quantities of radio active material released in effluents during normal operation, including anticipated operational occurrences, and resultant radiation doses to in dividuals from principals pathways of exposure be evaluated. These pro grams should be conducted to verify the effectiveness of in-plant measures used for controlling the release of radioactive materials.
Surveillance should be established to identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to provide a basis for modifications in the monitoring programs for evaluating doses to individuals from principal pathways of exposure. NRC Regulatory Guide 4.1, Rev. 1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants,".provides an acceptable basis for the design of programs to monitor levels of radia tion and radioactivity in the station environs.
This position sets forth an example of an acceptable minimum radiological monitoring program.. Local site characteristics must be examined to determine if pathways not covered by this guide may significantly contribute to an individual's dose and should be included in the sampling program.
AN ACCEPTABLE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Program Requirements Environmental samples shall be oilected and analyzed according to Table 1 at locations shown in Figure 1".
Analytical techniques used shall be such that the detection capabilities in Table 2 are achieved.
The results of the radiological environmental monitoring are intended to supplement the results of the radiological effluent monitoring by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measure ments and modeling of the environmental exposure pathways. Thus, the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radio nuclides which lead to the highest potential radiation exposures of indivi duals resulting from the station operation. The initial radiological environ mental monitoring program should be conducted for the first three years of commercial operation (or other period corresponding to a maximum burnup in the initial core cycle).
Following this period, program changes may be proposed based on operational experience.
The specified detection capabilities are state-of-the-art for routine environmental measurements in industrial laboratories. The.LLDs for 1-131 in water, milk and other food products correspond to one-quarter of the Appendix I (10 CFR Part 50) design objective dose-equivalent of 15 mrem/yr for atmospheric releases and 10 mrem/yr for liquid releases to the most sensitive organ and age group. They are based on the assumptions given in Regulatory Guide 1.109, Rev 1.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.
If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the annual report.
The laboratories of the licensee and licensee's contractors which perform analyses shall participate in theEnvironmental Protection Agency's (EPA's)
Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck)
Program or equivalent program. This participation shall include all of the It may be necessary to require special studies on a case-by-case and site specific basis to establish the relationship between quantities of radioactive material released in effluents, the concentrations in environmental media, and the resultant doses for important pathways.
determinations (sample medium-radionuclide combination) that are offered by EPA and that also are included in the monitoring program. The results of analysis of these crosscheck samples shall be included in the annual report.
If the results of a determination in the EPA crosscheck program (or equivalent program) are outside the specified control limits, the laboratory shall investigate the cause of the problem and take steps to correct it. The results of this investigation and corrective action shall be included in the annual report.
The requirement for the participation in the EPA crosscheck program, or similar program, is based on the need for independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
A census shall be conducted annually during the growing season to determine the location of the nearest milk animal and nearest garden greater than 50 sq. meters (500 sq. ft.) producing broad leaf vegetation in each of the 16 meteorological sectors within a distance of 8 km (5 miles).2 For elevated releases as defined in Regulatory Guide 1.111, Rev. 1., the census shall also identify the locations of all milk animals, and gardens greater than 50 sq. meters producing broad leaf vegetation out to a distance of 5 km. (3 miles) for each radial sector.
If it is learned from this census that the milk animals or gardens are pre sent at a location which yields a calculated thyroid dose greater than those previously sampled, or if the census results in changes in the location used in the radioactive effluent technical specifications for dose calculations, a written report shall be submitted to the Director of Operating Reactors, NRR (with a copy to the Director of the NRC Regional Office) within 30 days identifying the new location (distance and direction).. Milk animal or garden locations resulting in higher calculated doses shall be added to the surveillance program as soon as practicable.
The sampling location having the lowest calculated dose may then be dropped from the surveillance program at the end of the grazing or growing season during which the census was conducted. Any location from which milk can no longer be obtained may be dropped from the surveillance program after Broad leaf vegetation sampling may be performed at the site boundary in a sector with the highest D/Q in lieu of the garden census.
notifying the NRC in writing that they are no longer obtainable at that location. The results of the land-use census shall be reported in the annual report.
The census of milk animals and gardens producing broad leaf vegetation is based on the requirement in Appendix I of 10 CFR Part 50 to "Identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to permit modifications in monitoring programs for evaluating doses to individuals from principal pathways of exposure."
The consumption of milk from animals grazing on contaminated pasture and of leafy vegetation con taminated by airborne radioiodine is a major potential source of exposure.
Samples from milk animals are considered a better indicator of radioiodine in the environment than vegetation. If the census reveals milk animals are not present or are unavailable for sampling, then vegetation must be sampled.
The 50 sq. meter garden, considering 20% used for growing broadleaf vege tation (i.e., similar to lettuce and cabbage), and a vegetation yield of 2 kg/m 2, will produce the 26 kg/yr assumed in Regulatory Guide 1.109, Rev 1., for child consumption of leafy vegetation. The option to consider the garden to be broad leaf vegetation at the site boundary in a sector.
with the highest D/Q should be conservative and that location may be used to calculate doses due to radioactive effluent releases in place of the actual locations which would be determined by the census. This option does not apply to plants with elevated releases as defined in Regulatory.
Guide 1.111, Rev. 1.
Reporting Requirement A. Annual Environmental Operating Report, Part B, Radiological.
A report on the radiological environmental surveillance program for the previous calendar year shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) as a separate document by May 1 of each year.
The period of the first report shall begin with the date of initial criticality. The reports shall include a summary (format of Table 3),
interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with operational controls, preoperational studies (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the station operation on the environment.
In the event that some results are not available the report shall be submitted noting the explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supple mentary report.
The reports shall also include the following:
a summary description of the radiological environmental monitoring program including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; the results of land use censuses; and the results of licensee participation in the Environmental Protection Agency's Environmental Radioactivity Laboratory Intercom parisons Studies (Crosscheck) Program.
B. Nonroutine Radiological Environmental Operating Reports "If a confirmed3 measured radionuclide concentration in an environ mental sampling medium averaged over any quarter sampling period exceeds the reporting level given in Table 4, a written report shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) within 30 days from the end of the quarter. If it can be demonstrated that the level is not a result of plant effluents (i.e., by comparison with control station or preoperational data) a report need not be submitted, but shall be discussed in the annual report. When more than one of the radionuclides in Table 4 are detected in the medium, the reporting level shall have been exceeded if:
concentration (1
+
concentration (2)
+
> 1 reporting level (1) reporting level (2)
If radionuclides other than those in Table 4 are detected and are due from plant effluents, a reporting level is exceeded if the potential annual dose to an individual is equal to or greater than the design objective doses of 10 CFR Part 50, Appendix I. This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result.
A confirmatory reanalysis of the original, a duplicate, or a new sample may be desirable, as appropriate. The results of the confirmatory analysis shall be completed at the earliest time consistent with the analysis, but in any case within 30 days.
TABLE 1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and Type and Frequency and/or Sample and Locations Collection Frequency and Analysis AIRBORNE Radioiodine an d Samples from 3 offsite locations (in Radioiodine Cannister:
Particulates different sectors) of the highest analyze weekly for calculated annual average ground-1-131 level D/Q.
1 sample from the vicinity of a Continuous sampler Particulate Sampler:
community having the highest operation with sample Gross beta radio calculated annual average ground-collection weekly or activity folloging level D/Q.
as required by dust filter change, composite loading, whichever is (by loca ion) for gamma more frequente isotopic quarterly 1 sample from a control location 15-30 km (10-20 miles) distant and in the least prevalent wind directiond DIRECT RADIATIONf 2 or more dosimeters or one in-Monthly or quarterly Gamma dose monthly or strument for measuring and record-quarterly ing dose rate continuously to be placed at each of the same loca tions as for air particulates, and at each of three additional offsite locations (different sectors) or highest calculated annual average ground-level X/Q.
TABLE 1 (Continued)
Exposure Pathway Number of Samplesa' Sampling and a
Type and Frequency and/or Sample and Locations Collection Frequency of Analysis WATERBORNE Surfaceg1 sample upstream Composite samplehoyer Gamma isotopic analysis 1 sample downstream one-month period monthly. Composite for tritium analyses quarterly Ground Samples from 1 or 2 sour es only Quarterly Gamma isotopic and if likely to be affected tritium analysis quarterly Drinking 1 sample of each of 1 to 3 of Composite sample 1-131 analysis on each the nearest water supplies which over two-week period composite when the dose could be affected by its if 1-131 anlysis is calculated for the con discharge performed, monthly sumption of the water composite otherwise is greateK than 1 mrem per year.
Composite for Gross p and gamma isotopic analyses monthly. Compo site for tritium analysis quarterly 1 sample from a control location Sediment from 1 sample from downstream area Semiannually Gamma isotopic analyses Shoreline with existing or potential semiannually recreational value INGESTION Milk Samples from milking animals Semimonthly when ani-Gamma isotopic and 1-131 in 3 locations within 5 km mals are on pasture, analysis semimonthly when distant having the highest dose monthly at other times animals are on pasture; potential.
If there are none, monthly at other times, then, 1 sample from milking animals in each of 3 areas between 5 to 8 km distant where doses are calculated to be k greater than 1 mrem per year
TABLE 1 (Continued)
Exposure Pathway Number of Samplesa Sampling and Type and Frequency and/or Sample and Locations Collection Frequencya of Analysis Milk (cont'd) 1 sample from milking animals at a control location (15-30 km distant and in the least prevalent wind direction)
Fish and 1 sample of each commercially and Sample in season, or Gamma isotopic Invertebrates recreationally important species seiannallyif they:are analysis on edib in vicinity of discharge point not seasonal portions 1 sample of same species in areas not influenced by plant discharge Food Products 1 sample of each principal class At time of harvest Gamma isotopic of food products from any area analysis on edible which is irrigated by water in portion.
1-131 which liquid plant wastes have analysis on broad been discharged leaf vegetation 3 samples of broad leaf vegetation Monthly when available grown nearest offsite locations of highest calculated annual average ground-level DIQ if milk sampling is not performed 1 sample of each of the similar Monthly when available vegetation grown15-30 km distant in the least prevalent wind direction if milk sampling is not performed
TABLE 1 (Continued) aThe number, media, frequency and location of sampling may vary from site to site. It is recognized that, at times, it may not be possible or practical to obtain samples of the media of choice at the most desired location or time.
In these instances suitable alternative media and locations may be chosen for the particular pathway in question and submitted for acceptance. Actual locations (distance and direction) from the site shall be provided. Refer to Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants."
bParticulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air or water is greater than ten times the mean of control samples for any medium, gamma isotopic analysis should be performed on the individual samples.
cGamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
The purpose of this sample is to obtain background information. If it is not practical to establish control loca tions in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted.
eCanisters for the collection of radioiodine in air are subject to channeling. These devices should be carefully checked before operation in the field or several should be mounted in series to prevent loss of iodine.
fRegulatory Guide 4.13 provides minimum acceptable performance criteria for thermoluminescence dosimetry (TLD) systems used for environmental monitoring. One or more instruments, such as a pressurized ion chamber, for measur ing and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters.
For the purposes of this table, a thermoluminescent dosimeter may be considered to be one chip, and two or more chips in a packet may be considered as two or more dosimeters.
The "upstream sample" should be taken at a distance beyond significant influence of the discharge. The "down stream" sample should be taken in an area beyond but near the mixing zone. "Upstream" samples in an estuary must be taken far enough upstream to beyond the plant influence.
hGenerally, salt water is not sampled except when the receiving water is utilized for recreational activities.
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).
jGroundwater samples should be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
kThe dose shall be calculated for the maximum organ and age group, using the methodology contained in Regulatory Guide 1.109, Rev. 1., and the actual parameters particular to the site.
1 If harvest occurs more than once a year, sampling should be performed during each discrete harvest. If harvest occurs continuously, sampling should be monthly. Attention should be paid to including samples of tuborous and root food products.
TABLE 1 (Continued)
Note:
In addition to the above guidance for operational monitoring, the following material is supplied for guid ance on preoperational programs.
Preoperational Environmental Surveillance Program A Preoperational Environmental Surveillance Program should be instituted two years prior to the institution of station plant operation.
The purposes of this program are:
- 1. To measure background levels and their variations along the anticipated critical pathways in the area surrounding the station.
- 2. To train personnel
- 3. To evaluate procedures, equipment and techniques The elements (sampling media and type of analysis) of both preoperational and operational programs should be essen tially the same.
The duration of the preoperational program, for specific media, presented in the following table should be followed:
Duration of Preoperational Sampling Program for Specific Media 6 months 1 year 2 years airborne iodine airborne particulates direct radiation iodine in milk (while milk (remaining analyses) fish and invertebrates animals are in pasture) surface water food products groundwater sediment from shoreline drinking water
TABLE 2 Detection Capabilities for Environmental Sample Analysisa Lower Limit of Detection (LLD)b Airborne Particulate Water or Gas Fish Milk Food Products Sediment Anaysis (pCi/1)
(pCi/m)
(pCi/kg,wet)
(pCi/l)
(pCi/kg, wet)
(pCi/kg, dry) c gross beta 2
1 x 102 3H 330 54Mn 15 130 5 9Fe 30 260 58,60Co 15 130 65Zn 30 260 95Zr-Nb 10 131I 0.5d 7 x 10-2 0.8d 25d,e 134,137Cs 15 1 x 10-2 130 15 80 150 140Ba-La 15 15
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.*
CLLD for drinking water.
dLLDs for 131 1 in water, milk and other food products correspond to one quarter of the Appendix I (10 CFR Part 50) design objective dose-equivalent of 15 mrem/year for atmospheric releases and 10 mrem/yr for liquid releases to the most sensitive organ and age group using the asssumptions given in Regulatory Guide 1.109, Rev. 1.
eLLD for leafy vegetables.
- For a more complete discussion of the LLD, and other detection limits, see the following:
(1) HASL Procedures Manual, HASL-300 (revised annually).
(2) Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).
(3) Hartwell, J. K., "Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).
TABLE 2 NOTES aAcceptable detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.
bTable 2 indicates.acceptable detection capabilities for radioactive materials in environmental samples.
These detection capabilities are tabulated in terms of the lower limits of detection (LLDs). The LLD is defined, for purposes of this guide, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely con cluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66 sb LLD =
E V *2.22
- Y exp(-AAt) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) s is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per disintegration)
V is the sample size (in units of mass or volume) 2.22 is the number of disintegrations per minute per picocurie Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide At is the elasped time between sample collection (or end of the sample collection period) and time of counting The value of S used in the calculation of the LLD for a particular measure ment system sh uld be based on the actual observed variance of the back ground counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.
In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background should include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples).
Typical values of E, V, Y and At should be used in the calculation.
TABLE 3 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
Name of Facility Docket No.
Location of Facility Reporting Period (County, State)
Medium or Type and Lower Limit All Indicator Location with Highest Control locat ons Number of Pathway Sampled Total Number of Locationg Annual Mean b
Mean (f)
Nonroutine (Unit of of Analyses Detectiona Mean (f)
Name Mean (f)
Range Reported Measurement)
Performed (LLD)
Range Distance &
Range Measurements Direction Air Particu-3 lates (pCi/m3)
Gross 1 416 0.01 0.08(200/312) Middletown 0.10 (5/52) 0/08 (8/104) 1 (0.05-2.0) 5 miles 3400 (0.08-2.0)
(0.05-1.40) y-Spec. 32 137Cs 0.01 0.05 (4/24)
Smithville 0.08 (2/4)
<LLD 4
(0.03-0.13) 2.5 miles 1600 (0.03-2.0) 131 0.07 0.03 (2/24)
Podunk 0.05 (2/4) 0.02 (2/4) 1 Fish p~(0.01-0.08) 4.0 miles 2700 (0.01-0.08)
Fish pCi/kg (wet weight) y-Spec. 8 137 130
<LLD
<LLD 90 (1/4) 0 134Cs 130
<LLD
<LLD
<LLD 0
60 130 120 (3/4)
River Mile 35 See Column 4
<LLD 0
0Co (90-200) aSee Table 3, note b.
bMean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f) cNote:
The example data are provided for illustrative purposes only.
TABLE 4 REPORTING LEVELS FOR NONROUTINE OPERATING REPORTS Reporting Level (RL)
Broad Leaf Water Airborne Particulate Fish Milk Vegetation Analysis (pCi/1) or Gases (pCi/m 3)
(pCi/Kg,wet)
(pCi/1)
(pCi/Kg, wet)
H-3 3 x 104 Mn-54 1 x 103 3 x 104 Fe-59 4 x 102 1 x 104 Co-58 1 x 103 3 x 104 Co-60 3 x 102 1 x 104 Zn-65 3 x 102 2 x 104 Zr-Nb-95 4 x 102 1-131 2
0.9 3
1 x 102 Cs-134 30 10 1 x 103 60 1 x 103 Cs-137 50 20 2 x 103 70 2 x 103 Ba-La-140 2 x 102 3 x 102
Figure 1 (This figure shall be of a suitable scale to show the distance and direction of each monitoring station. A key shall be provided to indicate what is sampled at each location.)
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