ML20041G077
| ML20041G077 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/03/1982 |
| From: | Snyder B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20041G076 | List: |
| References | |
| NUDOCS 8203190177 | |
| Download: ML20041G077 (20) | |
Text
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GENERAL PUBLIC UTILITIES NUCLEAR CORPORATION DOCKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 20 License No. DPR-13 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Metropolitan Edison Company, Jersey Central Power and Light Company, and Pennsylvania Electric Company (thelicensee),datedOctober 30, 1981 and amended by letter dated December 3,1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will be operated by GPU Nuclear Corporation (established by Amendment and Modification of Order dated 12/30/81 replacing Metropolitan Edison as the operating licensee) in conformity with the License, the Order for Modification of License dated July 20, 1979, the Order of February 11, 1980, as subsequently modified and amended, the application for amendment, the prov1sions of the Act, and the rules and regulations cf the Comission.
C.
There is reasonable assurance (i) that the activities authorized by this amendment will be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and
(
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Operating License Technical Specifications as indicated in the attachment to this license amendment, by changing paragraph 2.C. (2) to Facility Operating License No. DPR-73, to read as follows:
2.C.(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 20, and hereby incorporated in the license.
The licensee shall operate the facility in accordance 8203190177 820303 PDR ADOCK 05000320 P
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, with the Technical Specifications and all Comission Orders, issued subsequent to March 28, 1979.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGL'LATORY COMMISSION Bernard J. Snyd.eF, Program [ Director TMI Program Office Office of Nuclear Reactor Regulation
Attachment:
Revised Technical Specifications Date of Issuance: March 3, 1982 ag e
D
1 4
FACILITY OPERATING LICENSE NO. DPR-73 DOCKET NO. 50-320 Replace the following pages of Appendix "B" Technical Specifications with the enclosed pages as indicated.
The revised pages contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Pages 3.2-1 through 3.2-11 5-6 through 5-12 4
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3.2 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.2.1 MONITORING PROGRAM REQUIREMENTS LIMITING CONDITIONS FOR OPERATION:
The radiological environmental monitoring program shall be conducted and samples shall be collected as specified in Table 3.2-1 from the locations given in the tables and figures in the Offsite Dose Calculation Manual (0DCM) and shall be analyzed pursuant to the requirements of Table 3.2-1 and 3.2-2.
The NRC shall be notified of any intended changes of the environmental sample locations indicated in the ODCM prior to the effective date of such changes.
APPLICABILITY:
At all times.
ACTION:
a.
With the radiological environmental monitoring program not being conducted as specified in Table 3.2-1, prepare and submit to the Commission the annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
b.
With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 3.2-3 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a report purstant to 5.6 of Appendix B.
When more than one of the radio-nuclides in Table 3.2-1 are detected in the sampling medium, this report shall be submitted if:
concentration (1) concentration (2)
+***> 1.0 limit level (1) limit level (2)
When radionuclides other than those in Table 3.2-3 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specification 2.1.1 or 2.1.2 of Appendix B.
This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
c.
With milk or fresh leafy vegetables unavailable from one or more of the sample locations required by Table 3.2-1 in Jieu of any other report required by Specification 5.6 of Appendix B prepare and submit to the Commission within 30 days, a Special Report which identifies the cause of the unavailability of samples and identifies TMI-2 3.2-1
$"I Table 3.2-1.
Radiological environmental monitoring program to Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or sample Sample Locations **
Collection Frequency of Analysis 1.
AIRBORNE Radioiodine and A minimum of 5 locations Continuous operation of Radiciodine canister.
Particulates from Table 1 of the ODCM.
sampler with sample col-Analyze at least once per lection as required by 7 days for I-131.
dust loading but at least once per 7 days.
Particulate sampler.
Analyze for gross beta radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> P'
following filter change.
"?
Perform gamma isotopic analysis on each sample
^3 when gross beta activity is > 10 times the calendar yearly mean of control samples.
Perform gamma isotopic analysis on composite (by location) sample at least once per 92 days.
2.
DIRECT RADIATION A minimum of 38 locations At least once per 92 days.
Gamma dose.
At least from Table 2 of the ODCM -
once per 92 days.
(using either 2 dosimetens or at least 1 instrument.for continuously measuring and recording dose rate at each location).
See footnotes, last page of table.
o
"I Table 3.2-1 (Continued)
~
Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or sample Sample Locations **
Collection Frequency of Analysis 3.
WATERBORNE a.
Surface A minimum of 2 locations Composite
- sample collected Gamma isotopic analysis of from Table 3 of the ODCM over a period of 1 31 days each composite sample.
Tritium analysis of composite sample at least once per 92 days.
b.
Drinking A minimum of 2 locations Composite
- sample collected Gross beta and gamma from Table 3 of the ODCM.
over a period of 1 31 days.
composite sample.
Tritium analysis of composite P'
sample at least once per i'
92 days.
w c.
Sediment from A minimum of 2 locations At least once per 184 days.
Gamma isotopic analysis of Shoreline (1 Control and 1 Indicator) each sample.
from Table 4 of the ODCM.
4.
INGESTION a.
Milk A minimum of 4 locations At least once per 15 days Gamma isotopic and I-131 from Table 5 of the ODCM.
when animals are on pas-analysis of each sample.
ture; at least once per Sr-90 analysis by compo-31 days at other times.
sites for each location shall be conducted at least once per 92 days.
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Table 3.2-1 (Continued)
Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or sample Sample Locations **
Collection Frequency of Analysis 4.
INGESTION (continued) b.
Fish and A minimum of 2 locations One sample in season, or at Gamma isotopic analysis Invertebrates from Table 6 of the ODCM.
least once per 184 days if on edible portions.
not seasonal.
One sample of each of the following species:
1.
Predator (channel cat-fish or Bluegill or Pumkinseed).
w 2.
Prey h>
c.
Food Products A minimum of 4 locations At time of harvest.
One Gamma isotopic analysis from Table 7 of the ODCM sample of each of the fol-on edible portion.
(when available).
lowing classes of food products:
1.
Fruits 2.
Vegetables Indicator Location and At time of harvest.
One I-131 analysis.
Control Location sample of broad leaf vegetation.
. Composite samples shall be collected by collecting an aliquot at intervals not exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
AASample locations are shown on the figure in the ODCM.
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2
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.,.. m,
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Table 3.2-2.
Maximum values for the lower limits of detection (LLD)a,c
^n N
ge? ~ '
r". y j;,
,. Airborne Partica-f.
. Water
-late or gas Fish.
Milk Food Products Sediment
/
. Analysis (pCi/1)
(pCi/m )
(pCi/kg, wet)
(pCi/1)
(pCi/kg, wet)
(pCi/kg, dry) '
s gross beta
,4 1 x 10 2 3H 200D' i.
^
54Mn 15'
- 130 59Fe.
30 260 58:6 Co 15 130
~ +
ssZn 30 260 95Zr 30 u
'i 90Sr 8
- m..
O sNb"..
15 us.
s.
~b 1311 -
1 7 x 10 2 1
60 134Cs 15 5 x 10 2 130 15 60 150 137Cs 18 6 x 10 2 150 14
-80 180 I40Ba 60 60 140La 15.
15 O
l
=
e'
/
0
s
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TABLE 3.2-2 (Continued)
TABLE NOTATION a.
The LLD is the smallest concentration of radioactive material in a sample that will be' detected with 95%
probability with 5% probability of falsely concluding that a blank
+
observation represents' a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66 Sb LLD = E x v x 2.22 x 106 x Y x exp (-Aat)
Where:
LLD is the "a priori" lower limit of detection as defined above (as l
microcurie per uni mass or volume),
Sb 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 transformativo),'
V is the sample size (in units of mass or volume),
l i
2.22 x 108 is the number of tran: formations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
The value of Sb used in the calculation of LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.
Typical values of E, V, Y, and at shall be used in the calculation.
b.
LLD for drinking water.
c.
Other peaks which are measured and identifiable, together with the radioactivity in Table 3.2-2, shall be identified and reported.
THI-2 3.2-6 s
7 Table 3.2-3.
Reporting levels for radioactivity concentrations in environmental samples m
Reporting Levels Analysis Water Airborne Particulate Fish Milk Food Product (pCi/1) or Gases (pCi/m )
(pCi/kg, wet)
(pCi/1)
(pCi/kg, wet) a H-3
.2 x 104(a)
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
}
'Sr-90 8
w Zr-Nb-95 4 x 102
- m i
O I-131 2
0.9 3
1 x 102 Cs-134 30 10 1 x 103 60 1 x 103 i
f Cs-137 50 20 2 x 103 70 2 x 103 l
Ba-La-140 2 x 102 3 x 102 i
(a)For drinking water samples.
This is 40 CFR Part 141 value.
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1 b
RADIOLOGICAL ENVIRONMENTAL MONITORING MONITORING PROGRAM REQUIREMENTS LIMITING CONDITIONS FOR OPERATION 3.2.1 (Continued) locations for obtaining replacement samples.
The locations from which samples were unavailable may then be deleted from those required by Table 3.2-1, provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations.
BASES:
The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation.
This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measureable concentrations cr radioactive
. materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposura pathways.
The initially specified monitoring program will be effective for at least the first three years of commercial operation.
Following this period, program changes may be initiated based on operational experience.
C TMI-2 3.2-8
RADIOLOGICAL ENVIRONMENTAL MONITORING LAND USE CENSUS LIMITING CONDITIONS FOR OPERATION 3.2.2 LAND USE CENSUS A land use census shall be conducted at least once per 12 months during the grazing season (June 1 to October 1) to determine the location of the nearest milk animal in each of the 16 meteorological sectors within a distance of 5 miles.
Broad leaf vegetation sampling at the site boundary or closest landsite location in a sector with the nighest annual average 0/Q shall be conducted during the harvest season.
APPLICABILITY:
At all times.
ACTION:
a.
With land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 2.1.1 or 2.1.2 of Appendix B, in lieu of any other report required by Specification 5.6 of Appendix B, prepare and submit to the Commission within 30 days, a Special Report which identifies the new locations.
b.
With a land use census identifying a location which yieids-a calculated dose or dose commitment (via the same exposure pathway) greater than at a location from which samples are currently being obtained in accordance with Specification 5.6 of Appendix B, prepare and submit to the Commission within 30 days, a Special Report which identifies the new locations.
The new location shall be added to the radiological environmental monitoring program within 30 days.
The sampling location, excluding the control staion location, having C
the lowest calculated dose or dose commitments (via the same exposure pathway) may be deleted frcm this monitoring program after October 31 of the year in which this land use census was conducted.
BASIS:
This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census.
The best survey information from the door-to-door or aerial surveys or consulting with local agricultural authorities shall be used.
This census satisfies the require-ments of Section IV.B.3 of Appendix I to 10 CFR Part 50.
Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be-identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 TMI-2 3.2-9
l-RADIOLOGICAL ENVIRONMENTAL MONITORING l
LAND USE CENSUS LIMITING CONDITIONS FOR OPERATION 3.2.2 (Continued) for consumption by a child.
To determine this minimum garden size, the following assumptions were used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and
- 2) a vegetation yield of 2 kg/souare meter.
e 4,
b ag TMI-2 3.2-10
RADIOLOGICAL ENVIRONMENTAL FONITORING INTERLABORATORY COMPARIS0N PROGRAM LIMITING CONDITIONS FOR OPERATION 3.2.3 INTERLABORATORY COMPARISON PROGRAM Analysis shall be performed on radioactive materials supplies as part of an Interlaboratory Comparison Program which has been approved by NRC.
APPLICABILITY:
At all times.
ACTION:
With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
BASIS:
The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
C TMI-2 3.2-11
I with Subsection 5.7.2.
These reports shall describe the changes made, the reasons for making the changes, an evaluation of the environmental impact of these changes, and the statement required under the provisions of Subsection 5.5.5.
5.5.5 Consistency with Initially Approved Programs Any modifications or changes of the initially approved program descriptions developed in accordance with Subsection 5.5.1 shall be governed by the need to maintain consistency with previously used procedures so that direct comparisons of data are technically valid.
Such modifications or changes shall be justified and supported by adequate comparative sampling programs or studies demonstrating the comparability of results or which provide a basis for making adjustments that would permit direct comparisons.
These demonstrations of comparability shall be submitted to the NRC in accordance with the provisions of Subsections 5.5.4 and 5.6.1.
5.5.6 NRC Authority to Require Revisions The NRC may require modifications or revisions in the program description document developed in accordance with Subsection 5.5.1 or require modification or revisions of changes made by the licensee in accordance wth Subsection 5.5.4, as a result of NRC reviews of the results of these programs, if such modifica-tions or revisions are judged necessary to maintain consistency wittf the initially approved programs or with the intent of these ETS.
The NRC may also require modifications or revisions of procedures and programs as a r changes in station operation or changes in envir,onmental conditions,esult of or concerns associated with station operation.
5.6 Station Reporting Requirements 5.6.1 Routine Reports A.(1)
Annual Environmental Operating Report Part A Nonradiological A report on the environmental monitoring programs for the previous calendar year shall be submitted to the NRC as a separate document by May 1 of each year.
The period of the first report shall begin with the date of initial criticality subsequent to issuance of the operating license.
The report shall include summaries, analyses, interpretations, and statistical evaluation of the results of the environmental monitoring required by the nonradiological environmental monitoring activities (Section 3), and the special studies and requirements (Section 4) for the report period, including a comparison with preoperational studies, operational controls (as appropriate) and previous environmental monitoring reports, and an assessment of the observed impacts of the station operation on.the environment.
If harmful effects or evidence of irreversibl damage are suggested by the monitoring or special programs, the licensee shall provide a 5-6
more detailed analysis of the data and a proposed course of action to alleviate the problem.
The Annual Report shall also include a summary of:
1)
All ETS noncompliances and the corrective artions taken to remedy them.
2)
Changes made to state and federal permits and certification.
3)
Changes made to the Environmental Program Description Document.
4)
Changes in station design which could involve an environmental impact or change the findings of the FSFES.
5)
All nonroutine reports submitted per ETS Section 4.6.
6)
Changes in ETS.
A.(2)
Annual Environmental Operating Repr't 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 bach year.
The period of the first report shall begin with the date of initial criticality.
The report shall include a summary of T-ab.le.,5.6-1, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, as deemed appropriate by the licensee, 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.
(
The report shall also include the following:
a summary description of the radiological environmental monitoring program including sampling methods for each sample type, size and physical character-i 'ics 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 the site; the results of land use censuses; and the results of licensee participa-tion in the Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck)
Program.
In the event that some results are not available the report 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.
5-7
B.
Data Reporting Formats Results of analysis of all nonradiological environmental data collected shall be summarized and tabulated on an annual basis.
In the event that some results are not available by May 1, the report shall be submitted noting and explaining the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
C.
Quarterly Radiological Releases and Estimated Dose Report The following information shall be submitted to the Director of the Regional Office.
This information shall be submitted on a calendar quarter basis (January-March, April-June, July-September, and October-December) and shall be submitted no later than 60 days following the end of each calendar quarter.
(1) Estimates of the amounts and types of radioactivity that were released to the environment during the quarter and during the calendar year.
This shall include estimates of the total activity of each nuclide and time rate of release of each nuclide.
(2) Estimates of populations and maximum individual doses which occurred during the calendar quarter and during the calendar year shall be provided.
The estimates shall be based on actual hydrological and meteorological conditions which occurred during the releases.
Calculational methods shall be~those of U.S. NRC Regulatory Guides 1.109 (Revision 1, October 1977),
1.111 (Revision 1, July 1977), 1.112 (Revision 0-R, April 1976) and 1.113 (Revision 1, April 1977).
These calculations shall be based on estimates of actual population distributions during the releases and shall take into consideration factors such as boating or fishing recreation, c
5.6.2 Nonroutine Reports A report shall be submitted in the event that a " Limiting Condition for Operation" (Section 2), if applicable, is exceeded, a report level as specified in Section 3, " Environmental Monitoring," is reached or if an " Exceptional Occurrence" as specified in Section 4.6 occurs.
Reports shall be submitted under one of the report schedules described below.
5.6.2.a Prompt Report These events specified as prompt report occurrences shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, telegraph, or facsimile transmission to the NRC followed by a written report to the NRC within 30 days.
l l
l 5-8
5.6.2.b Thirty Day Event Nonroutine events not requiring a prompt report as described in Subsection 5.6.2.a, shall be reported to the NRC either within 30 days of their occurrence or within the time limit specified by the reporting requirement of the corresponding certification or permit issued pursuant to Sections 401 or 402 of PL 92-500, whichever time duration following the nonroutine event shall result in the earlier submittal.
5.6.2.c Content of Nonroutine Reports Written 30-day reports and, to the extent possible, the preliminary telephone, telegraph, or facsimile reports shall (a) describe, analyze, and evaluate the occurrence, including extent and magnitude of the impact, (b) describe the cause of the occurrence, and (c) indicate the corrective action (including any significant changes made in procedures) taken to preclude repetition of the occurrence and to prevent similar occurrences involving similar components or systems.
5.6.2.d Nonroutine Radiological Environmental Operating Reports "If a confirmed 1 measured radionuclide concentration in an environmental sampling medium averaged over any quarter sampling period exceeds the reporting level given in Table 3.2-2, 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.(e g., by t
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 3.2-2 are detected in the medium, the reporting level shall have been exceeded if:
concentration (1) concentration (2) reporting level (1). reporting level (2),**, y b
If radionuclides other than those in Table 3.2-2 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 l
Part 50, Appendix I.
This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous results.
IA confirmatory reanalysis ce 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.
5-9
5.7 Changes in Environmental Technical Specifications and Permits 5.7.1 Change in Environmental Technical Specifications Request for changes in environmental technical specifications shall be submitted to the NRC for review and authorization per 10 CFR 50.90.
The request shall include an evaluation of the environmental impact of the proposed change and a supporting justification.
Implementation of such requested changes in ETS shall not commence prior to incorporation by the NRC of the new specifications in the license.
5.7.2 Changes in Permits and Certifications Changes or addition to required Federal, State, local, and regional authority permits and certificates for the protection of the environment that pertain to the requirements of these ETS shall be reported to the NRC within 30 days.
In the event that the licensee initiates or becomes aware of a request for changes to any of the water quality requirements, limits or values stipulated in any certification or permit issued pursuant to Sections 401 and 402 of PL 92-500 which is also the subject of an ETS reporting requirement, NRC shall be notified concurrently with the authorizing agency.
The notification to the NRC shall include an evaluation of the environmental impact of the revised requirement, limit or value being sought.
If, during NRC's review of the proposed change, it is determined that a potentially severe environmental impact could r3sult from the change, the NRC will consult with the authorizing agency to determine the apprapriate action to be taken.
~
5.8 Records Retention Records and logs relative to the following areas shall be made and retained throughout the term of the operating license.
These records and logs shall be made available to NRC on request.
e a.
Records and drawing changes dtta ding station and unit design changes made to systems and equipment wnich could potentially affect the environment.
b.
Records of all data from environmental monitoring, surveillance and study activities required by these environmental technical specifications.
5-10
Table 5.6-1.
Environmental radiological monitoring program annual summary format example Name of Facility Docket No.
Location of Facility Reporting Period (County, State) l Medium or Pathway Type & Total Lower Indicator Control Number of Location Nonroutine Location Location with Highest Annual Mean Sampled Number of Limit of Mean(f)g Reported Mean(f)g a
Name Name (f)"
(Unit of Analyses Detection Measurement)
Performed (LLD)
Range Distance & Direction Range Range Measurements Air Particulates (pCi/m)
Gross B416 0.003 0.008 Middletown 0.10(5/52) 0/08 (8/104) 1 (200/312)
(0.05-2.0) 5 miles NNW (0.08-2.0)
(0.05-1.40) m
,L I-Spec. 32 ea 137C0 0.003 0.05 (4/24)
Smithville 0.08 (2/4)
<LLD 4
(0.03-(0.13) 2.5 miles 0.03-(0.13) 140Ba 0.003 0.03 (2/24)
Podunk 0.05 (2/4) 0.02 (2/4) 1 (0.02-0.08) 4.0 miles (0.01-0.08)
<LLD 0
895r 40 0.002
<LLD
<LLD 0
90Sr 40 0.0003
<LLD Fish pCi/kg (net weight) 1-Spec. 8 137Ca 80
<LLD
<LLD 90 (1/4) 0 134Ca 80
<LLD
<LLD
<LLD 0
60Co-80 120 (3/4)
River Mile 35 See Column 4 <LLD 0
r (90-200)
Podunk River aSee Table 3.2-2, note b.
bMean and range based upon all measurements with LLD treated Fraction of detectable measurements at specified as positive value.
locations is indicated in parentheses. (f) cNote:
the example data are provided for illustrative purposes only.
o