ML19317H166
| ML19317H166 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/18/1975 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19317H162 | List: |
| References | |
| NUDOCS 8004210635 | |
| Download: ML19317H166 (28) | |
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UN!TED STATES t
NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555 ARKANSAS POWER AND LIGHT COMPANY DOCKET N0. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE 9
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Amendment No. 3 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Arkansas Power & Light Company (the licensee) dated January 17,1975, April 11,1975, two dated April 17,1975 and July 11, 1975, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Conmission's rules and regulations set forth in 10 CFR Ch Q ter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; and 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.
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.c.(2) of Facility License No. DPR-51 is hereby amended to read as follows:
"(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised, are hereby incorporated in the license.
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1 The licensee shall operate 'the facility in accordance with the Technical Specifications as revised by issued changes thereto through Change No. 5."
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COPHISSION Dennis L. Ziemann, hief Operating Reactors Branch 2 Division of Reactor Licensing
Attachment:
Change No. 3 to Technical Specifications Date of Issuance: SEP 181975 e
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 3 TO FACILITY OPERATING LICENSE N0. DPR-51 bHANGENO.3TOTECHNICALSPECIFICATIONS ARKANSAS POWER NND LIGHT COMPANY ARKANSAS NUCLEAR ONE, UNIT 1 DOCKET N0. 50-313 I
Revise Appendix B as follows:
Remove pages i, ii, iii, iv, 2-1, 2-2, 2-3, 2-4, 2-9, 2-10, 2-17, 2-18, 2-19, 2-20, 4-7, 4-8, 4-11, 4-12, 4-13, 4-14, 4-15, 4-16, 4-17,'4-18, 4-27, 4-28, 4-29, 4-30, 5-3, 5-4, 5-5 and 5-6; and insert the attached revised pages (no changes made on pages ii, iv, 2-9, 2-20, 4-7, 4-14, 4-16, 4-17, 4-27, 4-30, 5-6). Add pages 4-12a, 4-15a, 6-3 and 6-4.
The changed areas on the revised pages are shown by marginal lines.
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Effective January 19, 1975, activities under the U. S. Atomic Energy Commission regulatory program were assumed by the U. S.
=
Nuclear Regulatory Comission in accordance with the Energy 3
Reorganization Act of 1974.
Any references to the Atomic
, Energy Commission (AEC) contained herein should be interpreteu I
as Nuclear Regulatory Comission (NRC).
TABLE OF CONTENTS Pg 1.0 DEFINITIONS............................................... 1-1 1.1 Standard Methods........... -
1-1
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1.2 Gamma Isotopic Analysis...........................
1-1 1.3 Environmental Samples................................ 1-1 1.4 Chlorine Demand...................................... 1-1
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1.5 Free Available Chlorine Residual......................
1-1 1.6 Combined Available Chlorine Residual................*.
'l-1 1.7 Total Available Chlorine Residua 1.....................
1-1
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1.8 RID...................................................
1-1 1.9 Radiation Monitor checks, Tests, and Calibration...
1-2 1.10 Equivalent Decay Time..................................
1-2 2.0 LIMITING CONDITIONS FOR OPERATION..........................
2-1 2.1 Therma 1...............................................
2-1 2.1.1 Mavimum AT Across Condenser....................
2-1 2.1.2 Mavim m Dis charge Temperature.............
u 2-2 2.1.3 Mav b - BTU /hr............................
2 -3 2.1.4 Rate of Change of Discharge Temperature........
2-3 2.1.5 Heat Treatment of Circulating Water S 2-4 2.1.6 Deicing, 0perations..................ys tem.....
.......... 2-4 2.2 Hydraulic.............................................
2-5 2.2.1 Intake veloc1ty................................
Discharge velocity.............................
2-5 2.2.2 2-5
~2.2.3 Flow Rate Restrictions...............
2.2.4* Raservoir Drawdown...................
2-5 i
2-5 2.3 Chemica1..............................................
2-5 2.3.1 Biocides.......................................
2-5 2.3.2 Corrosion Inhibitors...........................
2-6 2.3.3 Suspended and Total Dissolve y
pH..........................d So11ds...........
2-7 2.3.4 1
2-8 2.3.5 Chemicals which Affect Water Quality...........
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2.4 Radioactive Dis charge.................................
2-9 2.4.1 Liquid Discharge...............................
2-10 2.4.2 Gaseous Discharge..............................
2-12
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s iii TABLE OF CONTENTS (Cont'd)
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__ age 5.5 Procedures.....
5-3 5.5.1 Defailed Written Procedures...........
5-3 5.5.2 Operating Procedures
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5-3 5.5.3 Temporary changes.....
5-3 5.6 Plant Reporting Requirements.
5-3 5.6.1 Routine Reports.....
5-3 5.6.2 Non-Routine Reports..
5-4 5.6.3 Changes.
5-5
- 5.7' Records Retention 5-6 5.7.1 Records and Logs Retained for Life of the Plant.
5-6 5.7.2 All Other Records..
5-6 6.0 SPECIAL SURVZILLANCE, RESEARCH, OR STUDY ACTIVITIES.....
6-1 6.1 Thermal Plume Mapping 6-1 6.2 Fish Spawning Characteristics of Dardanelle Reservoir 6-2 6.3 Diel changes in Impingement Levels.
6-3 6.4 Cove Rotenone Surveys 6-4 O
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,i 2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Thermal 2.1.1 Maximum AT Across Condenser Ob_iective To limit thermal stress to the aquatic ecosystem by limiting the
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AT across the condenser during operation.
Specification:
The==vinum differential temperature across the condenser shall a.
not exceed 15*F during normal operatica with all four circulating water pumps in operation.
b.
If one or two circulating water pumps are out of service'at any given time the==v4=m condenser AT shall not exceed 30*F; and Specification 2.1.2 of this Appendix shall be met.
Monitoring Requirement The temperature differential across the condenser shall be monitored r
every hour utilizing the computer output of the condenser inlet and the circulating water discharge flume temperature measurements.
The l3:
range of these measurements shall be 0-150*F and their accuracy shall be +0.5%.
If the plant computer is inoperable, the condenser AT shall be' monitored at least once each shift when the plant is operating at steady state power levels.
The condenser AT shall be measured within two (2) hours after a change in power level has been stabilized and at least once 3 *3 each shift thereafter.
The condenser AT shall be determined using measurements at the condenser inlet and in the discharge canal.
4 Bases Maximum AT's of 15'F with 4 circulating water pumps operating (*1700 cfs flow) and -30*F with 2 circulating water pumps operating will insure that the limits of the applicable water quality criteria will not be exceeded.
The difference in temperature readings of the RTD's at the inlet of the condensers and at the circulating water discharge fiume l3 provides the AT across the condensers.
Specification 2.1.1.b allows maintenance to be performed on circulating water pumps when the Dardanelle Reservoir ambient temperature is such that Specification 2.1.2 will not be exceeded.
Hydraulic model studies have shown that a 30*F AT at 850 cfs circulating waterflow will not i
result in adverse changes in the Dardanelle Reservoir isotherms when I
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5 2-2 compared to the isotherms resulting from a 15*F AT at 1700 cfs except on the surface of the discharge embayment.
2.1.2 M ximum Dischargo. Temperature a
Objective To limit thermal stress to the aquatic ecosystem by limiting the plant's maximum discharge water temperature.
Specification The condenser discharge water temperature shall not exceed 105'F for more than two consecutive hours.
If the water temperature exceeds 105*F for two hours an investigation of the situation
'will be undertaken and corrective action shall be taken to main-tain the discharge water temperature at 105*F or less.
One such corrective action would be a reduction in the plant power level
' 'unless there is an emergency need for the lost power.
This emergency need would exist when a reduction in power would mean cutting off firm customers.
If conitoring (sea below) indicates that the temperature at the mouth of the discharge embayment is ;$ 105*F, the plant load will not be reduced.
Monitoring Requirements Condenser discharoe water temnerature shall be monitored every hour utilizing the average of the computer output of the circulating water discharge flume RTD readings.
The RTD's have a 0-150*F range and an 3
accuracy of +0.5%.
If the plant computer is inoperable, the condenser discharge temperature shall be measured at least once each shift.
If the condenser inlet temperature exceeds 85 F with all four circulating water pumps running or 70 F with less than four circulating water pumps running, the 3
circulating water discharge flume temperature shall be monitored every two (2) hours.
If the circulating water discharge flume temperature exceeds 105 F, plant personnel will be dispatched to the mouth of the discharge embayment to monitor the exit temperature from the embayment.
Monitoring 3
of the embayment will continue every two hours as long as the condenser outlet temperature remains at 105*F.
Bases The 105*F maximum discharge water temperature limit ic set to assure that the Dardanelle Reservoir temperature does not exceed 95*F as I
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2-3 established by the applicable water quality criteria. The use
'of the circulating water discharge flume RTD's provides the circulatina water discharge temperature prior to mixina with
/the Dardanelle Reservoir water.
No credit was taken in the analyses and models of the circulating water system for heat exchange within the discharge embayment even though it is expected that the water temperature will be re-duced in the embayment.
Thus, the average temperature should be
<105 F even when the temperature at the circulating water discharge flume is greater.
2.1.3 Maw== BTU /hr Not applicable.
2.1.4 Rate of Change of Discharge Temperature Obiective To avoid thermal stress to the aquatic ecosystem due to sudden changes in water temperature.
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-Specification In the event of a planned shutdown during the period November
,through April, the reactor power level shall be reduced to 0% at a rate such that the decrease in the circulating water discharge l3 flume temperature shall be <5%F/hr in order to avoid any adverse i
thennal impact on the aquatic environment in the discharge embayment. As the reduction in power level is made, the number of operating circulating water pumps will be reduced so as to limit the rate of decrease of the water temperature in the discharge embayment.
This limitation may be exceeded for brief periods as necessary to prctect plant equipment and for certain safeguard operations which cannot be limited or negated by plant operation. These safeguard operations include automatic plant trips and compliance with safety-related technical specifications.
If after a few planned shutdowns at tne 19ecified rate, there are no detectable adverse effects on the discharge embayment environment, then future planned shutdowns may be conducted at slightly higher rat 2s.
The required monitoring shall be 9
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N 2-4 conducted until it is established that there is no adverse environmental impact associated with plant shutdowns conducted at the higher rate.
If there is adverse environmental impact detected, then future planned shutdowns will be conducted at slightly slower rates,until a shutdown rate where there is no detectable adverse environmental impact is determined.
Monitoring Requirement ~
Circulating water discharge flume temperature will be monitored every hour during the power reduction utilizing the average of the computer output of the circulating wi.ter discharge fiume RTD readings.
The 3
' RTDfs have a 0-150*F range and an accuracy of +0.5%.
If the plant computer is inoperable, the circulating water discharge 3
fiume temperature shall be monitored at least once per hour during the power reduction utilizing the condenser temperature recorder which has a 0-150*F range and a _+0e5% accuracy.
The aquatic environment of the discharge embayment will be watched
-during and immediately after planned shutdowns in order to detect any adverse environmental impacts on the embayment, which might i.
A record of the observations made, rate of temperature occur.
change, and appropriate data shall be maintained.
Bases There has been no incidence of adverse environmental impact associated with any operating AP&L power plant.
There is also a lack of data or evidence which would support a limiting rate of change of temperature for the specific species that might inhabit the discharge embayment.
In view of this, a conservative rate of change,_<5*/hr, is specified.
It is also conservative because the actual rate of change of the discharge embayment will be slower than the rate of change of the circulating water system.
A reduction in circulating water flow will further decrease the rate of change of temperature in the discharge embayment.
2.1.5 Heat Treatment of Circulating Water System
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2.1.6 _ Deicing Operations Not Applicable.
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2-10 b.
Averaged over a yearly interval, the ' release rate of I-131 and other particulate' radioisotopes with half lives longer than eight days discharged from the plant should result in a dose in the unrestricted area of less than 15 mrem to the thyroid of a child through the grass-cow-eflic chain.
2.4.1 Liquid Discharge Specification 1.
The rate of release of radioactive materials in liquid waste from the plant shall be controlled such that the instantaneo.us concentrations of radioactivity in liquid waste, uport releasef.,
from the Restricted Area, do not exceed the values listed in 10 CFR 20, Appendix B, Table II, Column ~2.
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2.
If the cumulative release of radioactive materials in liquid a
effluents, excluding tritium and dissolved gases, over a l3 calendar quarter, exceeds 2.5 curies, the Licensee shall:
Maite an investigation to identify the causes for such.
a.
release rates; i
b.
Define and initiate a program of action to reduce such.
release rates to the design levels; and,
' c.
Notify the Director, Directorate of Licensing within 3C days, identifying the causes and describing the proposed program of action to reduce such release rates.
- 3. - The release rate of radioactive liquid effluents, excluding tritium and dissolved gases, shall not exceed 10 curies during any calendar quarter.
4.
During release of liquid radioactive vaste, the following con-ditions shall be met:
a.
At least two (2) condenser circulating veter pumps shall be in operation to provide a minimum dilution flow of approximately 383,000 gpm in.the discharge canal for the-liquid waste effluent; b.
The effluent control monitor shall be set to alarm and auto-natically close the waste discharge valve such that the re-l quirements of Specification 2.4.1 are met; and, i
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- ~i TABLE 2-2 MINIMUM SAMPLING FREQUENCY
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Sensitivity of Waste I
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Item Check Frequency
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Analysis in Lab (3)~
Gansna Nuclides
- 1. ' Filtered Waste Monitor a.
Gasna isotopic analysis a.
Prior to release a.
5 x 10-7 pCi/m1 Tank, Treated Waste
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Monitor Tank, and Laundry Drain Tank
-8 b.
Radiochemical b.
Sr-89
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5 x 10 pCi/ml l3, Analysis Sr 89, 90 Sr-90 Quarterly, l
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c.
Diessolved Noble Cases c.
Monthly c.
Dissolved Gases I
105 pCi/mi d.
Tritium d.
Monthly Pr rtional d.
105 pCi/mi Composite n
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Monthly Proportional,
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10~7 pCi/mi U
l Gross Alpha Activ'ity e.
composite 4
1 f.
Ba-La-140 I-131 f.
Weekly Pro rtional f.
106 pCi/m%
l Composite (
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- 2. Weste Gas Decay Tank a.
Gamma Isotopic Analysis a.
Prior to release of
'a. 104 pCi/cc each batch j
b.
Deleted b.
. Deleted b.
Deleted l3 l
c.
Tritium c.
Prior to release of c.
106 pCi/cc l
each batch
-12 1-131(1) a.
Weekly a.
10 pci/cc
- 3. Unit Vent Sampling a.
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I-133, I-135 b.
Monthly b.
10 Ci/cc,
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TABLE 2-2 (Cont'd)
MINIMUM SAMPLING FREQUENCY Sensitivity of Waste Item check Frequency Analysis in Lab (3)
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Unit Vent Sampling c.
Particulates (Cont'd) a I
- 1) Delete'd
- 1) Deleted
- 1) Deleted l3 '
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- 2) Groas Alpha
- 2) Quarterly on Weekly
- 2) 10 11 pCi/cc Ii Activity Esmple j
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Gamma Isotopic 3)
Biweekly Composite p) 10 pCi/cc 3
Analysis Y'
- 4) Radiochemicil 4)
Quarterly Composite 4) 10~11 pCi/cc Analysis Sr 89,'90 5)
Ba-La-140. I-131
- 5) Weekly
'5) 10 10 pCi/cc' d.
Cases 3
- 1) DELETED 1)
DELETED i
- 1) DELETED
- pCi/cc-3 2)
Tritium 2)
Monthly 2) 106 Reactor Building Purge s., Gamma Isotopic -
a.
Each~ Purge a.
10~4 pCi/cc Analysis b.
Deleted' l3 b.
Deleted b.-
Deleted c.
Tritium c.
Each Purge c.
106 pCi/cc 10-4 pCi/cc 5
Condenser Vacuum Pump a.
Gama Isotopic Analysis a.
Monthly a.
3; j
b' Tritium b.
Monthly b.
10-6 pCi/cc i
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TABLE 2-2 (Cont'd)
MINIMUM SAMPLING FRE0VENCY (1) When activity level exceeds 10 percent of the limits of Specification 2.4.2.3.b. the sampling frequency shall be increased to a minimum of once each day.
When the gross activity release rate exceeds one percent of maximum release rate specified in Specification 2.4.2.3.a and the 3
average gross activity release rate increases by 50 percent over the previous day, an analysis
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shall be performed for iodines and oarticulates.
(2) A proportional sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant.
(3) The detectability limits for activity analysis are based on the technical feasibility and on the potential significance in the environment of the quantities released.
For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the n,,
i, stated limits, they should also be reported.
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(4) For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations.
Under these circumstances, it will be more appropriate to calculate the concentration of such radionuclides-using observed ratios with those radio-nuclides which are measurable.
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- operati,onal monitoring program described herein. The opera-tional monitoring shall begin with the operation of Unit 1 and
- shall continue for five years after Unit 2 goes into operation.
The. effects of plant operation shall be determined by comparison of ecological parameters studied in the preoperational program.
Survey Plan A map of the survey area showing sampling locations is pre-sented in Figure 4-3.
The type and frequency of field sampling shall be as presented in Table 4-3.
Specification (a): Biological Surveys
- 1) Plankton Plankton samples shall be obtained by use of the Wisconsin plankton net.
These samples shall be analyzed for plankton (fauna, periphyton, filimentous algae) count and these counts will indicare numbers of organisms per liter of water sample as determined by the strip count method.
2)
Benthic Organisms
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The bottom organisms shall be obtained by the use of the Ekman dredge.
The number of specimens of each group will be listed by sampling areas.
Counts shall be made for the number of organisms per one-fourth square foot.
A.alysis of the plankton and benthic organisms will pro-vide important information regarding the food chain.
3)
Fish Survey a) Gill Net Survey A fish population and fish species count shall be taken with sizes noted, through the use of gill and trammel nets'.
A minimum of 16 net-nights' sampling will be accomplished each quarter. At each sampling point two (2) sets 3
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of 2 net-nights' sampling will be obtained within 30 days on a quarterly basis.
Spines, scale samples, and length / weight frequencies shall be
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obtained for representatives of each species.
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4-11 Frequencies of sampling were chosen to obtain a trend of aquatic.
life in the area.
Most fish surveys are set up to be conducted in the summer because the fish are more plentiful at this time of year.
It is felt that more frequent sampling of the organisms would produce repetitive data.
However, less frequent sampling might yield erratic data from which no trend could be detected.
The data will be evaluated in relation to preoperational data obtained by AP&L, UALR, Ark. Tech., and various governmental agencies.
By comparing preoperational data with postoperational data, changes in the environment can be detected.
It is felt that in this way effects on the aquatic life by ANO can be monitored and controlled.
(2)
Impingement of Organisms Objective The objective is to monitor those fish impinged on the' intake screens 1
to pennit an assessment of impingement impacts.
Potential impacts of concern are effects on the fishery resource and dissolved oxygen i
resource of Lake Dardanelle.
If' these impacts are significant, appropriate state and federal agencies responsible for fisheries shall be consulted, and the necessary modifications to the intake system shall be implemented to satisfactorily reduce these impacts.
Specification Fish trapped on all of the intake screens shall be sluiced to a collection basket where they shall be identified, counted and weighed following a twenty-four (24) hour sampling period twice each week during the period April 1 through September 30 and three times each week during the period October 1 through March 31.
If the weight of fi'sh and trash impinged during any given 24-hour sampling period exceeds 150 pounds, two replicate subsamples of 75 pounds each shall be taken and their averages used for extrapolation and deter-3 mination species data for the total weight and number of each species impinged.
Length and weight of each fish in a subsample shall be detennined for each species collected up to 25 fish per specie.
If the number of fish in a subsample for a particular species is greater than 25, 25 fish plus 1% of N-25 (where N is the number of fish for a particular species in the subsample) shall have their length and weight measured.
Total biomass of all fish impinged shall be estimated regardless of the number impinged.
Tabulations of this data shall be made.
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4-12 Fish shall be disposed of in a manner consistent w'ith U. S. Environmental Protection Agency, Arkansas Department of Pollution Control and Ecology and Arkansas Game and Fish Commission guidelines.
Reporting Requirement Monthly results from'this study shall be submitted to the NRC, Division of Reactor Licensing, no later than 30 days after the end of the reporting month.
The reports shall contain the following information:
the date of the sample, the species collected, the number or estimated number impinged in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for each species, the modal length (in mm) for each species, the maximum length (in m..) for each species, the modal weight (in g) for each species, and the number of pumps operating during each sample collection.
A summary of the impingement results shall be included in the report required by Specification 5.6.1.
Bases The purpose of this program is to permit accomplishment of the specifi-cation objective.
Surveillance frequency is based on previous surveil-
-lance data at Arkansas Nuclear One indicating large impingements during the period October through March.
Subsampling is done to reduce the 3
sampling effort and replicates are taken to reduce subsampling error.
Length and weight determinations are made to detennine impingement selectivity.
(3) Entrainment of Ichthyoplankton Objective The objective of the entrainment study is to determine the effects of operation of the Circulating Water System on the ichthyoplankton.
Specification A sampling program shall be implemented to determine estimated numbers of ichthyoplankton passing through the circulating water system.
Intake samples shall be taken in the intake canal; discharge samples shall be taken from the discharge canal.
Samples from the same water mass shall be obtained from the intake and discharge by coordinating their collection with circulating water passage time.
Physio-chemical parameters to be monitored at sampling shall include water temperature, dissolved oxygen
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and pH.
Ichthyoplankton shall be sampled monthly during the months of hprfl through septem'ber.
samrile's shall be taken at eight-hour intervals over 24-hour periods..
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4-12a jThe samples shall be taken at surface, mid-depth, and near bottom at the jintake and at mid-depth at the discharge by a metered plankton net. As an alternative, a high capacity pump sampler shall be used to take samples at surface, mid-depth, and near bottom.
.t Specimens collected shall be identified to the lowest possible taxonomic level and densities shall be calculated.
Inmediate mortality shall be determined for intake and discharge samples based on the following criteria:
LIVE: ~~ Swimming vigoro~usly, no apparent orientation problems, behavior 3
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normal.
STUNNED:
Swimming erratically, struggling and swimming on side, some twitching but motile.
DEAD:
No vital life signs, no body or operc"lar movements, no response to gentle probing.
Reporting Requirement Report levels shall be develeped from the data collected at the conclusion of the first year study. A summary of the entrainment study shall be included in the report required by Specification 5.6.1.
Bases s
This study and subsequent analysis of the results will aid in determining the effect on the ichthyoplankton of passage through the Circulating Water System.
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_s 4-13 (b) Terrestrial.
Not applicable.
(c) Aerial Not applicable.
4.2 Radiological Environmental Monitoring Objective:
To provide information on the radiological effects of station operation on the environment.
Specification:
An environmental radiological monitoring program shall be carried out as defined in Tables 4-1 and 4-2 at locations defined in Figure 4-1 and Table 4-2 4.2".1 ir Sampling Continuous air sampling shall be performed at four locations onsite, two off-site within a ten-mile. radius of the Plant, and'one reference
. location. Locations have been selected near site boundaries and in existing populated areas for evaluation of possible exposure to airborne particulate and halide radioactivity resulting from station operation. The collection devices for iodine shall contain potassium iodide impregnated charcoal or equivalent, and shall be constructed j
and operated so as to retain quantitatively the iodine in the air passing through the device. Appropriate analyses of particulate filters and halide collection devices shall be performed on all samples in accordance with accepted techniques and nuclides of interest.
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4.2.2 Direct Radiation Ambient levels of direct external radiation shall be measured at the same locations as air particulate. Measurements shall be made by exposing thermoluminescent dosimeters for periods of three months and six months.
3
- 4.2.3 Precipitation Sampling Precipitation sampling shall be carried out at four locations; two ousite, one within a ten-mile radius, and one reference location approximately twenty miles southwest of the plant.
Analyses shall be l
performed as given in Table 4-1.
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4-15 4.2.10 Milk Sampling Samples of milk shall be collected within a 10-mile radius of
.the plant, The milk sampling program shall include:
(a) one (1) sample from the location of the offsite dairy farm or. individual milk animal with the highest expected X/Q, (b) one (1) sample from existing milking animals in each of 3
three (3) areas where infant thyroid doses are calculated to be greater than 1 mrem per year.
The infant thyroid dose shall be evaluated in the manner of Regulatory Guide 1.42.
(c) one (1) sample monthly from milking animals at a control location (10-20 miles distant and in the least prevalent wind direction).
Samples shall be analyzed for Iodine-131, Strontium-89-90, and gama emitting isotopes.
The sampling frequency for locations nearer than three (3) miles shall be every two weeks during the 3
season animals are on pasture and the locations nearer than 1.5 miles shall be sampled weekly during the season animals are on pasture.
Each sample shall be analyzed for I-131 as in Table 4-1, and monthly composites shall be analyzed for radiostrontium and gama emitters.
The analytical procedure used to detennine the radiciodine concentration will have a sensitivity of 0.5 picocuries per liter, the overall error (one sigma confidence level) of the analysis will be within 135%.
Results will be reported, with associated calculated error, as picocuries of I-131 per liter of milk at the time of sampling.
The area within ten (10) miles of the plant shall be surveyed semiannually for the locations of animals (cows, goats) producing milk for human consumption.
The results of this survey shall be included in the Operating Report required by Specification 3
s 5.6.1.
If it is learned from this survey that milk animals are present at a location which yields a calculated infant thyroid dose greater than from previously _ sampled animals, the new location shall be added to the milk sampling program as soon as practicable.
The sampling location having the
. lowest calculated dose may then be dropped from the sampling program at the end of the grazing season during which the survey was conducted. Also, any location from which milk can no longer be obtained may be dropped from the program after notifying the NRC in writing that milk animals are no longer present at that location.
i en i
l 4-15a If milk animals are present in a location where milk cannot be 3
obtained, a sample of the nearest grass shall be analyzed for
~ the isotopes stated above.
4 4.2.11 Vegetation Sampling i
Grass and the leafy portions of other natural vegetation available at each of the air sampling stations shall be collected three times per year (spring, summer, and fall).
Food crops and pasturage in the vicinity of the plant also shall be collected as available at harvest time. Appropriate analyses of all samples shall be per-formed in accordance with accepted techniques and nuclides of interest as given in Table 4-1.
4.2.12 Soil Sampling Soil samples shall be collected semi-annually at the same locations i
as vegetation samples and analyzed for gross alpha and gross beta and gamma emitting isotopes as described in Table 4-1.
The Fall sample also shall be analyzed for Strontium 89-90.
. Bases One of the limiting conditions for operation of Arkansas. Nuclear
- One is restricting environmental effects due to plant operation in unrestricted areas surrounding the plant site to within limits i
specified in AEC Regulations 10 CFR - Parts E0, 50, and 100.
This
. Radiological Monitoring Program includes measurements made on the air, water, and land environments to insure that these limits are i
observed.
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, TABLE 4-2
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SAMPLE LOCATION AND SCHEDULE Sample Direction and Sample Station
,Stetien #
Distance from Plant Location Sample Types Sample Frequency Remarks c-i 16 295 * - 6.0 miles Piney Creek Area
- 1) Lake Water
- 1) Honthly
- 2) Bottom Sediment 2) Semi-annually s
- 3) Aquatic Biota
- 3) Semi-annually
)-
i 17 Note 1
- 1) Milk
- 1) Honthly'
- 2) Spring, Summer, Fall 3l-l
- 2) Pasturag2
- 2) 3 times / year 18 Note 1
- 1) Milk
- 1) Honthly
- 2) Pasturage
- 2) 3 times / year
- 2) Spring, Summer, Fall 3 19 99* - 5.0 miles
.Akansas-Tech.
- 1) Milk
- 1) Honthly i
Herd
- 2) Pasturage
- 2) 3 times / year'
- 2) Spring, Summer, Fall Es 2
l l
Note 1:
These sample _ stations wi.11 be detennined as 'per Specification 4.2.10 and will be reportid
- in the Operating Report as per Specification 5.6.1.
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TABLE 4-3
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AQUATIC SAMPLING LOCATION AND FREQUENCIES Sample Type Sauple Frequency Sample Station #
1,2,3,5,10,11,l3 Plankton Quarterly - January, April 14, 15, 16, 21 i
July, October Benthic Organisms Quarterly - January, April 1,2,3,5,10,11,l3 July, October 14, 15, 16, 21,
Gill Net Survey 2 se.ts?lof 2 net-nights in Areas A, B, C, D l3l each area,.within 30 days of each quarter a
l Two samples in each area Trawling Survey every other week Areas A, B,'C, D l3 March, April, May, June Trap Net Survey 5 cons.ecutive. days. _ _ _ _.
Areas A, B, D Spring and Fall 3 ;
Cove Rotenone Survey September Areas A, C l3 Two samples in each area Shoreline Seine every other week
. Areas A C,
3
. Survey March, April, May, June Fish Cage Survey Semi-Annually Ar&as A, B, C, D 3
(Mussels)
ChemicaI Honthly 3, 5, 7, 8, 10, 11, 3
13, 14, 15, 16, 17, 21 1
Physical Monthly 3, 5, 7, 8, 10, 11, 3'
13, 14, 15, 16, 17, 21 en e
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. 5-3 5 4,3 A report for eadh occurrence shall be prepared as specified in Section 5.6.2.
i i
5.i Procedures j
i.,5,1 Detailed written procedures shall be prepared and followed for all activities involved in carrying out the environmental technical specifications.
Procedures shall include sampling, instrument calibration, analysis, and, actions to be taken when limits are approached or exceeded.
Testing frequency of any alarms shall be included.
These frequencies shall be l
determined from experience with similar instruments in similar environments and from manuf acturers ' technical manuals.
5.5.2 In addition to dhe procedures specified in Section 5.5.1, the plant standard operating procedures shall include provisions to ensure the plant and all its systems and components are operated in compliance with the limiting conditions for operations established as part of the environmental technical specifications.
5.5.3 Temporary changes to procedures in 5.5.1 above, which do not change the intent of the original procedure may be made, pro-vided such changes are approved by two members of the. plant -
staff, at least one of whom shall be a Shift Supervisor.
Such
~
changes shall be documented.
5.6 Plant Reporting Reauirements 5.6.1 Routine Reports A report on environmental surveillance progr$ms for the previous nix months operations shall be submitted as part of the Semiannual Operating Report within 60 days af ter January 1 and July 1 of each year.
The period of the first report shall begin with the date of initial criticality.
The report shall be a summary of the results of the environmental activities for the 6 month period and an assessment of the observed impacts of the plant operation on the environment.
l The report shall include a su= mary of the quantities of radio-active effluents released from the plant as outlined in USAIC Regulatoqr Guide 1.21, with data summarized on a monthly basis following the format of Appendix A thereof. A summary of the iodine analyses performed on primary coolant as required by 3
Appendix A of these Technical' Specifications shall also be in-cluded.
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n If statistically significant variations of off, site environmental radionuclide concentrations with time are observed, a comparison of these results with effluent releases shall be provided.
Individual samples which shcw' higher than normal icvels (25% above background for exter' al dose, or twice background for radionuclide n
content) shall be noted in the reports.
Results from all radiological samples taken shall be summarized on a quarterly basis following the format of Table 5-1 for inclusion in the ceniannual report.
In the event that some results are not' available within the 60 day period-, the report should be submitted.
l noting and explaining the reasons for~ the missing results.
The missing data shall be submitted as soon as possible in a*supplemen-tary report.
3.6.2 Non-Routine Reports s.
Radioactive Discharge The reporting requirements for radioactive discharges are specified in Section 2.4 of the Technical Specification.
b.
Radiological Environmental Monitorine (1) In the event that a report level specified belev is reached, a report shall be made within the designated time period to the Director of Regulstory Operations, Region'II, with a copy to the Deputy Director for Reactor Projects.
Jf a i measured level of radioactivity in " critical pathway env1ronmental medium semples" indicates that the resultant annual dose to an individual fromi these levels could equal or exceed 4 times the design objective, a plan shall be
~
submitted v1 thin tenidays advising the AEC of the proposed 3
action to ensure the plant related annual doses will be within the design objective.
For example, with an I-131 design objective of 15 mrem /yr to the thyroid of any
. ; f'
..-.o individual, if individual charcoal filters show I-131 concentrations in air of 4 x 10-12 uC1/cm3 3
(4 pei/m ) or greater (2 x 10-14 pC1/m3 if the milk pathway is involved),
or if individual milk samples shew I-131 concentrations of 10 pCi/l or greater, the results shall be reported along with a proposed plan of action, as discussed above.
For purposes of calculating doses the"models presented
'in WASH-1258 issued in July 1973 and Regulatory Guide 1.42 '
shall be used.
- Critical pathway is defined by 514 of ICRP Publication 7.
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5-5' (2) If samples of critical pa'thway environmental media collected over a calendar quarter show total levels of radioactivity that could result in accumulated plant related domas to an individual for that quarter of 1/2 the annual design objective, the results shall be reported and a plan submitted and implemented within 30 days to limit conditions so that the annual dose to an individual will not exceed the design objective.
c.
donradiological 2
In the event a limiting condition for operation is exceeded, or a report level specified in Section 4, Environmental Surveillance is reached, or an unusual event involving a significant environmental impact occurs, a report shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph to the Director of the Regional Regulatory Operations Office, followed by a written report within ten days to the 3
Director of the Regional Regulatory Operations Office (cc to Director of Licensing).
The written report and to the extent possible, the preliminary telephone and telegraph report, 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.
5.6.3 Channes When a change to the plant design, to-the plant operation, or a.
to the procedures described in Section 5.5 is planned which would have a significant adverse effect on the environment or which involves an environmental matter or question not pre-viously reviewed and evaluated by the AEC, a report on the change shall be made to the AEC prior to implementation.
The report shall include a description and evaluation of the change including a supporting benefit-cost analysis.
b.
Changes or additions to permits and ce'rtificates requi I
by Federal, State, local and regional authorities for the protection of the environment shall be reported.
When the required changes are submitted to the concerned agency for approval, they shall' also be submitted to the Deputy Director for Reactor Projects, Directorate e
.~
n 6-3 6.3 Diel Changes In Impingement Levels Objective:
To provide information necessary for quantifying the extent of fluctuations in impingement levels within a 24-hour period.
Program Specification:
Beginning October 1 and continuing to April 1,1976, sub-divisions of a daily impingement sample (See Specification 4.1.2.a.(2)) into three eight hour subsamples shall be performed twice per month during regular impingement mon-3 itoring.
The results of this study shall be analyzed to identify the extent of fluctuations in impingement levels within a 24-hour period.
The data required by Specification 4.1.2.a.(2) shall be collected for each subdivision of the daily sample.
Reporting Requirements:
An interpretive report shall be submitted to NRC by June 1,1976.
Bases The'information provided by this study will indicate whether modifications, if any, to current operating procedures will reduce impingement levels.
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6-4 6.4 Cove Rotenone Surveys Objective To aid in providing a larger base with which to index variations from year to year of fish populations in Lake Dardanelle.
Specification In addition to those cove'rotenone surveys required by Envirohmental Technical Specification 4.1.2.a(1) three additional cove rotenone surveys shall be donc in the summer of 1975 and again in the fall of 1975, one in each of three areas other than those specified in Environmental Technical Specification 4.1.2.a(1).
The additional 3
cove rotenone surveys shall be conducted under the supervision of the Arkansas Game and Fish Commission personnel.
t Reporting Requirements The results of these surveys shall be reported as part of the report required by Specification 5.6.1 for the period August 1975 through December 1975.
Bases It is felt that the cove rotenone surveys required by Environmental Technical Specification 4.1.2.a(1) need to be augmented by additional cove rotenone surveys to aid in establishing the base referred to in the objective above.
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