ML19308E078
| ML19308E078 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/07/1974 |
| From: | Graf J US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19308E076 | List: |
| References | |
| NUDOCS 8003200807 | |
| Download: ML19308E078 (5) | |
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v 2.1.4 Uses of Adjacent Lands and Waters The Crystal River Plant is located in a predominantly rural area.
Less than 1000 persons live within 5 miles of the plant.
The largest city within 50 miles is Ocala, with a population of 22,583. Major land use in the vicinity of the site is for agriculture. According to the 1969 Census of Agriculture about 30% of the land in Citrus County is in farms, a 2% decrease from the 1964 Census.
These statistics also show that the number of milk cows in the county increased from 100 in 1964 to 131 in 1969, and that the commercially important products of Citrus County are fruits (peaches) and cattle (beef).
The applicant reports that more than 90% of the area in the vicinity of the plant is devoted to agriculture.
The closest dairy herd is located approximately 21 miles ESE of the plant.
The nearest location where milk cows are actually present is 2.3 miles NE.
Major water uses in the vicinity of the plant re for fishing, both sport and commercial, and recreation. All consumab'e water within 20 miles is supglied by wells or springs.
The applicant has estimated that 1.4x100 lb of fish and 3x100 lb of shellfish (mostly crabs) are harvested from the Gulf by Citrus county fishernen.
Based on the details presented by the applicant in the FSAR and ER, information gained on the site visit, and that gleaned from the 1969 Census of Agriculture we conclude that sufficient information is available to permit an adecuate independent dnalysis of exposure pathways by the staff.
11.6 Offsite Radiolecical Monitoring Proaram The applicant has undertaken a radiological environmental monitoring program the purpose of which is to measure and evaluate the significance of contributions to the existing environmental radicactivity levels frcm plant operations.
Estimates of potential exposure to the population will be made from the data collected.
The program is excected to demonstrate the effectiveness of plant control over radioactive waste disposal operations and of compliance with Federal and State regulations for the disposal of these materials. The scope the program is conparable to that of other nuclear facilities currently in operation or being licensed, and is in accordance with the recomendations of regulatory guide 4.1 and of the Environmental Protection Agar.cy as set forth in " Environmental Radioactivity Surveirllance Guide" - ORP/S 10 72-2.
Details of the program will be finalized in the review and approval of the Environmental Technical Specifications.
Preoperational measurements were becun in Sectember 1970 and thus will provide more than three years of pre-startup data to serve as a baseline for evaluating the impact of the plant.
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The program was subjected to-Staff review which,through rounds of questions,
' positions ~.and resubmittals has resulted in a ~ number of modifications..
- Sampling.of air iodine, milk, and pasture grass was 'added to.the program.
Analysis of-seawater and bottom sediments for Sr-89, 90 has also been included.. Gross radioactivity analysis has been replaced by specific-radtonuclide analysis for most samples in order to further specify the
- contribution of the plant to = observed environmental radioactivity.
We conclude that the applicant's program as will be finalized in the Environmental Technical Specifications will be adequate for monitoring the radiological impact of plant operation on the environs and for verifying predictions of concentrations of specific radionuclides in the environment
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based on effluent measurements.
The program is-considered adequate to
. monitor the control of radioactivity with regard to the health and safety _
aspects of the release of radionuclides to the environment from the proposed operation of the plant.
12.0 Radiation Protection This section presents an evaluation of the adequacy of the shielding, ventilation and health physics program to control radiation excosures
.within 10 CFR Parts 20 and 50 of the Comission reculations.
Because facility design w : cc:cnticily ccmpleta, emph& sis in Um review was placed on plans and procedures for radiation exposure reduction.
12.1 Shieldino F
The radiation shielding provided has been designed based on a criterion that during normal plant operation the radiation dose to operatina cersonnel and to.the general public is within the limits set forth in.10 CFR 20.
Standard methods and racognized computer ccdes (SDC, QAD) were used by the applicant to evaluate the shield design. Staff calculations at selected locations (using SCC) indicate that the shielding provided.will be adequate to meet designated radiation zone requirements.
Information provided in the FSAR as well as observations made during the
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site. visit show that the general principle -of shielding compartmentalization for major components which are expected to contain radioactivity-has been employed. ~In general enough rocm has been provided to allow for maintenance and temporary shielding if necessary.
The solid radioactive waste packaging system has been designed to minimi::e the radiation excosure of personnel performing the-packaging operations.
Piping of radioactive process systems is-not " field-run" but is routed by the architect-engineer.
The applicant estimates the total exposure of on-site personnel.to be about 220 man-rem per year based on the operating experience of similar facilities. ' The utility has estimated (site visit) that in addition approximately 75 man-rem would accrue to contractor personnel during a projected annual six week outage.
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We conclude that adequate consideration has been given to shielding design to keep exposures within applicable limits and to reduce unnecessary exposures during normal operation of the plant. - During startup of the plant, and when full power operation is attained, the plant will be mapped for dose. levels'and these will be compared with anticipated levels.
12.f.4 Area Monitoring Area radiation monitors will be provided at 19 locations in the Unit. The locations have been selected to aid in detemining the radiation levels throughout the plant.
The initial alam set points for high radiation alarms are based on the radiation zone requirements for each location.
These may be adjusted based on radiation surveys made during actual operation.
Low level alam set ooints will be established above the normal operating plant backpround to provide an alert in the event of a change of the normal plant operating conditions.
The coverage provided by this monitoring system along with the regular surveys of plant radiation levels planned by the applicant is considered adequate.
12.2 Ventilation The (suilding veni.ilai.iun system has been cesigneo to cont 1nuously supoly e fresh air flow from the nomally occupied areas of the building, through rocms containing radicactive wasts squipment to the ventilation exhaust discharge system.
The capacity of tne exhaust system is hicher than that of the fresh air supply system so that the air pressure inside the building is slightly below the cutside.
All tanks and processing ecuicment which may evolve radioactive gases are vented to the waste gas vent header system to prevent radioactive gases f"cm escaping to the building atmosphere.
The spent fuel pit ventilatic system design provides a continuous sweep of air across the top of the spei c fuel pits and cash loading pit.
Based on the description of the ventilation system in the FSAR, the monitoring of airborne contamination, and the planned orocedures for inhalation exposure control we conclude that the ventilation system will be adequate.
2.2.4 Airborne Radioactivity Monitorina Eleven fixed systems monitor airborne activity in vents and in rooms where airborne contamination might be anticipated.
Also tuo menitors rounted on movable carts will be used to mcnitor operations in the radioachemical laboratory-and in handling spent fuel. The applicant has made a verbal agreement to provide 8 portable air samplers.
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We. conclude thatisufficient equipment will be provided to adequately ~
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12.3 Health Physics-Prooram The health physics-program is the responsibility of.the' Chemical'and '
e Radiation Protection-Department. ;It is plant policy to~ keep radiation -
exposure to personnel ~as low as possible-~and~to adhere-to pertinent-2 regulations. This-department is responsible for the orientation and
_ training of personnel in radiation protection principles and. procedures L
to maintain. exposures-as low as: practicable.
p Personnel protection will be accomplished through administrative controls and procm'ures, through the use~of protactive equipment and-verified 3
through an extensive personnel monitoring.procram. Administrative:-exoosure limits and the use of Radiation Work Permits {RNP) enable the Chemistry and Radiation Protection Engineer to ensure compliance with 10 CFR 20.'
The issuance?of a RWP allows for prejob surveillance and specification of'
- protective measures such as protective equipment and radiation monitoring.
4 Special protective equipment includes a full array of protective clothing, t
temporary shielding, respirators and self-contained breathing apparatus.
- Personnel decontamination facilitis av Aso provided.
The f!~c: of traffic 2-to the Radiation Controlled Area frca the sccendary side is through?the Health Physics area where moniters and change rooms are available.
All plant employees aill wear TLD dosimeters and neutron sensitive: film 3
' badges.
Pocket chambers or special TLD bad
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working in relatively high radiation areas.'ges will be issued to personnel Nhole body counts will be made on plant employees routinely and in special cases as needed.
5 Bioassays for tritium will be performed on an as needed basis.
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. the ' applicant has made a ve^al commitment to provide 2 air oarticulate and iodine monitors and at least 6 TLD badges in the conventional units.-
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Based on the above information contained in the FSAR cnd the applicant's-Radiation Control Procedures, and that obtained from the applicant in i
response to'AEC questions we conclude that the applicant plans to implement a health physics program of sufficient scope to' maintain.in-plant exposures,
of personnel within applicable limits.
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References
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- 1. : Crystal River Unit 3 Nuclear Final Safety Analysis Report 2.
Crystal River Unit 3. Applicant's Environmental Report
- 3.. Final Environmental Statement Related to the Proposed Crystal River Unit 3.
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1969 Census of Agriculture U.S. Department of Comr:erce. Social-and Economic Statistics Administration Bureau of the Census 5.
Radiological Control Procedure RP-1601 Florida Power Corporation Crystal River Unit 3.
Radiation Protection Manual' 6.
SDC, A Shielding-Design Calculation Code for Fuel-Handling Facilities, ORNL-3041 e
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