ML19319C755
| ML19319C755 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/01/1972 |
| From: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| To: | FLORIDA POWER CORP. |
| Shared Package | |
| ML19319C754 | List: |
| References | |
| NUDOCS 8003030866 | |
| Download: ML19319C755 (1) | |
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_s ATOMIC ENERGY COMMISSION DOCKET NO. 50-302 FLORIDA POWER CORPORATION ORDER EXTENDING PROVISIONAL CONSTRUCTION PERMIT COMPLETION DATE By application dated May 30, 1972, Florida Power Corporation requested an f
extension of the latest date specified in Provisional Construction Permit No. CPPR-51. The permit authorizes the construction of a pressurized water nuclear reactor designated as the Crystal River Unit 3 Nuclear Generating Plant at the applicant's site on the Gulf of Mexico, about seven and one-half miles northwest of the town of Crystal River, Citrus County, Florida.
Good cause having been shown for this extension pursuant to Section 185 of the Atomic Energy Act of 1954, as amendmed, and Section 50.55(b) of 10 CFR Part 50 of the Commission's regulations, IT IS HEREBY ORDERED THAT the latest completion date specified in Provisional Construction Permit No. CPPR-51 is extended from June 1, 1972 to September 30, 1974.
FOR THE ATOMIC ENERGY COMMISSION 0
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A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Date of Issuance:
June 1, 1972
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QUALITY PROGRAM RESPONSIBILITIES F.0erca P,eett Co#PO48 698e q ua6 ti, PReseed at,evtist s
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RESPONSIBLE ORGANIZATION FUNCTION I
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fuel arrives on site the annual premitum is expected to be g,'
$211,000. When the plant becomes opcrational the annual premitna is expected to be $808 600 e
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Mec6erships_ (Cont'd) 8.
Mr. W. A. Sze11stowski IEEE Nuclear Science Group g
Power Engineering Society Subcomittee II of J.C.N.P.S.
(developing qualification standards for -
Nuclear Plant equipment and systems) 9.
Mr. J. C. Hobbs, Jr.
ANSI N45-NSS1, Design, Qualifications Testing and Installation Requirements for Pump Operability, Task Force No. 2 - Punp Seals 10.
Mr. D. W. Pedrick, IV Southeastern Electric Exchange Quality Assurance Comnittee 11.
Mr. W. H. Cox, A-erican Chemical Society State Health Physics Society Power Reactor Chemists Group
- 12. "r. J. L. Curtis Institute of Nuclear Materials Management D
13.
Vr. G. R. Westafer Arerican Nuclear Society
- 14. Mr. P. F. McKee A'tS-21, PWR Design Standard Comittee (alternate center) 15.
Mr. D. W. West Florida Chapter of the Health Physics Society Legislation, Regulations, and Governmental Agency Committee Puer Reactor Health Physics Group
- 16. Mr. J. A. Hancock A.nerican Nuclear Society A'iS (National)
A'4S (Florida Section), Chairrran Atomic Industrial Forus O
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.eerican Nuclear Society (National) a-erican Nuclear Society (Florida Section, Program Chairr an)
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Topic e.3 Crystal River Unit 3
Subject:
Price-Anderson snd Related Insurance 1.
Price-Anderson, enacted in 1957 and extended and amended in 1965 and 1966 provides funds for public liability in the event of a nuclear incident up to a total amount of $560 million.
This figure represents the sum of the amount of Government indemnity fixed at $500 million by the Congress, and the then-existing (1957) maximum available private liability insurance, $60 million.
The amount of private insurance has gradually risen, so that it stands now (June, 1974 ) at $110 million; the Government's indemnity has commensurately decreased to $450 million.
Other features included in the Act by the amendments of 1966 are no-fault liability and provisions for accelerated payment of claims immediately upon occurrence of a nuclear incident.
The indemnity agreement extends for the life of the license (40 years for Crystal River 3).
The Price-Anderson Act is incorporated in the Atomic gy Energy Act in Sections 2, 11, 53, and 170.
The House on July 10th passed the extension (by a vote of 360-43) of a bill to extend Price-Anderson to August 1,1987.
The'AEC fee for Price-Anderson is $30/mwt.
Crystal River is rated at 2,452 mwt and accordingly, the current and AEC fee would be $73,560.
(This fee is additional to all other fees required by AEC regulations.)
There can he no increase in the mwt rating because of limitations of the steam generating equipment.
2.
NELIA - MAELU Sindicate Insurance is available up to $110,000,000.
When the plant is in full operation the annual insurance syndicate insurance cost is estimated to be
$298,000.
NELIA - MAELU has estimated the insurance cost for the time nuclear fuel is stored at the plant site to total some $4,000.
3.
NEPIA - MAERP provides property. damage insurance for both builder's risk and the operational period.
When the NELIA and NEPIA are merging into NELPIA but the insurance arrangements remain the same.
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Le 50 mile radius area is laracly open with very 1 w densitics, except for naral concentrations. We present population of the 50 mile radius area is estimated to be 155,900 persons. Le largest city in the area is Ocala with a population of O
22,583. G2innville, located 55 miles from the site, has a populatica of 63,818, while Tx.pa. 75 miles south, has a population of 277,767 persons.
For the pu 7,cses of 10 CFR 100 accidents dose calculations and considerations, 5 niles is tued :u the low popalation r.one (1.PZ) distance. I!cwever, the distance 1,ased cn actual population density is 41 niles. His is done with the intent of added safety.
T1.c projected year 2015 pcpulatica of the 50 uile radius is approximatcly 359,000 rcrsons. Bis increase in population can be expected as a result of:
e Xortherly expansion of Tampa-St. Potcrsburg netropolitan area along U.S. 19, o Growth of the Gainesville area, e Area of infitence of Disney World, aral e Inproved employrvat corditions initiated by the
- mer plant constriction.
Q Le only mjor u&in develo;rcnt which is expected to occur will be along lii3J.way 19 a s it p use< throurji the fringe of the 5. nile rudius area wid to a degrec along the Cry 2 tal idver.
Nithin 50 uilea, u;banir.ation occurs in two pattems:
lj Ae strip of residential, business and tourist develo;nnt extending northward along liighway 19 frua Cle:.rwater and New Port Richey, and
- 2) Urban concentration of sti:all resort and residential c:crunities such as Crystal River, llorosassa, Inverness, lirecksville, Ccala, etc.
Ccatinued develognent of the !!irJreay 19 strip is anticipated. Poth Citata and Pasco Cct:at les' r.trter pimis are incitding expansion of IlirJreay 19 teses. Inland co:nunitics are expceted to increase but not as quickly as Gulf-oriented areas.
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l Ibferences:
- 1) Crystal 1 iver Unit 3 @plicants I:swironnental heport, Operating, l.ieense Stage, Sectica 111.
- 2) Crystal !!iver Unit 3 Nuclear Final Safety Analysis 1:cport, Section 2.
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Memberships (Cont'd) 18 Mr. E. C. Simpson American Nuclear Society (Florida Section)
O xemser ^a5 Stendards Co-ittee 2.8 Worxina aroug 19 Mr. J. R. Duren American Societ'y of Civil Engineers Utilities Nuclear Coatings Working Comittee
- 20. Mr. A. L. Gomez IEEE - Industrial Group Applications
- 21. Mr. E. M. Good Instrument Society of America ISA - Power Industrial Division Executive Committee (National)
ISA - POWID - Standards Connittee (hational)
ISA - Tampa Chapter 22.
Mr. D. A. Shook IEEE - Sequential Event Recording Working Gruuo O
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CRYSTAL RIVER 3 ARKANSAS 1 RANCHO SECO OCONEE I OCONEE II Dil-1 PLANT 2,772 2,568 for other 2,535 2,452 2,568 Kdt-Core (Cuar) 963 data ese 880 871 855 886 Oconee I KJe 2.57 2.62 2".62 2.62 2.44 2.10 Enrich. Avg.
204,820 205,286 207,486 205,286 205,286 205,267 2 (1b) 92.5 95.0 UO 92.5 92.5 93.5 92.5 68E 0 23 C Fuel Density 2 3'I C 23 4 4
DC 68E2i4 68AL 0 ;B C 68E 02f4 23 4 None Burn. Poison 112%
Rods 1121 112%
112%
112%
112%
Des. Overpower 6.25 5.77 5.74 5.77 5.69 5.51 KW/FT (Avg) 19.5 18.0 17.9 18.0 17.8 17.2 KW/FT (Max) 4,900 4,800 4,700 4,600 4,400 4,800 100% Power Fuel Temp (Max) 1.33 1.45 1.48 1.45 1.46 1.61 Min. DNBR 4
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TOPIC
.4 CRYSTAL RIVER UNIT 3
SUBJECT:
Coolina Systems Nuclear Services Coolina Water Systest (NSCVS)_
The NSCWS is comprised of a -mclear services seawater system (MSSS) and a nuclear services closed cycle cooling water system (NSCCCWS).
The system provides cooling water to safety related components necessary for safe reactor shutdown during normal and emergency operating conditions. The heat removed from the sdfaty related components by this system leaves the plant by way of the seawater discharge canal. The entire system has been designed to Seismic Class I.
Nuclear Services Sesvater System (NSSS)
The seawater system uses four 50 percent capacity heat exchangers h
to ensure continuous heat removal from the closed cycle system during all operating conditions. One normal and two emergency 100 percent capacity, motor driven ptasps for this system are located in the intake structure and appropriate valving has been provided to enable any pump to furnish seawater to the system. Motor operated valves provide the isolation capabilities so that the pumps and the heat exchangers connected to the system are capable of being isolated on an individual basic.
When offsite power is lost under any operating or accident condition, the seawater pumps will be powered by the emergency diesel generators.
Only one of the emergency seawater pumps is required to supply the minimum essential cooling requirements.
Nuclear Service closed Cycle Coolina Water System (NSCCCUS).
The nuclear service closed cycle cooling water system including pumps, heat exchangers and associated equipment have been designed to Seio-nic Class I requirements.
Th'.s system performs as an intermediate heat sink for all essential components non-essential components or systens normally cooled by this system are automatically isolated O
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ecia e aitie sr i i c teso T 1 v 1 es-2ais system provides an additional barrier between systems that may contain radioactivity and the seawater intake canal to prevent accidental release of radioactivity. A radiation monitor vill
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detect the accidental in-leakage of radioactivity in tais system.
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. Redundant component trains (motor driven pumps and heat exchangers)
O are protected against missiles and appropriate valving allows any pinep to provide cooling water to the heat exchangers connected to the headered system. The system components can be isolated on an individual basis.
Decay Heat Services Cooling System (DRSCS)
The decay heat service cooling system (DESCS) also utilizas two independent system functions comprised of the decay heat service seawater cooling system (DHSSCS) and the decay heat closed cycle cooling water system (DBCCCWg). This system has been designed to meet seismic Category I requirements and provides cooling water to safety related components. These components include the decay heat removal heat exchangers, decay heat service seawater pusy motor, DHCCCWS pump motor air handling units, decay heet pumps and motors, reactor building spray pump and motors, and the makeup (HPIS) ptmps. The heat removed from the safety related components 1
leaves the plant by way of the seawater discharge canal. In the event that off-site power is lost durins normal or accident con-1 ditions, the pumps in both systems will be powered by the emergency
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diesel generators. Any single header in each system can furnish O
es i i a res i e4 cooti==-
i Decay Heat Service Seawater Cooling System (DHSSCS)
The DHSSC System consists of two independent full capacity,100 percent redundant headers to ensure continuous transfer of heat from the DHCCCWS during all operating and accident conditions.
Each header of the DHSSC system contains a full capacity motor driven pump and heat exchanger. Appropriate valving has been provided to enable isolation of the pump or heat exchanger. It is concluded that the system is espable of providin, required coo? u g in the event of a single failure in any past of the DHSSC syr,ces.
Decay Heat Closed Cycle Cooling Water System (DHCCCWS)
The decay heat closed cycle cooling water systma (DHCCCWS) con-sisting of cooling water ptmps, heat exchangers and associated 1
equipment have been designed to Seismic Class I requiremer:ts.
I This system acts as an intermediate heat sink for the decay heat removal system and for safety related components.
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HUCLEAR PLANT ORCAHlZATION CRYSTAL RIVER UNIT 3 m
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FIGURE 12.1-4
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OFF-SITE CRYSTAL RIVER PLANT S M ORT C N S SUPERINTENDENT (RAD MONITORINC)
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NOTIFY AEC l
OPERATING SHIFT INSTITUTES MEASURES
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CRYSTAL RIVER GENERAL PLANT TO PLACE NUCLEAR OF HEALTH SIGN-UNITS IN SAFE SUPERINTENDENT IFICANC:: OF IN-OPERATING CONDITION CIDENT, DIV. OF HEALTH, TO INITI-ATE RAD. RESPONCE FOSSIL PLANT PLAN AS REQUIRED EMEl.JENCY l
SUPERINTENDENT LIAISON OFFICER SUPPORTIh*G AGENCIES INSTITUTE MEASURES TO PLACE FOSSIL UNITS IN SAFE OPER-ATING CONDITION ENVIRONMENTAL EVACUATE ANY OR ALL NOTIFY MEDICAL SURVEY TEAM I3RSONNEL FROM PLANT FACILITY, AS (EST)
SITE REQUIRED MEDICALEMERCENCYh EMERGENCY REPAIR RADIATION EMERG.
FIRE EMERGENCY PLANT SECURITY TEAM LEADER TEAM LEADER TEAM LEADER TEAM LEADER TEAM LEADER (EMT)
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(RET)
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AUGMENTING EMERGENCY OPERATING ORGANIZATION
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LINE OF C0!DIUNICATION FIGnRE 2
Baertency Teams Y
TEAM RESPoltSIBILITIES Radiation Emergency Radiation Protection i
e matters on-site.
Firo Brigade Fight fires within the Nuclear Plant Medical Daergency Provide'First Aid and transport seriously lajured personnel.
Security Security matters re-quired by the incident.
Repair Repair equipunen:. to enable shutdown of plant or return to normal operation.
i On-site and off-site Environmental Survey radiological surveys.
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b PRODUCTION SUPERINTENDENT 8
I PLANT EMERCENCY
- MANAGER, OFF-SITE COORDINATOR RADIOLDCICAL SUPPORT I
I PUBLIC RELATIONS COMMUNICATIONS REPRESENTATIVE ENCINEER l
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MEDICAL TRANSPORTATION SPECIALIST REPRESENTATIVE l
LECAL PROCUREMENT REPRESENTATIVE SPECIALIST FINANCING AND
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Line of Consunication Florida Power h
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Line of Authority Enerrency Orcant:stion FICCRE 4 y
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CITSTAL RITER UNIT 3 SUBJECT - m-3 70551 EATING AS CottPARED TO OTHER B W 177 F.A. FLAlr!S POSITION StBMARY See next page AFFLICABLP REGULATORI WIDE - NONE REFERENCES - EDEE I
D D
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e Tcpic CRYSTAL RIVER UNIT #3
Subject:
Discussion of what has been done on CR-3 to take advantage of k
i h existing operating plants' data and experiences including con-L struction.
r Florida Power Corporation has taken advantage of other nuclear project experiecces through the use of publications and participation in professional societies, indus-try societies, standard development comittees, and through comunication channels with Nuclear Steam System suppliers and consultants. We participate both as a supplier and recipient of data and information. The following is a listing of the F
various organizations in which the company key personnel participate:
E Publica tions b
1.
Atomic Energy Clearing House E
2.
Reactor Safety-Operatin i-Nuclear Standard News (g Experience 3.
Informatio's Center of Nuclear Standards) g Memberships h
b 1.
Mr. R. E. Raymond Institute of Electrical and Electronics Engineers I
g American Nuclear Society - Florida Section Coard of Directors 2.
Mr. J. T. Rodgers ANSI - Nuclear Standards Policy Lomittee A:nerican Nuclear Society p
Atomic Industrial Forum
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Mr. G. W. Mr.rshall kk Prime Movers Comittee of the Edison Electric Institute
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Nuclear Power Subcomittee (EEI)
Sk 4.
Mr. J. Alberdi E-EEI Nuclear Plant Design and Operations Task Force 5.
Mr. H. L. Bennett N45.2.6 Comittee for Qualification of Inspection and Testing Personnel
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for the Ccnstruction Phases of Nuclear Power Plants b
Southeastern Electric Exchange Generating Plant Construction Comittee 6.
Mr. M. E. Kleinman EEL Quality Assurance Task Force k
7.
Mr. E. E. Froats o,
Southeastern Electrical Exchange Quality Assurance Comittee k
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Crystal River Unit 3
Subject:
Emergency Plan The Emergency Plan is Appendix 123 of the FSAR. It contains plans for coping wit *: emergency situations including organization, authority and duties of personnel. The plan was developed using the AEC Cuide to the Preparation of Emergency Plans For Production and Utilitation Facilities, May 1970 and meeta.
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Nor sal organization involving FPC' personnel is shown in Figure 1.
The operation of the Nuclear Plant is the direct responsibility of the Nuclear Plant Super-intendent. The Nucle.ar Plant Superintendent is responsible to the General Plant Superintendent who in turn is responsible to the Production Superintendent.
Figure 2 (Figure 2.2 of the Emergency Plan) delinestes the organization during an emergency. The organization includes both on-site and off-site support personnel.
On-site, there are six teams established to cope with emergency situations. Regarding of f-site personnel, the Energency Organization includes tne Florida Power Corporation Radiological Emergency Support Organization, the AEC, and the State of florida Division of Health.
FPC On-Site Emergency Support: The Emergency Plan establishes the position of the Emergency Coordinator for the direction of all activities at the plant site during emergencies. His authority includes the decision to evacuate any or all personnel f rom the site, to place any or all generating plants in a safe ' shut-down condition, to notify all applicable agencies and decide upon re-entry to the emergency affected areas.
The position of Emergency Coordinator requires a highly qualified person. There-fore, the Nuclear Plant Superintendent, the Assistant Nuclear Plant Superintendent or on a temporary basis, the Duty Shift Supervisor acts as the Emergency Coordinator.
The Emergency Coordinator will coordinate plant activities through the various Emergency Tea.a Leaders. These teams are listed in Figure 3.
The degree of implementation of the Emergency Plan is dependent upon the classifica-tion of the emergency. The classification of an emergency is the responsibility of the Emergency Coordinator. By definition of the Emergency Plan:
1.
A Class a Emergency is one which involves excessive and/or uncontrolled radioactive spills and unexpected high radiation areas which may re-quire partial evacuation f rom, or within, the Nuclear Plant Area only.
2.
A Class B Emergency involves accidental and/or excessive radiosctive releases, or the ic=iinent release of, from the plant, and may require evacuation fro 1 the Nuclear and Fossil Plants, as well as other personnel within the Excltsion Area.
3.
A Class C Emergency involves radiological hazards not only to those stipulated in a Class A or B incident, but also to the general public located outside the Exclusion Area.
O Each accident classification has a set of action levels included in the Emergency Plan and Implementing Procedures. lo help the Emergency Coordinator resolve the classification, a set of meteorological overlays has been developed based upon weather data taken at the site and calculated doses based upon serious accident conditions.
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in addition to the Dscrgency Plan, the on-site support person..el h.ve a series of impicmenting procedures. These procedures trovide guidance at.d instruction to personnel carrying out their designated duties.
Off-Site Emergency Support: The purpose of off-site support persoasel is to help in ninimizing the radiological hazards to the general public. If a Class C lbergency has been.lassified by the D2erger.cy Coordinator, of f-site support is notified. There are three najor groups involved:
O 1.
L'niver sity of Florida, Shands Teachieg Ilospf tal 2.
Florida Power Corporation Radiological Eme rgenc/ Stepport Organization 3.
Division of 18calth and Rehabiliative Services of the State of Florida 4.
E=crgency Response Team The Shands Teaching ilorpital has experienced Physicians and Nurses to handle a radiation exposure or contasinated case invoiring medical injuries. Other (non-radiological) injtared personnel may be treated by a Crystal River Physician or taken to the Citrus Countf Me:sorial Hospital is Inverness, Florida.
The Florida Power Corporatien of f-site support organization is shawn in Figure 4 Those involved are qualified personnel on a " call" basis. It is not expected to take longer ti.an three hours fer Florida Fever Corporaticn off-site support tc reach Crystal River. Two headquarters are at their disposal. Depending on the circumstances, they will locate at either the Florida Power Office in Cry tal River or in the Florida Power Corporation int.lis Plant near Yanks:etcun.
The State of Florida Radiological response plas includes assistance fros the liighway Patrol, Marine Patrol, Civil Defense, Civision of I!calth, and Division oi Lacrgency ':overnment. The various authorities of these groups include; con-trol of traffic, control of waterways, evacuation she.ters, medical assistance, i'
decontamination, and control of agricultural or dairy products. Ad.iitional personnel are also available f rom FPC headq s.arters to provide Techrical Support durlag hoth escrgency and norrul operations.
Training and Drills: In order to fulfill the intentions of the Energency Plan all personnel and agencies involved are trained and will perfora scheduled drills.
L1ch separate agency is responsible for tral =ing.
Florida Power Corporation training includes general familiarization by a*.1 persons assigned to the Crystal River site, as well as training to carry out specific assignments.
l Drills planned by Florida Power Corporation vill be conducted to maintain a high state of profleien.y in areas of fire, radismo, and medical emer;n ncies. The I portance of drills is to; (1) demonstrate ciequate familiarizat ion of Inuividuals i
with the plan; (2) test co=::rnications network.s; and (3) delineate probles areas i
and provide remedial solutions. They will le u realistic as possible wi;hout ie;rding plant operations or endangering pers::cel.
%:ua ry : in sucusary, the Energency Plan establishes accident or c: crgency criteria, delineates authority, forms a plas of action for all possible e=crgencies, documents agrec=ents with of f-site agencies ani in general, is the official actica i
which will take place. during c=crgency situstuns at the Crystal River Nuclear Plant.
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References:
A.
10 CFR 50 Appendix E; AEC Culde To The Preparation of Energency Planc. For Production and Utilization Facilities, May 1910 d
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Recent Porulation Trends Durinq the last several years the growtn rate in population for the l
West-Central Florida area has increased significantly.
Figure 4 shows the rec.ent trends in growth for Citrus County. It can be seen that the population increased by 6.8% from 1970 to 1971.
From 1971 to 1973, over a 'wo-year interval, the population increased by about 47.6",, or an average of 23.8*. per year for the interval.
Abrupt changes in the pepulation trends such as this have an extreme influence on the long-tem projections. The year 2020 projected population for Citrus County based on trends observed through 1970 was 54,000. The year 2020 projections as based on observations through June,1974, is about 159,000 persons. Thus, in a period of three and one-half years, the 2020 projection has changed by a factor of nearly three.
In trying to assess the reasons for such rapid and unpredictable growth, one itect has becoce evident. That is the boorling residential development
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bu s ir.ess. The character of a region can be changed very rapidly by i
land and housing developers who create instant cities out of once rural lar.d. We have assembled some incomplete but representative examples, through telephone contact with realtors, private individuals
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and developers, concerning growth in the area around Crystal River.
following are soma specific items.
(Figure 5) l.
Beverly Hills Development in the Dunnellon area is adding 125-150 houses per year.
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6 2.
Highlands West and South Developoent near Inverness plans to develop 3,500 acres.
3.
Along U.S. Highway 19 between Homosassa and Crystal River, significant amounts of trailers have been obser ved.
k 4.
Sagamill Woods Development south of Homosassa is planning I'
about 40,000 homes.
It is obsicas that developments such as these can have drastic influence on gria.th patterns.
j j
In the past, the aujor concentrations of population have occurred in waterfront areas.
T*.e ultimate de lise of this trend will be due to the finite arount of waterfront area. The practice entployed in the past of dredge-and-fill to create instant waterfront property is now being l
all but eliminated due to stringent control over dredging by the State of Florida.
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The west coast of Florida from Dunedin northward to about the Suwar. nee
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River or slightly above has no natural beaches or well-defined shoreline i
and hence was arrong the last of the coastal areas to feel the impact of waterfront development.
Due to the strict dredging regulations and the natural swampy character of the adjacent coastline, we do not expect any extreme population 2
increases due to massive development in the immediate (less than 5 miles) area of Crystal River Unit 3.
References:
1)
Bureau of Economic & Business Research.
University of Florida, P_opulation Estimates, Bulletin No. 30; June 1974 2)
Crystal River Unit 3 Applicant's Environmental Report Operating License Stage, Sooplement 1 E
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FIGURE 4 2020 - IE9,000
/
140 CITRUS COUtlTY, FLA.
POPULAT!0tl IN THOUSA! IDS sT) 120 100 flew PROJECT!0!1 1970 - 19,200 6.8%
1971 - 20,500 47.6%
1973 - 30,253 80 60 2070 - 54,000
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OLD PROJECT!0'l 20 YEAR 75 80 85 90 2000 05 10 15 20 j.
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