ML19284A446
| ML19284A446 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/28/1979 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML19284A445 | List: |
| References | |
| NUDOCS 7903060431 | |
| Download: ML19284A446 (6) | |
Text
D 9
ENVIRONMENTAL IMPACT APPRAISAL AND BALANCE OF PLANT REVIEW FOR CYCLE 2 RELOAD AND POWER LEVEL UPGRADE CRYSTAL RIVER UNIT 3 February, 1979
, LNVIRONMLNIAL If' PACT APPRAISAL Radiological Impact We hcve reviewed the Final Environmental Statement (FES) dated May.1973 related to the operaticn of Crystal River Unit 3 Nuclear Plant. lhe r.nh o-logical consequences of the postulated accidents in the iLS were calculated based on the design power of 2544 MWt. Therefore, increasing the power level of CR-3 from 2452 MWt to 2544 MWt will not change the conclusion in the FES that the environmental risk due to postulated radiological acci-dents is exceedingly small.
We expect that increasing the thennal power level of CR-3 from 2452 MWt to 2544 MWt will increase the concentration of activity in the reactor primary coolant and in water entering the radwaste treatment systems. This increase should be less than the percentage increase in the thermal power level which is 3.7%. This small increase in the concentration of activity will not affect the perfonnance of equipment in the radwaste treatment sys-t e.ns . There
- ill also be no change in the flows and voic.ies of liquids and gases in these systems. Therefore, we expect the increase in radwaste ef-fluents due to the change in thennal power level to also be less than the percentage increase in the thermal power level . This small increase does not change the conciusion that the radwaste treatment systen at CR-3 will be capable of limiting radioactive releases to values which are a small fraction of 10 CfR 20 limits.
Review of the CR-3 FSAR indicates that the radiological effects on control roon habitability during accident conditions and consideration in dose calculations of ECCS leakage outside containment were analyzed. Section 14.2.2.6.3 " Inhalation Dose to Reactor Operators in the Control Room", and Section 14.2.2.6.5 " Effects of Engineered Safeguards Leakage During the Maximum Hypothetical Accident" of the CR-3 FSAR indicates that the dose to the operators or at the site exclusion distance are a small fraction of 10 CFR Part 100 during these events.
Thermal Impact We expect that the increase in power level froia 2452 MWt to 2544 MWt may thgoretically result inina the 10 BTV/hr (assumed condenser heat output Report)
CR-3 Environmental increasetofrom 5,6605,532 x 106x BTU /hr. This increase in heat output will increase the AT by about 0.4 F .
We are planning modifications at CR-3 to re-route some heater drains which will reduce the rejected heat from the condenser. The current Appendix B Environmental Technical Specifications has a Af limit of 17.5 F and CR-3 will operate within these thermal limits.
Meteorologic3l Data Meteorological data at the Crystal River Site for the years 1975, 1977 and 1978 in the standard fonnat was submit +ed under separate cover to the NRC on January 24, 1979. X/Q values for the 1975 and 1977 meteorological data were also sunnitted to the NRC on January 24, 1979. The X/Q values used in the accident analyses described in the CR-3 FSAR and the B & W Reload Simpson (RadImpact)
D52
Report for Cycle 2 operation were based on the 1975 meteorological data.
The 1975 meteorological data has been reviewed and accepted by the f4RC for use as the reference year in the Appendix I Technical Specifications for CR No. 3.
The X/Q values from 1975,1977 and 1978 were evaluated for the West sector which consistently had the highest or next highest X/Q values. This evaluation showed that the 19/5 values were very close to the average values of the three years with 1977 being above average and 197P being below average. This representative year will ensure that the doses to the population around the Crystal River site will not be underestimated over the life of the Plant.
The X/Q values for the 1978 meteorological data are enclosed for your review.
Review of Site Parameters The following is a summary of our review of the CR No. 3 site parameters to detennine if there has been any significant changes in land use, population or public facilities since receipt of our Operating License in December of 1976.
Land Use - As was the case when our OL was issued, the CR No. 3 site region is predominately agricultural in nature. The exclusion area has a radius of 4400 feet within a 4,738 acre site wholly owned and controlled by Florida Power Corporation. There are no residents within four miles of the nuclear plant.
There are no public access roads to areas adjacent to the plant site except at the plant access road. Approximately four miles east of the plant, a road crosses the plant access road. The north and south plant site boundaries are bordered by woods and swamps and are generally inaccessible.
The Crystal River is locateo approximately one mile south of the exclusion area boundary and is csed for commercial fishing and pleasure craft.
Directly west of the plant is the Gulf of Mexico, from which the Crystal River plant site receives its condenser cooling water. Fishing and pleasure craft have unrestricted access to the Gulf waters. C ompa ny property extends to the Gulf of Mexico, approximately 3000 feet beyond the exclusion boundary.
As stated above, the area in the vicinity of the CR No. 3 site is predoninately agriculture. However, little of the available land is involved in crop production. Woodland constitutes the most significant use of the acreage while pasture and range for grazing purposes constitutes approximately 20 percent of the total acreage. However, there are no milk producing animals located within 5 miles of the Crystal River site.
Simpson (Radimpact)
D52
fio new major highways are expected to pass through the five-mile radius area surrounding the CR th. 3 site. A railroad spur off the Seaboard Coast Line Railroad serves the Crystal River site for the purposes of delivery of coal to the fossil units located at the site.
Population - For the purposes of 10 CFR 100, the calculated low population distance is five miles; however, the distance based on actual population density is much larger. For the purposes of this application, in the intent of added safety, the low population zone will remain at a five mile radius.
The distribution of the estimated population for 1980 within five miles is mainly in the NNW to NNE and in the E to SE quandrants with no residents within 3 miles of the site as shown in Figure 2-6 of the CR No. 3 FSAR. A large portion of the land between the north boundary of the site and the Cross State Barge Canal is under lease to a pulp and paper producer for use as a tree fann until the year 2002. The area within three miles south and east of the site is mostly uninhabited woodland and is expected to remain so through the year 2020.
The nearest population center of 25,000 or more is Ocala which is located 36 miles ENE of the site. Population projections to the year 2020 for a 5 mile, 20 mile and 50 mile radius are shown in Figure 2-6 of the CR No. 3 FSAR.
Public Facilities - We reviewed the public facilities located within 10 miles of the plant sit: to determine if any new schools, hospitals, airports or parks have been built since the issuance of the CR No. 3 OL.
There have been no new schools built within 10 miles of the plant site.
The present schools within 10 miles of the site are identified in Section 2.2.8 of the CR No. 3 FSAR.
There is now one hospital within the 10 mile zone. Seven Rivers Community Hospital, located approximately 4.5 miles from the plant site, opened August of 1978. It's facilities include 75 regular hospital beds and 8 Intensive Care beds.
There have been no new airports or parks built within a 10 mile radius of the plant site. The existing airports and parks are described in Sections 2.2.9 and 2.2.8, respectively, of the CR No. 3 FASR.
Conclusion Based on our review of the Final Environmental Statement, we have determined that the environmental radiological conclusions reached in that document were based on a power level of 2544 MWt and, the efore, have not changed and are still valid for this license amendment request. Also, this license amendment request to raise the power level at CR No. 3 from 2452 MWt to 2544 MWt does not require any changes to the Environmental Technical Specifications (Appendix B).
Simpson (Radimpact) 052
BALANCE OF PLANT REVIEW Florida Power Corporation has reviewed the balance of plant syst im, especially the power conversion systems to insare their ability to accommodate Core power levels up to 2544 MWL. Our review included discussion with Westinghouse Electric Corporation concerning the capability of the turbine and the generator at CR No. 3. We have confinnation from Westinghouse that the turbine and generator are acceptable for continuous operation at the maximum calculated operating conditions of 890 MWe, The generator is rated for 989 MVA which, at a power factor of 0.9, would give a generator output of 890 MWe. Our step-up trans fonners are rated for 855 MWe at 0.9 pf (65 C, FOA). The station service load is detennined as 35 MWe, which, when added to the step-up transfonner rating, gives 890 MWe.
There are no design changes being made at CR No. 3 to accommodate the power level increase to 2544 MWt other than the addition of Reactor Coolant Pump Power Monitors which are described in the attached B & W Reload Report and our submittals of November 29, 1978 and Janua.ry 29, 1979.
Simpson (RadImpact)
D52
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