ML19322E507

Forwards BAW-1607, Cycle 3 Reload Rept & Eia.Environ Radiological Conclusions Reached in Fes Are Still Valid for License Amend Request.Certificate of Svc Encl

ML19322E507
Person / Time
Site:	Crystal River
Issue date:	03/21/1980
From:	Richard Bright FLORIDA POWER CORP.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML19322E508	List: ML19322E507 ML19322E510
References
NUDOCS 8003280271
Download: ML19322E507 (8)

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March 21, 1980 File: 3-0-3-a-3 Director Office of Nuclear Reactor Regulation Division of Operating Reactors U.S. Nuclear Regulatory Coanission Washington, DC 20555

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72

Dear Sir:

Enclosed are three (3) originals and forty (40) copies of the Report BAW-1607, February 1980, Crystal River Unit 3 Cycle 3 Reload Report and forty (40) copies of the report, Environmental Impact Appraisal .nd Bal-ance of Plant Review for Cycle 3 lieload and Power Level Upgrade.

These reports justify the operation of Crystal River Unit 3 (Cycle 3) at a rated core power of 2544 MWt, which corresponds to the ultimate core power level identified in the Crystal River Unit 3 FSAR.

Section 8, " Proposed Modifications to Technical Specifications of BAW-1607", is included for completeness of information only. A formal Tech-nical Specification Change Request will be filed under separate cover.

Florida Power Corporation considers the Cycle 3 Reload and Power Level Upgrade to be a Class IV Amendment, per 10 CFR 170.22, and hereby sub-mits our licensing fee in the amount of twelve thousand three hundred dollars ($12,300). FPC filed Technical Specification Change Request No. 39 on March 15, 1979, which we determined to be a Class V Amend-ment. Since both Technical Specification Change Request Jo. 39 and our present Technical Specification Change Request concern the same subject of power level upgrade, we consider the fee for the power level upgrade to have been included in the fee for Technical Specification Change Request No. 39, and our determination of the current amendment request as a Class IV Amendment to be appropriate.

Based on the analyses and reviews performed in the enclosed reports, it has been concluded that Crystal River Unit 3 can be safely operated for Cycle 3 at the rated core power level of 2544 MWt.

3003280M\4 General Office 3201 in.rtyaourin street soutn . P O Box 14042. St Petersburg. Flonda 33733 . 8:3 - 866 5151

Director Page Two Office of Nuclear Reactor Regulation March 21, 1980

! In view of the fact that Cycle 2 .did not reach the exposure window on which the analyses in Report BAW-1607 for Cycle 3 were based, Babcock and Wilcox has initiated reanalysis of Cycle 3, based on the exposure f which was attained. Florida Power Corporation currently estimates that

! the reanalysis and any necessary revisions to Report BAW-1607 will be completed- by mid-April, 1980. Florida Power Corporation will subse-quently submit any necessary revisions to Report BAW-1607 in conjunction j with our formal Technical Specification Change Request at that time.

Please advise if further discussion is desired.

f. Sincerely, FLORIDA POWER CORPORATION

.k/1(/ .

Ronald M. Brigh h

Acting Manager

Nuclear Support Services F

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! cc: Director I

Office of Inspection and Enforcement

U.S. Nuclear Regulatory Commission

Suite 3100 i 101 Marietta Street i Atlanta, GA 30303 s

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1 STATE 0FJFLORIDA

_ COUNTY OF PINELLAS

'- Ronald M. Bright states that he is the Acting Manager, Nuclear Support Services, of Florida Power Corporation; that he is authorized on - the part. of _ said company- to sign and f.ile with the Nuclear Regulatory Commission the information attached hereto; and that ill such statements

.made and matters set forth therein are true and correct -to the best of

his knowledge, information, and belief.

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, Ronalcf M. Aright 4

Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 21st day of March, 1980. '

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j Notary Public Notary Public, State of Florida at Large,

My Commission Expires

August 8, 1983 J

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF )

) DOCKET NO. 50-302 FLORIDA POWER CORPORATI9N- )

i l CERTIFICATE OF SERVICE Ronald M. Bright deposes and says that the following has been served on the Chief Executive of Citrus County, Florida, by deposit in the United

. . States mail, addressed as-follows:

Chairman Board of County Commissioners of Citrus County Citrus County Courthouse Inverness, FL 32650 An original copy of our March 21, 1980, submittal.

FLORIDA POWER CORPORATION I L4atA Ronald M. Br'ight i Acting Manager Nuclear Support Services SWORN TO AND SUBSCRIBED BEFORE ME THIS 21ST DAY OF MARCH,1980.

i Notary Public Notary Public ~ State of Florida at Large My Commission expires: August'8, 1983 (NOTARIAL SEAL)

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-(Cert .Ser.v.012)

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F ENVIRONMENTAL IMPACT APPRAISAL Radiological Impact We have reviewed the Final Environmental Statement (FES) dated May, 1973, related to the operation of Crystal Rivcr Unit 3. The radiologi-cal consequences of the postulated accidents in the FES were calculated based on the design power of 2544 MWt. Therefore, increasing the power level of Crystal River Unit 3 from 2452 MWt to 2544 MWt will not change the conclusion in the FES that the environmental risk due to postulated radiological accidents is exceedingly small.

We expect that increasing the thermal power level of Crystal River Unit 3 from 2452 MWt to 2544 MWt will increase the concentration of ac-tivity in tha reactor primary coolant and in water entering the radwaste treatment systems. This increase should be less than the percentage in-crease in the thermal power level which is 3.7 percent. This small in-crease in the concentration of activity will not affect the performance of equipment in the radwaste treatment systems. There will also be no change in the flows and volumes of liquids and gases in these systems.

Therefore, we expect the increase in radwaste effluents due to the change in thermal power level to also be less than the percentage in-

! crease in the thermal power level. This small increase does not change the conclusion that the radwaste treatment system at Crystal River Unit 3 will be capable of limiting radioactive releases to values which are a small fraction of 10 CFR 20 limits.

Review of the Crystal River Unit 3 FSAR indicates that the radiological effects on control room habitability during accident conditions and con-sideration 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 Safe-guards Leakage During the Maximum Hypothetical Accident", of the Crystal River Unit 3 FSAR indicate that the dose to the operators or at the site exclusion distance are a small fraction of 10 CFR Part 100 dur-ing these events.

Thermal Impact

, We expect that the increase in power level from 2452 MWt to 2544 MWt

! may, theoretically, result in a condenser heat output increase from i 5,532 x 106 Etu/hr (assumed in the Crystal River Unit 3 Environmental l Report) to 5,660 x 106 Btu /hr. This increase in heat output will in-l crease the AT by about 0.4 F*. We are evaluating possible modifications l at Crystal River Unit 3 to reroute some heater drains which will reduce the rejected heat from the condenser. The current Appendix B Environ-mental Technical Specifications has a AT limit of not in excess of 17.5 F* for a period of more than 3 consecutive hours or a maximum of 21 F* unless there is an emergency need for pcwer. Crystal River Unit 3 will operate within these thermal lunits at the 2544 MWt power level.

When the condenser is operating at optimum condition, operation within Simpson(Radlmpact)DN-94

s these thermal limits can be attained. However, periodic load reductions may be necessary when the condenser becomes fouled in order to clean the condenser to ensure continued operation within these thermal limits.

Meteorological Data Meteorological data at the Crystal River site for the years 1975, 1977, and 1978, in the standard format was submitted under separate cover to the NRC on January 24, 1979. X/Q values for the 1975 and 1977 meteoro-logical data were submitted to the NRC on January 24, 1979. X/Q values for the 1978 meteorological data were submitted to the NRC on Febru-ary 28, 1979. The X/Q values used in the accident analyses described in the Crystal River Unit 3 FSAR and the B&W Reload Report for Cycle 3 op-eration were based on the 1975 meteorological data. The 1975 meteoro-logical data has been reviewed and accepted by the NRC for use as the reference year in the Appendix I Technical Specifications for Crystal River Unit 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 1975 values were very close to the aver-age values of the three years with 1977 being above average and 1978 be-ing below average. This representative year will ensure that the dose to the population around the Crystal River site w;11 not be underesti-mated over the life of the Plant.

Review Of Site Parameters The following is a sumary of our review of the Crystal River Unit 3 site parameters to determine if there has been any significant changes in land use, population or public facilities since receipt of our Opera-ting License in December of 1976.

Land Use - As was the case when our Operating License was issued, the Crystal River Unit 3 site region is predominately agricultural in na-ture. 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 4 miles of the nuclear plant.

There are no public access roads to areas adjacent to the plant site ex-cept at the plant access road. Approximately 4 miles east of the plant, a road crosses the plant access road. The aorth and south plant site boundaries are bordered by woods and swamps and are generally inacces-si ble. The Crystal River is located approximately one mile south of the exclusion area boundary and is used 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. Company property extends to the Gulf of Mexico, approximately 3000 feet beyond the exclusion boundary.

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• As stated above, the area in the vicinity of the Crystal River Unit 3 site is predominately agricultural. However, little of the available land is involved in crop production. Woodland use constitutes the most significant use of the acreage while pasture and range for grazing pur-poses constitute approximately 20 percent of the total acreage. How-ever, there are no milk-producing animals located within 5 miles of the Crystal River site.

No new major highways are expected to pass through the 5-mile radius area surrounding the Crystal River Unit 3 site. A railroad spur off the Seaboard Coast Line Railroad serves the Crystal River site for the pur-poses of delivery of coal to the fossil units located at the site.

Population - For the purposes of 10 CFR 100, the calculated low popula-tion distance is 5 miles; however, the distance based on actual popula-tion density is much larger. For the purposes of this application, in the intent of added safety, the low population zone wG remain at a 5-mile radius.

The distribution of the estimated population for 1980 within 5 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 Crystal River Unit 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 farm until the year 2002. The area within 3 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 lo-cated 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 Crystal River Unit 3 FSAR.

Public Facilities - We reviewed the public facilities located within 10 miles of the plant site to determine if any new schools, hospitals, airports or parks have been built since the issuance of the Crystal River Unit 3 Operating License.

There have been no schcols built within 10 miles of the plant site. The present schools within 10 miles of the site are identified in Sec-tion 2.2.8 of the Crystal River Unit 3 FSAR.

There is now one hospital within the 10-mile zone. Seven Rivers Commun-ity Hospital, located approximately 4.5 miles from the plant site, opened in August of 1978. Its 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 Crystal River Unit 3 FSAR.

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j e Conclusion Based on our review of the Final Environmental Statement, we have deter-mined that the environmental radiological conclusions reached in that document were based on a power level of 2544 MWt and, therefore, have not changed and are still valid for this license amendment request.

Also, this license amendment request to raise the power level at Crystal River Unit 3 from 2452 MWt to 2544 MWt does not require any changes to the Environmental Technical Specifications (Appendix B).

BALANCE OF PLANT REVIEW Florida Power Corporation has reviewed the balance of plant systems, especially the power conversion system, to insure their ability to ac-conmodate core power levels up to 2544 MWt. Our review included discus-sion with Westinghouse Electric Corporation concerning the caoability of the turbine and the generator at Crystal River Unit 3. We have confir-mation 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 transformers are rated for 855 MWe at 0.9 pf (65 C, F0A). The station service load is determined as 35 MWe, which,' when added to the step-up transformer rat-ing, gives 890 MWe.

There are no design changes being made at Crystal River Unit 3 to accom-modate the power level increrea to 2544 MWt other than the addition of Reactor Coolant Pump Power h itors which are described in Report BAW-1607 and our earlier submittals of November 29, 1978 and January 29, 1979.

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