ML17213B326

Notice of Issuance of License NPF-16

ML17213B326
Person / Time
Site:	Saint Lucie
Issue date:	04/06/1983
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML17213B325	List: ML17213B324 ML17213B326
References
NUDOCS 8305030022
Download: ML17213B326 (11)

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N 7590-01 UNITED STATES NUCLEAR REGULATORY COtdtIISSION DOCKET HO. 50-389 ST.

LUCIE PLANT, UNIT 2

FLORIDA POWER 8 LIGHT COMPANY, ET AL NOTICE OF ISSUANCE OF FACILITY OPERATING LICENSE Notice is hereby given that the U. S. Nuclear Regulatory Commission

( the Commission),

has issued Facility Operating License No. HPF-16, (License) to Florida Power 8'ight Company, Orlando Utilities Commission of the City of Orlando and Florida IIunfcipal Power Agency (licensees).

This License e

authorizes operation of the St. Lucie Plant, Unit 2 (facility) at reactor core power levels not fn excess of 2560 megawatts thermal in accordance with the provisions of the License, the Technical Speciffcations and the Environmental Protection Plan.

However, the License contains a condition currently limiting operation to five percent of full power (128 megawatts thermal).

Authorization to operate at greater than five percent power will require specific Commission approval.

St. Lucie Plant, Unit 2 fs a pressurized water reactor located at the licensees'ite on Hutchinson Island in St. Lucie County, Florida approximately 34 miles north-northeast of the city of l(est Palm Beach.

The License fs effective as of the date of issuance and shall expire at midnight on Apr>l 61 2023.

The application for the license complies with the standards and requirements of the Atomic Energy Act of 1954, as amended

( the Act), and the Commission's regulations.

The Commission has made appropriate findings as required by the 8305030022 830406

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NRG FORM 318 u0-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981~5.960

4 fn the License.

Prior public notice of the overall action involving the proposed issuance of an operating license was published in the FEDERAL REGISTER on Ilarch 9, 1981 (46 F. R. 16831).

The CotFmission has determined that the issuance of this license will not result fn any environmental impacts other than those evaluated fn the Final Environmental Statement since the activity authorized by the license is encompassed by the overall action evaluated fn the Final Environmental Statement.

For further details with respect to this action, see (1) Facility Operating License No. NPF-16, with Technical Specifications (NUREG-0949) and Environmental Protection Plan; (2) the report of the Advisory Committee on Reactor Safeguards dated November 17, 1981; (3) the Commission's Safety Evaluation Report dated October 1981; Supplement Ho.

1 dated December 1981; Supplement No. 2 dated September 1982; Supplement No. 3 datedt'April',1983; (4) the Final Safety Analysis Report and amendments thereto; (5) the Environmental Report and supplements thereto; (6) the Draft Envfronmental Statement dated October 1981; (7) the Final Environmental Statement dated April 1982; and (8) the assessment of the effect of license duration on matters discussed in the Final Environmental Statement for St. Lucie Plant,, Unit 2.

These documents are available for public inspection at the Commission's Public Document

Room, 1717 H Street, N. H., Washington, D. C.,

and the Indian River Community College Library, 3209 Virginia Avenue, Ft. Pierce, Florida OFFICE/

SURNAME/

OATE 0

,: NRC FORM 318 (10 80) NRCM 0240 OFFICIAL RECORD COPY

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A copy of Facility Operating License No. NPF-16 may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C.

20555, Attention:

Director, Division of Licensing.

Copies of the Safety Evaluation Report and its Supplements 1 through 3 (NUREG-0843) and the Final Environmental Statement (NUREG-0842) may be purchased at current rates from the National Technical Information Service, Department of Commerce, 5285 Port Royal Road, Springfield, Virginia

22161, and through the NRC GPO sales program by writing the U. S. Nuclear Regulatory Commission, Attention:

Sales

Manager, l<ashington, D. C.

20555.

GPO desposit account holders can call 301-492-9530.

Dated at Bethesda, t]aryland, the 6th day of April 1983.

FOR THE NUCLEAR REGULATORY COMMISSION

/s/

George W. Knighton, Chief Licensing Branch No.

3 Division of Licensing DFFICEI SURNAME/

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Docket No. 50-335 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASMINGTON,D. C. 20555 AMENDMENT"TO INDEMNITY AGREEMENT NO. B-76 MENDMENT N Effective October 14, 1982; Indemnity Agreement No. B-76, between Florida Power 8 Light Company and the Atomic Energy Commission, dated February ll,

1975, as

amended, is hereby further amended as follows:

Wherever the name "Florida Power 8 Light Company" appears in the indemnity agreement, the following named licensee is added:

"Orlando Utilities Commission of the City of Orlando, Florida."

FOR THE UNITED STATES NUCLEAR REGULATORY COMMISSION State and Licensee Relations Office of State Programs Accepted 1983

, Acceptt.d

, 1983 By 'LORIDA P

'liER 5 LIGHT C MPANY By ORLANDO UTILITIES C YiMISSION F

THE CITY OF ORLANDO, FLORIDA

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qo UNIT/D STATES NUCLEAR REGULATORY COMMISSION YVASHINGTON,D. C. 20555 Docket No. 50-335 AMENDMENT TO INDEMNITY AGREEMENT NO. B-76 9

Effective February 3, 1983, Indemnity Agreement No. B-76, between Florida Power 8 Light Company, Orlando Utilities Commission of the City of Orlando,

Florida, and the Atomic Energy Commission, dated February 11,

1975, as

amended, is hereby further. amended as follows:

Wherever the names "Florida Power 8 Light Company, and "Orlando Utilities Coranission of the City of Orlando, Florida" appear in the indemnity agreement, the following named licensee is added:

"Florida Municipal Power Agency" FOR THE UNITED STATES NUCLEAR REGULATORY COMMISSION Jerome Saltzman, Assistant Director State and Licensee Relations Office of State Programs Accepted 1983 Accepted 1983 By FL R

D P

5 LIGHT C MiP NY By RL ND U IL IES C MMISSI N

F THE CITY OF ORLANDO, FLORIDA Accepted 1983 By FL R

MiUN P L

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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket No. 50-335 50-389 AMENDMENT TO INDEMNITY AGREEMENT NO. B-76 N

N N.10 Effective APR 6

]983, Indemnity Agreement No. B-76, between Florida Power 8 Light Company, Orlando Utilities Commission of the City of Orlando,

Florida, and Florida Municipal Power Agency, and the Atomic Energy Commission, dated February 11,

1975, as

amended, is hereby further amended as follows:

Item 3 of the Attachment to the indemnity agreement is deleted in its entirety and the following substituted therefor:

Item 3 - License number or numbers SNM-1514 SNM-1902 DPR-67 NPF-16 (From 12:Ol a.m.,

February 11, 1975 to 12 midnight, February 29,

1976, inclusive)

(From 12:01 a.m., October 14, 1982 to 12 midnight, p,pR 5

]983 inclusive)

(From,12;01 a.m.',

March 1, 1976)

(From 12:01 a.m.

APR 6 tS83

)

FOR THE UNITED STATES NUCLEAR REGULATORY COMMISSION State and Licensee Relations Office of State Programs Accepted

, 1983 Accepted 1983 By FLRID P WR LGH dPN By RL N

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ES ASS N

F THE CITY OF ORLANDO, FLORIDA Accepted 1983 By 1983 FLRID MUNCIPLPWR GNY

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~,V ASSESSMENT OF THE EFFECT. OF LICENSE DURATION ON t<ATTERS DISCUSSED IN THE FINAL ENVIRONhlENTAL STATEtiiENT FOR THE ST.

LUCIE PLANT, UNIT INTRODUCTION The Final Environmental Statement (FES) for the operation of the St. Lucie Plant, Unit 2 was published in April 1982.

At that time it was staff practice to issue operati'ng licenses for a period of 40 years from the date of the construction permit.

This was approximately 30 years of operating life.

However, since the applicant has requested in their application that the operating license (OL) for their St. Lucie Plant, Unit 2 then under consideration by the staff, have a duration of 40 years from the date of OL issuance, an assessment contained herein is made for those issues affected by the 40 year duration.

DISCUSSION The staff has reviewed the St. Lucie 2 FES to deter'mine which aspects considered in the FES are affected by the duration of the operating license.

In general, the FES assesses various impacts associated with operation of the facility in terms of'nnual impacts and balances these against the anticipated annual energy production benefits.

Thus, the overall assessment and conclusions would not be dependent on specific operating life.

There are,

however, a few areas in which a specific operating life was assumed.

These are as follows:

1.

Radiological assessments are based on a 15-year plant midlife.

2.

Probabilistic assessm nt of severe accidents.-

The evaluation and findings in the FES are applicable to 40 years of operation, therefore, no further appraisal is necessary is this area.

3.

Community characteristics.

The evaluation and findings in the FES are applicable to 40 years of operation; therefore, no further appraisal is necessary in this area.

4.

Uranium fuel cycle impacts are based on one initial core load and 29 annual refuelings.

EVALUATION The staff's appraisal of the sighificance of the use of 40 ye'ars of operation rather than 30 as it affects the two areas above (i.e.

1 and 4) is presented in the fol 1 owing di scussi ons:

1.

Radiolo ical Assessments

- The NRC staff calculated dose commitments to the human popu at>on residing around nuclear power reactors to assess the impact on people from radioactive material released from these reactors.

The annual dose commitment is calculated to be the dose that would be received over a 50-year period following the intake of radioactivity for one year under the conditions that would exist 15 years after the plant began operation.

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The 15 year period is chosen as representing the midpoint of plant operation and is incorporated into the dose models by allowing for buildup of long life radionuclides in the soil. It affects the estimated doses only for radfonuclfdes ingested by humans that have half-lives greater than a few years.

For a plant licensed for 40 years, increasing the buildup period from 15 to 20 years would increase the dose from long life radionuclides via the ingestion pathways by 10% at most. It would have much less effect on dose from shorter life radionuclides.

Table E-6.6 of the FES indicates that the estimated doses via the ingestion pathways are well below the regulatory design objectives.

For example, the ingestion dose to the thyroid from Unit 2 is 0.61 mrem/yr compared to an Appendix I design objective of 15 mrem/yr.

Thus, an increase of even as much as 10% in these pathways would remain well below the Appendix I guidelines and would not be significant.

2.

Uranium Fuel C cle Im acts The impacts of the uranium fuel cycle are ased on 0 years o

operation of a model LHR.

The fuel requirements for the model LWR were assumed to be one initial core load and 29 annual refuelfngs (approximately 1/3 core).

The annual fuel requirement for the model LWR averaged out over a 40-year operating life (1 initial core and 39 refuelings of approximately 1.3 core) would be reduced slightly as compared to the annual fuel requirement averaged for a 30-year operating life.

The net result would be approximately 1.M reduction in the annual fuel requirement for the model LWR.

This small reduction in fuel requirements would not lead to signiffcant changes in the impacts of the uranium fuel cycle.

The staff judges that there would not be any changes to St. Lucie 2 FES Table 5.11 (S-3) that would be necessary in order to consider 40 years of operation.

If anything, the values in Table 5.11 become more conservative when a 40-year period of operation is considered.

CONCLUSION The staff has reviewed the St. Lucie 2 FES and determined that only a few of the areas related to its HEPA analysis discussed in the statement were tied directly to a 30-year operating period.

We have concluded, based on the reasons discussed in the sections above, that the impacts associated with a 40-year license duration are not significantly different from those associated with a 30-year license duration and are not significantly different from those assessed in the St. Lucfe 2 FES.

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