3F0286-01, Application for Amend to License DPR-72,incorporating Change Request 143 Re Extension of License Duration to 40 Yrs from Issue Date.Justification for Change Encl.Fee Paid

Application for Amend to License DPR-72,incorporating Change Request 143 Re Extension of License Duration to 40 Yrs from Issue Date.Justification for Change Encl.Fee Paid

ML20214C487
Person / Time
Site:	Crystal River
Issue date:	02/17/1986
From:	Wilgus W FLORIDA POWER CORP.
To:	Harold Denton, Stolz J Office of Nuclear Reactor Regulation
References
3F0286-01, 3F286-1, NUDOCS 8602210154
Download: ML20214C487 (8)

Text

__________ __

Florida P.o.w..e. r Walter S.Wilgus vice President Nuclear Operations February 17, 1986 3F0286-01 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Subj ect: Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Operating License Change Request Number 143

Dear Sir:

Pursuant to 10 CFR 50, Section 50.90, Florida Power Corporation (FPC) hereby requests an amendment to Facility Operating License DPR-72 for Crystal River Unit 3 (CR-3). The purpose of this license amendment is to 'xtend the duration of the license to forty (40) years from o .e date of issuance of the operating license. A license tem of 40 years from the date of issuance of the operating license is permitted by the NRC regulations, specifically 10 CFR 50, Section 50.51. Further, Comission -

approval of the proposed amendments would be consistent with recent NRC actions.

The CR-3 plant is currently licensed for operation for 40 years commencing with the issuance of the construction pemit, which was on September 25, 1968. Thus, the operating license will expire at midnight September 25, 2008. It is requested that the license expiration date be changed to December 3, 2016, 40 years from the issuance of the Operating License on December 3, 1976 A

IL,se 8602210154 860217 DR ADOCK 05 g2 g iglp Cs l

0 40 g 3201 Thirty-fourth Street South P.O. Box 14042,St Petersburg, Florida 33733 813 866 5202

February 17, 1986 3F0286-01 Page 2 i

The Attachment provides a description of the proposed change to the Facility Operating License and associated supporting >

! evaluations.

An application fee, Check number 750541, of one hundred fifty

, dollars ($150), as required by 10 CFR 170, has been attached.  ;

j Sincerely,

/ - '

W.'S. Wi s Vice Pr'e dent NucleadOperations j EHD/DM0/feb

Attachments cc: Dr. J. Nelson Grace Regional Administrator, Region II Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, GA 30323 i.

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UNITED STATES OF AMERICA NUCLEAR REGULATORY CO M ISSION IN THE MATTER OF )

) DOCKET No. 50-302 FLORIDA POWER CORPORATION )

CERTIFICATE OF SERVICE W. S. Wilgus deposes and says that the following has been served on the Designated State Representative and the Chief Executive of Citrus County, Florida, by deposit in the United States mail, addressed as follows:

Chairman, Administrator Board of County Commissioners Radiological Health Services of Citrus County Rehabilitative Services Citrus County Courthouse 1323 Winewood Blvd.

Inverness, FL 32650 Tallahassee, FL 32301 Three (3) copies of Operating License Change Request No. 143, requesting amendment to Item 2G of Operating License No. DPR-72.

FLORIDA POWER CORPORATION N

W. S. Wil g(

Vice Pre igent Nuclear erations SWORN TO AND SUBSCRIBED BEFORE ME THIS 17th day of February 1986.

Notary public Notary Public, State of Florida at Large My Comission Expires: July 22,1989 (NOTARIAL SEAL) w.d

STATE OF FLORIDA COUNTY OF PINELLAS W. S. Wilgus states that he is the Vice Presiuent Nuclear Operations, for Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.

W. S. Wilg Vice Pres'1 dent NuclearOperations Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 17th day of February,1986.

Notary (fublic r

W Notary Public, State of Florida at Large, My Commission Expires: July 22,1989

3F0286-01 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302/ LICENSE NO. DPR-72 OPERATING LICENSE CHANGE REQUEST NO.143 LICENSE DOCUMENT INVOLVED: Facility Operating License PORTIONS: Item 2G.

DESCRIPTION OF REQUEST:

Amend the CR-3 operating license expiration date from midnight September 25, 2008 to midnight December 3, 2016.

REASONS FOR REQUEST:

Crystal River Unit 3 (CR-3) is currently licensed for plant operation for 40 years commencing with issuance of the Construction Pemit. The CR-3 li,:ense (DPR-72) currently expires on September 25, 2008. By this license amendment application, FPC requests that this license expiration date be changed to December 3, 2016. Accounting for tne time required for plant construction, the current license represents an ef fective plant operating license tem of only 32 years. This request, if approved, would provide a full 40 year plant operating license tem for CR-3. The basis for granting our request is clearly established in the Commission's regulations. 10 CFR 50.51 states that the Comission will issue an operating license for the tem (not to exceed 40 years) requested by the applicant or for the estimated useful life of the facility if the Comission detemines the estimated useful life is less than the term requested.

We fully expect that the facility will remain useful beyond the current operating license expiration date, and will continue to enhance the economic health and well-being of the Company's service area. The plant is a major asset to Citrus County and surrounding comunities by virtue of its ongoing contributions to the property tax base, secondary benefits to the local economy from employee payroll, and from expenditures for goods and services to operate the plant. As a baseload generating station, CR-3 provides power and stability to the Southeastern Electric Reliability Council interconnection serving Florida, Georgia, Alabama, Mississippi, Tennessee, South Carolina, North Carolina, and Virginia. The additional years of plant operation allowed by the proposed change would defer the need to install replacement baseload capacity or to purcha:e supplemental power from outside our system. Utilization of domestic nuclear power helps reduce our nation's dependence on imported oil and on other valuable domestic fossil fuel resources.

Finally, residents and industrial interests throughout the Company's service area will benefit from the lower cost of electricity that would result from spreading capital costs of the plant over a longer period of time.

3F0286-01 SAFETY EVALUATION OF REQUEST:

ASSESSMENT OF NSSS SCOPE An assessment of the potential impact to the Nuclear Steam Supply System (NSSS) equipment was performed by the vendor, Babcock and Wilcox (B&W). Based on this assessment, B&W concluded that there is no need to change the existing criteria for determining the design life of the NSSS equipment, since the 40-year design life is equivalent to 32 Effective Full Power Years (EFPYs). Specifically, from a materials point of view, the equipment design life is based on the time and cycles of exposure to the plant operating environment. During the plant construction stage, plant equipment was not exposed to the operating environment except for short time periods for various system functional tests. The system components were not subjected to the environmental impact of radiation until after the operating license was issued.

Reactor vessel material and fluence analyses have shown that the expected cumulative neutron fluence on the reactor vessel will not limit the 40 year operating life. The Babcock & Wilcox Owners Group's Integrated Reactor Vessel Surveillance Program and the planned Cavity Dosimetry Program shall provide a means for continuing to monitor the cumulative effects of the neutron exposure on the materials of the reactor vessel to satisfy the requirements of 10 CFR 50, Appendices G and H. The analyses of the CR-3 plant specific surveillance capsules irradiated inside the reactor vessel of CR-3 will confirm that the predictions used in the analytical techniques for establishing operating limitations for the reactor vessels are conservative.

Compliance with 10 CFR 50.61 provides assurance that the pressurized thermal shock screening criteria will be met. In a Babcock & Wilcox Report (BAW - 1895, January 1986), Table 2-1 indicates that these criteria will not be exceeded until the year 2031. The results are conservatively based upon a unit capacity factor of 80%.

MECHANICAL SYSTEMS AND EQUIPMENT ASSESSMENT FPC concludes that safety-related mechanical systems, equipment, and components considered will not be impacted by a 40 year operating lifetime. This does not imply that some mechanical system related equipment and components will not wear out or need replacement during the plant operating lifetime. However, existing surveillance and maintenance programs are sufficient to maintain or determine replacement of safety-related components. Periodic inservice inspection and testing requirements have been incorporated into procedures to provide the added assurance that any unanticipated degradation in systems or equipment will be identified and corrected in a timely manner.

ELECTRICAL EQUIPMENT ASSESSMENT The safety implications of extending CR-3's operating license have been evaluated for safety-related electrical systems and equipment. This evaluation included a review of extended service life impacts on equipment integrated dose qualification and environmental qualification in response to NRC IE Bolletin 79-01B and 10 CFR 50.49. For safety-related electrical equipment within the scope of 10 CFR 50.49, aging reviews have been conducted so as to establish a

3F0286-01 qualified life for the equipment. Where necessary, qualifica* ion related m ai nten a n ce/ s u rv ei l l a n ce/ re f u rb i s hme n t/ re pl a ceme nt requirements are integrated into a qualification program to ensure that these requirements are maintained over the life of the plant. Based on this evaluation, FPC concludes that the electrical systems design, electrical equipment selection and application, and environmental qualification of electrical equipment considered are not adversely impacted by a 40 year operational lifetime.

REVIEW 0F CR-3 FES The Final Environmental Statement (FES) for Crystal River Unit 3, dated May 1973, has been reviewed by FPC to detemine if the conclusions in the FES will be materially affected by an extension of the plant's operating life. The population estimates, the radiological impact on the public, and the environmental monitoring programs were reviewed to assess the effects of a life extension on the assumptions made in the FES.

The FES addresses population growth through 2020. However, population estimates for the Emergency Planning Zone (EPZ) are only specifically listed for the year 1971 and the year 1980. More complete population estimates through the year 2020 are provided in the plant's Final Safety Analysis Report (FSAR). Minor differences in population estimates between FSAR and the FES will not significantly alter the favorable conclusions reached by the FES. Population estimates are periodically updated to reflect current census data. The most recent available data indicate that the 10-mile radius EPZ is still a low population area and is expected to continue as such in the future. Furthermore, the site requirements of 10 CFR 100 will still be met. The radiological releases resulting from CR-3 continue to be as low as practicable. Therefore, the additional years of plant operation will not significantly increase the annual public risk from reactor operation.

Environmental monitoring programs at CR-3 were al so reviewed to verify compliance with operating license commitments referenced in the FES. The license for the operation of CR-3 was issued provided that comprehensive monitoring described in the FES be undertaken to monitor the effects of plant operation on aquatic life in the surrounding area. On February 19, 1982, FPC requested deletion of the technical specification requirements for further non-radiological environmental monitoring. On October 12, 1982, final approval was given to modify the technical specifications to be consistent with the National Pollutant Discharge Elimination System Permit issued by the Environmental Protection Agency. This permit is periodically reviewed and modified as needed to assure that the environment surrounding the facility is protected throughout the plant's operating life.

In conclusion, FPC has reviewed the CR-3 FES and has determined that an extension of operating life to the year 2016 will not have an increased impact on the environment.

l OCCUPATIONAL EXPOSURE IMPACTS 4

FPC has also considered the impact on occupational radiation exposures for the l additional years of operation from 2008 to 2016 for CR-3. Based on nine years of operation to date (1977 through 1985) and other considerations, the additional operation of CR-3 is expected to result in no more than an average of 250 person-rem per year. The dose reduction / benefits from the ALARA program are

d 3F0286-01 expected to offset increases due to plant age and higher dose rates. CR-3's average dose for operation to date is considerably below the current PWR average and represents no undue risk to the plant staff.

ECONOMIC ASSESSMENT Operation of the CR-3 plant beyond its current operating license period will be a considerable financial benefit to the customers served by Florida Power Corporation. The CR-3 plant currently provides approximately 30% of the electrical power generated by Florida Power Corporation. Replacement of CR-3 plant generation at the present retirement date is currently projected to cost about $210 million (in 1985 dollars) over the eight years that an extension of the license would give. This cost difference includes deferral of the capital cost of the replacement generating facility.

CONCLUSIONS In conclusion, FPC reviews of pl ant systems, equipment selection and applications, environmental qualification, and the assessment of the NSSS scope of supply by the vendor indicate that a 40 year plant operational lifetime creates no significant safety hazard. Additionally, the evaluation of population growth trends and the CR-3 FES indicates that an extended CR-3 operating life will not have an increased impact on FES conclusions.

SHOLLY EVALUATION OF REQUEST:

FPC proposes that this amendment does not involve a significant hazards consideration. The extension will not modify any operating parameters and restrictions except to allow continued operation for a longer period of time.

This is consistent with current regulatory practice under the requirements of 10 CFR 50.51. Based on the evaluations on the preceding pages, FPC finds this amendment will not:

1. Involve a significant increase in the probability or consequence of an accident previously evaluated because no operational restrictions are modified by changing the duration of the license.

2. Create the possibility of a new or different kind of accider.t from any accident previously evaluated because the proposed change introduces no new mode of plant operation nor does it require physical modification to the plant.

3. Involve a significant reduction in the margin of safety. Any reduction in the margin of safety will be maintained within acceptable bounds by continued implementation of the referenced ongoing programs (Qualification Maintenance Program, RV Materials Surveillance Program, environmental monitoring, etc.). These programs are designed to assure no significant reduction in the associated margin (s) of safety.

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