ML20070H318

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Application to Amend License DPR-40,allowing Operation of Plant at Nominal Reactor Core Power Level of 1,500 Mwt
ML20070H318
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 12/21/1982
From: William Jones
OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20070H307 List:
References
NUDOCS 8212230326
Download: ML20070H318 (5)


Text

e BEFORE THE UNITED STATES NUCLEAR REGULATORY COMIISSION In the Matter of )

OMAHA PUBLIC POWER DISTRICT Docket No. 50-285 (FortCalhounStation, Unit No.1)

APPLICATION FOR AMENDMENT OF OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U. S. Nuclear Regulatory Commission ("the Commission"), Omaha Public Power District, holder of Facility Operating License No. DPR-40, herewith requests that Part 3.A. of Page 4 to that License be amended to allow operation of the Fort Calhoun Station at a nominal reactor core power level of 1500 megawatts thermal, where this power level is defined to be a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> average power level.

The proposed changes to Operating License DPR-40 are set forth in Attachment A to this Application. A discussion, which demonstrates that the proposed changes do not involve significant hazards considerations, is appended in Attachment B. The proposed Amendment is deemed to be Class III Amendment, within the meaning of Section 170.22 of the regulations of the U. S. Nuclear Regulatory Commission. Accordingly, a check for the appropriate fee, $4,000.00, accompanies this Application. Ju:tifi-cation for classification of the Amendment pursuant to 10 CFR 5170.22 is included in Attachment C to this Application. The proposed changes in specifications would not authorize any change in the types or any increase in the amounts of effluents.

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WHEREFORE, Applicant respectfully requests that Part 3.A. of Page 4 to facility Operating License No. DPR-40 be amended in the form attached hereto as Attachment A. Commission review and approval of this amendment application is requested prior to March 15, 1983.

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OMAHA PUBLIC POWER DISTRICT By  ; _ ((b W. C. Jones Divisio'n Manager Production Operations l

Subscribed and sworn to before me this f/c/ day of December, 1982.

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A. Maximum Power Level Omaha Public Power District is nuthorized to operate the Fort Calboun Station, Ur.it 1, at a steady state reactor core power level of 1500 megawatts thermal, where the steady state reactor core power level is defined to be a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> average power level. The thermal power level during steady state and con-trolled transients shall not exceed 1505 megawatts thermal.

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 65, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

C. Security Plan The licensee shall maintain in effect and fully implement all provisions of the Commission-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p). The approved security plan consists of proprietary documents, collectively titled, " Fort Calhoun Station Unit No. 1, Site Security Plan," dated April 7, 1978, with Revision No. I dated July 31, 1978.

D. Safeguards Contingency Plan The licensee shall fully implement and maintain in effect all provisions of the Commission-approved Safeguards Contingency Plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p). The approved Contingency Plan consists of documeats withheld from public disclosure pursuant to 10 CFR 2.790(d) and is identified as " Fort Calhoun Station Safeguards Contingency Plan" dated March 12, 1979, as revised by pages dated June 18, 1979, July 7, 1979, and October 9, 1980. The Contingency Plan shall be fully implemented, in accordance with 10 CFR 73.40(b), within 30 days of this approval by the Commission.

4. This amended license is effective as of the date of issuance and shall expire at midnight on June 7, 2008.

FOR Tile ATOMIC ENERGY COMMISSION Original signed by A. Giambusso l A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Encicoures:

Appendices A and B - Technical Specifications l Date of Issuance: June 18, 1982 e

ATTACllMENT A 1

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DISCUSSION The safety analyses contained in Section 14 of the Fort Calhoun Station, Unit No. 1,tipdated Safety Analysis Report (USAR) are based on full rated power transients commencing at 102% of 1500 megawatts thermal.

This two percent conservatism has been included in the USAR to conform with the requirements of Regulatory Guide 1.49. The Fort Calhoun Station Technical Specification LSSS's and LCO's that are a function of thermal power include an uncertainty of at least two percent to accommodate a two percent uncertainty in measured thermal power. The Technical Specifications are defined such that the assumptions and uncertainties of the safety analysis are bounded and yet assure that the safety limits are not violated during transients originating at 102% of 1500 megawatts thermal. Therefore, the Fort Calhoun Station Operating License and Technical Specifications are based on a safety analysis which assumes a maximum power level of 1530 megawatts thermal.

The District requests this license change to operate the Fort Calhoun Station at a nominal 100% power level of 1500 megawatts thermal.

Experience at the Fort Calhoun Station indicates that a five megawatt operating band is required to maintain a nominal power level. The District proposes to revise the present maximum power level statement to permit operation at a " nominal" 1500 megawatts thermal. The proposed ,

wording defines a steady state power level as a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> average thermal power level and also defines a maximum power level (1505 megawatts thermal) vhich is not to be exceeded during normal reactor operation.

Operating at the subject power levels is consistent with the assumption i of the Fort Calhoun St :lon USAR and does not constitute an unreviewed safety question.

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ATTACHMENT B i

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JUSTIFICATION FOR FEE CLASSIFICATION The proposed amendment is deemed to be Class III, within the mean-ing of 10 CFR 170.22, in that it involves a single safety concern.

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