ML20023E220

Application for Amend to Licenses NPF-9 & NPF-7,extending Time Limit for Operation W/Reactor Coolant Flow Greater than 395,850 Gpm & Adding Stricter Limit for Nuclear Enthalpy Rise Hot Channel Factor During Operation

ML20023E220
Person / Time
Site:	McGuire, Mcguire
Issue date:	06/09/1983
From:	Thies A DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
References
TAC-49164, NUDOCS 8306150177
Download: ML20023E220 (5)

Text

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DUKE POWER GOMPANY Powan BmLuixo, Box 30180, GiuRLOTTE,N. G. 2024u A. C. T HI ES (704) 373-4249 cxccutivt vecc PRcssocur POwcm OPcRATIONS June 9, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: McGuire Nuclear Station Docket Nos. 50-369, 50-370

Dear Mr. Denton:

A proposed amendment to McGuire Units 1 and 2 License Nos. NPF-9 and NPF-17 is attached. The proposed amendment shown in Attachment I would extend the time limit for operation with reactor coolant flow greater than 395,850 gpm andaddastricterlimitfortheNuclearEnthalpyRiseHotChannelFactor(FfH) during operation under this condition. Attachment 2 contains justification for the proposed amendment. As required by 10 CFR 50.91, Attachment 3 provides an analysis that supports a "no significant hazards" determination. This change is proposed to be effective upon issuance and expire either on August 10, 1983 or upon issuance of the pending change to this same technical specification.

Pursuant to 10 CFR 170.22, a check for $4,400 is enclosed for these Class III and Class 1 amendments for McGuire Units 1 and 2.

Very truly yours, o A. C. Thies REH:j fw Attachments cc: Mr. James P. O'Reilly, Regional Administrator Dayne H. Brown, Chief U. S. Nuclear Regulatory Commission Radiation Protection Branch Region II Div. of Facility Services 101 Marietta Street, NW, Suite 2900 Dept. of Human Resources Atlanta, Georgia 30303 P. O. Box 12200 Raleigh, NC 27605 Mr. W. T. Orders NRC Resident Inspector McGuire Nuclear Station //

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8306150177 830609 PDR ADOCK 05000369 P PDR

1 Harold R. Denton June 9, 1983 Page 2 A. C. THIES, being duly sworn, states that he is Executive Vice President of Duke Power Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission this revision to the McGuire Nuclear Station Technical Specifications, Appendix A to License Nos..NPF-9 and NPF-17; and that all statements and matters set forth thereie are true and correct to the best of his knowledge.

A. C. Thies, Executive Vice President Subscribed and sworn to before me this 9th day of June, 1983.

- b Notary Public My Commission Expires:

September 20, 1984

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m FIGURE 3.2-3 RCS TOTAL FLOWRATE VERSUSi R AND R 2 - FOUR LOOPS IN OPERATION

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)Y Attachment 2 Justification and Safety Analysis Technical Specification Figure 3.2-3 is intended to specify the allowable combination of Reactor Coolant System flow, core enthalpy rise hot channel factor (F5H)andreactorpower. Currently the specified reactor coolant flow at full power is 3.5% above the thermal design flow (390,000 gpm) in order to account for a flow measurement uncertainty of 3.5%. With a speci-fied flow of 395,850 gpm, as allowed by the footnote to Figure 3.2-3, the flow margin above the thermal flow is 1.5%. The remaining 2% flow margin necessary to accomodate the 3.5% flow measurement uncertainty can be com-pensatedforifitisconfirmedthatF$ghasanequivalentorgreatermargin.

-Since 1.8% flow margin is equivalent to1.0%FfNmargin,themargininF$H necessary to accomodate a 2% margin in flow is 1.1%. Therefore, limitingFfH to 1.46 which is 2% below the specified value of 1.49 ensures more than adequate overall margin for full power operation with a total RCS flow of-395,850 gpm.

It is concluded that the proposed change in Technical Specification Figure 3.2-3 involves more margin to thermal limits than currently required.

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. ,e Attachment 3 Determination of No Significant Hazards Considerations The following is an analysis of the proposed amendments to License Nos. NPF-9 and NPF-17 for McGuire Units 1 and 2. The proposed amendments would change the footnote to Technical Specification Figure 3.2-3 to add an additional restriction on the Nuclear Enthalpy Rise Hot Channel Factor (F{H) for operation above 90%. power with greater than 101.5% of Thermal Design Flow. This analysis is performed according to the standards of 10 CFR 50.92.

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TheproposedamendmentswouldreducethemaximumFNH by 2% to 1.46. Because this change is more restrictive and would involve operation in a more safe condition than is already allowed .and because the safety margins in the FSAR accident analyses are not affected, operation under this condition would clearly not:

(1) Involve a significant lacrease in the probability or consequences of an accident previously. evaluated; or

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(2) ' Create the possibility of a new or different kind of accident from any accident previously. evaluated; or (3) Involve'a significant reduction in a margin of safety.

.Therefore, the. proposed amendments do not involve significant hazards considera-tions.

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