ML20149H168

Application for Amends to Licenses NPF-35 & NPF-52,involving Reduction of Required RCS Total Flow from 396,100 Gpm to 387,600 Gpm.Fee Paid

ML20149H168
Person / Time
Site:	Catawba
Issue date:	02/10/1988
From:	Tucker H DUKE POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20149H172	List: ML20149H168 ML20149H174
References
NUDOCS 8802190160
Download: ML20149H168 (4)

Text

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e DUKE POWER Godm.txy ,

P.O. HOX 331HD i cnAntorTE. N.C. 28242

!!ALB. TUCKER trixenovz ut a persierut (704) 373 4SO4 uneas enoot rtme February 10, 1988 I

I U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555

Subject:

Catawba Nuclear Station, Units 1 and 2 Docket Nos. #50-413 and 50-414 {

Technical Sper:ification Amendment  !

Reduction of Required Reactor Coolant System Flow

Dear Sir:

This letter contains a proposed amendment to the Technical Specifications for .

Facility Operating License Nos. NPF-35 and NPF-52 for Catawba Units 1 and 2.

The request involves reducing the required Reactor Coolant System (RCS) total i[

flow from 396,100 gpm to 387,600 gpm.

It is requested that this change be handled as an exigent Technical Specification change pursuant to 10 CFR 50.91(a)(6). Absent this change Catawba Unit 1 is limited to 98% of its licensed power level.

This situation has occurred on Catawba Unit 1 after startup from the refueling outage which ended in late December, 1987. Flow rate measurements have been taken and have indicated that the total RCS flow is averaging between 100.1%

and 99.9% of the total required flow. During the previous cycle, and following startup after the outage, total RCS flow was consistent at slightly greater than 100% of the required flow and the unit was able to run at 100% power. Following refueling, on January 13, 1988, a precision heat balance was conducted pursuant to Technical Specification surveillance requirement 4.2.3.5. This test resulted in the lowering of the RCS elbow tar flow coefficients which are used to convert albow tap pressure drops to flow rates. Upon insertion of the new constants into the operator aid computer, indicated RCS flow decreased. Therefore this condition did not exist until recently and this application is being submitted in a timely manner.

The attachment contains the proposed change and a discussion of the justification and a No Significant Hazards analysis. The analysis is included pursuant to 10 CFR 50.91 and it has been concluded that the proposed amendment does not involve significant hazards considerations.

This proposal involves one amendment request to Catawba'c Technical Specifications. Accordingly, pursuant to 10 CFR 170.21 a check for $150.00 is enclosed.

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i U. S. Nuclear Regulatory Commission February 10, 1988 Page Two 1

t Pu'rsuant to 10 CFR 50.91 (b) (1) the appropriate South Carolina State l Official is being provided a copy of this amendment request.

Very Truly yours i

/b< & ,

Hal B. Tucker RWO/1336/sbn Attachmente xc: Dr. J. Nelson Grace, Regional Administrator 1

U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 i Mr. Heyward Shealy, Chief ,

Bureau of Radiological Health i '

South Carolina Department of Haalth &

Environmental Control 2600 Bull Street Columbia, South Carolina 29201 American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange, Suite 245 1 270 Farmington Avenue n Farmington, CT 06032 M&M Nuclear Consultants i 1221 Avenue of the Americas New York, New York 10020 INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30339 Mr. P. K. Van Doorn i NRC Resident Inspector Catawba Nuclear Station l

Y U. S. Nuclear Regulatory Commission February 10, 1988 Page Three HAL B. TUCKER, being duly sworn, states that he is 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 Catawba Nuclear Station Technical Specifications, Appendix A to License No.

NPF-35 and NPF-52; and that all statements and matters set forth therein are true and correct to the best of his knowledge.

A F fs t k ' w 4ial B. Tucker, Vice President Subscribed and sworn to before ne this 10th day of February, 1988.

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l ATTACHMENT 1 4

Technical Specification Changes l

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