ML20137Z509

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Application for Amends to Licenses NPF-35 & NPF-48,changing Tech Specs Listed in Encl Re Steam Generator lo-lo Level Setpoint,Rcs Total Flow Rate,Dnb Parameters,Reactor Trip Sys & Ice Condenser Inlet Doors.Fee Paid
ML20137Z509
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 03/07/1986
From: Tucker H
DUKE POWER CO.
To: Harold Denton, Youngblood B
Office of Nuclear Reactor Regulation
References
NUDOCS 8603130059
Download: ML20137Z509 (4)


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Duxe POWER GOMPANY l'.O. ItoX 33180 CILAH1.OTTE. N.C. 28242 HALH. TUCKER retEPHowe ww e e.e. .,

(to 4 :B7:s-4s:as March 7, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Consnission Washington, D. C. 20555 Attention: Mr. B. J. Youngblood, Project Director PWR Project Directorate No. 4 Re: Catawba Nuclear Station, Unit 2 Docket No. 50-414 Technical Specification Amendment

Dear Mr. Denton:

On February 24, 1986 the NRC issued to Duke Power Company, Facility Operating License No. NPF-48 for Catawba Unit 2. . Issued with the license (

were combined Technical Specifications for both Unit 1 and Unit 2. Prior to issuance of the Unit 2 license and combined Technical Specifications, numerous changes were proposed to the Catawba Unit 1 Specifications.

Several of these changes were reviewed by the Staff and were incorporated into the combined Technical Specifications. Due to schedular constraints and higher priority review items, several were not.

Those Specification changes which were not included, along with the dates of their submittals are listed in the attachment. These changes have been reviewed and are deemed to be applicable to Unit 2. It is therefore requested that these changes be reviewed and approved for inclusion into the combined Catawba Units 1 and 2 Technical Specifications and incorporated into Facility Operating License No. NPF-48 (Unit 2) as well as NPF-35 (Unit 1) .

This request involves an amendment request to the Catawba Units 1 and 2 Technical Specifications. Accordingly, pursuant to 10 CFR 170.21 a check for $150.00 is enclosed.

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Mr. Harold R. Dentcn, Dirsetor March 75, 1986 Page Two Pursuant to 10 CFR 50.91 (b)(1) the appropriate South Carolina State Official is being provided a copy of this amendment request.

Very truly yours, h/ (d Hal B. . Tucker RWO: sib Attachment cc Dr. J. Nelson. Grace, Regional Administrator U. S. Nuclear Regulatory Cosumission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Hayward Shealy, Chief Bureau of Radiological Health South Carolina Department of Health &

Environmental Control 2600 Bull Street Columbia, South Carolina 29201 INFO Records Center Suite 1500 1100 circle 75 Parkway Atlanta, Georgia 30339 American Nuclear Insurers e/o Dottie Sherman, ANI Library The Exchange, Suite 245 270 Farmington Avenue Farmington, CT 06032 M&M Nuclear Consultants 1221 Avenue of the Americas New York, New York 10020 Mr. P. H. Skinner NRC Resident Inspector Catsuba Nuclear Station

, Mr. Harcld R. Denttn, Directer' I March 7, 1986 Page Four 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 Comission this revision to the Catawba Nuclear Station Technical Specifications, Appendix A to License

'Nos. NPF-35 and NPF-48; and that all statements and matters set forth therein are true and correct to the best of his knowledge, i

M /b &

Hal B. Tucker, Vice President l

Subscribed and sworn to before me this 7th day of March, 1986, tu {~ '

Notary Public My Commission Expires: /. 2g / 7 O l

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Attachment Tech. Spec. No.

Submittal Date(s)

(1) 2.2.1, Table 2.2-1 Item 13 and 9/10/85, 11/27/85 and 3/4.3.2, Table 3.3-4 Item 8e 1/7/86 regarding the Steam Generator Low-Low Level Setpoint.

(2) 3/4.2.3, Figure 3.2-3 regarding Reactor 7/31/85, 11/8/85 and Coolant System Total Flowrate. 12/26/85 (3) 3/4.2.5, Table 3.2-1 regarding DNB 8/7/85, 11/8/85 and Parameters. 12/4/85 (4) 3/4.3.1 regarding the WOG WCAP-10271 7/22/85 and 9/11/85 revisions for the Reactor Trip System (5) 3/4.6.5 regarding the surveillance for 8/7/85 and 11/8/85 the Ice Condenser Inlet Doors (6) 3/4.7.13 regarding the Standby Shutdown 8/7/85 and 11/8/85 System (7) Section 6 regarding Administrative 7/31/85, 8/7/85 and controls 11/8/85