ML20207J099

Revised Application for Amends to Licenses NPF-35 & NPF-52, Reflecting Change to Steam Generator Tube Rupture Accident Analysis.Fsar Pages Reflecting Steam Generator Tube Rupture thermal-hydraulic Analysis & Dose Calculations Also Encl

ML20207J099
Person / Time
Site:	Catawba
Issue date:	08/24/1988
From:	Tucker H DUKE POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20207J102	List: ML20207J099 ML20207J106
References
NUDOCS 8808300228
Download: ML20207J099 (2)

Text

.., J .,

II. l Duke kn Cornpany flatit h k PO Bar33198 Vice President Charlotte, N C 28242 Nuclear Mductwn .

(104)3734531 DUKEPOWER August 24, 1988 U. S. Nuclear Reg *latory Consnission Attention: Document Control Desk Washington, D. C. 20555 l

Subject:

Catawba Nuclear Station, Units.1 and 2 Docket Nos. 50-413 and 50-414 License Conditis 16 (Unit 1) and 10 (Unit 2) SGTR Technical Specification Amendment Steam Generator Tube Rupture Analysis

Dear Sir:

This letter contains the Steam Generator Tube Rupture Analysis and a revision to the proposed amendment to the Technical Specifications for Facility Operating License Nos. NPF-35 and NPF-52 for Catawba Units 1 and 2 (the Technical Specificacion amendment was transmitted by my letter of December 4, 1987). This proposa'l is in response to License Conditions 16 (Unit 1) and 10 (Unit 2) concerning the Steam Generator Tube Rupture l Accident analysis. l l

l Attached are proposed changes to the Technical Specifications and also l

} FSAR pages which reflect the Steam Generator Tube Rupture I thermal-hydraulic analysis and dose calculations.

The Technical Specification amendment request has beer, revised from the i December 4, 1987 submittal to reflect a change in M e accident analysis assumptions. Previously, the accident analysis as='uned that three Steam 1 Generator PORVs were operable to alleviate the consequences of a tube rupture. Revised analyses now take credit for having only two PORVs available to mitigate the accident. Therefore, ;a Technical t Specifications need only require that three PORVs be operable assuming a single failure of one PORV.

The No Significant Hazards Analysis provided in the December 4, 1987 and December 11 F87 letters are still applicable to this amendment request. l The attached FSAR pages provide the SGTR analysis and satisfy the conditions specified in the above referenced License Conditions.

By letter dated June 16, 1988, we committed to provide this Technical  !

Specification change and the accompanying SGTR analysis by August 15, 1988. '

8808300228 800024 ~ l L PDR ADOCK 05000413 ~

P PNV, ,

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U. S.-Nuclser Ragulatory Commission August 24, 1988 Page Two Uu apologize for any inconvenience in the slight delay of thic submittal.

This proposal involves a supplement to an amendment request to Catawba's Technical Specifications. Accordingly, pursuant to 10 CFR 170.21 no license fee is required.

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, i- ,

Hal B. Tucker

• a- .

RWOO6.D1/lec '

Attachments xc: Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II l

101 Marietta Street, NW, Suite 2900 l Atlanta, Georgia 30323  :

Mr. Heyward Shealy, Chief - J Bureau of Radiological Health i South Carolina Department of Health &

Environmental Control 2600 Bull Street Columbia, South Carolina 29201 American Nuclear Insurers c/o Dottie Sherman, ANI Library l

] The Exchange, Suite 245 l 270 Farmington Avenue 1 Farmington, CT 06032

, M&M Nuclear Consultants 1221 Avenue of the Americas New York, New York 10020 l

INPO Records Center l' Suite 1500 1100 Circle 75 Parkway 1 Atlanta, Georgia 30339 1

. Mr. P. K. Van Doorn I NRC Resident Inspector I Catawba Nuclear Station

.I

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