ML19322B573

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Forwards Rept, Analysis of Capsule OC1-F from Util Unit 1 Reactor Vessel Matls Surveillance Program, Re Results of Tests on Irradiated Reactor Vessel Matl Specimens Removed Durinng Unit 1 Initial Refueling.W/O Encl
ML19322B573
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 08/29/1975
From: Parker W
DUKE POWER CO.
To: Moseley N
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 7912040600
Download: ML19322B573 (1)


Text

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[) U K l? I'OWI? H COM PANY Powe:u thisui No 422 SouT s Cuuncu STurw.T. Cu Ant.oTTE. N. C. uneae

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August 29, 1975 Wt Opt biot ee t ICLEPMOs t: Anta 704 e

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Mr. Norman C. Moseley, Director U. S. Nuclear Regulatory Commission Suite 818

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230 Peachtree Street, Northwest (Z

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Atlanta, Georgia 30303 C/D -

23

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Re: Oconee Unit 1 A

Docket No. 50-269 O

Dear Mr. Moseley:

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6 Pursuant to Sections 4.2.8 and 6.6.1.6 of the Oconee Nuclear Station Technical Specificatione, please find attached a report entitled

" Analysis of Capsule OCl-F from Duke Power Company Oconee Unit 1 Reactor Vessel Materials Surveillance Program." This report describes the results of tests performed on unirradiated reactor vessel material specimens and on the irradiated reactor vessel material specimens removed during the initial refueling of Oconee Unit 1.

As required by Section 3.1.2.6 of the Oconee Nuclear Station Technical Specifications, appropriate revisions to the pressurization, heatup and cooldown limitations are in preparation and will be submitted to the Commission by October 1, 1975.

The results documented in the attached indicate that the current pres-surization, heatup and cooldown limitations for Oconee Unit 1 are conservative except for heatup at temperatures of approximately 160 F 0

and below. This region of the heatup curve is not entered during normal operation, however, due to fission product decay heat.

Neverthe-less,,these limitations will be incorporated into the appropriate oper,ating procedures fa Oconee Unit 1.

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William O. Parker, Jr.

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Mr. Roger Boyd (10) y

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