ML19332F121

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Forwards YAEC-1710 Yankee Nuclear Power Station Pilot Evaluation Rept for Plant License Renewal, for Review. Methodology & Criteria Based on DOE 891006 Rept
ML19332F121
Person / Time
Site: Yankee Rowe
Issue date: 11/30/1989
From: Papanic G
YANKEE ATOMIC ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19332F122 List:
References
BYR-89-172, NUDOCS 8912130433
Download: ML19332F121 (2)


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$80 Main Street, Bolton, Massachusetts 01740-1398

.Ye.v November 30, 1989 DYR 89-172 United States Nuclear Regulatory Commission Atta: Document Control Desk Washington, DC 20555

References:

(a) License No. DPR-3 (Docket No. 50-29)

(b)

" Methodology to Evaluate Plant. Equipment for License 4

Renewal," Nuclear Management and Resources Council, Inc.,

U.S. Department of Energy /Sandia National Laboratories, October 6, 1989.

4

Subject:

YNPS Pilot Evaluation Report for Plant License Renewal

Dear Sirs:

Transmitted herein for your review is Yankee topical report YAEC-1710, " Yankee Nuclear Power Station Pilot Evaluation Report for Plant License Renewal".

This report'provides the application of a process for evaluating systems, structures, and components for license renewal. The methodology and criteria used are based on Reference (b).

The key objectives of ' the Pilot Evaluation Report are to demonstrate, through a formalized evaluation process, that:

o All systems, structures, and components requiring license renewal evaluation are identified o

Any potentially significant age-related degradation is recognized and properly managed.

As demonstrated in the report, these objectives have been met. Of the total 78 systems and 46 structures at Yankee, 43 systems and 27 structures were determined to require evaluation for license renewal. The potential for significant age-related degradation and the methods of managing degradation were assessed for the pilot systems and structures.

The components evaluated in the Pilot Evaluation Report are all related to the Safety Injection System.

Included are SI fluid system components, SI 160 components, Emergency Electrical Power System components, and the structural components of the Primary Auxiliary Building, Diesel Generator Building, and the Battery Room No. 3 Building.

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8912130433 891130 PDR ADOCK 05000029 P

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United States Nuclear Regulatory Commission November 30, 1989 Page 2 i

The methodology, criteria, and technical justification supporting the evaluation process are provided, as well as, examples of specific assessments, checklists, and other supporting information to allow the NRC Staff to conclude that the process used is both thorough and technically justified.

The Pilot Evaluation Report is a product of the Yankee Lead Plant License Reneual Project which is co-sponsored by Yankee, the U.S. Department of EnerEy, and the Electric Power Research Institute.

An expedited review of the Pilot Evaluation Report is requested because the Pilot Report is the basis for ongoing reviews of other systems and structures.

We trust that you will find the-e'.tachment satisfactory; however, if you have any questions, please contact us.

Very truly yours, i

YANKEE ATOMIC ELECTRIC COMPANY j

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Georg apanic, J.

Senior Project Engineer j

Licensing GP/mts Attachment i

cc:

USNRC Region I USNRC Resident Inspector, YNPS F. M. Akstulewicz, USNRC, NRR F. P. Gillespie, USNRC, NRR D. P. Cleary, USNRC, RES.