ML20028C743

From kanterella
Jump to navigation Jump to search

Advises That Regeneration of Time History Thermal Hydraulic Loads Testing Completed by Westinghouse,Per 820701 Submittal Re NUREG-0737,Item II.D.1.Final Sys Qualification Rept Will Be Completed by 830611
ML20028C743
Person / Time
Site: Beaver Valley
Issue date: 01/05/1983
From: Carey J
DUQUESNE LIGHT CO.
To: Varga S
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM TAC-44562, NUDOCS 8301140057
Download: ML20028C743 (2)


Text

.

g 3

'Af Duquesneu@t 1.,. -. -.s -

Nuclear Division.

Qf[ghrt, PA 150U4004 January 5, 1983 Dire,ctor of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn:

Mr. Steven A. Varga, Chief

~

Operating Reactors Branch No.1 Division of Licensing Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 NUREG-0737, item II.D.1:

Pressurizer Safety and Relief Line Piping and Support Evaluation.

Gentlemen:

Our submittal of July 1, 1982, addressing NUREG-0737, item II.D.1 contained an interim report prepared by the Westinghouse Electric Corporation entitled Pressurizer Safety and Relief Line Piping and Support Evaluation. This report stated that the regeneration of time history thermal hydraulic loads subsequent to the Electric Power Research Institute (EPRI) testing is currently underway, and that upon completion of the thermal hydraulic models, analyses will be performed and the impact of the new results on the previous analyses will be evaluated. From this evaluation, the determination if all pertinent stress intensities are within the allowable limits can be made and if system modifications would be needed. Our July submittal indicated a report would be submitted to the Staff at this time in support of the above evaluations.

This work was recently presented to our Mechanical Engineering Department by Westinghouse for our review. As a result of this review, a second iteration of the thermal hydraulic evaluation and the structural '

analysis has been initiated.

Section 5 of the Westinghouse interim report states a final system qualification report will be prepared.

It is now expected that this report will be completed and ready for submittal to the NRC Staff on or about the time Beaver Valley, Unit 1 begins the next refueling outage, currently scheduled to begin June 11, 1983.

If system modifications are necessary, they will be discussed at that time.

If you have any questicas, please contact my office.

Very truly yours, j

. J. Carey 8301140057 830105 DR ADOCK 05000333 p

PDR QU

h' 4

k-M i

~

Beaver. Valley: Power-Station. Unit Ns.1

-1 Docket No..;50-334,. License'No. DPR-86

'NUREG-0737, item II.D.1:-

Pressurizer Safety and Relief -Line Piping and Support-Evaluation.

Page 2

cc:

Mr. W. M. Troskoski, Resident Inpsector1 U. S. -Nuclear Regulatory Commission

~

Beaver Valley Power Station

- Shippingport, PA - 15077 U. S. Nuclear' Regulatory Commission c/o Document Management Branch Washington, DC 20555 1

4 i

b 1

1 f

k i

9

_r r-

-,-,,-..g.,r..

..,,4._

.p.

,,, -,