ML20246F215

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Advises That Question 4 from Kn Jabbour Re Performance Testing of Relief & Safety Valves (NUREG-0737, Item II.D.1) Will Be Provided No Later than 900531,per Vendor Thermal Hydraulic Analysis
ML20246F215
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 08/16/1989
From: Tucker H
DUKE POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8908300207
Download: ML20246F215 (1)


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DuxE POWER COMPANY U-L P.O. BOX 33189 I

E CHARIDTrE, N.O. 28242 iHALH. TUCKER.

TELEPHONE s

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'(704) 373-4533 mma. man s'monmmon i.l-4 August'16. 1989 K

Document Control Desk l

U. S. Nuclear Regulatory Commission Washington,'D.

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20555

Subject:

Catawba Nuclear. Station, Units.l'and.2 Docket Nos. 50-413'and 50-414, Performance Testing of Relief and Safety Valves Gentlemen:

Dr.

K.~ N. Jabbour's letter dated October 18.-1988 transmitted a request for additional information regarding.the performance testing of-relief and-safety valves (NUREG-0737,- Item II.D.1). These questions were based on my -

e submittals dated April-29,'May 31,.and June 14, 1988. Responses to Questioni Nos. 1; 3, and 5 were transmitted to the NRC,per my March 16, 1989 letter to the Document Control Desk. The response to-Question No.12 was submitted to the ENRC per my August 4, 1989 letter to the Document Control Desk. My August 4, 1989 letter also indicated'that we were preparing a plan of action regarding Question'No. 4 and would provide the details by August 16, 1989.

Please be advised that we have chosen to contract a vendor to provide the necessary' design data to evaluate Question No. 4. The vendor will perform reanalysis of the thermal hydraulic analysis of the Pressurizer Safety / Relief-Valve discharge piping for Catawba Nuclear Station. The analysis will be performed using the EPRI recommended input parameters noted in Question No. 4.

The'results of the reanalysis will be reviewed for any significant. impact.to

.the structural analysis.

The vendor.should complete the analysis and supply Duke Power with a report on approximately January 19, 1990. If the structural analysis does not require reanalysis, I will answer Question No. 4 on March 16, 1990. If the structural analysis needs to be revised, I will answer Question No. 4 on May 31, 1990.

'Should the values provided with my August 4, 1989 response to Question No. 2 increase significantly, I will provide the revised data along with my response to Question No. 4.

Very truly yours, f

y H. B. Tucker JGT/4/IID1R1

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