ML20112B358

From kanterella
Jump to navigation Jump to search
Affidavit of Rf Burski Supporting Conclusion That Cracks Do Not Significantly Affect Structural Adequacy of Facility Basemat.Certificate of Svc Encl.Related Correspondence
ML20112B358
Person / Time
Site: Waterford Entergy icon.png
Issue date: 01/03/1985
From: Burski R
LOUISIANA POWER & LIGHT CO.
To:
Shared Package
ML20112B305 List:
References
OL, NUDOCS 8501100343
Download: ML20112B358 (7)


Text

._

s-REL/sTED COngCNDM January 3, 1985 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION -

s in Before the Atomic Safety and Licensing Appeal Board CZqn-

.L,n In the Matter of )

LOUISIANA POWER & LIGHT COMPANY ) Docket No. 50-38 O N0 :27

)

(Waterford Steam Electric Station, ) 09Ct - , ..

Unit 3) D

) QgNEi.e AFFIDAVIT OF RAYMOND F. BURSKI, JR.

The undersigned, being duly sworn, deposes and says:

My name is Raymond F. Burski, Jr. I am Engineering and Nuclear Safety Manager for Louisiana Power & Light Company. In this position I am responsible for engineering and independent review activities. A copy of my professional qualifications is attached.

On October 19, 1984 in a letter to Mr. J. M. Cain, President and Chief Executive Officer (LP&L) from Dennis M. Crutchfield, Assistant Director for Safety Assessment (NRC) , LP&L was requested to provide additional information to the NRC staff as a result of several questions raised by the Atomic Safety and Licensing Appeal Board in its October 2, 1984 Memorandum and Order, ALAB-

~786. Specifically, I was requested to provide information to respond to the following NRC Staff question: " Additionally as noted on page 14 of the same document, a discrepancy exists in Harstead Report No. 8304-3. Appendix II of this report indicates Cadweld No. 2W120 is located in Pour 16, whereas, according to G

A K obb PDR

- -_ __. - __ _ _ __ __ _ m

1 Appendix I Pour 16 contains no Cadwelds. Please provide the staff with your explanation of this error and your assurance that it is not indicative of a reliability problem with data supplied to Harstead by LP&L contractors."

To respond to the NRC staff's question, a review was per-formed of the data packages utilized by Harstead in preparing P., art No. 8304-3,-specifically to identify any discrepancies in Appendices I and II, and to respond to the discrepancy noted I

by the ASLAB.

A review of the cadweld data, utilized by HEA to generate Report No. 8304-3 dated January 9, 1984, was performed, and the data for cadweld 2W120 indicates that the cadweld was a produc-

, . tion splice test from block No. 1 of the common foundation mat.

As such, Appendix I of the HEA Report is correct as there were no mechanical splices in block 16.

Additionally, a review of the data in Appendices I and II of the HEA determined of there were other errors. The following is a summary of the review:

Appendix I Sheet 5 - The date for block 14 A should be 4/23/76 not 4/23/79 l Appendix II Sheet 1 - The tensile strength for 3W119 should be 94,150 not 94,750 l Sheet 2 - The tensilo strength for 7W122 should be 95,250 not 92,250

) Sheet 2 - The date for 4W36 should be 11/13/75 not 11/12/75.

l I

I l

FE.

These errors appear to be typographical errors on the part of HEA in transposing data in the preparation of their report

~

and are not indicative of a problem with inconsistent or unre-liable data in the records packages.

In addition HEA was contacted to determine what effect, if any of the above discrepancies would have on their report. HEA indicated that the minor deficiencies noted would have no effect on the conclusion contained in their report. The overall effect of the tensile strength deficiencies would be to increase the average tensile strength on sheet 4 of Appendix II from 95,401 to 95,430.

s //LJ d YMOND F.' BURSKI,/8R.

Subscribed and sworn to before me this 3r4 day of January, 1985.

A rWL l

~SOTARY PUliLIC My Commission Expires: d-30'fd c

~'

()l ' '

r.

I WSES-FSAR-UNIT-3 Raymond F. Burski, Jr.

6 ENGINEERING AND NUCLEAR SAFETY MANAGER-Responsible for management of the Engineering Discipline sections and the Nuclear _ Safety section to provide engineering support of Waterford 3 design

. modifications and independent reviews of plant activities.

Educational Background Professional Experience

  • ~ University of Dayton Duquesne Light Company B.S. Mechanical Engineering.(1969) Engineer (1970-1973)

Environmental Testing Basic Simulator Courses Procedure Preparation

' Westinghouse-Zion (1 week) Plant Availability Testing

' Combustion Engineering-Windsor Maintenance Support (1 week) Mechanical Naintenance Engineer

~

(1973-1975)

Numerous Company Sponsored Preventative & Corrective courses and seminars Maintenance Spare Parts. Procurement Procedure Preparation Senior Engineer.(1975-1979)

Design Modification Support-l Plant Engineering Supervision Industrial Safety Safety Committee Member Senior Compliance Engineer (1979-1980)

NRC Regional Regulatory Activities Senior. Licensing Engineer (1980-1981)

NRC Headquarters Regulatory Activities Louisiana Power and Light Company Onsite Safety Review Supervisor (1981-1983)-

Engineering and Nuclear Safety

, Manager (1983-Present)

_ _ __ . _f

p tfdED COf M'"

\

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Appeal Board In the Matter of )

)

LOUISIANA POWER & LIGHT COM"ANY ) Docket No. 50-382 OL

)

(Waterford Steam Electric Station, )

Unit 3) )

CERTIFICATE OF SERVICE This is to certify that copies of the foregoing " Applicant's Reply to NRC Staff's December 17, 1984 Basemat Submittal" were served, by deposit in the United States mail, first class, postage prepaid, to all those on the attached Service List, this 7th day of January, 1985.

'I

~ b BruC3 W. Churchill, P.C.

Dated: January 7, 1985 r

i t.

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Appeal Board In the Matter of- )

)

' LOUISIANA POWER & LIGHT COMPANY ) Docket No. 50-382

)

(Waterford Steam Electric )

Station, Unit 3) )

SERVICE LIST Christine N. Kohl Sheldon J. Wolfe Administrative Judge Administrative Judge chairman, Atomic Safety and Chairman, Atomic Safety and Licensing Appeal Board Licensing Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Washington, D.C. 20555 W. Reed Johnson Harry Foreman Administrative Judge Administrative Judge Atomic Safety and Licensing Atomic Safety and Licencing Appeal Board Board U.S. Nuclear Regulatory Commission Director, Center for Population Washington, D.C. 20555 Studies Box 395, Mayo Howard A. Wilber University of Minnesota Administrative Judge Minneapolis, MN 55455 Atomic Safety and Licensing Appeal Board Walter H. Jordan U.S. Nuclear Regulatory Commission Administrative Judge Washington, D.C. 20555 Atomic Safety and Licensing Board Sherwin E. Turk, Esquire 881 West Outer Drive Office of the Executive Oak Ridge, TN 37830 Legal Director U.S. Nuclear Regulatory Commission Docketing & Service Section (3)

Washington, D.C. 20555 office of the Secretary U.S. Nuclear Regulatory Commission Atomic Safety and Licensing Washington, D.C. 20555 Appeal Board Panel U.S. Nuclear Regulatory Commission Atomic Safety _and Licensing Washington, D.C. 20555 Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 1 <

l U LP&L g SOrvic3 Lict-ASLAB Page Two Mr. Gary Groesch 2257 Bayou Road New Orleans, LA 70119 Carola H. Burstein, Esq. -

445 Walnut Street New Orleans, LA 70118 Lynne Bernabei, Esq.

Government Accountability Project 1555 Connecticut Avenue, N.W.

Suite 202 Washington, DC 20009 M

e e

O