ML20195C508

Submits Summary of 990527 Telcon Between J Rajan of NRC & K Korcz of Niagara Mohawk Power Co Re Util Requesting NRC Approval of Proposed Mod to Upper Spring Assembly of Four Core Shroud Tie Rods

ML20195C508
Person / Time
Site:	Nine Mile Point
Issue date:	06/03/1999
From:	Hood D NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
TAC-MA5433, NUDOCS 9906080200
Download: ML20195C508 (5)

Text

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y n p-fU 4- UNITED STATES g- ,g NUCLEAR REGULATORY COMMISSION c WASHINGTON. D.C. 20555-4001 g . . . . . p' June 3, 1999 LICENSEE: Niagara Mohawk Power Corporation FACILITY: Nine Mile Point Nuclear Station, Unit No.1

SUMMARY

OF TELEPHONE CONVERSATION OF MAY 27,1999, REGARDING MODIFICATION OF TIE ROD ASSEMBLIES (TAC NO. MA5433)

On May 27,1999, Mr. Jai Rajan of the NRC staff called Mr. Ken Korcz of Niagara Mohawk Power Company (NMPC) to discuss NMPC's letter of May 21,1999, that requests NRC approval of a proposed modification to the upper spring assembly of the four core shroud tie rods. Mr. Rajan asked four questions and received the following responses:

Question 1:

With regards to Enclosure 3 titled "Nine Mile Point 1 Shroud Repair Upper Lateral Stabilizer Modification Stress Analysis," describe the modeling used in General Electric's (G E's) calculations.

Response 1:

The calculations were performed using strength of material equations, thermal and mechanical properties, and allowable Sm values per the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code).

Question 2:

What Computer code was used for GE's calculations?

Resoonse 2:

Analysis was performed using EXCEL spread sheets and MathCad inputting the theory of elasticity / strength of materials equations as well as material properties.

Question 3:

How was the analysis performed by GE in the calculations?

Response 3:

The analysis includes consideration of thermal stresses for normal and upset conditior,s, other prying loads on the cap screws from the wedge contact force with the vessel and preload due to torquing. Bearing and shear stresses, and intergranular stress corrosion cracking margins were also evaluated. The stresses in the cap screws, nut plate, and the upper spring were evaluated and shown to be acceptable. The calculations were performed using theory of elasticity / strength of materials equations.

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June 3, 1999 Ouestion 4:

How was the analysis verified and benchmarked?

Response 4:

The results were verified by individual design review and comparisons with hand calculations. '

/ Original signed by:

Darl S. Hood, Sr. Project Manager, Section 1 ,

Project Directorate I _ .

Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-220 cc: See next page DISTRIBUTION:

• Docket File ,

• PUBLIC PDl-1 R/F .

S. Bajwa S. Little l

~ J. Rajan K. Manoly '  :

E. imbro W. Koo

D. Hood T. Tschlitz l OGC ACRS M. Oprendek DOCUMENT NAME: G:\PDI-1\NMP1\TELSUM1.WPD To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy -

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DATE 06/ 3 /99 06/ 3 /99 06/ D /99 06/ *1 /99 Official Record Copy

e 1 June 3,'1999 Question 4:

How was the analysis verified and benchmarked?

. Response 4:

The results were verified by individual design review and comparisons with hand calculations.

Original signed by:

Darl S. Hood, Sr. Project Manager, Section 1 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-220 cc: See next page DISTRIBUTION:

Docket File l

PUBLIC PDI-1 R/F S. Bajwa S. Little i J. Rajan K. Manoly E. Imbro W. Koo -

D. Hood T. Tschlitz OGC ACRS M. Oprendek .

DOCUMENT NAME: G:\PDl-1\NMP1\TELSUM1.WPD Ta receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy 0FFICE- PDI-1:PM lE PDI1:LA()G _ PDI-)r$C / [ EMCB r-- #Al l l NAME DHood/rsl J f /-f SLittl 7 SBaWL P Elmbro DATE 06/ ~f /99 - 06/ 3 /99 06/ b /9'9 ,

06/ 3 /99 Official Record Copy

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.y .

r .. Question 4:

How was the analysis verified and benchmarked? -

Response' 4:

The results were verified by individual design review and comparisons with hand calculations.

L/hihn/

Darl S. Hood, Sr. Project Manager, Section 1

- Project Directorate I

. Division of Licensing Project Management

. Office of Nuclear Reactor Regulation

' Docket No. 50-220 cc: See next page f

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, Nine Mile Point Nuclear Station Unit No.1 Mr. John H. Mueller - Resident inspector l Chief Nuclear Officer U.S. Nuclear Regulatory Commission Niagara Mohawk Power Corporation P.O. Box 126 Nine Mile Point Nuclear Station Lycoming, NY 13093 -

Operations Building, Second Floor P.O. Box 63 . Charles Donaldson, Esquire Lycoming, NY 13093 Assistant Attorney General

. New York Department of Law Regional Administrator, Region i 120 Broadway U.S. Nuclear Regulatory Commission New York, NY 10271 475 Allendale Road King of Prussia, PA 19406 Mr. Paul D. Eddy State of New York Mark J. Wetterhahn, Esquire Department of Public Service Winston & Strawn Power Division, System Operations 1400 L Street, NW 3 Empire State Plaza Washington, DC 20005 3502 Albany, NY 12223 Supervisor Mr. F. William Valentino, President Town of Scriba New York State Energy, Research, Route 8, Box 382 and Development Authority Oswego, NY 13126 Corporate Plaza West 286 Washington Avenue Extension

~ Gary D. Wilson, Esquire Albany, NY 12203-6399 Niagara Mohawk Power Corporation 300 Erie Boulevard West Syracuse, NY 13202

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