ML17059B336

Summary of 961023 Telcon Re Results of Audit of Certain Calculations by M Hartzman of NRC Structural Engineering Branch Re Plant

ML17059B336
Person / Time
Site:	Nine Mile Point
Issue date:	11/13/1996
From:	Hood D NRC (Affiliation Not Assigned)
To:	NRC
References
TAC-M94858, NUDOCS 9611180162
Download: ML17059B336 (8)

Text

R~00

,+~

~o 0O cA0

+~

~O

++*++

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON( D C 2055&4001 November 13, 1996 go ->Z-O LICENSEE:

Niagara Mohawk Power Corporation FACILITY:

Nine Mile Point Nuclear Station Unit No.

1

SUMMARY

OF TELEPHONE CONVERSATION OF OCTOBER 23,

1996, ON REACTOR AND TURBINE BUILDING BLOWOUT PANELS (TAC NO. M94858)

On October 23, 1996, the NRC staff discussed, via telephone, the results of an audit of certain calculations by Hr. H. Hartzman of the NRC's Structural Engineering Branch regarding the Nine Mile Point, Unit 1, Reactor and Turbine Building relief (blowout) panels.

Participants for the NRC staff were Mr.

M. Hartzman and Ms. H. Pastis.

Participants for the licensee included Messrs.

A. Zalnik, W. Yager, and Mohamed Ali.

Hr. Hartzman reviewed the calculations provided by Niagara Mohawk Power Corporation (NHPC) during a recent audit.

The calculations are for the blowout panel impacting the roof of the Turbine Building above the condensate storage tanks.

These calculations are an enclosure to the "Trip Report Regarding August 20, 1996, Audit of Reactor and Turbine Building Blowout Panel Calculations" dated October 7, 1996; The calculations consist of two parts:

a primary calculation by NHPC and a

confirmatory calculation by Sargent and Lundy (S&L).

The S&L analysis is based on an energy

approach, similar to that used by Bechtel in analyzing the impact of tornado missiles.

Hr. Hartzman selected the confirmatory analysis as the basis for his audit.

S&L determined that the maximum ductility in two impacted roof beams was 9.2, which is less than NHPC's allowable value of 10.

Using the same

model, Hr. Hartzman calculated a ductility factor of 17.6, which is considerably larger than the S&L value and exceeds the NHPC allowable ductility.

The reason for this discrepancy is that there is a fundamental error in the S&L

method, having to do with the calculation of the impact velocity and the kinetic energy of the falling panel.

Hr. Hartzman advised NHPC that the S&L analysis, and by implication the NHPC

analysis, are not acceptable.

The maximum expected deflection of the impacted roof beams is about 1.5 feet.

The height of the roof above the tanks is about 9 feet.

Mr. Hartzman does not believe there is an immediate safety issue

here, but NHPC/S&L should take appropriate measures to show that the ductility is really below allowable

values, or else modify the roof.

9biii80ib2 9biiiS PDR ADQCK 05000220 P

. PDR

r1 P

( ~ %

4 I

'I 1

,~a 1I

Mr. Zalnik stated that NMPC would discuss the NRC's audit conclusions with S&L, and further advise the NRC as to its future course of action.

Sincerely,

/s/

Docket No. 50-220 cc:

See next page DISTRIBUTION:

Docket File PUBLIC PDI-1 Reading SVarga JZwolinski SBajwa SLittle DHood OGC ACRS CCowgill, RI MHartzman DJeng RWessman it II 4

II ili Darl S.

Hood, Senior Project Manager Project Directorate I-1'ivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation It

(

7

((

tli li II i

Ii 1(

p it

'W 4

j

\\

DOCUMENT NAME:

G: iNMPliNMP19485.TEL To receive a copy of this document, indicate in the box:

"C" = Copy without attachment enclosure "E" - Co y with attachment enclosure "N" = No co y OFFICE PM:PDI-1 E

LA:PDI-1 D:

I-1 NAME DNood/rsl S

t.

SLittle 11/

/96 DATE 11/ ~/96 11/I'96 11 6

0 Icia Recor Copy 11/

/96

/I I

yr

't V

I I

),

J(

n

'1 ja J

i1 1 I

/

sl

Mr. Zalnik stated that NMPC would discuss the NRC's audit conclusions with S&L, and further advise the NRC as to its future course of action.

Sincerely, Docket No. 50-220 cc:

See next page Darl S.

Hood, Senior Project Manager Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

B. Ralph Sylvia Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit No.

1 CC:

Mr. Richard B. Abbott Vice President and General Manager Nuclear Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Hr. Hartin J.

McCormick, Jr.

Vice President Nuclear Safety Assessment and Support Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Ms. Denise J. Wolniak Manager Licensing Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Hr. Kim A. Dahlberg General Manager Projects Niagara Mohawk Power Corporation Nine Nile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Hr. Norman L. Rademacher Plant Manager, Unit 1

Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O.

Box 126

Lycoming, NY 13093 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Hr. Paul D.

Eddy State of New York Department of Public Service Power Division, System Operations 3 Empire State Plaza

Albany, NY 12223 Hr.

F. William Valentino, 'President New York State

Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension

Albany, NY 12203-6399 Hark J. Wetterhahn, Esquire Winston 8 Strawn 1400 L Street, NW Washington, DC 20005-3502 Gary D. Wilson, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, NY 13202 Supervisor Town of Scriba Route 8, Box 382

Oswego, NY 13126 Mr. B. Ralph Sylvia Executive Vice President Generation Business Group Niagara Mohawk Power Corp.

Nuclear Learning Center 450 Lake Road

Oswego, NY 13126

h

~'%r