ML20237E012

Forwards RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions

ML20237E012
Person / Time
Site:	Farley
Issue date:	08/25/1998
From:	Jacob Zimmerman NRC (Affiliation Not Assigned)
To:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
References
GL-96-06, GL-96-6, TAC-M96809, TAC-M96810, NUDOCS 9808280146
Download: ML20237E012 (4)

Text

- _ _ _ _ - - _ _ _ _ _ _ _ - _ _ _

, August 25, 1998 Mr. D. N. Morey Vice President - Farley Project Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295 SU3 JECT:' REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 96-06, " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN BASIS ACCIDriNT CONDITIONG"- JOSEPH M.

FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. M96809 AND M96810)

Dear Mr. Morey:

By letters dated October 24,1996, January 27, May 23,1997, and June 29,1998, Southern Nuclear Operating Company, Inc. (SNC), submitted information related to Generic Letter 97-05, I for the Joseph M. Farley Nuclear Plant, Units 1 and 2. The staff has reviewed SNC's submittals and determined that additional information is required. The enclosure identifies the requested additional information (RAI) needed.

The enclosed RAI has been discussed with Ed Carmack of your staff. A target date for your response has been agreed upon to be November 6,1998. Should a situation occur that  :

prevents you from meeting the target date, please contact me at (301) 415-2426.

Sincerely, ORIGINAL SIGNED BY:

Jacob 1. Zimmerman, Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364

Enclosure:

As stated g pp p ' g

& . stia cc w/ encl: See next page '

Distribution: k Docket File .

PUBLIC HBerkow LBerry ACRS LPlisco, Rll hC )

PD ll-2 Rdg.- JZimmerman PSkinner, Ril JZwolinski OGC To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure j "E" = Copy with attachment / enclosure "N" = No copy l OFFICE PM:Ppff-T l4 LA:PDll\2( lY dip $lk{ , l l l l NAME JZinfi$$(/ nan:cn LBerry V(1/ HBdMo(uV ~

DATE f/nW8  %/4998 t /zf/98 ' / /98 / /98 / /97 DOCUMENT NAME: G:\FARLEY\M96809.RAI OFFICIAL RECORD COPY j

9808280146 980825 PDR ADOCK 05000348 P PDR f

pe uro n #*, UNITED STATES

[

2 j NUCLEAR REOULATORY COMMISSION WASHINGTON, D.C. 30eeH001

% . . . . . ,o! August 25, 1998 Mr. D. N. Morey Vice President - Farley Project

. Southem Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 96-06, " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN BASIS ACCIDENT CONDITIONS"- JOSEPH M.

FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. M96809 AND M96810)  ;

I

Dear Mr. Morey:

By letters dated October 24,1996, January 27, May 23,1997, and June 29,1998, Sodhern Nuclear Operating Company, Inc. (SNC), submitted information related to Generic Letter 97-05, for the Joseph M. Farley Nuclear Plant, Units 1 and 2. The staff has reviewed SNC's submittals and determined that additional information is required. The enclosure identifies the requested additional information (RAl) needed.

l The enclosed RAI has been discussed with Ed Carmack of your staff. A target date for your response has been agreed upon to be November 6,1998. Should a situation occur that prevents you from meeting the target date, please contact me at (301) 415-2426.

Sincerely, AD -

i b 1. Zi merman, Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364

Enclosure:

As stated l.

cc w/ encl: See next page r

l e

l l

Joseph M. Farley Nuclear Plant I cc:

, Mr. L. M. Stinson Rebecca V. Badham i General Manager - SAER Supervisor

! Southem Nuclear Operating Company Southem Nuclear Operating Company  !

Post Office Box 470 . P. O. Box 470 Ashford, Alabama 36312 Ashford, Alabama 36312 Mr. Mark Ajiuni, Licensing Manager Southem Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201-1295 Mr. M. Stanford Blanton Balch and Bingham Law Firm j

Post Office Box 306 1710 Sixth Avenue North Birmingham, Alabama 35201 l Mr. J. D. Woodard l

Executive Vice President Southem Nuclear Operating Company l Post Office Box 1295 Birmingham, Alabama 35201 l

State Health Officer Alabama Department of Public Health 434 Monroe Street Montgomery, Alabama 36130-1701 Chairman i Houston County Commission Post Office Box 6406 Dothan, Alabama 36302 Regional Administrator, Region 11 U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303 Resident inspector l U.S. Nuclear Regulatory Commission 7388 N. State Highway 95

[ Columbia, Alabama 36319 l

l

[ Reauest for Additional Information i

Generic Letter 96-06 Resoonse Southam Nuclear Ooeratina Comoanv. Inc.

Joseoh M. Farlev Nuclear Plant. Units 1 and 2 Docket Nos. 50-348 and 50-364 I

~ In your submittals, you indicated that a total of eight-pipe segments in each unit were susceptible to thermally induced pressurization, and stated that for two of these segments j (Penetrations 29 and 49), the pressurization was calculated based on a heat transfer analysis.

In order for the staff to complete its review of your responses, please provide the following information for these penetrations.

. Provide the applicable design criteria for the piping and the valves. Include the required load combinations.

. Provide a drawing of the piping run between the isolation valves. Include the lengths and l thicknesses of the piping segments and the type and thickness of the insulation.

I l

. Provide the maximum calculated temperature and pressure for the pipe run. Describe, in L

detail, the method used to calculate these pressure and temperature values. Please include j a discussion of the heat transfer model used in the analysis and the basis for the heat transfer  !

coefficients used in the analysis. '

in addition, you also stated that for two of these penetrations (Penetrations 50 and 43),

pressurization in these piping segments would be relieved by valve leakage. In order for the ,

staff to complete its review of your responses, please provide the following information for these '

penetrations.

j

. Describe the applicable design criteria for the piping and valves. Include the required load combinations.

• Provide a drawing of the valve. Provide the pressure at which the valve was determined to lift

off its seat or leak and describe the method used to estimate this pressure. Discuss any sources of uncertainty associated with the estimated lift off or leakage pressure.

. Provide the maximum calculated stress in the piping run based on the estimated lift off or leakage pressure.-

L Enclosure i