ML20210G335

Forwards Second Request for Addl Info Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions

ML20210G335
Person / Time
Site:	Vogtle
Issue date:	07/27/1999
From:	Assa R NRC (Affiliation Not Assigned)
To:	Beasley J SOUTHERN NUCLEAR OPERATING CO.
References
GL-96-06, TAC-M96881, TAC-M96882, NUDOCS 9908030067
Download: ML20210G335 (4)

Text

Mr. J. B. Brisl:y,'Jr.

t Vics Presid:nt Distribution: b ' -

Dockst Fila COgla, Ril Srythurn Nucl:ar Optrating PUBLIC I Company, Inc. PD ll-1 R/F Post Office Box 1295 SBlack Birmingham, Alabama 35201-1295 ' OGC '

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SUBJECT:

VOGTLE ELECTRIC GENERA flNG PLANT, UNITS 1 AND 2 RE: SECOND REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER 96-06,

" ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN BASIS ACCIDENT CONDITIONS" (TAC NOS. M96881 AND M96882) .

Dear Mr. Beasley:

By letter dated January 27,1997,' Georgia Power Company (the licensee) submitted its

response regarding GL 96-06,," Assurance of Equipment Operability and Containment integrity During Design Basis Accident Conditions." This submittal addresses the issues of water hammer, two-phase flow and thermal-induced pressurization of pipi_ng runs panetrating the containment for the Vogtle Electric Generating Plant.'

in its submittal, the licensee identified pipe lines associated with 15 penetrations at each unit that are susceptible to thermally-induced overpressure. The licensee implemented controls to assure that the Reactor Coolant System Hot Leg Sample Line and the Postaccident Sampling System Return to Containment are only isolated while the fluid is hot during normal operation.

For the remaining thirteen lines in each unit, the licensee performed operability assessments basud on an evaluation of isolation valve leakage or an evaluation of the maximum inelastic strain in the pipe. The NRC staff has reviewed your letter dated January 27,1997, and discussed your corrective actions during a conference call on July 21,1999. The staff needs additional information in order to complete its assessment of the operability of the affected

' systems and corrective actions in accordance with the requirements stated in Title 10 of the Code of Federal Reaulations (10 CFR) Part 50, Appendix B. Please respond to the enclosed request for additionalinformation within thirty days of the date of this letter.

Sincerely, original signed by:

p"DR A 7 990727 r Ramin Assa, Project Manager, Section 1 P M 05000424 Project Directorate il PDR '

Division of Licensing Project Management /

Office of Nuclear Reactor Regulation

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Docket Nos.'50-424 ana 50-425' g

Enclosure:

Request For AdditionalInformation h bDf cc w/ encl: See next page DOCUMENT NAME: G:\PDil-1\VOGTLE\ra19606.wpd To receivs a copy of this document, indicate in the box C= Copy w/o attachment / enclosure E= Copy with attachment / enclosure N = No t

copy OFFICE PDill1/P % 6 Ril m PDil-1/LA I PDil-1/S_C l

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% y[$qcn'a Ije UNITED STATES NUCLEAR REGULATORY COMMISSION l WASHINGTON D.C. aoseMoot I l

' \*****p8 July 27,1999 l Mr. J. B. Beasley, Jr.

Vice President Southern Nuclear Operating 1 Company, Inc. l Post Office Box 1295 l

Birmingham, Alabama 35201-1295 1

SUBJECT:

VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 RE: SECOND l REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER 96-06,

" ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN BASIS ACCIDENT CONDITIONS" (TAC NOS. M96881 AND M96882)

Dear Mr. Beasley:

By letter dated January 27,1997, ' Georgia Power Company (the licensee) submitted its

. response regarding GL 96-06," Assurance of Equipment Operability and Containment integrity During Design Basis Accident Conditions." This submittal addresses the issues of water hammer, two-phase flow and thermal-induced pressurization of piping runs penetrating the containment for the Vogtle Electric Generating Plant.

In its submittal, the licensee identified pipe lines associated with 15 penetrations at each unit that are susceptible to thermally-induced overpressure. The licensee implemented controls to '

assure that the Reactor Coolant System Hot Leg Sample Line and the Postaccident Sampling System Return to Containment are only isolated while the fluid is hot during normal operation.

For the remaining thirteen lines in each unit, the licensee performed operability assessments based on an evaluation of isolation valve leakage or an evaluation of the maximum inelastic strain in the pipe. The NRC staff has reviewed your letter dated January 27,1997, and discussed your corrective actions during a conference call on July 21,1999. The staff needs additional information in order to complete its assessment of the operability of the affected systems and corrective actions in accordance with the requirements stated in Title 10 of the Code of Federal Reculations (10 CFR) Part 50, Appendix B. Please respond to the enclosed request for additional information within thirty days of the date of this letter.

Sincerely.

Ramin Assa, Project Manager, Section 1 Project Directorate ll Division of Licensing Project Management Office of Nuclear Reactor Regulation

} Docket Nos. 50-424 and 50-425

Enclosure:

Request For AdditionalInformation cc w/ encl: See next page

I

s. ,

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Vogtle Electric Generating Plant cc: Harold Reheis, Director Mr. J. A. Bailey Department of Natural Resources Manager, Licensing 205 Butler Street, SE. Suite 1252 Southern Nuclear Operating Atlanta, Georgia 30334 Company, Inc.

P. O. Box 1295 Attomey General Birmingham, Alabama 35201-1295 Law Department

, 132 Judicial Building Mr. J. Gasser . Atlanta, Georgia 30334 General Manager, Vogtle Electric Generating Plant Mr. R. D. Barker Southern Nuclear Operating Program Manager Company, Inc. Fossil & Nuclear Operations P. O. Box 1600 Oglethorpe Power Corporation Waynesboro, Georgia 30830 2100 East Exchange Place P. O. Box 1349 Office of Planning and Budget Tucker, Georgia 300851349 Room 6158 270 Washington Street, SW. Charles A. Patrizia, Esquire Atlanta, Georgia 30334 Paul, Hastings, Janofsky & Walker 10th Floor Mr. J. D. Woodard 1299 Pennsylvania Avenue Executive Vice President Washington, DC 20004 9500 Southern Nuclear Operating l Company, Inc. Arthur H. Domby, Esquire '

P. O. Box 1295 Troutman Sanders Birmingham, Alabama 35201-1295 NationsBank Plaza 600 Peachtree Street, NE. i Steven M. Jackson Suite 5200 Senior Engineer - Power Supply Atlanta, Georgia 30308-2216 Municipal Electric Authority i of Georgia Resident inspector '

1470 Riveredge Parkway, NW. Vogtle Plant Atlanta, Georgia 30328-4684 8805 River Road Waynesboro, Georgia 30830 Office of the County Commissioner Burke County Commission Waynesboro, Georgia 30830

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REQUEST FOR ADDITIONAL INFORMATION I

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1. Provide the following information for those penetrations found acceptable based on leakage through the isolation valves: -

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

b. 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; and ,

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

2. Provide the following additionalinformation for those penetrations found acceptable based on engineering analysis:

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a. Provide the applicable design criteria for the piping and the valves, include the j required load combinations;

b. Provide a drawing of the piping run between the isolation valves. Include the lengths and thickness of the piping segments and the type and thickness of the insulation; and i

c. Provide the maximum-calculated temperature and pressure for the pipe run. Describe, j in detail, the method used to calculate these pressure and temperature values. This '

should include a discussion of the heat transfer model used in the analysis and the basis for the heat transfer coefficients used in the analysis.

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