ML20203L169

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

ML20203L169
Person / Time
Site:	Browns Ferry
Issue date:	02/27/1998
From:	De Agazio A NRC (Affiliation Not Assigned)
To:	Zeringue O TENNESSEE VALLEY AUTHORITY
References
GL-96-06, GL-96-6, TAC-M96784, TAC-M96785, TAC-M96786, NUDOCS 9803050383
Download: ML20203L169 (4)

Text

_

Mr. O. J. Zcringue February 27, 1998 4

Chief Nucle:r Officer and Ex:cutiva Vice Pr:sident Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402 2801

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER 96-06, ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN BASIS ACCIDENTS (TAC NOS. M96784, M96785, AND M96786)

Dear Mr. Zeringue:

By letter dated January 23,1997, the Tennessee Valley Authority (TVA) responded to Generic Letter 96-06. In that response, TVA indicated that two pipelines penetrating containment and identified as susceptible to thermally-induced pressurization were evaluated using ASME Code Appendix F criteria. TVA letter dated October 23,1997, revised the response. In the revised response, TVA indicates that further evaluation has demonstrated that these lines meet the design code criteria.

One of these lines is associated with the penetration for the sampling system. TVA's revised response indicates the sampling system inboard isolation valve will unseat and relieve pressure prior to exceeding the design criteria for the piping or valves. Please provide a drawing of the inboard isolation valve and the calculationN used to determine the pressure needed to unseat the valve. Additionally, provide a discussu. of the uncertainties associated with this calculation.

The October 23,1997, revision also identified additional lines where valve leakage is expected to prevent overpressure of the lines. These are the Drywell Floor and Equipment Drain Sump discharge lines. TVA indicated that it intends to implement a design change to provide overpressure protection for these lines. Please describe the intended design change which will provide overpressure protection for these lines.

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Please provide your response no later than March 27,1998.

Sincerely, Albert W.NAgadioNtYrofdct Manager Project Directorate ll 3 t

Division of Reactor Projects - l/ll Office of Nuclear Reactor Regulation O

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,A Docket Nos. 50-259,50-260, and 50-296 cc: See next page gy 3

4 DISTRIBUTION (Dochet File '

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Mr. O. 'J; Z:ringue rebruary 27, 1998 Chief Nucle:r Officer i

and Executive Vice President-

-Tennessee Valley Authority -

l 6A Lookout Place.

1101 Market Street Chattanooga, Tennessee 37402 2801 i-

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SUBJECT:

. - REQUEST FOR ADDITIONAL INFORMATION GENERIC LETTER 96-06, ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT

_ INTEGRITY DURING DESIGN BASIS ACCIDENTS (TAC NOS. M96784, M96785, AND M96786)

Dear Mr. Zeringue:

By letter dated January 23,1997, the Tennessee Valley Authority (TVA) responded to Generic L

Letter 96-06. In that response, TVA indicated that two pipelines penetrating cor tainment and identifed as susceptible to thermally-induced pressurization were evaluated vaing ASME Code Appendix F criteria. TVA letter dated October 23,1997, revised the responso, in the revised -

response,' TVA indicates that further evaluation has demonstrated that these lines meet the

. design code criteria.

- One of these lines is associated with the penetration for the sampling system. TVA's revised -

response indicates the sampling system inboard isolation valve will unseat and relieve p sssure

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prior to exceeding the design criteria for the piping or valves. Please provide a drawing of the inboard isolation valve and the calculation (s) used to determine the pressure needed to unseat the valve.- Additionally, provide a discussion of the uncertainties associated with this calculation.

l The October 23,1997, revision also identified addit onal lines where valve leakage is expected to prevent overpressure of the lines.- These are the n ywell Floor and Eqi.ipment Drain Sump r

discharge lines. TVA indicated that it intends '"

ilement a design change to provide overpressure protection for these lines. P" scribe the intended design change which will 4

provide overpressure protection for tbr j

Please provide your response no later than March 27,1998.

Sincerely, Albert W.0@dgalioMYrokc't Manager 1

Project Directorate ll-3 Division of Reactor Projects - 1/II i

Office of Nuclear Reactor Regulation -

Docket Nos. 50-259, 50-260, and 50-296 cc: See next page DISTRIBUTION.

Docket File.

J. Zwolinski(A)

A. DeAgazio-L.- Plisco, Region ll-i PUBLIC:

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PDil-3 R/F

' B., 05yton ACRS DOCUMENT NAME: G;\\BFN\\96784RAl.WPD

• See previous concurrence To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy t

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30606-4001 4, * *

• e February 27, 1998 Mr. O. J. Zeringue Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - GENERIC 1 ETTER 96-06, ASSURANCE OF EQUIPMENT OPC'tABILITY AflD CONTAINMENT INTEGRITY DURING DESIGN BASIS ACCIDENTS (TAC NOS. M96784, M96785, AND M96786) 2 Npr Mr. Zeringue:

By letter dated January 28,1997, the Tennessee Valley Authority (TVA) responded to Generic Letter 96-06. In that response, WA indicated that two pipelines penetrating containment and identified as susceptible to thermally-induced pressurization were evaluated using ASME Code Appendix F criteria. TVA letter dated October 23,1997, revised the response. In the revised response, TVA indicates that further evaluation has demonstrated that these lines meet the design code criteria.

One of these lines is associated with the penetration for the sampling system. TVA's revised response indicates the vampling system inboard isolation valve will unsea; and re'ieve pressure prior to exceeding the design criteria for the piping or valves. Please provida a drawing of the inboard isolation valve and the calculation (s) used to determine the pressure needed to unseat the valve. Additionally, provide a discussion of the uncertainties associated witn this calculation.

The October 23,1997, revision also identified aiaional lines where valve leakage is expected to prevent overpressure of the lines. Ti$ese are the Drywell Floor and Equipment Drain Sump discharge lines. TVA indicated that it intends to implement a design change to provide overpressure protection for these lines. Please describe the intended design change which wi'l provide overpressure protection for these lines.

Please provide your response no later than March 27,1998.

Sincerely, h

Albert W.

^gazio, Sr. Proj ct Manager Project Directorate ll 3 Dwision of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-259,50-260, and 50-296 cc: See next page

Mr. O. J. Zeringue BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:

Mr. J. A. Scalice, Senior Vice Piesident Mr. Mark J. Burzynski, Managar Nuclear Operations Nuclear Licensing Tenreessee Valley Authority Tennessee Valley Authority 6A Lookout Place 4J Blue Ridge 1101 Market Street 1101 Market Street Chattanooga, TN 37402 2801 Chattanooga, TN 37402-2801 Mr. Jack A. Bailey, Vice President Mr. Timothy E. Abney, Manager Engineering & Technical Services Licensing and Industry Affairs Tennessee Valley Authority Browns Ferry Nuclear Plant O 8.ookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402 2801 Decatur, AL 37402-2801 Mr. C. M. Crane, Site Vice President Regional Administrator, Region ll Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission Tennessee Valley Authority 61 Forsyth Street, SW., Suite 23T85 P.O. Box 2000 Atlanta, GA 30303-3415 Decatur, AL 35609 Mr. Leonard D. Wert General Oounsel Senior Resident inspector Tennessee Valley Authority U.S. Nuclear Regulatory Commission ET 10H Browns Ferry Nuclear Plant 400 West Summit Hill Drive 10833 Shaw Road Knoxville, TN 37902 Athens, AL 35611 Mr. Raul R. Baron, General Manager State Health Officer Nuclear Assurance Alabama Dept. of Public Hee:'h Tennessee Valley Authority 434 Monroe Street 4J Blue Ridge Montgomery, AL 35130-1701 1101 Market Street Chattanooga, TN 37402 2801 Chairman Limestone County Commission Mr. Karl W. Singer, Plant Manager 310 West Washington Street Browne Ferry Nuclear Plant Athens, AL 35611 Tennessee Valley Authority P.O. Box 2000 Decatur, AL 25609

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