ML20136J377

Forwards Request for Addl Info Re FSAR Sections 3.2 & 5.2 on Piping Supports & safety-related Tubings & Fittings. Schedule for Responses Requested

ML20136J377
Person / Time
Site:	South Texas
Issue date:	08/06/1985
From:	Knighton G Office of Nuclear Reactor Regulation
To:	Goldberg J HOUSTON LIGHTING & POWER CO.
References
NUDOCS 8508200700
Download: ML20136J377 (5)

Text

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s gus 0 6 1985 2

Docket Nos.: 50-498 and 50-499 Mr. J. H. Goldberg Group Vice President - Nuclear Houston Lighting and Power Company Post Office Box 1700 Houston, Texas 77001

SUBJECT:

S0llTH TEXAS PROJECT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION The staff has determined that additional information is needed pertaining to Sections 3.2 and 5.2 of the South Texas Project FSAR. The enclosure lists the items requiring additional information as questions numbered 210.1 through 210.6.

Please inform us as to your schedule for responding. Please contact the Project Manager N. P. Kadarrbi at (301) 492-7272 if you have any questions.

Sincerely, i

M/

George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing

Enclosure:

As stated cc: See next page l

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NRC PDR BGrimes LPDR EJordan PRC System FCCherney, MEB NSIC WBelke, QAB, I & E LB#3 Reading JLee NPKadambi OELD, Attorney j

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4 South Texas Mr. J. H. Goldberg Villiam S. Jordan, III, Esq.

Group Vice President, Nuclear Farmon, Weiss & Jordan Houston Lighting and Power Company 2001 S Street, N.W.

P. O. Box 1700 Suite 430 Fauston, Texas 77001 Washington, D. C.

20009 Brian Berwick, Esq.

Mr. J. T. Westermeir Assistant Attorney General Manager, South Texas Project Environmental Protection Division Houston Lighting and Power Company P. O. Box 12548 P. O. Box 1700 Capitol Station Houston, Texas 77001 Austin, Texas 78711 Mr. E. R. Brooks Mr. Claude E. Johnson, Pesident Mr. R. L. Range Inspector /Scuth Texas Project Central Power and Light Comoany c/o U. S. NRC P. O. Box 2121 P. O. Box 910 Corpus Christi, Texas 78403 9ay City, Texas 77414 Mr. H. L. Peterson Mr. Jonachan Davis Mr. G. Pokorny Assistant City Attornev City of Austin City of Austin P. O. Box 1088 P. O. Box 1088 Austin, Texas 78767 Austin, Texas 78767 Mr. J. B. Poston Mr. A. Vcn Rosenberg Ms. Pat Coy City Public Service Board Citizens Concerned About Muclear P. 0. Box 1771 Power San Antonio, Texas 78796 5106 Casa Oro San Antonio, Texas 78223 Jack R. Newman, Esc.

Newran & Holtzinger, P.C.

Mr. Mark R. Wisenberg 1615 L Street, NW Manager, Nuclear Licensing Washincton, DC 2CC36 Houston Liohting and Power Coroanv P. O. Box 1700 Melbert Schwartz,Jr., Esq.

Houston, Texas 77001 Baker & Botts One Shell Plaza Mr. Charles Halligan Fcuston, Texas 77002 Mr. Burton L. Lex Bechtel Corooration Mrs. Peggy Buchorn P. O. Box 2166 Executive Director Houston, Texas 77001 Citizens #or Equitabla Utilities, Inc.

Poute 1, Box 1684 3ra:oria, Texas 77422

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4 Regicnal Administrator - Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011 Mr. Lanny Sinkin Citizens Concerned About Nuclear Power 3022 Porter St. N. W. #304 Washington, D. C.

20008 Mr. S. Head HL&P Representative Suite 1309 7910 Woodment Avenue Bethesda, Maryland 20814 4

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Enclosure Scuth Texas Project Units 1 and 2 Docket Hos. 50-498 and 50-499 The following questions are based on the MEB review of Sections 3.2 and 5.2 4

and the applicable Piping and Instrumentation Diagrams of the South Texas FSAR with respect to compliance with the Codes and Standards Rule 10 CFR 50, Section 50.55a, (FSAR Sections 5.2.1.1 and 5.2.1.2), Seismic Classification of Structures, Systems and Components (FSAR Section 3.2.1), and System Quality Group Classification of components that are part of the reactor coolant pressure boundary, other fluid systems which are important to safety and safety related, and mechanical equipment that perform a safety function (FSAR Section3.2.2). The questions are posed in the form of observations and suggested corrective actions.

Please justify the current information in the FSAR or respond to the suggested corrective action.

l 210.1 In Table 3.2.A-1, page 3.2-7, the piping, supports, and valves in the cooling loops of the spent fuel pool cooling and cleanup system should be within the scope of a Quality Assurance Program that is in conformance with 10 CFR 50, Appendix B.

210.2 In Table 3.2.A-1, page 3.2-27b, Note 10 (page 3.2-29a) is not applicable to i

safety-related instrument tubing and fittings since it applies only to equipment that is not safety-related. Revise Table 3.2.A-1 accordingly.

210.3 In Table 3.2.B-1, page 3.2-34, the shell side of the letdcwn heat exchanger of the Chemical and Volume Control System is incorrectly classified Safety Class NNS, Compenent Code ANSI B31.1, Quality Assurance NA, and Seismic Category NA.

In addition notes 21 and 22 are not applicable.

To be acceptable, the shell side of this component should be classified

• Ouality Group C (Safety Class 3), Ccmponent Code ASME Section III, Class 3, Seismic Category I, and be within the scope of a Quality Assurance Program that is in conformance with 10 CFR 50, Appendix B.

Reference to notes 21 and 22 should be deleted.

210.4 In Table 3.2.B-1, page 3.2-35, the shell side of the excess letdown heat exchanger of the Chemical and Volume Control System is incorrectly classified Safety Class NNS, Component Code ANSI B31.1, Quality Assurance NA, and Seismic Category NA.

In addition, notes 21 and 22 are not applicable.

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8 To be acceptable, the shell side of this component should be classified Quality Group C (Safety Class 3), Component Code ASME Section III, Class 3, Seismic Category I, and be.within the scope of a Quality Assurance Program that is in conformance with 10 CFR 50, Appendix B.

Reference to notes 21 and 22 should be deleted.

210.5 In Table 3.2.B-2, page 3.2-50, the code edition and addenda of Section III of the ASME Boiler and Pressure Vessel Code for reactor coolant pressure boundary (RCPB) components are inconsistent with those identified in Table 5.2-1 for RCPB components. Resolve this inconsistency.

210.6 Identify all ASME Code Cases including those that are listed as acceptable in Regulatory Guides 1.84 and 1.85 that are used in the construction of each Quality Group A (Safety Class 1) component within the reactor coolant pressure boundary. These ccde cases should be identified by code case number, revision, and title for each component to which the ccde case has been applied. A number of Code Cases in Regulatory Guides 1.84 and 1.85 are identified as conditionally acceptable to the NRC staff. Verify that in those instances where conditionally acceptable code cases have been applied in the construction of components you are in compliance with the additional conditions applicable to each conditionally approved Code Case.

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