ML20206M421

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Rev 0 to Procedure 20061.2, Proposed Qualification Program for Special Door Gaskets for South Texas Project Electric Generating Station
ML20206M421
Person / Time
Site: South Texas  
Issue date: 07/01/1985
From: Farwell C, Maynard T, Woeste R
FARWELL & HENDRICKS, INC.
To:
Shared Package
ML20206M077 List:
References
20061.2, NUDOCS 8704200107
Download: ML20206M421 (13)
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Text

1 2 0 0 6 I. O PG0 51 Procedure No. 20061.2, Rev. 0 Date:

7/1/85 Total Pages:

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PROPOSED QUALIFICATION PROGRAM FOR SPECIAL 000R GASKETS FOR HOUSTON LIGHTING AND POWER COMPANY SOUTH TEXA5 PROJECT ELECTRIC GENERATING STATION PREPARED FOR M05LER SAFE COMPANY 1561 GRAND AVENUE HAMILTON, OHIO 45012 PREPARED BY FARWELL & HENDRICKS, INC.

1000 FORD CIRCLE, SUITE C MILFORD, OHIO 45150 (513) 831-9390 APPROVED BY:

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al PREPARED BY:

cr-Anomas M. Maynarf, Jr.

3 7 A. woeste Manager, NEQ Kanager, Q.A.

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APPROVED AND REVIEWED BY:

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Chief Executive Officer CUST0MER CONTACT:

Mr. Charles oder 8704200107 870415

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2006 I. 0PG052 20061.2.0PG2 RECORD OF REVISIONS REVISION ISSUE PREPARED APPROVED QA PAGES REVISED NUMBER DATE BY BY BY AND DESCRIPTION C' F RAW Original Issue 0

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7 2006 I. OPG053 20061.2.0PG3 TABLE OF CONTENTS Page 1.0 Introduction......................................

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2.0 Applicable Documents.. Codes, Standards and Regulations.......................................

5 3.0 Qualification Progras.............................

6 3.1 Environmental Qualification..................

6 3.2 Seisaic Qualification........................

7 4.d Final Report......................................

8 5.0 Q u a l i ty A s s u r a n c e.................................

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6.0 Ownership of Documents............................

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2006 I.0PG054 20061.2.0PG4

1.0 INTRODUCTION

The Proposed Qualification Program (PQP) presented herein describes the bases and philosophies used by Farwell & Hendricks, Inc. in developing qualification programs for safety-related mechanical equipment used in Nuclear Power Generating Stations.

The qualification of equipment can be considered a

four phase process:

1)

Service Condition Definition 2)

Aging Evaluation 3)

Qualification Demonstration 4)

Qualification Documentation The qualification of the subject equipment will be accomplished by a combination of an environmental analysis of the constituent materials as well as seismic analysis.

The qualification documentation must include the qualified lives of the equipment and/or its components based on the results of the test program.

The documentation will also include the maintenance and replacement schedules established as part of the qualification program.

The specific details of qualification are defined durin the development of the Nuclear Environmental Qualification lan.

This document provides'the rationale and justification for all approaches to the qualification process.

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2.0 APPLICABLE DOCUMENTS, CODES, STANDARDS AND REGULATIONS i

Qualif1'c'ation of the test sample (s) will be effected in a

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prograa conducted in accordance with the following documents:

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IEEE Std. 323-1983, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Situations" (including the November 21, 1975 Supplement) and USNRC Endorsing Regulatory Guide 1.89.

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e IEEE Std. 344-1974 IEEE Recommended Practices for Nuclear Power Generating Stations" quipment for Seismic Qualification of Class 1E E j

and USNRC Endorsing Regulatory Guide 1.100.

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USNRC IE Bulletin No.79-01B, " Environmental Qualification of Class 1E Equipment" and D0R Guidelines.

e USNRC NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment".

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10 CFR Part 50, Section 50.49, " Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants".

e 10 CFR Part 21

" Reporting of Defects and Non-1 Conformances".

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i 10 CFR Part 50, Appendix 8. " Quality Assurance e

I Criteria for Nuclear Power Plants and Fuel

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Reprocessing Plants".

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e ANSI /ASME NQA-1-1979, Quality Assurance Program i

j Requirements for Nuclear Power Plants.

e ANSI /ASME N45.2-1977, Quality Assurance Program Requirements for Nuclear Facilities.

e Houston Lighting and Power Specification 3A51955 0036, Rev. 3, including Specification Change Notice No. 5 i

Dated 4/18/85.

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3.0 QUALIFICATION PROGRAM The qualification program used to meet the requirements of the documents listed in Section 2 is presented in this section.

The program includes an environmental and seismic analysis to evaluate the acceptability of the equipment for the intended application.

3.1 Environmental Qualification The environmental status of the subject equipment to be installed at the South Texas Project Electric Generating Station will be addressed by analysis of the non-metallic materials used in the manufacture of this equipment as provided by Mosler Safe Company.

The qualification will be accomplished by a combination of an environmental survey of the constituent materials as well as seismic qualification.

A description of the equipment, along with service conditions, will be presented.

The qualification status of the equipment will also be presented as determined by comparison of the service requirements to the demonstrated capabilities of the The applicable references will be listed for O

equipment materials.each demonstrated capability to provide complete traceability and auditability of the assessment.

In

addition, the qualification maintenance / surveillance requirements will be presented.

The materials evaluations and data used to perform the envi.ronmental qualification assessment of the equipment will be included in the final report.

Materials properties such as temperature limits. Arrhenius parameters, and radiation thresholds will be utilized for each constituent material of each component, where known.

If either the specific material and its properties or the actual manufacturer of the constituent material are

unknown, conservative properties for the generic material classification will be utilized to assess aging.

Where data is unavailable, conservative properties will be based on engineering judgement.

This is consistent with the industry philosophy of using the best data available.

Where more than one material is evaluated for a given component, the data will be presented to provi de-sufficient i nformation to j usti fy the assessed qualification status.

The effects of synergism on materials are generally act available in literature.

These effects have not been sufficiently examined or quantified whereby they can be accounted for in most materials, especially with regards to the qualification process.

7 IEEE Standard 323-1983 requires that only known effects be O

considered in qualification programs.

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2 00 61. 0 PG0 57 20061.2.0PG7 The data presented will identi fy the application (classification) of each material and the failure parameter for which the material was evaluated.

This will provide the necessary information to justify the qualification based on servic,e used and potential failure mechanism.

References will be presented to provide complete auditability and traceability of the data used for qualification assessment.

The expected life calculation will be based on the.Arrhenius formul a :-

in (life) = slope (1/T) + intercept Where:

1) Slope and intercept are derived from Arrhenius testing.
2) T is the service temperature in degrees Kelvin.

I This approach, comprising a

combination of environmental evaluation of the materials and seismic qualification of the equipment, is consistent with current NRC guidelines for qualification.

l 3.2 Seismic Qualification O

Seismic qualification of the equipment will be accomplished by analysi,s performed by Mosler Safe Company.

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2006I.0PG058 20061.20PG8 4.0 Final Report The final report will certify that the testing was done in accordance with the approved test program.

IEEE 323-1974, IEEE 344-1975, customer provided specifications, and the applicable codes, standards and regulations listed in Section 2.0.

This report will be signed by a Registered Professional Engineer.

The report will include the procedures and results for each phase of the test program.

The results of the seismic analysis will be documented separately.

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5.0 QUALITY ASSURANCE The NEQP will be-prepared and the test program will be conducted in accordance with the Farwell & Hendricks Inc. Quality Assurance Program and Technical Procedures Manual which conforms to the applicable sections of ANSI N-45.2, 10 CFR 50, Appendix 8.

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6.0 Ownership of Documents All drawings, plans, specification's, reports, raw data, and documents / data prepared and, collected under this other, l/ plan / agreement / contract / purchase order, shall become the proposa property of the client.

This documentation shall be delivered to the client upon completion of services; however.

Farwell &

Hendricks. Inc. may retain and use copies thereof.

Farwell & Hendricks. Inc. will forward these records which should be caintained. for the life of the particular item while it is installed in the nuclear facility and stored for future used by the owner per 10 CFR 50 Appendix B.requi'rements.

Thus, the customer is responsible for lifetime storage requirements with respect to the subcontract work performed by Farwell & Hendricks.
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6 APPENDIX D PURCHASE ORDER

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Specification. A111a accordance with your quotation of May 7,1985 & " Proposed qualification program for Special door gaskets" prepared by you, dated N1r 1,1985 Materials to be evaluated are specified on Moster Dewgs. Herewith K-18611, K-18408 Rev. 2, E-18473, K-18574. Send certified I

copies of test reports to Moster Quality Assurance Dept.

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