ML20205Q820
| ML20205Q820 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 03/30/1987 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-83-28, NUDOCS 8704060064 | |
| Download: ML20205Q820 (2) | |
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DuxE POWER GOMPAhT P.O. BOX 33189 -
CHARLOTTE, N.C. 28242 HAL B. TUCKER Trs.mmons
== r=====v (704) 373-4531 woca. man recommon March 30, 1987 U. S. Nuclear Regulatory Commission Attention: Doctament Control Desk Washington, D. C. 20555
Subject:
Catawba Nuclear Station Docket Nos. 50-413 and 50-414 McGuire Nuclear Station Docket Nos. 50-369 and 50-370 Generic Letter 83-28,' Item 2.2 (Part 1)
Dear Sir:
Attached is a combined response for Catawba and McGuire Nuclear Stations to your request for additional information transmitted on February 12, 1987.
Very truly yours, 7/A -
i Hal B. Tucker LTP/29/sbn Attachment xc:
Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II s
101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. P. K. Van Doorn NRC Resident Inspector Catawba Nuclear Station Mr. W. T. Orders NRC Resident Inspector McGuire Nuclear Station g4060064870330 p
ADOCK 05000369 PDR g[1 m,
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Response to Request for Additional Information on Equipment Qualification Your letter of February 12, 1987 transmitted several questions concerning our program for equipment classification as it relates to work activities on and procurement of safety-related components. We have addressed each of these concerns in a aingle response which follows:
l Safety-related (QA Condition 1) components were identified during the design phase of each station and are identified as such on applicable specifications, drawings, flow diagrams, purchase requisitions and system descriptions. All of these j
documents are maintained in accordance with the Duke Power Quality Assurance i
Program as specified in procedures contained in the Design Engineering Quality Assurance M'nual.
Likewise, revisions to the design of the station and/or a
revisions to the applicable documents are also controlled by the QA program.
The Quality Standards Manual (QSM) is the basic reference for determination of QA Condition.
It is not sufficiently detailed to cover all components and thus serves as a "first-cut" guide. The manual directs the user to supplementary component lists, which may be used to obtain cross references to the applicable QA controlled drawings, specification, etc. The QSM contains procedures for submittal of revisions or additions to the QSM which require cross-departmental review and concurrence, including QA management approval.
In accordance with the Administrative Policy Manual for Nuclear Stations (APM),
each station has a work request system, the procedures for which require the determination of QA Condition as a prerequisite to performing maintenance and the identification of any special procedures to be used.
In addition, station 1
i procedures and special instructions which address activities associated with safety-related components are subject to a QA defined review and approval process.
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On the matter of procurement, the Design Engineering QA Manual and the APM contain j
procedures for the preparation of procurement specifications for all QA Condition 1 components. These procedures require the identification of any applicable codes, 4
testing, standards and design or QA requirements. These procedures also require a supplier QA certification to ensure that the supplied component conforms to specified codes, standards, tests or inspections. In addition, the Equipment Qualification Reference Index for each station details explicit qualification testing requirements for procurement documents.
Purchase documents for safety-related equipment are rcviewed in accordance with the QA program to assure that QA requirements, including vendor documentation and-applicable 10 CFR 50, Appendix B requirements are incorporated.
l In conclusion, we feel that the implementation of these programs and their adequacy are confirmed by virtue of Quality Assurance inspections and audits as well as NRC OIE inspections.
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