ML20215M526
| ML20215M526 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/04/1987 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GL-83-28, NUDOCS 8705130292 | |
| Download: ML20215M526 (4) | |
Text
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Telephone (412) 393-6000
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Shippmgport. PA 15077M4 May 4, 1987 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Generic Letter 83-28, Item 2.2.1 -
Equipment Classification Gentlemen:
By letter dated March 5,
- 1987, the NRC requested additional information on the Equipment Classification program for Beaver Valley Unit 1
based on the review of our November 4, 1983 response to Generic Letter 83-28, item 2.2.1.
Attached is Beaver Valley Unit 1 response to the March 5, 1987 request for additional information.
If there are any questions regarding this information, please contact my office.
Very truly yours, J. D.
Sieber Vice President, Nuclear cc: Mr. S. M. Pindale, Resident Inspector U.
S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission Regional Administrator Region 1 631 Park Avenue King of Prussia, PA 19406 Mr. Peter S. Tam U.
S. Nuclear Regulatory Commission Project Directorate No. 2 Division of PWR Licensing - A Washington, DC 20555
- Mail Stop 316 g
Addressee only
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RESPONSE TO MARCH 5, 1987 REQUEST FOR INFORMATION ON GENERIC LETTER 83-28, ITEM 2.2.1 BEAVER VALLEY POWER STATION UNIT 1 A.
Program Summary The classification of equipment / components exists in several sources as indicated in our November 4, 1983 response to item 2.2.1.2.
In summary these sources are:
Master Equipment List (MEL)
Q*5 Document e
Quality Assurance Program, Appendix B e
Operating Manual e
Electrical and Mechanical Drawings e
Original Equipment Specifications e
Westinghouse Spare Parts Report The MEL is the most complete and accessible source of equipment classification, thus it has been designated as the "first line" information system.
In situations where component classification information is not available from the
- MEL, the Nuclear Engineering Department is consulted and the classification information is obtained upon review of the other sources.
B.
Responses to Request for Information 1.
Item 2.2.1 - Program The licensee's response does not confirm that all safety-related components are designated as safety-related on plant documents such as procedures, system descriptions, test and maintenance instructions, operating procedures, and in information handling systems so that personnel performing activities that affect such safety-related components are aware that they are working on safety-related components and are guided by safety-related procedures and constraints.
Response
The Master Equipment List (MEL) is used as the primary information handling system for plant components.
Included as part of the data base on each component is the components Quality
^?surance category.
The MEL contains the majority of safety. elated components.
Maintenance activities, such as troubleshooting and corrective maintenance, are controlled by a Maintenance Work Request (MWR).
The Quality Assurance category of the component to be worked on is required to be identified on the MWR form and is obtained from the MEL.
Operating / Maintenance procedures and surveillance tests do not specifically identify components as safety-related.
These documents are generated in a controlled manner and are reviewed and approved by the Onsite Safety Committee and management.
In
- addition, procedure adherence is required and verified by Quality Control inspections and Quality Assurance audits.
<1
. RESPONSE TO MARCH'5, 1987 REQUEST FOR'INFORMATION-(Continued)
,e 2.
Item.2.2.1.2 -Information-Handling-Systems The
- licensee's response has not confirmed that the information' handling system includes a
list of safety-related. equipment and that procedures. exist which governLits development and validation.
Response
The Master Equipment List (MEL) includes a components CA category as part of the database for each component.
Administrative engineering. procedures are in place-that control' the update and validation of.the MEL as well as guidelines for classifying components.not. contained in the database.
3.
Item 2.2.1.4 - Management controls The. licensee's response has.not confirmed how management determines that the management controls utilized to verify that.the procedures for preparation, validation and routine utilization of the information system have been followed.
Response
As stated 'in our November 4, 1983-response to item 2.2.1.4,
~ Management verifies compliance with proceduresL for preparation,'
validation. and' routine utilization of-the Master. Equipment List (MEL) through audits conducted by the Quality Assurance Departmenc.
4.
Item 2.2.1.5 - Design Verification and Procurement The licensee's response does not -confirm that their procurement specifications require that the appropriate design verification and qualiitcation testing be provided by
}
the supplier.
t
Response
The procurement of new safety-related components is controlled by a design change program which requires design verific& tion for changes that affect safety-related structures, system or components per the requirements of E
ANSI N4E.2.ll..
A procurement specification must be issued for the procurement of items designed and/or manufactured specifically for nuclear safety-related use and requires the following:
I e
The seller must have a
quality assurance program reviewed and approved by Duquesne Light Company or be on the Duquesne Light qualified suppliers list.
i l !
a.
4 RESPONSE TO MARCH 5, 1987 REQUEST FOR INFORMATION (Continued)
The seller to be informed that 10 CFR 21 applies.
The seller to be informed of what documentation is required.
Requirements for qualification testing.
Requirements for design verification.
Per the design change program, the verifying engineers are required to review and assure that procurement specifications specify appropriate design verification requirements, including qualification testing.
Spare and replacement parts are purchased to the original equipment procurement specifications.
If the supplier can no longer provide parts to the original specification, the Nuclear Engineering Department is consulted to review and resolve the problem.
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