ML20034C680
| ML20034C680 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/01/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034C678 | List: |
| References | |
| GL-83-28, NUDOCS 9005040317 | |
| Download: ML20034C680 (3) | |
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NUCLEAR REGULATORY COMMISSION
\\.....J WASHINGTON, D. C. 20$55 SAFETY EVALUATION BY THE OFFICE OF-NUCLEAR REACTOR REGULATION GENERIC LETTER 83-28c ITEM 2.2.1, EQUIPMENT CLASSIFICATION PROGRAM FOR ALL-SAFETY-RELATED COMPONENTS JOSEPH M. FARLEY NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364-
1.0 INTRODUCTION
Generic Letter 83-28 was issued by the NRC on July 8,1983, to indicate actions' i
to be taken by -licensees and applicants based on the generic-implications of the Salem ATWS events.
Item 2.2.1 of.that letter states'that: licensees and-applicants shall' describe in considerable detail their-program for classifying all safety-related components other than reactor trip system components as safety-related on plant documents and in information handling systems that.are used to control plant activities that may affect these components. -Specifically, the licensee's submittal was required to contain information describing:-
(1) the criteria used to identity these components as safety-related; (2 information handling system which identifies the components.as safety-related; (3) the manner in which station personnel use this information handling system to control activities affecting these components;-(4) the management controis--
that are used to verify that the information handling system is prepared, maintained, validated, and used in accordance with approved procedures; and (5) the design verification and qualification-testing requirements that are part of l
the specifications for procurement of' safety-related components..
Alabama Power Compa'ny, the licensee for Farley Nuclear Plant (FNP or Farley),
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Units 1 and 2, responded to the requirements of this item in submittals' dated i
November 4,1983, February 15,1964, April 22,1985, May 8,1987, August 12, 1988, November 30, 1989 and March 20, 1990. We have evaluated these responses and found them acceptable.
2.0 DISCUSSION AND EVALUATION The licensee provided submittals describing programs to assure that all' components necessary for accomplishing the required safety-related functions are properly designated on plant documents, procedures, and in the information handling systems that are used to control plant activities that may hffect these components.
The criteria for classifying components as safety-related were described.
Also described was the use of the information handling system in the preparation of maintenance work requests (MWRs) which govern testing, maintenance and modification work at the plant and 'the management controls used by the licensee to assure that the information handling system is adequately prepared, maintained, and used as intended.
In addition, the licensee's Obbbh C
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O l submittals stated that procurement procedures ensure that specifications for safety-related components and parts include design verification, qualification testing and requirements for supporting documentation.
By telephone conference call on October 13, 1989, the licensee stated that a computerizea maintenance management planning system (MMPS) is used to sup?ly component level classification information for use in preparing MWRs whici control all testing, maintenance, and modification work on safety-related components. The licensee also stated that the MMPS is controlled and maintained by a group at the plant according to procedures which have provisions to prevent unauthorizec changes to the classification information. The licensee oocumented this information on November 30 1989.
r The staff reviewed this documented response and in telephone conference calls on February 15 ano March 2,1990, requested further clarification of the status and use of the computerized database and source documents.
By letter dated March 20, 1990, the licensee stated that. the primary source of equipment
-t classification is from controlled " source documents" which include the Q List, the Final Safety Analysis Report, the plant design documents.:and the-FNP Operations Quality Assurance Policy Manual.
Design chan
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against these source documents for classification purposes. ges'are evaluated The Farley Nuclear Plant Information Management System (FNPIMS) computerized equipment classification database was developed to work with the source documents by providing a more detailed and convenient listing of components and subcomponents than is readily available in the-source documents.
The database thus functions as an aid in determining the classification of, components and subcomponents in procurement, maintenance, operations, and daily work planning.
The FNPIMS database was. stated to have been developed using the source documents and any design changes are entered into the database through an access authorization system which ensures that such changes to the database are.
made only by designated personnel authorized to do so.
The licensee states; that the database can be accessed from the plant site, the Birmingham General Office, and from the various design organizations.
The licensee also states that this database is used to determine. classification of equipment involved in routine maintenance, procurement actions, routine operations, and in-daily work planning through the MWR process.
3.0 CONCLUSION
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The staff has found acceptable the information provided by' the licensee -
l' concerning the Farley information handling system.
The staff _-has also found-l.
acceptable the licensee's submittals aadressing the other sub-items of this issue. Therefore, we conclude that the licensee's responses to Item 2.2.1 of
-Generic Letter 83-28 are acceptable.
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L Principal Contributor:
D. Lasher Date: May 1, 1990 m
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DISTRIBUTION Deskt~fHe NRC PDR i
Local PDR S. Varga 14-E- 4 L G. - Lai nas 14-H-3 E..Adensam 14-B-20' P. Anderson 14-B-2 0 S. Hoffman 14-B-20 S. Newberry 7-E-12' D. LaBarge 14-B-2 i
OGC (for inform. Only) 115-B-18 E. Jordan HNBB-3302 ACRS (10)
P-315 Farley Plant File
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