ML13330B303
| ML13330B303 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/25/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13330B302 | List: |
| References | |
| GL-83-28, NUDOCS 8805040347 | |
| Download: ML13330B303 (6) | |
Text
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ENCLOSURE 1 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION REPORT SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 1 DOCKET NO. 50-206 GENERIC LETTER 83-28, ITEM 2.2.1 EQUIPMENT CLASSIFICATION PROGRAMS FOR ALL SAFETY-RELATED COMPONENTS
1.0 INTRODUCTION
Generic Letter 83-28 was issued by the NRC on July 8, 1983 to indicate actions 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 RTS 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/
applicant's submittal was required to contain information describing (1) the criteria used to identify these components as safety-related; (2) the 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) management controls that are used to verify that the information handling system is prepared, maintained, validated, and used in accordance with approved procedures; and (5) design verification and qualification testing requirements that are part of the specifications for procurement of safety-related components.
The licensee for San Onofre Nuclear Generating Station, Unit 1 submitted a response to Generic Letter 83-28, Item 2.2.1 in a submittal dated November 28, 1983. We have evaluated this response and find it to be acceptable.
8805040347 880425 PDR ADOCK 05000206 PDR
-2 2.0 EVALUATIONS AND CONCLUSIONS In these sections the licensee's responses to the program and each of five sub items are individually evaluated against guidelines developed by the staff and conclusions are drawn regarding their individual and collective acceptability.
- 1. Identification Criteria Guideline: The licensee's response should describe the criteria used to identify safety-related equipment and components.
(Item 2.2.1.1)
Evaluation:
The licensee states that equipment that is part of safety-related systems is classified as safety-related. Component and system function, interfaces, General Design Criteria, 10 CFR 50, ANSI N18.2 and applicable regulatory guides are cited as additional basis for classification of a component as safety-related.
==
Conclusion:==
The licensee's submittal meets the staff requirements for this item and is acceptable.
- 2. Information Handling System Guideline:
The licensee's response should confirm that the equipment classification program includes an information handling system that is used to identify safety-related equipment and components. Approved procedures which govern its development, maintenance, and validation should exist.
(Item 2.2.1.2)
-3 Evaluation:
The licensee identifies the Q-list as the information handling system that lists safety-related equipment. The Q-list is developed, reviewed, approved and controlled in accordance with Quality Assurance Program Procedures.
==
Conclusion:==
The licensee's submittal, for this item, meets staff requirements and is acceptable.
- 3. Use of Information Handling System Guidelines:
The licensee response should confirm that their equipment classification program includes criteria and procedures which govern the use of the information handling system to determine that an activity is safety-related and that safety-related procedures for maintenance, surveillance, parts replacement and other activities defined in the introduction to 10CFR50, Appendix B, are applied to safety related components. (Item 2.2.1.3)
Evaluation:
The licensee states that procedures are written using the Q-list to determine if an activity is safety-related. The licensee describes how each station organization verifies that a given procedure is current.
==
Conclusion:==
The licensee's submittal meets the staff requirements and is acceptable, for this item.
-4
- 4. Management Controls Guideline: The licensee/applicant should ccnfirm that management controls used to verify that the procedures for preparation, validation, and routine utilization of the information handling system have been and are being followed. (Item 2.2.1.4)
Evaluation:
The licensee states that their Quality Assurance Program serves as the method of managerial control. These controls identify management responsibilities and are stated to require strict adherence to procedures, applicable interdisiplinary reviews and control of documentation.
==
Conclusion:==
The licensee's submittal meets the staff requirements for this item and is acceptable.
- 5. Design Verification and Procurement Guideline: The licensee/applicant's response should document that past usage demonstrates that appropriate design verification and qualification testing is specified for the procurement of safety-related components and parts. The specifications should include qualification testing for expected safety service conditions and provide support for licensee's receipt of testing documentation which supports the limits of life recommended by the supplier. If such documentation is not available, confirmation that the present program meets these requirements should be provided. (Item 2.2.1.5)
-5 Evaluation:
The licensee's submittal specifies that Material Control Procedures require the application of the proper technical and quality requirements. Inspections and audits imposed by these procedures are used to assure the appropriate design and manufacture. The environmental qualification package must be completed, before an item is used in plant operations.
==
Conclusion:==
The licensee's submittal meets.the staff requirements and is acceptable, for this item.
- 6. "Important To Safety" Comments Guideline: Generic Letter 83-28 states that licensee/applicant equipment classification programs should include (in addition to the safety-related components) a broader class of components designated as "Important to Safety." However, since the generic letter does not require licensee/
applicant to furnish this information as part of their response, staff review of this sub-item will not be performed.
(Item 2.2.1.6)
- 7. Program Guideline:
Licensees/applicants should confirm that an equipment classification program exists which provides assurance that all safety-related components are designated as safety-related on plant documents such as drawings, procedures, system descriptions, test and maintenance instructions, operating procedures, and information handling systems so that personnel who perform activities that affect such safety-related components are aware that they are working
-6 on safety-related components and are guided by safety-related procedures and constraints. (Item 2.2.1)
Evaluation:
The licensee's response to these requirements was contained in a submittal dated November 28, 1983. This submittal describes the licensee's program for identifying and classifying safety-related equipment and components which meet the staff requirements as indicated in the preceding sub-item evaluations.
==
Conclusion:==
We conclude that the licensee's program addresses the staff concerns regarding equipment and component classification and is acceptable.
3.0 REFERENCES
- 1. NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits, "Required Actions Based On Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.
- 2. Letter, Southern California Edison Company (M. 0. Medford) to Director, Office of Nuclear Reactor Regulation, NRC (D. M. Crutchfield), "Generic Letter 83-28: Required Actions Based on Generic Implications of Salem ATWS Events," Nov. 28, 1983