ML17056A303
| ML17056A303 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/20/1989 |
| From: | Slosson M Office of Nuclear Reactor Regulation |
| To: | Burkhardt L NIAGARA MOHAWK POWER CORP. |
| Shared Package | |
| ML17056A304 | List: |
| References | |
| CON-IIT07-437-91, CON-IIT7-437-91 GL-83-28, NUREG-1455, TAC-53692, TAC-71821, NUDOCS 8909260007 | |
| Download: ML17056A303 (8) | |
Text
~ jr
~
~
QgR AEONS P0 Cy n
C
~
O I
C 0
r+
o~
+**++
UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON,D. C. 20555 September 20, 1989 Docket Nos. 50-220 and:.50;410.
'r.
Lawrence Burkhardt III Executive Vice President Nuclear Operation Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212
Dear Hr. Burkhardt:
SEP =;-;
C I
'I
'/
s <g~
SUBJECT:
SAFETY EVALUATION REPORT FOR GENERIC LETTER 83-28, ITEM 2.2.1 (EQUIPMENT CLASSIFICATION PROGRAM FOR ALL SAFETY-RELATED COMPONENTS),
FOR NINE MILE POINT UNITS 1 AND 2 (TAC NOS.
53692 AND 71821)
Generic Letter 83-28, Item 2.2.1, required that licensees and applicants "describe their program for ensuring that all components of safety-related systems necessary for accomplishing required safety functions are identified as safety-related on documents, procedures, and information handling systems used in the plant to control safety-related activities, including maintenance, work orders and replacement parts."
Item 2.2.1 applies to equipment clarification.
By letters dated November 8, 1983, December 31, 1985, and October 17, 1988 for Nine Mile Point Unit 1 and April 10, 1984, December 20, 1985 and April 15, 1986 for Nine Mile Point 2, Niagara Mohawk submitted a response to Generic Letter 83-28, Item 2.2.1.
The NRC staff and our contractor, Idaho National Engineering Laboratory (INEL), have reviewed the responses and have concluded that they are acceptable.
The staff's Safety Evaluation and INEL's Technical Evaluation Report (EGG-NTA-7275) are enclosed.
Based on our review, we consider Generic Letter 83-28, Item 2.2.1, to be resolved.
Sincerely, m
Harylee
. Slosson, Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/enclosure:
See next page
~2 (.5 Rgp:
RECEIVED SEP 25.lJu>
NUCLEAR LICEg$jgQ
l l
)
1
IC Mr. Lawrence Burkhardt III Niagara Mohawk Power Cor poration Nine Mile Point 1/2 CC ~
Hr. Troy B. Conner, Jr., Esquire Conner 5 Wetterhahn Suite 1050 1747 Pennsylvania
- Avenue, N.W.
Washington, DC 20006 Hr. Kim Dahlberg Unit 1 Station Superintendent Nine Mile Point Nuclear Station Post Office Box 32
- Lycoming, New York 13093 Supervisor Town of Scriba R. D. 84
- Oswego, New York 13126 Hr. Richard Abbott Unit 2 Station Superintendent Nine Mile Point Nuclear Station Post Office Box 32
- Lycoming, New York 13093 Mr. James L. Willis General Supt.-Nuclear Generation Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Post Office Box 32
- Lycoming, New York 13093 Charlie Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Resident Inspector U. S. Nuclear Regulatory Commission Post Office Box 126
- Lycoming, New York 13093 Mr. Paul D. Eddy State of New York Department of Public Service Power Division, System Operations 3 Empire State Plaza
- Albany, New York 12223 Mr. Gary D. Wilson, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Hr. Peter E. Francisco, Licensing Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Richard Goldsmith Syracuse University College of Law E. I. White Malle Campus
- Syracuse, New Yor k 12223 Hs.
Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor
- Albany, New York 12223 Mr. Richard H. Kessel Chair and Executive Director State Consumer Protection Board 99 Washington Avenue
- Albany, New York 12210
1 l
ENCLOSURE 1
NINE MILE POINT NUCLEAR STATION UNITS 18I2 DOCKET NOS. 50-220 50-410 GENERIC LETTER 83-28 ITEM 2.2.1 E UIPMENT CLASSIFICATION PROGRAM 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 Nine Mile Point, Units 1&2 submitted responses to Generic Letter 83-28, Item 2.2.1 in submittals for Unit 1 dated November 8, 1983, December 31, 1985, and October 17, 1988, and for Unit 2 dated April 10, 1984, December 20, 1985, and April 15, 1986.
Me have evaluated these responses and find them to be acceptable.
2.0 DISCUSSION AND EVALUATION The Niagara Mohawk Power Corporation, the licensee fot'ine Nile Point Nuclear Station, Units 152 provided submittals that describe 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 system that are used to control safety-related plant activities.
A description of the criteria used for classifying components and equipment as safety-related and a description of the preparation, maintenance, control and use of the information handling system which contains the classification information were also provided.
In addition, management controls used by the licensee assure that the information handling system will be consistent, adequately prepared and maintained, and will be used as intended.
Furthermore, the licensee assures that appropriate design verification and qualification is specified for the procurement of safety-related components and parts.
Detailed evaluation of this item is documented in the contractor's technical report EGG-NTA-7275 (Enclosure 2).
3.0 CONCLUSION
The staff and our contractor have reviewed the licensee's responses to Generic Letter S3-28 Item 2.2.1 regarding the equipment classification program for safety-related components and conclude that they are acceptable.
1 A