ML19325E063
| ML19325E063 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 10/24/1989 |
| From: | Diianni D Office of Nuclear Reactor Regulation |
| To: | Parker T NORTHERN STATES POWER CO. |
| Shared Package | |
| ML19325E064 | List: |
| References | |
| GL-83-28, TAC-53705, TAC-53706, NUDOCS 8911010121 | |
| Download: ML19325E063 (4) | |
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UNITED STATES 4
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NUCLEAR REGULATORY COMMISSION
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October 24,.1989 o
Docket Nos.. 50-282/306 4
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6 Mr. T. M. Parker, Manager i
Nuclear Support Services Northern States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401
Dear Mr. Parker:
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NOS 1 AND 2, 1
' SAFETY EVALUATION FOR ITEH 2.2 (PART 1) 0F GENERIC LETTER 83-28. EQUIPMENT CLASSIFICATION (PROGRAMS FOR ALL SAFETY-RELATED COMPONENTS) (TAC NOS. 53705 AND 53706) i
' Generic Letter 83-28 was issued by the NRC On July 8,1983 to specify actions to be taker by licensees and applicants based on the generic implications of the j
t Salem ATWS events.
Item 2.2 (Part 1) of that letter states that licensees and
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applicants shall describe in considerable detail their program for classifying j
and identifying all safety-related components, other than Reactor Trip ~ System (RTS) components, as. safety-related on plant documents and in information i
handling systems that are used to control plant activities that may affect these-
~ components. Specifically, the licensee's/ 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)designverificationandqualificationtestingrequirements that are part of the specifications for procurement of safety-related components.
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Your response to Generic Letter 83-28, Item 2.2 (Part 1) was forwarded to the NRC staff by letters dated November 4,1983, and March 31, 1987 describing your program for identifying and clasrifying safety-related equipment other than RTS m
components. We have evaluated your program and concluded that it is acceptable.
Our conclusion is based on our A copy of our Safety (Evaluation is enclosed. EGG-NTA-7422), (April 1987), which is atta contractor's report Evaluation.
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Please contact the Prairie Island, Project flanager, Dominic Dilanni at 301 492-1309 if you have any questions concerning this action.
Sincerely, i
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C Dominic Dilanni. Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V & Special Projects
Enclosure:
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'Mr.-T.'N. Parker
. Northern States. Power Company Prairie Island Nuclear Generating
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. Plant cc:
' Gerald Charnoff, Esq..
. Shaw, Pitteen. Potts and Trowbridge 2300 N Street, N.W.-
' Washington, DC 20037 Dr.' J. W. Ferman Minnesota Pollution Control Agency 1h,,
520. Lafayette Road St. Paul, MN 55155 e
Mr. E. L. Watzl, Plant Manager
' Prairie Islar.c huclear Generating Plant
' Northern States Power Company _
Route 2-L';
Welch, Minne.sota' 55089 i
JosepF G. Ma'ternowski i
Assistant Attorney General Environmental Protection Division Silite 200
'520' Lafayette Road
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St. Paul,'Minnesotal 55155
.U.S. Nuclear Regulatory Commission Resident.Inspe: tor's Office 1
1719 Wakonade'Drtve' East Welch,flinnesota-55089 t
' Rgional Administrater, Region III U.S. Nuclear Regulatory Commission Office of Executive Dire'etor for l
Optratiors 799 Roosevelt Road.
i Glen Ellyn, Illinois 60137 Mr. William Miller, Auditor
.Goodhue County Courthouse
~ Red Wing, Minnesota 55066 o
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