ML20205Q807
| ML20205Q807 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/30/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205Q792 | List: |
| References | |
| GL-83-28, NUDOCS 8704060058 | |
| Download: ML20205Q807 (1) | |
Text
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j' SAFETY EVALUATION REPORT DOCKET NOS. 50-787/306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1,9 l
GENERIC LETTER 83-78, ITEM 4.5.7 REACTOR TRIP SYSTEM RELIARILITY-DN-LINE TESTING
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3 INTRODUCTION AND
SUMMARY
Generic Letter 83-28 was issued by NRC on July 8,1983, indicating actions to be taken by applicants and licensees based on the generic implications of the Salen i
ATWS events.
Item 4.5 states a staff position which requires on-line functional testing of the reactor trip system, including independent testing of the diverse 4
j trip features of the reactor trip breakers, for all plants.
Item 4.5 ? requires applicants and licensees with piants not currently designed to permit this peri-l odic on-line testing to justify not making modifications to permit such testing.
Ry letters dated November 4,1983, and July 6,1984, the licensee, Northern ' States I
Power Company, responded to the staff position regarding item 4.5.2 of Generic i
Letter 83-28. Our review of these responses finds them to be acceptable, i
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EVALUATION 1
The licensee states that Prairie Island is designed to permit on-line testing of the Reactor Trip System and independent testing of the undervoltage and shunt trip attachments of the reactor trip breakers.
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CONCLUSION I
t The staff finds that the Prairie Island Nuclear Generating Plant, Units 1,?,
is designed to permit on-line functional testing of the reactor trip system,
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including independent testing of the diverse trip features o'f the reactor trip breakers. Thus, the applicant meets the staff position of Item 4.5.2 of Generic Letter 83-28 07040600h M h e2
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