ML20212B567
| ML20212B567 | |
| Person / Time | |
|---|---|
| Site: | Millstone, 05000000 |
| Issue date: | 02/24/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20211K514 | List: |
| References | |
| GL-83-28, NUDOCS 8703030589 | |
| Download: ML20212B567 (1) | |
Text
4 SAFETY EVALUATION RED 0DT DOCKET NO. 50-473 MILLSTONE NUCLEAR POWER STATION, UNIT ?
GENERIC LETTER 83-78, ITEM 4.5.7 REACTOR TRIP RELI ABILITY, ON-LINE TESTI%
INTRODUCTION ann
SUMMARY
Generic Letter 83-?R was issued by NRC on July 8,1983, indicatino actions to be taken by applicants and licensees based on'the generic implications of the Salen ATWS events. Item 4.5 states a staff position which reautres on-line functional testing of the reactor trip system, including independent testing of the diverse trip features nf the reactor trip breakers, for a,ll plants.
Iten 4.5.7 requires applicants and licensees with plants'not currently designed to permit this peri-edic on-line testing to,iustify not making modifications to permit such testina.
By letter dated November 8,1983, the licensee, Northeast Nuclear Eneroy Company, responded to the staff position regarding Item 4.5.2 of Generic Letter 83-28.
Our review of this response finds it to be acceptable.
EVALUATION The licensee states that the Millstone Nuclear Powar Station, Unit 3 is designe i
to allow on-line functional testing of the Reactor Trip System and that procedures will be developed to perforn independent testing of the undervoltage and shunt trip attachments.
CONCLUSION The staff finds that the Millstone Nuclear Power Station, Unit 3 is designed permit on-line functional testing of the reactor trip system, including indepe testing of the diverse trip features of the reactor trip breakers Thus, the applicant meets the staff position of Item A.S.? of Generic letter 83 78 8703030589 B70224 PDR ADOCK 05000423 P