ML16341E126
| ML16341E126 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/18/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16341E127 | List: |
| References | |
| GL-83-28, NUDOCS 8703260482 | |
| Download: ML16341E126 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEN 4.5.2 REACTOR TRIP SYSTEM RELIABILITY, ON-LINE TESTING DIABLO CANYON NUCLEAR POMER PLANT, UNITS 1 AND 2 DOCKET NOS.
50-275 AND 50-323 Generic Letter 83-28 was issued by the NRC on July 8, 1983, indicating actions to be taken by applicants and licensees based on the generic implications of the Salem ATHS events (Reference 1).
Item 4.5 states the staff position which requires on-line functional testing of the reactor trip system (RTS), including independent testing of the diverse trip features of the reactor trip breakers, for all plants.
Item 4.5.2 requires applicants and licensees with plants not currently designed to permit this periodic on-line testing to justify not making modifications to permit such testing.
By letters dated November 7, 1983 (Reference
- 2) and June 27, 1984 (Reference 3), Pacific Gas and Electric Company, the licensee for the Diablo Canyon Plant, responded to the staff position regarding Item 4.5.2 of Generic Letter 83-28.
The licensee states in Reference 2 that the Diablo Canyon Power Plant, Units 1
and 2, are designed to allow on-line testing of the reactor trip system and in Reference 3 that this on-line testing includes independent testing of the undervoltage and shunt trip attachments of the reactor trip breakers.
The staff was assisted in its evaluation by its consultant, the Idaho National Engineering Laboratory (EGAE Idaho) who prepared the attached report (Enclosure A).
The staff concurs with the conclusions stated in the report.
The staff concludes that the Diablo Canyon Nuclear Power Plant, Units 1 and 2, are designed to permit on-line functional testing of the reactor trip system, including independent testing of the diverse trip features of the reactor trip breakers.
Thus, the licensee meets the staff position of Item 4.5.2 of Generic Letter 83-28 and this item is closed.
PRINCIPAL CONTRIPUTOR:
D. Lasher (PAEI)
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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 83-18)," July 8, 1983.
k 2.
Letter from J. 0. Schuyler (PG&E) to D.
G. Eisenhut (NRC), "Generic Letter 83-28:
Required Actions Based on Generic Implications of ATWS Events,"
November 7, 1983.
3.
Letter from J. 0. Schuyler (PG&E) to D. G. Eisenhut (NRC), "Test Procedures for Shunt Trip Modification and Generic Letter 83-28, Item 4.5.1,"
DCL 84-241, June 27, 1984.
ENCLOSURES:
A.
Idaho National Engineering Laboratory (EG&E Idaho), "Input for Safety Evaluation Report:
Beaver Yalley Power Station Units 1 and 2, Braidwood Station Units 1 and 2, Byron Station Units 1 and 2, Callaway Plant Unit 1, Catawba Nuclear Station Units 1 and 2, Comanche Peak Steam Electric Station Units 1 and 2, Donald C.
Cook Nuclear Power Plant Units 1 and 2, Diablo Canyon Units 1 and 2, Reactor Trip System Reliability Item 4.5.2 of Genreic Letter 83-28," F.
G. Farmer, November 1986 (EGG-NTA-7458).