ML19275A901
| ML19275A901 | |
| Person / Time | |
|---|---|
| Site: | Point Beach |
| Issue date: | 08/27/1979 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910220400 | |
| Download: ML19275A901 (6) | |
Text
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4;pa arag(o, UNITED STATES E
i NUCLEAR REGULATORY COMMISSION 3e E
WASW NGTO N, D. C. 20555
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AUG 2 71979 MEMORANDUM FOR: Brian K. Grimes, Assistant Director for Systems Engineering, D0R FROM:
G.'Lainas, Chief, Plant Systems Branch, DOR j
SUBJECT:
INSUFFICIENT DIESEL GENERATOR CAPACITY TO SIMULTANEDUSLY START EMERGENCY LOADS ON TWO UNITS AT POINT BEACH During the review of the Point Beach submittal in response to IEB 79-06 which required among other things that the licensee modify the 1/3 x 1/3 low pressurizer pressure / level logic to two-of-three low pressure for safety injection, a significant safety concern in the plant electrical system was detected.
This concern is stated most simply as, "certain single failures in one unit coincident with a LOCA in the opposite unit and a loss of offsite power will result in a transient over-loading of both redundant diesel generators." The two diesel generators are shared by both nuclear units. This transient over-load occurs at the point in time when the HPCI's of both units are started simultaneously being loaded onto the diesel generators. The diesel generators would be loaded beyond their "30 minute" rating.
We believe a solution is available to the licensee to correct this safety concern.
We discussed this matter with the ORPM and licensee on Friday, May 11.
The solution entails the installation of an additional station battery and two additional inverters.
The new battery with the two existing batteries for the station will energize three inverters in each plant.
The three engineered safety feature actuation channels of each plant will be energized from the three inverters. This arrangement will preclude the single failure (loss of a battery) which will initiate a safety injection signal. The licensee indicates that they do not plan to take corrective action unless required to do so by the NRC. With your concurrence, we are prepared to issue a safety evaluation as the basis for an order.
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We have reviewed other multiunit plants (ses Enclosure 1) to detemine if this problem exists elsewhere and have concluded that th's problem is peculiar only to the Point Beach Station.
i ai Plant Systems Bra ch Division of Operating Reactors
Enclosure:
As stated
Contact:
J. Burda' X-280-I cc w/ enclosure:
D. Eisenhut W. Russell W. Gammill A. Schwencer C. TranTnel G. Lainas D. Tondi R. Scholl P. Shemanski R. Kendall J. Burdain t
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