ML19256C765
| ML19256C765 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/07/1979 |
| From: | Jordon E, Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| References | |
| PNO-79-070, PNO-79-70, NUDOCS 7910120442 | |
| Download: ML19256C765 (1) | |
Text
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i PRELIMINARY NOTIFICATION April 7, 1979 (Y )
PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PNO-79-70 This preliminary notification constitutes EARLY notice of an event of POSSIBLE safety or public interest significance.
The information presented is as initially received without verification or evaluation and is basically all that is known by IE as of this date.
Facility:
Florida Power Corporation Crystal River 3 Docket No. 50-302 Crystal River, Florida
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Subject:
UNANTICIPATED LOAD REDUCTION While operating at full power on April 6, the seal leakage on reactor coolant pump nxuoar 38 increased from less than 1 gpm (normal) to 2.4 gpm.
On recommendation of Babcock and Wilcox, reactor power was reduced to approxi-mately 60% and the leaking pump was shutdown at 3:25 p.m., April 6.
Reactor instrumentation overpower trip points were reduced to 77%.
At approximately 4:15 p.m. the licensee attempted to change the turbine ioad limiter control from 100% to 75%.
Instantaneously the load limiter dropped to zero demand.
This action resulted in an unexpected down ramp in turbine output when all turbine control valves shut.
Electrical output dropped from 600 to 150 mwe.
Reactor pressure rose to 2250 psi but was quickly reduced to 1970 psi by the pressurizer relief valves which operated at 2100 psi.
Pressure stabilized at 2100 psi in about 2 minutes.
During the transient a 65-inch swing in pressurizer level was experienced.
The load limiter was manually returned to 100% and the plant returned to stable operation without a reactor trip.
During the transient all safety features functioned as expected and tt.e operators response was satisfactory.
The reactor continues in operation at 75% power with three of the four reactor coolant pumps operating.
The total leakage from the 38 pump is 3.03 (2.94 identified and 0.09 controlled leakage).
Technical Specification limits are 10 gpm maximum.
An NRC inspector was on site during the event and had just completed a planned discussion of the Three Mile Island accident with the licensed operators on duty.
There has been no media interest however media interest is expected based on the noise associated with main steam safety valve operation and interest in B&W facilities at this time.
The licensee has not issued a press release NRC does not plan a press release.
The State of Florida has been informed.
CONTINUED 1452 337
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Continued Ap-il 7, 1979 Page 2 PNO-79-70 Region II (Atlanta) received notification of this occurrence by telephone from IE inspector on site at 7:30 p.m. on April 6.
This information is current as of 11:00 a.m. on April 7.
Contact:
E. Jordan, IE x28180 N. C. Moseley, IE x28160 Distribution:
Transmitt'ed H St 9 / /6 Bn Chairman Hendrie Commissioner Bradford S. J. Chilk, SECY Commissioner Kennedy Commissioner Ahearne C. CT Kammerer, CA Commissioner Gilinsky (For Distribution)
Trahamitted:
MNBB 7-
/#7 P. Bldg 7.YffB1 J.G.DavisOg I
L. V. Gossick, EDO H. R. Denton, NRR Region I 7-g /C/o C f/2 H. L. Ornstein, EDO R. C. DeYoung, NRR J. J. Fouchard, PA R. J. Mattson, NRR N. M. Haller, MPA V. Stello, NRR (MAIL)
R. G. Ryan, OSP
~R. S. Boyd,0 4NRJ J. J. Cummings, 0IA SS Bldg 71 R. Minogue, SD H. K. Shapar, ELD W. J. Dircks, NMSS PRELIMINARY NOTIFICATION 1452 338 w
.