ML19257B635
| ML19257B635 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/27/1979 |
| From: | Dolan J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| AEP:NRC:00301A, AEP:NRC:301A, NUDOCS 8001180020 | |
| Download: ML19257B635 (3) | |
Text
Ttc lNDIANA MICHIGAN ELECTRIC COMPANY P. o. B o X 18 BOWLING GREEN ST ATloN N EW YORK. H. Y.10004 December 27, 1979 AEP:NRC:00301A Donald C. Cook Nuclear Plant Unit 2 Docket No. 50-316 License No. DPR-74 Mr. J. G. Keppler, Regional Director U.S. Nuclear Regulatory Coninission Office of Inspection and Enforcement Region III 799 Roosevelt Road Glen Ellyn, Il. 60137
Dear Mr. Keppler:
By our letter dated October 2,1978 (AEP:NRC:00084) we transmitted to you the Startup Test Report for the Donald C.
Cook Nuclear Plant Unit No. 2.
Attached to this letter and as promised in our letter (AEP:NRC:00301) of November 30, 1979 addressed to Mr. H. Denton, we are transmitting to you the results of the load rejection test. Two copies of the test report are enclosed with this letter, in compliance with the reporting requirements for startup testing set forth in Section 6.9.1 of the Technical Specifications and in Regulatory Guide 1.16.
Very truly yours, I.
ohn E. Dolan ice President cc:
R. C. Callen G. Charnoff D. V. Shaller -Bridgman
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s Mr. J. G. Keppler, Regional Director AEP:NRC:00301A Test Results (Continued) valves.
The wide range steam generator water level indicator (not compensated for water density) showed a quick initial drop from 52%
to a minimum of 37.5% in 1.0 sec and a quick recovery to about 47%
by 2.0 sec, above which it remained for at least 8 min. The pres-surizer level decreased from 58% to 31.2% in 1.0 min and to 27.55 in 7.0 min.
The no-load pressurizer setpoint was 23%. The pres-surizer pressure decreased from 2244 psi to a broad minimum of 2023 psi in 33 sec and recovered fully by 11 min.
Conclusion This test has demonstrated that a generator trip from 100%
power will cause a turbine trip and a reactor trip and the safe shutdown of the Unit.
No detrimental transients resulted and all systems and components performed adequately.
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ATTACHMENT TO AEP:NRC:00301A DONALD C. COOK NUCLEAR PLANT UNIT 2 FULL LOAD REJECTION / TURBINE TRIP TEST REPORT
Purpose:
The objective of this test was to verify that a generator trip will initiate a turbine trip and a reactor trip and will result in the Unit being brought to a safe shutdown with no detrimental transients during the process.
Initial State of Unit The Unit was stable at 100% power with the control rods, steam generator level, pressurizer level, pressurizer pressure and steam dump in TAV mode under automatic control. Manual transfer of the auxiliary loads to reserve power was done prior to the test in order to ensure power availability to the reactor coolant pump busses. Auxiliary power transfer has been verified in she past during Unit trips.
Initiation of Test The generator was tripped at 1205 'iours on July 21, 1979 by depressing the " Emergency Unit Trip' push button. This action caused operation of the Unit differential relay (at time = 0) causing the trip of the generator air circuit breakers, the trip of the generator excitation field breaker and the trip of both the left and right main turbine control systems. The latter trip caused closure of the main steam stop valves (closure complete at 1.02 sec) and the reheat stop valves (closure complete at 1.14 sec). The low pressure signal from the turbine control system (due to the turbi'ne trip condition) caused the trip of both reactor breakers B (~at 0.301 sec) and A (at 0.327 sec). Nuc. lear power decreased to 20% at 2.0 sec and 0% at 11.5 sec. 'he reactor trip caused automatic trip of the main feedwater pumps, isolation of main feedwater and startup of the auxiliary feedwater system.
Test Results At 1.73 sec, the turbine reached its maximum speed of 1854 rpm (3% overspeed), well below the overspeed setpoint. The steam dump and auxiliary feedwater systems functioned automatically to control the primary coolant average temperature (TAV),which decreased from 573.30F to 5470F in 60 sec and to 5400F in 15 min.
Main steam pressure increased from 816 psi to 955 psi in 7.5 sec, then approximately leveled off and reached a broad peak of 972 psi at 35 sec, remaining below the setpoint of the atmospheric relief 1767 351
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