ML20196L642
| ML20196L642 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire, 05000000 |
| Issue date: | 05/06/1988 |
| From: | Robert Davis DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20196L539 | List: |
| References | |
| NUDOCS 8807080089 | |
| Download: ML20196L642 (52) | |
Text
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ATTACIDIENT III i
e DUKE POWER COMPANY McGUIRE NUCLEAR STATION ATWS MITIGATION SYSTEMS ACTUATION CIRCUITRY
- RESPONSE TO UNIT TRANSIENTS d
R. KENT DAVIS NUCLEAR PRODUCTION ENGINEER McGUIRE NUCLEAR STATION MAY 6,1988 0
9 8807060089 880601 PDR ADOCK 05000369 ,
P PDC
4 f
CONTENTS 1
INTRODUCTION...............................................
CALCULATIONS............................................... 2 VALVE POSITION RESPONSE DURING RUNBACKS.................... 3 PREDICTIONS FOR FULL LOAD REJECTIONS....................... 5 MODIFICATIONS TO THE INITIAL CIRCUITRY DESIGN.............. 6 7
CONCLUSIONS................................................
s
LIST OF FIGURES SEPTEMBER 1,1987 McGUIRE UNIT 2 Feedwater Regulating Valve Position (Bypass valves open) A.1 A.2 Steam Generator Level A.3 Feedwater & Steam Flow A.4 Reactor Power A.5 Average Loop T-AVG Feedwater Regulating Valve Position & Differential Pressure Across Valve A.6 Fe6dwater Regulating Valve Position (Bypass valves closed) A.7 I
NOVEMBER 24,1987 McGU RE UNIT 2 I
Feedwater Regulating Valve Position (Bypass valves open) B.1 B.2 Steam Generator Level B.3 Feedwater & Steam Flow B.4 Reactor Power B.5 Average Loop T-AVG Feedwater Regulating Valve Position & Differential B.6 Pressure Across Valve B.7 Feedwater Regulating Valve Position (Bypass valves closed)
JANUARY 4,1985 McGUIRE UNIT 2 Feedwater Regulating Valve Position (Bypass valves open) C.1 C.2 Steam Generator Level C.3 Feedwater & Steam Flow C.4 Reactor Power C.5 Average Loop T-AVG F.aedwater Regulating Valve Position & Differential C.6 Pressure Across Valve C.7 Feedwater Regulating Valve Position (Bypass valves closed)
Pago 1 of 49 l INTRODUCTION The ATWS Mitigation Systems Actuation Circuitry (AMSAC) provides protection for ATWS conditions by tripping the main turbine and initiating auxiliary feedwater upon sensing a total loss of normal feedwater. This loss of normal feedwater is sensed by a trip of both main feedwater pumps or the blockage of three-out-of-four main feedwater flowpaths. This system is based upon the Westinghouse Owners, Group (WOG) WCAP-10858 "AMSAC :
Generic Design Package" generic design 3. A feedwater flowpath l is considered blocked if the Main Feedwater Containment Isolation valve is closed or if the Main Feedwater Regulating valve is less than 25% open. The AMSAC circuit actuates if the three-out-of-four flowpath blockage condition exists for greater than 30 seconds above 404 power (turbine impulse pressure).
After the original design and NRC approval process was completed, plant operating procedures were slightly modified to allow operation chove 50 percent power levels with the Feedwater Control Bypass Valves (FCBVs) fully open. This operating change was found to produce an offset in the respective Feedwater Control Valves (FCVs) which would impact the accuracy of the flowpath monitoring portion of the AMSAC design.
During unit runback or full load rejections, the feedwater regulating valves will modulate to less than 25% open due to the nature of the transient even above the 40% threshold that AMSAC is required to operate. This condition would result it, a unit l
trip during a runback to 50% power or during a full load rejection. If the full load rejection had occurred due to a i
! separation from the system, then a unit blackout will result following the turbine trip.
The new operating procedure was analyzed and found to have flowpath arrangements which were very similar to those associated with the Feedwater Isolation Valves (FIVs) of the D5 model steam generators. Because of this similarity, flowpath blockage can only occur if both the FCV and FCBV are closed or the FIV is closed.
This study shows the feedwater regulating valve position response l using actual plant transient data and describes the circuit changes developed by Duke Power Company Design Engineering and Nuclear Production Departments. These changes should reduce the vulnerability to spurious trips during controlled transients while maintaining the reliability of the AMSAC system to perform it's intended function.
l l
l Pega 2 of 49 CALCULATIONS Data from actual McGuire transients is analyzed to estimate the Main Feedwater Regulating valve position. Individual steam generator feedwater flow is calculated from the feedwater flow nozzle data, feedwater temperature, and the differential pressure across the nozzle.The differential pressure across the main feedwater regulating valve is estimated from main feed pump discharge pressure and main steam pressure using a correction calculation for pressure drop thru the piping as a function of flow.The feedwater flow for a given valve and the differential pressure across the valve are then used to calculate the flow passing capability of the valve CV.Since McGuire operates with the main feedwater regulating bypass valves full open above 50 %
power, this CV is the total Cv for both valves in parallel.The CV for the main feedwater regulating valve is calculated by subtracting the CV for the bypass valves from the total CV for both valves.From data curve McM-1201.08-03 (Main Feedwater Regulating Valve % CV vs. % Valve Lift) the valve position in % open is obtained.The data curves generated show the main valves position for the case of the bypass valves open (normal operation) and for the case of the bypass valves being closed.
Additional data from these transients show Nuclear Power and Reference Power (Turbine Impulse Pressure), T-Average and T-Reference (from Turbine Impulse Pressure), % Feedwater flow and % Steam flow for a typical steam generator, typical steam generator level, and Main Feedwater Regulating Valve position and differential pressure across the valve.
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Pegs 3 of 49 VALVE POSITION RESPONSE DURING,RUNBACKS l
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Three runback transients fro 9 McGuire Nuclear Station have been analyzed to determine the response of the main feedwater l regulating valve.Two of these transients involved the loss of one main feedwater pump from near full load which resulted in a runback to 56 % power.In these transients, steam flow is initially greater than feedwater flow until the reactor has runback to match turbine load.This causes steam generator level to drop until steam flow becomes less than feedwater flow.Then steam generator level will start it's recovery and will overshoot the setpoint until the feedwater regulating valves and feedwater pump reduce feedwater flow to match steam flow.The overshoot is caused by the integral action of the feedwater control system.It is during this feedwater flow reduction phase that the feedwater regulating valves modulate to less than 25 % open.This effect is aggravated by the feedwater regulating bypass valves which are full open (in manual) by McGuire's normal mode of operation.
The third transient analyzed involved the loss of one busline resulting in a runback to 56 4.Here, the feedwater flow and steam flow stay more closely matched during the runback but the feedwater regulating valves still modulate to less than 25 %
open.Again, this condition occurs on a half load rejection due to the feedwater regulating bypass valves being open.This transient is of particular value for extrapolating to the full load rejection condition.
l The data shown in the figures and discussed below show various l
key parameters vs. time in seconds.The tima marked 0 is tne point that the runback was initiated and the data to the left is the steady state conditions existing prior to the transient.
LOSS OF FEEDWATER PUMP SEPTEMBER 1,1987 McGUIRE 2 On September 1,1987 McGuire Unit 2 was operating at 100 % power when one main feeddater pump turbine tripped.The feedwater regulating valves. modulate full open and the feedwater pump turbine operates with the steam control valves full open to provide the maximum feedwater flow possible with one pump. Figure A.3 shows the feedwater flow in this condition to be spproximately 70 %.As the reactor runback continues, steam flow Jacones less than feedwater flow at approximately 100 seconds. As steam generator level recovers, the feedwater regulating valve modulates closed beginning at 250 seconds and shows fully closed at 370 seconds.
Page 4 of 49 f
Steam generator level drops back to setpoint and the feedwater regulating valve again opens to maintain leve at setpoint.The ef fect of the bypass regulating valve being open can be seen by comparing the main valve positions shown in Figure A.1 and A,7. A second level overshoot occurred and the feedwater regulating valve is observed less than 25 % open at 750 seconds.Both times, the valve is less than 25 % open for greater than thirty seconds.Thus the AMSAC system as designed in the Westinghouse Generic Design option 3 would have resulted in a unit trip if installed.
LOSS OF FEEDWATER PUMP NOVEMBER 24,1987 McGUIRE 2 On November 24,1987 McGuire Unit 2 experienced another runback to 56 4 power due to the loss of one main feedwater pump.The basic transient is the same as the September 1,1987 transient except that load was beimg reduced to remove the troubled feedwater pump from service when it failed.The runback actually started from approximately 84 % power.The feedwater regulating valve is observed at less than 25 % at 550 seconds and remains there for 205 seconds.Again the AMSAc system as designed in the Westinghouse Generic Dasign option 3 would have resulted in a unit trip if installed.
LOSS OF BUSLINE JANUARY 4,1985 McGUIRE 2 On January 4,1985 McGuire Unit 2 lost one busline resulting in a runback to 56 % power. Note the high feedwater flow in relation to steam flow initially.This is opposite from the loss of feedwater pump transient as expected and results in a more controlled runback. Steam flow and feedwater flow then are more closely matched thru the remainder of the transient.However, the greater feedwater flow initially forces steam generator level high and the decrease in setpoint as reactor power decreases force the feedwater regulating valve below 25 % open at approximately 165 seconds.The valve opens above 25
- after 100 seconds.The AMSAC system as designed in the Westin w use Generic Design option 3 would have trippe$.,the unit if installed.
9
Pega 5 of 49 PREDICTIONS .OR FULL LOAD REJECTIONS The loss of busline runback from January 4,1985 on McGuire unit 2 provides the data to predict the effects during a full load rejection.Since the turbine will continue to runback to between zero and ten percent impulse pressure,the reactor can be expected to runback at maximum rod speed until approximately forty percent.This will cause steam flow and feedwater flow to decrease at the same initial rate but for a longer period of time.From the January 4,1985 transient, this rate is observed during the first 180 seconds.This rate will cause the main feedwater regulating valve to close to less than 25 % open at approximately 170 seconds.Since the turbine runback is at 200 % per minute, turbine impulse pressure will fall below 40 % at 18 seconds.This leaves the operator about 2.5 minutes in which to block the AMSAC circuitry or experience a turbine trip.If the full load rejection had occurred due to a separation from the grid,then a unit blackout will result and a loss of forced reactor coolant.This condition is highly undesirable since natural circulation cooling must be established on a unit that has been operating at full power and due to the potential for damage to the secondary plant during hot restart conditions.The 2.5 minute time span available for manual blocking is extremely short during this type of transient and forces the attention of the operator away from the plant as a whole into a single critical operation.
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Pags 6 of 49 f
l MODIFICATIONS TO THE INITIAL CIRCUITRY DESIGN The high potential for spurious trips outlined previously necessitated a redesign of portions of the AMSAC circuitry from the initial design as approved by the NRC for McGuire Nuclear Station.The first change involves adding an automatic block of the AMSAC function when turbine impulse chamber pressure has decreased below 40 %.This automatic block occurs after a 120 second time delay as specified in the Westinghouse Generic Design Package.By automatically blocking the AMSAC trip circuit,the operator is relieved of the burden of manually blocking during a full load rejection.Since this decreases the probability of a unit blackout on a separation from the grid,the margin of safety of the unit is increased. Manual block capability is maintained for the operator provided impulse pressure is less than 40 %.
The second change is a modification of the feedwater regulating valve status indication.Since McGuire is operating with the feedwater regulating bypass valves open above 50 % power, credit is taken for the flow available to the steam generator thru thy bypass valve even if the main feedwater regulating valve were to close.This is accomplished by monitoring the bypass valve position instead of the main valve position (25 %) as long as the bypass valve is in the full open position.If the bypass valve is not full open, then the circuit monitors the main valve position to ensure the main valve is greater than 25 % open.This approach is suitable since Westinghouse has indicated the required flow is 15 % of nominal full load flow. (The CV for the main feedwater regulating valve at 25 % open is 15 %).The CV for the bypass valve when full open is 18% of the ce for the main valve.Thus for the same conditions of valve differential pressure assumed in the Westinghouse generic analysis, the bypass valve will provide equal o." slightly greater flow.This modification will reduce the probability of spurious trips during controlled transients such as runbacks to 50 % load.
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Pcg3 7 cf 49 CONCLUSIONS The circuitry changes described in this document should improve the reliability of the unit to withstand non-ATWS events without detracting f. rom the ability of the AMSAO system to perform it's design function.These changes are unique to McGuire Nuclear Station as a result of operating with the feedwater bypass valves open above 50 % power. operation with the bypass valves open has shown to be very beneficial to certain operating transients and therefore it is thc station's plans to continue in this manner.Tha operating department of McGuire Nuclear Station feels that the modified AMSAC system will best meet the station's and the NRC's requirements for maintaining nuclear safety and plant reliability at the same time.
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