ML19338F561
| ML19338F561 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/10/1980 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19338F555 | List: |
| References | |
| TP-1-A-2150-23, NUDOCS 8010200577 | |
| Download: ML19338F561 (11) | |
Text
TP/1/A/2150/23
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DUKE PO'1ER COMPANY McGUIRE NUCLEAR STATION 7 hr-NATURAL CIRCULATION WITH SIMULATED LOSS OF OFFSITE POWER FOR INFORMATION RfDl0R BEY!EW ONI.Y 1.0 Purpose
'1.1 To demonstrate that, following a simulated loss of offsite AC power, natural circulation cooling can be established and maintained while the diesel generators are supplying power to the appropriate loads.
2.0 References 2.1 System Description - Chemical and Volume Control System, MC-1223-04, Rev. 2.
2.2 System Description - Safety Injection System, Addendum 1 (Upper Head Inj ection System), MC-1223-12, Rev. O.
2.3 System Description - Auxiliary Feedwater System, MC-1223.42, Rev. 4.
2.4 System Description - 4160 Essential Auxiliary Power System, MCSD-Oll5-00, Rev. 4.
3.0 Time Required 3.1 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 3.2 Manpowei needed - 2 engineers 4.0 Prere'quisite *.'ests Initial /Date
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4.1 TP/1/A/2150/20, Natural Circulation Verification 4.2 E, _,...' 212-:, _;,
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5.0 Test Equipment 5.1 OAC - Transient Monitor Program 5.2 Reactivity. Computer - (Flux, reactivity, Wide range T de
- H0T, range TCOLD) 5.3 OAC - Thermocouple Map Program.
5.4 CAC - Subcooling from Saturated Conditions Curve.
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'6.0 Limits'rnd Pr"c utions
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~6.l' An operator initiated. safety injection should be performed if the reactor coolant system subcooling;is less than or equal to 10 F.
6'. 2 An operator. initiated reactor trip should be performed for one or more of the following conditions:
6.2.1 If the reactor coolant system subcooling is less than 10 F.-
6.2.2-
'If one of_three excore power range detectors indicates
-a reactor power greater than or equal to 10% F.P.
6.2.3' If'any NC loop average temperature exceeds 588 F.
6.2.4 If any'NC loop delta temperature exceeds 58 F.
6.2.5 If any NC loop hot leg temperature exceeds 617 F.
6.3 Do not exceed 5% F.P. at any time during the test.
6.4 Avoid any sudden changes in feedwater flow, steam generator level, or steam pressure.
6.5 Without forced reactor coolant flow, the narrow range temperatures (TCOLD **
AVG) may be unreliable. Wide range instrumentation should be used.
6.6 Whenever possible maintain NC system cold leg temperature stable.
This will minimize errors in NI power dete.rmination.
6.7 Ensure that control bank D position remains at >100 steps with-drawn. If this limit is reached, boron concentration must be increased.
6.8 Maintain pressuri er level greater than 20* level.
6.9 Ensure seal flow is maintained to the reactor coolant pumps during the test.
6.10 Should a~ reactor trip take place during the performance of this j
test, restart at least one reactor coolant pump prior to closing to.LI h*d N,, #f
- *#8pttons e4 w6ter i s 'av M ( htt tn WL "M" 7.0 Required Unit Status-w,p va, 7.1 The. unit is in startup mode (ModeL2).
8.0 Prerequisite Svstem conditions
'Initir.1/Date
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8.1 Reactor is critical and in MANUAL rod control at -l% power with j
control bank D in Bank Select and at -160 steps withdrawn or as
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.specified by the test coordinator.
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g Initial / Data.
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8.2 All four reactor' coolant pumps are-in operation'.
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-8.3 Pressurizer pressure and level controls are in AUTO maintaining pressure at 2235 psig and level at -25%.
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8. 4'
-The motor driven auxiliary feedwater pumps are in service and operating on offsite power.
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8.5 Steam pressure approximately 1090 psig and being maintained by steam dump to the condenser.
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8.6 Steam dumps are in the Steam Header Pressure Controller mode and are being operated in AUTO.
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8.7 Steam. generator level being maintained at approx 1=ately 26% and the auxiliary feedwater control valves are in MANUAL.
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8.8 NC r-r; 2:25 ;:i, -12 temperature e557 F.
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8.9.
Excess letdown is available for service if required during the test.
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8.10 Isolate steam flow to the auxiliary feedvater turbine driven pump.
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8.11 The steam generator power operated relief valves control switch is in AUTO.
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8.12 Verify all valves listed on Enclosure 13.1 have been blocked.
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8.13 Verify all input logic circuitry has been modified per Enclosure 13.2.
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8.14 Reset the low power range and low intermediate range trip setpoints 05
- to 7% F.P.
(Current _ equivalent to 2.8 x 10 amps on the inter-mediate range.)
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8.15 The steam generator blowdown system will automatically be isolated on an automatic start of the auxiliary feedwater pumps. Therefore, steam generator chemistry should be such that blowdown will not be
-r quired for a period of -3 hours.
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This ist is dasigned to demonstrate that natural circulation can be init.
Ein conjunction with loss of offsite power. The initial condi-t1ons-are as follows:
I (a) The reactor is at -l% F.P.
(b) All four reactor coolant pumps are running.
(c) The auxiliary feedwater system is in service and operating on offsite power.
(d) Primary-system is at normal operating temperature and pressure.
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-Tha tdct :will be initittcld by.51multenncusly tripping til four rccctor :
coolant-pumps and-opening breakers 1 ETA-l' and 1ET3-1. 1This 'will result
'in a loss'of. motor driven auxiliary feedwater'pumpt,. pressurizer heaters,
- and charging-pumps.' The: diesel generators will start: automatically and-the sequencer wil1~ pick up these loads. 'Af ter this 'the establishment of-
-L natural circulation will be verified.
10.0' Data Required-10.1 Outputs of the 0AC Transient Monitor Program.
JNOTE: ~The ' data on the OAC Transient Monitor Program will have to be " frozen" and " dumped" to 2 floppy disc every 30_ minutes from the beginning of the test.
'10.2 Record initial-conditions data on~ Enclosure 13.3.
- 10.3 Output of the OAC Thermocouple Map Program.
-10.4 Output-of-the OAC Saturation Limit Graphic.
'11.0 Acceptance Criteria 11.1 Natural ' circulation was established and maintained while emergency
. loads'were powered from the emergency diesel generators.
11.2 Offsite_ power was restored and the emergency loads' transferred back to offsite power.
-11.3 Core exit thermocouple temperature did not exceed 617 F.
11.4'. T for any loop did not. exceed 588 F.
i avg 11.5-Delta-T for any loop did not exceed 65 F.
11.6 ~ A margin of at least 15 F subcooled 'from saturated conditions is 1
maintained throughout the test.
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12.0'Pree-durn'
- NOTE: Thermocouple; Map, Transient Monitor Output,.and Initial Conditions
' data need not be repeated for multiple test performances., N/A signoffs for these' steps.
Initicl/Date-
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12.1' Record data on Enclosure 13.3.
12.2E Place. backup pressurizer heaters A and B in AUTO and trip heaters
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, Place heater D in MANUAL on the AUTO-MANUAL switch and
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C and D.
O in OFF on the MANUAL switch.- Place heater group C SUPPLY BREAKER switch to-OPEN position.)
NOTE: The next-step will simulate a loss of.offsite power.
12.3 '- As close to simultaneously as possible, perform the following actions.
NOIE: -Record this time in thA test log.
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12.3.1
. Trip all four reactor coolant pumps.
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12.3.2 Open breakers 1 ETA-1 and lETB-1.
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12.3.3 Disable the steam dumps.
(Place teh 0FF-RESET buttons to OFF.)
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12.3.4 Close the main steam isolation valves.(from the Control Room.)
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12.3.5 Reset the main steam power operated relief valves (from the Control Room).
NOTE: The operators should continuously monitor the Saturation Limit Graphic on the OAC beginning at j
this point.
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12.4 Verify both diesel generators start and that their loads are sequenced on:
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12.4.1 Component Cooling Water Pumps
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12.4.2 Auxiliary Feedwater Pumps
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12.4.'3 Centrifugal Charging Pumps
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~ 12.4.4' Air _-Conditioning System Compressor NOTE: 'If either diesel generator fails to start, restore power to the appropriate train by closing either lETA or lET3.
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12.5 -Verify 1etdown flow and transfer centrol of the pressurizer heaters to MANUAL.-
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12.6 Begin taking THERMOCOUPLElMPS on the OAC every 30 minutes and dumping the output of TRANSIENT MONITOR on the OAC to floppy disc every 30 minutes starting at the time recorded in Step 11.3.
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112.6.1 Begin taking an output of the Saturation Limit Graphic
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once every 10 minutes.
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12.7. Verify MANUAL control of. auxiliary feedwater and AUTO control of 1the steam generator power operated relief valves.
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12.8 Maintain steam generator levels at -252.
NOTE: ~ If automatic control of the-steam generator, power operated
' relief valves fails to maintain level, switch to MANUAL control.
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12.9 Verify natural circulation is established and maintain steady state conditions for 30 minutes.
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12.10 After 30' minutes of steady state operation, discontinue data taking from the Transient Monitor Program and Thermocouple Map on the OAJ.
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12.11 Restore normal station power to lETA-1 and lETB-1.
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12.12 Restart the turbine driven nux111ary feedwater pump.
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12.13 Set' the Main Steam Header Pressure AUT0/ MANUAL CONTROL STATIO!.
setpoint to 1090 psig and engage the ON switch on the OFF-RESET, ON, BYPASS INTERLOCK switch.
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12.lk-Placepressurizer.heatergroupDMANUALswitchtoONandtheAUTO-MANUAL ~ switch to AUTO.
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112.15 Place pressurizer heater group C SUPPLY BREAKER switch to CLOSED position.
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12.16 Insert control bank D until the reactor is in the zero power test range.
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12.17 Ensure pressurizer spray. valves are closed.
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12.18 Restart _the reactor coolant pumps.
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12.19 Place pressurizer level and pressure controls in automatic.
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12.20 Maintain =anual control of auxiliary feedwater with steam generator -
level at -262.
l2.21 Reset.the intermediate range trip setpoint to 1 x 10 ' amps and the
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~ low power range trip setpoint to 25% F.P. unless the next test also requires this adjustment.
If this is the case, N/A this step.
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.12.22 Remove the blocksifrom the. valves listed in Enclosure 13.1 unless
- the next test'to be perfermed requires the valves to-be blocked.
If:this is.the case, disregard this step and N/A this signoff and
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-signoffs on Enclosure 13.1.
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12.23. Verify all input 'ogic circuitry has been placed back in its normal statua per. Enclosure 13.2 unless the next test to be performed requires the' logic circuitry to be modified. If this is ~ the case, disregard this step and N/A'~this signoff and signoffs on Enclosure 13.2.
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.12.24 All_' Acceptance Criteria has been. met.
. 13.0 Enclosures.n-13.1 Valvec.to;be. Blocked 13.2 Modifications to Input Logic Circuitry 13.3-l Initial' Conditions u
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Enclocurs 13.1.
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Valves to be Blocked TP/1/A/2150/23-
' Natural Circulation with Simulated?
Loss of10ffs1*.e Power xThe following'UEI: Isolation' Valves shall be blocked for the performance of this test.
'(1) 1NI242B
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(2)' 1NI243A
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(3)
INI244B (4).lNI245A
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The'following UHI Isolation Valve' Blocks shall be removed after the performance:
of this test unless the next test to be performed requires these valves to be blocked-If this is the case, N/A the signoff steps.
~(1) 1NI242B
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(2) INI243A
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(3) INI244B
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(4)'. 1NI245A
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s Encloeura 13.2' Modifications to Input: Logic Circuitry:
TP/1/A/2150/23 Natural-Circulation with Simulated.
. Loss of Offsita Power
- The'following modifications to input logic circuitry shall be made for the
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performance-of chis test.
(1)~. Block ^ safety injection from low pressurizar pressure.
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-(2)' Block safety injection initiated by low steam line
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pressure.
-(3)'
Block safety injection initiated by negative rate on the. steam line pressure.
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' NOTE: -;The safety injection alarm, manual safety injection hand switch, and the reactor' trip portion of the protection logic will remain in oper-ation.
If, truly,'the conditions exist that.would normally, initiate
. a safety injection the operator shall manually initiate the safety i
injection. The operator shall be ale-t'as to the' conditions that would-initia:e t safety injection and shall be able to differentiate 0
between the actual test conditions and the conditions that would initiate safety injection..
The follow 1'ng mo'ifications to input logic. circuitry shall be removed after d
~ the performance of this test unless the next test to be performed requires these modifications.- If this is the case, N/A the signoff steps.
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' (1) Remove'the block of safety injection from low pressurizer
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- pressure, w
~(2): Remove the block.of safety injection ~ initiated 1by_lcw ateam line pressure.
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(3) Remove the block.of safety injection' initiated by negative rate-on the steam line pressure.
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Enclotura 13.3 Initial Conditions TP/1/A/2150/23
. Natural Circulation with Simulated c
-Loss of-Offs 1te Power Point ID#
Point-Value All18.
. Pressurizer Pressure'l' All24 Pressurizar Level 1 A1061
-Loop A Cold Leg Temp.
A1067 Loop B-Cold Leg Temp.
A1073 Loop C Cold Leg Temp.
-A1079 Loop D Cold Leg Temp.
A0965 Loop A Hot Leg Temp.
A0971 Loop B Hot Leg Temp.
A0977
' Loop C Hot Leg Temp.
A0983 Loop'D Hot leg Temp.
A1059 Steam Generator A Level A1065 Steam Generator B Level A1071 Steam Generator C Level A1077 Steam Generator D Level A11Q7 Steam Generator A Pressure All13 Steam Generator B Pressure All19-Steam Generator C Pressure All25 Steam Generator D Pressure A0890 Steam Generator A Aux. Feedwater Flow A0884 Steam Generator E Aux. Feedwater Flow A0878 Steam. Generator C Aux. Feedwater Flow.
A0872 Steam Generator.D Aux. Feedwater Flow A1060:
Steam Generator.A Steam Flow A1066 Steam Generstor B: Steam Flow-A1072-Steas Generator C Steam Flow A1078 Steam Generator D Eteam Flow
~Alll2-NC Loop Highes: Avg. Temp.
- A0555 Steam Generator A Aux. Feedwater Temp.
A0561 Steam' Generator B Aux. Feedwater Temp.
.A0567-Steam Generator C Aux. Feedwater Temp.
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- 3.3-Initial Conditions, TP/1/A/2150/23
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Natural' Circulation with Simulated Loss of Offsite Power iPoint ID#1
' Point-Valut
'A0573L Sen e Cenerator D Aux.' Fsedwater Temp.
- A1058
'Lcap A ST=
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~ 1070.
Loop B AT A
l zA1082 Loop.C'aT iA1094
-Loop.D'AT-A0628 Power Range Avg. Level Quad. 1
-A0627 Pcwer Range: Avg. Level Quad. 2 l
A0629
-Power Range Avg. Level': Quad. 3 A0626
-Power Range Avg. Level Quad. 4 I
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