ML20058G268
| ML20058G268 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/06/1982 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20058G191 | List: |
| References | |
| ZPT-9.1, NUDOCS 8208030246 | |
| Download: ML20058G268 (34) | |
Text
'
SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION pp?;Ozd.a.nq AflhM NUCLEAR OPERATIONS 4 d vin Y fb bYb 5' 0~
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-- s ZERO POWER TESTING NATURAL CIRCULATION DEMONSTRATION ZPT-9.1 REVISION O MAY 25, 1982 SAFETY RELATED (X)
Reviewed by:
l V/f}
w-A ORIGINATOR (oFfris revision)
Datb T
1 i
I QUAL 2D RWEWER
'Date l
Approved:
O L
TECHNICAL SUPPORT PERVISOR
- D#te 3))l-b Date Issued:
Form AP-101-2, (1/80) 8208030246 820729
{DRADOCK 05000395 PDR
ZPT-9.1 PAGE i REV. NO. O 5/2 5/82 O
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ZPT-9.1 PAGE 11 REV. NO. 0
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5/25/82 i
INDEX 1.0 PURPOSE
2.0 REFERENCES
3.0 PREREQUISITES 4.0 SPECIAL TEST. EQUIPMENT 5.0 LIMITS AND PRECAUTIONS 6.0 TEST METHOD 7.0 DATA REQUIREMENTS 8.0 ACCEPTANCE CRITERIA ATTACHMENTS l
ATTACHMENT I
- NATURAL CIRCULATION INITIAL CONDITIONS DATA O
ATTACHMENT II
- NATURAL CIRCULATION FINAL CONDITIONS DATA ATTACHMENT III - APPENDIX A - PROCESS COMPUTER TREND BLOCKS ATTACHMENT IV
- APPENDIX B - TEST RECORDER INPUTS l
ATTACHMENT V
- APPENDIX C - CALCULATION OF AT LIMIT FOR NATURAL CIRCULATION ATTACHMENT VI
- FIGURE 1 - DELTA-T LIMIT VS REACTOR POWER, NATURAL CIRCULATION l
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ZPT-9.1 PAGE 1 REV. NO. O O
DATE 5/25/82 1.0 PURPOSE 1.1
'1b demonstrate the capability of the NSSS for removing fission product decay heat by natural circulation.
NOTE:
Since this test is performed' at the beginning of core life when the ' fission product density is low, decay heat will be simulated by nuclear power.
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ZPT-9.1 PAGE 2 REV. NO. 0
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DATE 5/25/82
2.0 REFERENCES
2.1 V. C. Summer Nuclear Station FSAR, Chapter 14, Td31e 14.1-65.
2.2 V. C. Summer Nuclear Station Technical Specifications.
2.3 Precautions, Limitations, and Setpoints Document for Westinghouse NSSS.
2.4 Westinghouse Startup Manual Procedure, CGE-SU-3.1.4, Initial Criticality and Low Power Test Sequence (1MS-94B-072-3G-0).
2.5 ZPT-0, Technical Specifications Surveillance and Periodic Data Acquisition During Low Power Physics Testing.
2.6 ZPT-1, Initial Criticality.
2.7 ZPT-10, Acquisition of Data to verify Power Level During Low Power Testing Below 5%.
2.8 ASME Steam Tables, 1967.
2.9 AP-1700, Power Ascension Test Program.
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ZPT-9.1 PAGE 3 REV. NO. O l
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DATE 5/25/82 3.0 PREREQUISITES INITIAL / DATE 3.1 Procedure ZPT-1, Init,ial Criticality, has been completed.
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3.2 The reactivity computer has been connected and functionally tested per Procedure ZPT-0 with a flux signal from the sum of the upper and lower detectors of one power range channel.
Record the channel below.
Reactivity computer input channel
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3.3 The strip chart recorders of the reactivity computer package have been connected per Procedure ZPT-0 and are trending the following parameters.
3.3.1 Reactivity (Recorder #1)
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3.3.2 Flux Level (Recorder 91)_
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3.3.3 RCS Thot (Recorder 92)
TI-
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3.3.4 RCS Tcold (Recorder #2) TI-
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NOTE:
03tain the RCS Thot signal from one of the following MCB indicators:
TI-413 (Loop A Hot Leg Wide Range Temperature) or TI-423 (Loop B Hot Leg Wide Range Temperature).
03tain the RCS Tcold signal from one of the following MCB indicators:
TI-410 (Loop A Cold Leg Wide Range Temperature) or TI-420 (Loop B Cold Leg Wide Range Temperature).
Signal scaling is 0-10VDC for 0-700*F and recommended scaling for the strip chart is 500-444*F.
The Thot and Tcold signals should be from the same RCS loop.
NOTE:
Label each recorder trace with the parameter measured, scale, units and the test point from which the signal is derived.
Compare recorder traces with installed instrumentation readout to determine if the recorded parameters are being calculated correctly and that the test recorder readings are in agreement with installed instrumentation.
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ZPT-9.1 PAGE 4 REV. NO. 0
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DATE 5/25/82 INITIAL / DATE 3.4 Multi-channel strip chart recorders have been connected to trend the parameters listed in Appendix B.
A common remote event marker switch has been connected to the recorders.
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3.5 Periodic logging of reactor power is in progress per Procedure ZPT-0.
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3.6 Periodic logging of RCS Tavg is in progress per Procedure ZPT-0.
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3.7 Periodic boron sampling and concentration logging is in progress per Procedure ZPT-0.
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3.8 The Process Computer Trend Blocks of Appendix A have been established and are being output per Procedure ZPT-0.
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As required by Procedure ZPT-0, for the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period preceeding this test, verify one of the following:
3.9.1 The Phase III Low Power Test Program has been in progress, or:'
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3.9.2 A Channel Functional Test (with reactor trip setpoints changed to <25% of Rated Thermal Power instead of setpoints for normal operation) has been completed on each l
Intermediate and Power Range channel.
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3.10 Procedure ZPT-10 has been completed to align the operable Power l
Range Channels with the narrow range Delta-T indications.
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3.11 The Subcooling Monitor is operable.
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I 3.12 Pressurizer Level is being maintained near its no-load level of l
25%.
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O 3.13 Steam Generator Level is being maintained near its nc-load level of 24%.
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DATE 5/25/82 4.0 SPECIAL TEST EQUIPMENT The following components of the reactivity computer package (4.1 thru 4.5):
4.1 Reactivity Computer ID#
Cal. Due Date
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4.2 Two, 2-pen Strip Chart Recorders ID#
Cal. Due Date
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ID#
Cal. Due Date
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4.3 Picoammeter ID#
Cal. Due Date
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4 High Voltage Power Supply
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.4 ID4 Cal. Due Date
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4.5 Signal Conditioning and Test Panel ID#
Cal. Due Date '
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l 4.6 8 - Channel Strip Chart Recorder (Gould Model 2800 or equivalent).
ID#
Cal. Due Date
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4.7 4 - Channel Strip Chart Recorder (Gould Model 2400 or equivalent).
ID6 Cal. Due Date
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4.8 Three (3) Digital Voltmeters (DVMs)
ID#
Cal. Due Date
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I ID#
Cal. Due Date
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ID#
Cal. Due Date
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.r ZPT-9.1 PAGE 6 REV. NO. 0 DATE 5/25/82
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5.0 LIMITS AND PRECAUTIONS 5.1 Maintain reactor power less than 5% of Rated Thermal Power as indicated by the operable power range channels.
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5.2 With the NSSS in the natural circulation mode avoid sudden changes in steam pressure and flow, emergency feedwater flow to the steam generators, and steam generator level.
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5.3 With all reactor coolant pumps tripped, do not restart any reactor coolant pump until the. reactor is subcritical.
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5.4 With all reactor coolant pumps tripped, the narrow range RCS temperature channels cannot be used to monitor RCS temperature g
due to loss of flow in the RTD bypass loops (the loss of RTD
)
bypass loop flow alarms are anticipated during this test).
RCS s
temperature must be monitored by the wide range RCS temperature channels and/or the core exit thermocouples.
The Lo-Lo Tavg Permissive, P12, will be initiated when indicated narrow range RCS Tavg reaches 553*F.
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5.5 Limit loop Delta-T to less than 64 *F and limit loop Tavg to less than 587*F per Refernece 2.3.
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5.6 Maintain RCS margin to saturation greater than 50* F.
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NOTE:
RCS margin to saturation is the dif ference between the saturation temperature based on the lowest indicated pressurizer pressure and the highest indicated wide range hot leg temperature or highest core exit thermocouple temperature.
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ZPT-9.1 PAGE 7 REV. NO. O
'g DATE 5/25/82
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y 5.7 With the NSSS in the natural circulation mode pressurizer spray from the RCS loops will be lost.
If the Pressurizer Pressure controller were to remain in Automatic the reset contribution to the controller would eventually cause the controller output to increase to the pressurizer relief valves setpoint.
Therefore Pressurizer Pressure control must be placed in Manual while in a natural circulation condition.
The pressurizer pressure increase during the transition to natural circulation should be limited to less than the pressurizer relief, valves setpoint (233 5 psig) by using auxiliary pressurizer spray.
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5.8,With the NSSS in the natural circulation mode Pressurizer Level control must be placed in Manual and charging flow adjusted to match letdown such that constant RCS mass inventory is maintained.
Pressurizer level will then rise during the transition to natural circulation.
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5.9 The Limiting Conditions for Operation and Surveillance
(-wg Requirements of Technical Specifications Special Test Exception g j 3.10.3, Physics Tests, must be observed during this test.
The surveillance data logging initiated in Procedure ZPT-0 must be continued during this test.
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5.10 In order to maintain the reactor critical with all reactor coolant pumps tripped it is necessary to invoke Special Test Exception 3.10.4 to suspend the requirements of Specification i
3.4.1.1.
The Limiting Conditions for Operation (LCO) and Surveillance Requirements (SR) of Special Test Exception 3.10.4 and associated compliance measures are detailed below.
5.10.1 LCO 3.10.4.a The Thermal Power does not exceed the P-7 interlock setpoint.
SR 4.10.4.1 The Thermal Power shall be determined to be less than the P-7 interleck setpoint at least once per hour during startup and Physics Tests.
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TPT-9.1 PAGE 8
- REV. NO. O DATE 5/25/82 COMPLIANCE The Reactor Protection System effectively limits reactor power to less than the P-7 interlock setpoint since exceeding P-7 with all reactor coolant pumps of f will result in a reactor trip.
Power will be limited to less than 5% of Rated Thermal Power per Precaution 5.1.
The Power Range Nuclear Channels will be calibrated by performance of Procedure ZPT-10 during low power testing.
During performance of this test record readings from the operable Power Range Channels on Data Sheet 1, NIS Excore Detector Data, at least once per hour to document that reactor power is less than 5% of Rated Thermal Power.
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5.10.2 LCO 3.10.4.b The reactor trip setpoints on the operable Intermediate and Power Range Nuclear Channels are set at less than or equal to 25% of Rated Thermal Power.
SR 4.10.4.2 Og j Each Intermediate, Power Range Channel and P-7 interlock _. ___
shall be subjected to a Channel Functional Test within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating Startup or Physics Tests.
COMPLIANCE Compliance with this LCO and SR is ensured by completing Prerequisite 3.9 of this procedure.
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5.11 The minimum allowable RCS tempeature to maintain criticality is 541*F.
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5.12 Immediately start RCP A if a Reactor Trip or Safety Injection occur.
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5.13 Do not use Auxiliary Spray if letdown is isolated.
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DATE 5/25/82 6.0 TEST METHOD 6.1 Establish or verify the following plant conditions.
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6.1.1 The plant is in a Startup,(Mode 2) condition and the reactor is critical with the flux level within the range established for zero power physics testing.
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6.1.2 The BTRS Master Control Switch is OFF.-
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6.1.3 The Rod Control Bank Select Switch is in the MANUAL position.
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6.1.4 Control Bank D is~ positioned at 150 + 10 steps.
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6.1.5 Pressurizer Pressure control is in Automatic with only the proportional heaters on.
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l 6.1.6 Pressurizer Level control is in Automatic.
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6.1.7 RCS temperature is being controlled by steam dump to the condenser or atmosphere in the Steam Pressure mode.
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l NOTE:
If RCS temperature control is by steam dump to the atmosphere, verify adequate Condensate Storage Tank water volume to permit approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of operation at approximately 3 % of Rated Thermal Power.
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DATE 5/25/82 5.1.9 RCS Tavg is 557 +1/-4*F.
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CAUTION:
Minimum RCS Tavg to maintain criticality is 541*F.
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6.1.10 Pressurizer Pressure is 2235 + 25 PSIG.
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6.2 Instruct the Chemistry Department to sample the RCS and pressurizer for initial boron concentration analysis.
Each sample is to be labeled with the date, time, and sample point and saved until released by the Test Supervisor.
Initial Boron Concentration RCS ppm PZR ppm
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NOTE:
The RCS and PZR should be within + 15 ppm.
6.3 Verify RCS Makeup blended flow is set to match the RCS boron concentration.
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O 6.4 Start the Process Computer Trend Blocks of Appendix A at 5 minute intervals with output to the Trend Typewriter.
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6.5 Start the strip chart' rec $rders of the reactivity computer package at 1 inch / minute and mark the charts with the procedure number and title, date and time, chart speed, parameter scales, and control bank positions.
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6.6 Start the multi-channel strip chart recorders at approximately 25mm/ minute and label the charts as in Step 6.4.
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6.7 Connect a DVM to monitor Loop Delta-T signals at the following test points:
Loop A, C1-423, TP1, Loop B, C2 - 72 3, TP1; Loop C, C3-72 3, TPl.
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NOTE:
These Delta-T reading will be used to monitor reactor power.
Signal scaling is 0-10 VDC for 0-150% Delta-T.
At present the Delta-T modules are scaled for a 55 *F Delta-T input at 100% o f Rated Thermal Power.
Since the expected full power Delta-T is 64*F a correction factor of 55/64 O
must be applied to the DVM reading.
Best estimate reactor power is given by the following formula.
POWER (%) = DVM voltage x 15 x 55/64
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ZPT-9.1 1
PAGE 11 REV. NO. 0
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DATE 5/25/82 6.8 By Control Bank D withdrawal in MANUAL, slowly increase ' reactor power until the DVM reading indicates a best estimate power level of 3 j; 0.5% of Rated Thermal Power (0.233 j; 0.039 VDC).
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6.9 Stabilize reactor power and record the required data on Data Sheets 1A and IB, Natural Circulation Initial Conditions Data.
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6.10 Increase the Process Computer Trend Blocks output frequency to one minute intervals.
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6.11 Pulse the event markers to synchronize the charts and indicate the time on the charts.
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) 6.12 Place Pressurizer Level control in MANUAL and match charging plus seal injection flow to letdown plus seal return flow.
l 6.13 Close Relief 444B Isol MVG-8000B and Pwr Relief PCV-444B.
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CAUTION:
Pressurizer Relief Valve PCV-444B works off an integral circuit.
If a high mismatch exists between actual and reference pressure long enough PCV-444B will actuate.
To prevent release of steam from the Pressurizer due to activation of PCV-444B its associated isolation valve l
MVG-8000B is to be closed.
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DATE 5/25/82 6.14 On a signal from the Test Supervisor:
A.
Simultaneously trip all three Reactor Coolant Pumps.
B.
Pulse the recorder event markers.
C.
Place the spray valve controllers in manual and open the spray valves.
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NOTE:
At the initiation of Natural Circulation ( RCP Tr ip ), the following system response is expected.
a)
Wide range THot Increase (26 to 45'F at approximately 3 % power).
b)
Wide range TCold - Slight decrease or constant.
c)
Core exit thermocouple - increase (26 to 45*F at approximately 3 % power).
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d)
Pressurizer level increase (10 to 164 at approximately 3 4 power).
e)
Pressurizer Pressure - increase.
NOTE:
Steam Generator pressure, level and flow conditions should be held as close as possible to stable conditions as natural circulation develops.
Reactor Coolant System cold leg temperatures should be maintained within +5*F of 557'F.
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NOTE:
Continuously monitor main steam line pressures and carefully l
control feedwater addition during the transient to insure that differential pressure between any two steam lines is
< 100 psid.
CAUTION:
After tripping the Reactor Coolant Pumps, Reactor Coolant System pressure is expected to increase as much as 50 psi l
depending on the power level.
Be prepared to use Aux.
I Spray to control pressure.
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ZPT-9.1 PAGE.13 REV. NO. O O
DATE 5/25/82 CAUTION:
Following Reactor Coolant Pump trip, T OnceP-1$,andaTTavg 553*F, is av indication will be unrelisble.
initiated steam dump to the condenser is blocked except
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for the two cooldown dump valves when in the MANUAL bypass mode.
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6.15 Initiation of Auxiliary Spray i
6.15.1 Maintain regenerative heat exchanger charging outlet temperature W3ove 350*F.
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l 6.15.2 Open or check open PZR SPRAY Valves PCV-444C and 444D.
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6.15.3 When Reactor Coolant pressure exceeds 2285 psig, open PZR O
SPRAY FR CVCS PVT-8145.
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6.15.4 Confirm that the 320*F maximum temperature diffe'rential between pressurizer and spray water is not being violated.
PZR temperature
- F Charging Temperature
- F
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l 6.15.5 When RCS pressure exceeds 2310 psig, close NORM CHG TO RCS LP B PVT-8146.
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6.15.6 Manually throttle PZR SPRAY Valves PCV-444C and 444D as required to maintain RCS pressure below 2310 psig.
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ZPT-9.1 PAGE 14 REV. NO. 0
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DATE 5/25/82 6.16 Once pressure is stabilized terminate Auxiliary Spray by opening NORM CHG TO RCS LP B PVT-8146, closing PZR SPRAY FR CVCS PVT-8145, and closing PZR SPRAY valves PCV-444C and 444D.
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6.17 Maintain RCP seal injection between 6 and 12 gpm to each RCP with a maximum total flow of 33 gpm.
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6.18 Maintain a constant Reactor Coolant System mass by ensuring charging plus seal injection flow is matched with letdown plus seal return flow.
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6.19 Pressurizer level will increase as THot increases.
~After THgt becomes stable maintain const. ant pressurizer level by adjusting charging flow, i
i 6.20 Carefully control steam generator levels at approximately 24%
. level.
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6.21 If required, adjust the pressure sotpoint on the steam dump pressure controller to maintain RCS cold leg temperatures within
+5* F o f 557* F.
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DATE 5/25/82 6.22 Maneuver Coa'
'l Bank D as required to maintain reactor power at 3 + 0.5% of rated thermal power using the flux level recording on the reactivity computer as a reference.
A
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NOTE:
Natural circulation flow will be stable within approximately 10 to 20 minutes when:
e a.
A T is constant.
b.
Wide range T ot is approximately equal to core H
exit thermocouple average temperature.
I 6.23 Maintain stdale natural circulation for a minimum of 30 minutes and perform the following.
6.23.1 Mark the strip chart recorders of the reactivity computer package.
Continue to record data during stable conditions.
Indicate the time on the charts.
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O 6.23.2 Pulse the multi-channel strip chart recorders event marker to synchronize the charts.
Continue to record data during stable conditions.
Indicate the time on the charts.
6.23.3 Record the required data on Data Sheets 2A and 2B, Natural Circulation Final Conditions.
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6.23.4 Obtain a Process Computer Long Form Thermocouple Map.
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6.23.5 For optional information a movable incore detector full core flux map may be taken.
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ZPT-9.1 PAGE 16 REV. NO. O O
DATE 5/25/82 6.24 Reduce core power level and achieve subcritical configuration by inserting Control Bank D to O steps.
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6.25 Flace the Pressurizer Spray controller in manual operation and close the spray valves.
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6.26 Place the Pzr. Backup Heaters in the " AUTO" position.
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6.27 Once stable, start the Reactor Coolant Pump A which is the loop with the pressurizer surge line.
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6.28 Once stable, start the remaining Reactor Coolant Pumps, C and B.
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6.29 Return the Pressurizer Level and Spray controllers to automatic control.
6.30 Terminate data collection on the process computer and multi-channel.
recorders.
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6.31 Instruct the Chemistry Department to sample the RCS and Pressurizer for final boron concentration analysis.
Each sample is to be labeled with the date, time and sample point and saved until released by the Test Supervisor.
Final Boron Concentrations RCS ppm PZR ppm
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6.32 When RCS pressure is stabilized at approximately 2235 psig, place PWR RELIEF PCV-444B switch in the " AUTO" pos ition.
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I 6.33 Ensure PCV-444B is closed, then open RELIEF 444B.ISOL MVG-8000B.
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6.34 Notify the Shif t Supervisor and/or Control Room Foreman that the test is completed and that the plant may be restored to normal consistent with plant operations and subsequent testing requirements.
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ZPT-9.1 PAGE 17 REV. NO. 0
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DATE 5/25/82 7.0 DATA REQUIREMENTS 7.1 The completion of each Step will be indicated by initialing and dating in ink in Section 6 and the attached data sheets.
The signing or initialing of a part of procedure signifies that, based on personal observation or reports from assigned test personnel, the Step. has been performed as written and the results are as recorded.
7.2 The Of ficial Test ' Copy of the completed test procedure, along with the data collected, will be retained by Document Control as part of the plant historical record.
7.3 Test Data 7.3.1 Data Sheet 1, Natural Circulation Initial Conditions Data.
7.3.2 Data Sheet 2, Natural Circulation Final Conditions Data.
7.3.3 Strip chart recording from all recorders for the duration of the test.
7.3.4 Process computer trend blocks for the duration of the test.
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l ZPT-9.1 PAGE 18 REV. NO. O DATE 5/25/82 8.0 ACCEPTANCE CRITERIA LEVEL I 2
8.1 The highest loop Delta-T is less than the assumed value in the safety analysis for the power level at which the test was conducted.
Refer to Pigure 1 and Appendix C.
LEVEL II 8.2 Natural circulation has been demonstrated.
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ZPT-9.1 ATTACHMENT I PAGE 1 OF 2 REVISION 0 d[
DATA SHEET 1A Natural Circulation Initial Ccuditions Data
- 1. RC5'Temnerature Data Loop Tanneratures - Wide Range Loop AT - Nar cv Range! Correction Strip Chart Recorder Data DTM Factor
@I)WR AI
)NR f i,
- I I
hot celd py)
(CT)
(Ovi (C?i (Volts)
(O )
?
A B
C Average Value, (ET),NR l
- 8 NR WR 1*
@)o - M)o
- 2. Core Pever Level Data Parameter value I
Average ciccammetar current, o
amps NR average Narrow Ranas loop AT, f !)o CF Estimated Full Power loop AT, %T)
C7 i
~
g"+II (AT) g :/amql Piccammater calibration facecr,a =
W )e a
i Racer:ied bv l
--,w-<
,-y_ - _ _ -,,. _ -,
DATA SHEET 1B g7 PAGE 2 0F 2 O
Natural Circulatica Initial, Conditions Data REVISION O Looo A Leon 3 Loco C Parameter Description i
i Source Value l Source l Value Source Value 87)
T1-413 TR-413 TR-413 l Wide Range Thoe bI)
TR-410 lTR-410 l
Wide Range Teoid TR-410 RCS Loop Flow (I)
FI414 lFI-424 lFI-434 l FI-415 l
lyI-425 l
l FI-435 l FI-416 l71-426 l
lFI-436 l Stama Generator LI-474 lLI-484 l
lLI-494 Level (I)
LI-475 l
l LI-485 l
l LI-495 l LI-476 LI-486 l
lLI-496
~ Steam Generator PI-474 lPI-484 l
lPI-494
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PI-475 lPI-485,l PI-495 PI-476 lPI-486 PI-496 l Stama Flow (MPFH)
FI-474 lFI-484 lFI-494 FI-475 l
FI-485 lFI-495 l Emertency Feed Flow (gem)lFI-3561 lFT-3571 !
!?I-3581 LI 59 Pressurizar Level (7.)
LI-460 LI-461 Pressuriser Pressure (psig) PI-444 l
PI-445 l
PI-455 l
PI-456 PI-457 l
Intermediate Range l
935 l
- 8 N36 Recorded by O
ZPT-9.1 ATTACHMENT II PAGE 1 0F 2 REVISION 0 DATA SHEET 2A Natural Circulation Final Conditions Data l
- 1. RCS Tannerature Data Loop Tannerature - Wide Range Corrected Wide Range Strip Chart Recorder Data Loop AT Loop T
(AT)
@ )ktCCRR " W )WR, +bi Thoc eold
@?)
(0 )
(G )
?
?
A 3
C
,3 Average Loop AT (AT) CORR 1
- 2. Power Level Data Parameter 7alue Average Picoammeter current, I anps Core power level,C(I Recorded by
ZPT-9.1 ATTACHMENT II DATA SHEET 2B PAGE 2 0F 2 O
REVISION 0 Natural Circulation Final Conditions Data o
Looo A Loco B l
Loco C Paranater Description i
Source value Source 1 7alue Source 7alue 6F) 7g.413
'l TR-413 TR-413 Wide Range Thec Wide Range Teold I)
TR-410
!TR-410
!n-410 RCS Loco now (I)
FI-414 FI-424 l
FI-434 FI-415 l
lFI-425 lFI-435 FI-416 l
ln-425 l
lFI-436 l Steam Generator LI-474 l
lLI-484 l
lLI-494 l Level
(%)
LI-475 l
lLI-485 l
LI-495 l
LI-476 lLI-486 l
lLI-496 l Steam Generator PI-474 l
lPI-484 l
lPI-494 l hessure (I)
PI-475 l PI-485, l l PI-495 l
PI-476 PI-486 lPI-496 Seese now (MPPH) n-474 lFI-484 l
lFI-494 l FI-475 l FI-485 l
FI-495 l Imerzency Feed now (gem) l n-3561 l773571 l l 77 35gt l Pressurizar Level (I)
LI-460 l
LI-461 l
l Pressurizer Pressure (psig) PI-444 l
PI-445 l
l PI-455 l
l PI-456 PI-457 l
l Intermediate Range y35 N36 Recorded by O
ZPT-9.1 ATTACHMENT III PAGE 1 of 4 REVISION 0
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APPENDIX A COLUMN ADDRESS PARAMETER DESCRIPTION 1
N0033A INTERM RNG DETECTOR 1 LOG Q 2
N0034A INTERM RNG DETECTOR 2 LOG Q 3
N0049A PWR RNG CHANNEL 1 Q (QUAD 4) 4 N0050A PWR RNG CHANNEL 2 Q (QUAD 2) 5 N0051A PWR RNG CHANNEL 3 Q (QUAD 1) l 6
N0052A PWR RNG CHANNEL 4 Q (QUAD 3) 7 UGG"1 CQNT ROD BNK C STEP COUNT 8
00052 CONT ROD BNK D STEP COUNT
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9 F0400A REACTOR COOLANT LOOP 1 FLOW %
10 F0401A REACTOR COOLANT LOOP 2 FLOW %
11 F0402A REACTOR COOLANT LOOP 3 FLOW %
12 T0419A RCLI WIDE RNG HOT LEG T 13 T0439A RCL2 WIDE RNG HOT LEG T I
14 T0459A RCL3 WIDE RNG HOT LEG T NOTE:
Trend parameters may be changed at the discretion of the Test Supervisor.
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l ZPT-9.1 ATTACHMENT III PAGE 2 o f 4
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REVISION 0 APPENDIX A COLUMN ADDRESS PARAMETER DESCRIPTION 1
T0401A RCL1 2 TAVG 2
T0421'A RCL2 2 TAVG 3
T0441A' RCL3 2 TAVG 4
T0404A RCL1 2 DT 5
T0424A RCL2 2 DT 6
T0444A RCL3 2 DT 7
T0406A RCL1 WIDE RNG COLD LEG T 8
T0426A RCL2 WIDE RNG COLD LEG T
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9 T0446A RCL3 WIDE RNG COLD LEG T 10 PO480A PRESSURIZER PRESSURE 1 1
11 P0481A PRESSURIZER PRESSURE 2 12 P0482A PRESSURIZER PRESSURE 3 13 PO483A PRESSURIZER PRESSURE 4 14 LO480A PRESSURIZER LEVEL 1 15 LO481A PRESSURIZER LEVEL 2 16 LO482A PRESSURIZER LEVEL 3 NOTE:
Trend parameters may be charged at the discretion of the Test Supervisor.
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ZPT-9.1 ATTACHMENT III PAGE 3 o f 4 REVISION 0
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APPENDIX A COLUMN ADDRESS PARAMETER DESCRIPTION 1
F0405A STEAM FLOW LOOP 1 2
F0425A STEAM FLOW LOOP 2 3
F0445A STEAM FLOW LOOP 3 4
PO400A STM GEN 1 STM OUT I P 5
P0420A STM GEN 2 STM OUT 1 P 6
PO440A STM GEN 3 STM OUT 1 P 7
LO400A STM GEN 1 NAR RNG 1L 8
LO420A STM GEN 2 NAR RNG 1 L
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9 LO440A STM GEN 3 NAR RNG 1 L 10 F3561A EMERG FW TO STM GEN A FLOW 11 F3571A EMERG FW TO STM GEN B FLOW 12 F3581A EMERG FW TO STM GEN C FLOW 13 00090 HOTTEST INCORE T/C *F 14 U0092 IDENTITY OF HOTTEST INCORE T/C NOTE:
Trend parameters may be changed at the discretion of the Test Supervisor.
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4 ZPT-9.1 ATTACHMENT III PAGE 4 o f 4 REVISION 0 APPENDIX A COLUMN ADDRESS PARAMETER DESCRIPTION 1
F0128A CHARGING FLOW i
2 F0134A LETDOWN PLOW 3
T012 6A CHARGING TEMPERATURE 4
T0127A LETDOWN TEMPERATURE 5
LO 112 A VOLUME CONTROL TANK L 6
U0104 BORIC ACID FLOW SINCE LAST HR 7
UO105.
TOT MAKEUP WTR F SINCE LAST HR 8
U1399 BORON CON CVC3 BORON METER 9
F0483A PRESSURIZER SPRAY CONT 1 DEMAND 10 U1301 BORIC CONC IN COOLANT - CALC 11 U1302 BORON CONC IN PRESSURIZER 12 01303 BORON CONC IN VOL CONT TANK 13 YO400D RCP A BKR POSITION l
14 YO420D RCP B BKR POSITION 15 YO440D RCP C BKR POSITION NOTE:
Trend parameters may be changed at the discretion of the hest Supervisor.
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ZPT-9.1 l
ATTACHMENT IV PAGE 1 0F 2 REVISION 0 APPENDIX B TEST RECORDER INPUTS RECORDER 41 SIGNAL SIGNAL SOURCE SIGNAL LOCATION SIGNAL SCALING REMARKS / INITIALS Wide Range Thot, Loop A TP/413A C1-435, TP1 0-10VDC 0-700*P e
Wide Range Tcold, Loop A TP/410A C4-441, TP1 0-10VDC i
0-700*P Wide Range Thot, Loop B TP/423A C1-436, TPI 0-10VDC 0-700*P i
Wide Range Teold, Loop B TP/420A C4-442, TP1 0-10VDC 0-700*P Wide Range Thot, Loop C TP/433A C4-447, TP1 0-10VDC 0-700*P Wide Range Tcold, Loop C TP/430A C4-443, TP1 0-10VDC 0-700*P Pressurizer Pressure PQY-444 C8-128, Output 0-10VDC l
(Used for control) 1700-2500 psig 1-Pressurizer Level UY/768H C8-122, TPI-0-10VDC
]
(Used for control) 0-100%
l l
i
ZPT-9.1 ATTACHMENT IV PAGE 2 OF 2 REVISION 0 APPENDIX B TEST DECORDER INPUTS RECORDER 92 SIGNAL SIGNAL SOURCE SIGNAL LOCATION SIGNAL SCALING REMARKS / INITIALS 1
f Steam Generator Level, LP/474B C1-429, TP2 0-10VDC l
Loop A LP/475B C2-729, TP2 0-1004 l
LP-476B C3-729, TP2 Steam Generator Pressure PP/474D C2-743, TP2 0-10VDC Loop A
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PP/475B C3-743, TP2 0-1300 psig PP/476D C4-424, TP2 Emergency Feedwater FQY-3561 C9-233, Output 0-10VDC 0-300 gpm Plow, Loop A Intermediate Range N35 XPN-7071, TB1d2- 0-10VDC Current or 7& 8 l
N36 XPN-7072, TB202-10
-10 amps 7& 8 l
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d ZPT-9.1 ATTACHMENT V PAGE 1 0F 2
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REVISION 0 l
APPENDIX C CALCULATION OF AT LIMIT FOR NATURAL CIRCULATION FROM FSAR TABLE 15.2-4 GET THE ASSUMED RCS PLOWRATE VERSUS POWER t
POWER %
FLOW (%)
4.0 4.69 3.5 4.49 3.0 4.26 2.5 4.01 2.0 3.73 Full Power = 2775 MW, Full flow = 109.6 MPPH (FSAR Section 4.4) t O
CALCULATE POWER AND PLOW IN ENGINEERING UNITS AND Ah POWER (MWJ)
FLOW (MPPH)
Ah (BTU /lb 111.0 5.140 73.705 97.125 4.921 67.362' 83.25 4.669 60.855 69.375 4.395 53.874 55.5 4.088 46.336 Ah = Power (MWt) X 3.413 MBTU/hr Flow (MPPH)
MW w.
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ZPT-9.1 ATTACHMENT V PAGE 2 0F 2 O
REVISION 0 For Teold = 557*F and Pressure = 2200 psia, hcold = 556.04 BTU /lb PCWER %
h (BTU /lb hhot(BTU /lb)
Thot ( F)
AT (*F)
Tavq (*F) 4.0 73.705.
629.74 611.09 54.09 584.05 3.5 67.362 623.40 606.80 49.80 581.90 3.0 60.855 6 fB.89 602.34 45.34 579.67 2.5 53.874 609.91 597.46 40.46 577.23 2.0 46.336 602.37 592.10 35.10 574.55 For Teold = 557*F and Pressure = 2300 psia, hcold = 555.85 BTU /lb POWER %
h (BTU /lb hhot(BTU /lb)
Thot (*F) 4T (*F)
Tavq (*F) 4.0 73.705 629.56 611.38 54.38 584.19 3.5 67.362 623.21 607.06
~50.06 582.03 3.0 60.855 616.71 602.57 45.57 579.78 2.5 53.874 609.72 597.66 40.66 577.33 2.0 46.336 602.19 592.25 35.25 574.62 For Teold = 557'F and Pressure = 2400 psia, hcold = 555.67 BTU /lb POWER %
h (BTU /lb hhot(BTU /lb)
Thot (*F) dT f*F)
Tavq (*F) 4.0 73.705 629.38 611.65 54.65 584.33 3.5 67.362 623.03 607.31 50.31 582.15 3.0 60.855 616.53 602.78 45.78 579.89 2.5 53.874 609.54 597.85 40.85 577.42 2.0 46.336
'602.01 592.41 35.41 574.70 0
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