ML19309B148
| ML19309B148 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/02/1980 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML19309B136 | List: |
| References | |
| 2-ST-10, NUDOCS 8004030200 | |
| Download: ML19309B148 (27) | |
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I VIRGINIA ELECTRIC AND POWER CCMPANY Revisicn Nc.. o Date:
b SPECIAL TEST PRCCEDURE FOR NCRTH ANNA PCWER STATICH UNIT # 2 737(.
NATURAL CIRCULATICN WITH LCSS CF PRESSURIZER HEATERS Precared Sv:
F. R. ETLING Date:
Engineerinc Recermended Accreval:
Date:
STATICN NUCLEAR SAFETY AND CPERATING COMMITTEE APPRCVAL OF PRCCEDURE:
Chairr.an's Signature:
Date:
All personnel cenduc:ing actual testing in acccedas.
wi:h :his procedure will verify by their signature that they have read it in its entirety price to ccernencing any testing:
16 TEST RE5 ULT 3 REVIE'4ED BY ENGINEER!'4G:
Date:
RST RESULTS APPROVED BY STATICN NUCLEAR SAFET( AND CPERATING COMMl~' TEE:
Cha i r.an ' s S i cna tu re :
Date:
Cermen ts :
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TEST RESULTI (Use addi tional :: ages as necced)
Pace, or.
6 OlSCRE?ANCI ES (Li st bv nurne.tr):
lio RESOLUTicN ar otscagpANCIES (List by number carrescendina to abcve):
III ORITICUE:
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CHRCNOLOGIC/L LOG (Use acd'l pages as needed)
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O 2-ST-10 Page 1 of 9 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 2 NATURAL CIRCULATION WITH LOSS OF PRESSURIZER HEATERS RE N NCES:
1.
Precautions, Limitations, and Setpoints for Westinghouse NSSS System.
2.
Technical Specifications, North Anna Unit No.2.
3.
WCAP-8747; North Anna Nuclear Design Report.
4.
ASME Steam Tables.
5.
North Anna Station Curve Book.
6.
2-0P-5.2.
7.
2-EP-2.
1.0 Purpose 1.1 Verify natural circulation conditions can be established in all loops once the RCP's are tripped.
1.2 Verify the ability to maintain natural circulation and saturation margin with the loss of the pressurizer heaters.
1.3 Determine RCS depressurization rate after the RCP's and pressuriz-er heaters are tripped.
1.4 Verify saturation margin can be controlled through the use of primary. cLarging flow and secondary steam flow.
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2-ST-10 Page 2 of 9 Initials 2.0 Initial Conditions 2.1 The reactor is critical at ~ 3% power and under manual control with control bank D at ~ 160 steps or as specified by test engineer.
2.2 All three reactor coolant pumps in operation.
2.3 Steam generator level maintained at approximately 33% on the narrow range indicators by the main feedwater system (or auxiliary feedwater).
2.4 Pressurizer pressure being maintained at approximately 2235 psig automatically by pressurizer heaters and spray and pressurizer level at approximately 22%.
2.5 RCS temperature (Tavg) approximately 547 *F.
2.6 Low Power Physics Test program has been completed to the extent necessary for conduct of this test.
2.7 Steam generator pressure at approximately 1005 psig and being maintained by steam dump to the condenser on pressure control.
(or power-operated relief valves)).
2.8 Connect brush recorders to the following test points:
Brush Recorder 1 Connect To:
Monitoring:
Channel #1 FP-414B,C1-432 RCS Flow-Loop 1 Channel #2 FP-42.B,C1-433 RCS Flow-Loop 2 Channel #3 FP-434B,C1-434 RCS Flow-Loop 3 Channel #5 PP-455B,C1-427 Pressurizer Pressure i
Channel #6 LP-459B,Cl-442 Pressurizer Pressure Brush Recorder 2 Connect To:
Monitoring:
1 Channel #1 LP-474B,C2-429 Steam Gen. #1 Level Channel #2 FP-474B,C3-741 Steam Gen. #1 Steam Flow Channel #3 PP-474B,C2-443 Steam Gen. #1 Pressure Channel #4 LP-484B,Cl-430 Steam Gen. #2 Level Channei #5 FP-484B,C3-746 Steam Gen. #2 Steam Flow Channel #6 PP-489B,C2-444 Steam Gen. #2 Pressure
2-ST-10 Page 3 of 9 Initials 2.0 Initial Conditions-(cont.)
Brush Recorder 3 Connect To:
Monitoring:
Channel #1 LP-494B,C1-431 Steam Gen. #3 Level Channel #2 FP-494B,C3-748 Steam Gen. #3 Steam Flow Channel #3 PP-494B,C2-445 Steam Gen. #3 Pressure Cnannel #4 CC-424 S/G A Aux. Feed Flow Channel #5 CD-425 S/G B Aux. Feed Flow Channel #6 DB-426 S/G C Aux. Feed Flow Brush Recorder 4 Connect To:
Monitoring:
]
Channel #1 FD-122,C6-556 RCS Charging Flow Channel #2 FD-150,C6-456 RCS Letdown Flow Channel #3 PP-403A,C4-433 Wide range Press. Press.
Channel #4 TD-454,C6-636 Press Steam Temp.
Channel #5 TD-453,C6-636 Press Liquid Temp.
NOTE:
Record the following on each strip chart:
a)
Test Number
]
b)
Recorder QA Number c)
Time and Date d)
Chart Speed e)
Scale Used f)
Test Point f)
Parameters 2.9 Set up the P-250 computer trend printer to monitor the parameters indicated in Attachment 6.4.
2.10 Notify the Shift Supervisor on duty of the impending test and co-ordinate its performance through him.
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2-ST-10 Page 4 of 9 Initials 3.0 Precautions 3.1 Maintain reactor coolant pump seal and thermal barrier differential pressure requirements as given in 2-0P-5.2.
3.2 Do not exceed 5% nuclear power at any time while the test is in progress.
3.3 Do not exceed any of the following temperature limits:
3.3.1 Core exit temperature of 610*F.
3.3.2 A T as indicated by T f 65*F.
~
H C
3.3.3 Tavg Temperature of 580.3 *F.
3.4 When equilibrium has been established after the initial transient, avoid any sudden changes in feedwater flow or in steam generator water level.
3.5 Af ter the reactor coolant pumps are tripped the normal Tavg and A T indications will become unreliable. A T and Tavg should be calculated by taking the difference and the average of the hot and cold leg temperature inoications respectively.
3.6 Maintain saturation margin greater than 10 degrees Fahrenheit at all times.
3.7 Maintain Tcold at approximately the pretrip temperature to maintain accurate NIS power level monitoring.
(Through the use of steam generator pressure control).
3.8 The pressurizer temperature shall be limited to a normal maximum heatup or cooldown of 90 F in any one hour period with a maximum spray water temperature to pressurizer temperature differential of 320 F.
3.9 Pressurizer spary should be initated slowly to minimize thermal stress and maintain cantinuous flow for uniform chemistry.
~
I 2-ST-10 Page 5 of 9 Initials 3.0 Precautions 3.10 The reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4-2 and 3.4-3 of the Technical Specificaitons during heatup or cooldown with a maximum heat up or cooldown of 50*F in any one hour period.
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2-ST-10 Page 6 of 9 Initials 4.0 Instructions 4.1 Ensure the pressurizer backup heaters Groups 1, 2, 4 & 5 will remain off by moving handswitches to "Stop" position and place in "Stop-Pull to Lock".
4.2 Record the data indicated on Attachment 6.2.
4.3 Start the computer trend printer printing on a one minute interval.
4.4 Shut off the pressurizer Group 3 control heater group by moving handswitch " Pull to Lock".
4.5 Record the time on the data recorder charts and then start them at 125 mm/ min.
CAUTION:
Continuously monitor main steamline pressure and carefully control feedwater addition during the transient to ensure the differential pressure between any two steam lines does not exceed 100 psid..This would initiate a safety injec-tion. Should this occur, refer to 2-EP-2.
(Feedwater to each steam generator must be equal before tripping the pumps).
4.6 Shutdown the reactor coolant pumps in accordance with 2-0P-5.2 (Simultaneously).
i NOTE:
At the initiation of natural circulation the following 1
temperature response is expected.
a)
Wide range hot increase C
b)
Wide range old slight decrease or constant
{
c) gore exit thermocouple increase d) avg indication unreliable e)
Delta-T indicaiton - unreliable f)
Pressurizer level increase 4.7 Verify natural circulation is established by follow.sg the opera-1 tional guidelines.
NOTE:
Natural circulation vill be stable when:
T T
1)
A T between wide range hot and gold is constant T
2) a T between wide range cold and cold and core exit thermocouple average temperature is constant 3)
Wide range T
~ c re exit thermocouple average tempera-hot ture i
4.71 Assume manual control of charging flow and match charging to letdown to maintain a constant RCS water volume.
2-ST-10 Page 7 of 9 Initials 4.0 Instructions 4.8 Once equilibrium has been established adjust trend printer intervals as specified by the test engineer.
NOTE:
The following steps will allow the pressurizer to cool and slowly decrease system pressure. The purpose is to deter-mine the time that saturation margin can be maintained without the use of pressurizer heaters and then verify the margin can be reestablished through charging or secondary flow.
(Reactor power level will be reduced to simulate an actual shutdown situation with residual heat).
4.9 The primary system pressure will now be monitored to determine the rate of depressurization. The saturation margin should be monitor-ed closely on the trend recorder and steam dump or RCS charging flow increased when the saturation margin approches 10 F or as specified by test engineer.
4.10 If Reactor Coolant System pressure decreases to <1990 psig:
4.10.1 Verify loss of two out of three "PRZ PRESS LO INT-SI CH I", "II" and "III" (2L-E5,E6,E7).
4.10.2 Place both (Train A and B) LO PRZ SI BLOCK AND RESET SWITCHES in the " BLOCKED" position.
4.10.3 Verify illumination of "PRZ PRESS-LEVEL SI BLOCK TRNS A &
B (2P-H2).
4.11 As Reactor Coolant System pressure decreases, reduce seal injec-tion HCV-2186, to maintain reactor coolant pump seal water flow at 6-12 GPM (not to exceed 30 gpm total flow).
4.12 Approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after RCP trips, reduce reactor power to approximately 1.5% and maintain this power level for the duration of the test.
2-ST-10 Page 8 of 9 Initials 4.0 Instructions 4.13 Once it is determined by the test engineer that sufficient data has been recorded to satisfy the requirements of this test or saturation margin approaches 10'F, increase saturation margin above 50*F through the use of charging flow and/or steam dump and pressurizer heaters.
NOTE:
Marginwi}lincreasebyeitherincreasingRCSpressureor reducing cold.
4.14 Stop the brush recorders and trend printers and attach the printouts and charts to this procedure.
4.15 Manually adjust PC-2444J to 40% output and energize the control heater group by moving handswitch to "0N".
Return PC-2444J to "AUT0".
NOTE:
Maintain RCS pressure at approximately 2235 by using Auxiliary Spray in if necessary.
4.16 Insert control bank D until the reactor is in the hot zero power test range.
CAUTION: Ensure pressurizer spray controller are at zero output prior to starting the first reactor coolant pumps.
4.17 Restart all three reactor coolant pumps in accordance with 2-0P-5.2.
4.18 Return the pressurizer backup heaters to automatic control by moving hand switch to the "AUT0" position.
4.19 Return pressurizer level to approximately 22%.
NOTE:
Conditions can now be established tor the conduct of the next test.
4.20 Complete Data Sheet 1.
Completed By:
Date:
2-ST-10 Page 9 of 9 5.0 Acceptance Criteria 5.1 Core exit T/C temperatures did not exceed 610 *F.
5.2 Delta-T for any loop does not exceed 65 *F.
'5.3 T,y for any loop does'not exceed 580.3
- F.
5.4 RCS saturation margin can be controlled through the use of charging and secondary steam flow.
5.5 Natural circulation can be established and maintained without the use of the pressurizer heaters.
6.0 Attachments 6.1 Test Equipment Data Sheets 6.2 Initial Conditions 6.3 Primary Calormetric 6.4 Process Computer Trend Block Data 6.5 Data Sheet 1
2-ST-10.1 Page 1 of 1 TEST EQUIPMENT DATA SHIET TEST EQUIPMENT DESCRIPTION
- MODEL N1?MBER VEPCO Q NUMBER 1
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Th:.s applies only to temporaril; installed test equipmer.t oc instrumentation Permanent instrumentation which is part of the system and shown on drawings should not be included.
Completed By:
Date:
2-ST-10.2 Page 1 of 3
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2-ST-10.4 Page 1 of 2 l
1 PROCESS COMPUTER TREND BLOCK A CCLUMNS ADDRESS PARAMETER UNITS 1
T0406A RCL A TCOLD 2
T0426A RCL B ICOLD 3
T0446A RCL C TCOLD 4
T0419A RCL A TH0T 5
T0939A RCL B TH0T 6
T0959A RCL C T 3
HOT 7
T0400A T
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T0420A T
00P B
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T0440A T
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- F AVG 10 T0403A AT LOOP A 11 T0423A AT LOOP B 12 T0443A AT LOOP C 13 F0128A CHARGING FLOW GPM 14 F0143A LETDOWN FLOW GPM 15 U1250 HIGHEST REL FUEL ASSY P%R I
16 LO480A PRESSURIZER LEVEL 17 10112A VCT LEVEL 18 U1251 HIGHEST REL ASSY Pk3 INDENT I
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2-ST-10 Attachasnt 6.4 Page 2 of 2 PROCESSCgff-*f.R.TRENDBLOCKB COLLHNS ADDRESS PARAMETER UNITS 1
LO400A S/G A LEVEL 2
LO420A S/G B LEVEL 3
LO440A S/G C LEVEL 4
PO400A S/G A PRESS PSIG 5
PO420A S/G B PRESS PSIG 6
PO440A S/G C PRESS PSIG 7
PO480A PRESSURIZER P PSIG 8
PO498A RCL SYSTEM P PSIG 9
P0142A CHARGING PRESS PSIG 10 UO482 AVG PZR PRESS PSIG 11 UO483 AVG PZR LEVEL 12 U1118 RX THERMAL P0bT.R
.W 13 U1170 AVG T/C TEnP
- F 14 AS REQUIRED HOTTEST T/C (QUADRANT 1)
F 15 AS REQUIRED HOTTEST T/C (QUADRANT 2)
F 16 AS REQUIRED HOTTEST T/C (QUADRANT 3)
- F 17 AS REQUIRED HOTTEST T/C (QUADRANT 4)
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2-ST-10 Attach:nent 6.5 Page 1 of 1 DA*.A S~r.:.e."'
1 A::sch c pies of the c:=putar ::and pri=: cut and de brush race de: charts :: dis page.
7:Om the above da:a, s:arti=g af:ar eqndbrius has been reached, calcula:a the deprassuri:stien ra:a and the pressuri:er cecidewn s:a (liquid : =p) and racerd balcw.
Deprassurizati:n 22:a psig/hr.
?:assurima Cecidew: la:a 7/hr.
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