ML19309B150

Special Test Procedure 2-ST-11:Effect of Steam Generator Secondary Side Isolation on Natural Circulation.

ML19309B150
Person / Time
Site:	North Anna
Issue date:	04/02/1980
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19309B136	List: ML19309B135 ML19309B137 ML19309B139 ML19309B142 ML19309B144 ML19309B148 ML19309B150 ML19309B151
References
2-ST-11, NUDOCS 8004030205
Download: ML19309B150 (26)

Text

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2 _s;_ 11 L.L.

VIRGINIA ELECTRIC AND ?OWER COMPANY Revisien Nc. 0 Date:

SPECIAL TEST PROCEDURE FOR NORTH ANNA POWER STAT 1CN UNIT j 2 717 3 EFFECT OF STEAM GENERATOR SECCNDARY SIDE ISOLATICN ON NATURM, CIRCULATICN . .

Precared Sv: R. R. ETLING Oate: Q3 i

l Engineering Ree:nrnended Accreval: Date: )

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I STATION NUCLEAR SAFETf AND CP5 RATING CCMMITTEE APcRCVAL CF Po,CCEDURE:

Chair =an's Sienature: Date: _

All cerscnnel conducting actual testing in acccedance with :his precedure will verify by their signature :nat they have read it in its entirety price to cemencing any testing:

l UST RESULU RE*/IE'4ED 3Y ENGINEER!NG: l Date:

TEST RESULT 5 APPRCVED BY STATION NUCLEAR SAFET/ AND CPERATING CCMMlHEE: O Chair.an's 5ignature_: Date: l l

Cemen ts :

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2-ST-11 Page 1 of 9 J

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 2 EFFECT OF STEAM GENERATOR SECONDARY SIDE INSOLATION ON NATURAL CIRCULATION

References:

1. Precautions, Limitation and Setpoints for Westinghouse NSSS system

2. Technical Specifications, North Anna Unit No. 2

3. WCAP-8747: North Anna Nuclear Design Report

4. North Anna Station Curve Book

5. 2-OP-5.2 1.0 Purpose i

1.1 Determine the effect of steam generator isolation on natural circulation conditions.

1.2 Verify that natural circulation can provide sufficient flow to remove decay heat after partial loss of heat sink.

1.3 Verify that natural circilation can be reestablished in primary loops af ter steam generators are returned to service.

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2-ST-11 Page 2 of 9 Initials 2.0 Initial Conditions 2.1 Reactor is critical and manually controlled at approximately 3%

power.

2.2 All three reactor coolant pumps in operation.

2.3 Rt. coolant system pressure is being maintained at approxi-mately 2235 psig and average coolant temperature is being maintained at approximately 520 F.

2.4 Steam generator pressure is being maintained at approximately 800 psig using steam dumps in automatic under pressure control.

2.5 Feedwater to the steam generator will be supplies by the main feedwater system with manual flow control if possible. If previous testing proves additional control is required, the auxiliary feedwa$er system will be used. Steam generator levels should be maintained at approximately 33% on narrow range indicators.

2.6 If auxiliary feedwater is to be used, at least 110,000 gallons in the condensate storage tanks are available to supply the steam generators.

2.7 Steam generator chemistry is in a condition that the absolute minimum steam generator blowdown can be maintained through the test.

2.8 The 100 psi steamline differential pressure safety injection bistables have been blocked through temporary conditions.

2.9 Brush recorders have been set up to monitor test points at the following locations:

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2-ST-11 Page 3 of 9 Initials 2.0 Initial Conditions (cont.)

2.9.1 Recorder No. 1 (6 Channel)

Channel Parameter Connect To:

1 RCS Flow-Loop 1 FP-414B, C1-432.1 2 RCS Flow-Loop 2 FP-424B, C1-433.1 3 RCS Flow-Loop 3 FP-434B, C1-434.1 5 Pressurize Pressure PP-455B, C1-427.1 6 Pressurizer Isvel LP-459B, C1-442.1 2.9.2 Recorder No. 2 (6 Channel)

Channel Parameter Connect To:

1 SG 1 Pressure PP-474B, C2-443 2 SG 1 Level LP-474B, C1-429 3 SG 1 Steam Flow FP-474B, C3-741 4 SG 2 Pressure PP-484B, C2-444 5 SG 2 Level LP-484B, C1-430 6 SG 2 Steam Flow FP-434B, C3-746 2.9.3 Recceder No. 3 (6 Channel)

Channel Parameter Connect To:

1 SG 3 Pressure PP-494B, C2-445 2 SG 3 Level LP-494B, C1-431 3 SG 3 Steam Flow FP-494B, C3-748 4 SG A Aux Feed Flow CC-424 5 SG B Aux Feed Flow CD-425 6 SG C Aux Feed Flow CB-426 2.9.4 Record the following on all strip charts:

a) Test Number b) Recorder QA Number c) Time and Date d) Chart Speed e) Scale Used f) Test Point g) Parameter 2.10 Record the following parameters on the reactivity computer recorders:

a. Flux

b. Average wide range T old

c. Average wide range T hot

d. Average steam generator pressure

2-ST-11 Pago 4 of 9 Initials 2.0 Initial Conditions (cont.)

2.11 Four incore T/C may be trended as determined by the test engineer on the analog trend recorders in the main control room. It is suggested that these thermocouples be the bettest responding thermocouple in each core quadrant.

2.12 Control Bank D is at approximately 160 steps or as specified by the test engineer to permit reactor power increase up to approxi-mately 3% (required control bank D position may be determined during the hot zero power test program).

2.13 Pressurizer pressure and level control are in automatic, main-taining pressurizer pressure at approximately 2235 psig and level at approximately 22%.

2.14 Normal charging and letdown are in service under automatic control. 1 2.15 Notify t.te Shif t Supervisor on duty of the impending test and co-ordinate its performance through him.

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2-ST-11 Page 5 of 9 Initials 3.0 Precautions 3.1 Do not exceed 5% rated thermal power at any time while the test is in progress.

3.2 Do not exceed any of the following temperature limits.

3.2.1 Core exit temperature of 610*F.

3.2.2 aT as indicated by T H

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C f 100 F.

3.3.3 Tavg of 580.3 F for any loop.

3.3 Maintain reactor coolant pump seal and thermal barrier differen-tial pressure requirements as specified in 2-0P-5.2.

3.4 Avoid any sudden changes in feedwater flow or steam generator level.

3.5 Ensure seal flow to each reactor coolant pump is maintained at or slightly abov 6 gpm during the test.

3.6 Af ter the reactor coolant pumps are tripped, the normal Tavg and AT indications will become unreliable. AT and Tavg should be calculated by taking the difference and the average of the hot and cold leg temperature indications respectively.

3.7 Do not exceed 1600 psi primary to secondary differential pressure limit.

3.8 Maintain reactor colant system leg temperatures as stable as possible during system transients. This is required to determine changes in core power level on the MIS channels.

3.9 Because safety injection on high-steamline differential pressures has been disabled, manual safety injection should be initiated

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if required.

3.10 Do not restart a reactor coolant pump if there is any indication of an excessively high AT in any of the loops.

2-ST-11 Page 6 of 9 Initials 4.0 Inst ructions 4

4.1 Start brush recorders, at 125 mm/in analog trend recorders, reactivity computer and F-2~0 trend blocks at one minute intervel.

CAUTION: Following reactor coolant pump trip Tavg and aT indication will be unreliable.

4.2 Simultaneously trip all reactor coolant pumps. Reduce seal water flow to each pump to approximately 6 gpm.

4.3 Maintain steam generator level at approximately 33%.

NOTE: At initiation of natural circulation the following initial response is expected.

1. Wide range T , increase

2. Wide range I ofd,slightdecreaseorconstant

3. Core exit thermocouples, increase

4. Pressurizer level, increase Natural circulation will be stable when:

1. AT between wide range T , and T eold is constant

2. 6T between wide range T old.a d core exit thermo-couple average temperature is cot _ tant

3. Wide range T E e re exit thermocouple average hot temperature 4.4 Adjust setpoint on steam dump pressure controller PC-2464P as needed to maintain cold leg temperature at the initial values.

4.5 Adjust setpoints on atmospheric relief valve pressure controllers PCV-MS-201A, B, C for each loop to maintain steam pressure below 1025 psig before isolating any steam generators. This should prevent opening of main steam safety valves.

4.6 Establish maximum flow through normal letdown path, and manually increase charging flow to maintain a constant RCS water vclume.

Start an additional centrifugal , charging pump if necessary.

CAUTION: Monitor primary to secondary differential pressure very closely during the transient and do not allow it to exceed 1600 psi.

NOTE: Allow the pressurizer level to increase when T is increased. ^"8

2-ST-11 Page 7 of 9 Initials 4.0 Instructions (cont.)

a 4.7 Close MOV-FW-2554C, TV-MS-201C and TV-MS-213C. Isolate steam generator to C. Carefully control feedwater additions to the remaining steam generators to hold the levels at approximately_

33%. It will be necessary to adjust the steam dump pressure controller setpoint to reduce T in the unisolated loops cold so that the steam generator pressure in the isolated loop remains below the setpoint of the atmospheric relief valve.

NOTE: During the transient the following responses can be expected.

1. Wide range T E, slight increase

2. Wide range T for Loop C, increase

3. Wide range T C fforotherloops,decreasedusing steam dump

4. Core exit thermocouples, slight increase 4.8 Allow natural circulation conditions to stabilize. Steady state should be achieved when the calculated loop C 6T is approximately zero.

4.9 Verify that the calculated value for Tavg for the remaining 2 loops have stabilized. If Tavg continues to increase and a

cannot be stabilized the test engineer should determine whether further testing can be conducted.

4.10 Slowly reduce the setpoint on atmospheric relief valve controller PC-2464B and reduce steam dump to condenser, allowing steam generator #C to reach approximately equilibrium with steam pressure of 1005 psig.

4.11 Slowly open PCV-MS-201C to equalize pressure with steam header if necessary. Open TV-MS-213C and the TV-MS-201C to unisolate "C" steam generator. Open MOV-FW-2554C and maintain steam generator level at % 33%.

l 2-ST-11 l Page 8 of 9 Initials 4.0 Instructions (cont.)

NOTE: During the transient the following responses can be expected.

1. Wide range Thot, decrease

2. Wide range Teold for loop C, decrease

3. Wide range Teold for loops, A and B, increase using steam dump 4.12 Allow natural circulation conditions to stabilize. Steady state should be achieved when the calculated loop AT's are approximately equal.

4.13 Stop recording test data.

4.14 Insert control bank D until the reactor is in the hot zero power test range.

CAUTION: Ensure pressurizer spray controlle. s are at zero cutput prior to starting the first reactor coolant pump.

4.15 Restart all three reactor coolant pumps in accordance with 2-0P-5.2.

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Completed By:

Date:

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2-ST-11 Page 9 of 9 Initials 5.0 Acceptance Criteria 5.1 Core exit thermocouple temperature does not exceed 610 degrees Fahrenheit.

5.2 AT for any loop does not exceed 100 degress Fahrenheit.

5.3 Tavg for any loop does not exceed 580.3 degrees Fahrenheit.

5.4 Sufficient natural circulation could be maintained in active primary loops to maintain stable temperatures following partial loss of he3t sink.

5.5 Natural circulation could be restored to the inactive loop when associated the steam generator were returned to service.

6.0 Attachments 6.1 Test Equipment Data Sheet 6.2 Initial Conditions 6.3 Primary Caloremetric 6.4 Process Computer Trend Block Data 1

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Attachment 6.1 Page 1 of 1 TEST EQUIPMENT DATA S'rfEET TEST EQUIPMENT DESCRIPTION

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• NOTE: This applies only_ to temporarily installed test equipment or instrumentation i

Permanent instrumentation which is part of the system and shown on drawings j should not be included.

Completed By:

Date:

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2-ST-11 Attachment 6.4 Page 1 of 2 PROCESS COMPUTER TREND BLOCK A COLUMNS ADDRESS PARAMETER UNITS 1 T0406A RCL A T F COLD 2 T0426A RCL B T F COLD 3 T0446A RCL C T F COLD I 4 T0419A RCL A T F HOT 5 T0939A RCL B T F HOT 6 T0959A RCL C T HOT 7 T0400A T LOOP A *F AVG 8 T0420A T LOOP B *F AVG 9 T0440A Tgyg LOOP C *F

. 10 T0403A AT LOOP A  %

11 T0423A AT LOOP B  %

12 T0443A AT LOOP C  %

13 F0128A CHARGING FLOW GPM 14 F0134A LETDOWN FLOW GPM 15 U1250 HIGHEST REL FUEL ASSY PWR 16 LO480A PRESSURIZER LEVEL  %

17 LO112A VCT LEVEL  %

18 U1251 HIGHEST REL ASSY PWR INDENT

2-ST-11 Attachment 6.4 Page 2 of 2 PROCESS COMPUTER TREND BLOCK B COLUMNS ADDRESS PARAMETER UNITS 1 LO400A S/G A IIVEL  %

2 LO420A S/G B LEVEL  %

3 LO440A S/G C LEVEL  %

4 PO400A S/G A PRESS PSIG S 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 PO'ER .W 13 U1170 AVG T/C TEMP 'F 14 AS REQUIRED HOTTEST T/C (QUADRAM 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) *F l l

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