ML19305E273

Startup Test Procedure 2-ST-14, Establishment of Natural Circulation from Stagnant Conditions.

ML19305E273
Person / Time
Site:	North Anna
Issue date:	04/21/1980
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19305E260	List: ML19305E259 ML19305E264 ML19305E268 ML19305E273 ML19305E274
References
2-ST-14, NUDOCS 8004230255
Download: ML19305E273 (15)

Text

_ _ _ __ _ _ _ _ ____ -__ _ _ _ _ __

,7 O 1 1

1 Page 1 of _ l 2 ST 14 d iIRGINIA ELECTRIC AND POWER COMPANY Revision No.. O l Date: I NORTH ANNA POWER STATION UNIT # 2 STARTUP TEST PROCEDURE FOR TITLE: ESTABLISHMENT OF NATUnnL CIRCULATICN FROM STAGNANT CCNDITIONS l l

Prepared By: E.R. SMITH, .JR. Date:

Engineering Recommended Approval: Date:

STATICN NUCLEAR SAFETY AND CPERATING COMMITTEE APPROVAL OF PROCEDURE,:

Chalrman's SIgnacura: Date:

All personnel conducting actual testing in accordance with this procedure will verify by their signature that they have read it In its entirety prior to commencing any testing:

NOT A CONTROL!.ED OCCUMENT

~ 'I20 NOR NECESSAfitLY THE )

i LAicdi. .idVlS:CN l

d TEST RESULTS REVIEWED BY ENGINEERING: Date:

TEST RESULTS APPROVED BY STATION NUCLEAR SAFEvf AND OPERATING COMMITTEE:

Chairman's Signature: Date:

Comen ts :

i 8004280 .h 6

-l

< t s .

c.

i i

TEST RESULTS (Use additional pages as needed) Page 2 of f I

110 OtSCRE?ANCIE3 (List av nur .ce r) :

.n... _ ___. .-

r t

'i, i

1 i

s i i

I

,RESOLUTICN CF 315C?,EPANCIE3 (LI5t by numcer corres:cnding to above): !II [

l l

l l

l CRITICUE: l i2 t

- l l

. 9 -

CHRCNOLCGICAL LOG (Use add'l pages as needed) Page _ of i f3 O

O t

I k

e

(

l l

l I

i O

k e

• O +e M

2-ST-14 Page 1 of 9 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 2 ESTABLISHMENT OF NATURAL CIRCULATION FROM STAGNANT CONDITIONS

References:

1. Precautions, Limitation and Setpoints for Westinghouse NSSS e system <

2. Technical Specifications, North Anna Unit #2

3. WCAP-8747: North Anna Nuclear Design Report

4. North Anna Station Curve Book

5. 2-0P-5.2 1.0 Purpose 1.1 Verify establishment of natural circulation from stagnant (no flow) conditions in the primary system using reactor power to r simulate decay heat.

L k

2-ST-14 Page 2 of 9 Initials 2.0 Initial Conditions 2.1 Reactor critical in the hot zero power test range.

2.2 All reactor coolant pumps operating.

2.3 Steam pressure approximately 900 psig (Tavg

• 531*F) and being maintained by the atmospheric relief valves or by steam dump to the condenser (preferred).

2.4 Steam generator water level at approximately the normal no-load setpoint and being maintad " by auxilitty feedwater system (motor-drivert pumns).

2.5 Control Bank D at approximately 10 steps or as specified by the test engineer to permit reactor power increase up to approximately 3% (required control band D position may be determined during the hot zero power test program).

2.6 Overpower AT trip is disabled.

2.7 Overtemperature AT trip is disabled.

2.8 Pressurizer level control in manual.

2.9 Record the following parameters 2.9.1 Obtain thermocouple map at 15-minute intervals.

2.9.2 Install brush recorders to record data at the following locations.

. Brush Recorder No. 1 Connect To: Monitoring Channel No. I FP-414B, C1-432 RCS Fl: , Loop i .

Channel No. 2 FP-424B, C1-433 RCS Flow, Loop 2 Channel No. 3 FP-434B, C1-434 RCS Flow, Loop 3 Channel No. 4 PP-455B, C1-427 Pressurizer Pressure Channel No. 5 '?-459B, Cl-442 Pressurizer Level

2-ST-14 Page 3 of 9 Initials 2.0 Initial Conditions (cont.)

Brush Recorder No. 2 Connect To: Monitoring Channel No. 1 PP-474B, C2-433 Steam Gen. #1 Pressure Channel Nc. 2 LP-474B, C1-429 Steam Gen. #1 Level Channel No. 3 FP-474B, C3-741 Steam Gen. #1 Steam Flow Channel No. 4 PP-484B, C2-444 Steam Gen. #2 Pressure Channel No. 5 CP-489B, C1-430 Steam Gen. #2 Level Channel No. 6 FP-484B, C3-746 Steam Gen. #2 Steam Flow Brush Recorder No. 3 Connect To: Monitoring Channel No. 1 PP-494B, C2-445 Steam Gen. #3 Pressure Channel No. 2 LP-494B, C1-431 Steam Gen. #3 Level Channel No. 3 FP-494B, C3-748 Steam Gen. #3 Steam Flow Channel No. 4 S/A6 Aux Feed Flow Channel No. 5 S/B6 Aux Feed Flow Channel No. 6 S/C6 Aux Feed Flow 2.9.3 Record the following on eact strip chart:

a) Test Number b) Recorder QA Number c) Time and Date d) Cabrt Speed e) Scale Used t f) Test Point l g) Parameters 2.9.4 Record on reactivity-computer recorder I

a. Flux

b. Average wide range T cold i

c. Average wide range T

d. AverageSteamgenerakohpressure l 2.13 Four incore T/C may be trended on the analog trend recorder on j the main control board. (Suggest trending the four hottest thermocouples, one from each quadrant.)  ;

l 2.14 A steady feed to the steam generators should be set up to minimize temperature variation in the RCS.

2.15 Notify the Shift Supervisor on duty of the impending test and co-ordinates its performance through him.

2-ST-14 Page 4 of 9 Initials 3.0 Precautions 3.1 Do not exceed 5% rated thermal power.

3.2 Do not exceed any of the following temperature limits.

3.2.1 610*F for any core outlet thermocouples 3.2.2 65*F for any loop Delta-T 3.2.3 580.3*F for any loop Tavg 3.3 Avoid sudden changes in steam pressure.

3.4 Avoid sudden changes in auxiliary feedwater.

3.5 Maintain pressurizer pressure at about 2235 psig.

3.6 Onset of natural circulation may be accompanied by a power increase due to the introduction of cooler water into the core.

3.7 During natural circulation, reactor coolant loop transient time is on the order of 3 to 5 minutes.

3.8 Pressure should remain equalized between steam generators throughout the test. ,

3.9 Maintain constant steam ger.erators pressure throughout test except where specifically stated otherwise.

3.10 Maintain steam generator water level contant at

• 33%.

3.11 Do not maintain no flow conditions in the primary system for j more than 30 minutes, j l

3.12 Reactor coolant pumps should not be restarted for 30 minutes l

after pump trip unless required by this instruction or unless i

safety concerns necessitate the re-establishment of forced '

circulation.

3.13 Monitor condensate storage tank level '.hroughout test.

I

4 2-ST-14 Page 5 of 9 Initials 3.0 Precautions (cont.)

3.14 Do not exceed primary to secondary differential pressure of 1600 psi.

3.15 Do not exceed 100 psi differential pressure between any two steam lines. This will result in a safety injection signal.

3.16 Note pr.aible effects of a positive moderator temperature coefficient.

e e

i l

r l

l

2-ST-14 Page 6 of 9 Initials 4.0 Instructions CAUTION: If primary system temperatures reach within 10*F of the limits specified in step 3.2:

i r

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

b) Verify pressurizer spray valves closed.

c) Start loop 3 reactor coolant pump.  ;

d) Establishe stability: presurizer level and pressure, steam generator level and pressure, and primary system temperature.

e) Return pressurizer level control to automatic.

f) Start the remaining reactor coolant pumps one at a time.

4.1 Start recorder and P-250 trend blocks.

4.2 Begin recording crossover pipe T/C temperature at 5-minute ,

intervals.

CAUTION: Following reactor coolant pump trip Tave and Delta-T indication will be unreliable.

4.3 Trip all reactor coolant pumps simultaneously and record time:

4.4 Stabilize steam generator water level at approximately the no-load level.

4.5 Close main steam dump valves to condenser. l 4.6 Close auxiliary feedwater system valves.

NOTE: During control bank withdrawal continuously monitor increase in:

a) reactivity computer flux level, b) NIS indicated power level, and core exit thermocouple temperature (except delayed response).

4.7 Approximately 5 minutes after auxiliary feedwater system valve closure open main steam dump valves to condenser as needed, open auxiliary feedwater level valves, and begin control bank D withdrawal, as requested by the test engineer, until reactor power is at 1 percent.

l

2-ST-14 Page 7 of 9 Initials ,

4.0 Instructions (cont.)

4.8 Record control bank D position: steps f CAUTION: Onset of natural circulation may be accompanied by a i power increase. Control bank D may be inserted to I reduce the magnitude of the increase. Imediately 1 following power transient, return control bank D to the l position recorded in step 4.8. j l

CAUTION: Reduction in T may result in a nonconservative,  !

falseNISpoweEkvelindication. Do not withdraw f control bank D beyond the position recorded in ste) 4.8 unless req::ested by test engineer.

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

1) Reactivity computer flux level increase

2) NIS power level indication increase l

3) Wide range T increase

4) Wide range T slight decrease or stable ;

d

5) Core exit thermocouples a) Increase if T/C temp. + (*17'F) < initial T I cold b) Decrease if T/C temp. + (*17'F) < initial T cold CAUTION: Primary coolant system may be held in a stagnant condition  !

(no flow) for a maximum of 30 minutes. If the NIS or  !

primary system temperature instrumentation does not l indicate that natural circulation has started within 25 '

minutes after RCP trip, insert control bank D until  !

reactor power is in the hot zero power test range, and  !

restart reactor coolant pumps as previously described.  !

4.9 Reduce steam generator pressure 50 psig $20'F or until natural  ;

circulation is initiated. Rate of pressure decrease should be i accomplished at a controlled rate as requested by the test l

engineer. Utilize auxiliary feed as necessary to maintain steam generator level constant.

NOTE: Natual circulation flow will be stable when:

a) AT between wide range T g and T eold is constant.

b) AT between wide range T average eold and core exit T/C temperatue is constant.

c) Wide range T E core exit T/C average temperature.

2-ST-14 Page 8 of 9 Initials 4.0 Instructions (cont.)

4.10 When natural circulation flow has established, slowly regulate secondary side steam flow T cold to

• 547*F. During natural circulation loop transient time is long (3 to 5 minutes).

4.11 Maintain natural circulation under the established conditions ,

for approximately 15 minutes.

4.12 Stop recording test data.

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

4.14 Restart reactor coolant pumps one at a time.

4.15 Attach all strip charts, trend data, and T/C maps to this test procedure.

4.16 Return pressurizer level control to automatic.

NOTE: Reactor trip disregard actuation signals specified in steps 2.6, 2.7, may remain disabled provided testing scheduled to be performed immediately following this test required disabling the trip or safety injection signal. If a trip is to remain disabled place N/A and i your initials on the signature line.

4.17 Overpower AT trip is operable.

4.18 Overtemperature AT trip is operable.

Completed By:

Date:

i i

2-ST-14 Page 9 of 9 5.0 Acceptance Criti,-ia 5.1 Delta-T established between wide range T hot and T is stable eold and less than 65'F. I 5.2 Delta-T established between wide range T eold and core exit T/C ,

averags temperatue is stable and less than 65*F.

6.0 Attachments 6.1 Test Equipment Data Sheet  ;

6.2 Trend Blocks i

t l

2-ST-14 Attachment 6.1 Page 1 of 1 s

TEST EQUIPMENT  :

DATA SHEET i TEST EQUIPMENT DESCRIPTION

• MODEL NUMBER VEPCO QA NUMBER e

t l 4 l l 4  !

I I

, i I t l

i I

j i e

r i

) l I

f I

i i

e i ,

• NOTE: This applies only_to temporarily installed test equipment or instrumentation Permanent instrumentation which is part of the system and shown on drawings should not be included.

Completed By:

Date: _

- -- ~ . - - - . -

2-ST-14 Attachment 6.2 Page 1 of 2 l-PROCESS COMPUTER TREND BLOCK A COLUMNS, ADDRESS PARAMETER UNITS I 1 T0406A RCL A T COLD -

2 T0426A RCL B T COLD 3 T0446A RCL C T COLD 4 T0419A RCL A T HOT L T0939A RCL B T HOT 6 T0959A RCL C T HOT 7 T0400A T A 'F AVG 8 T0420A T '

AVG  ;

9 TO440A T C 'F AVG 10 T0403A AT LOOP A  % ,

i 11 T0423A AT LOOP B  %

12 T0443A AT LOOP C  %

i 13 F0128A CHARGING FLOW GPM 14 F0134A LETDOWN FLOW GPM l

15 U1250 HIGHEST REL FUEL ASSY PWR 16 LO480A PRESSURIZER LEVEL  %

17 LO112A VCT LEVEL  %

l 18 U1251 HIGHEST REL ASSY PWR INDENT i

l

2-ST-14 Attachment 6.2 Page 2 of 2 PROCESS COMPUTER TREND BLOCK B COLUMNS 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 P0440A 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 POWER MW 13 U1170 AVG T/C TEMP *F 14 AS RcQUIRED 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) *F 1

.