ML19309B151

Special Test Procedure 2ST-12:Natural Circulation at Reduced Pressure.

ML19309B151
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-12, NUDOCS 8004030206
Download: ML19309B151 (27)

Text

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P Page 1 of 2 -ST- 12 W VIRGINIA ELECTRIC AND POWER COMPANY gey;3;en ne,: o Date:

SPECIAL TEST PRCCEDURE FOR NCRW M A pgygg 3747ggg gg g7 y 2 b TITLE: NATURAL CIRCULATICN AT RECUCED PRESSURE Precared Sv: R. R. ETLING Date: 63 Engineerino Recermended Accreval: Date:

STATION NUCLEAR SAFETf AND CPERATING CCMMITTEE ApoROVAL CF PCCCECURE_.:

Cha i rman 's S igna ture: Data:

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All perscnnel ccnducting actual testing in acccedance with this precedure will verify by their signature that they have read it in i ts entirety prior te cemencing any testing:

(6 TEST RE3 ULT 3 REVIE'4ED BY ENGINEERING:

Date:

TEST RESULTS APOROVED BY STATION NUCLEAR SAFIT/ AND CPERATING COMMlHEE:

Cha i r .an 's S igna ture: Da te:

Cecrnents :

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800 4030 E Og.

i TEST RESULTS (Use additional pages as needed) Page 2 of OlSCRE?ANCIES (List my numce r) : 110 l

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RESCLUTICN CF DISCREPANCIES (Lis; by numcer correscending :o a'c eve): III CRITICUE: l12 l

t CHRCN0 LOGICAL LOG (Use add'l pages as needed)' Page _ cf i 13 l

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2-ST-12 Page 1 of 9 VIRGINIA EI.ECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO._2 NATURAL CIRCULATION AT REDUCED PRESSbM

REFERENCES:

1. Precautions, Limitations, and Setpoints for Westinghouse NSSS System i

2. Technical Specifications, North Anna Unit #2

3. WCAP-8747; North Anna Nuclear Design Report

4. ASME Sresa Tables

5. North Anna Station Curve Book

6. 2-0P-5.2 1.0 Purpose 1.1 Verify tue ability to maintain natural circulation at reduced pressure levels.

1.2 Verify the accuracy of the saturation margin indication from the plant computer.

1.3 Provide operational experience at lower saturation margins and the affects of charging and secondary steam flow on the control of the saturation margin.

a 2.0 Initial Conditions NOTE: This test can be done in conjunctica with the Natural Circulation With Loss of Pressurizer Heaters.

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-ST-12 Page 2 of 9 Initials 2.0 Initial Conditions (co-2.2 All 3 reactor coolan* pumps in operation.

2.3 Steam generar level maintained at approximately 33% on the narrow range indicators by the main feedwater pumps. (Auxilia ry feedwater may be used if main feedwater proves to difficult to control.)

2.4 Preararizer pressure and level being maintained automatically at atyroximately 2235 psig and 22% respectively.

2.5 RCS temperature (Tavg) approximately 547*F.

2.6 Low Power Physics Test Prograu 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.

2.8 Connect brush recorders to the following test points:

Brush Recorder 1 Connect To: Monitoring:

Channel #1 FP-414B, Cl-432 RCS Flow-Loop 1 Channel #2 FP-424B, C2-433 RCS Flow-Loop 2 Channel #3 FP-434B, C3-439 RCS Flow-Loop 3 Channel #5 FP-455B, C1-427 Pressurizer Pressure Channel #6 LP-459B, C1-442 Pressurizer Level Brush Recorder 2 Connect To: Monitoring:

Channel #1 LP-474B, C2-429 Steam Gen. #1 Level Channel #2 FP-474B, C3-741 Steam Gen. #1 Steam Flow Channel #3 LP-474B, C2-433 Steam Gen. #2 Pressure Channel #4 LP-489B, C1-430 Steam Gen. #2 Level l Channel #5 FP-484B, C3-746 Steam Gen. #2 Steam Flow l Channel #6 PP-489B, C2-444 Steam Gen. #2 Pressure 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 Channei #4 CC-424 S/G A Aux Feed Flow Channel #5 CD-425 S/G B Aux Feed Flow Channel #6 CB-426 S/G C Aux Feed Flow l

2-ST-12 Page 3 of 9 INITIALS 2.0 Initial Conditions (cont.)

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, C4-443 Wide range RCS Pressure Channel #4 TD-454, C6-636 Pressurizer Steam Temp Channel #5 TD-453, C6-636 Pressurizer Liquid Temp 2.9 Record the following on each recorder chart, 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 on reactivity-computer recorder a) Flux b) Average wide-range T eold c) Average wide-range T g ,t d) Average steam-generator pressure 2.11 Set the trend recorders and computer trend printer in the main control room to monitor the parameters indicated in attachment 6.5.

2.12 Notify the shift supervisor on duty of the impending test and coordinate its performance through him.

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2-ST-12 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-OP-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 AT as indicated by ? 3 -T C f 65*F.

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 After 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 indicaticns 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.

3.8 The pressurizer temperature shall be limited te a normal maximum heatup or cooldown at 90*F in any one hour period with a l maximum spray water temperature to pressurizer temperature differential of 320*F.

3.9 Pressurizer spray should be initated slowly to minimize thermal 1

stress and maintain continuous flow for uniform chemistry.

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2-ST-12 Paga 5 of 9 INITIALS 3.0 Precautions (cont.)

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 Specifi-cations during heatup or cooldown with a maximum heatup or cooldown of 50 F in any one hour period.

4.0 Instructions 4.1 Ensure the pressurizer backup heaters Group 1,2,4 and 5 remain off by moving handswitches to the '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 at a one minute interval.

4.4 Shutoff the pressurizer control heater group by moving hand-switch to ' Pull to Lock'.

4.5 Record the time, on the data recorder charts and then start them at 125mm/ min.

. CAUTION: Continuously monitor main steam line pressures and l

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 injection. 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).

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

a) Wide range Thot - increase b) Wide range Teold - slight decreace or constant c) Core exit thermocouple - increase d) Tavg indication - unreliable e) Delta-T indication - unreliable f) Pressurizer level and pressure - increase

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, 2-ST-12 Page 6 of 9 INITIALS 4.0 Instructions (cont.)

4.7 Verify natural circulation is established by following the operational guidelines.

NOTE: Natural Circulation will be stable when:

1) AT between wide range Thot and Tcold is constant.

2) AT between wide range Tcold and core exit thermocouple average temperature is constant.

3) Wide range Thot s core exit thermocouple average temperature.

4) Assume manual control of charging f3cw and match charging to letdown to maintain a constant RCS water volume.

4.8 Once equilibrium has been established adjust trend printer printout intervals aa specified by the test engineer.

NOTE: A slow cooling of the pressurizer will begin at this point and a corresponding decrease in RCS pressure.

Maximum spray water temperature to pressurizer temperature differential of 320*F.

4.9 Record the highest T/C temperature indicated on the T/C maps, the lowest of the three pressurizer pressure protection channels, and the saturation margin indicated on the analog trend recorder on data sheet 6.3 at periodic intervals during the depressuriza-tion.

NOTE: If desired, tne depressurization rate can be increased by using auxiliary spray. Once the RCS pressure drops below 1700 psig, the pressure reading for Data Sheet.

6.3 should be taken from the RCS wide range pressure indicators.

CAUTION Safety injection must be manually blocked when Reactor Coolant System pressure decreases to < 1930 psig:

Verify loss of two out of three "PRZ PRESS LO INT-SO CH I", "II" and "III" (2L-E5, E6, E7).

Place both (Train A and B) LO PR2 SI BLOCK AND RESET SWITCHES in the " BLOCKED" position.

Verify illumination of "PRZ PRESS-LEVEL SI BLOCK TRNS A

& B" (2P-H2).

As Reactor Coolant System pressure decreases, reduce seal injection HCV-2186, to maintain reactor coolant pump seal water flow at 6-12 GPM (not to exceed 30 gpm total flow).

2-ST-12 Page 7 of 9 INITIALS 4.0 Instructions (cont.)

4.10 Approximately one hour after RCP trips, reduce reactor power to approximately 1.5% and maintain this power level for the duration of the test.

4.11 Continue to monitor the core exit T/C temperature to verify natural circulation is maintained as the saturation margin is decreased. Continue pressure drop until the test engineer indicates sufficient data has been recorded to verity the accuracy of the saturation margin indicated on the trend recorder.

Increase charging and/or steam flow to increase the saturation margin at this time.

NOTE: Do not allow the saturation margin to decrease below 10'F.

The margin can be increased by either increasing RCS pressure or reducing Teold.

4.12 Using 1967 ASME steam tables, determine the saturation margin using the pressure and temperature recorded in Data Sheet 6.3 and plot this value along with the saturation margin taken frem the saturation meter vs time and attach to this procedure.

NOTE: Step 4.12 can be conducted concurrent with the depressurization.

4.13 Increase the saturation margin back to above 50 degrees Fahrenheit and stop the brush recorders and trend printers. j Attach copies of the printouts and charts to this procedure.

4.14 An evaluation of the accuracy of the saturation meter should be done at this time. The saturation meter should indicate a saturation margin within 3% of the margin determined from the 1

steam tables.

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2-ST-12 Page 8 of 9 INITIALS 4.0 Instructions (cont.)

4.15 Increase RCS pressure back to 2235 by selectively energizing the pressurizer backup heaters.

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

4.17 Restart all 3 reactor coolant pumps in accordance with 2-0P5.2.

4.18 Return pressurizer level to approximately 22% and return RCS pressure and level control to automatic.

NOTE: Conditions can now be established for the conduct of the next test.

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2-ST-12 Page 9 of 9 5.0 Acceptance Criteria 5.1 Core exit T/C temperatures does not exceed 610*F.

5.2 Delta-T for any loop does not exceed 65*F.

5.3 T,yg for any loop does not exceed 580.3*F.

5.4 Natural circulation can be established and maintained at reduced low RCS pressure.

5.5 The plant computer calculated saturation margin is in agreement with margins determined using recorded plant parameters.

6.0 Attachments 6.1 Test Equipment Data Sheet 6.2 Initial Conditions 6.3 Primary Caloremetric 6.4 Process Computer Trend Block Data b.5 Saturation Margin Data Sheet e

2-ST-12 Attachment 6.1 Page 1 of I l

TEST EQUIPMENT DATA SHEET

, TEST EQUIPMENT DESCRIPTION

• MODEL NUMBER VEPCO QA NUMBER 1

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• NOTE: This applies only to temporarily installed test equipment or instrumentation Permanent instrumentation which i.4 cart of the system and shown on drawings should not be included.

Completed By:

Date:

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2-ST-12 Attachment 6.4

, Page 1 of 2 PROCESS COMPUTER TREND BLOCK A COLUMNS ADDRESS PARAMETER UNITS 1 T0406A RCL A T COLD 2 T0426A RCL B T COLD 3 T0446A RCL C T COLD 4 T0419A RCL A T H0T 5 T0939A RCL B T H0T 6 T0959A RCL C T H0T 7 T0400A T A AVG 8 T0420A T AVG 9 T0440A T LOOP C *F VG 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 PWR 16 LO480A PRESSURIZER LEVEL  %

17 LO112A VCT LEVEL  %

18 U1251 HIGHEST REL ASSY PWR INDENT t

I

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2-ST-12 Attachment 6.4 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 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 POWLR MW 13 U1170 AVG T/C TEMP *F 14 AS REQUIRED HOTTEST T/C (QUADRANT 1) *F 15 AS REQUIRED HOTTEST T/C (QUADRANT 2) *F 16 AS REQUIRED *F HOTTEST T/C (QUADRANT 3) 17 AS REQUIRED HOTTEST T/C (QUADRANT 4) *F i

.a 2-ST-12 Attachment 6.5-Page 1 of 1 SATURATION MARGIN DATA SHEET Lowest of 1

PI-68-34A, 334A, 323A or 322A (PI-68-66A if below Higest Incore Computer Saturation 1700 psig) T/C Margin on Trend i

Time = 0 l

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Completed By:

Date: _,,