ML19309B137

Special Test Procedure 2-ST-6:Cooldown Capability of Chemical & Vol Control Sys.

ML19309B137
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-6, NUDOCS 8004030185
Download: ML19309B137 (15)

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-sT- 6 1 VIRGINIA ELECTRIC AND PCWER COMPANY Revisicn No.:

Date:

SPECIAL TEST PROCEDURE FCR NORTH MMA PCWER STAT!CN UN IT .# 2 71TLE: CCOLDCW WABILITY OF THE CVCS I3 Precared Sv: R. R. ETLING Date:

• Engineering Recommended Acoreval: Date:

STATION NUCLEAR SAFETY AND CPERATING COMMITTEE APPROVAL OF PROCEDURE _:

Chai man's Signature: Date:

All perscnnel ccnducting actual testing in acccedance with this precedure will verify t:y their signature that they have read it in its entirety prior te cernnencing any testing:

d TEST RESULTS REVIE'4ED BY ENGINEERING:

Date: ,

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i' TEST RESULTS APoROVED BY STATICN NUCLEAR SAFE f AND CPE3ATING COMMlHEE: L .-

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1 Cernnen ts :

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i T7.37 RESULTS (Use additional pages as needed) Page 2 of i i

OlSCRE?ANCIES (List av numeer): l10 '

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l RE3OLUTION OF DISCRE?ANCIES (Lis ty numcer correscendinc :o aceve): III i

CRITICUE: 1II 4

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2-ST-6 Page 1 of 6 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 1 l

CCOLDOWN CAPABILIT' 'F THE CVCS ZNITIALS

REFERENCES:

1. Precautions, Limitations, and Setpoint for Westinghouse NSSS.

2. Unit 2 Technical Specifications.

3. WCAP-8747, North Anna Nuclear Design Report.

4. Station Curve Book.

5. 20P-5.2.

6. 2-0P-28.1.

1.0 Purpose The purpose of this test is to determine the capability of the charging and letdown system to cooldown the reactor coolant system with the steam generators isolated and at least one reactor coolant pump in operation.

2.0 Initial Condtions 2.1 The reactor is shutdown and borated to ensure adequate shutdown margin. (Mode 3) 2.2 All three reactor coolant pumps are in operation.

2.3 Steam generator level being maintained at approximately 33% with the auxiliary feedwater system.

2.4 Reactor coolant system pressure and level under automatic control at approximately 2235 psig and 21.4%.

2.5 Reactor coolant system temperature beins controlled at approximate-ly 547*F by steam dump to the condenser under automatic pressure control. (Steam generator pressure at 1005 psig).

2-ST-6 Page 2 of 6 INITIALS 2.0 Initial Condtions 2.6 Steam generator chemistry is within normal guidelines such that steam generator blowdown can be isolated when the steam generators are isolated.

2.7 Set up one of the source range channels on NR-45 to monitor any changes in the core flux level.

2.8 Normal charging and letdown in service and under automatic control.

2.9 Connect Brush recorder to the following test points in the auxiliary instrument room.

Bruch Recorder 1 Connect To: Monitoring:

Channel No. 1 TD-144,C6-456 Letdown ETX Outlet Temp.

Channel No. 2 TD-140,C5-256 Letdown Temp.

Channel No. 3 TD-123,C5-156 Charging Tem.

Channel No. 4 FD-122,C6-556 RSS Charging-Flow Channel No. 5 FD-150,C6-456 RCS Letdown-Flow Brush Recorder 2 Connect To: Monitoring:

Channel No. 1 TP-412H,C1-421 Loop 1 Hot Leg Temp.

Channel No. 2 TP-412,C1-422 Loop 1 Cold Leg Temp.

Channel No. 3 TP-422H,C2-421 Loop 2 Hot Leg Temp.

Channel No. 4 TP-422,C2-422 Loop 2 Cold Leg Temp.

Channel No. 5 TP-432H,C3-721 Loop 3 Hot Leg Temp.

Channel No. 6 TP-432,C3-722 Loop 3 Hot Leg Temp.

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2-ST-6 Page 3 of 6 Initials 2.0 Initial Conditions (cont.)

2.10 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) Parameters 2.11 Setup the P-250 computer trend printer to monitor the parameters indicated in Attachment 6.3 2.12 Notify the Shift Supervisor of the impending test and co-ordinate its performance through him.

3.0 Precautions 3.1 Before beginning, and while the test is conducted, verify adequate shutdown margin.

I 3.2 The difference in boron concentration between the RCS and Pressur-izer should not exceed 50 PPM. Use pressurizer spray to equalize j concentration.

3.3 One source range channel shall be in operation and monitored continuously on NR-45 during the conduct of this test.

3.4 Charging flow to the RCS must be at the same boron concentration as that required for shutdown.

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2-ST-6 Page 4 of 6 Initials 2.0 Initial Conditions (cont.)

3.5 The RCS should be sampled for boron concentration once toward the end of the 30-minute period of maximum letdown and charging so that the shutdown margin is verified.

4.0 Instruction 4.1 If the reactor coolant system Tavg is above 545*F, reduce it by manually increasing steam dump to the condenser.

4.2 Start the brush recorders at 25 mm/ min. and trend printer at a one minute interval and record the data listed on Attachment 6.4 4.3 Shutdown reactor coolant pumps 1A and IB in accordance with 2-0P-5.2.

NOTE: It may be necessary to operate two RCP's for necessary heat addition.

4.4 Isolate all three steam generators by closing main steam isolation valves (TV-MS 201A,B,C and IV-:ts 213A,B and C).

4.5 Isolate steam generator blowdown if it is presently in operation by closing TV-BD 200 A,B,C,D,E, and F.

1 4.6 Allow the RCS Tavg to increase to approximately 547*F and then l increase charging flow and letdown to the maximum allowable.

4.7 Continue maximum letdown and charging for a 30-minute period and then reduce letdown and charging to the minimum allowable. Con-tinue recording data.

NOTE: Toward the end of the 30-minute period a boron analysis of the RCS should be done to verify adequate shutdown margin.

l 4.8 After operating with minimum letdown and charging for a 30-minute period, stop the recorders, and trend printer attach the charts to this procedure. -

4.9 Restore steam to the secondary side per applicable portions of 2-0P-28.1.

2-ST-6 Page 5 of 6 4.0 Instruction (cont.)

4.10 Start reactor coolant pumps IA and IB in accordance with 2-OP-5.2.

NOTE: Two RCP's may be operating. See step 4.3.

4.11 On Data Sheet 6.2, using recorded data, calculate the average rate of temperature change for the 30-minute periods of maximum and minimum

] letdown and charging.

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2-ST-6 Page 6 of 6 5.0 Acceptance Criteria 5.1 Core exit T/C temperature did not exceed 610*F.

5.2 Delta-T for any loop did not exceed 66*F.

5.3 Tavg for any loop does not exceed 580.3 *F.

i, 6.0 Attachments 6.1 Test Equipment Data Sheet.

6.2 Letdown and Charging Data Sheet.

6.3 Process Computer Trend Block Data.

6.4 Initial Conditions.

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2-ST-6 Attachment 6.1 Page 1 of 1 TEST EQUIPMENT DATA SHEET TEST EQUIPMENT DESCRIPTION

• MODEL NLMBER VEPC0 QC NLHBER

• NOTE: This applies only to temporarily installed test equipment or instrumentation Permanent instrumentation which is part of the system and shown on drawings should bct be included.

Completed By: 1 Date:

2-ST-6 Attachment 6.2 Page 1 of 1 LETDOWN AND CHARGING DATA SHEET Mrximum Letdown and Charging Charging Flow gpa Letdown Flow _ gpm Av2 rage Temperature Change *F over the 30-minute period.

Rate of Temperature Change = Avg. change _ *F

.5 hr Minimum Letdown and Charging Charging Flow gpa Letdown Flow gpm Avarage Temperature Change *F over the 30-minute period.

Rste of Temperature Change = Avg. change _ *F

.5 hr 4

Completed By:

Date:

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2-ST-6 Attachment 6.3 Page 1 of 2 PROCESS COMPUTER TREND BLOCK A COLL 7fNS ADDRt.Sb 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 HOT 5 T0939A RCL B T F HOT 6 T0959A RCL C T HOT 7 T0400A Tgyg LOOP A *F 8 T0420A T 00P B *F AVG 9 T0440A T LOOP C *F AVG 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  % l 17 LO112A VCT LEVEL  %

18 U1251 HIGHEST FIL ASSY PWR INDENT ,

2-ST-6 Atttchment 6.3 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 POWER MW 13 U1170 AVG T/C TEMP *F 14 AS REQUIRED HOTTEST T/C (QUADRMT 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

2-ST-6 Attachment 6.4 Page 1 of 2 INITIAL CONDITIONS Pressurizer Pressure psig PR-2444 Red Pen Pressurizer Level  %

LR-2459 Red Pen RCS Loop 1 Hot Leg Temperature F TR-2413 Red Pen RCS Loop 1 Cold Let Temperature *F TR-2410 Red Pen RCS Loop 2 Hot Leg Temperature *F TR-2423 Green Pen RCS Loop 2 Cold Leg Temperature *F TR-2420 Green Pen RCS Loop 3 Hot Leg Temperature F TR-2433 Blue Pen RCS Loop 3 Cold Leg Temperature *F TR-243 Blue Pen Steam Generator 1 Level (NR)  %

(LI-2474)

Steam Generator 1 Level (NR)  %

(LI-2484)

Steam Generator 3 Level (NR)  %

(LI-2494)

Steam Generator 1 Level (WR)  %

LR-2477 Pen 1 Red Pen Steam Generator 2 Level (WR)  %

LR-2477 Pen 2 Green Pen i

Steam Generator 3 Level (WR)

LR-2477 Pen 1 Blue Pen Steam Generator 1 Pressure Psig PI-2474 Steam Generator 2 Pressure Psig PI-2484 l

Steam Generator 3 Pressure Psig PI-2494 6

l Steam Generator 1 Feedwater Flow X10 #/hr (FI-2476)

2-ST-6 Attachment 6.4 Page 2 of 2 INITIAL CONDIT0NS 6

Steam Generator 1 Feedwater Flow X10 #/hr (FI-2486) 0 Steam Generator 3 Feedwater Flow X10 #/hr (FI-2496) 0 Steam Generator 1 Steam Flow X10 lbs/hr (FI-2474) 0 Steam Generator 2 Steam Flow X10 lbs/hr (FI-2484) 0 Steam Generator 3 Steam Flow X10 lbs/hr (FI-2494)

Loop 1 Tavg Protection *F (TI-2412D)

Loop 2 Tavg Protection *F (TI-2422D)

Loop 3 Tavg Protection 'F (TI-2432D)

Loop 1 A T Protection  %

(TI-2412A)

Loop 2 AT  %

(TI-2422A)

Loop 3 AT  % i (TI-2432) )

NIS Channel N-41  %

NIS Channel N-42 ' '

NIS Channel N-43  %

i NIS Channel N-44  %

, Attach a copy of the computer printout of the Incore Thermocouple Tempera-ture map.

t Completed By:

Date:

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