ML20090B561

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Rev 3 to Procedure 1-AP-24.1, Large Steam Generator Tube Leak Requiring Immediate & Rapid Unit Shutdown
ML20090B561
Person / Time
Site: Ginna Constellation icon.png
Issue date: 10/08/1987
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20090B375 List:
References
FOIA-91-106 1-AP-24.1, NUDOCS 9203030463
Download: ML20090B561 (8)
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Text

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REQUEST TO CHANGE PROCEDURE ADM-5.4

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NORTH ANNA POWER STATION VIRGTNIA POWER Page 1 of 1

<l 07-09-67 k,UPERVISOR RESPONSIBLE FOR FOLLOWING PROCEDURE:

1 l O ABNORMAL O CURVE BOOK

, O OFFRATING O WELDING O ADMINISTRATIVE O EMERGENCY O PERIODIC TEST O

O ANNUNCIATOR O IN-SERVICE INSPECTION O EIALTH PETSICS O

O CALIBRATION O MAINTENANCE O SPECIAL TEST O

O CHEMISTRY

. O NON-DESTRUCTIVE TEST Q START <UP TEST O

2 UNIT NO:

3 REC SION DATE:

f 3f_g 5 PROCEDURE NO:

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j TITLE: w ecg y m S y m x m g,qr_, w s,j c. qmmcom.7g m(y yp,, upg r ;,maA CHANGES REQUISTED:

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O TIS No DOES THIS CHANGE I'IVOLVE A POSSIBLE UNREVIEWED SAFETT CUESTION/

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IF ANT "TES". A " SAFETY ANALYSIS" IS REQUIRED.

(10CFR50.59) APPROVED COPY TO BE PROVIDED TO LICDSING COORD. FOR INCLUSION IN ANNUAL REPORT RECOMMENDED ACTION:

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E APPROVED O DISAPPROVED O APPROVED AS MODITIED BT COMMIITEI s.JMAN SIGNATURE:

18 DATE:

H NEW PROCEDURE REVISION DATE:

ACTIOh COMPLETED BY:

21 DATE:

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1-AP-24.0 Page.1 of I 00-00-00.

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~ VIRGINIA POWER WORTE A30tA POWER STATIM UNIT 1 LARGE STEAM CEIOtRATOR TURE LEAK 1.0 Purpose This procedure-will provide the indications of, probable causes for

- and.immediate and long term operator actions to be taken for steam generator tube leaks.

24.1 Large steam generator tube leak, requiring immediate and rapid unit shutdown.

24.2 Small generator tube leak.

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1-AP-24.1 Page 1 of 6 00-00-00 TIRGINIA POWER

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NOETH AIGIA POWER STATIN UNIT 1 LARGE STEAK CENEltATOR TURE LEAK REQUIRING DeGDIATE AND RAPID UNIT SHUTDOWN (With No Attachments)

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REFERENCES:

1.

UFSAR Chapter 2.

11715-FM-70A, 70B 3.:

EWR-87-560 REV. NO.

5 PAGE DATE 00-00-00 APPROVAL RECOMMEND APPROVAL:

APPROVED BY:

CHAIRMAN STATION NUCLEAR SAFETY AND OPERATING COMMITTEE DATE: 00-00-00

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1-AP-24.1 Page 2 of 6 00-00-00 1.0 Purpose 1.1 This procedure provides the indications of, probable causes for, and the immediate and long term operator actions to be taken in the event of a large steam generator tube leak requiring a immediate and rapid unit shutdown.

2.0 Indications 2.1 Increased Charging flow 2.2 VCT low level 2.3 Radiation Monitors 2.3.1 Condenser Air Ejector 2.3.2 Steam Generator Blovdown 2.3.3 Main Steamline 2.3.4 Main Steam Header N-16 3.0 Probable-Cautes 3.1 Large steam generator tube leak 4.0 Immediate Operator Action 1

i 4.1 j(( required, start a second Char 21ng pump.

4.2 Notify the SR0 of the affected unit.

1-AP-24.1 Page 3 of 6 00-00-00 Initiala e

5.0 Long Term Operator Actions NOTE:

IF,at ANY time during this procedure a Reactor Trip occurs, THEN immediately go to 1-EP-0 REACTOR TRIP OR SAFETY INJECTION.

5.1 Commence a unit ramp down as per 1-OP-2.2 at a rate determined by the SRO and in accordance with Standing Order #155 while continuing with this procedure.

5.2 Attempt to identify the affected SG while continuing with this procedure.

  • SGBD Radiation Monitors
  • Main Steamline Radiation Monitors
  • Steam Flow - Feed Flow mismatch
  • Main Feed Reg Valve position 5.3 Notify Chemistry AND Health Physics to sample SGs for activity.

THEN isolate ALL SGBD sample purge lines.

5.4 Dispatch an operator to the Auxiliary Building to isolate SGBD from Af.L SGs at the Blovdown Tanks.

A SG Close 1-BD-9.

B SG Close 1-BD-18.

C SG Close 1-BD-27.

5.5 Energize PRZR heater as required to maintain PRZR pressure.

5.6 Maintain PRZR level:

  • Start standby Charging pump.
  • Increase Charging flow.
  • Isolate letdown.

1-AP-2 4.1 Page 4 of 6 s

00-00-00 l

5.7 Place Auxiliary Steam on unaffected unit or Auxiliary Boilers.

5.8 Notify the unaffected Unit to initiate 1-AP-47, UNIT OPERATION DURING OPPOSITE UNIT EMERGENCY.

5.9 Dispatch an operator to place ALL Turbine Building sumps pumps in OFF.

NOTE: IF the affected SG is NOT. identified THEN continue with this h ocedure AND perform Step 5.10 when it H identified.

5.10 Verify affected SG identified, THEN:

5.10.1 Dispatch an operator to the MSVH to isolate steam from the affected 50 to the Turbine Drive AFW pump:

A SG 1-MS-18 B SG 1-MS-57 C SG 1-MS-95 5.10.2 Increase the setpoint for the affected SG PORV to 1025 psig (potentiometer setting at 5.3).

5.11-Determine Cold Shutdown boration requirements (Minimum Boron -

Shutdown Concentration Curvei while continuing with this procedure.

5.12 Verify 1-0P-2.2 completed. THEN:

5.12.1 Select the highest IR channel on NR-45.

5.12.2 Open both reactor trip breakers and verify all rods fully inserted.

5.12.3 Emergency borate to Cold Shutdown Concentration.

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1-AP-24.1 Page 5 of 6 g

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  • CAUTION:

Remember to block Tave SI inputs at 543'F.

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  • 5.13_ Rapidly cooldown the RCS to less than 500'F by dumping steam.

5.14 Verify RCS temperature is lees than 500'F, THEN:

5.14.1 Close the affected SCs MSIV and Bypass valve.

CAUTION:-

Remember to block Lo PRZR pressure SI inputs at apx 1990 psig.

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CAUTION:

Maincain 50'F.subcooling at all times.

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CAUTION:

Adjust _ seal: injection as required.

5.15 Rapidly depressurize the RCS to a pressure equal to the affected SG pressure.

~II 5.16 Verify Source Range unblocked at 5 x 10 amps THEN:

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5.16.1 Select highest reading source and IR channels on.NR-45.

5.17 Maintain stable plant conditions:

5.17.' 1 : At least 50*F subcooling i

5.17.2' RCS pressure equal to affect-SG pressure.

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1-AP-24.1 Page 6 of 6 00-00-00 1

1 5.18 Go to the appropriate POST-SGTR C00LDOW procedure:

1-ES-3.1 POST-SGTR C00LDOW USING BACKFILL.

1-ES-3.2 POST-SGTR C00LDOW USING BLOWDOW.

1-ES-3.3 POST-SCTR C00LDOW USING STEAM DUMP.

Completed By:

Date:

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