ML051730536
| ML051730536 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/10/2005 |
| From: | Marlow T Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML051730536 (29) | |
Text
1503 Lake Road Ontario, New York 14519-9364 585.771.3000 Constellation Energy R.E. Ginna Nuclear Power Plant, LLC June 10, 2005 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very truly yours, Thomas A. Marlow TAM/jdw xc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s):
AP Index AP-TURB.1, Rev 15 AP-TURB.3, Rev 13 c6\o;
(7 ( C NPSP0200 Ginna Nuclear Power Plant Fri 6/10/2005 10:15:55 am I E66429 PROCEDURE INDE) Page 1 of 2 INPUT PARAMETERS: TYPE. PRAP STATUSVALUE(S): EF.QU s YEARS ONLY:
!,?
PRAP ABNORMAL PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TlTLE REV DATE REVIEW REVIEW ST AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLiNG LOOP 017 06/30/2004 06/26/2002 06/26/2007 EF AP-CCW2 LOSS OF CCW DURING POWER OPERATION 020 04128/2005 06/26/2002 06/26/2007 EF AP-CCW.3 LOSS OF CCW- PLANT SHUTDOWN 017 04/28/2005 06/26/2002 06/26/2007 EF AP-CR.1 CONTROL ROOM INACCESSIBILITY 021 04/26/2005 06/2612002 06/26/2007 EF AP-CVCS.1 CVCS LEAK 014 06130/2004 06/03/2002 06/03/2007 EF AP-CVCS.3 LOSS OF ALL CHARGING FLOW 005 04/1012005 02/27/2004 02/27/2009 EF AP-CW.1 LOSS OF A CIRC WATER PUMP 012 09/17l2004 04/16/2003 04/16/2008 EF AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES 028 01/21/2005 06/26/2002 06/26/2007 EF AP-ELEC.2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY O11 06/10/2004 06/26/2002 06/26/2007 EF AP-ELEC.3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW350 F) 013 01121/2005 0812612002 06/26/2007 EF AP-ELEC.13Y15 LOSS OF BUS 13i15 001 08130/2004 09/24/2003 09/24/2008 EF AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14116 009 01/21/2005 06/26/2002 06/26/2007 EF AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 008 01/21/2005 06/26/2002 06/2612007 EF AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW 016 06/30/2004 06/26/2002 06/26/2007 EF AP-IA.1 LOSS OF INSTRUMENT AIR 018 06/26/2002 04116/2003 04/16/2008 EF AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 015 06/30/2004 06/26/2002 06/26/2007 EF AP-RCC.1 CONlINUOUS CONTROL ROD WITHDRAWALJINSERTION 009 06130/2004 04/16/2003 04/16/2008 EF AP-RCC.2 RCC/RPI MALFUNCTION 012 04/10/2005 2/120/51/2 01/22/2007 AP-RCC.3 DROPPED ROD RECOVERY 007 04/28/2005. 02/25/2003 02/25/2008 AP-RCP.1 RCP SEAL MALFUNCTION 017 06130/2004 04/24/2003 04/24/2008 AP-RCS.1 REACTOR COOLANT LEAK 017 06/30/2004 04/16/2003 04/16/2008 AP-RCS.2 LOSS OF REACTOR COOLANT FLOW 012 06/30/2004 "04/16/2003 04/16/2008 AP-RCS.3 HIGH REACTOR COOLANT ACTMITY O11 06130/2004 04/01/2002 01/22/2007 AP-RCS.4 SHUTDOWN LOCA O17 03/18/2005 04/30/2003 04/30/2008 AP-RHR.1 LOSS OF RHR 019 04130/2003 04130/2003 04/30/2008 AP-RHR.2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDmONS 015 04/05/2005 04/3012003 04/3012008 AP-SG.1 STEAM GENERATOR TUBE LEAK 004 04/10/2005 06/26/2002 06/26/2007 AP-SW.1 SERVICE WATER LEAK 021 09/17/2004 04121/2003 04/21/2008 AP-SW.2 LOSS OF SERVICE WATER 007 01/21/2005 1//20/5013 10/31/2006 EF AP-TURB.1 TURBINE TRIP WITHIIJT RX TRIP REQUIRED 015 06/10/2005 06/26/2002 06/26/2007 EF
( C C(
NPSP0200 Ginna Nuclear Power Plant Fri 6/10/2005 10:15:55 am FrA9Q nonnrani I0C lKlnC - D-n 7) nf 73 INPUT PARAMETERS: TYPE, PRAP STATUS VALUE(S): EF. QU 5 YEARS ONLY:
PRAP ABNORMAL PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE llTLE REV DATE REVIEW REVIEW ST AP-TURB.2 TURBINE LOAD REJECTION 021 04110/2005 06/20/2002 06/26/2007 EF AP-TURB.3 TURBINEMBRATION 013 0611012005 06/26/2002 06/26/2007 EF AP-TURB.4 LOSS OF CONDENSER VACUUM 018 04110/2005 04/30/2003 04/3012008 EF AP-TURB.5 RAPID LOAD REDUCTION 008 04110/2005 06/26/2002 06/2612007 EF PRAP TOTAL 34 GRAND TOTAL 34
. GINNA STATION CONTROLLED COPY NUMBER -_______
RESPONSIBLE MANAGER k-/l-z, a s EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
A. PURPOSE - This procedure provides the necessary instructions to control the plant following a turbine trip without a reactor trip required.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS - This procedure is entered from:
- b. AR-I-8, EH RESERVOIR HI-LO LEVEL, if level is decreasing and cannot be stabilized.
- c. AR-I-16, EH RESERVOIR LO LEVEL PUMP LOCKOUT, if level is decreasing and cannot be stabilized.
- d. AR-J-2, GENERATOR STATOR WINDING HI TEMP, if generator conditions warrant turbine trip.
- e. AR-VOLT-REG-3, LOSS OF BOTH FIRING CIRCUITS, if voltage regulator will not control voltage.
- f. AP-CW.1, LOSS OF A CIRC WATER PUMP, or,
- g. AP-FW.1, ABNORMAL FEED FLOW, or,
- h. AP-TURB.2, TURBINE LOAD REJECTION, or,
- i. AP-TURB.3, TURBINE VIBRATION, or,
- j. AP-TURB.4, LOSS OF CONDENSER VACUUM, when power is less than P-9 and the turbine trips without a Rx trip.
- k. AP-TURB.5, RAPID LOAD REDUCTION, when Rx is to be maintained critical.
- 2. SYMPTOMS - The symptoms of TURBINE TRIP WITHOUT RX TRIP REQUIRED are:
- a. Annunciator F-21, COND HI PRESS 20" HG OR LOSS OF BOTH CIRC WTR PMPS, lit, or
- b. Annunciator G-15, STEAM DUMP ARMED, lit, or
- c. Annunciator J-11, GENERATOR REVERSE POWER, lit, or
- d. Annunciator J-26, GENERATOR EXCITER FIELD BREAKER TRIP, lit, or
- e. Annunciator K-1, THRUST BEARING FAILURE, lit, or
- f. Annunciator K-3, AMSAC ACTUATED, lit.
- g. Annunciator K-9, TURBINE BEARING OIL LO PRESS TRIP 6 psi, lit, or
- h. Annunciator K-10, TURBINE HIGH HIGH VIBRATION, lit, or
- i. Annunciator K-17, TURBINE LOW VACUUM TRIP 20" HG, lit, or
- j. Annunciator K-25, TURBINE OVERSPEED ALERT 1980 RPM, lit, or
- k. Annunciator K-26, GENERATOR LOCKOUT RELAY, lit, or
- 1. Annunciator -L-12, CONDENSER PIT OR SCREENHOUSE HI LEVEL 6.5",. lit, or
- m. Annunciator VOLT-REG-12, LOSS OF BOTH PWR SUPPLY, lit.
ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED l 1 Verify Turbine Stop Valves - Manually trip turbine.
CLOSED IF turbine stop valves can NOT be closed, THEN perform the following:
- a. Trip the reactor
- b. WHEN all E-O Immediate Actions done. THEN ensure both MSIVs closed
- c. Go to E-O. REACTOR TRIP OR SAFETY INJECTION NOTE: o Automatic rod control is desired, if available.
o Transition to E-O is NOT required if the reactor trip breakers are opened in the following step.
2 Check Reactor Power:
- a. NIS power ranges - ABOVE 1% a. Perform the following:
- 1) IF the reactor is subcritical. THEN shut down the reactor using manual trip pushbutton.
- 2) Go to Step 3.
- b. Verify control rods driving in b. Perform the following:
to reduce reactor power in AUTO
- 1) Place rods in MANUAL
- 2) Adjust rods to control reactor power between 1% and 2%.
- c. Borate to maintain control rods above rod insertion limits
ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED I
- 3 Monitor MFW Regulating Valves Perform the following:
- RESTORING S/G LEVEL TO 52%
IN AUTO a. Place affected S/G(s) MFW regulating valve in MANUAL
- b. Restore S/G level to 52%
IF S/G level can NOT be controlled manually, THEN refer to AP-FW.l.
ABNORMAL MAIN FEEDWATER FLOW.
4 Verify Proper Operation Of.
Steam Dump:
- a. Verify annunciator G-15, STEAM a. Place steam dump mode selector DUMP ARMED - LIT switch to MANUAL.
- b. Condenser steam dump operating b. IF steam dump NOT available.
in AUTO THEN perform the following:
- 1) Adjust SIG ARV setpoints to 1005 psig and verify ARV operating to control Tavg to approximately 5470F.
- 2) IF power is greater than 8%.
THEN ensure reactor trip and go to E-O. REACTOR TRIP OR SAFETY INJECTION.
- c. Check RCS Tavg: c. Verify control rods responding in AUTO. IF NOT. ,THEN place
- Tavg - GREATER THAN 545 0 F rods to MANUAL and adjust
- Tavg - LESS THAN 5660 f control rods to restore Tavg within limits.
IF Tavg is outside limits and can NOT be controlled. THEN trip the reactor and go to E-O.
REACTOR TRIP OR SAFETY INJECTION.
EOP: TITLE: REV: 15 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 6 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: With PRZR pressure controller 431K in manual. PORV-431C will not.
operate in the automatic mode. (Refer to TR 3.4.3) 5 Check PRZR Pressure - Control PRZR pressure by one of the TRENDING TO 2235 PSIG IN AUTO following:
- 431K in MANUAL
- Manual control of heatero and sprays IF PRZR pressure can NOT be controlled manually, THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.
TIE EOP~
.EDP: TLE:
TI -
REV: 15 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PE 7o 1 6
. PAGE 7 of 16 STE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check PRZR Level:
- a. Level - GREATER THAN 13% a. Perform the following:
- 1) Place letdown isolation valve AOV-427 switch to CLOSE.
- 2) Place letdown orifice valve switches to CLOSE (AOV-200A.
AOV-200B. and AOV-202).
- 3) Close excess letdown isolation valve, AOV-310.
- 4) Ensure PRZR heaters off.
- 5) Close letdown isolation AOV-371 WHILE adjusting charging pump speed to maintain:
o RCP labyrinth seal D/P between 15 inches and 80 inches o PRZR level at program
- 6) WHEN PRZR level greater than 13%. THEN restore letdown.
(Refer to ATT-9.0, ATTACHMENT LETDOWN)
- b. Level - TRENDING TO PROGRAM IN b. Perform the following:
AUTO CONTROL
- 1) Place affected charging pumps in MANUAL
- 2) Adjust charging pump speed to restore PRZR level to program.
IF PRZR level can NOT be controlled manually, THEN refer to AP-RCS.1, REACTOR COOLANT LEAK.
ACTION/EXPECTED RESPONSE lRESPONSE STEP NOT OBTAINED 7 Check MFW System:
- a. MFW pumps - BOTH RUNNING a. Perform the following:
- 1) Verify one MFW pump running.
IF NOT. THEN establish sufficient AFW flow to maintain S/G levels
- MDAFW pump(s)
- TDAFW pump
- 2) Go to Step 8.
- b. Close one MFW pump discharge valve
- c. Stop selected MFW pump
P ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED w * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *r
- CAUTION IF AT ANY TIME IT IS SUSPECTED THAT THE REACTOR IS SUBCRITICAL. THEN MANUALLY TRIP THE REACTOR.
NOTE: o With PRZR pressure controller 431K in manual, PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3) o Transition to E-0 is NOT required if the reactor trip breakers are opened in the following step.
8 Establish Stable Plant Conditions:
- a. NIS power ranges - LESS THAN 2% a. Return to Step 2.
- b. Place rods in MANUAL
- c. Check reactor power - GREATER c. IF the reactor is subcritical.
THAN 1% THEN perform the following:
- 1) Shut down the reactor using manual trip pushbutton.
- 2) Go to Step 8e.
- d. Maintain reactor power between 1% and 2%
- e. PRZR pressure - BETWEEN e. Control PRZR pressure between 2220 PSIG AND 2260 PSIG 2220 prig and 2260 psig by one of the following:
- 431K in AUTO
- 431K in MANUAL
- Manual control of heaters and spray
- f. RCS Tavg - GREATER THAN 545 0 F f. Control dumping steam to control Tavg. IF cooldown continues, THEN close both MSIVs.
IF MSIVs closed AND Tavg still decreasing, THEN trip the reactor and go to E-O. REACTOR TRIP OR SAFETY INJECTION.
S P ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED CAUTION IF ANY S/G LEVEL ABOVE 52%. THEN AEW FLOW MAY BE THROTTLED IMMEDIATELY TO PREVENT S/G ISOLATION.
NOTE: Maintaining reactor power less than 2% is within the capacity of MDAFW pumps.
9 Check S/G Feed Flow Status:
- a. Manually start both MDAFW pumps
- b. Verify MDAEW pump flow - b. Perform the following:
SUFFICIENT FLOW TO MAINTAIN S/G LEVELS 1) Establish MFW flow using MFW regulating valve bypass valves.
IF MEW NOT available, THEN perform the following:
a) Manually start TDAFW pump and establish flow.
b) Adjust feed flow to restore S/G level to 52%.
c) Go to Step 9c.
- 2) Adjust feed flow to restore S/G level to 52%.
- 3) Go to Step 11.
- c. Verify MEW flow control valves -. c. Place A and B MEW regulating and CLOSED bypass valve controllers in manual at 0% demand.
- MEW regulating valves
- MEW bypass valves This Step continued on the next page.
EOP: TITE:- REV: 15 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED
. . PAGE 11 of 16 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED (Step 9 continued from previous page)
- d. Close MEW pump discharge valves
- MOV-3977, A MEW pump
. MOV-3976, B MEW pump
- e. Stop any running MEW pump
- f. Close MEW pump recirc valves by placing BOTH MEPs in PULL STOP.
- g. Place A and B MEW regulating and bypass valve controllers in' manual at 0% demand.
- h. Adjust AFW pump flow to restore S/G level to 52%.
I I EOP: TITLE:
REV: 15
-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 12 of 16 I,
STE ..
ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINED 10 Verify TDAFW Pump Aligned For AUTO Start:
- a. Any MDAFW pump - AVAILABLE a. Verify TDAFW pump operating to maintain required S/G level and go to Step 12.
light - EXTINGUISHED
- c. Verify both S/G levels - GREATER c. Continue with Step 12. WHEN S/G THAN 17% level greater than 17%, THEN do Steps lOd. e and 11.
- d. Verify Bus 11A and Bus 11B - AT d. Perform the following:
LEAST ONE ENERGIZED
\K>
- MOV-3504A
- MOV-3505A
- 2) Go to Step 11.
- e. Verify the following:
- 1) TDAFW pump - OFF 1) Perform the following:
a) IF TDAFW pump required to maintain S/G level. THEN go to Step 12.
b) Stop TDAFW pump.
- 2) TDAFW pump steam supply valve 2) Place TDAFW pump steam supply switches in AUTO valve switches in AUTO.
- AOV-4297
- AOV-4298
EOP: TITLE:
I REV: 15 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED I .PAGE 13 of 16 STP ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINEDI 11 Establish Normal AFW Pump Shutdown Alignment:
- a. Place AEW bypass switches to DEE
- b. Verify the following: b. Continue with Step 12. WHEN conditions met, THEN do Steps o Both S/G levels - STABLE OR lic through d.
INCREASING o Total AEW flow - LESS THAN 200 GPM
- c. Close MDAEW pump discharge valves
. MOV-4007
- MOV-4008
- d. Adjust AFW bypass valves to control S/G levels at 52%
- AOV-4480
- AOV-4481
ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 12 Establish Normal Shutdown Alignment:
- a. Check condenser - AVAILABLE a. Dispatch AO to perform ATT-17.1.
ATTACHMENT SD-2.
- b. Perform the following:
o Open generator disconnects
- 1G13A71
- 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cam to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump (Refer to T-5F.
STARTING OR STOPPING THE CONDENSATE PUMPS)
- c. Verify Bus 11A and Bus 11B c. IF either bus NOT energized.
energized - BOTH BUSSES GREATER THEN refer to 0-6.9.2.
THAN 4 KV ESTABLISHING AND/OR TRANSFERRING OFFSITE POWER TO BUS 12A/
BUS 12B.
- d. Dispatch AO to perform ATT-17.0, ATTACHMENT SD-1
STP ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINED 13 Etabish Sstes ontol I
13 Establish Control Systems In Auto:
- a. Verify 431K in AUTO a. Place 431K in AUT(). if desired.
- b. Verify PRZR spray valves in AUTO b. Place PRZR spray valves in AUTO, if desired.
- c. Verify one charging pump in AUTO c. Place one charginjg pump in AUTO.
if desired.
- d. Verify PRZR heaters restored: d. Restore PRZR heat4arc, if desired.
o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -
RESET, IN AUTO 14 Evaluate MCB Annunciator Status (Refer to AR Procedures) 15 Notify RP To Obtain Primary Samples Required By ITS LCO 3.4.16 (Load Reduction > 15%
In One Hour)
NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.
16 Notify Higher Supervision
IEOP: TITLE:
REV: 15
[P-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED
. . PAGE 16 of 16 STP ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINEDl 17 Establish Desired Plant Conditions:
- a. Reactor shutdown - DESIRED a. IF turbine is to be restored to cservice. THEN maintain reactor critical and refer to 0-1.2.
PLANT STARTUP FROM HOT SHUTDOWN TO FULL LOAD.
- b. Refer to 0-2.1. NORMAL SHUTDOWN TO HOT SHUTDOWN
-END-
AP-TURB.1 APPENDIX LIST TITLE
- 1) ATTACHMENT SD-1 (ATT-17.0)
- 2) ATTACHMENT SD-2 (ATT-17.1)
- 3) ATTACHMENT LETDOWN (ATT-9.0)
EOP TITLE:
REV: 13 KP-TURB.3 TURBINE VIBRATION PAE 1 I9 PAG f l GINNA STATION CONTROLLED COPY NUMBER ____
CQCC6.Laj RESPONSIBLE MANAGER 6_ M c S EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
A
.EOP: lTITLE:RE: 1 TLP-TURB.E3 TURBINE VIBRATION PAGE 2 of 9 A. PURPOSE - This procedure provides the necessary actions to be taken in the event of increasing turbine vibrations.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS - This procedure is entered from:
- a. N/A
- 2. SYMPTOMS - The symptoms of TURBINE VIBRATION are;
- a. Increasing or High Turbine Vibration detected, or
- b. Annunciator I-27, Rotor Eccentricity or Vibration alarm is lit, or
- c. Annunciator K-10, Turbine High High Vibration alarm lit.
EOP: TITLE:
REV: 13 AP-TURB.3 TURBINE VIBRATION
. . PAGE 3 of 9.
ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED STE
- 1 Verify Turbine Vibration - Perform the following:
ALL BEARINGS LESS THAN 14 MILS IF power greater than P-9, THEN trip the reactor and go to E-O.
REACTOR TRIP OR SAFETY INJECTION.
IF power less than P-9, THEN trip the turbine and go to AP-TURB.1.
TURBINE TRIP WITHOUT RX TRIP REQUIRED.
A.
EOP: TITLE: REV: 13 AP-TURB.3 TURBINE VIBRATION PAGE 4 of 9 STEP ACTION/EXPECTED RESPONSE 1RESPONSE NOT OBTAINED NOTE: IF power reduction is required the thumb rule for initial boron addition is -2 gal/% load reduction.
2 Check Turbine Vibration:
- a. Bearings No. 1 through No. 8 - a. Attempt to stabilize vibration LESS THAN 7 MILS as follows:
o IF increasing turbine speed, THEN stop speed increase and evaluate. Evaluate reducing speed to a non-resonance region. (Refer to 0-1.2) o IF generator on line. THEN begin reducing load to stabilize vibrations. (Refer to AP-TURB.5. RAPID LOAD REDUCTION)
- b. Bearing No. 9 - LESS THAN b. Attempt to stabilize vibrations 8.5 MILS as follows:
o Adjust generator hydrogen temperature.
-OR-o Adjust turbine lube oil temperature,
-OR-o Adjust exciter cooling,
-OR-o Adjust generator seal oil cooling.
A.
EDP: TITLE:
- 1 REV: 13 AP-TURB.3 TURBINE VIBRATION
. . PAGE 5 of 9.
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Evaluate Plant Conditions:
- a. Check turbine vibrations - a. Reduce turbine load until STABLE OR DECREASING turbine vibrations stabilize.
IF vibrations can NOT be stabilized with the plant at power. THEN take unit off line (refer to AP-TURB.5, RAPID LOAD REDUCTION)
- b. Stop load reduction
EOP: TITLE:
REV: 13 AP-TURB.3 TURBINE VIBRATION PAGE 6 of 9 ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINED I 4 Establish Stable Plant Conditions
- a. Tavg - TRENDING TO TREE a. IF Tavg greater than Tref. THEN restore Tavg to Tref by one or more of the following:
- Insert control rods
- RCS boration IF Tavg less than Tref, THEN restore Tavg to Tref by one or more of the following:
. Withdraw control rods
- Reduce turbine load
- Dilution of RCS
- b. PRZR pressure - TRENDING TO b. Control PRZR pressure by one of 2235 PSIG IN AUTO the following:
. 431K in MANUAL
. Manual control of PRZR heaters and sprays IF pressure can NOT be controlled manually, THEN refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.
- c. PRZR level - TRENDING TO PROGRAM c. Perform the following:
IN AUTO CONTROL
- 1) Place affected charging pumps in MANUAL
- 2) Adjust charging pump speed to restore PRZR level to program IF PRZR level can NOT be controlled manually, THEN refer to AP-RCS.1, REACTOR COOLANT LEAK.
- d. MEW Regulating valves - d. Perform the following:
RESTORING S/G LEVEL TO 52% IN AUTO 1) Place affected S/G(s) MEW regulating valve in MANUAL.
- 2) Restore S/G level to 52%.
IF S/G level can NOT be controlled manually, THEN refer to AP-FW.1. ABNORMAL MAIN FEEDWATER FLOW.
ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED 5 Evaluate Turbine Operation:
- a. Verify no unusual noises exist a. IF unusual noises detected, THEN locally at turbine generator notify the Maintenance Manager.
- b. Monitor turbine supervisory instrumentation to ensure conditions stable o Turbine Vibration Recorder (Front of MCB) o Turbine Vibration Monitor (Back of MCB)
K>1-
VF EOP: TITLE:
REV: 13 AP-TURB.3 TURBINE VIBRATION P
. . lPAGE 8 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Establish Control Systems In Auto:
- a. Restore EH controls
- 1) Place in OP PAN. IMP OUT
- 2) Place load rate thumbwheel to 10%/hr
- 3) Match setter and reference
- b. Verify annunciator G-15. STEAM b. WHEN Tavg within 5 0E of Tref, DUMP ARMED - EXTINGUISHED THEN perform the following:
- 1) Ensure steam dump valves cloned.
- 2) Reset steam dump.
- c. Verify one charging pump in AUTO c. Place one charging pump to AUTO.
if desired.
- d. Verify rods in AUTO d. Place rods in AUTO. if desired.
- e. Verify 431K in AUTO e. Place 431K in AUTO, if desired.
- f. Verify spray valves in AUTO f. Place spray valves in AUTO, if desired.
- g. Verify PRZR heaters restored: g. Restore PRZR heaters, if desired.
o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -
RESET, IN AUTO
- h. Verify MEW regulating valves in h. Place MEW regulating valves in AUTO AUTO, if desired.
ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 7 Evaluate MCB Annunciator Status (Refer to AR Procedures) 8 Notify Higher Supervision
-END-