Similar Documents at Ginna |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17250B3061999-10-20020 October 1999
Proposed Tech Specs,Consisting of 1999 Changes to TS Bases
ML17265A6941999-06-28028 June 1999
Proposed Tech Specs,Revising ITS Associated with RCS Leakage Detection Instrumentation,As Result of Commitment Submitted as Part of Staff Review of Application of leak-before-break Status to Protions of RHR Piping
ML17265A6401999-05-12012 May 1999
Rev 11 to Technical Requirements Manual for Ginna Station.
ML17265A6261999-04-18018 April 1999
Rev 10 to Technical Requirements Manual (Trm), for Ginna Station
ML17311A0701999-04-14014 April 1999
Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure.
ML17309A6521999-04-14014 April 1999
Rev 14 to AP-RCS.1, Reactor Coolant Leak.
ML17309A6531999-04-13013 April 1999
Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr
ML17265A6111999-03-26026 March 1999
Rev 9 to Technical Requirements Manual for Ginna Station.
ML17265A5911999-03-0101 March 1999
Proposed Tech Specs Change Revising Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6)
ML17265A5571999-02-25025 February 1999
Rev 4 to Technical Requirements Manual (Trm).
ML17265A5491999-02-12012 February 1999
to EOP FR-H.5, Response to SG Low Level.
ML17265A5481999-02-12012 February 1999
to EOP ATT-22.0, Attachment Restoring Feed Flow.
ML17265A5461999-02-12012 February 1999
0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required.
ML17309A6481999-01-25025 January 1999
Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr
ML17265A5151999-01-14014 January 1999
Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index
ML17265A5081999-01-0808 January 1999
Rev 7 to Technical Requirements Manual, for Ginna Station
ML17265A4961998-12-18018 December 1998
Rev 6 to Technical Requirements Manual.
ML20198C0361998-12-14014 December 1998
Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required
ML20198C0121998-12-14014 December 1998
Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow
ML20198C0581998-12-14014 December 1998
Rev 5 to FR-Z.1, Response to High Containment Pressure
ML20198C0411998-12-14014 December 1998
Rev 16 to FR-C.1, Response to Inadequate Core Cooling
ML20198C0521998-12-14014 December 1998
Rev 13 to FR-S.1, Response to Reactor Restart/Atws
ML17265A4661998-11-24024 November 1998
Proposed Tech Specs 4.2.1,revising Description of Fuel Cladding Matl & Updating List of References Provided in TS 5.6.5 for COLR
ML20155G0301998-10-30030 October 1998
Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop
ML17265A4091998-08-24024 August 1998
Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr
ML17265A3721998-07-16016 July 1998
Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr
ML17265A3151998-06-0404 June 1998
Proposed Tech Specs Basis Re Main Steam Isolation Setpoint
ML17265A2941998-05-21021 May 1998
Tech Specs Consisting of Submittal Changes for 1998
ML17265A2861998-05-0606 May 1998
Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr
ML17265A2461998-04-27027 April 1998
Proposed Tech Specs Revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool
ML17265A1821998-02-20020 February 1998
Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria.
ML17265A1491997-12-31031 December 1997
Rev 1 to Inservice Testing Program.
ML17264B0731997-10-14014 October 1997
Rev 4 to Technical Requirements Manual (TRM) for Ginna Station.
ML17264B0671997-10-0808 October 1997
Proposed Tech Specs,Correcting & Clarifying Info Re RCS Pressure & Temp Limits Rept Administrative Controls Requirements
ML17264B0441997-09-29029 September 1997
Proposed Tech Specs Revising Adminstrative Controls W/ Respect to Reactor Coolant Sys Pressure & Temp Limits Rept
ML17264B0391997-09-29029 September 1997
Proposed Tech Specs Revising Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Rev Revised Setpoint Analysis Study
ML17265A1541997-09-16016 September 1997
Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification.
ML17264B0031997-08-19019 August 1997
Proposed Tech Specs Allowing Testing of Three ECCS motor- Operated Valves in Mode 4 Which Currently Requires Entry Into LCO 3.0.3
ML17264A9991997-08-19019 August 1997
Proposed Tech Specs Correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values
ML17264A9791997-08-0505 August 1997
Rev 7 to AP-RCS.3, High Reactor Coolant Activity.
ML17264A9781997-08-0505 August 1997
Rev 12 to AP-RCS.1, Reactor Coolant Leak.
ML17264A9771997-08-0505 August 1997
Rev 11 to AP-RCP.1, RCP Seal Malfunction.
ML17264A9751997-08-0505 August 1997
Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses.
ML17264A9851997-08-0404 August 1997
Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants.
ML17264A9391997-07-0707 July 1997
Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev
ML17264A9341997-07-0101 July 1997
to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624
ML17264A9461997-06-20020 June 1997
to Inservice Insp (ISI) Program.
ML17264A9241997-06-0303 June 1997
Proposed Tech Specs Clarifying Issues Re Low Temperature Overpressure Protection
ML17311A0471997-05-22022 May 1997
Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr
ML17264A8671997-04-24024 April 1997
Proposed Tech Specs,Revising Rcs,Pt & Administrative Control Requirements
1999-06-28
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17265A6401999-05-12012 May 1999
Rev 11 to Technical Requirements Manual for Ginna Station.
ML17265A6261999-04-18018 April 1999
Rev 10 to Technical Requirements Manual (Trm), for Ginna Station
ML17309A6521999-04-14014 April 1999
Rev 14 to AP-RCS.1, Reactor Coolant Leak.
ML17311A0701999-04-14014 April 1999
Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure.
ML17309A6531999-04-13013 April 1999
Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr
ML17265A6111999-03-26026 March 1999
Rev 9 to Technical Requirements Manual for Ginna Station.
ML17265A5571999-02-25025 February 1999
Rev 4 to Technical Requirements Manual (Trm).
ML17265A5481999-02-12012 February 1999
to EOP ATT-22.0, Attachment Restoring Feed Flow.
ML17265A5491999-02-12012 February 1999
to EOP FR-H.5, Response to SG Low Level.
ML17265A5461999-02-12012 February 1999
0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required.
ML17309A6481999-01-25025 January 1999
Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr
ML17265A5151999-01-14014 January 1999
Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index
ML17265A5081999-01-0808 January 1999
Rev 7 to Technical Requirements Manual, for Ginna Station
ML17265A4961998-12-18018 December 1998
Rev 6 to Technical Requirements Manual.
ML20198C0581998-12-14014 December 1998
Rev 5 to FR-Z.1, Response to High Containment Pressure
ML20198C0361998-12-14014 December 1998
Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required
ML20198C0521998-12-14014 December 1998
Rev 13 to FR-S.1, Response to Reactor Restart/Atws
ML20198C0411998-12-14014 December 1998
Rev 16 to FR-C.1, Response to Inadequate Core Cooling
ML20198C0121998-12-14014 December 1998
Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow
ML20155G0301998-10-30030 October 1998
Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop
ML17265A4091998-08-24024 August 1998
Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr
ML17265A3721998-07-16016 July 1998
Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr
ML17265A2861998-05-0606 May 1998
Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr
ML17265A1821998-02-20020 February 1998
Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria.
ML17265A1491997-12-31031 December 1997
Rev 1 to Inservice Testing Program.
ML17264B0731997-10-14014 October 1997
Rev 4 to Technical Requirements Manual (TRM) for Ginna Station.
ML17265A1541997-09-16016 September 1997
Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification.
ML17264A9751997-08-0505 August 1997
Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses.
ML17264A9771997-08-0505 August 1997
Rev 11 to AP-RCP.1, RCP Seal Malfunction.
ML17264A9791997-08-0505 August 1997
Rev 7 to AP-RCS.3, High Reactor Coolant Activity.
ML17264A9781997-08-0505 August 1997
Rev 12 to AP-RCS.1, Reactor Coolant Leak.
ML17264A9851997-08-0404 August 1997
Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants.
ML17264A9391997-07-0707 July 1997
Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev
ML17264A9341997-07-0101 July 1997
to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624
ML17264A9461997-06-20020 June 1997
to Inservice Insp (ISI) Program.
ML17311A0471997-05-22022 May 1997
Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr
ML20140B8291997-03-24024 March 1997
Rev 3 to EOP ATT-12.0, Attachment N2 Porvs
ML17264A8221997-02-0606 February 1997
Rev 15 to FR-P.1, Response to Imminent Pressurized Thermal Shock Condition.
ML17264A8201997-02-0606 February 1997
Rev 7 to AP-RCC.2, Rcc/Rpi Malfunction.
ML17264A8081997-01-23023 January 1997
Revised Emergency Operating Procedures,Including Rev 14 to E-1,Rev 19 to E-3,Rev 14 to ECA-2.1,Rev ECA-3.3,Rev 20 to ES-1.3,Rev 13 to FR-C.1,Rev 12 to FR-C.2 & Rev 14 to FR-P.1
ML20133N3351997-01-10010 January 1997
Rev 7 to FR-C.3, Response to Saturated Core Cooling
ML17264A8881996-10-10010 October 1996
Rev 9 to ODCM for Ginna Station.
ML20128N0681996-10-0303 October 1996
Revised Emergency Operating Procedures,Including Rev 5 to Att-10.0, Attachment Faulted S/G & Rev 6 to Att-16.0, Attachment Ruptured S/G
ML17264A5311996-05-31031 May 1996
Revised Emergency Operating Procedures,Including Rev 10 to AP-RCP.1,Rev 12 to ECA-0.1,Rev 12 to ECA-2.1,Rev 3 to FR-H.2,Rev 3 to FR-H.4,Rev 7 to FR-I.1,Rev 12 to FR-P.1,Rev 10 to FR-S-1 & Rev 6 to FR-S.2
ML17264A5161996-05-22022 May 1996
Rev 2 to Technical Requirements Manual (TRM)
ML17264A4581996-04-0808 April 1996
Rev 7 to ODCM for Ginna Station.
ML17264A4371996-04-0101 April 1996
Rev 1 to Technical Requirements Manual (TRM)
ML17264A4391996-04-0101 April 1996
Rev 1 to Updated Technical Requirements Manual (TRM)
ML17264A4191996-02-24024 February 1996
Rev 0 to Technical Requirements Manual (Trm).
ML17264A6901996-02-23023 February 1996
Rev 0 to Inservice Testing Program.
1999-05-12
[Table view] |
Text
EOP: TITLE:
REV: 7 P-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 1 of 12 ROCHESTER GAS AND ELECTRIC ORPORATION GINNA STAT ON CONTROLLED COPY BER TECHNICAL REVIEW PORC VIEW DATE P T SUPERINTENDENT EFF TIVE DATE CAT G RY 1.0 REVIEWED BY:
9306040i5i 930524 PDR ADQCK 05000244 P PDR L
\~
EOP: TITLE:
REV 7 P-TURB.'1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 2 of 12 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:
- a. AP-CW.1, LOSS OF A CIRC WATER PUMP, or,
- b. AP-ELEC.l, LOSS OF 12A AND/OR 12B TRANSFORMER, or, c ~ I I AP FW 1 g PART AL OR COMPLETE LOSS OF MA N FEE DWATER g or,
- d. AP-TURB.2, AUTOMATIC TURBINE RUNBACK, or,
- e. AP-TURB.3, TURBINE VIBRATIONS, or,
- f. AP-TURB.4, LOSS OF CONDENSER VACUUM, when power is less than P-9 and the turbine trips without a Rx trip.
- 2. SYMPTOMS The symptoms of TURBINE TRIP WITHOUT RX TRIP REQUIRED are:
a ~ Annunciator K-l, THRUST BEARING FAILURE, lit, or
- b. Annunciator K-9, TURBINE BEARING OIL LO PRESS TRIP 6 psi, lit, or c Annunciator K-17, TURBINE LOW VACUUM TRIP 20" HG,
~
lit, or
- d. Annunciator K-18, MAIN FEEDWATER PUMPS TRIPPED, lit, or
- e. Annunciator K-26, GENERATOR LOCKOUT RELAY, lit, or Annunciator K-25, TURBINE OVERSPEED ALERT 1980 RPM, lit, or gi Annunciator F-21, 20" CIRC WTR PMPS, lit, or HI PRESS COND HG OR LOSS OF BOTH
- h. Annunciator K-3, AMSAC ACTUATED, lit.
~l T
EOP: TITLE:
REV 7 P-TURB;1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 3 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- * * * * * * * * * * * * * *.* * * * * * * * * * * * * * * * * * * * * * * * *
- CAUTION IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURS, E-O, REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED.
1 Verify Turbine Stop Valves Manually trip turbine.
CLOSED IF turbine stop valves can NOT be closed, THEN close both MSIVs.
IF reactor power greater than 8%
with both MSIVs closed, THEN manually trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
EOP: T!TLE:
REV: 7 P-'TURB; 1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 4 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
CAUTION PRZR PRESSURE LOW PRESSURE TRIP IS RATE SENSITIVE, THEREFORE, MONITOR PRESSURE WHEN REDUCING RCS TEMPERATURE.
NOTE: Automatic rod control is desired, if available.
2 Check Reactor, Power:
- a. NIS intermediate ranges - ABOVE a. Go to Step 3.
THE POINT OF ADDING HEAT (APPROXIMATELY 2.5xlO 6 AMPS)
- b. Verify control rods driving in b. Perform the following:
to reduce reactor power in AUTO l) Ensure ROD CONTROL BANK SELECTOR switch to MANUAL
- 2) Insert rods as necessary to reduce reactor power.
- c. Borate as necessary to maintain control rods above rod insertion limits
EOP:
REV: 7 P-TURB;1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 5 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Monitor S/G Levels:
- a. Levels - GREATER THAN 30% OR a. IF MFW regulating and bypass INCREASING valves NOT controlling in AUTO, THEN place controllers in MANUAL and restore narrow range level to program.
IF S/G level can NOT be restored, THEN trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
- b. Levels - TRENDING TO PROGRAM b. IF S/G level above program and increasing uncontrolled, THEN place controller(s) in MANUAL and decrease flow as necessary.
IF flow can NOT be controlled, THEN perform the following:
l) Trip the reactor.
- 2) Stop the running MFW pump.
- 3) Close MFW pump discharge valves.
- 4) Go to E-O, REACTOR TRIP OR SAFETY INJECTION.
EOP:
REV: 7 P.~TURB; 1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 6 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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 S/G ARV setpoints to 1005 psig and verify proper operation.
- 2) IF power is greater than 8%,
THEN ensure reactor trip and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
- c. Tavg - TRENDING TO PROGRAM c. IF Tavg can NOT be controlled, THEN manually trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
5 Check PRZR Pressure IF PRZR pressure can NOT be TRENDING TO 2235 PSIG controlled, THEN refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.
EOP: TITLE:
REV: 7 P-TURB;1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 7 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check PRZR Level:
- a. Level - GREATER THAN 13% a. Perform the following:
- 1) Place loop B cold leg isolation valve to REGEN Hx (AOV-427) switch to CLOSE.
- 2) Place letdown orifice valve switches to CLOSE (AOV-200A, AOV-200B, and AOV-202).
- 3) Verify excess letdown isolation valve (AOV-310) closed.
- 4) Ensure PRZR heaters off.
- 5) Control charging to restore PRZR level greater than 13%.
- 6) WHEN PRZR level greater than 13%, THEN restore letdown.
- b. Level - TRENDING TO PROGRAM 'b. Increase charging flow as necessary to restore PRZR level to program.
EOP: T1jLE:
REV 7 P-TURB;1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 8 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check MFW System:
- a. Verify MFW regulating and bypass a. Place MFW regulating and bypass valves - OPERATING IN AUTO valve controllers in MANUAL and restore S/G level.
- b. MFW pumps - BOTH RUNNING b. Perform the following:
- 1) Verify one MFW pump running.
IF NOT, THEN verify both MDAFW pumps running.
- 2) Go to Step 8.
- c. Close one MFW pump discharge valve
- d. Stop selected MFW pump 8 Establish Stable Plant Conditions:
- a. Place rod control bank selector in MANUAL
- b. NIS intermediate ranges - BELOW b. Return to Step 2.
THE POINT OF ADDING HEAT (APPROXIMATELY 2.5x10 AMPS)
- c. PRZR pressure - BETWEEN c. Control PRZR heaters and spray 2220 PSIG AND 2260 PSIG as necessary.
- d. PRZR level - TRENDING TO PROGRAM d. Control charging as necessary.
- e. S/G levels - TRENDING TO PROGRAM e. Control S/G feed flow as necessary.
- f. RCS Tavg - GREATER THAN 540'F f. Control dumping steam as necessary. IF cooldown continues, THEN close both MSIVs.
~ ~
A
EOP: T1TLE:
REV 7 P-WRB:1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 9 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
CAUTION IF ANY S/G LEVEL ABOVE PROGRAM, THEN AFW FLOW MAY BE THROTTLED IMMEDIATELYTO PREVENT S/G ISOLATION.
NOTE: Maintain Reactor power less than 2%. This is within the capacity of MDAFW pumps.
9 Check S/G Feed Flow Status:
- a. Manually start both MDAFW pumps
- b. Verify AFW flow - ESTABLISHED b. Perform the following:
- 1) Establish MFW flow using MFW regulating valve bypass valves.
IF MFW NOT available, THEN manually start TDAFW pump and establish flow as necessary.
- 2) Go to Step 10.
- c. Verify MFW flow control valves c. Place A and B MFW regulating and CLOSED bypass valve controllers in manual at 0% demand.
~ MFW regulating valves
~ MFW bypass valves
- d. Close MFW pump discharge valves
~ MOV-3977, A MFW pump
~ MOV~976, B MFW pump
- e. Stop any running MFW pump and place in PULL STOP
- f. Check S/G level - TRENDING TO 39% f. Adjust MDAFW pump flow as necessary to restore S/G level.
4
EOP: TITLE:
REV: 7 P~ TURB." 1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 10 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
CAUTION WHEN FEEDING BOTH S/G(S) USING ONE MDAFW PUMP, THEN THE SUM OF THE FLOWS TO BOTH S/G(S) MUST BE LESS THAN 230 GPM.
10 Establish Normal AFW Pump Shutdown Alignment:
- a. Place AFW bypass switches to DEF
- b. Verify the following: b. Continue with Step ll. WHEN conditions met, THEN do Steps o Both S/G levels - STABLE OR 10c through f.
INCREASING o Total AFW flow - LESS THAN 200 GPM
- c. Close MDAFW pump discharge valves
~ MOV-4007
~ MOV-4008
- d. Stop all but one MDAFW pump
- e. Open AFW discharge crossover valves
~ MOV-4000A
~ MOV-4000B
- f. Open AFW bypass valves as necessary to control S/G levels
~ AOV-4480
~ AOV-4481
EOP: TITLE:
REV: 7 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 11 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Establish Normal Shutdown Alignment:
- a. Check condenser - AVAILABLE a. Dispatch AO to perform Attachment SD-2.
- b. Perform the following as necessary:
o Open generator disconnects
~ 1G13A71
~ 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cern to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump
- c. Verify Bus llA and Bus llB 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 Attachment SD-1
('
EOP:
II REV 7 PERTURB;1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 12 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
12 Notify Higher Supervision 13 Establish Desired Plant Conditions:
- a. Reactor shutdown - DESIRED a. IF turbine is to be restored to service, THEN maintain reactor critical and refer to 0-1.2, PLANT FROM HOT SHUTDOWN TO STEADY LOAD.
- b. Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN
-END-
0 ~J 0
EOP:
REV: 7 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 1 of 1 AP-TURB.1 APPENDIX LIST TITLE PAGES
- 1) ATTACHMENT SD-1
- 2) ATTACHMENT SD-2
