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: P-TURB.1 TITLE: TURBINE TRIP WITHOUT RX TRIP REQUIRED REV: 7 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: P-TURB.'1 TITLE: TURBINE TRIP WITHOUT RX TRIP REQUIRED REV 7 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~AP FW 1 g PART I AL OR COMPLETE LOSS OF MA I 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~b.c~d.e.gi Annunciator K-l, THRUST BEARING FAILURE, lit, or Annunciator K-9, TURBINE BEARING OIL LO PRESS TRIP 6 psi, lit, or Annunciator K-17, TURBINE LOW VACUUM TRIP 20" HG, lit, or Annunciator K-18, MAIN FEEDWATER PUMPS TRIPPED, lit, or Annunciator K-26, GENERATOR LOCKOUT RELAY, lit, or Annunciator K-25, TURBINE OVERSPEED ALERT 1980 RPM, lit, or Annunciator F-21, COND HI PRESS 20" HG OR LOSS OF BOTH CIRC WTR PMPS, lit, or h.Annunciator K-3, AMSAC ACTUATED, lit.
~l T EOP: P-TURB;1 TITLE: TURBINE TRIP WITHOUT RX TRIP REQUIRED REV 7 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-CLOSED Manually trip turbine.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: P-'TURB;1 T!TLE: TURBINE TRIP WITHOUT RX TRIP REQUIRED REV: 7 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 THE POINT OF ADDING HEAT (APPROXIMATELY 2.5xlO 6 AMPS)a.Go to Step 3.b.Verify control rods driving in to reduce reactor power in AUTO b.Perform the following:
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: P-TURB;1 TURBINE TRIP WITHOUT RX TRIP REQUIRED REV: 7 PAGE 5 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Monitor S/G Levels: a.Levels-GREATER THAN 30%OR INCREASING a.IF MFW regulating and bypass 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: P.~TURB;1 TURBINE TRIP WITHOUT RX TRIP REQUIRED REV: 7 PAGE 6 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Verify Proper Operation Of Steam Dump: a.Verify annunciator G-15, STEAM DUMP ARMED-LIT a.Place steam dump mode selector switch to MANUAL.b.Condenser steam dump operating in AUTO b.IF steam dump NOT available, 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-TRENDING TO 2235 PSIG IF PRZR pressure can NOT be controlled, THEN refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.
EOP: P-TURB;1 TITLE: TURBINE TRIP WITHOUT RX TRIP REQUIRED REV: 7 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: P-TURB;1 T1jLE: TURBINE TRIP WITHOUT RX TRIP REQUIRED REV 7 PAGE 8 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check MFW System: a.Verify MFW regulating and bypass valves-OPERATING IN AUTO b.MFW pumps-BOTH RUNNING c.Close one MFW pump discharge valve a.Place MFW regulating and bypass valve controllers in MANUAL and restore S/G level.b.Perform the following:
1)Verify one MFW pump running.IF NOT, THEN verify both MDAFW pumps running.2)Go to Step 8.d.Stop selected MFW pump 8 Establish Stable Plant Conditions:
a.Place rod control bank selector in MANUAL b.NIS intermediate ranges-BELOW THE POINT OF ADDING HEAT (APPROXIMATELY 2.5x10 AMPS)b.Return to Step 2.c.PRZR pressure-BETWEEN 2220 PSIG AND 2260 PSIG d.PRZR level-TRENDING TO PROGRAM e.S/G levels-TRENDING TO PROGRAM f.RCS Tavg-GREATER THAN 540'F c.Control PRZR heaters and spray as necessary.
d.Control charging as necessary.
e.Control S/G feed flow as necessary.
f.Control dumping steam as necessary.
IF cooldown continues, THEN close both MSIVs.
A~~
EOP: P-WRB:1 T1TLE: TURBINE TRIP WITHOUT RX TRIP REQUIRED REV 7 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 IMMEDIATELY TO PREVENT S/G ISOLATION.
NOTE: Maintain Reactor power less than 2%.This is within the capacity of MDAFW pumps.4 9 Check S/G Feed Flow Status: a.Manually start both MDAFW pumps b.Verify AFW flow-ESTABLISHED c.Verify MFW flow control valves CLOSED~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%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.Place A and B MFW regulating and bypass valve controllers in manual at 0%demand.f.Adjust MDAFW pump flow as necessary to restore S/G level.
EOP: P~TURB." 1 TITLE: TURBINE TRIP WITHOUT RX TRIP REQUIRED REV: 7 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:
o Both S/G levels-STABLE OR INCREASING b.Continue with Step ll.WHEN conditions met, THEN do Steps 10c through f.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: TURBINE TRIP WITHOUT RX TRIP REQUIRED REV: 7 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 energized-BOTH BUSSES GREATER THAN 4 KV c.IF either bus NOT energized, THEN refer to 0-6.9.2, ESTABLISHING AND/OR TRANSFERRING OFFSITE POWER TO BUS 12A/BUS 12B.d.Dispatch AO to perform Attachment SD-1
('
EOP: II PERTURB;1 TURBINE TRIP WITHOUT RX TRIP REQUIRED REV 7 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: TURBINE TRIP WITHOUT RX TRIP REQUIRED REV: 7 PAGE 1 of 1 AP-TURB.1 APPENDIX LIST TITLE PAGES 1)2)ATTACHMENT SD-1 ATTACHMENT SD-2
