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: FR-S.1 TITLE: RESPONSE TO REACTOR RESTART/ATWS REV: 7 PAGE 1 of 11 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY: 930514005b 930505'PDR ADOCK 05000244 F PDR
.L1 EOP: FR-S.1 RESPONSE TO REACTOR RESTART/ATWS REV!7 PAGE 2 of 11 A.PURPOSE-This procedure provides actions to add negative reactivity to a core which is observed to be critical when expected to be shut down.B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS
-This procedure is entered from: a.E-O, REACTOR TRIP OR SAFETY INJECTION, when reactor trip is not verified and manual trip is not effective.
b.F-0.1, SUBCRITICALITY Critical Safety Function Status Tree on either a RED or ORANGE condition.
EOP: FR-S.1 RESPONSE TO REACTOR RESTART/ATWS REV: 7 PAGE 3 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o Steps 1 through 4 are IMMEDIATE ACTION steps.o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.o At least one train of reactor trip breakers-OPEN o Neutron flux-DECREASING o MRPI indicates-ALL CONTROL AND SHUTDOWN RODS ON BOTTOM Manually trip reactor.IF reactor trip breakers NOT open, THEN manually insert control rods.O 2 Verify Turbine Stop Valves-CLOSED Manually trip turbine.IF turbine trip can NOT be verified, THEN close both MSIVs.3 Check AFW Pumps Running: a.MDAFW pumps-RUNNING b.TDAFW pump-RUNNING IF NECESSARY a.Manually start MDAFW pumps.b.Manually open steam supply valves.~MOV-3505A~MOV-3504A
EOP: FR-S.1 TITLE: RESPONSE TO REACTOR RESTART/ATWS REV: 7 PAGE 4-of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION ACTIONS TAKEN TO INITIATE RCS BORATION SHALL NOT BE REVERSED WHEN PERFORMING IMMEDIATE ACTIONS OF E-O, REACTOR TRIP OR SAFETY INJECTION.
NOTE: If offsite power is lost coincident with SI, then MCC C and MCC D lockout relays must be reset to restore BA and RMW pumps.O 4 Initiate Emergency Boration Of RCS: a.Check SI status: o All SI annunciators EXTINGUISHED o All SI pumps-OFF IN AUTO b.Verify at least one charging pump-RUNNING c, Align boration path: 1)Start two BA transfer pumps 2)Open MOV-350 3)Verify BA flow d.Verify charging flow path: o Charging valve to loop B cold leg (AOV-294)-OPEN o Charging flow control valve (HCV-142)-DEMAND AT 0'5 a.Perform the following:
1)Complete the immediate actions of E-O, REACTOR TRIP OR SAFETY INJECTION, while continuing with this procedure 2)IF SI flow indicated, THEN go to Step 5.IF NOT, THEN go to Step 4b.b.Perform the following:
1)Reset SI if necessary.
2)Start one charging pump.c.Initiate normal boration at maximum rate using the boric acid flow control valve, FCV-110A.IF flow can NOT be established, THEN refer to ER-CVCS.1, REACTOR MAKEUP CONTROL MALFUNCTION.
d.Manually align valves and verify flow.
EOP: FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS REV: 7 PAGE 5 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check If The Following Trips Have Occurred: a.Reactor trip a.Dispatch AO to locally trip reactor: o Trip MG set breakers at bus 13 and bus 15.b.Turbine trip o Open reactor trip breakers locally.b.Dispatch operator to locally trip turbine using manual trip lever on west end of HP turbine.6 Check PRZR PORV Status: o RCS pressure-LESS THAN 2335 PSIG o PORVs-CLOSED Verify CNMT ventilation isolation.
IF dampers NOT closed, THEN momentarily deenergize CNMT particulate monitor, R-ll, to actuate CVI.o Annunciator F-19, PRZR PORV OUTLET HI TEMP-EXTINGUISHED
EOP: FR-S~1 TITLE: RESPONSE TO REACTOR RESTART/ATWS REV'PAGE 6 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).7 Check S/G Level: a.Narrow range level in at least one S/G-GREATER THAN 5%(25%adverse CNMT]b.Control feed flow to maintain narrow range level between 17$t25%adverse CNMT]and 50%a.Perform the following:
1)Verify total feed flow greater than 400 gpm.IF NOT, THEN manually start pumps and align valves as necessary.
2)Maintain total feed flow greater than 400 gpm until narrow range level greater than 5$[25%adverse CNMT]in at least one S/G.8 Verify Dilution Paths-ISOLATED Manually isolate dilution paths.o Place RMW mode switch to BORATE o Verify RMW to blender (HCV-ill)CLOSED o Verify RMW pumps-OFF y't EOP: FR-ST 1 RESPONSE TO REACTOR RESTART/ATWS REV: 7 PAGE 7 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Stabilize RCS Temperature:
a.Control steam dump as necessary b.Verify the following:
o Core exit T/Cs-STABLE OR INCREASING b.IF RCS cooldown can NOT be controlled, THEN close both MSIVs and go to Step 10.o Pressure in both S/Gs STABLE OR INCREASING o Pressure in both S/Gs GREATER THAN 100 PSIG c.Go to Step 14 10 Verify MFW Isolation:
a.MFW pumps-TRIPPED b.MFW flow control valves-CLOSED~MFW regulating valves~MFW bypass valves a.Manually close MFW pump discharge valves and trip MFW pumps.b.Place A and B S/G MFW regulating valve and bypass valve controllers to MANUAL at 0%demand.11 Identify Faulted S/G: o Any S/G Pressure-DECREASING IN AN UNCONTROLLED MANNER Go to Step 14.-OR-o Any S/G-COMPLETELY DEPRESSURIZED
EOP: FR-S.1 TITLE: RESPONSE TO REACTOR RESTART/ATWS REV: 7 PAGE 8 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION o AT LEAST ONE S/G SHALL BE MAINTAINED AVAILABLE FOR RCS COOLDOWN.o IF BOTH S/GS ARE FAULTED, AT LEAST 50 GPM FEED FLOW SHOULD BE MAINTAINED TO EACH S/G.12 Isolate Feed Flow To Faulted S/G: o Close faulted S/G MDAFW pump discharge valve~S/G A, MOV-4007~S/G B, MOV-4008 o Pull stop faulted S/G MDAFW pump o Close faulted S/G TDAFW flow control valve Manually close valves.IF valves can NOT be closed, THEN dispatch AO to locally isolate flowpaths as necessary.
~S/G A, AOV-4297~S/G B, AOV-4298 o Verify faulted S/G MFW regulating valve and bypass valve-CLOSED~S/G A, HCV-466 and HCV-480~S/G B, HCV-476 and HCV-481 o Verify MDAFW pump crosstie valves-BOTH CLOSED~MOV-4000A~MOV-4000B o Close faulted S/G SAFW pump discharge valve~S/G A, MOV-9701A~S/G B, MOV-9701B
EOP: FR-S.1 RESPONSE TO REACTOR RESTART/ATWS REV: 7 PAGE 9 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Isolate Steam Flow From Faulted S/G: o Verify faulted S/G ARV-CLOSED~S/G A, AOV-3411~S/G B, AOV-3410 o Close faulted S/G TDAFW pump steam supply valve and place in PULL STOP Manually close valves.IF valves can NOT be closed, THEN dispatch AO to locally isolate flowpaths as necessary.
~S/G A, MOV-3505A~S/G B, MOV-3504A o Verify faulted S/G blowdown and sample valves-CLOSED~S/G A, AOV-5738 and AOV-5735~S/G B, AOV-5737 and AOV-5736 o Dispatch AO to complete faulted S/G isolation (Refer to Attachment FAULTED S/G)
A EOP: FR-S.1 T1TLE: RESPONSE TO REACTOR RESTART/ATWS REV: 7 PAGE 10 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION BORATION SHOULD CONTINUE TO OBTAIN ADEQUATE SHUTDOWN MARGIN DURING SUBSEQUENT ACTIONS.NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.
14 Verify Reactor Subcritical:
o Power range channels-LESS THAN 5%o Intermediate range channels STABLE OR DECREASING o Intermediate range channels startup rate-NEGATIVE o Core exit T/Cs-STABLE Perform the following:
a.Stabilize RCS temperature.
b.Continue to inject boric acid.c.Direct HP to sample RCS and PRZR for boron concentration.
d.Verify boron concentration greater than Figure SDM.IF adequate shutdown margin verified, THEN return to procedure and step in effect.IF NOT, THEN perform the following:
a.Allow RCS to heat up.b.Perform actions of other FR procedures in effect which do NOT cooldown or otherwise add positive reactivity to the core.c Return to Step 5.
EOP: FR-S.1 RESPONSE TO REACTOR RESTART/ATWS REV: 7 PAGE 11 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Return to Procedure And Step In Effect-END-
EOP: FR-S.1 RESPONSE TO REACTOR RESTART/ATWS REV: 7 PAGE 1 of 1 FR-S.1 APPENDIX LIST TITLE PAGES 1)FIGURE SDM 2)ATTACHMENT FAULTED S/G
EOP: FR-ST 1 TITLE: RESPONSE TO REACTOR RESTART/ATWS REV: 7 PAGE 1 of 1 FIGURE SDM 1 NOTE: o Curve includes allowance for one stuck rod.Add 100 ppm for each additional stuck rod.o To obtain core burnup, use PPCS turn on code BURNUP.BORON CONCENTRATION (PPH)1800 1600 BORON INCREMENTS 20 PPM 1400 1200 1000 ADEQUATE SDM 100 PPH CONS ERVATISH INCLUDED 800 600 400 BORA 200 BURNUP INCREMENTS 100 HWD/MTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 23 BURNUP (HWD/HTU)
