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-PRZR.1 TITLE: ABNORMAL PRESSURIZER PRESSURE REV'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: 94iOi80209 940930 PDR ADDCK 05000244 P 4I EOP: P-PRZR.l TITLE: ABNORMAL PRESSURIZER PRESSURE REV 7 PAGE 2 of 11 A.PURPOSE-This procedure provides the actions necessary to mitigate the consequences of abnormal PRZR pressure.B.ENTRY CONDITIONS/SYMPTOMS l.ENTRY CONDITIONS
-This procedure is entered from: a.AP-CVCS.1, CVCS LEAK, or b~AP FW 1 i PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER, or c.AP-IA.1, LOSS OF INSTRUMENT AIR, or d.AP-RCC.1, CONTINUOUS CONTROL ROD WITHDRAWAL OR INSERTION, or e.AP-RCS.1, REACTOR COOLANT LEAK, or f AP TURB~1 g TURBINE TRI P WITHOUT RX TRI P REQUIRED g or g.AP-TURB.2, TURBINE LOAD REJECTION, when PRZR pressure can NOT be controlled.
2.SYMPTOMS-The symptoms of ABNORMAL PRZR PRESSURE are;a.Annunciator F-19, PRZR PORV OUTLET HI TEMP 145'F, lit, or b.Annunciator F-18, PRZR SAFETY VLV OUTLET HI TEMP 145'F, lit, or c.Annunciator AA-13, PRESSURIZER SAFETY VALVE POSITION, lit, or d.Annunciator F-l, PRT LIQUID HI TEMP 220'F, lit, or e.Annunciator F-9, PRT HI PRESS 5 PSI, lit, or f.Annunciator F-17, PRT LEVEL 60.8 4 84.5, lit, or g.Annunciator F-2, PRESSURIZER HI PRESS 2310 PSI, lit, or h.Annunciator F-10, PRESSURIZER LO PRESS 2185 PSI, lit, or i.Annunciator F-6, PRESSURIZER HEATER BREAKER TRIP, lit.j.Annunciator F-26, PRESSURIZER HI PRESS CHANNEL ALERT 2377 PSI.
EOP: P-PRZR.1 TITLE: ABNORMAL PRESSURIZER PRESSURE REV: 7 PAGE 3 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************
4**%**%*****************
CAUTION IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURS, E-O, REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED.
- xx***xxx*x*x*xx%%'ex xxk*xxxxx**%x**x%'*xx NOTE: Actual PRZR pressure should be verified by more than 1 indicator.
1 Check PRZR Pressure: o All 4 narrow range channels APPROXIMATELY EQUAL o All 4 narrow range channels TRENDING TOGETHER IF one pressure channel deviates significantly from the other 3, THEN perform the following:
a.IF the controlling PRZR pressure channel has failed, THEN place controller, 431K, in MANUAL and adjust output to restore PRZR pressure.b.Refer to ER-INST.l, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE.2 Check Reactor Power-STABLE IF the abnormal, PRZR pressure is a result of a power transient, THEN evaluate conditions and go to the appropriate plant procedure.
3 Check PRZR Pressure: a.Pressure-LESS THAN 2235 PSIG b.Pressure-GREATER THAN 2000 PSIG a.Go to Step 12 b.IF pressure decreasing uncontrollably, THEN trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
EOP: P-PRZR.1 TITLE ABNORMAL PRESSURIZER PRESSURE REV: 7 PAGE 4 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED**x***x x x~x**x x x x 4*x x x x x w~*x x x x**x*******
CAUTION OBSERVE D/G LOADING LIMITS OF 2300 KW FOR 1/2 HOUR, 2250 KW FOR 2 HOURS, AND 1950 KW FOR CONTINUOUS SERVICE.*******xx*xx*xxxxxxxxxx>x****xx**xx**x***
4 Check PRZR Heater Status: a.PRZR heater control group BREAKER CLOSED a.Place PRZR heater control group switch to TRIP to reset, then place switch to CLOSE and let return to AUTO.b.PRZR heater backup group-ON b.IF PRZR pressure less than 2220 psig, THEN energize PRZR backup heaters.IF PRZR backup heater breaker has tripped, THEN perform the following:
1)Place the breaker switch to OFF to reset breaker.2)Place the breaker switch to ON to energize heaters.3)Verify load increase on Bus 16.
1 EOP: P-PRZR.1 TITLE: ABNORMAL PRESSURIZER PRESSURE REV'PAGE 5 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Verify Normal PRZR Spray Valve Controllers
-DEMAND AT 0~o Place controllers in MANUAL at 0%demand.IF valves can NOT be closed, THEN perform the following:
a.Trip the reactor.b.Trip the associated RCP.c.Go to E-O, REACTOR TRIP OR SAFETY INJECTION.
NOTE: With PRZR pressure controller 431K in manual, PORV-431C will not be operable in the automatic mode.6 Check PRZR Pressure Controller, 431K, Demand-LESS THAN 504 Place 431K in MANUAL and decrease output t:o energize PRZR heaters.
I ll 0 ts EOP: P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE REV: 7 PAGE 6 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check PRZR PORVs: a.PORVs-CLOSED a.Manually close PORVs.IF any valve can NOT be closed, THEN manually close the associated block valve.~MOV-516 for PCV-430~MOV-515 for PCV-431C b.Annunciator F-19, PRZR PORV OUTLET HI TEMP 145'F EXTINGUISHED b.IF PORV leakage is indicated, THEN perform the following:
1)Close PORV block valves one at a time AND check if pressure stabilizes.
~MOV-515~MOV-516 c.Go to Step 9 2)IF a leaking PRZR PORV is identified, THEN restore any nonleaking PORV to operable AND go to Step 8.
I EOP: P-PRZR.1 TITLE ABNORMAL PRESSURIZER PRESSURE REV: 7 PAGE 7 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Attempt To Reseat Any Leaking PORV: a.Verify affected PORV block valve CLOSED a.Close the affected PORV block valve.b.Cycle the leaking PORV open then closed c.Open affected PORV block valve d.Verify leakage has stopped d.IF leakage continues, THEN perform the following:
1)Reclose leaking PORV block valve.e.Go to Step 11 2)Refer to Tech Spec section 3.1.1.4 for required actions.
(~q I 4~'
EOP: P-PRZR.1 TITLE: ABNORMAL PRESSURIZER PRESSURE REV 7 PAGE 8 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED**x**x*xx*x**xxx%xx%***x*x*****xx**x*****
CAUTION o IF PRZR PRESSURE IS TO BE REDUCED WHILE AT POWER, IT SHOULD BE DONE SLOWLY SINCE THE PRZR LOW PRESSURE TRIP IS RATE SENSITIVE.
o WHEN REDUCING PRZR PRESSURE, OT4T SETPOINT WILL DECREASE.******%**x'****%x*x x x*x***x******%'***x***
9 Check PRZR Safety Valves: o Position indicator-LESS THAN 0.1 INCH.o Annunciator F-18, PRZR SAFETY VLV OUTLET HI TEMP 145'F EXTINGUISHED o Annunciator AA-13, PRESSURIZER SAFETY VALVE POSITION EXTINGUISHED IF safety valve leakage indicated, THEN perform the following to attempt to reseat the leaking valve: a.SLOWLY reduce PRZR pressure (remain above 2000 psig).b.IF symptoms indicate leakage has stopped, THEN restore pressure to normal.c.IF leakage recurs or can NOT be stopped, THEN perform the following:
1)Verify leakage within limits of Tech Spec section 3.1.5.2)Go to Step 17.10 Check AUX Spray'alve, AOV-296-CLOSED Manually close valve.IF valve can NOT be closed, THEN consider isolating letdown and closing cha'rging flow control valve, HCV-142.
I' EOP: P-PRZR.1 TITLE: ABNORMAL PRESSURIZER PRESSURE REV: 7 PAGE 9 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Check PRZR Pressure Control Restored: a.Pressure-TRENDING TO 2235 PSIG b.Go to Step 17 a.IF pressure continues to decrease, THEN return to Step 1.12 Check PRZR Backup Heaters-OFF Verify PRZR backup heater switch in AUTO, AND ensure proper operation.
NOTE: With PRZR pressure controller 431K in manual, PORV-431C will not be operable in the automatic mode.13 Check PRZR Pressure Controller, 431K, Demand-INCREASING Place 431K in MANUAL at 50%demand.NOTE: o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.o The bT between the REGEN Hx charging outlet and the PRZR shall NOT exceed 320'F.14 Check RCPs-ANY RUNNING IF letdown in service, THEN perform the following:
a.Open AUX spray valve, AOV-296, as necessary to control PRZR pressure.b.Go to Step 16.
EOP: P-PRZR.1'f!TLE: ABNORMAL PRESSURIZER PRESSURE REV 7 PAGE 10 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: If either RCP is off, then the associated PRZR spray valve controller should be placed in MANUAL with demand at 0%.15 Check PRZR Spray Valve Controllers Demand-GREATER THAN 0%~PCV-431A~PCV-431B Place PRZR spray valve controllers in MANUAL and open as required to control pressure.16 Check PRZR Pressure-TRENDING TO 2235 PSIG IF PRZR pressure continues to increase uncontrollably, THEN trip the reactor and go to E-O, REACTOR TRIP or SAFETY INJECTION.
17 Check PRT Indications:
a.Level-BETWEEN 61%AND 84%a.Drain PRT to RCDT using PRT drain valve, AOV-526.b.Pressure-APPROXIMATELY 1.5 PSIG AND STABLE c.Temperature
-AT CNMT AMBIENT TEMPERATURE AND STABLE b.Open PRT vent, AOV-527.IF PRT pressure will NOT decrease, THEN open PRT drain valve, AOV-526, to reduce pressure.c.To feed and bleed the PRT, perform the following:
1)Start a RMW pump.2)Verify RMW to CNMT isolation valve, AOV-508, open.3)Feed and bleed the PRT using PRT fill valve from'RMW, AOV-548, and PRT drain valve, AOV-526.
EOP:~W P-PRZR.1 TITLE: ABNORMAL PRESSURIZER PRESSURE REV'PAGE ll of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
18 Notify Higher Supervision-END-
