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' P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 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: TITLE:
REV 7 P-PRZR.l ABNORMAL PRESSURIZER PRESSURE 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, or PRZR PORV OUTLET HI TEMP 145'F, lit,
- 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, 2377 PSI.
PRESSURIZER HI PRESS CHANNEL ALERT
EOP: TITLE:
REV: 7 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 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: IF one pressure channel deviates significantly from the other 3, o All 4 narrow range channels THEN perform the following:
APPROXIMATELY EQUAL
- a. IF the controlling PRZR pressure o All 4 narrow range channels channel has failed, THEN place TRENDING TOGETHER 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 a. Go to Step 12
- b. Pressure - GREATER THAN 2000 PSIG b. IF pressure decreasing uncontrollably, THEN trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
EOP: TITLE REV: 7 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 4 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- x***xx x x**xx x x 4*x x x x x
~
CAUTION w ~ *x x x x**x*******
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 a. Place PRZR heater control group BREAKER CLOSED 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: TITLE:
REV' P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 5 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Verify Normal PRZR Spray Place controllers in MANUAL at 0%
Valve Controllers DEMAND AT demand. IF valves can NOT be 0~o 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 Place 431K in MANUAL and decrease Controller, 431K, Demand output t:o energize PRZR heaters.
LESS THAN 504
I ll 0
ts
EOP:
REV: 7 P-PRZR. 1 ABNORMAL PRESSURIZER PRESSURE 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 b. IF PORV leakage is indicated, OUTLET HI TEMP 145'F THEN perform the following:
EXTINGUISHED
- 1) Close PORV block valves one at a time AND check if pressure stabilizes.
~ MOV-515
~ MOV-516
- 2) IF a leaking PRZR PORV is identified, THEN restore any nonleaking PORV to operable AND go to Step 8.
- c. Go to Step 9
I EOP: TITLE REV: 7 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 7 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Attempt To Reseat Any Leaking PORV:
- a. Verify affected PORV block valve a. Close the affected PORV block CLOSED 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.
- 2) Refer to Tech Spec section 3.1.1.4 for required actions.
- e. Go to Step 11
(
~q I
4~ '
EOP: TITLE:
REV 7 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 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: IF safety valve leakage indicated, THEN perform the following to o Position indicator - LESS THAN attempt to reseat the leaking valve:
0.1 INCH.
- a. SLOWLY reduce PRZR pressure o Annunciator F-18, PRZR SAFETY (remain above 2000 psig).
VLV OUTLET HI TEMP 145'F EXTINGUISHED b. IF symptoms indicate leakage has stopped, THEN restore pressure o Annunciator AA-13, PRESSURIZER to normal.
SAFETY VALVE POSITION EXTINGUISHED 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, Manually close valve. IF valve can AOV-296 CLOSED NOT be closed, THEN consider isolating letdown and closing cha'rging flow control valve, HCV-142.
I' EOP: TITLE:
REV: 7 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 9 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Check PRZR Pressure Control Restored:
- a. Pressure - TRENDING TO 2235 PSIG a. IF pressure continues to decrease, THEN return to Step 1.
- b. Go to Step 17 12 Check PRZR Backup Heaters- Verify PRZR backup heater switch in OFF 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 Place 431K in MANUAL at 50% demand.
Controller, 431K, Demand INCREASING 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: 'f!TLE:
REV 7 P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 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 Place PRZR spray valve controllers Controllers Demand GREATER in MANUAL and open as required to THAN 0% control pressure.
~ PCV-431A
~ PCV-431B 16 Check PRZR Pressure IF PRZR pressure continues to TRENDING TO 2235 PSIG 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 b. Open PRT vent, AOV-527. IF PRT 1.5 PSIG AND STABLE pressure will NOT decrease, THEN open PRT drain valve, AOV-526, to reduce pressure.
- c. Temperature - AT CNMT AMBIENT c. To feed and bleed the PRT, TEMPERATURE AND STABLE 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: TITLE:
~ W REV' P-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 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-
