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:
REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 1 of 11 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIB MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BX:
9708130%38 970805 05000244 PDR ADQCK
EOP:
REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 2 of 11 A. PURPOSE This procedure provides the instructions necessary to mitigate the consequences of a reactor coolant leak.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS This procedure is entered from:
- a. S-12.2, OPERATOR ACTION IN THE EVENT OF INDICATION OF SIGNIFICANT INCREASE IN LEAKAGE, when a significant increase in RCS leakage is indicated.
- b. AP-CVCS.1, CVCS LEAK, when leak cannot be isolated.
- 2. SYMPTOMS The symptoms of REACTOR COOLANT LEAK are;
- a. Annunciator F-14, CHARGING PUMP, SPEED, lit, or
- b. Annunciator A-2, VCT LEVEL 144 86, lit, or
- c. Annunciator E-16, RMS PROCESS MONITOR HIGH ACTIVITY, lit, or
- d. Annunciator E-24, RMS AREA MONITOR HIGH ACTIVITY, or lit, lit,'r
- e. Annunciator F-4, PRESSURIZER LEVEL DEVIATION -5 NORMAL +5,
- f. Annunciator F-10, PRESSURIZER LO PRESS 2185 PSI, lit, or
- g. Annunciator F-11, PRESSURIZER LO LEVEL 134, lit.
EOP:
REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 3 of 11 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.
NOTE:- Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION.
1 Check PRZR Level STABLE AT IF PRZR level decreasing, THEN PROGRAM LEVEL start additional charging pumps and increase speed as necessary to stabilize PRZR level.
IF PRZR level continues to decrease, THEN close loop B cold leg to REGEN Hx isolation valve, AOV-427.
IF available charging pumps are running at maximum speed with letdown isolated, AND PRZR level is decreasing, THEN trip the reactor and go to E-O, REACTOR TRIP or SAFETY INJECTION.
EOP: T1TLE:
REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 4 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: IF VCT level decreases to 5%, charging pump suction will swap to the RWST. This may require a load reduction.
2 Check VCT Makeup System:
- a. Verify VCT level - GREATER THAN a. Ensure charging pump suction 5a aligned to RWST.
~ LCV-112B - OPEN
~ LCV-112C - CLOSED
- b. Verify the following: b. Adjust controls as necessary.
- 1) RMW mode selector switch in AUTO
- 2) RMW control armed - RED LIGHT LIT
- c. Check VCT -level: c. Check letdown divert valve, LCV-112A, closed.
o Level GREATER THAN 20$
IF VCT makeup flow NOT adequate,
-OR- THEN perform the following:
o Level - STABLE OR INCREASING 1) Ensure BA transfer pumps and RMW pumps running.
- 2) Adjust RMW flow control valve, HCV-111, to increase RMW flow.
- 3) Increase boric acid flow as necessary to maintain required concentration.
IF VCT level can NOT be maintained, THEN refer to ER-CVCS.1, REACTOR MAKEUP CONTROL MALFUNCTION, necessary.
if
EOP: TITLE:
REV: 12 AP-RCS.l REACTOR COOLANT LEAK PAGE 5 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Check If RCS Leakage In CNMT: IF leakage is indicated in CNMT, THEN perform the following:
o Check CNMT radiation monitors-NORMAL a. Direct HP to sample CNMT for entry.
~ R-2
~ R-7 b. Continue'with Step 4. WHEN CNMT
~ R-lOA cleared for entry, THEN dispatch
~ R-11 personnel to investigate CNMT
~ R-12 for RCS leakage. /
o CNMT sump A pump run frequency-NORMAL (Refer to RCS Daily Leakage Log)
CAUTION RADIATION PROTECTION TECHNICIAN SHOULD BE CONSULTED PRIOR TO ENTERING A HIGH AIRBORNE AREA.
4 Dispatch AO To AUX BLDG To Investigate For CVCS Leak (locked area keys required) 5 Check For Leak To CCW System: Go to AP-CCW.1, LEAKAGE INTO THE COMPONENT COOLING LOOP.
o CCW surge tank level-APPROXIMATELY 50% AND'TABLE o CCW radiation monitor, R NORMAL
EOP: TITLE:
REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 6 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check CVCS Conditions:
- a. Letdown indication: a. IF letdown isolated, THEN continue with Step 6b. IF NOT o Letdown flow - APPROXIMATELY isolated, THEN go to AP-CVCS.1, 40 GPM CVCS LEAK, Step 6.
o Low pressure LTDN pressure-APPROXIMATELY 250 PSIG o Letdown pressure control valve, PCV-135, demand-APPROXIMATELY 35% OPEN
- b. Charging indication: b. Go to AP-CVCS.1, CVCS LEAK, Step 6.
o Seal injection flows GREATER THAN 6 GPM AND STABLE o RCP Labyrinth seal D/Ps GREATER THAN 15 INCHES AND APPROXIMATELY EQUAL o Charging pump discharge pressure - GREATER THAN RCS PRESSURE
- c. AUX BLDG radiation levels c. Go to AP-CVCS.1, CVCS LEAK, NORMAL Step 6 and refer to CVCS piping diagrams for further guidance.
~ R-4
~ R-9
~ R-10B
~ R-13
~ R-14
EOP: TlTLE:
REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 7 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check PRT Indications: Check tailpipe and valve leakoff temperatures for the PRZR safety
- a. Level - >BETWEEN 61% AND 84% valves and PORVs for indication of leakage.
- b. Pressure - APPROXIMATELY 1.5 PSIG AND STABLE IF no PORV,or safety valve leakage is indicated, THEN check other leak
- c. Temperature - AT CNMT AMBIENT paths from the RCS to the PRT.
TEMPERATURE AND STABLE
~ Letdown relief valve, RV-203
~ Seal return relief valve, RV-314 CAUTION STEAM GENERATOR TUBE LEAKAGE IN ONE S/G SHALL NOT EXCEED 0.1 GPM WHEN AVERAGED OVER 24 HOURS.
8 Check S/Gs For Leakage: IF S/G tube leak indicated, THEN refer to 0-6.10, PLANT OPERATION o Air ejector radiation monitors - ~
WITH A S/G TUBE LEAK INDICATION.
NORMAL
~ R-15
~ R-15A o S/G blowdown radiation monitor (R-19) - NORMAL o Steamline radiation monitors NORMAL
~ R-31
~ R-32 o S/G sample activity - NORMAL (Check with RP Department for normal)
EOP:
REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 8 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Check SI Accumulator Levels Calculate inleakage to SI STABLE accumulators (Refer to S-16.11, MONITORING INLEAKAGE TO SI ACCUMULATORS).
10 Check RCP Seal Leakoff Flows: Go to AP-RCP.l, RCP SEAL MALFUNCTION.
o Leakoff flows - WITHIN THE NORMAL OPERATING RANGE OF FIGURE RCP SEAL LEAKOFF o Leakoff flows - STABLE 11 Check RCDT Leak Rate NORMAL Check other sources of in leakage (Refer to RCS Daily Leakage to RCDT:
Log and PPCS point ID L1003)
- a. IF Rx vessel flange leakoff temperature has increased, THEN close Rx VESS FLANGE VLV, AOV-521.
SEAL'EAKOFF
- b. Verify excess letdown isolated.
IF NOT, THEN ensure RCDT divert valve, AOV-312, in the VCT position.
- c. IF source of leakage NOT determined, THEN suspect loop drains.
EOP: TITLE REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 9 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check Valve Leakoff IF any valve leakoff temperature is Temperatures NORMAL (Refer abnormally high, THEN initiate to Pressurizer Valve Leak-Off investigation of that leakage path.
Temperature Record Log) 13 Establish Stable Plant Conditions:
- a. PRZR level - TRENDING TO PROGRAM a. Control charging and letdown flows to restore PRZR level to program.
- b. Check PRZR pressure control: b. Verify proper operation of PRZR heaters and spray or take manual o Pressure - TRENDING TO control of PRZR pressure 2235 PSIG controller 431K. IF pressure can NOT be controlled, THEN o PRZR backup heaters - OFF refer to AP-PRZR,l, ABNORMAL PRESSURIZER PRESSURE, 14 Evaluate RCS Leakage:
- a. Leakage within limits (Refer to a. IF leak NOT isolable, but PRZR leakage surveillance sheet and level and seal injection can be ITS section 3.4.13) maintained, THEN shut the plant down (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN or AP-TURB.5, RAPID LOAD REDUCTION).
- b. Leak location identified b. Return to Step l.
REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 10 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
15 Notify Higher Supervision
-END-
EOP:
REV: 12 REACTOR COOLANT LEAK PAGE 11 of ll AP-RCS.1 APPENDIX LIST TITLE PAGES
- 1) FIGURE RCP SEAL LEAKOFF
EOP: TITLE:
REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 1 of 1 FIGURE RCP SEAL LEAKOFF kl SEAL LEAK RATE (GPH) 6 LEAK RATE INCREHENTS 0.2 GPH 3
NORHAL OPERATING RANGE DP INCREHENTS 50 PSI 250 500 750 1000 1250 1500 1750 2000 2250 2500 81 SEAL DP (RCS PRESS - VCT PRESS) PSI
J
