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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: 8 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 1 of 15 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE 2'p Pv .
CATEGORY 1'0 REVIEWED BY:
isosziooa7~ ~o~goooz+
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EOP:
REV: 8 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 2 of 15.
A. PURPOSE - This procedure provides actions to restore core cooling.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS This procedure is entered from:
- a. F-0.2, CORE COOLING Critical Safety Function Status Tree, on a RED condition.
EOP:
REV: 8 FR-C. 1 RESPONSE TO INADEQUATE CORE COOLING PAGE 3 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Adverse CNMT values should be used whenever CNMT ~ressure is greater than 4 psig or CNMT radiation is greater than 10+ 5 R/hr.
1 THAN 284'erform Check RNST LeVel GREATER the following:
- a. Ensure SI system aligned for cold leg recirculation using Steps 1 through 11 of ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.
- b. WHEN the SI system is aligned for sump recirculation, THEN go to Step 4.
EOP T1TLE0 REV: 8 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 4 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4' CAUTION RHR PUMPS SHOULD NOT BE RUN LONGER THAN 1 HOUR WITHOUT CCW TO THE RHR HEAT EXCHANGERS.
2 Verify SI Pump And RHR Pump Emergency Alignment:
- a. RHR pump discharge to Rx vessel a. Ensure at'east one valve open.
deluge - OPEN
~ MOV-852A
~ MOV-852B
- b. Verify SI pump C - RUNNING b, Manually start pump on available bus.
- c. Verify SI pump A - RUNNING c, Perform the following.
- 1) Ensure SI pumps B and C running.
- 2) Ensure SI pump C aligned to discharge line A:
o MOV-871B closed o MOV-871A open
- 3) Go to Step 3.
- d. Verify SI pump B - RUNNING d. Perform the following:,
- 1) Ensure SI pumps A and C running.
- 2) Ensure SI pump C aligned to discharge line B:
<m r, WP
( %pl o MOV-871B open o MOV-871A closed
- 3) Go to Step 3.
- e. Verify both SI pump C discharge e ~ Manually open valves as valves - OPEN necessary.
~ MOV-871A
~ MOV-871B
EOP I TITLE:
REV: 8 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 5 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Verify SI Pump Suction Alignment:
- a. Check BAST level: a. Perform the following:
o Level - GREATER RQQl 10$ 1) Ensure at least one SI pump suction valve from RWST open.
o Annunciator B-23, BORIC ACID TANK LO LO LEVEL- ~ MOV-825A EXTINGUISHED ~ MOV-825B
- 2) Ensure at least one valve in each SI pump suction line from BAST closed.
~ MOV-826A or MOV-826B
~ MOV-826C or MOV-826D
- 3) Go to Step 4.
- b. Verify SI pump suction valves b. Ensure both valves in either from BAST - OPEN flow path open.
~ MOV-826A o MOV-826A and MOV-826B
~ MOV-826B
~ MOV-826C -OR-
~ MOV-826D o MOV-826C and MOV-826D
- c. Verify SI pump suction from RWST c. Manually align valves as CLOSED necessary.
~ MOV-825A
~ MOV=825B
EOP:
REV: 8 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 6 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Verify SI Flow In Both Trains: Perform the following:
o SI line loop A and B flow a. Manually start pumps and align indicators - CHECK FOR FLOW valves as necessary.
o RHR loop flow indicator - CHECK b. Establish maximum charging flow.
FOR FLOW 5 Check RCP Support Conditions: Continue attempts to establish RCP support conditions.
- a. Verify Bus 11A or 11B - ENERGIZED
- b. Check other RCP support conditions (Refer to Attachment RCP START) 6 Check SI ACCUM Discharge IF SI ACCUM discharge valves closed Valves OPEN after ACCUM discharge, THEN go to Step 7. IF NOT, THEN perfone the
~ MOV-841 following:
~ MOV-865
- a. Dispatch AO 'with locked valve key to locally close breakers for SI ACCUM discharge valves.
~ MOV-841, MCC C position 12F
~ MOV-865, MCC D position 12C
- b. Open SI ACCUM discharge valves.
~ ACCUM A, MOV-841
~ ACCUM B, MOV-865
'efrw
'g
KOP REV: 8 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 7 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check Core Exit T/Cs LESS Go to Step 10.
THAN 1200'F 8 Check RVLIS Indication:
- a. RVLIS level (no RCPs) - GREATER a. IF RVLIS increasing, THEN return THAN 438 t46% adverse CNMT) to Step 1. IF NOT, THEN go to Step 9.
- b. Return to procedure and step in effect 9 Check Core Exit T/Cs:
- a. Temperature - LESS THAN 700'F a. IF decreasing, THEN return to Step 1. IF NOT, THEN go to Step 10.
- b. Return to procedure and step in effect
- * * * * * * * * * * * * * * * * * * * *,* * * * * * * * * * * * * * * * * * *
%
CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, THEN SELECTED SV PUMPS AND ONE CCW PUMP WILL AUTO START ON EMERGENCY D/G. MANUAL ACTION VILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.
10 Reset SZ
~e
0 EOP:
REV: 8 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 8 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Reset CI:
- a. Depress CI reset pushbutton
- b. Verify annunciator A-26, CNMT b. Perform the following:
ISOLATION - EXTINGUISHED
- 1) Reset SI.
- 2) Depress DI reset pushbutteu.
NOTE: This procedure should be continued while obtaining CNMT hydrogen sample in Step 12.
12 Check CNMT Hydrogen Concentration:
- a. Direct HP to start CNMT hydrogen monitors as necessary
- b. Hydrogen concentration - LESS b. Consult TSC to determine if THAN 0.5% hydrogen recombiners should be placed in service.
EOP TITLE:
REV' FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 9 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
CAUTION o 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).
o A FAULTED OR RUPTURED S/G SHOULD NOT BE USED IN SUBSEQUENT STEPS UNLESS NO INTACT S/G IS AVAILABLE.
NOTE: TDAFP pump flow control valves fail open on loss of IA.
- 13 Monitor Intact S/G Levels:
a.'arrow range level - GREATER a. Maintain total feed flow greater THAN 5% [25% adverse CNMT] than 200 gpm until narrow range level greater than 5% [25%
adverse CNMT] in at least one S/G.
IF total feed flow greater than 200 gpm can NOT be established, THEN perform the following:
- 1) Continue attempts to establish a heat sink in at least one S/G (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
- 2) Go to Step 23.
b, Control feed flow to maintain narrow range level between 17%
[25%'-adverse CNMT] and 50%
I EOP: TITLE:
REV: 8 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 10 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 14B).
14 Check RCS Vent Paths:
- a. Power to PRZR PORV block valves a. Restore power to'lock valves
- AVAILABLE unless block valve was closed to isolate an open PORV:
~ MOV-515, MCC C position 6C
~ MOV-516, MCC D position 6C
- b. PORVs - CLOSED b. IF PRZR pressure less than 2335 psig, THEN manually close PORVs.
IF any PORV can NOT be closed, THEN manually close its block valve.
- c. Block valves - AT LEAST ONE OPEN c. Open one block valve unless it was closed to isolate an open PORV.
- d. Rx vessel head vent valves 'd. Manually close valves.
CLOSED
~ SOV-590
~ SOV=591
~ SOV 592
~ SOV<<"593
~ r
EOP: TITLE0 REV: 8 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 11 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Establish Condenser Steam Dump Pressure Control:
- a. Verify condenser available: a. Place intact S/G ARV controller in MANUAL and go to Step 16.
o Intact S/G MSIV - OPEN o Annunciator G-15, STEAM DUMP ARMED - LIT
- b. Place steam dump mode selector switch in MANUAL
- c. Place steam dump controller in MANUAL NOTE: Partial'ncovering of S/G tubes is acceptable in the following steps.
16 Depressurize All Intact S/Gs To 200 PSIG:
- a. Dump steam to condenser at a. Manually or locally dump steam maximum rate at maximum rate using S/G ARVs.
- b. Check S/G pressure - LESS THAN b. IF S/G pressure decreasing, THEN 200 PSIG return to Step 13.
IF NOT, THEN go to Step 23.
- c. Check RCS hot leg temperatures- c. IF RCS hot leg temperatures BOTH LESS THAN 400'F . decreasing, THEN return to Step 13.
P IF NOT, THEN go to Step 23.
Wa vk
- d. Stop- S/G depressurization
EOP:
REV: 8 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 12 of 1S STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Check Isolated:
If SI ACCUMs Should Be
- a. RCS hot leg temperatures - BOTH a. Go to Step 23.
LESS THAN 400'F
- b. Verify SI reset b. Manually reset SI.
- c. Close SI ACCUM discharge valves c. Vent any unisolated ACCUMs:
~ ACCUM A, MOV-841 1) Open vent valves for
~ ACCUM B, MOV-865 unisolated SI ACCUMs.
~ ACCUM A, AOV-834A
~ ACCUM B, AOV-834B
- 2) Open HCV-945.
- d. Locally reopen breakers for MOV-841 and MOV-865 18 Stop Both RCPs 19 Dump Steam to Condenser At Manually or locally dump steam at Maximum Rate To Depressurize maximum rate using S/G ARVs.
All Intact S/Gs To Atmospheric Pressure 20 Verify SI Flow: Perform the following:
o SI liztb loop A and B flow a. Continue efforts to establish SI indicators - CHECK FOR FLOW flow.
-OR- b. Try to establish charging flow.
o RHR loop flow indicator - CHECK c. IF core exit T/Cs less than FOR FLOW 1200'F, THEN return to Step 19.
IF NOT, THEN go to Step 23.
EOP: T1TLE:
REV' FR-C. 1 RESPONSE TO INADEQUATE CORE COOLING PAGE 13 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Check Core Cooling:
- a. Core exit T/Cs - LESS THAN 1200'F a. Go to Step 23.
- b. RCS hot leg temperatures - BOTH b. Return to Step 19.
LESS THAN 320'F
- c. RVLIS level (no RCPs) - GREATER c. Return to Step 19.
THAN 68% [73% adverse CNMT]
22 Go to Appropriate Plant Procedure
- a. Check RWST level - GREATER THAN a. Go to ES-1.3, TRANSFER TO COLD 28'.
LEG RECIRCULATION, Step l.
Go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step 17 NOTE: Normal conditions are desired but not required for starting the RCPs.
23 Check Core Exit T/Cs LESS Start RCPs as necessary until core THAN 1200'F exit T/Cs less than 1200'F.
IF core exit T/Cs greater than 1200'F and all available RCPs running, THEN open all PRZR PORVs and block valves. IF IA NOT available, THEN refer to Attachment .
N2 PORVS.
IF core exit T/Cs greater than 1200'F and all PRZR PORVs and block valves open, THEN open Rx vessel head vent valves.
~ SOV-590
~ SOV-591
~ SOV-592
~ SOV-593
4 I EOP:
REV: 8 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 14 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 24 Try To Locally Depressurize Use faulted or ruptured S/G.
All Intact S/Gs To Atmospheric Pressure:
o Use intact S/G(s) ARVs
-OR-o Open TDAFW pump steam supply valve from intact S/G(s)
~ S/G A, MOV-3505A
~ S/G B, MOV-3504A
-OR-o Perform the following:
a, Open intact S/G MSIV bypass valves
- b. Open both priming air ejector steam inlet valves
~ V-.3580
~ V-3581 25 Check Isolated:
If SI ACCUMs Should Be
- a. RHR loop flow indicator - AT a. Return .to Step 23.
LEAST INTERMITTENT FLOW
- b. Close: SI ACCUM discharge valves b. Vent any unisolated ACCUMs:
~ ACCUM A, MOV-841 1) Open vent valves for
~ ACCUM B, MOV-&65 unisolated SI ACCUMs.
~ ACCUM A, AOV-834A
~ ACCUM B, AOV-834B
- 2) Open HCV-945.
- c. Locally reopen breakers for MOV-841 and MOV-865
EOP: TLTLE:
REV: 8 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 15 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Check Stopped:
If RCPs Should Be
- a. Both RCS hot leg temperatures- a. Go to Step 27.
LESS THAN 320'F
- b. Stop all RCPs 27 Verify SI Flow: Perform the following:
o SI line loop A and B flow a. Continue efforts to establish SI indicators - CHECK FOR FLOW flow.
-OR- b. Try to establish charging flow.
o RHR loop flow indicator - CHECK c. Return to Step 23.
FOR FLOW 28 Check Core Cooling: Return to Step 23.
o RVLIS indication - GREATER THAN 68$ f73% adverse CNMT) o RCS hot leg temperatures - LESS THAN 320'F 29 Go to Appropriate Plant Procedure I
- a. Check RWST level - GREATER THAN a. Go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
28'.
Go to,.;E;-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 17
-END-
REV: 8 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 1 of 1 FR-C.1 APPENDIX LIST TITLE PAGES
- 1) ATTACHMENT RCP START
- 2) ATTACHMENT N2 PORVS