ML17309A519: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
(4 intermediate revisions by the same user not shown) | |||
Line 3: | Line 3: | ||
| issue date = 05/24/1993 | | issue date = 05/24/1993 | ||
| title = Forwards Ginna Nuclear Power Plant Eop,Including Rev 7 to AP-TURB.1, Turbine Trip W/O Rx Trip Required & Rev 8 to FR-C.2, Response to Degraded Core Cooling. | | title = Forwards Ginna Nuclear Power Plant Eop,Including Rev 7 to AP-TURB.1, Turbine Trip W/O Rx Trip Required & Rev 8 to FR-C.2, Response to Degraded Core Cooling. | ||
| author name = | | author name = Mecredy R | ||
| author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | ||
| addressee name = | | addressee name = Johnson A | ||
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | ||
| docket = 05000244 | | docket = 05000244 | ||
Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:A. | {{#Wiki_filter:A.CCEI ERAT 0 DOCUVIENT DIST UTION SYSTEM REGULAT INFORMATION DISTRIBUTIO SYSTEM (RIDS) | ||
ACCESSION NBR:9306040043 DOC.DATE: 93/05/24 NOTARIZED: NO DOCKET N FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp. | |||
RECIP.NAME RECIPIENT AFFILIATION /u 5'P JOHNSON,A. Project Directorate Z-3 ++4~+~ | |||
==SUBJECT:== | ==SUBJECT:== | ||
Forwards Ginna Nuclear Power Plant EOP,including Rev 7 to AP-TURB.l, "Turbine Trip W/o RX Trip Required" a Rev 8 to FR-C.2, "Response to Degraded Core Cooling." D DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR TITLE: OR/Licensing Submittal: Suppl 1 A ENCL SIZE: | |||
to NUREC-0737(Generic Ltr 82-33) | |||
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA 1 1 PD1-3 PD 1 1 JOHNSON,A 2 2 INTERNAL: NRR DRCH/HHFB11 1 1 OC/LFMB 1 0 REG E Ol 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 D | |||
D D | |||
NOTE TO ALL"RIDS" RECIPIENTS: | |||
PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! | |||
TOTAI NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 9 | |||
IIIII/i7llll IIIIIIIIII!II | |||
////// /// Ill/IIIII l IIIIII/ /IIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C MECREDY TELEPHONE trice Prerldent ArtEA cooE Tie 546-2700 Cinna Nudear Production May 24, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. Allen Johnson Project Directorate I-3 Washington, D.C. 20555 | |||
==Subject:== | ==Subject:== | ||
Emergency Operating Procedures R. E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen: | |||
AP-TURB. | As requested, enclosed are Ginna Station Emergency Operating Procedures. | ||
Very truly yours, Robert C. Mecredy Enclosures c: Mr. Lee Bettenhausen, USNRC, Region 1 Resident Inspector, Ginna Station oaoe06 pO~ | |||
I I 930b040043 'Tt30524 PDR ADDCK 05000244 P PDR | |||
t 1 | |||
l k | |||
~ ~ | |||
I/ | |||
l V | |||
ii | |||
AP-TURB.1 Turbine Trip Without RX Trip Required FR-C.2 Response To Degraded Core Cooling | |||
TITLE: | |||
REV: | |||
AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAG 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORAT ON GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT UPERINTENDENT EFF I E DATE CATEGORY 1.0 REVIEWED BY | |||
T1TLE: | |||
REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 2 of 10 A. PURPOSE This procedure provides the necessary instructions to control the plant following a turbine trip without a reactor trip required. | |||
B. ENTRY CONDITIONS/SYMPTOMS | |||
: 1. ENTRY CONDITIONS This procedure is entered from: | |||
: a. AP-CW.l, LOSS OF A CIRC WATER PUMP, or, | |||
: b. AP-ELEC.1, LOSS OF 12A AND/OR 12B TRANSFORMER, or, | |||
: c. AP-FW.l, PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER, or | |||
: d. AP-TURB.2, AUTOMATIC TURBINE RUNBACK, or, | |||
: e. AP-TURB.3, TURBINE VIBRATIONS, or, | |||
: f. AP-TURB.4, LOSS OF CONDENSER VACUUM, when power is less than P-9 and the turbine trips without a Rx trip. | |||
: 2. SYMPTOMS The symptoms of TURBINE TRIP WITHOUT RX TRIP REQUIRED are: | |||
: a. Annunciator K-1, THRUST BEARING FAILURE, lit, or | |||
: b. Annunciator K-9, TURBINE BEARING OIL LO PRESS TRIP 6 psi, lit, or | |||
: c. Annunciator K-10, TURBINE MANUAL TRIP, lit, or | |||
: d. Annunciator K-17, TURBINE LOW VACUUM TRIP 20" Hg, lit, or | |||
: e. Annunciator K-18, MAIN FEEDWATER PUMPS TRIPPED, lit, or | |||
: f. Annunciator K-26, GENERATOR LOCKOUT RELAY, lit, or | |||
: g. Annunciator K-25, TURBINE OVERSPEED ALERT 1980 RPM, lit, or | |||
: h. Annunciator F-21, COND HI PRESS 20" HG OR LOSS OF BOTH CIRC WTR PMPS, lit, or | |||
: i. Annunciator K-3, AMSAC ACTUATED, lit. | |||
TITLE REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 3 of 10 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. | |||
1 Verify Turbine Stop Valves- Manually trip turbine. | |||
CLOSED IF turbine stop valves can NOT be closed, THEN close both MSIVs. | |||
IF reactor power greater than 8% | |||
with both MSIVs closed, THEN manually trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION. | |||
CAUTION PRZR PRESSURE LOW PRESSURE TRIP IS RATE SENSITIVE, THEREFORE, MONITOR PRESSURE WHEN REDUCING RCS TEMPERATURE. | |||
NOTE: Automatic rod control is desired, if available. | |||
2 Check Reactor Power: | |||
F- | |||
: a. NIS intermediate ranges a. Go to Step 8. | |||
GREATER THAN 2.5x10 ~ AMPS | |||
: b. Verify control rods driving in b. Ensure rod control bank selector to reduce reactor power in AUTO switch in manual and drive rods in as necessary to reduce reactor power. | |||
: c. Borate as necessary to maintain control rods above rod insertion limits | |||
E TlTLE REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 4 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Establish Shutdown S/G Level Control | |||
: a. Place MFW regulating valve controllers in MANUAL | |||
: b. Control MFW flow as necessary to restore S/G level | |||
: c. S/G level - TRENDING TO PROGRAM c. Operate MFW bypass valves in MANUAL to restore. S/G level. | |||
IF S/G level can NOT be restored, THEN trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION. | |||
4 Verify Proper Operation Of Steam Dump: | |||
,a. Verify annunciator G-15, STEAN a. Place steam dump mode selector DUMP ARMED - LIT switch to MANUAL. | |||
: b. Condenser steam dump~operating b. IF steam dump NOT available, in AUTO THEN perform the following: | |||
: 1) Adjust S/G ARV setpoints to 1005 psig and verify proper operation. | |||
: 2) IF power is greater than 8%, | |||
THEN ensure reactor trip and go to E-O, REACTOR TRIP OR SAFETY INJECTION. | |||
: c. Tavg - TRENDING TO 547'F c. IF Tavg,can NOT be controlled, THEN manually trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION. | |||
EOP: TITLE: | |||
REV 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 5 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check PRZR Pressure IF PRZR pressure can NOT be TRENDING TO 2235 PSIG controlled, THEN refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE. | |||
6 Check PRZR Level: | |||
: a. Level - GREATER THAN 13% a. Perform the following: | |||
: 1) Place loop B cold leg isolation valve to REGEN Hx (AOV-427) switch to CLOSE. | |||
: 2) Place letdown orifice valve switches to CLOSE (AOV-200A, AOV-200B, and AOV-202). | |||
: 3) Verify excess letdown isolation valve (AOV-310) closed. | |||
: 4) Ensure PRZR heaters off. | |||
: 5) Control charging to restore PRZR level greater than 13%. | |||
: 6) WHEN PRZR level greater than 13%, THEN restore letdown. | |||
: b. Level - TRENDING TO PROGRAM b. Increase charging flow as necessary to restore PRZR level to program. | |||
EOP: TITLE: | |||
REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX'TRIP REQUIRED PAGE 6 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Placing MFW regulating valve controllers in MANUAL will restore automatic control of MFW bypass valves if desired. | |||
7 Check MFW System: | |||
: a. Verify MFW regulating valve a. Place MFW regulating valve bypass valves - OPERATING IN AUTO bypass valve controllers in AUTO and transfer to bypass control if desired. | |||
: b. MFW pumps - BOTH RUNNING b. Perform the following: | |||
: 1) Verify one MFW pump running. | |||
IF NOT, THEN verify both MDAFW pumps running. | |||
: 2) Go to Step 8. | |||
: c. Close one MFW pump discharge valve | |||
: d. Stop selected MFW pump 8 Establish Stable Plant Conditions: | |||
: a. Place rod control bank selector in MANUAL | |||
: b. Check Rx power - LESS THAN b. Return to Step 2. | |||
2.5x10 6 AMPS | |||
: c. PRZR pressure - BETWEEN c. Control PRZR heaters and spray 2220 PSIG AND 2260 PSIG as necessary. | |||
: d. PRZR level - between 20% and 30% d. Control charging as necessary. | |||
: e. S/G levels - TRENDING TO PROGRAM e. Control S/G feed flow as necessary. | |||
: f. RCS Tavg - GREATER THAN 540'F f. Control dumping steam as necessary. IF cooldown continues, THEN close both MSIVs. | |||
I' TITLE: | |||
REV: 5 AP- TURB. 1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 7 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Maintain Reactor power less than 2%. This is within the capacity of MDAFW pumps. | |||
9 Check S/G Feed Flow Status: | |||
: a. Manually start both MDAFW pumps | |||
: b. Verify total AFW flow - GREATER b. Perform the following; THAN 200 GPM | |||
: 1) Establish MFW flow using MFW regulating valve bypass valves. | |||
IF MFW NOT available, THEN manually start TDAFW pump and establish flow as necessary. | |||
: 2) Go to Step 10. | |||
: c. Verify MFW flow control valves c. Place A and B MFW regulating and CLOSED bypass valve controllers in manual at 0% demand. | |||
~ MFW regulating valves | |||
~ MFW bypass valves | |||
: d. Close MFW pump discharge valves | |||
~ MOV-3977, A MFW pump | |||
~ MOV-3976, B MFW pump | |||
: e. Stop any running MFW pump | |||
: f. Check S/G level - TRENDING TO 39% f. Adjust MDAFW pump flow as necessary to restore S/G level. | |||
TITLE REV: 5 AP-TURB. 1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 8 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION WHEN FEEDING BOTH S/GS USING ONE MDAFW PUMP, THEN THE SUM OF THE FLOWS TO BOTH S/GS MUST BE LESS THAN 230 GPM. | |||
10 Establish Normal AFW Pump Shutdown Alignment: | |||
: a. Place AFW bypass switches to DEF | |||
: b. Verify AFW bypass valves b. Go to Step 11. | |||
OPERABLE | |||
~ AOV-4480 | |||
~ AOV-4481 | |||
: c. Verify the following: c. Continue with Step 11. WHEN conditions met, THEN do Steps o Both S/G levels - STABLE OR 10d through g. | |||
INCREASING o Total AFW flow - LESS THAN 200 GPM | |||
: d. Close MDAFW pump discharge valves | |||
~ MOV-4007 | |||
~ MOV-4008 | |||
: e. Stop all but one MDAFW pump | |||
: f. Open AFW discharge crossover valves | |||
~ MOV-4000A | |||
~ MOV-4000B | |||
: g. Open AFW bypass valves as necessary to control S/G levels | |||
~ AOV-4480 | |||
~ AOV-4481 | |||
EOP: | |||
I REV: 5 AP-TURB. 1 E TRIP WITHOUT Rx TR1P REQUIRED PAGE 9 of 1O STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Establish Normal Shutdown Alignment: | |||
: a. Check condenser - AVAILABLE a. Dispatch AO to perform Attachment SD-2. | |||
: b. Perform the following as necessary: | |||
o Open generator disconnects | |||
~ 1G13A71 | |||
~ 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cern to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump it | |||
: c. Verify Bus 11A and Bus 11B c. IF either bus NOT energized, energized - BOTH BUSSES GREATER THEN refer to 0-6.9.2, THAN 4 KV ESTABLISHING AND/OR TRANSFERRING OFFSITE POWER TO BUS 12A/ | |||
BUS 12B. | |||
: d. Dispatch AO to perform Attachment SD-1 NOTE: Refer to 0-9.3, NRC STATE AND COUNTIES IMMEDIATE NOTIFICATION, for reporting requirements. | |||
12 Notify Higher Supervision | |||
Ebs: | |||
REV' AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 10 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Establish Desired Plant Conditions: . | |||
: a. Reactor shutdown - DESIRED a. IF turbine is to be restored to service, THEN maintain reactor critical and refer to 0-1.2, PLANT FROM HOT SHUTDOWN TO STEADY LOAD. | |||
: b. Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN | |||
-END- | |||
F.OP: | |||
REV: 5 TURBINE TRIP WITHOUT Rg TRIP REQUIRED PAGE 1 of 1 APPENDIX LIST | |||
: 1) Attachment SD-1 | |||
: 2) Attachment SD-2 | |||
r}} | |||
Latest revision as of 04:28, 4 February 2020
ML17309A519 | |
Person / Time | |
---|---|
Site: | Ginna ![]() |
Issue date: | 05/24/1993 |
From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
Shared Package | |
ML17263A305 | List: |
References | |
NUDOCS 9306040043 | |
Download: ML17309A519 (18) | |
Text
A.CCEI ERAT 0 DOCUVIENT DIST UTION SYSTEM REGULAT INFORMATION DISTRIBUTIO SYSTEM (RIDS)
ACCESSION NBR:9306040043 DOC.DATE: 93/05/24 NOTARIZED: NO DOCKET N FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION /u 5'P JOHNSON,A. Project Directorate Z-3 ++4~+~
SUBJECT:
Forwards Ginna Nuclear Power Plant EOP,including Rev 7 to AP-TURB.l, "Turbine Trip W/o RX Trip Required" a Rev 8 to FR-C.2, "Response to Degraded Core Cooling." D DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR TITLE: OR/Licensing Submittal: Suppl 1 A ENCL SIZE:
to NUREC-0737(Generic Ltr 82-33)
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA 1 1 PD1-3 PD 1 1 JOHNSON,A 2 2 INTERNAL: NRR DRCH/HHFB11 1 1 OC/LFMB 1 0 REG E Ol 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 D
D D
NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAI NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 9
IIIII/i7llll IIIIIIIIII!II
////// /// Ill/IIIII l IIIIII/ /IIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C MECREDY TELEPHONE trice Prerldent ArtEA cooE Tie 546-2700 Cinna Nudear Production May 24, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. Allen Johnson Project Directorate I-3 Washington, D.C. 20555
Subject:
Emergency Operating Procedures R. E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:
As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very truly yours, Robert C. Mecredy Enclosures c: Mr. Lee Bettenhausen, USNRC, Region 1 Resident Inspector, Ginna Station oaoe06 pO~
I I 930b040043 'Tt30524 PDR ADDCK 05000244 P PDR
t 1
l k
~ ~
I/
l V
ii
AP-TURB.1 Turbine Trip Without RX Trip Required FR-C.2 Response To Degraded Core Cooling
TITLE:
REV:
AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAG 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORAT ON GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT UPERINTENDENT EFF I E DATE CATEGORY 1.0 REVIEWED BY
T1TLE:
REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 2 of 10 A. PURPOSE This procedure provides the necessary instructions to control the plant following a turbine trip without a reactor trip required.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS This procedure is entered from:
- a. AP-CW.l, LOSS OF A CIRC WATER PUMP, or,
- b. AP-ELEC.1, LOSS OF 12A AND/OR 12B TRANSFORMER, or,
- d. AP-TURB.2, AUTOMATIC TURBINE RUNBACK, or,
- e. AP-TURB.3, TURBINE VIBRATIONS, or,
- f. AP-TURB.4, LOSS OF CONDENSER VACUUM, when power is less than P-9 and the turbine trips without a Rx trip.
- 2. SYMPTOMS The symptoms of TURBINE TRIP WITHOUT RX TRIP REQUIRED are:
- a. Annunciator K-1, THRUST BEARING FAILURE, lit, or
- b. Annunciator K-9, TURBINE BEARING OIL LO PRESS TRIP 6 psi, lit, or
- c. Annunciator K-10, TURBINE MANUAL TRIP, lit, or
- d. Annunciator K-17, TURBINE LOW VACUUM TRIP 20" Hg, lit, or
- e. Annunciator K-18, MAIN FEEDWATER PUMPS TRIPPED, lit, or
- f. Annunciator K-26, GENERATOR LOCKOUT RELAY, lit, or
- g. Annunciator K-25, TURBINE OVERSPEED ALERT 1980 RPM, lit, or
- h. Annunciator F-21, COND HI PRESS 20" HG OR LOSS OF BOTH CIRC WTR PMPS, lit, or
- i. Annunciator K-3, AMSAC ACTUATED, lit.
TITLE REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 3 of 10 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.
1 Verify Turbine Stop Valves- Manually trip turbine.
CLOSED IF turbine stop valves can NOT be closed, THEN close both MSIVs.
IF reactor power greater than 8%
with both MSIVs closed, THEN manually trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
CAUTION PRZR PRESSURE LOW PRESSURE TRIP IS RATE SENSITIVE, THEREFORE, MONITOR PRESSURE WHEN REDUCING RCS TEMPERATURE.
NOTE: Automatic rod control is desired, if available.
2 Check Reactor Power:
F-
- a. NIS intermediate ranges a. Go to Step 8.
GREATER THAN 2.5x10 ~ AMPS
- b. Verify control rods driving in b. Ensure rod control bank selector to reduce reactor power in AUTO switch in manual and drive rods in as necessary to reduce reactor power.
- c. Borate as necessary to maintain control rods above rod insertion limits
E TlTLE REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 4 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Establish Shutdown S/G Level Control
- a. Place MFW regulating valve controllers in MANUAL
- b. Control MFW flow as necessary to restore S/G level
- c. S/G level - TRENDING TO PROGRAM c. Operate MFW bypass valves in MANUAL to restore. S/G level.
IF S/G level can NOT be restored, THEN trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
4 Verify Proper Operation Of Steam Dump:
,a. Verify annunciator G-15, STEAN a. Place steam dump mode selector DUMP ARMED - LIT switch to MANUAL.
- b. Condenser steam dump~operating b. IF steam dump NOT available, in AUTO THEN perform the following:
- 1) Adjust S/G ARV setpoints to 1005 psig and verify proper operation.
- 2) IF power is greater than 8%,
THEN ensure reactor trip and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
- c. Tavg - TRENDING TO 547'F c. IF Tavg,can NOT be controlled, THEN manually trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.
EOP: TITLE:
REV 5 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 5 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check PRZR Pressure IF PRZR pressure can NOT be TRENDING TO 2235 PSIG controlled, THEN refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.
6 Check PRZR Level:
- a. Level - GREATER THAN 13% a. Perform the following:
- 1) Place loop B cold leg isolation valve to REGEN Hx (AOV-427) switch to CLOSE.
- 2) Place letdown orifice valve switches to CLOSE (AOV-200A, AOV-200B, and AOV-202).
- 3) Verify excess letdown isolation valve (AOV-310) closed.
- 4) Ensure PRZR heaters off.
- 5) Control charging to restore PRZR level greater than 13%.
- 6) WHEN PRZR level greater than 13%, THEN restore letdown.
- b. Level - TRENDING TO PROGRAM b. Increase charging flow as necessary to restore PRZR level to program.
EOP: TITLE:
REV: 5 AP-TURB.1 TURBINE TRIP WITHOUT RX'TRIP REQUIRED PAGE 6 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Placing MFW regulating valve controllers in MANUAL will restore automatic control of MFW bypass valves if desired.
7 Check MFW System:
- a. Verify MFW regulating valve a. Place MFW regulating valve bypass valves - OPERATING IN AUTO bypass valve controllers in AUTO and transfer to bypass control if desired.
- b. MFW pumps - BOTH RUNNING b. Perform the following:
- 1) Verify one MFW pump running.
IF NOT, THEN verify both MDAFW pumps running.
- 2) Go to Step 8.
- c. Close one MFW pump discharge valve
- d. Stop selected MFW pump 8 Establish Stable Plant Conditions:
- a. Place rod control bank selector in MANUAL
- b. Check Rx power - LESS THAN b. Return to Step 2.
2.5x10 6 AMPS
- d. PRZR level - between 20% and 30% d. Control charging as necessary.
- e. S/G levels - TRENDING TO PROGRAM e. Control S/G feed flow as necessary.
- f. RCS Tavg - GREATER THAN 540'F f. Control dumping steam as necessary. IF cooldown continues, THEN close both MSIVs.
I' TITLE:
REV: 5 AP- TURB. 1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 7 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Maintain Reactor power less than 2%. This is within the capacity of MDAFW pumps.
9 Check S/G Feed Flow Status:
- a. Manually start both MDAFW pumps
- b. Verify total AFW flow - GREATER b. Perform the following; THAN 200 GPM
IF MFW NOT available, THEN manually start TDAFW pump and establish flow as necessary.
- 2) Go to Step 10.
- c. Verify MFW flow control valves c. Place A and B MFW regulating and CLOSED bypass valve controllers in manual at 0% demand.
~ MFW regulating valves
~ MFW bypass valves
- d. Close MFW pump discharge valves
~ MOV-3977, A MFW pump
~ MOV-3976, B MFW pump
- e. Stop any running MFW pump
- f. Check S/G level - TRENDING TO 39% f. Adjust MDAFW pump flow as necessary to restore S/G level.
TITLE REV: 5 AP-TURB. 1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 8 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION WHEN FEEDING BOTH S/GS USING ONE MDAFW PUMP, THEN THE SUM OF THE FLOWS TO BOTH S/GS MUST BE LESS THAN 230 GPM.
10 Establish Normal AFW Pump Shutdown Alignment:
- b. Verify AFW bypass valves b. Go to Step 11.
~ AOV-4480
~ AOV-4481
- c. Verify the following: c. Continue with Step 11. WHEN conditions met, THEN do Steps o Both S/G levels - STABLE OR 10d through g.
INCREASING o Total AFW flow - LESS THAN 200 GPM
- d. Close MDAFW pump discharge valves
~ MOV-4007
~ MOV-4008
- e. Stop all but one MDAFW pump
- f. Open AFW discharge crossover valves
~ MOV-4000A
~ MOV-4000B
- g. Open AFW bypass valves as necessary to control S/G levels
~ AOV-4480
~ AOV-4481
EOP:
I REV: 5 AP-TURB. 1 E TRIP WITHOUT Rx TR1P REQUIRED PAGE 9 of 1O STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Establish Normal Shutdown Alignment:
- a. Check condenser - AVAILABLE a. Dispatch AO to perform Attachment SD-2.
- b. Perform the following as necessary:
o Open generator disconnects
~ 1G13A71
~ 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cern to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump it
- c. Verify Bus 11A and Bus 11B c. IF either bus NOT energized, energized - BOTH BUSSES GREATER THEN refer to 0-6.9.2, THAN 4 KV ESTABLISHING AND/OR TRANSFERRING OFFSITE POWER TO BUS 12A/
BUS 12B.
- d. Dispatch AO to perform Attachment SD-1 NOTE: Refer to 0-9.3, NRC STATE AND COUNTIES IMMEDIATE NOTIFICATION, for reporting requirements.
12 Notify Higher Supervision
Ebs:
REV' AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED PAGE 10 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Establish Desired Plant Conditions: .
- a. Reactor shutdown - DESIRED a. IF turbine is to be restored to service, THEN maintain reactor critical and refer to 0-1.2, PLANT FROM HOT SHUTDOWN TO STEADY LOAD.
- b. Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN
-END-
F.OP:
REV: 5 TURBINE TRIP WITHOUT Rg TRIP REQUIRED PAGE 1 of 1 APPENDIX LIST
- 1) Attachment SD-1
- 2) Attachment SD-2
r