ML040020416
ML040020416 | |
Person / Time | |
---|---|
Site: | Ginna ![]() |
Issue date: | 12/17/2003 |
From: | Widay J Rochester Gas & Electric Corp |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
Download: ML040020416 (47) | |
Text
Joseph A. Widay ROe Always at Your Servke Vice President and Plant Manager December 17, 2003 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very truly yours, JAW/jdw xc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s):
E Index E-3, Rev 35 An equal opportunity employer 89 East Avenue I Rochester, NY 14649 tel (585) 546-2700 www.rge.com EE An Erg Ea st Company
C
-- -are NPSP0200 Ginna Nuclear Power Plant Wed 12/17/2003 11:09:32 am WRIGHTJ PROCEDURE INDEX Page 1 of I INPUT PARAMETERS: TYPE: STATUS VALUE(S): EF. 0Qt 5 YEARS ONLY:
PRE EMERGENCY PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVmW ST E-0 REACTOR TRIP OR SAFETY PINECTION 035 1011012003 03/24/003 03124/2008 EF E-1 LOSS OF REACTOR OR SECONDARY COOLANT 028 05/30/2003 03/2412003 03/24)2008 EF E-2 FAULTED STEAM GENERATOR ISOLATION 011 05/30/2003 03/2412003 03/24/2008 EF E-3 STEAM GENERATOR TUBE RUPTURE 035 12/17/2003 4/120143/2 03/24/2008 EF PRE TOTAL: 4 GRAND TOTAL: 4
Il ElF: TITL:
REV: 3 5 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 42 ROCHESTER GAS AND ELECTRIC CORPORATION '
GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLO MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
[EOP: TIT: REV: 35 E-3 STAM GENERATOR TUBE RUPTURE PAGE 2 of 42 A. PURPOSE - This procedure provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube rupture (SGTR), this procedure should also be used for a SGTR in one S/G and a fault in the other S/G.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS - This procedure is entered from:
- a. E-0, REACTOR TRIP OR SAFETY INJECTION, when condenser air ejector radiation or blowdown radiation is abnormal, or
- b. E-0, REACTOR TRIP OR SAFETY INJECTION, E-1, LOSS OF REACTOR OR SECONDARY COOLANT, E-2, FAULTED STEAM GENERATOR ISOLATION, and FR-H.3, RESPONSE TO STEAM GENERATOR HIGH LEVEL, when secondary radiation is abnormal, or
- c. E-0, REACTOR TRIP OR SAFETY INJECTION, E-1, LOSS OF REACTOR OR SECONDARY COOLANT, E-2, FAULTED STEAM GENERATOR ISOLATION, ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, when an intact S/G narrow range level increases in an uncontrolled manner.
- d. ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, when pressurizer pressure control is restored.
- e. Any FOLDOUT page that has E-3 transition criteria whenever either S/G level increases in an uncontrolled manner or either S/G has abnormal radiation.
EOP: TllLE: REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 3 of 42
_ACTION/EXPECTED RESPONSEREPNEOTBAID -
NOTE: o FOLDOUT page should be open AND monitored periodically.
o Critical Safety Function Status Trees should be monitored (Refer to Appendix 1 for Red Path Summary).
o Personnel should be available for sampling during this procedure.
o Conditions should be evaluated for Site Contingency Reporting (EPIP-1.0. GINNA STATION EVENT EVALUATION AND CLASSIFICATION).
o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.
- 1 Monitor RCP Trip Criteria:
- b. SI pumps - AT LEAST TWO RUNNING b. Go to Step 2.
- c. RCS pressure minus maximum SIG c. Go to Step 2.
pressure - LESS THAN 175 psig
[400 psig adverse CNMT]
- d. Stop both RCPs
EOP: TITLE:
REV: 3 5 E-3 STEAM GENERATOR TUBE RUPTURE l PAGE 4 of 42 l STEP ACTION/EXPECTED RESPONSE l RSPONSE NOT OBTAINED
- * *
- 0 * * *
- 0 0 0* * * * *
- O0* * * *
- 0 0* 0 * * * * * * * *
- CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET. THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5. ATTACHMENT LOSS OF OFFSITE POWER) 0 00 0
- 0 *
- 0 0
- 0* 00 0 *
- 0
- 0
- 0
- 0 *
- 0 0 0 0 * * * *
- 0 * *
- 2 Identify Ruptured S/G(s): Perform the following:
o Unexpected increase in either a. Reset SI SIG narrow range level
- b. Continue with Steps 10
-OR- through 16. WHEN ruptured S/G(s) identified. THEN do Steps o High radiation indication on 3 through 9.
main steamline radiation monitor
- R-31 for S/G A
- R-32 for S/G B
-OR-o AO reports local indication of high steamline radiation
-OR-o RP reports high radiation from S/G activity sample
MP: TITLE:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 5 of 42 STEP_ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDl
- * * * * * *
- ii 0 ii 0 h *
- 0 * * * * * * * *
- 0 *
- 0 * * * * * * * *
- 0 CAUTION o IF THE TDAFW PUMP IS THE ONLY AVAILABLE SOURCE OF FEED FLOW. STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE SG.
o AT LEAST ONE SG SHALL BE MAINTAINED AVAILABLE FOR RCS COOLDOWN.
- * * * * * * * *--- *
- 0* - * * * * * * . * *0 * * *
- 0* * * * *-
3 Isolate Flow From Ruptured S/G(s):
- a. Adjust ruptured SIG ARV controller to 1050 psig in AUTO
- b. Check ruptured SIG ARV - CLOSED b. WHEN ruptured SG pressure less than 1050 psig. THEN verify S/G ARV closed. IF NOT closed. THEN place controller in MANUAL and close SIG ARV.
IF SIG ARV can NOT be closed.
THEN dispatch AO to locally isolate.
- c. Close ruptured SIG TDAFW pump c. Dispatch AO with locked valve steam supply valve and place in key to locally isolate steam PULL STOP from ruptured SG to TDAFW pump.
- S/G A. MOV-3505A
- S/G A, V-3505
- S/G B. MOV-3504A
- S/G B. V-3504
- d. Verify ruptured S/G blowdown d. Place S/G blowdown and sample valve - CLOSED valve isolation switch to CLOSE.
- SIG A. AOV-5738 IF blowdown can NOT be isolated
- SIG B. AOV-5737 manually, THEN dispatch AO to locally isolate blowdown.
- S/G A. V-5701
- S/G B. V-5702
EOP: TITE:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 6 of 42 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED 4 Complete Ruptured S/G Isolation:
- a. Close ruptured SIG MSIV - a. Perform the following:
- 1) Close intact S/G MSIV.
- 3) Adjust condenser steam dump controller to 1050 psig in AUTO.
- 4) Place condenser steam dump mode selector switch to MANUAL.
- 5) Adjust reheat steam supply controller cam to close reheat steam supply valves.
- 6) Ensure turbine stop valves -
CLOSED.
- 7) Dispatch AO to complete ruptured S/G isolation (Refer to ATT-16.0. ATTACHMENT RUPTURED SG, parts A and B).
- 8) Go to step 5.
- b. Dispatch AO to complete ruptured S/ isolation (Refer to ATT-16.0. ATTACHMENT RUPTURED S/G part A)
EOP: TITE:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE P l ~~~~~~~~~~~~~~PAGE 7 of 42l SP ACTION/EXPECTED RESPONSE l lRESPONSE NOT OBTAINED
- h * * * * * * * * * * . * * * * * . * * * . * * * * * * . * * * * * * * . . .
- CAUTION IF ANY RUPTURED S/G IS FAULTED. FEED FLOW TO THAT SIG SHOULD REMAIN ISOLATED DURING SUBSEQUENT RECOVERY ACTIONS UNLESS NEEDED FOR RCS COOLDOWN.
- * * * - R - - * * * - * * - * * * * - - - - * * * * * * * * - - * * * - *
- 5 Check Ruptured S/G Level:
- a. Narrow range level - GREATER a. IF ruptured S/G NOT faulted.
THAN 5 [25% adverse CNMT] THEN perform the following:
- 1) Maintain feed flow to ruptured SIG until level greater than 5% [25% adverse CNMT].
- 2) Continue with Step 6. WHEN ruptured SG level greater than 5% [25% adverse CNMT],
THEN do Steps 5b through e.
- SIG A. MOV-4007
- S/G B. MOV-4008
- c. Pull stop MDAFW pump for ruptured S/G
- d. Close TDAFW pump flow control- d. Dispatch AO with locked valve valve to ruptured S/G key to locally close TDAFW pump manual feedwater isolation valve
- S/G A. AOV-4297 to ruptured S/G.
- S/G B. AOV-4298
- S/G A. V-4005
- S/G B. V-4006
- e. Verify DAFW pump crosstie e. Manually close valves.
valves - CLOSED
- MOV-4000A
- MOV-4000B
lOP TITLE: RV E-3 STEAM GENERATOR TUBE RUPTURE PAGE 8 of 42 TION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl STEP 6 Verify Ruptured S/G Isolated:
- a. Check ruptured MSIV - CLOSED a. Ensure air ejector/gland steam supply and flange heating steam isolated. (Refer to ATT-16.0.
ATTACHMENT RUPTURED SG, part B).
- b. Check TDAFW pump steam supply b. Continue efforts to isolate from ruptured SG - ISOLATED steam supply from ruptured S/G:
- SIG A. MOV-3505A OR V-3505
- S/G B. MOV-3504A OR V-3504
- c. Ruptured S/G pressure - GREATER c. Go to ECA-3.1. SGTR WITH LOSS OF THAN 300 PSIG REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.
7 Establish Condenser Steam Dump Pressure Control:
- a. Verify condenser available: a. Adjust S/G ARV controllers to maintain intact S/G pressure in o Intact SG MSIV - OPEN AUTO and go to Step 8.
o Annunciator G-15. STEAM DUMP ARMED - LIT
- b. Adjust condenser steam dump controller HC-484 to maintain intact S/G pressure and verify in AUTO
- c. Place steam dump mode selector switch to MANUAL
EOP: TITLE:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 9 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET. THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5. ATTACHMENT LOSS OF OFFSITE POWER)
- . a * . . . . . . - . . .a *
- a - . - - - - - -a - - - - - * - - - - - - -
8 Reset SI
EOP: TITLE: 1 REV: 35I E-3 STEAM GENERATOR TUBE RUPTURE PAGE 10 of 42 STEP _ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4
- 4 4
- 4
- 4 *
- 4
- 4 4 4 4 44*
- 4
- 4 4 4 4 4 *
- 4
- 4 4
- 4 4 4 4
- 4 CAUTION RUPTURED SIG LEVEL SHALL BE MAINTAINED GREATER THAN 5 [25% ADVERSE CNMT]
DURING THE RCS COOLDOWN, UNLESS THE RUPTURED SIG IS ALSO FAULTED.
- .
- 4 . 4 *
- 4 * *. * *4 * * .4 *
- 4 . * * * * *4 *
- 4 * *
- 4.4*
- 4
- 4
- NOTE: Following initiation of controlled cooldown or depressurization, RCP trip criteria is no longer applicable.
9 Initiate RCS Cooldown:
- a. Determine required core exit temperature from below table RUPTURED REQUIRED CORE EXIT SG PRESSURE TEMPERATURE (F) 1100 PSIG 525 [517 adverse CNMTI 1000 PSIG 512 [504 adverse CNMTI 900 PSIG 499 [490 adverse CNMT]
800 PSIG 484 [475 adverse CNMT]
700 PSIG 468 [457 adverse CNMT]
600 PSIG 449 [437 adverse CNMT]
500 PSIG 428 [413 adverse CNMT]
400 PSIG 402 [384 adverse CNMT]
300 PSIG 369 [344 adverse CNMT]
- b. IF ruptured S/G MSIV closed. b. Manually or locally initiate THEN initiate dumping steam to steam dump from intact SG at condenser from intact S/G at maximum rate using SIG ARV.
maximum rate IF no intact SG available. THEN perform the following:
o Use faulted SG.
-OR-o IF a ruptured S/G must be used. THEN go to ECA-3.1.
SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
- c. Core exit T/Cs - LESS THAN c. Continue with Step 10. WHEN REQUIRED TEMPERATURE core exit T/Cs less than required. THEN do Step 9d.
l EOP: TITLE:
I ~~~~~~~~~~~~~~REV:
35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 11 of 42 I~~~~~~~~~~~~~~~~~~~~~~~~~~~~-'-
ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINE NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.
10 Monitor Intact SG Level: -
- a. Narrow 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 SIG.
- b. Control feed flow to maintain b. IF narrow range level in the narrow range level between 17% intact SIG continues to increase
[25% adverse CNMT] and 50% in an uncontrolled manner. THEN go to ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.
EW: TIThE:
i TIILE: REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 12 of 42 SE ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINED1
- * * *
- h a * * * * * * * * * * * * * *
- 0 * *
- 0 * * * *
- 0
- 0 0 *
- 0 0
- 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 liB).
- . * * * * * * * * *
- 0 * *
- 0
- 0 * *
- 0
- 0 0 0
- a a U * . *
- a a *
- 11 Monitor PRZR PORVs And Block Valves:
- a. Power to PORV block valves - a. Restore power to block valves AVAILABLE unless block valve was closed to isolate an open PORV:
- MV-515, MCC D position 6C
- MOV-516, MCC C position 6C
IF any PORV can NOT be closed.
THEN manually close its block valve. IF block valve can NOT be closed. THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.
- c. Block valves - AT LEAST ONE OPEN c.tOpen one block valve unless it was closed to isolate an open PORV.
EOP: TIRE: REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE j PAGE 13 of 42 Eli ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Reset CI:
- a. Depress CI reset pushbutton
- b. Verify annunciator A-26. CNMT b. Perform the following:
ISOLATION - EXTINGUISHED
- 1) Reset SI. -
- 2) Depress CI reset pushbutton.
EOP: TITLE:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE l
. ~~~~~~~~~~~~~~PAGE 14 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Monitor All AC Busses - Perform the following:
BUSSES ENERGIZED BY OFFSITE POWER a. IF any AC emergency bus normal feed breaker open. THEN ensure o Normal feed breakers to all 480 associated D/G breaker closed.
volt busses - CLOSED
- b. Perform the following as o 480 volt bus voltage - GREATER necessary:
THAN 420 VOLTS
- 1) Close non-safeguards bus tie o Emergency D/G output breakers - breakers:
OPEN
- Bus 13 to Bus 14 tie
- Bus 15 to Bus 16 tie
- 2) Place the following pumps in PULL STOP:
- EH pumps
- Turning gear oil pump
- HP seal oil backup pump
- 3) Restore power to MCCs.
- A from Bus 13
- B from Bus 15
- E from Bus 15
- F from Bus 15
- 4) Start HP seal oil backup pump.
- 5) Start CNMT RECIRC fans as necessary.
- 6) Ensure D/G load within limits.
- 7) WHEN bus 15 restored. THEN reset control room lighting.
- c. Try to restore offsite power to all AC busses (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER).
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 15 of 42 STEP~ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 14 Verify Adequate SW Flow:
- a. Check at least two SW pumps - a. Manually start SW pumps as power RUNNING supply permits. (257 kw each).
IF less than two SW pumps running. THEN:
- 1) Ensure SW isolation.
- 2) IF NO SW pumps running. THEN perform the following:
a) Pull stop any DG that is NOT supplied by alternate cooling. AND immediately depress VOLTAGE SHUTDOWN pushbutton.
b) Refer to ATT-2.4.
ATTACHMENT NO SW PUMPS.
- 3) IF only one SW pump running.
THEN refer to AP-SW.2, LOSS OF SERVICE WATER.
- b. Dispatch AO to establish normal shutdown alignment (Refer to ATT-17.O. ATTACHMENT SD-1)
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 16 of 42 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I STP 15 Establish IA to CNMT:
- a. Verify non-safeguards busses a. Perform the following:
energized
- 1) Close non-safeguards bus tie o Bus 13 normal feed - CLOSED breakers:
-OR-
- Bus 13 to Bus 14 tie
- Bus 15 to Bus 16 tie o Bus 15 normal feed - CLOSED
- 2) Verify adequate emergency D/G capacity to run air compressors (75 kw each).
IF NOT. THEN perform the following:
o Start diesel air compressor (refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR)
-OR-o Evaluate if CNMT RECIRC fans should be stopped (Refer to ATT-4.0.
ATTACHMENT CNMT RECIRC FANS)
- b. Check SW pumps - AT LEAST TWO b. Perform the following:
PUMPS RUNNING
- 1) Restore IA using service air compressor OR diesel air compressor (refer to ATT-11.2. ATTACHMENT DIESEL.
AIR COMPRESSOR)
- 2) Go to step 15d.
- c. Verify turbine building SW c. Manually align valves.
isolation valves - OPEN
- MOV-4613 and MOV-4670
- MOV-4614 and MOV-4664 This Step continued on the next page.
EOP: TIRE: REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 17 of 42 ACTION/EXPECTED RESPONSE STEP PRESPONSE NOT OBTAINEDl (Step 15 continued from previous page)
- d. Verify adequate air compressors d. Manually start air compressors
- RUNNING as power supply permits (75 kw each). IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.
- e. Check IA supply: e. Perform the following:
o Pressure - GREATER THAN 1) Continue attempts to restore 60 PSIG IA (Refer to AP-IA.1. LOSS OF INSTRUMENT AIR).
o Pressure - STABLE OR INCREASING 2) Continue with Step 16. WHEN IA restored. THEN do Steps 15f and g.
- * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * . .
- 0 0 CAUTION RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT]. THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
. . . . . . . . 0 . . . . . . . . . . . . . . . .
- 0 0
- 0
- 0 * *
- 0 . 0 * . 0 16 Check If RHR Pumps Should Be Stopped:
- a. Check RCS pressure - GREATER a. Go to Step 17.
THAN 250 psig [465 psig adverse CNMT]
- b. Stop RHR pumps and place both in AUTO
,W: TITLE: REV: 35 E-3 STEAUM GENERATOR TUBE RUPTURE l ~~~~~~~~~~~~~~PAGE 18 of 42 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 17 Establish Charging Flow:
- a. Charging pumps - ANY RUNNING a. Perform the following:
- 1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high.
THEN dispatch AO to locally close seal injection needle valves to affected RCP.
- V-300A for RCP A
- V-300B for RCP B
- 2) Ensure HCV-142 demand at 0%.
- b. Align charging pump suction to b. IF LCV-112B can NOT be opened.
RWST: THEN dispatch AO to locally open V-358. manual charging pump o LCV-112B - OPEN suction from RWST (charging pump room).
o LCV-112C - CLOSED IF LCV-112C can NOT be closed.
THEN perform the following:
- 2) Verify charging pump A NOT running and place in PULL STOP.
- 3) WHEN V-358 open. THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (charging pump room).
- c. Start charging pumps as necessary and establish 75 gpm total charging flow
- Charging line flow
- Seal injection
MP: TILE:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 19 of 42 ACTION/EXPECTED RESPONSE llRESPONSE STE NOT OBTAINED I 18 Check If RCS Cooldown Should Be Stopped:
- a. Core exit T/Cs - LESS THAN a. Do NOT proceed until core exit REQUIRED TEMPERATURE T/Cs less than required temperature.,.
- b. Stop RCS cooldown
- c. Stabilize core exit T/Cs - LESS THAN REQUIRED TEMPERATURE 19 Check Ruptured S/G Pressure - IF pressure continues to decrease STABLE OR INCREASING to less. than 250 psi above the pressure of the intact S/G. THEN go to ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.
20 Check RCS Subcooling Based On Go to ECA-3.1. SGTR WITH LOSS OF Core Exit T/Cs - GREATER THAN REACTOR COOLANT - SUBCOOLED 20 0F USING FIG-1.0, FIGURE RECOVERY DESIRED. Step 1 .
MIN SUBCOOLING
4 EOP: TITLE: REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE l ~~~~~~~~~~~~~~PAGE 20 of 42 STEP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl NOTE: SI ACCUMs may inject during RCS depressurization.
21 Depressurize RCS To Minimize Break Flow And Refill PRZR:
- a. Check the following: a. Go to Step 22.
o Ruptured SIG level - LESS THAN 90% [80% adverse CNMT]
o Any RCP - RUNNING o IA to CNMT - AVAILABLE
- b. Spray PRZR with maximum available spray until ANY of the following conditions satisfied:
o PRZR level - GREATER THAN 75%
[65% adverse CNMT]
-OR-o RCS pressure - LESS THAN SATURATION USING FIG-l.0, FIGURE MIN SUBCOOLING
-OR-o BOTH of the following:
- 1) RCS pressure - LESS THAN RUPTURED SIG PRESSURE
- 2) PRZR level - GREATER THAN 5% [30% adverse CNMT]
- c. Close normal PRZR spray valves: c. Stop associated RCP(s).
- 1) Adjust normal spray valve controller to 0% DEMAND
- 2) Verify PRZR spray valves -
CLOSED
- PCV-431A
- PCV-431B
- d. Verify auxiliary spray valve d. Decrease charging speed to (AOV-296) - CLOSED minimum and ensure charging valve to loop B cold leg open (AOV-294).
- e. Go to Step 24
ACTI~~~~~~~~~~~O/XETE RESPONE
- * * *
- X 4
- 4 *
- 4
- 44* *
- 4 *
- 4 * *
- 4 4 4
- X 4
- 4 * *
- 4 * * * -
CAUTION o THE PRT MAY RUPTURE IF A PRZR PORV IS USED TO DEPRESSURIZE THE RCS. THIS MAY RESULT IN ABNORMAL CNMT CONDITIONS.
o CYCLING OF THE PRZR PORV SHOULD BE MINIMIZED.
o THE UPPER HEAD REGION MAY VOID DURING RCS DEPRESSURIZATION IF RCPS ARE NOT RUNNING. THIS MAY RESULT IN A RAPIDLY INCREASING PRZR LEVEL.
. . 4 4 . . 4 * . * * . . * * *
- 4
. *
- 4 * * .4 *4 4 * . * . . * .44
- 4 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 When using a PRZR PORV select one with an operable block valve.
22 Depressurize RCS Using PRZR PORV To Minimize Break Flow And Refill PRZR:
- b. PRZR PORVs - AT LEAST ONE b. IF auxiliary spray available.
AVAILABLE THEN return to Step 21b.
IF auxiliary spray can NOT be established. THEN go to ECA-3.3.
SGTR WITHOUT PRESSURIZER PRESSURE CONTROL. Step 1.
This Step continued on the next page.
EOP: TITLE:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 22 of 42 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED (Step 22 continued from previous page)
- c. Open one PRZR PORV until ANY of c. IF auxiliary spray available.
the following conditions THEN return to step 21b.
satisfied:
- 1) IF auxiliary spray can NOT be o PRZR level - GREATER THAN 75% established. THEN go to
[65% adverse CNMT] ECA-3.3. SGTR WITHOUT PRESSURIZER PRESSURE CONTROL.
-OR- Step 1.
o RCS pressure - LESS THAN SATURATION USING FIG-1.0, FIGURE MIN SUBCOOLING
-OR-o BOTH of the following:
- 1) RCS pressure - LESS THAN RUPTURED SIG PRESSURE
- 2) PRZR level - GREATER THAN 5% [30% adverse CNMT]
ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 23 Check RCS Pressure - Close block valve for the PRZR PORV INCREASING that was opened.
IF pressure continues to decrease.
THEN perform the following:
- a. Monitor the following conditions for indication of leakage from PRZR PORV:
o PORV outlet temp (TI-438) NOT decreasing.
o PRT pressure, level or temperature continue to increase.
- b. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.
REV: 35 E-3 STESAM GENERATOR TUBE RUPTURE l l l ~~~~~~~~~~~~PAGE 24 of 42 STEP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl
- * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- a * * - - -
- CAUTION SI MUST BE TERMINATED WHEN TERMINATION CRITERIA ARE SATISFIED TO PREVENT OVERFILLING OF THE RUPTURED SIG.
- * * * *
- a * *
- a * * * * *
- a * * * *
- a * *** * * * * * * * * * * * * * -
24 Check If SI Flow Should Be Terminated:
- a. RCS subcooling based on core a. Do NOT stop SI pumps. Go to exit T/Cs - GREATER THAN F ECA-3.1. SGTR WITH LOSS OF USING FIG-l.O. FIGURE MIN REACTOR COOLANT - SUBCOOLED SUBCOOLING RECOVERY DESIRED, Step 1.
- b. Secondary heat sink: b. IF neither condition satisfied, THEN do NOT stop SI pumps. Go to o Total feed flow to S/G(s) - ECA-3.1. SGTR WITH LOSS OF GREATER THAN 200 GPM AVAILABLE REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.
-OR-o Narrow range level in at least one intact SG -
GREATER THAN 5% 25% adverse CNMTI
- c. RCS pressure - STABLE OR c. Do NOT stop SI pumps. Go to INCREASING ECA-3.1, STR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.
- d. PRZR level - GREATER THAN 5% d. Do NOT stop SI pumps. Return to
[30% adverse CNMT] Step 6.
MOP: TITLE:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 25 of 42ll ACTION/EXPECTED RESPONSE l[RESPONSE STP NOT OBTAINED 25 Stop SI Pumps And Place In AUTO I 26 Establish Required Charging Line Flow: ,
- a. Charging pumps - ANY RUNNING a. Perform the following:
- 1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high.
THEN dispatch AO to locally isolate seal injection to affected RCP:
- RCP A. V-300A
- RCP B. V-300B
- 2) Ensure HCV-142 open.
- 3) Start one charging pump.
- b. Establish 20 gpm charging line flow 27 Monitor SI Reinitiation Criteria:
- a. RCS subcooling based on core a. Manually start SI pumps as exit T/Cs - GREATER THAN 0F - necessary and go to ECA-3.1.
USING FIG-1.O. FIGURE MIN SGTR WITH LOSS OF REACTOR SUBCOOLING COOLANT -SUBCOOLED RECOVERY DESIRED. Step 1.
- b. PRZR level - GREATER THAN 5% b. Control charging flow to
[30% adverse CNMT] maintain PRZR level.
IF PRZR level can NOT be maintained. THEN manually start SI pumps as necessary and go to ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.
EOP: TITLE:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE P PAGE 26 of 42 STEP ACTION/EXPECED RESPONSEREPNEOTBAID -
28 Check If SI ACCUMs Should Be Isolated:
- a. Check the following: a. Manually operate SI pumps as necessary and go to ECA-3.1.
o RCS subcooling based on core SGTR WITH LOSS OF REACTOR exit T/Cs - GREATER THAN 0F COOLANT - SUBCOOLED RECOVERY USING FIG-l.O. FIGURE MIN DESIRED. Step 1.
SUBCOOLING o PRZR level - GREATER THAN 5%
[30% adverse CNMT]
- MOV-841. MCC C position 12F
- MOV-865. MCC D position 12C
- c. Close SI ACCUM discharge valves c. Vent any unisolated ACCUMs:
- MOV-841 1) Open vent valves for
- MOV-865 unisolated SI ACCUMs.
- ACCUM A. AOV-834A
- ACCUM B. AOV-834B
- 2) Open HCV-945.
IF an accumulator can NOT be isolated or vented. THEN consult TSC to determine contingency actions.
- d. Locally reopen breakers for MOV-841 and MOV-865
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 29 Verify Adequate SW Flow To CCW Hx:
- a. Verify at least three SW pumps a. Manually start pumps as power RUNNING supply permits (257 kw each).
IF less than two SW pumps can be operated. THEN perform the following:
- 1) IF NO SW pumps running. THEN perform the following:
a) Pull stop any D/G that is NOT supplied by alternate cooling. AND immediately depress VOLTAGE SHUTDOWN pushbutton.
b) Refer to ATT-2.4.
ATTACHMENT NO SW PUMPS.
- 2) I only one SW pump running, THEN refer to AP-SW.2. LOSS OF SERVICE WATER.
- 3) Go to Step 36.
- b. Verify AUX BLDG SW isolation b. Manually align valves.
valves - AT LEAST ONE SET OPEN
- MOV-4615 and MOV-4734
- MOV-4616 and MOV-4735 This Step continued on the next page.
E-3 TITLE:
STEAM GENERATOR TUBE RUPTURE REV:
P 35 fJ l ~~~~~~~~~~~~~~PAGE 28 of 42l STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 29 continued from previous page)
- c. Verify CNMT RECIRC fan c. Perform the following:
annunciator C-2. HIGH TEMPERATURE ALARM - EXTINGUISHED 1) Determine required SW flow to CCW HXs per table:
SW DISCHARGE CCW HXs IN REQUIRED SW FLOW ALIGNMENT SERVICE Normal 2 Total of 5000 - 6000 gpm equally divided to both HXs Normal 1 5000 - 6000 gpm to in-service HX Alternate 2 30-33" d/p across each HX Alternate 1 95-100" d/p across in-service HX
o IF on normal SW discharge:
- V-4619, CCW Hx A
- V-4620. CCW Hx B
-OR-o IF on alternate SW discharge:
- V-4619C. CCW Hx A
- V-4620B, CCW Hx B
EOP: TM:IREV:35IE:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 29 of 42 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED 30 Check If Normal CVCS Operation Can Be Established
- a. Verify IA restored: a. Continue with Step 36. WHEN IA restored. THEN do Steps 30 o IA to CNMT (AOV-5392) - OPEN through 35.
o IA pressure - GREATER THAN 60 PSIG
- b. Verify instrument bus D - b. Energize MCC B. IF MCC B NOT ENERGIZED available, THEN perform the following:
- 1) Verify MCC A energized.
- 2) Place instrument bus D on maintenance supply.
- c. CCW pumps - ANY RUNNING c. Perform the following:
- 1) IF any RCP #1 seal outlet temperature offscale high.
THEN isolate CCW to thermal barrier of affected RCP(s).
- RCP A. MOV-749A and MOV-759A
- RCP B. MOV-749B and MOV-759B
- 2) Manually start one CCW pump.
- d. Charging pump - ANY RUNNING d. Continue with Step 36. WHEN any charging pump running. THEN do Steps 31 through 35.
STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 31 Check If Seal Return Flow Should Be Established:
- a. Verify RCP 1 seal outlet a. Go to Step 32.
temperature - LESS THAN 2350 F
- b. Verify RCP seal outlet valves - b. Manually open valves as.
OPEN necessary.
- AOV-270A
- AOV-270B
- c. Reset both trains of XY relays for RCP seal return isolation valve MOV-313
- d. Open RCP seal return isolation d. Perform the following:
valve MOV-313
- 1) Place MOV-313 switch to OPEN.
- 2) Dispatch AO to locally open MOV-313.
- e. Verify RCP #1 seal leakoff flow e. Perform the following:
- LESS THAN 6.0 GPM
- 1) Trip the affected RCP
- 2) Allow 4 minutes for pump coast down. THEN close the affected RCP seal discharge valve
- RCP A. AOV-270A
- GREATER THAN 0.8 GPM MALFUNCTION.
EOP: TITLE:
. ~~~~~~~~~~~~~~REV:
35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 31 of 42 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 32 Verify PRZR Level - GREATER Continue with Step 34. WHEN PRZR THAN 13% [40% adverse CNMT] level increases to greater than 13%
[40% adverse CNMT], THEN do Step 33.
33 Establish Normal Letdown: IF RCP seal return has been established. THEN establish excess
- a. Establish charging line flow to letdown as follows:
REGEN Hx - GREATER THAN 20 GPM o Place excess letdown divert
- b. Place the following switches to valve. AOV-312. to NORMAL.
CLOSE:
o Ensure CCW from excess letdown
- Letdown orifice valves open. (AOV-745).
(AOV-200A. AOV-200B. and AOV-202) o Open excess letdown isolation
- Letdown isolation valve AOV-371 valve AOV-310.
- Loop B cold leg to REGEN Hx AOV-427 o Slowly open HCV-123 to maintain excess letdown temperature less
- c. Place letdown controllers in than 1950F and pressure less MANUAL at 40% open than 100 psig.
- TCV-130 o Adjust charging pump speed as
- PCV-135 necessary.
- d. Reset both trains of XY relays IF RCP seal return NOT established.
for AOV-371 and AOV-427 - THEN consult TSC to determine if excess letdown should be placed in
- e. Open AOV-371 and AOV-427 service.
- f. Open letdown orifice valves as necessary
- g. Place TCV-130 in AUTO at 105°F
- h. Place PCV-135 in AUTO at 250 psig
- i. Adjust charging pump speed and HCV-142 as necessary
EOP:
E-3 I.
TITLE:
STEAM GENERATOR TUBE RUPTURE 35
~~~~~~~~~~~~~~REV:
RVJ
-~~~~~~~~. . PAGE 32 of 42 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED I 34 Check VCT Makeup System:
- a. Adjust boric acid flow control valve in AUTO to 9.5 gpm
- b. Adjust RMW flow control valve in AUTO to 40 gpm
- c. Verify the following: c. Adjust controls as necessary.
- 1) RMW mode selector switch in AUTO
- 2) RMW control armed - RED LIGHT LIT
o Level - GREATER THAN 20%
- 1) Ensure BA transfer pumps and
-OR- RMW pumps running. IF NOT.
THEN reset MCC C and CC D UV o Level - STABLE OR INCREASING lockouts as necessary.
- 2) Place RMW flow control valve HCV-l11 in MANUAL and increase RMW flow.
- 3) Increase boric acid flow as necessary.
EOP: TITLE: REV: 35 li E-3 STEAM GENERATOR TUBE RUPTURE l 33 of 42
.PAGE ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED 1 35 Check Charging Pump Suction Aligned To VCT:
- a. VCT level - GREATER THAN 20% a. IF.VCT level can NOT be maintained greater than 5%. THEN perform the following:
- 1) Ensure charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed
- 2) Continue with Step 36. WHEN VCT level greater than 40%.
THEN do Step 35b.
- b. Verify charging pumps aligned to b. Manually align valves as VCT necessary.
o LCV-112C - OPEN o LCV-112B - CLOSED
SP ACTION/EXPECTED RESPONSE l lRESPONSE NOT OBTAINED 4 * * * *
- 4 *4 * *4 *4 4 4 *
- 44
- 44 4 *4 **4 * *
- 44 * *
- 4 4 *
- 4 44 4
- *4 * *4
- 4 4 *
- 4 * * *
- 4
- 44* 4 4 4 4 4 4.4 *4 44 4
- 36 Control RCS Pressure And Charging Flow To Minimize RCS-To-Secondary Leakage:
- a. Perform appropriate action(s) from table:
PRZR RUPTURED SIG NARROW RANGE LEVEL LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13% o Increase Increase o Increase
[40% ADVERSE CNMT] charging flow charging charging flow flow o Depressurize RCS o Maintain RCS and using Step 36b ruptured S/G pressure equal BETWEEN 13% Depressurize RCS Energize Maintain RCS and
[40% ADVERSE CNMT] using Step 36b PRZR ruptured S/G AND 50% heaters pressure equal BETWEEN 50% AND 75% o Depressurize RCS Energize Maintain RCS and
[65% ADVERSE CNMT] using Step 36b PRZR ruptured S/G heaters pressure equal o Decrease charging flow GREATER THAN 75% o Decrease Energize Maintain RCS and
[65% ADVERSE CNMT] charging flow PRZR ruptured S/G heaters pressure equal
- b. Control pressure using normal b. IF letdown is in service. THEN PRZR spray. if available. to use auxiliary spray (AOV-296).
obtain desired results for IF NOT. THEN use one PRZR PORV.
Step 36a
EOP: TML:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE E -. < PAGE 35 of 42 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I STP 37 Monitor If CNMT Spray Should Be Stopped:
- a. CNMT spray pumps - ANY RUNNING a. Go to Step 38.
- b. Verify CNMT pressure - LESS THAN b. Continue with Step 38. WHEN 4 PSIG CNMT pressure less than.4 psig, THEN do Steps 37c through f.
- c. Reset CNMT spray
- d. Check NaOH flow (FI-930) - NO d. Place NaOH tank outlet valve FLOW switches to CLOSE.
- AOV-836A
- AOV-836B
- e. Stop CNMT spray pumps and place in AUTO
- f. Close CNMT spray pump discharge valves
- MOV-860A
- MOV-860B
- MOV-860C
- MOV-860D
- ~~~~~~~~~~~~~~
EMP: TIR1E:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE l ~~~~~~~~~~~~~~PAGE 36 of 42 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 38 Check If Emergency D/Gs Should Be Stopped:
- a. Verify AC emergency busses a. Try to restore offsite power energized by offsite power: (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER).
o Emergency DIG output breakers
- OPEN o AC emergency bus voltage -
GREATER THAN 420 VOLTS o AC emergency bus normal feed breakers - CLOSED
- b. Stop any unloaded emergency DIG and place in standby (Refer to ATT-8.1. ATTACHMENT D/G STOP) 39 Minimize Secondary System Contamination:
- a. Isolate reject from hotwell to a. IF hotwell level increasing.
CST: THEN direct RP to sample hotwells for activity.
o Place hotwell level controller (LC-107) in MANUAL at 50%
o Verify hotwell level - STABLE
- b. Check status of local actions to complete ruptured S/G isolation (Refer to ATT-16.0. ATTACHMENT RUPTURED SG)
EGI': TIRE:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE P PAGE 37 of '42l ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 40 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure 41 Check RCP Cooling: Establish normal, cooling to RCPs (Refer to ATT-15.2, ATTACHMENT SEAL
o Annunciator A-7, RCP 1A CCW RETURN HIGH TEMP OR LOW FLOW
- EXTINGUISHED o Annunciator A-15. RCP B CCW RETURN HIGH TEMP OR LOW FLOW
- EXTINGUISHED
- b. Check RCP seal injection:
o Labyrinth seal D/Ps - GREATER THAN 15 INCHES OF WATER
-OR-o RCP seal injection flow to each RCP - GREATER THAN 6 GPM
E: P TITLE: REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 38 of' 42 STEP ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINEDl h 4 4
- 4 *
- X 4 * * * *
- 4 4 4 *
- 4 4 4
- 4 4
- 4 4 * *
- 4 * * * * * * * *
- CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.
4
- 4 0 4 4
- S*
- t* * *
- 0 4 0
- 4 * * * * * * * *
- 0 0
- 4 0*
- 0 *
- 42 Check RCP Status
- b. Ensure conditions for starting b. IF conditions can NOT be met.
an RCP. THEN perform the following:
o Bus 11A or 11B energized. 1) Verify natural circulation (Refer to ATT-13.0.
o Refer to ATT-15.0, ATTACHMENT ATTACHMENT NC).
RCP START.
IF natural circulation can NOT be verified. THEN increase dumping steam.
- 2) Go to step 43.
This Step continued on the next page.
EP: TITLE: REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 39 of 42 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED]
(Step 42 continued from previous page)
- c. Check RVLIS level (no RCPs) c. IF RVLIS level (no RCPs) less 2 95% than 95%. THEN perform the following:
o Increase PRZR level to greater than 65% [82% adverse CNMT].
o Dump steam to establish RCS subcooling based on core exit T/Cs to greater than 20°F using FIG-1.0, FIGURE IN SUBCOOLING.
o Energize PRZR heaters as necessary to saturate PRZR water IF conditions NOT met. THEN continue with step 43. WHEN conditions met. THEN do step 42d.
THEN verify natural circulation (Refer to ATT-13.0, ATTACHMENT NC).
IF natural circulation can NOT be verified. THEN increase dumping steam.
FEOP:Il TITLE: RV REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE l PAGE 40 of 42 STP ACTION/EXPECTED RESPONSE REPNENTOTIE NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.
43 Check If Source Range Detectors Should Be Energized:
- a. Source range channels - a. Go to Step 43e.
DEENERGIZED
- b. Check intermediate range flux - b. Perform the following:
EITHER CHANNEL LESS THAN 10-10 AMPS 1) IF neither intermediate range channel is decreasing. THEN initiate boration.
- 2) Continue with Step 44. WHEN flux is LESS THAN 10-10 amps on any operable channel. THEN do Steps 43c through e.
- c. Check the following: c. Continue with Step 44. WHEN either condition met. THEN do o Both intermediate range Steps 43d and e.
channels - LESS THAN 10-10 AMPS
-OR-o Greater than 20 minutes since reactor trip
- d. Verify source range detectors -- d. Manually energize source range ENERGIZED detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).
IF source ranges can NOT be restored, THEN refer to ER-NIS.l. SR MALFUNCTION and go to Step 44.
- e. Transfer Rk-45 recorder to one source range and one intermediate range channel
EOP: TITLE:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE l ~~~~~~~~~~~~~~PAGE 41 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 44 Establish Normal Shutdown Alignment:
- a. Check condenser - AVAILABLE a. Dispatch AO to perform ATT-17.1, ATTACHMENT SD-2.
- b. Perform the following:
o Open generator disconnects
- 1G13A71
- 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cam to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump
- c. Verify adequate Rx head cooling:
- 1) Verify at least one control 1) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw)
- 2) Verify one Rx compartment 2) Perform the following:
cooling fan - RUNNING o Dispatch AO to reset UW relays at NCC C and MCC D.
o Manually start one fan as power supply permits (23 kw)
- d. Verify ATT-17.0. ATTACHMENT SD-1
- COMPLETE
.EW: - TIRE:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE P
, _ ~~~~~~~~~~~~~PAGE 42 of 42l STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 45 Consult TSC To Determine Appropriate Post-SGTR Cooldown Procedure:
o Go to ES-3.1. POST-SGTR COOLDOWN USING BACKFILL. Step 1
-OR-o Go to ES-3.2. POST-SGTR COOLDOWN USING BLOWDOWN, Step 1
-OR-o Go to ES-3.3. POST-SGTR COOLDOWN USING STEAM DUMP. Step 1
-END-
EOP: TITLE:. Ed: ~~~~~~~~~~~~REV: RV 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of l E-3 APPENDIX LIST TITLE
- 1) RED PATH
SUMMARY
- 2) FIGURE MIN SUBCOOLING (FIG-i.0)
- 3) ATTACHMENT CNMT RECIRC FANS (ATT-4.0)
- 4) ATTACHMENT D/G STOP (ATT-8.1)
- 5) ATTACHMENT N2 PORVS (ATT-12.0)
- 6) ATTACHMENT NC (ATr-13.0)
- 7) ATTACHMENT SEAL COOLING (ATT-15.2)
- 8) ATTACHMENT RCP START (ATT-15.0)
- 9) ATTACHMENT RUPTURED SG (ATT-16.0)
- 10) ATTACHMENT SD-1 (AT-17.0)
- 11) ATTACHMENT SD-2 (ATT--17.1)
- 12) ATTACHMENT NO SW PUMPS (ATT-2.4)
- 13) ATTACHMENT LOSS OF OFFSITE POWER (ATT-8.5)
- 14) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)
- 15) FOLDOUT
EOP: TITLE: REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 RED PATH
SUMMARY
- a. SUBCRITICALITY - Nuclear power greater than 5%
- b. CORE COOLING - Core exit T/Cs greater than 12000F
-OR-Core exit T/Cs greater than 7000F AND RVLIS level (no RCPs) less than 52% [55%
adverse CNMT]
- c. HEAT SINK - Narrow range level in all S/Gs less than 5%
[25% adverse CNMT] AND total feedwater flow less than 200 gpm
- d. INTEGRITY - Cold leg temperatures decrease greater than 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F
- e. CONTAINMENT - CNMT pressure greater than 60 psig
EOP: TITLE:
REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 FOLDOUT PAGE
- a. Pull stop any DG that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
- b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
- 2. SI REINITIATION CRITERIA Following SI termination, IF either condition listed below occurs, THEN start SI pumps manually as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o RCS subcooling based on core exit T/Cs - LESS THAN F USING REQUIREMENTS OF FIG-1.0, FIGURE MIN SUBCOOLING.
OR o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% [30% adverse CNMT].
- 3. SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1, UNLESS faulted S/G needed for RCS cooldown.
- 4. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
- 5. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
- 6. MULTIPLE SG TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled manner OR IF any intact S/G has abnormal radiation, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.