ML043420203
| ML043420203 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/19/2004 |
| From: | Marlow T Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML043420203 (29) | |
Text
1503 Lake Road Ontario, New York 14519-9364 585.771.3000 Constellation Energy R.E. Ginna Nuclear Power Plant, LLC November 19, 2004 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, Thomas A. Marlow TAM/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-1, Rev 31 A- C)t
( C (
NPSP0200 Ginna Nuclear Power Plant Fri 11/19/2004 10:22:23 am E66429 PROCEDURE INDE) Page 1 of I INPUT PARAMETERS: TYPE: PRE STATUS VALUE(S): EF, QU 5 YEARS ONLY: .1 PRE EMERGENCY PROCEDURE -
PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST E-0 REACTOR TRIP OR SAFETY INJECTION 037 1111712004 03/2412003 0312412008 EF E-1 LOSS OF REACTOR OR SECONDARY COOLANT 031 11/19/2004 03/24/2003 03/2412008 EF E-2 FAULTED STEAM GENERATOR ISOLATION 012 11/17/2004 03124/2003 0312412008 EF E-3 STEAM GENERATOR TUBE RUPTURE 038 11/17/2004 03124/2003 03/2412008 EF PRE TOTAL: 4 GRAND TOTAL: 4
IEOP: - TITLE:
REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT
, .PAGE 1 of 23 GINNA STATION CONTROLLED COPY NUMBER ___
RESPONSIB O MANAGER
// EF-/ -00T EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:_
geO: lTITL: - REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 2 of 23 A. PURPOSE - This procedure provides actions to recover from a loss of reactor or secondary coolant.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS - This procedure is entered from:
- a. E-0, REACTOR TRIP OR SAFETY INJECTION, and FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when a PRZR PORV is stuck open and its block valve can not be closed.
- b. E-0, REACTOR TRIP OR SAFETY INJECTION, with any of the following symptoms: high containment radiation, high containment pressure, or high containment recirculation sump level.
- c. E-0, REACTOR TRIP OR SAFETY INJECTION, ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, and FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when RCS pressure is less than the shutoff head pressure of the RHR pumps or is decreasing.
- d. ES-1.1, SI TERMINATION, and FR-I.2, RESPONSE TO LOW PRESSURIZER LEVEL, if SI has to be reinitiated.
- e. E-2, FAULTED STEAM GENERATOR ISOLATION, after identification and isolation of a faulted S/G.
- f. ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, after normal injection mode conditions are established.
- h. FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, and FR-C.2, RESPONSE TO DEGRADED CORE COOLING, after core cooling has been reestablished.
- i. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, after secondary heat sink has been reestablished and all PRZR PORVs are closed.
EOP: TIT:REV:I
. REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT
- PAGE 3 of 23 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED CAUTION IF RWST LEVEL DECREASES TO LESS THAN 28%. THEN THE SI SYSTEM SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING ES-1.3. TRANSFER TO COLD LEG RECIRCULATION, STEP 1.
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 Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.O. 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 S/G c. Go to Step 2. -
pressure - LESS THAN 175 psig
[400 psig adverse CNMT]
- d. Stop both RCPs
ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 2 Check If S/G Secondary Side IF any S/G pressure decreasing in Is Intact: an uncontrolled manner OR completely depressurized. THEN o Pressure in both S/Gs - STABLE verify faulted SIG isolated unless OR INCREASING needed for RCS cooldown:
o Pressure in both S/Gs - GREATER
- Steamlines THAN 110 PSIG
- Feedlines IF NOT. THEN go to E-2. FAULTED STEAM GENERATOR ISOLATION. Step 1.
NOTE: TDAEW pump flow control AOVs may drift open on loss of IA.
- 3 Monitor Intact S/G Levels:
- a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 7% [25% adverse CNMT] than 200 gpm until narrow range level greater than 7% [25%
adverse CNMT] in at least one S/G.
- b. Control feed flow to maintain b. IF narrow range level in any S/G narrow range level between 17% continues to increase in an
[25% adverse CNMT] and 50% uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE. Step 1.
- 4 Monitor If Secondary IF cteamline radiation monitors NOT Radiation Levels Are Normal available. THEN dispatch AO to locally check steamline radiation.
o Steamline radiation monitor (R-31 and R-32) IF abnormal radiation levels detected in any S/G. THEN go to o Request RP sample S/Gs for E-3. STEAM GENERATOR TUBE RUPTURE.
activity Step 1.
EOP: TIfLE:
REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 5 of 23 STP ACTION/EXPECTED RESPONSE lRESPONSE 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 5B).
- 5 Monitor PRZR PORV Status:
- a. Power to PORV block valves a. Restore power to block valves AVAILABLE unless block valve was closed to isolate an open PORV:
- MOV-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 dispatch AO to locally check breaker.
. MOV-515. MCC D position 6C
- MOV-516. MCC C position 6C
- c. Block valves - AT LEAST ONE OPEN c. Open one block valve unless it was closed to isolate an open PORV.
' EOP: - TITLE:
REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 6 of 23 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl
_* * * *- * *
- _* * * * * * * * * * * * * * * * * *
- t * * * * *
- 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 OFESITE POWER) 6 Reset SI 7 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: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 7 of 23 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 8 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 perform the following:
- 1) Ensure SW isolation.
- 2) 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 associated 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-17.0. ATTACHMENT SD-1)
EOP: TITLE:
REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 8 of 23 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED 9 Establish IA to CNMT:
- a. Verify non-safeguards busses a. Perform the following:
energized from offsite power
- 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).
- 3) WHEN bus 15 restored. THEN reset control room lighting.
- 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 9d.
This Step continued on the next page.
ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED]
(Step 9 continued from previous page) -
- c. Verify turbine building SW c. Perform the following:
isolation valves - OPEN
- 1) Manually align valves.
- MOV-4613 and MOV-4670
- MOV-4614 and MOV-4664 2) Dispatch AO to locally reset compressors as necessary.
- d. Verify adequate air compressors d. Manually start electric air
- RUNNING compressors as power supply permits (75 kw each). IF electric air compressors can NOT be started. THEN start diesel air compressor (refer to ATT-l1.2. ATTACHMENT DIESEL AIR COMPRESSOR).
- 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 10. WHEN IA restored. THEN do Steps 9f and g.
EOP: TITE: REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 10 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check Normal Power Available Verify adequate emergency D/G To Charging Pumps: capacity to run charging pumps (75 kw each).
o Bus 14 normal feed breaker -
CLOSED IF NOT. THEN evaluate if CNMT RECIRC fans can be stopped (Refer o Bus 16 normal feed breaker - to ATT-4.0. ATTACHMENT CNMT RECIRC CLOSED FANS).
EOP: TITLE: REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 11 of 23 11 Check If Charging Flow Has Been Established:
- 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 close seal injection needle valve(s) to affected RCP:
. V-300A for RCP A
- V-300B for RCP B
- 2) Ensure HCV-142 open, demand at 0%.
- b. Charging pump suction aligned to b. Manually align valves as RWST: necessary.
o LCV-112B - OPEN IF LCV-112B can NOT be opened.
THEN dispatch AO to locally open o LCV-112C - CLOSED V-358. manual charging pump suction from RWST (charging pump room).
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 adjust charging flow to restore PRZR level
EOP: TITLE:
. LREV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 12 of 23 ACTION/EXPECTED RESPONSEINED 12 Check If SI Should Be Terminated:
o Pressure - GREATER THAN 1625 psig [1825 psig adverse CNMT]
o Pressure - STABLE OR INCREASING
- b. RCS subcooling based on core . b. Do NOT stop SI pumps. Go to exit T/Cs - GREATER THAN 0 0F Step 13.
USING FIG-l.O. FIGURE MIN SUBCOOLING
- c. Secondary heat sink: c. IF neither condition satisfied.
THEN do NOT stop SI pumps. Go o Total feed flow to intact to Step 13.
S/Gs - GREATER THAN 200 GPM
-OR-o Narrow range level in at least one intact S/G -
GREATER THAN 7% [25% adverse CNMTI
- d. PRZR level - GREATER THAN 10% d. Do NOT stop SI pumps. Perform
[30% adverse CNMT] the following:
- 1) IF normal PRZR spray available. THEN try to stabilize RCS pressure with PRZR spray.
- 2) Go to Step 13.
EOP: TITLE:
. REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 13 of 23 i i... -A _,,
ACTIO/EECTED RESPONSEOT OBTAINED
- 13 Monitor If CNMT Spray Should Be Stopped:
- a. CNMT spray pumps - RUNNING a. Go to Step 14.
- b. Check the following: b. Continue with Step 14. WHEN BOTH conditions satisfied, THEN o CNMT pressure - LESS THAN do Steps 13c through f.
4 PSIG o Sodium hydroxide tank level -
LESS THAN 55%
- c. Reset CNMT spray
- d. Check NaOH flow (EI-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
. . . i -; .. -
EOP: TITLE:
[EUP:REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 14 of 23
.I; X . ._ , . ;.-
TE ACTION/EXPECTED RESPONSE l lRESPONSE NOT OBTAINEDl CAUTION o IF OFESITE POWER IS LOST AFTER SI RESET. THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5. ATTACHMENT LOSS OF OFESITE POWER) o 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.
- 14 Monitor If RHR Pumps Should Be Stopped:
- a. RHR pumps - ANY RUNNING IN a. Go to Step 15.
INJECTION MODE
- b. Check RCS pressure:
- 1) Pressure - GREATER THAN 1) Go to Step 16.
250 psig [465 psig adverse CNMT]
INCREASING
- a. Check pressures in both S/Gs - a. Return to Step 1.
STABLE OR INCREASING
- b. Check pressures in both S/Gs - b. Monitor RCS pressure. IF RCS GREATER THAN 110 PSIG pressure does NOT increase after faulted S/G dryout, THEN go to Step 16.
DECREASING
EON: TILEREV:31 REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT
.OP .E PAGE 15 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Check If Emergency D/Gs Should Be Stopped:
- a. Verify AC emergency busses a. Perform the following:
energized by offsite power:
- 1) Close non-safeguards bus tie o Emergency D/G output breakers breakers as necessary:
- OPEN
- Bus 13 to Bus 14 tie o AC emergency bus voltage -
- Bus 15 to Bus 16 tie GREATER THAN 420 VOLTS
- 2) Place the following pumps in o AC emergency bus normal feed PULL STOP:
breakers - CLOSED
- EH pumps
- Turning gear oil pump
- HP seal oil backup pump
- 3) Ensure condenser steam dump mode control in MANUAL.
- 4) Restore power to MCCs:
- A from Bus 13
- B from Bus 15
- E from Bus 15
- F from Bus 15
- 5) Start HP seal oil backup pump.
- 6) Ensure D/G load within limits.
- 7) WHEN bus 15 restored. THEN reset control room lighting breaker.
- 8) Refer to ATT-8.4. ATTACHMENT SI/UV for other equipment lost with loss of offsite power.
- 9) Try to restore offsite power (Refer to ER-ELEC.1.
RESTORATION OF OFFSITE POWER).
- b. Stop any unloaded emergency D/G and place in standby (Refer to ATT-8.1, ATTACHMENT D/G STOP)
STE P ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Check If RHR Should Be Throttled:
- a. Check RWST level - LESS THAN 70% a. Continue with Step 18. WHEN RWST level less than 70%. THEN perform step 17b.
- b. Perform ATT-14.7. ATTACHMENT b. Manually adjust RHR Hx outlet ADJUST RHR FLOW to locally valves equally to reduce flow to adjust HCV-624 and HCV-625. lees than 1500 gpm per operating pump
- RHR Hx A. HCV-625
- RHR Hx B. HCV-624
EOP: TITE:
REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT
. . PAGE 17 of 23 4, . ~.
SE ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINEDl 18 Verify CNMT Sump Recirculation Capability:
- 1) At least one recirculation NOT be verified. THEN go to flowpath. including required ECA-l.l. LOSS OF EMERGENCY power supplies, from Sump B COOLANT RECIRCULATION. Step 1.
and back to RCS available per ATT-14.5. ATTACHMENT RHR SYSTEM
- 2) At least one CCW pump available.
- 3) At least one CCW Hx available.
- b. Check SW pumps - AT LEAST 2 b. Attempt to restore at least 2 SW PUMPS AVAILABLE pumps to operable.
IF only 1 SW pump available.
THEN refer to ATT-2.1.
ATTACHMENT MIN SW for additional guidance.
IF no SW pumps are available.
THEN perform the following:
- 1) Pull stop any D/G that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
- 2) Refer to ATT-2.4. ATTACHMENT NO SW PUMPS.
- 3) Go to ECA-1.1. LOSS OF EMERGENCY COOLANT RECIRCULATION.
- c. Dispatch AO to check AUX BLDG c. IF any RHR pump seal leakage sub-basement for RUR system indicated. THEN leakage should leakage (AUX BLDG sub-basement be evaluated and isolated if key may be required) necessary.
EOP: TITE:
REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT .
PAGE 18 of 23 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 19 Evaluate Plant Status:
- a. Check auxiliary building a. Notify RP and refer to radiation - NORMAL appropriate AR-RMS procedure.
- Plant vent particulate (R-13) inventory outside CNMT. THEN go
. Plant vent gas (R-14) to ECA-1.2. LOCA OUTSIDE CONTAINMENT. Step 1.
- CCW liquid monitor (R-17)
- LTDN line monitor (R-9)
- CHG pump room (R-4)
- b. Direct RP to obtain following samples:
- RCS activity
- 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 UV relays at MCC C and MCC D.
o Manually start one fan as power supply permits (23 kw)
I EOP: TITLE: R REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 19 of 23 b . .
SE ACTION/EXPECTED RESPONSE REPNENTOTIE 20 Check If RCS Cooldown And Depressurization Is Required:
- a. RCS pressure - GREATER THAN a. IF RHR pump flow greater than 250 psig [465 psig adverse CNMT1 475 gpm. THEN go to Step 21.
[
EOP:
E-1 TITUE:
l LOSS OF REACTOR OR SECONDARY COOLANT
. REV: 31 PAGE 20 of 23 STP ACTION/EXPECTED RESPONSE 1 RESPONSE NOT OBTAINED NOTE: IF DIGs supplying emergency AC busses. THEN non-essential loads may be shed as necessary to allow start of additional SW pumps.
21 Establish Adequate SW Flow:
- a. Verify at least two SW pumps - a. Start additional SW pumps as RUNNING power supply permits (257 kw each). IF only 1 SW pump operable. THEN perform the following:
- 1) Ensure ATT-2.1, ATTACHMENT MIN SW is in progress.
- 2) Go to Step 22.
IF no SW pumps are available, THEN perform the following:
- 1) Pull stop any D/G that is NOT supplied by alternate cooling. AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
- 2) Refer to ATT-2.4. ATTACHMENT NO SW PUMPS.
- 3) Go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION.
- b. Verify AUX BLDG SW isolation b. Manually align valves.
valves - OPEN
- MOV-4615 and MOV-4734
. MOV-4616 and MOV-4735
- IN SERVICE service This Step continued on the next page.
EOP:. TITLE:
REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 21 of 23 ACTION/EXPECTED RESPONSE STE lRESPONSE NOT OBTAINEDl (Step 21 continued-from previous page) -
SW DISCHARGE CCW HXs IN REQUIRED SW FLOW ALIGNMENT SERVICE Normal 2 Total of 5000 - 6000 gpm equally divided to both HXe 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
- e. Direct AO to adjust SW flow to e. IF the required SW flow can NOT required value be obtained. THEN perform the following:
o IF on normal SW discharge:
- 1) Isolate SW to screenhouse and
. V-4619. CCW HX A air conditioning headers.
. MOV-4609/MOV-4780 - AT
-OR- LEAST ONE CLOSED
. MOV-4663/MOV-4733 - AT o IF on alternate SW discharge: LEAST ONE CLOSED
- SEP Hx B (V-8689)
- 4) Verify SW portions of ATT-17.0. ATTACHMENT SD-1 are complete.
. EO: 'TITLE:-:
.I .:REV: 31
- E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 22 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Establish CCW flow to RHR Hxs
- a. Check both CCW pumps - RUNNING a. Perform the following:
- 1) Start CCW pumps as power supply permits (122 kw each)
- 2) IF both CCW pumps are running. THEN go to step 22b.
- 3) IF only one CCW pump is running. THEN perform the following:
a) Direct AO to isolate CCW to boric acid evaporator o Close V-760A b) Manually open CCW MOV to only one operable RHR Loop o Open MOV-738A
-OR-o Open MOV-738B c) Go to step 23.
- MOV-738A
. MOV-738B
EOP: TITLE:
REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 23 of 23 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED 23 Check If Transfer To Cold Leg Recirculation Is Required:
- a. RWST level - LESS THAN 28% a. Return to Step 17.
- b. Go to ES-1.3. TRANSFER TO COLD LEG RECIRCULATION. Step 1
-END-
EOP: TITLE: REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 1 E-1 APPENDIX LIST TITLE
- 1) RED PATH
SUMMARY
- 2) FIGURE MIN SUBCOOLING (FIG-1.0)
- 3) ATTACHMENT CNMT RECIRC FANS (ATT-4.0)
- 4) ATTACHMENT D/G STOP (ATT-8.1)
- 5) ATTACHMENT SD-1 (ATT-17.0)
- 6) ATTACHMENT SI/UV (ATT-S.4)
- 7) ATTACHMENT MIN SW (ATT-2.1)
- 8) ATTACHMENT NO SW PUMPS (ATT-2.4)
- 9) ATTACHMENT LOSS OF OFFSITE POWER (ATT-8.5)
- 10) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)
- 11) ATTACHMENT RHR SYSTEM (ATT-14.5)
- 12) ATTACHMENT ADJUST RHR FLOW (AlT-14.7)
- 13) FOLDOUT
EOP: TITLE: - REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT 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 7% I
[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: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 2 FOLDOUT PAGE
- a. Si pumps - AT LEAST TWO RUNNING
- a. Pull stop any D/G that is NOT supplied by alternate cooling,AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
- b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
- 3. SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually start SI pumps as necessary:
o RCS subcooling based on core exit T/Cs - LESS THAN 0e F USING FIGURE MIN SUBCOOLING
-OR-o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 10% [30% adverse CNM
- 4. Si TERMINATION CRITERIA IF ALL conditions listed below occurTHEN go to ES-1.1, SI TERMINATION, Step 1:
a; RCS subcooling based on core exit T/Cs - GREATER THAN 0' F USING FIGURE MIN SUBCOOLING
- b. Total feed flow to intact S/Gs - GREATER THAN 200 GPM
-OR-Narrow range level in at least one intact S/G - GREATER THAN 7% [25% adverse CNMT]
- c. RCS pressure:
o GREATER THAN 1625 PSIG [1825 psig adverse CNMT]
o STABLE OR INCREASING N
- d. PRZR level - GREATER THAN 10% [30% adverse CNMT]
- 5. SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurizedAND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.
- 6. E-3 TRANSITION CRITERIA IF any S/G level increased in an uncontrolled manner or any S/G has abnormal radiation.THEN manually start SI pumps as necessaryAND go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
EOP: TITLE:
REV: 31 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 2 of 2