ML20209J264
| ML20209J264 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/08/1985 |
| From: | PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20209J234 | List: |
| References | |
| PROC-850408-02, NUDOCS 8511110418 | |
| Download: ML20209J264 (703) | |
Text
{{#Wiki_filter:. _ _ PGandE Letter No.: DCL-85-141 4 CUPRENT O' EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS Volume 3A TITLE REV E-0 Reactor Trip or Safety Injection 0 E-0.1 Reactor Trip Response 0 i E-0.2 Natural Circulation Cooldown 0 E-0.3 Natural Circulation Cooldown with Steam Void in Vessel 0 (with RVLIS) E-0-4 Natural Circulation Cooldown with Steam Void in Vessel 0 (Without RVLIS) E-1 Loss of Reactor or Secondary Coolant 0 E-1.1 SI Termination 0 E-1.2 Post LOCA Cooldown and Depressurizction 0 E-l.3 Transfer to Cold Leg Recirculation 0 Transfer to Eot Leg Recirculation
]v E-1.4 E-2 E-2.1 Fac1ted Steam Generator Isolation Alternate Auxiliary Feedwater Supplies 0
0 0 E-3 Steam Generator Tube Rupture 0 ECA-0.0 Loss of All AC Power 0
- ECA-0.1 Loss of All AC Power hcovery Without SI Required 0-ECA-0.2 Loss of All AC Power i;ecovery with SI Required 0 ECA-0.3 Restore Vital Bus 0 i
EcA-1.1 Loss of Emergency Coolant Recirculation 0 l ECA-1.2 LOCA Outside Containment 0 ECA-2.1 Uncontrolled Depressurization of All Steam Generators 0 , ECA-3.1 SGTR With Loss of Reactor Coolant-Subcooled Recovery Desire 0 ECA-3.2 SGTR with Loss of Reactor Coolant - Saturated Pecovery Desired 0 ECA-3.3 SGTR Without Pressurizer Pressure Control 0 F-0 Critical Safety Function Status Trees 0
- FR-S.1 Response to Nuclear Power Generation /ATWS 0 FR-S.2 Response to Loss of Core Shutdown -
0 FR-C.1 Response to Inadequate Core Cooling 0 FR-C.2 Response to Degraded Core Cooling 0 FR-C.3 Response to Saturated Core Conditions 0 FR-H.1 Response to Loss of Secondary Heat Sink 0 FR-H.2 Response to Steam Generator Overpressure 0 FR-H.3 Response to Steam Generator High Level 0 FR-H.4 Response to Loss of Normal Steam Release Capabilities 0 O 0502d/0005K 04/08/85 l o41s esO40s
@21jDOCK05000275 p
i PDR l
F TABLE OF CONTENTS (Continued) FR-H.5 Response to Steam Generator Low Level 0 FR-P.1 Response to Imminent Pressurized Thermal Shock Condition 0 FR-P.2 Response to Anticipated Pressurized Thermal Shock Condition 0 FR-Z.1 Response to High Containment Pressure 0 FR-Z.2 Response to Containment FlooCng 0 FR-Z.3 Response to High Containment Radiation Level 0 FR-I.1 Response to High Pressurizer Level 0 FR-I.2 Response to Low Pressurizer Level 0 Fr-I.3 Response to Voids in Reactor Vessel 0 R-1 Personnel Injury or Illness (Radiologically Pelated) 14 and/or Overexposure R-2 Release of Airborne Radioactive Materials 5 R-3 Release of Radioactive Liquids 4 R-4 High Radiation (In Plant) 3 R-5 Radioactive Liquid Spill 3 P-6 Radiological Fire 8 R-7 Offsite Transportation Accidents 5 M-1 Employee Injury or Illness (Nonradiological) 12 M-2 Nonemployee Injury or Illness (Third Party) 10 M-3 Chlorine Release 5 M-4 Earthquake 8 M-5 Tsunami Warning 5 M-6 Nonradiological Fire 10 M-7 011 Spill Isolation and Clean Up Procedure 6 M-8 Containment Emergency Personnel Hatch 0 s M-9 Hazardous Waste Management Contingeacy Plan 1 M-10 Fire Protection of Safe Shutdown Equipment 3 G-1 Accident Classification and Emergency Plan Activation 5 G-2 Establishment of the On-Site Emergency Organization 6 G-2 S1 Emergency Organization Call List Form 69-10297 1 G-3 Notification of Off-Site Organizations 5 G4 Personnel Accountability and Assembly 5 G-5 Evacuation of Nonessential Site Personnel 2 i i 4
' 0502d/0005K 04/08/8e
NUMBER EP E-0
)
7 39/3 Pacific Gas and Electric Company REVISION 0 l DATE 3/8/85 DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 17 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE .. I TITLE . REACTOR TRIP OR SAFETY INJECTION IMPORTANT APPROVED Td TO PLANTMANAGERg) DATE SAFETY _ SCOPE This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of a reactor trip or safety injection, to assess plant conditions, and to identify the appropriate recovery procedure. This procedure and changes thereto require PSRC review. SYMPTCMS OR ENTRY CONDITIONS The following are symptoms that require a reactor trip, if one has not occurred: p) N,,
- 1. Annunciator PK04-11 or PK04-12, REACTOR TRIP INITIATED, in alarm, without annunciator PK04-14, REACTOR TRIP ACTUATED, in alarm.
- 2. Bistable lights on the Protection system status panel (VB2) indicates sufficient logic without a reactor trip.
- 3. Annunciator PK08-21, SAFETY INJECTION ACTUATION in alarm, without annunciator PK04-14, REACTOR TRIP ACTUATED, in alarm.
The following are symptom: at a reactor trip:
- 1. REACTOR TRIP ACTUATED annunciator in alarm (PK04-14).
- 2. Reactor trip and bypass breakers open.
- 3. Shutdown and control rods fully inserted. Rod bottom lights lit.
- 4. Rapid decrease in neutron flux level indicated by NIS.
The following are symptoms that require a reactor trip and safety injection, if one has not occurred:
- 1. Annunciator PK 02-2, SAFETY INJECTION INITIATE, in alarm, without annunciator PK 08-21, SAFETY INJECTION ACTUATION, in alarm .
r O DC0010 IX I
NUMBER EP E-0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 2 0F 17 m LE. REACTOR TRIP OR SAFETY INJECTION
- 2. Bistable lights on Safeguards status panel (V82) indicate sufficient logic for SI Initiation.
The following are some possible symptoms of safety injection:
- 1. SAFETY INJECTION ACTUATION annunciator in alarm (PK08-21).
- 2. Automatic actions of SI occurring:
Start Signals 150 Signals Go To: Go To: 51 Pp's Phase A valves CC Pp's Cont. Vent valves RHR Pp's FW valves (including CCW Pp's MFW Pp Trip) ASW Pp's Ncrmal Charging AFW Pp's CFCU's D/G's This procedure is entered from the foll wing procedures:
- 1. E-0.1, REACTOR iPIP RESPONSE, Step 1 CAUTION, if SI ACTUATION occurs during the procedure.
- 2. E-0.1, REACTOR TRIP RESPONSE, Step 5, when pressurizer pressure is less than 1850 psig and SI is required.
- 3. E-0.2, NATURAL CIRCULATI0h C00LDOWN, Step 1 CAUTION, if SI ACT' J ATION occurs during the procedure.
l 4. E-0.3,i!ATURAL CIRCULATION C00LDOWN WITH STEAM V0ID IN VESSEL (WITH RVL!S), Step 1 CAUTION, if SI ACTUATION occurs dering the procedure.
- 5. E-0.4, NATURAL CIRCULATION C00LDOWN WITH STEAM VOID IN VESSCL l (WITHOUT RVLIS), Step 1 CAUTION, if SI ACTUATION occurs during j the procedure.
I
- 6. FR-S.1, RESPONSE TO k'UCLEAR POWER GENERATI0h/ATWS, Step 1, when a j reactor trip is accomp?ished.
l l .. O 0C00010 2X I
NUMBER EP E-0 Os/ SLO CANYON POWEA PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 l PAGE 3 0F 17 Tirts. PEACTOR TRIP OR SAFETY INJECTION ACTION /EXECTED RESPONSE RESPONSE NOT OBTAINED NOTE: e IMMEDIAH ACTION steps are designated by circled steps. e Foldout page should be open. e The red actuates light on the CNMT Vent portion of Monitor Light Box B l has a 50 sec time delay. All red actuate lights on boxes B, C and 0 i have a 20 sec time delay. VERIFY Reactor Trip: (VB2/CC1) e Reactor trip and bypass bre ders Manually trip reactor.
. OPEN e Rod bottom lights - LIT IF reactor will NOT trip, o Neutron flux - DECREASING TiiEN go to FR-S.1,TESFONSE TO NUCLEAR POWER GENERATION /ATWS.
h VERIFY Turbine Trio: (CC3,VB2)
- a. Manually trip turbine.
- a. All four SVs CLOSED IF turbine will NOT trip, TfiEN close MSIVs and bypasses.
VEPIFY Vital 4KV Bus Status: (VB4)
- a. Verify all three vital 4KV a. E two vital busses are Duses F, G, and H energized,
- EhEPGIZED THEN refer to ECA-0.3, RESTORE VITAL BUS, while continuing in this procedure.
E only one vital bus is energized, THEN Lo to ECA-0.3, RESTORE VITAL BUS. IF all vital busses are de-energized, THEN Lo to ECA-0.0, LOSS OF ALL AC POWER. O DC00010 3X
l NUMBER EP E-0 ciAsto CANYON POWER PLANT UNIT NC(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 4 0F 17 TITLE. REACTOR TRIP OR SAFETY INJECTION O ACTION /EXhutu RESPONSE RESPONSE t0T OBTAINED CHECK If SI Is Actuated: (VB3)
- a. PK08-21, SAFETY INJECTI0h a. Check if SI required: (VB1)
ACTUATION annunciator - ON e PK02-2, SI INITIATE - ON. e Logic on safeguards bistable status light panel indicates symptom satisfied for SI initiation. IF SI required, TIIEN manually actuate. IF SI NOT required, TiiEN 90 to E-0.1, REACTOR TRIP RESPONSE. h VERIFY Containment Isolation Phase A: (V81) M nua actu t
- OR _
Paek
- a. Phase A portion of Monitor Light Box B: Manually close Phase A Iso vivs as necessary.
Red Activated Light - ON White Status Lights - 0FF h VERIFY Containment Vent Iso: (VB1)
- a. Containment Vent Iso portion of Manually actuate CVI Monitor Light Box B:
- OR _
Red Activated Light - ON White Status Lights - 0FF Manually close CVI vivs, as necessary. 0C00010 4X m
m a DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/8/85 5 0F 17 PAGE (#) TITLE REACTOR TRIP OR SAFETY INJECTION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED VERIFY ESF Pump and Valve Status: Manually start pumps and align (V51) vlvs as necessary. SI portion of Monitor Light Box C: Red Actuated Light - ON White Status Lights - 0FF VERIFY FW Isolation (VB1) Ma uakk chose vafves as necessary.
- a. FW isol portion of Monitor Light Box C:
Red Activated Light - ON White Status Lights - 0FF
- b. SG Ivl portion of Monitor Light Box C:
(d' Red Activated Light - ON White Status Lights - 0FF
- c. Place each MFW reg vivs in manual and run the demand to 0%
VERIFY Main Steamline Iso - NOT REQUIRED (VB1)
- a. Check Main Stream Isc portion of a. White status lights - 0FF Monitor Light Box D:
Manually close MSIV and Red Activated Light-0FF bypass vivs as necessary.
@ VERIFY Containment Spray and Phase B Iso - NOT REQUIRED: (VB1)
- a. Check Phase B portion of Monitor a. IF Phase B actuated, Light Box 0: TREN perform the following:
Red Activated light-OFF 1) Stop PD charging pp.
- 2) Verify white status lights are OFF.
^N 3) Open FCV 128 to provide (b
i seal injection flow. DC00010 SX
l NUMBER EP E-0 OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 6 0F 17 TITLE. REACTOR TRIP OR SAFETY INJECTION , ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l )
- 11. VERIFY ECCS Flow;
- a. BIT Flow, FI-917 - CHECK FOR a. e Verify ECCS valve FLOW (VB2) alignment. (monitor light box A C) e Manually or locally start pumps and align vivs.
(Refer to OP K-10 G-1, SEALED VALVE CHECKLIST FOR ECCS SYSTEMS.)
- b. RCS WR Pressure - LESS THAN 1650 b. Go to Step 12.
PSIG(VB2)
- c. SI Pump Flow, FI 918/922 - c. e Verify ECCS valve CHECK FOR FLOW (VB1) alignment (monitor light box A, C) e Manually or locally start pumps and align vivs.
(Refer to OP K-10 G-1, llll SEALED VALVE CHECKLIST FOR ECCS SYSTEMS.)
- d. RCS WR Pressure - LESS THAN 300 d. Go to Step 12.
PSIG (VB2)
- e. RHR Pump Flow, FI 970/971 - e. e Verify ECCS valve CHECK FOR FLOW (VB1) alignment (monitor light box A, C) e Manually or locally start pumps and align vivs.
(Refer to OP K.10 G.1, SEALED VALVE CHECKLIST FOR ECCS SYSTEMS.)
- 12. VERIFY MFW Pps - Tripped (VB3) Manually trip MFW pps.
+.e O
DC00010 6X
NUMBER EP E-0 olABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 p g DATE PAGE 3/8/85 7 0F 17 TITLE. REACTOR TRIP OR SAFETY INJECTION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 13. VERIFY AFW Status: (VB3)
- a. TD AFW pp - RUNNING IF NECESSARY a. Shutdown TD AFW pp, if not FOR RCS HEAT REMOVAL needed.
- b. SG AFW LCVs from MD pps . b. Manually maintain SG level.
IN AUTO
- c. SG AFW LCVs from TD pp . OPEN, if needed
- d. Verify AFW flow: d. IF total AFW flow greater
-~
than 460 gpm can NGT be e GREATER THAN 460 GPM TOTAL established, THEN go to FR.H.1, RESPONSE
- OR - TO LOSS OF SECONDARY HEAT SINK.
O, e SG NR level in at least one SG - GREATER THAN 4t, [20i]
- 14. Isolate Reheat Steam To MSRs: (VB3)
- a. Press RESET on MSR control a. Manually isolate MSRs.
panel IF
~~
MSRs can NOT be isolated, THEN close MSIVs and bypasses, if cooldown is NOT controllable.
- 15. VERIFY Ventilation Modes: (VB4)
- a. Auxiliary bldg vent system - BLDG a. Manually select Bldg and AND SAFEGUARDS MODE OR SAFEGUARDS Safeguards Mode.
MODE
- b. Control room vent system - MODE 4 b. Manually select Mode 4 on control room ventilation selector bus F and H for DCPP Unit 1
_ AND . DCPP Unit 2. l DC00010 7X
c. NUMBER EP E-0 DIABLo CANYON P(.,NER Pt. ANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 8 0F 17 rats. REACTOR TRIP OR SAFETY INJECTION ACTI0fuEXftutu RESPONSE RESPONSE NOT OBTAINED
- 16. CHECK Diesel Generator Status: (VB4)
- a. All three DGs running at rated a. Start DG if possible. Refer frequency and voltage to OP J-68 DIESEL GENERATORS.
- 17. CHECK RCS Average Temperature e IF temperature less than
. STABLE AT OR TRENDING TO 547'F 547"F and decreasing, (VB2) THEN stop dumping steam.
Verify steam dumps and SG 10% steam dumps closed. (VB3) e IF cooldown continues, TREN check for excessive feedwater by reducing flow. Feedwater flow can be reduced below 460 GPM total if level is greater than4%[20%)inoneSG. g e IF cool down continues and one SG is FAULTED, THEN go to step 18. e IF all SGs - FAULTED TREN close MSIVs and bypass vivs. e IF-- ten.perature greater than 547'F and increasing, THEN dump steam to condenser
. OR .
dump steam using SG 10% steam dumps. DC00010 8X O
i oiAsLO CANYON POWER PLANT UN!T NO(S) 1 AND 2 fff0N q DATE 3/8/85 Q PAGE 9 0F 17 TITLE, REACTOR TRIP OR SAFETY INJECTION ACTION /EXPEutu RESPONSE RESPONSE NOT OBTAINED
- 18. CHECK PZR PORVs And Spray Vlvs:
- a. PZR PORVs - CLOSED (VB2) a. IF-PZR pressure less than 2335 PSIG, o PCV-474 PORV-A THEN close PORVs.
e PCV-455C PORV-B e PCV-456 PORV-C E any PORV can NOT be closed, THEN close its stop vlvs. 8000A PORV.A 80008 PORV-B 8000C PORV-C E stop valve can NOT be closed. THEN go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT. O~ b. Normal PZR spray vivs
- b. IF- PZR pressure less than
- CLOSED (CC2) 2260 PSIG, THEN close PZR spray vivs.
e PCV-455A e PCV-455B E valve (s) can h0T be closed, THEN stop RCP(s) supplying failed spray valve (s): RCP 1 for PCV-455A RCP 2 for PCV-455B i DC00010 9X 4
NUMBER EP E-0 1 AND 2 REVISION 0 otABLO CANYCc POWER PLANT UNIT NO(S) DATE 3/8/85 PAGE 10 0F 17 7,7 g REACTOR TRIP OR SAFETY INJECTION ~ ACTION / EXPECTED RESPONSE FESPONSE NOT OBTAINED MTE: Seal injection flow should be maintained to all RCPs.
- 19. CHECK If RCPs Should Remain In Service:
- a. Check WR RCS pressure - GREATER a. -
IF RCS pressures less than THAN 1275 PSIG (VB2) 1275 psig, or Phase 8 - ACTUATED, THEN close 8105 and 8106 charg pumps miniflow recirc valves
- AND -
IF either one cent charging or one SI pp running, THEN stop all RCPs and go to the next step.
- b. Check Phase B - NOT ACTUATED b. Stop all RCPs.
(VB1)
- 20. CHECK If SGs Are Not Faulted: (VB3)
- a. Check pressure in all SGs: a. -
IF a faulted SG is identified and E-2, e NO SG PRESSURE DECREASING IN FAULTED STEAM GENERATOR AN UNCONTROLLED MANNER ISOLATION has NOT been performed on the e NO SG COMPLETELY faulted SG, DEPRESSURIZED THEN Go to E-2, FAULTED STEAM GENERATOR ISOLATION. me O DC0010 10X
NUMBER EP E.0 otAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION O DATE 3/8/85
) PAGE 11 0F 17 7,7 a REACTOR TRIP OR SAFETY INJECTION ACTION /EXRCTED RESPONSE RESPONSE NOT OBTAINED
- 21. CHECK If SG Tubes Are Not Ruptured: Go to E-3, STEAM GENERATOR TUBE RUPTURE.
o Steamline radiation . NORMAL (PK 11-18, R-71, 72, 73, 74) e SJAE radiation - NORMAL (R-15, RMS CAB II) e SG blowdown radiation - NORMAL (R-19 , RMS CAB III)
- 22. CHECK If RCS Is Intact: Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT.
e Containment radiation monitors
- NORMAL (R-30/31, PAM 1) (R 02/07 RNRM A) e Containnent pressure - NORMAL (VS1)
- e Containment recirc sump le'.el
) - NORMAL (LI-940/941, VB1) s
- 23. CHECK IF ECCS Flow Should Be Reduced:
- a. RCS subcoolirg based on core exit a. DO NOT STOP ECCS PUMPS. Go TCs - GREATER THAN 20*F (VB2) to Step 25.
- b. Secondary heat sink: (VB3) b. E neither condition satisfied, e Total Aux feed flow te SGs - THEN 00 NOT STOP ECLS PUMPS.
GREATER THAN 460 GPM Go to Step 25.
- OR .
e Narrow range levol in at least one SG . GREATER THAN 4f,
- c. RCS pressure - 51ABLE OR c. 00 NOT STOP ECCS PUMPS. Go INCREASING (VB2) to Step 25.
- d. PZR level - GREATER THAN 4% d. 00 NOT STOP ECCS PUMPS. Try (VB2) to stabilize RCS pressure and I
recover PZR Ivl with normal PZR spray. Return to Step 23a. v 1 OC0010 11X
NUMBER EP E-0 1 DIABLO CK4 YON POWER PLANT UNIT NO(S) 1 AND 2 REVZSION 0 OATE 3/8/85 PAGE 12 0F 17 mLE REACTOR TRIP OR SAFETY It!JECTION g ACTION /EXPEutu ESPONSE ESPONSE fOT OBTAINED ,
- 24. GO To E 1.1, SI TERMINATION
- 25. INITIATE Monitoring Of Critica*1 Safety Function Status Trees (SPDS)
CAUTION: Alternate water sources for AFW pumps will be necessary if CST level decreases to less than 10%. (Refer to E-2.1 ALTERNATE AUXILIARY FEE 0 WATER SUPPLIES)
- 26. CHECKSGLevels(VB3)
- a. NR level - GREATER THAN 4% a. Maintain total feed flow greater than 460 gpm UNTIL NR level is greater than 4* in at least cne SG.
................................ i
- b. Centrol AFW flow as necessary to b. IF, NR level in any %
maintain level between 4% and continu6s to ircrease 33% in an uncontrolled manc.er,
- c. Stcp TO AFW pp if not needed for THEN go to E-3, STEAM RCS heat removal GENEPATOR TUBE RUPTURE, Step 1.
- 27. CHECK Secondary Radiation Go to E-3, STEAM GENERATOR TU6E
- NORMAL RUPTURE.
l e hP Survey of main steam lines e SG Sample <
- 28. CHECK Auxiliar.v Building Radiation - Evaluate cause of abnormal NORMAL conditions.
IF
-~
the cause is a loss of RCS
- inventory outside
! containment, l THEN go to ECA-1.2, LOCA OUTSIDE CONTAIhMENT \ ................................ O DC00010 12X t l l l
NUMBER EP E-0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 3/8/85 (q ,j DATE PAGE 13 0F 17 TITLE REACTOR TRIP OR SAFETY INJECTION ACTION / EXPECTED ESPONSE ESPONSE NOT OBTAINED
- 29. CHECK PRT CONDITIONS - NORMAL (VB2) Evaluate cause of abnormal conditions (Refer to PK 05-25 annunciator response manual)
CAUTION: If offsite power is lost after SI reset, manual action will be required to restart some safeguards equipment. Refer to Appendix A for guidance if this condition occurs. 30 RESET SI (VB1)
- 31. RESET Phase A And Phase B Isolation (Vbl)
- 32. ESTABLISH Instrument Air To Try to establish air. Refer to Containment: OP AP-9, LOSS OF INSTRUMENT AIR.
ps Avoid excessive cycling of vivs (_,)
- a. Open FCV-584, cnmt inst air iso that have backup air, and i vlv (VB4) continue in this procedure.
- b. Verify at least one air compressor - IN SERVICE l
1 CAUTION: RCS pressure ;nould be monitored. If RCS pressure decreases below 300 psig, the Rhh pumps must be manually restarted to supply water to the RCS. ! 33. CHECK If RHR Pumps Should Be Stoppea:
- a. Check WR RCS pressure: (VB2)
- 1) Pressure - GREATER THAN 300 1) Go to E-1, LOSS OF REACTOR OR PSIG SECONDARY COOLANT.
- 2) Pressure - STABLE OR 2) Go to Step 34 INCREASING
-- b. Stop khk pumps (VB1) %.)
DC00010 13X 1
NUMBER EP E-( DiAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 14 0F 17 TITLE. REACTOR TRIP OR SAFETY INJECTION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 34. CHECK If Diesel Generators Should Be Stopped: (VB4)
- a. Check vital 4KV buses F, G, & H a. Try to restore offsite power
- ENERGIZED BY OFFSITE POWER to F, G, and H busses.
E offsite power can NOT be restored, THEN load needed non-vital equipment on vital busses, if possible: o PZR heaters e TSC
- 1) OPEh 52-22J-40
- 2) OPEN 52-2F-47
- 3) OPEN 52-1F-67
- 4) Switch EPISN to vital power
- 5) -- IF 0/G 13 on U1 F Bus THEN switch EPTSC to U-1 (52-1F-67) and CLOSE i 52-1F-67.
- 6) E D/G 13 on U2 F Bus THEN switch EPTSC to U-2 (52-2F-47) and CLOSE 52-2F-47.
e Air Compressors
- b. Stop any unloaded diesel and place in AUTO l
- 35. RETURN To Step 17 To Rediagnose
~
l Plant Conditions
- END -
DC00010 14X
ou&c CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/8/85 l
)
PAGE 15 0F 17 v REACTOR TRIP OR SAFETY INJECTION TITLE . APPENDIX A BLACK 0UT EMERGENCY LOADING OF VITAL BUSSES
- 1. If the vital busses lose voltage prior to resetting the safety injection signal, the vital busses will automatically load the vital equipment given below. Verify tre equipment has been loaded by observing breaker lights on the control board.
- 2. If the vital busses lose voltage af ter the safety injection signal has been reset, load or verify loaded the equipment given below onto the vital busses manually. Allow approximately 4 seconds between loading of each piece of equipment onto a given vital bus. Load or verify that the CFCU are running in Low Speed.
VITAL BUS F VITAL BUS G VITAL BUS H U-1(D/G 1-3) U-1(D/G No. 2) U-1(D/G No.1) ,C) U-2(D/G 1-3) U-2(D/G No. 1) U-2(D/G No. 2) 'o MCC F MCC G MCC H CC Pp No. 1 RHR Pp No. 1 SI Pp No.1 CFCU No. 3 SI Pp No. 2 CF(U No. 2 CFCU No. 5 RHR Pp No. 2 CFCU No. 1 CCW Pp No. 2 CFCU No. 4 CCW Pp No. 1 ASW Pp No. 2 CCW Pp No. 3 ASW Pp No.1 CC Pp No. 2 AFW Pp No. 2 AFW Pp No. 3
- 3. Load the containment spray Pumps only if they were running prior to the blackout.
VITAL BUS VITAL BUS G H Cont Spray Pp No.1 Cont Spray Pp No. 2 v DC00010 15x
NUMBEF' EP E-0 otAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVIS!ON 0 DATE 3/8/85 PAGE 16 0F 17 TITLE. REACTOR TRIP OR SAFETY INJECTION APPENDIX C 2600
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U0 OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DATE 3/8/85 PAGE 17 0F 17 ( TITLE REACTOR TRIP OR SAFETY INJECTION APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been implemented, and upon direction from the Shift Foreman, proceed as follows:
- a. Designate this event a Notification of Unusual Event if ECCS flow is indicated. Notify plant staff and response organizations required for this classification by implementing EP G-2
" Establishment of the On-Site Emergency Organization" and EP G-3
" Notification of Off-Site Organizations" in accordance with EP G-1 " Accident Classification and Emergency Plan Activation".
- b. Reclassify the event according to the Appendix Z instructiens in subsequent procedures, if the accident diagnostics require implementation of these procedures.
O o u l DC00010 17X l
. . . - . _. - . . = . - -
I FOLDOUT FOR E-0
>() ADMINISTRATIVE FUNCTIONS l
- 1. Notify STA, (Monitor Critical Safety Functions and SPDS. Do not implement FR series procedures until af ter step 23.)
- 2. Refer to Appendix Z -
RCP TRIP CRITERIA I e Trip all RCPs within 5 minutes of a Phase B actuation e Trip all RCPs if BOTH conditions below (a & b) are met:
- a. EITHER one cent charging pump or SI pump running.
i
- b. WR RCS pressure - LESS THAN 1275 PSIG.
AFW SUPPLY SWITCHOVER CRITERION l
! Switch to alternate AFW water supply when CST level decreases to less than 10%. Refer to E-2.1, ALTERNATE AFW SUPPLIES.
4 ADVERSE CONTAlhMENT INSTRUMENTATION REQUIREMENTS I 1
.O e Containment Pressure - GREATER THAN 3 psig
- 0R -
e Containment Rad rate > 10 R/hr 5
- OR - - 6 e Containment Rad dose > 10 R 1
t i i I O U DC0010 181X f l
""" ' ~ 'I T GW3 Pacific Gas and Electric Company REVISION 0
/ DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 3/8/85 DIABLO CANYON POWER PLANT UNIT NO(S)
PAGE 1 0F 23 1 AND 2 EMERGENCY PROCEDURE TITLE g REACTOR TRIP RESPONSE ... yd 5 TO APPROVED PLANTMANAGERg) DATE SAFETY SCOPE This procedure provides the necessary instructions to stabilize and control the plant following a reactor trip without a safety injection. This procedure and changes thereto requires PSRC review. SYMPTOM 0F ENTRY CONDITIONS This procedure is entered from EP OP-0, REACT 0P. TRIP OR SAFETY INJECTION, Step 4, when SI is neither actuated or required. i i i l O 0C0286 IV l
NUMBER EP E-0.1 otAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 2 0F 23 m LE- REACTOR TRIP RESPONSE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: e If SI actuation occurs during this procedure, go to E-0, REACTOR TRIP OR SAFETY INJECTION. e If subcooling monitor becomes inoperable, determine subcooling by using WR RCS pressure and core exit TCs (Refer to APPENDIX C). NOTE: Monitor CSF Status Trees and SPDS.
- 1. CHECK RCS Average Temperature -
IF temperature is less than
- STABLE AT OR TREhDIhG TO 547*F 547'F and decreasing, (CC1) THEN verify ALL steam dumps closed.783)
IF cooldown continues, TiiEN check for excessive feedwater by reducing flow. Feedwater flow can be reduced below 460 GFM if level is GREATER THAN 4% in at least one SG. (CC3) IF cooldown continues, TiiEN simultaneously close MSIVs AND bypass valves (VB3) closed. IF temperature is greater than 547'F and increasing THEN dump steam to condenser (CC3)
. OR -
dump steam using SG 10% steamdumps.(VB3) O DC0286 2V
NUMBER EP E.0.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 p/ s PAGE 3 0F 23 m LE. REACTOR TRIP RESPONSE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. CHECK FW Status:
- a. Check RCS average temperature a. Continue with Step 3
- LESS THAN 554*F (CCI)
- AND .
WHEN less than 554*F, TIIEIi do Steps 2b and 2c. - -
- b. Verify MFW regulator and bypass b. Manually close SG MN FDWTR valves closed on monitor light CONT and bypass valves:
box C, FW Isol SG level portion: (CC3) (VB1) FCV 510 - CLOSED
- 1) Rec activated light - ON FCV 520 - CLOSED FCV 530 - CLOSED
- 2) khite status lights - 0FF FCV 540 - CLOSED
- 3) Place MFW reg vivs in FCV 1510- CLOSED macual, and run the demand FCV 1520- CLOSED to Ok FCV 1530- CLOSED FCV 1540- CLOSED l
THIS STEP CONTINUED ON NEXT PAGE O DC0286 3V
NUMBER EP E-0.1 0AsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION O DATE 3/8/85 TITLE. REACTOR TRIP RESPONSE
. . . 1 ACTION / EXPECTED RESP 0 HSE RESPONSE NOT OBTAINED
- c. Verify total feed flow (VB3) c. 1) Establish feed flow to
- GREATER THAN 460 GPM the SGs as necessary:
(VB3)
. OR .
e Start AFW purrps and NR LVL in at least one SG align vivs as necessary 1
- GREATER THAN 4%
. OR -
e Reset MFW iso and attempt to feed with main feed.
- 2) IF total AFW flow >460 gpm can NOT be established THEN go to FR-H.1, RESPONSE TO LOSS OF SECONDARY HEATSINK.
- c. Shutdown TD AFW Pump if not required for RCS heat removal
- 3. VERIFY All Control Rods Fully -
IF tuo or more control rcds Inserted (%2) NOT fully inserted. THEN emergency borate 300 gal of 12% BA for each rod not fully inserted,
. OR -
100 ppm per rod. 9 ee 1 O I DC0286 4V l
NUMBER EP E-0.1 DIAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 A ' DATE 3/8/85 () PAGE 5 0F 23 TITLE. 3EACTOR TRIP RESPONSE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. CHECK PZR Level Controls;
- a. Level . GREATER THAN 17% a. Perform the following:
(CC2/VB2)
- 1) Verify letdown isolation.
IF NOT, ~THEN manually Tiolate.{VE2)
- 2) Verify PZR heaters off.
THEN manually IF turnNOT, off 7 C1)
- 3) Control charging to restore PZR level greater than 17%. (CC2)
- b. Verify charging and letdcwn b. To re-establish
. IN SERVICE (VB2) letdown: (VB2)
- 1) Ensure charging in service.
- 2) Open to 20% TCV 130, LTDN Temp Cent viv.
- 3) Ensure 8149A, B and C closed, Itdn orifice stop v1vs.
4)OpenLCV-459andLCV-460.
- 5) Check ogn 8152, letdown isc viv OC.
- 6) Open to 40% PCV-135, letdown press cont.
- 7) Open 81495 or C, 75 gpr orifice stop valve.
- 8) Adjust PCV.135 for 350 psig, place in AUTO.
3 c. PZR Level - TRENDING TO 22% c. Aojust charging flow to
/ (CC2/VB2) maintain level 22% to 601. -
DC0286 SV i l
NUMBER EP E-0.1 OIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 TITLE REACTOR TRIP RESPONSE ACTION / EXPECTED RESPOME RESPONSE NOT OBTAINED
- 5. CHECK PZR Pressure Control:
- a. Pressure - GREATER THAN 1850 PSIG a. IF SI required, (CC2/VB2) TREN manually actuate SI and go to E-0, REACTOR TRIP OR SAFETY INJECTION, Step 5.
- b. Pressure . STABLE AT OR TRENDING b. -
IF less than 2235 psig and TO 2235 PSIG (CC2) decreasing, THEN:
- 1) Verify PZR PORVs closed.
IF NOT, THEN manually cToFFORV or its stop viv.(VB2) e PCV-474, 8000A e PCV-455C, 80008 e PCV-456, 8000C
- 2) Verify PZR spray valves closed. (CC2)
IF NOT, THEN manually cTose spray valve (s) or stop RCP(s) supplying failed valve (s): RCP 1 for PCV-455A RCP 2 for PCV-455B
- 3) Ensure PZR heaters on.
I.F greater than 2235 psig and increasing, THEN: a) Ensure PZR heaters off, b) Control PZR pressure using normal spray, auxiliary spray or one PORV. DC0286 6V
DiA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/8/85 f) PAGE 7 0F 23 v TITLE REACTOR TRIP RESPONSE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. CHECK SG Levels: (VB3)
- a. All SG NR levels - GREATER THAN a. Maintain total feed flow 4% a minimum of 460 gpm until SG NR level is greater than 4% in at least one SG.
- b. Centrol feed flow to maintain SG b. IF
~-
narrow range level in NR levels between 4% and 33% any SG continues to increase. THEN stop feed to that SG. -
- c. Stop TO AFW pump if not needed for RCS heat removal
- 7. VERIFY Mair Generator Trip Af ter 30 Separate main generator from Second Delay: system grid (CC3). Refer to O e PK 14-1, Unit Trip - ON (VB4)
OP J-2:J. CODE ORDER TO SEPARATE THE MAIN GENERATOR FROM THE SYSTEM GRID, WHEN THE MAIN GENERATOR CIRCUIT BREAKERS FAIL TO OPEN, e Generator Vcltage - s 0 volts (CC3) n i
/
DC0286 7V
0iAsLO CANYON POWE] PLANT UNIT NO(S) 1 AND 2 ON DATE 3/8/85 PAGE 8 0F 23 Tirts REACTOR TRIP RESPONSE O ACTION /EMuw RESFGSE RESPONSE NOT OBTAINED NOTE: If the plant was backfeeding from the 500 KV system at the time of the reactor trip an automatic transfer to startup power will not normally occur unless the 500 KV system becomes unavailable.
- 8. VERIFY All AC Busses (VB4) Perform the following:
- ENERGIZED BY OFFSITE POWER a) IF offsite power NOT available.
THEN verify diesel generators have assumed the following loads: e ASW pumps No. 1 and No. 2 (VB1) e AFW pumps No. 2 and No. 3 (VB3) e Charg pumps No. I and No. 2 (V82) e CCW pumps No. 1, ho. 2 and No. 3 (VBI) e CFCUs No. 1, No. 2 No. 3, & No. 4 and No. $ (VB1) W b) Try to restore offsite power. IF RESTORED. TIIEN refer to OP J-68, DIESEL GENERATORS, to re-eriergize 4KV vital busses froe offsite p, owe r. THIS STEP CONTINUED ON NEXT PAGE DC0286 8V
otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/8/85 i PAGE 9 0F 23 TITLE REACTOR TRIP RESPONSE ACTION / EXPECTED RESPONSE RESP 0fGE NOT OBTAINED c) Enejize additional equipment from the vital busses if necessa ry, o PZR Heaters. Refer to OP A-4A:I PZR MAKE AVAILABLE PART C. e TSC: 1 OPEN 52-22J-40. 2 OPEN 52-2F-47. 3 OPEN 52-lF-67. 4 Switch EPTSN to VITAL POWER.
- 5) IF D/G 13 on U-l F bus TEEN switch EPTSC to U-l (52-1F-67) and CLOSE 52-1F-67.
- 6) IF 0/G 13 on U-2 bus G TFEN switch EPTSC to U-2 (52-2F-47) and CLOSE 52-2F-47.
e Crosstie a vital and nenvital 4 KV bus to establish instrument air. Refer to appendix N. d) Reestablish norcal letdown. i DC0266 9V
I AND 2 NUMBER EP E-).1 DIABLO CANYON POWE] PLANT UNIT NO(S) REVISION O DATE 3/8/85 PAGE 10 0F 23 7,7 a REACTOR TRIP RESPONSE g ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: On natural circulation, loop Tavg and associated interlocks for Feed Line Iso, Steam dump and Hi Stm Flow SI will be inaccurate. t0TE: Running RCP No. 2 (preferred) or RCP No. I should be given priority for purpose of nomal PZR spray.
- 9. Check RCP Status Try to start one RCP:
. AT LEAST ONE RUNNING (V82)
- a. Start an RCP per OP A-6:1, RCP . PLACE IN SERVICE.
- b. IF
~
an RCP can NOT be started, THEN manuolly close both nomal PZR spray vivs
- AND -
verify natural circulation based on: e RCS subcooling based on core exit TCs greater than 20'F. (V82) e SG pressures stable or decreasing. (VB3) e RCS hot leg temperatures stable or decreasing. (VB2) e Core exit TCs stable or decreasing. (SPOS/P250) e RCS cold leg temperatures at saturation temperature for SG pressure.(Appendix C/V82) IF natural circulation NOT verified. THEN increase dumping steam. O DC0286 10V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/8/85 h TITLE REACTOR TRIP RESPONSE PAGE 11 0F 23 ACTION / EXPECTED ESPONSE ESP 0f4SE NOT OBTAINED
- 10. CHECK Turbine Status During Coastdown: (V84)
- a. Verify turbine drain valves
- OPEN
- b. Start AC turbine bearing oil b. Start DC pumps as nessary, pump and high pressure seal oil backup pump
- c. Henitor turbine coastdown per OP C-3:IV, MAIN UNIT TURBINE -
TURB:hE SHUTDOWN
- 11. ALIGN MSPs:
(o' C'
- a. Press reset or MSR control panel (VB3)
- b. Refer to 0F C.5, MSRs fcr desired alignrent irstructier.s O
LC0286 11V l l
1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) [Vhf0N DATE 3/8/85 PAGE 12 0F 23 TITLE REACTOR TRIP RESPONSE ACTION /EXPEutu PESPONSE RESPONSE NOT OBTAINED
- 12. CHECK If SR Detectors Should Be Energized:
- a. Check IR flux - LESS THAN 1010 a. Continue with Step 14, and WHEN flux is less than 10-10 amps, THEN complete Steps 13b and c.
- b. Verify both SR detectors b. Manually reset and energize
- ENERGIZED (CC1) both SR detectors.
- c. Select highest SR and IR detector on NR-45 (CC1)
- 13. SHUTDOWN MFW Put'ps If Not Needed For feedwater Control: ()63)
- a. Irtplement OP C.6:1!!, SHUTDOWN AND CLEARING OF A PAIN FEE 0 WATER PUMP.
O CC0286 12V
NUMBER EP E-0.1 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 em PAGE 13 0F 23 b 7,7 a REACTOR TRIP RESPONSE ACTION / EXPECTED ESPONSE ESR)NSE NOT OBTAINED
- 14. CHECK IF Condenser Steam Dump Should E Condenser Steam Dump is NOT available Be In Pressure Control Mode:
THEN use SG 10% Steam Dump
. AND -
Go to Step 15.
- a. Check HSIVs - N3T ISOLATED (VB3)
- b. Check C-9 status light on (VB3)
- c. Set HC-507 at 8.38 turns (CC3)
- c. Check O' cerand en HC507 (CC3) d. Increase setting on HC-507 to achieve 0; demand
. OR .
Transfer HC-507 to rnanual and decrease demand to O';.
- e. Transfer to FRESSLRE CONTROL MODE on Stean Duns Selector Switch (CC2)
- f. Centrol Condenser Steam Dump Controller HC-507 to maintain steam pressure s1005 psigk (CC3/VB3) 9 Place to CONT ONLY, LCV-12 selector switch O
v DC0286 13V l
NUMBER EP E-0.1 DIABLO CANYON POWE. 7 PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 14 0F 23 ritts REACTOR TRIP RESPONSE g ACTION / EXPECTED RESK6SE RESPONSE NOT OBTAINED
- 15. SH'JT00WN Unnecessary Plant Equipment As Desired:
- a. Stop No. 2 Heater Drip Pump per OP C-78:II No. 2 HEATER DRIP PUMP SHUTDOWNANDCLEARING(VB3)
- b. Shutdown all but one Condensate and Booster Pump sets (VB3)
- c. Reset 4KV bus auto transfer relay, if necessary (VB4)
- d. Stop all but one ASW pumps (V61)
- e. Restore CFCU operation to pre-reactor trip status (VBI)
- 16. ALIGN Auxiliary Steam As Desired:
- a. :MPLEMENT OP K-5, PACKAGE 80lLER AND AUXILIARY STEAM SYSTEM
- 17. NOTIFY the Following of the Reactor Tri, o Chem / Rad Cepartment e !&C Department to perfom STP I-3A NUCLEAR INTEPPEDIATE RAhGE CHANNEL ANALOG CHANNEL OPERATIONAL / FUNCTIONAL TEST
- 18. PAINTAIN Stable Plant Ccndition>:
o PZR pressure - s2235 PSIG e PZR level - 22% to 60% e SG NR level - 4% to 33% e RCS average temperature
- s547'F O
OCO266 14V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h0N DATE 3/8/85 ' 15 0F 23 f] V PAGE Tiits REACTOR TRIP RESPONSE ACTION / EXPECTED ESPONSE ESPONSE NOT OBTAINED
- 19. COMPLETE Required Reports And Notifications:
- a. APA-10051, ADMINISTRATIVE PROGRAM TO CONTROL THE RETURN TO POWER AFTER REACTOR TRIP
- b. Refer to Appendix Z of this procedure
- c. STP M-55 Recording of Cyclic Fatique Transients
- 20. GO To Acclicable Plant Procedure:
- a. EP E-0.2, NATURAL CIRCULATION C00LD0'aN
- OR -
- b. CP L-2, HOT STANDEY TO MINIMUM LOAD
- OR -
- c. 0F L-5, PLANT C00LD0nh FRCM MINIMUM LOAD TO COLD SHUT 00WN
- END -
DC0286 I5V I
NUMBER EP E-0.1 OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 TITLE. REACTOR TRIP RESPONSE APPENDIX C 2600 a = cts . :__._r_ -j e =__ i. .y_.a + =a.m___. : =._. i. 2.
. . _ . ._ .. . . . _. iE.x=:p_.__is_
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=_ w=t .n=x:2. ;;:gn== = := =,. t== = ==
=,f=.m_
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. _ ;r. = : .pa 2.
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== : : : ::: .= =,.__== -- = g-
- . . . _ _ . . _ .= = = .== == _ : =-'
W ---~= * - - - - ~ ~ ~ -- - " - 1200 e ==r-- n :.=~== SATURATION CURVE EiEgr _ SATURATION =3-M . ~~ T i l. 1 .J CORRECTED FOR
.. = .::~_j CURVE w == P= = C= = INSTRUMENT ERROR = = ==-+----- t =*=
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u -~~'"~
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*~ * - - - - ' - - "- - i - ~~~~; ~ ~~
800 m ..:=;;= =_;;_
+ ~ "*""_ ,_
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,a =..".x '='__y~__.__.____.y.__.._.,
=_i._===-
=u - . = 2. m := ==. . : :_. :. ;
____:-- : t : = : = ._
, g_ . _ .
600
~~ = #'~ '-
~~
~M "- " - 1-~~
--- r m:= -
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--_ + t ; _,; 1 ;- ;. ,
- 4 --I'-~="-- ' = * ~ "= * ~
400
=M~ 72ij:=O ~ [y_=.t.5:~jE-" _
.=- - ""-IEEP=-i.~j= LEE-Is
- PRESSURE ERROR + 65 psig!
200 _7=p.;:_ g 7; . _ . _. ,_i=7; _ t- = TEMPERATURE ERROR i 24 'F !
; --f : :- . . - - . . = --t =a= 4 . . : -
u_...._.._.._.
^
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6.. ..
- [:;:.. :f:..=..
_ f.. nt.1: _ : == .=r. ... _ ......_ f ..n.}:.i..-
. . .n:: ,
200 300 400 500 600 700 CORE EXIT T/C TEMPERATURE (*F) DC0286 16V
DIABLO CANYON POWER PLANr UNIT NO(S) 1 AND 2 ON DATE 3/8/85 PAGE 17 0F 23 p# m LE REACTOR TRIP RESPONSE APPENDIX N ENERGIZING NON-VITAL 480V BUSSES WITH DIESEL GENERATOR SCOPE The purpose of this procedure is to make available selected non-vital systems to lessen the restriction on recovery until normal 0FF-SITE power is restored. This procecure deals with the situation when both Units are down. All S emergency diesel generators may not be available. In this case one unit will be deprived of the swing diesel generator. The selected non-vital systems which are desired to be returned to sersice are plant instrument air, service cooling water, CRDM shroud cooler fans, Turbine Generator lift pump and turning gear drive, 230KV and 500KV switchyard. DISCUSSION This precedure deals with bcth units since the plant air compresscrs are powered from either unit and are normally cross connected such O that it is ccm on to both units. Therefore, the unit to which the (_) swing diesel 13 is omitted will be responsible for re-energizing the compressed air systers. Unit 1 is responsible to re-energize the 230 and 50CKV switchyard. Any additional loading will be done by Shift Foreman evaluatier, for remaining diesel generators capacity. The following is a list of the minimum rumber of loads required for plant cooldown.
- a. 1 Centrifugal Charging - 50?KW
- b. 1 Cceponent Cooling Water - 324KW
- c. 1 Auxiliary Salt Water - 321kW
- d. 3 Containment Fan Coolers - 660KW
- e. 1 Auxiliary Feedwater - 429KW
- f. 1 Pressurizer Heater Group * -
483/207
- g. 2 480V Motor Control Centers - Refer to STP M-9M for Individual Loads and Intermittent Loads
- 483KW for 7 Heaters; 207 for 3 Heaters GCO286 17V
NUMBER EP E-0.1 otAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 18 0F 23 Tirts REACTOR TRIP RESPONSE APPENDIX N (Continued) PROCEDURE
- 1. Octermine which diesel generator will be used as source for the non-vital busses.
- a. On the Unit which has the 13 swing diesel generator available, transfer the maximum number of essential loads to the 4KV bus F and remove all non-essential 1 cads from bus G.
- b. On the Unit which does not have the 13 swing diesel generator available, transfer the maximum number of essential loads to bus G and remove all non-essential loads from bus H.
- 2. Cut out the Auto Transfer FCO's for all 4KV busses and 12KV busses.
- 3. Depress all Auto Transfer Reset Push buttons.
NOTE: The Auto Transfer Reset will NOT reset an'd the BLUE light will NOT de-energize for the F bus if the 13 diesel generator is operating on the other unit.
- a. OPEN or verify OPEN all vital bus 4KV auxiliary feeder breakers, 52-FH-13, 52-HG-13 and 52-HF-13.
- 5. OPEN or verify OPEN all vital bus 4KV startup feeder breakers, 52-HH-14, 52-HG-14 and 52-HF-14,
- 6. OPEN or verify OPEN startup power to vital busses F, G, H, 52-HG-15.
- 7. OPEN or verify OPEN auxiliary feeder to 4KV non-vital busses 0 and E.
UNIT 1 - UNIT 2 52-HE-2 and 52-HD-15 52-He-14 and 52-HD-4 O DC0286 18V
NUMBER EP E-0.1 otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 7s DATE 3/8/85 ( ,) PAGE 19 0F 23 rirts REACTOR TRIP RESPONSE APPENDIX N (Continued)
- 8. OPEN or verify OPEN startup feeder to 4KV non-vital busses D and E.
UNIT 1 UNIT 2 52-HE-3 and 52-HD-14 52-He-13 and 52-HD-5
- 9. OPEN or verify OPEN startup transformer feeder breaker.
UNIT 1 UNIT 2 52-VU-14 52-VU-23
- 10. OPEN ALL 4KV feeder breakers to 480 volt busses and 4KV busses 0 and E.
- 11. At SFM discretion cut in the FC0 to place all Diesel Generator Protection in service for the Diesel Generator selected to power
(-g x ,) the non-vital busses.
- 12. Verify all Condensate / Booster pump stand-by switches are set in MAhtAL.
- 13. Verify the Nash vacuum purp is 0FF and the ho 2 Heater Drip Pur.p is 0FF.
14 CLOSE ihe startup feeder breaker to the vital bus.
- a. If the non-vital bus po'ver source is UNIT 1 UNIT 2 D/G CLOSE BREALER D/G CLOSE BREAKER 11 52-HH-14 22 52-HH-14 12 52-HG-14 21 52-HG-14 13 52-HF-14 13 52-HF-14 CAUTION: If the diesel generator appears unstable during the performance of Step 15 or at any time beyond this point in the procedure, innediately OPEN 52-HG-15 to separate the diesel from the non-vital system.
-- 15. CLOSE startup power to vital busses F, G, H, 52-HG-15.
v DC028E 19V
~ NUMBER EP E-0.1 D'ABLo CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 20 0F 23 TITLE REACTOR TRIP RESPONSE APPENDIX N (Continued) NOTE: There will be short load surge on the Diesel Generator as the startup transformer 12 is energized.
- 16. CLOSE startup feeder to 4KV bus D.
UNIT 1 UNIT 2 52-HD-14 52-HD-5
- 17. CLOSE startup feeder to 4KV bus E.
UNIT 1 UNIT 2 52-HE-3 52-HE-13 NOTE: Evaluate the load on the diesel generator prior to energizing each additional load to ensure its reserve capacity is not exceeded. As each additional load is added if the diesel generator overloads it may only be necessary to trip the last load added rather than tripping the entire bus.
- 18. On the Unit which has the 13 swing diesel generator carrying the F vital bus energize the following 480V busses,
- a. Energize the following non-vital busses.
UNIT 1 UNIT 2 BUS CLOSE BREAKER BUS CLOSE BREAKER 15D 52-HD-6 250 52-HD-13 110 52-HD-10 210 52-HD-9
- 19. Return the instrument air system to service as per OP K-1, 20, inergize the 500KV switchyard 4KV bus CLOSE 52-HE-7 (U-1 only),
- a. Dispatch an Operator to the 500KV switchyard to verify CLOSED or CLOSE the local 4KV bus feeder breaker in the 500KV switchyard.
- b. Operator should also verify 480V bus is energized and 500KV switchgear compressed air system is available.
O DC0266 10V
OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/8/85 PAGE 21 0F 23 TITLE REACTOR TRIP RESPONSE APPENDIX N (Continued)
- c. Operator should verify 230KV yard 4KV bus is energized via the emergency tie cable and its compressed air system is available.
- 21. Additional loads such as CRDM shroud coolers, turbine generator lift pump and turning gear drive may be made available and their 480V busses energized at the discretion of the Shift Foreman, dependent on diesel generator reserve capacity.
9 l l DC0286 21v
NUMBER EP E-0.1 1 AND 2 REVISION O DIABLO CANYON POWER Pt. ANT UNIT NO(S) DATE 3/8/85 PAGE 22 0F 23 mLE REACTOR TRIP RESPCNSE h APPENDIX N sunwonnu. e I
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FIGURE ONE: DIESEL GENERATOR LOAD LIMITS O OC0286 22V w
'b l
l DiABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/8/85 l O PAGE 23 0F 23 i TITLE REACTOR TRIP RESPONSE APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When the erargency procedure has been activated and upon direction from the Shift Foreman proceed as follows:
- a. Notify the Plant Superintendent. Operations Manager, and Plant Manager or their designated alternates,
- b. Within four hours notify the NRC Operations Center using the red phone in the Control Room. Gather sufficient information from all sources prior to calling so that the phone call is meaningful. Complete the "NRC Event Notification Fortn" contained in Administrative Procedure C-11, Supplement 2, " Supplement 2 to Non-Routine Netification and Reporting to the NRC and Other Governmertal Agencies." Notify the NRC that your call is a four hour report pursuant to 10CFR Part S0.72, (Immediate Notification Requiremerits),
- c. Review the circumstances causing the reactor trip against the criteria for reports to the NRC contained in Administrative Procedure C-11, Supplement 2. If circumstances warrant, designate the event in accordance with the criteria contained in Procedure C-11, Supplement 2.
- d. When the cause of the reacter trip has been deternined, this and the subsequent plant conditions should also be reviewed against the classification criteria in Emergency Procedure G-1 " Accident Classification and Energency Plan Activation.
- 2. If plant conditions indicate the required conditions for reactor trip have occurred or the required coincidence of bistables have tripped, or trip is manually activated, and nuclear instrumentation indicates the reactor is not subcritical (e.g.,
non-negative startup rate) designated this event an Alert. Notify plant staff and response organizations required for this classification by implementing Procedures EP G-2 " Establishment of the On-Site Organization" and EP G-3 " Notification of Off-Site Organizations" in accordance with EP G-1 " Accident Classification and Emergency Plan Activation." (3 V l DC0286 23V i 1
mc m NUMBER EP E-0.2
..~ # 14 3 Pacific Gas and Electric Company REVISION 1 CEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 3/7/85 4 ,
DIABLO CANYON POWER PLANT UNIT NO(S) PAGE 1 0F 24 1 AND 2
. EMERGENCY PROCEDURE TITLE NATURAL CIRCULATION C00LDOWN IMPORTANT APPROVED ?E 6 I 3'M6 TO PLANT MANAGERO DATE SAFETY SCOPE This procedure provides actions to perfonn a natural circulation RCS cooldown and depressurization to cold shutdown, with no accident in progress, under requirements that will preclude any upper head void formation. This procedure and changes thereto requires PSRC review.
SYMPTOMS OR ENTRY C0t.DITIONS This procedure is centered from the following procedures:
- 1. E-0.1, REACTOR TRIP RESPONSE, Step 20, when it has been deter =ined that a natural circulation cooldown is required.
- 2. ECA-0.1, LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED, Step 21, when it has been determined that a manual circulation ccoldown is required.
[
'I l
O j' , DC0010 IV , I
otABLo CANYON POWER PLANT UNIT NO(S) I AND 2 S ON DATE 3/7/85 PAGE 2 0F 24 Tirte NATURAL CIRCULATION C00LDOWN ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: e If SI actuation occurs during this procedure, E-0, REACTOR TRIP OR SAFETY INJECTION, should be performed. e This procedure is not for use with an accident in progress. NOTE: e Foldout page should be open. e If cenditions can be established for starting a RCP during this procecure Step 1 should be repeated. e RCP No. 2 (preferred) or RCP No.1 should be given priority to permit the use of normal PZR spray.
- 1. TRY To Restart An RCP: (VB2)
- a. Establish conditions for starting a. Go to Step 2.
(Implement OP A-6:1, a RCP: RCPs - PLACE IN SERVICE) ---------------- g
- b. Start one RCP b. Go to Step 2.
- c. Go to appropriate plant procedure e OP L-1 PLANT HEATUP FROM COLD SHUTD0'aii TO HOT STANDBY
-OR-e OP L-5 PLANT C00LDOWN FROM MINIMUM LOAD TO COLD SHUTDOWN
- 2. Verify Instrument Air - Available Make instrument air available before proceedirg in this procedure. (Refer to OP AP-9 LOSS OF INSTRUMENT AIR)
O DC0010 2V i
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 VfON O DATE 3/7/85 d NATURAL CIRCULATION C00LDOWN PAGE 3 0F 24 TITLE ACTI0fuEXPECTEDRESPON$E RESPONSE NOT OBTMNED
- 3. MONITOR Cooldown
- a. Select natural circulation CRT displays:
e SPDS, Panel A and B e P-250, Group 5
- b. Start recording data every 30 minutes on attached data sheet 4 INITIATE Degassing Of The RCS If hC5 W111 Be Opened:
- a. Implement OP B-1A:VIII, RCS a. -
IF degassing is not 3 DEGASSING possible at this time, s THEN start degassing when conditions permit.
- 5. BORATE RCS Te Cold Shutdowr, Boron Concentration:
- a. Perforr. STF R.19, SHUTDOWN MARGIN CALCULATIGh for the expected shutdown condition
- b. Borate to desired shutdowr.
concentration O V DC0010 3V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/7/85 TiTts. NATURAL CIRCULATION C00LDOWN ACTION /EXPEutu RESPONSE RESPONSE NOT OBTAINED NOTE: The PZR may be borated by the use of PZR aux spray.
- 6. VERIFY Cold Shutdown Baron Concentration By Sampling:
- a. Establish program to obtain samples approximately every 30 minutes until the concentration is verified
- b. Sample:
- 1) RCS hot legs 1 and 4
- 2) PZR liquid volume.
- 3) Letdcwn demin inlet (if available)
- c. Verify cold shutdown baron c. Return to step 5.
concentration - ESTABLISHED
- 7. CHECK VCT Makeup Control System: Adjust controls as necessary.
(CC2)
- a. VCT makeup blend - SET FOR COLD SHUTCCWN BORON C0hc
- b. VCT makeup control system set for automatic control ----------------
l 8. VERIFY ALL CPDM Fans - RUNNING:
- a. P-250 address:
Fan 1 Y1005D Fan 2 Y1006D Fan 3 Y10070 Fan 4 Y1008D l l DC0010 4V
l NUMBER EP E-0.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 l REVISION 1 ; DATE 3/7/85 ; ("T PAGE 5 0F 24 L] T Tts. NATURAL CIRCULATION C00LDOWN ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- b. Locally start all CRDM fans while continuing in this procedure (Refer to OP H-6:I CRDM SHROUD COOLERS - PLACE IN SERVICE)
(Refer to Appendix N and STP M-9M, VERIFICATION OF AUTO LOADS LESS THAN 2750 KW for loads and loadlimits.) CAUTION: e Alternate water sources will be necessary if CST level decreases to less than 101. Refer to E-2.1, ALTERNATE AUXILIARY FEEDWATER SUPPLIES. e On natural circulation, RTD bypass temperatures and associated interlocks for Feedline Iso, High Stm Flow SI and Steam Dump will be inaccurate.
- 9. INITIATE RCS Cooldown To Cold Shutdown:
- a. During the subsequent cooldown and depressurization, maintain criteria listed on the foldout page of this prcceoure
- b. Dump steam to the condenser: b. Dump stear using SG 10'-
(CC-2) steam dumps. Balance use cf dumps to avoid 100 psid SI.
- 1) Set HC-507 at 8.38 turns (CC3)
- 2) Check Ot demand on HC-507 (CC3)
- 3) Transfer te FRESSURE CONTROL MODE ON Steam Dump Selector Switch (CC')c THIS STEP CONTINUED ON NEXT PAGE DC0010 SV
NUMBER EP E-0.2 oiABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 1 DATE 3/7/85 PAGE 6 0F 24 rirts NATURAL CIRCULATION C00LDOWN ACTION /EXH Q tv RESPONSE RESPONSE NOT OBTAINED
- 4) Adjust controller setpoint or manually adjust steam pressure controller to establish desired cooldown rate (Manual is preferred)
- 5) At P-12 activation:
(a) Select BYPASS INTERLOCK on both selector switches (b) Block both trains of high steam flow SI (PK 08-17. HI STM FLO SI ELOCKED)
- 10. CHECK WR RCS T-Hot Terceratures Return to Step 9. OBSERVE
- LESS THAh 550"F (VB2) CAUTION PRECEDING STEP 9.
1 DC0010 6V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/7/85 PAGE 7 0F 24 m LE. NATURAL CIRCULATION C00LDOWN ACTION / EXPECTED RESPONSE ESPONSENOTOBTAINED CAllTION: e Auxiliary spray flow to the PZR shall not be initiated if the delta-t between the PZR and the spray fluid exceeds 560*F. Spray flow should not be initiated if the delta-t exceeds 320*F. (TI-454 and TI-126, CC2/UB2) e SI actuation circuits will automatically unblock if RCS pressure increases above 1915 psig.
- 11. DEPRESSURIZE RCS To Allow Block of PZR Press SI:
- a. Check letdown - IN SERVICE (VS2) a. Try to establish letdown.
- b. Use auxillary spray and b. I,F auxiliary spray is NOT depressurize as follows: desired, THEN use one PZR PORV.
l l 1) Open bc:h PCV-455 A and B, PZR normal spray vivs (CC2)
- 1) Open 8145 or 8148, auxiliary spray vivs (VB2)
- 3) Cicse 81af er.d 8147, normal anc alt charg to LP4 and LP3 cold leg vivs (VB2)
- 4) Control RCS pressure by:
e Adjusting Charging line flow e By bypassing auxiliary spray with PCV-455 A/B e Controlling PZR heater as necessary (CC1/2) ----------------
- c. Block both trains of PZR low pressure SI when RCS pressure less than P-11 (1915 psig)
(CC-2)
- d. Maintain RCS pressure s1865 l l I DC0010 7V I
DiesLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 I ON I DATE 3/7/85 PAGE 8 0F 24 TITLE. NATURAL CIRCULATION C00LDOWN l ACTION / EXPECTED RESf08E RESPONSE NOT OBTAINED
- 12. CONTINUE The Cooldown While Maintaining The Following Conditions:
e RCS pressure - At s 1865 psig e PZR level - 22% to 60% e Maintain the cooldown and depressurization criteria listed on the foldout page of this procedure
- 13. MONITOR RCS Cooldown (SPDS or VB2):
e Core exit TCs - DECREASING e WR RCS T-hot temperatures
- DECREASIfiG e RCS subcooling - INCREASING O
O DC0010 SV
NUMBER EP E-0.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 1 o DATE 3/7/85 V PAGE 9 0F 24' TITLE. NATURAL CIRCULATION C00LDOWN ACTION / EXPECTED RESPONSE ESP 0tdE NOT OBTAINED NOTE: If at any time it is determined that a natural circulation cooldown and depressurization must be performed at a rate that may form a steam void in the vessel, implement E-0.3 or E-0.4 NATURAL CIRCULATION C00LDOWN WITH STEAM V0ID IN VESSEL WITH or WITHOUT RVLIS respectively.
- 14. INITIATE RCS Depressurization While Continuing With The Cooldown:
- a. Verify both trains of PZR low pressure SI blocked; PK 08-1C, PZR SI BLOCKED - ALARMED
- b. Maintain the cooldown and depressurization criteria listed on the foldout page of this procedure
- c. Check CRDM fans - ALL RUhNING c. 1) IF All CRDM fans can NOT be started, THEN cooldown and depress as follows:
- 1) Maintain cooldown and depress criteria cr.
foldout page.
- 2) Obtain max subcooling (200*F) witfout violating 5i tube Ap limit.
- 3) WHEN max subcooling (200*F)is obtained, THEN depressurize RCS to 1200 psig while maintaining 200*
subcooling. THIS STEP CONTINUED ON NEXT PAGE DC0010 9V
NUMBER EP E-0.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 1 DATE 3/7/85 PAGE 10 0F 24 NATURAL CIRCULATION C00LDOWN TITLE {lll ACTION / EXPECTED RESfGSE RESPONSE t0T OBTAINED
- 4) While maintaining RCS pressure at s 1200 psig, cooldown the RCS until:
e RCS average temperatures
- LESS THAN 350*F
-AND-e All four RCS loop WR T-cold - GREATER THAN 323'F.
e Unit 1 only Upper vessel head TCs - LESS THAN
'35*F (T
. for 350 psig). kkIscouldtake s 9 hrs.
- 5) When within plant cooldown curve. (Appendix P)
Begin an RCS depressurization toward 390 psig and go to Step 15.
- d. Maintain RCS subccoling - GREATER ThAN 50*F
- e. Start depre:surizaticr. using aux spray or cr.e PZR FORV and continue coolaown h
DC0010 10V
NUMBER EP E-0.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 1 DATE 3/7/85 f'Td PAGE 11 0F 24 TITLE. NATURAL CIRCULATION C00LDOWN ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 15. CHECK PZR Level - NO UNEXPECTED LARGE Repressurize RCS within limits VARIATIONS of Plant Cooldown Curve to collapse potential voids in system and continue cooldown.
IF RCS depressurization must continue. THEN 90 to E-0.? or E-0.4 NATURAL CIRLULATION C00LDOWN WITH STEAM VOIDS IN VESSEL WITH or WITHOUT RVLIS. - - - - - - - - - -
- 16. CHECK If Accumulators Can Be Isolated: (VB-1)
- a. Check RCS pressure - LESS THAh a. Continue with Step 17.
p) (, 1000 PSIG Perform Step 16 when pressure decreases to <1000 psig.
- b. Rack in the breakers for 8805 A, E, C and D, accum disch iso vivs
- c. Close 8808 A, B, C and D c. IF any accum oisch iso vlv does NOT close.
THEN perform the following:
- 1) Close FCV-8880, accum N2 fill iso viv.
- 2) Open 8875 A, B, C, or D accum N2 supply vent, to affected accum.
- 3) Open HCV 943, accum h2 supply vent UNTIL accum is depressurizeo and continue in this procedure. l l
O ! I l l DC0010 11V
NUMBER EP E-0.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 1 DATE 3/7/85 PAGE 12 0F 24 TITLE NATURAL CIRCULATION C00LDOWN O ACTION / EXPECTED RESP 0fSE RESPONSE NOT OBTAINED
- 17. MAINTAIN Letdown Flow (If Available):
- a. Open additional letdown orifice isolation valves to maintain at least 60 GPM
- b. Adjust PCV-135 to maintain letdown flow with adequate backpressure
- 18. MAINTAIN RCP Seal Injection Flow:
- a. Adjust HCV-142, to maintain s 8 GPM (6 - 12) GPM to each RCP
- 19. VERIFY RHR Eeron Concent-ition GREATER THAN OR EQUAL TO RCS Concentration:
- a. Implement OP 8-2:V, RHR
- PLACE IN SERVICE DURING PLANT C00LDOWN, Part A
- 20. ESTABLISF The Followirc Conditions: Perform the following:
e RCS average temperature - LESS a. Return to Step 14. OBSERVE ThAN 350*F THE NOTE PRECEDING STEP 14. e All four RCS Icop WR T-cold - GREATER THAN 323 F b. Continue cooldown and/or depressurization until e RCS pressure - s 390 psig conditions are met. i 1 DC0010 12V till
N OLABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 3/7/85 \ PAGE 13 0F 24 TITLE. NATURAL CIRCULATION C00LDOWN ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 21. ALIGN For Overpressure Protection:
- a. Disable both SI pumps by opening their DC control power switches and hang CAUTION tag to SFM
- b. Disable all but one centrifugal charging pump by opening DC control power switch and hang CAUTION tag to SFM
- c. PZR low setpoint overpressure protection:
- 1) Check PI-403 and PI-405
- LESS THAN 400 PSIG
- 2) Cut in low setpoint O protection for:
e PCV-455C e PCV-45t
- 22. PLACE RHk System In Service:
- a. Check RCS WR Hot Leg Temp a. Return to Step 14. Observe
- LESS THAN 350"F NOTE prior to Step 14.
- b. Check RCS pressure - s 390 psig b. Return to Step 14. OBSERVE NOTE PRIOR TO STEP I4
- c. Implement OP B-2:V, RHR PLACE Ih SERVICE DURING f'LANT C00LDOWN, Part B ----------------
- 23. CONTINUE RCS Cooldown To Cold Shutdown O
DC0010 13V
NUMBER EP E-0,2 l 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 DATE 3/7/85 PAGE 14 0F 24 7,7 g NATURAL CIRCULATION C00LDOWN ACTION / EXPECTED RESRASE RESPONSE NOT OBTAINED CAUTION: Depressurizing the RCS before the ENTIRE RCS is below 200*F may result in void formation in the RCS.
- 24. CONTINUE Cooldown Of Inactive Portions Of RCS:
- a. Cool upper head region using CRDM a. IF CRDM fans NOT fans available, THEN 00 NOT depressurize RCS UNTIL e 29 hrs have elapsed
- OR -
o Upper head TCs are less than 200F (Unit 1 only)
- b. Cool SG U-tubes by cumping steam from all SGs:
- 1) Maintain SG within chemistry specificaticris
- 2) Durrp stear: until Sbt tave stoppec steaning O
DC0010 lov l 1 i l
NUMBER EP E-0.2 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 ( \ DATE PAGE 3/7/85 15 0F 24 Tirtg NATURAL CIRCULATION C00LDOWN ACTION / EXPECTED RESPONSE RESP 04SE NOT OBTAINED CAllTION: Do not depressurize RCS until: e Upper head temperature - LESS THAN 200*F (U-1 only) e SGs stopped steaming. e The entire RCS is less than 200*F.
- 25. CONTINUE RCS Cooldown:
- a. Implement OP L-5, PLANT C00LDOWN FROM MINIMUM LOAD TO COLD SHUTDOWN, Part C and review for applicable actions
- b. Check RCS and upper vessel head b. Maintain RCS pressure s 350 temperature - LESS ThAh 200*F psig AND Return to Step 24
- END -
O DC0010 15V
DiAsto CANYON POWER PLANT IJNIT NO(S) 1 AND 2 fSf0N DATE 3/7/85 PAGE 16 0F 24 TITLE NATURAL CIRCULATION C00LD0WN ATTACHMENTS
- 1. Data Sheet No. 69-10851, Natural Circulation Cooldown, 9/84
- 2. Plant Cooldown Curve
- 3. Foldout Page O.
1 i I O 1 DC0010 16V l l l
NUMBER EP E-0.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 1 3/7/85 [bN DATE PAGE 17 0F 24 TITLE. NATURAL CIRCULATION C00LD0WN APPENDIX C 2600 .. . . . , _ .
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200 300 400 500 600 700 CORE EXIT T/C TEMPERATURE (*F) DC0010 17'l
NUMBER EP E-0.2 olABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 1 DATE 3/7/85 PAGE 18 0F 24 rirts NATURAL CIRCULATION C00LDOWN APPENDIX N ENERGIZING NON-VITAL 480V BUSSES WITH DIESEL GENERATOR SCOPE The purpose of this procedure is to make available selected non-vital systems to lessen the restriction on recovery until normal 0FF-SITE power is restored. This procedure deals with the situation when both Units are down. All 5 emergency diesel generators may not be available. In this case one unit will be deprived of the swing diesel generator. The selected non-vital systems which are desired to be returned to service are plant instrument air, service cooling water, CROM shroud cooler fans, Turbine Generator lif t pump and turning gear drive, 230KV and 500KV switchyard. DISCUSSION This procedure deals with both units since the plant air compressors are pcwered from either unit and are normally cross connected such that it is common to both units. Therefore, the unit to which the swing diesel 13 is emit *-d wili be responsible for re-energizing tne compressed air systems. Unit 1 is responsible to re-energize the 230 and 500KV switchyard. Any additional loading will be done by Shift g Foreman evaluation for remaining diesel generators capacity. The following is a list of the minimum number of loads required for plant cooldown.
- a. 1 Centrifugal Charging -
507KW
- b. 1 Component Cooling Water -
324KW
- c. 1 Auxiliary Salt Water - 321KW
- d. 3 Containment Fan Coolers -
660KW
- e. 1 Auxiliary Feedwater - 429KW
- f. 1 Pressurizer Heater Group * -
483/207 9 2 480V Motor Control Centers - Refer to STP M-9M for Individual Loads and Intemittent Loads
- 483KW for 7 Heaters; 207 for 3 Heaters DC0010 18V e
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 S ON m DATE 3///85
) PAGE 19 0F 24 TITLE NATURAL CIRCULATION C00LD0hN APPENDIX N (Continued)
PROCEDURE
- 1. Determine which diesel generator will be used as source for the non-vital busses,
- a. On the Unit which has the 13 swing diesel generator available, transfer the maximum number of essential loads to the 4KV bus F and remove all non-essential loads from bus G.
- b. On the Unit which does not have the 13 swing diesel generator available, transfer the maximum number of essential loads to bus G and remove all non-essential loads from bus H.
- 2. Cut out the Auto Transfer FCO's for all 4KV busses and 12KV busses.
,O 3. Depress all Auto Transfer Reset Push Buttons. LJ f0TE: The Auto Transfer Reset will NOT reset and the BLUE light will NOT de-energize for the F bus 7 the 13 diesel generator is operating on the other unit. 4 OPEN or verify OPEN all vital bus 4KV auxiliary feeder breakers, 52-HH-13, 52-HG-13 and 52-HF-13.
- 5. OPEN or verify OPEN all vital bus 4KV startup feeoer brea6 ers, 52-HH-14, 52-HG-14 and 52-HF-14.
- 6. OPEN or verify OPEN startup power to vital busses F, G, h, 52-HG-15.
- 7. OPEN or verify OPEN auxiliary feeder to 4KV non-vital busses D and E.
UhlT 1 UhlT 2 52-HE-2 and 52-HD-15 52-He-14 and 52-HD-4 (3 V DC0010 19V , i
NUMBER EP E-0.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 1 DATE 3/7/85 PAGE 20 0F 24 TITLE. NATURAL CIRCULATION C00LDOWN APPENDIX N (Continued)
- 8. OPEN or verify OPEN startup feeder to 4KV non-vital busses D and E.
UNIT 1 UNIT 2 52-HE-3 and 52-HD-14 52-He-13 and 52-HD-5
- 9. OPEN or verify OPEN startup transformer feeder breaker.
UNIT 1 UNIT 2 52-VD-14 _ 52-VU-23 1C. OPEN ALL eKV feeder t reakers to 480 volt busses and 4KV busses D and E I
- 11. At SFM discretien cut in the FC0 to place all Diesel Generator Protection in service for the Diesel Generator selected to pcwer the non-vital busses.
- 12. Verify all Condensate /Ecoster pump stand-by switches are set in PANUAL.
- 13. Verify the Nash Vacuum purrp is OFF and the No. 2 Heater Drip Punp is 0FF.
- 14. CLOSE the startup feeder breaker to the vital bus.
- a. If the non-vital but power source is UNIT 1 UNIT 2 D/G CLOSE BREAKER D/G CLOSE BREAKER 11 52-HH-14 22 52-HH-14 12 52-HG-14 21 52-HG-14 13 52-HF-14 13 52-HF-14 CAUTI0th If the diesel generatcr appears unstable during the performance of Step 15 or at any time beycnd this point in the procedure, irredia :ely 0 PEN 52-HG-15 to separate the ciesel from the non-vital system, i
- 15. CLOSES $artuppowertovitalbussesF,G,H,52-HG-15.
O l DC0010 20V l 1 i
N otAsLO CANYON POWER PLANT UNIT NO(S) 1 AND E R ON DATE 3/7/85 PAGE 21 0F 24 'virtE. NATURAL CIRCULATICN C00LDOWh APPENDIX N (Continued) NOTE: There will be short load surge on the Diesel Generator as the startup transformer 12 is energized.
- 16. CLOSE startup feeder to 4KV bus D.
UNIT 1 UNIT 2 ! 52-HD-14 52-HD-5
- 17. CLOSE startup feeder to 4KV bus E.
UNIT 1 UNIT 2 52-HE-3 52-HE-13 NOTE: Evaluate the load on the diesel generator prior to energizing each additional load to ensure its reserve capacity is not exceeded. As each additional load is added if the diesel generator overloads it may only be necessary to trip the last load added rather than tripping the entire bus.
- 18. Or. the Unit which has the 13 swing diesel generator carrying the F vital bus energize the following 480V busses.
- a. Energize the following ncn-vital busses.
Uhli 1 UNIT 2 BUS CLOSE BREAKEk BUS CLOSE BREAKER i 150 52-HD-6 250 52-ND-13 11D 52-HD-10 210 52-HD-9
- 19. Return the instrument air system to service as per OP K-1,
- 20. Energize the 500KV switchyard 4KV bus CLOSE 52-HE-7 (U-1 only).
- a. Dispatch an Operator to the 500KV switchyard to verify CLOSED or CLOSE the local 4KV bus feeder breaker in the 500KV switchyard.
- b. Operator should also verify 480V bus is energized ana 500KV switchgear compressed air system is available.
DC0010 21V
DIABLO CANYON POWER PLANT UMT NO(S) 1 AND 2 ON DATE 3/7/85 PAGE 22 0F 24 NATURAL CIRCULATION COOLDOWN TITLE O APPENDIX N (Continued)
- c. Operator should verify 230KV yard 4KV bus is energized via the emergency tie cable and its compressed air system is available.
- 21. Additional loads such as CRDM shroud coolers, turbine generator lift pump and turning gear drive may be made available and their 480V busses energized at the discretion of the Shift Foreman, dependent on diesel generator reserve capacity.
O OO 0C0010 22V O
1 AND 2 NUMBER EP E-0.2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 o DATE 3/7/85 Q TITLE. NATURAL CIRCULATION C00LD0WN PAGE 23 0F 24 APPENDIX h (Continued) M 8t&R& Tot E V. %
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O) ( v' FIGURE ONE: DIESEL GENERATOR LOAD LIMITS DC0010 23V
l l DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 lON DATE 3/7/85 PAGE 24 0F 24 rirts. NATURAL CIRCULATION C00LDOWN 1 APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Notify the Plant Superintendent, Supervisor of Operations and Plant Manager or their designated alternates,
- b. Designate this event a Notification of Unusual Event.
Notify plant staff and response organizations required for this classification by implementing Emergency Procedures G-2
" Establishment of the Organization" and G-3 " Notification of Off-Site Emergency Organization" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plant Activation."
- c. When the cause of the natural circulation cooldown has been determined, this and the subsequent plant ccrditions should be reviewed against the classification criteria in Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation."
O DC0010 24V
PACIFIC GAS AND ELECTRIC COMPANY ' DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 DATA SNEET - NATURAL CIRCUL AT!0h C00LDOWN Note: Recore values approximately every 30 minutes. Date started: By RCS (3) FZR ' LOWEST RCS (2) COOL CCCL LOOF 1 (1) LOOP 2 (1) LOOP 3 (1) LOOP 4 (1) RCS TIME WP TEMP ('F) WP TEWP ('F1 WC TEMP (*F) WR TEMP ('F) SG SUB DOWN HEAD PIR 00u ' PRESS PRESS COOLING RATE TC TEMP RATE In \Tc, Avg Tn\Tc Avg Tn \ Tc Avg 'Th\ Tc Avg (psig) (psig) ('F) (*F/hr) (*F) ('F) 0F/HE N N N N I I N N N N I I I N N N N I I 3 N N N N i i i N N N N I t i N N N N ! I I N N N N I i i i i i N N N N I i i ! i N IN N N I ! I i i ! N iN N N i i i i ! , i l NI iN N N l i ; ; iO N N N N < l i i N N N! N l i I i ' N NI N iN I I i ; I _ ! l i
- N t
N NN i I ! i ' I l I I 1 N N N N ; ' - t N N N N ' i : N N N N I I I i N N N N I I ! 1 ' l N N N N i i I
- 1. Values fror SFDS preferrec. Calculate average from in & Tc values.
- 2. If usirs sutccoling reciter, cefeat head TCs when measuring (toggle switch panel RNICA).
! 3. Coclec n rate s*cule te calculated for ore houe perioc, ng the instantaneeus value. COVyENTS: CC0010 171:1 ___-..,,,-._.,______-.,_,._.2__._.._, _ . _ , _ . _ , _ _ _ . _ _ _ _ _ - _ . _ - - -
i PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 FOLD 00T PAGE FOR E-0.2 NATURAL CIRCULATION C00LD0WN 3 ADMINISTRATIVE FUNCTIONS l
- 1. Notify STA (Monitor Critical Safety Function Status Trees and SPDS).
- 2. Refer to Appendix Z.
MAINTAIN THE FOLLOWING DURING C00LDOWN AND DEPRESSURIZATIONS:
- 1. Cooldown rate in RCS cold legs - LESS THAN 25'F IN ONE HOUR PERIOD.
- 2. PZR cooldown rate - LESS THAN 200*F IN ONE HOUR PERIOD.
l 3. RCS temperature and pressure - WITHIN LIMITS OF TECH SPEC PLANT
- C00LDOWN CURVE.
4 SG tube primary to secondary pressure differential - LESS THAN 1600 PSID. 1
- 5. SG NR level - 4% to 33%.
- 6. No vciding in the vessel upper head:
lf { e Vessel head subcooled locations for upper head TC's: (U-1 only) point core location l 16- H-8
- 21* K-3 25 M-5 j 29 H-5 e PZR level - RESPONSE NORMAL l e RVLIS Narrow or Full Range - GREATER OR EQUAL TO 951.
- - IF voiding is suspected, '
THEN repressurize RCS to collapse void and continue cooldown E AFW 50PFLY SWITCHOVER CRITERION I Switch to alternate AFW water supply.when CST level decreases to less than l. 10%. Refer to EP E-2.1 ALTERNATE AFW SUPPLIES. O
- Vessel upper head TC's 16(H-8)(U-1only and 21(K-3))can be selected to the subcooling monitor, if desired. -
DC0010 261V - 1
NUMBER EP E-0.3 3GsG Pacific Gas and Electric Company REVISION 1 DEPARTMENT OF NUCLEAR PLANT OPERATIONS 1
! DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE .
, NATURAL CIRCULATION COOLDOWN WITH STEAM --
1 TITLE. VOID IN VESSEL (WITH RVLIS) lW IMPORTANT APPROVED - 't DATE SAFETY PLANTMANA@' PURPOSE This procedure provides actions to continue plant cooldewn and depressurization to cold shutdown, with no accident in progress, under conditions that allow for the potential formation of a void in the upper heac region witn RVLIS available to monitor void growth. This procedure and changes thereto requires PSRC review. t SYMPTOMS OR ENTRY CONDITIONS Tnis procedure is entered from EP E-0.2, NATURAL CIRCULATION C00LOOWN, af ter ccmpleting the first thirteen steps, i i i O DC0414 IIII
NUMBER EP E-0.3 1 AND 2 OlABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 PAGE 2 0F 19 NATURAL CIRCULATION C00LDOWN WITH STEAM TITLE: VOID IN VESSEL (WITH RVLIS) h ACTION /D(PECTED RESR14SE RESPONSE NOT OBTAINED CAUTION: e If SI actuation occurs during this procedure E-0, REACTOR TRIP OR SAFETY INJECTION, should be performed. e The first thirteen steps of E-0.2, NATURAL CIRCULATION C00LDOWN should be performed before continuing with this procedure, e This procedure is not for use with an accident in progress. N)TE: e Fold out page should be open. e If conditions can be established for starting an RCP during this procedure, Step 1 should, be repeated. e RCP No. 2 (preferred) or RCP No. I should be given priority to provide normal PZR spray.
- 1. TRY To Restart An RCP: .
- a. Establish conditions for starting a. Go to Step 2. OBSERVE NOTE O
an RCP: PRIOR TO STEP 2. (Refer to OP A_6:I, RCP-PLACE IN SERVICE)
- b. Check RVLIS upper range b. Perform the following:
indication - GREATER THAN 100% (PAM 1/3/4) e Increase PZR level to (CC2/V82) UNIT I UNIT 2 67% 75% e Establish st.bcooling greater than 40 F using stean dump.
\
THIS STEP CONTINUED ON NEXT PAGE O' DC0414 2IV I
NUMBER EP E-0.3 i ABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 [l x/ NATURAL CIRCULATION C00LDOWN WITH STEAM PAGE 3 0F 19
'iT uE-VOID IN VESSEL (WITH RVLIS)
ACTION /EXftutU RESPONSE RESPONSE NOT OBTAINED
- c. Start one RCP (VB-2) c. Go to Step 2. OBSERVE NOTE PRIOR TO STEP 2.
- d. Go to appropriate plant procedure:
e OP L-1 PLANT HEATUP FROM COLD SHUTDOWN TO HOT STANDBY
- OR -
e 0F L-5 PLANT C00LDOWN FROM filNIMUM LOAD TO COLD SHUTDOWN NOTE: Saturated conditions in the PZR should be established before trying to decrease PZR level. (~N ESTABLISH PZR Level To Accomodate
\--) Void Growtn:
- a. Check PZR level - BETWEEN 20% AND a. Control charging and letdown 30% (VE2) as necessary.
- b. Place tc manual, hC-459, PZP level controller (CC2) s DC0414 31V l -
NUMBER EP E-0.3 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/7/85 PAGE 4 0F 19 NATURAL CIRCULATION C00LD0WN WITH STEAM TITLE. V0ID IN VESSEL (WITH RVLIS) ACTION /EX CTED RESFONSE RESPONSE NOT OBTAINED CAlJTION: Auxiliary spray flow to the PZR shall rot be initiated if the delta-T between the PZR and the spray fluid exceeds 560*F. Spray flow should not be initiated if the delta-T exceeds 320*F.
- 3. CONTINUE RCS Cooldown And Initiate Depressurization Towards RHR Entry Conditions:
- a. Maintain cooldown rate in RCS cold legs - LESS THAN 100 F IN ANY ONE HOUR PERIOD
- b. Maintain cooldown and depressurization WITHIN LIMITS OF THE FOLD OUT PAGE
- c. Verify both trains of PZR Icw pressure and high steam flow SI .
BLOCKED (PK08-16/17)
- d. Check letdown - IN SERVICE (VB2) d. Try to establish letdown.
(V82)
- e. Use auxiliary spray to e. E aux spray is NOT depressurize as follows: desired.
THEN use one PZR PORV.
- 1) Open 8145 or 8148, aux spray Go to Step 4 vivs (VB2)
- 2) Close PCV-455A and B, PZR normal spray vivs (CO2)
- 3) Close 8146 and 8147, normal and alt charg to LP4 and LP3 cold leg vivs (VB2)
- 4) Control RCS pressure by adjusting charging flow OR by bypassing auxil:ary spray with PCV-455 A or 8 (CC2)
- 5) Deenergize PZR heater!,, as recessary 1
O DC0414 41V l L f
NUMBER EP E-0.3 , 31/BLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 l REVISION 0 DATE 3/7/85 O TITLE NATURAL CIRCULATION C00LDOWN WITH STEAM V0ID IN VESSEL (WITH RVLIS) PAGE 5 0F 19 ) 1 i l i l ACTION /EXRCT8 RESPONSE RESPONSE NOT OBTAINED
- 4. CONTROL PZR Level:
- a. Level - GREATER THAN 20% a. Control charging and letdown, as necessary to increase PZR level to greater than 20%.
(VB2)
- b. Level - LESS THAh 90% b. Perform the following:
- 1) Turn on PZR heaters to maintain PZR pressure stable. (CCl)
- 2) Decrease PZR level to less than 90L by one of the followino:
/~'N e Control charging and letdown as necessary, (CC2)
- OR -
e Continue cooldnwn to shrink PCS inventory.
- 5. CHECK RVLIS Upper Range indication - Repressurize RCS to maintain GREATER THAN 73% (PAft 1) RVLIS Upper Range greater than 73L. Return to Step 3. (PAM 1)
O DC0414 SIV l
NUMBER EP E-0.3 1 AND 2 OlAsLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 PAGE 6 0F 19 NATURAL CIRCULATION C00LDOWN WITH STEAM TITLE. VOID IN VESSEL (WITH RVLIS) e ACTION / EXPECTED RESPONSE _RESFONSE NOT OBTAINED
- 6. CHECK If Accumulators Can Be Isolated:
- a. Check RCS pressure - LESS THAN a. Continue with Step 7.
1000 PSIG. (VB2) Perform Step 6 when pressure decrease to <1000 psig.
- b. Restore power to 8808 A, 8, C and D, accum disch iso vivs (VB1)
- c. Close 8808 A, B, C and D, c. E any accum disch iso viv accum disch iso viv does NOT close (VB1)
THEN perform the following:
- 1) Close FCV-8880 accum N2.
Fill iso viv.
- 2) Open 8835 A, B, C, 0 accum N2 supply and vent viv to affected accum.
- 3) Open HCV 943 accum N2 supply vent UNTIL accum is depressurized.
- 7. MAINTAIN Letdown Flow (If Available): (VB2)
- a. Open additional letdown orifice isolation valves as necessary
- b. Adjust PCV-135 to maintain letdown flow with adequate backpressure DC0414 61V l
l l
NUMBER EP E-0.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 PAGE 7 0F 19 (U3 TITLE: NATURAL CIRCULATION C00LDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS) ACTION /EXKCTED RESPONSE RESPONSE NOT OBTAINED
- 8. MAINTAIN RCP Seal Injection Flow:
(VB2)
- a. Adjust HCV-142, to maintain s 8 GPM (6 - 12) GPM to each RCP
- 9. VERIFY RHR Boron Concentration GREATER THAh OR E0 VAL TO RCS Concentration:
- a. Implement OP B-2:V, RHR . PLACE IN SERVICE DURING PLANT C00LDOWN
- Part A only
- 10. CHECK If RHR System Can Be Placed Return to Step 3.
In service: (V52) e RCS average temperature - LESS THAN 350'F e All four RCS loop WR T COLD GREATER THAN 323cf e RCS pressure - LESS THAh 390 psig l O V DC0414 71V I i' { -
1 NUMBER EP E-0.3 oiAsLo CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 PAGE 8 0F 19 I NATURAL CIRCULATION C00LD0WN WITH STEAM I TITLE- VOID IN VESSEL (WITH RVLIS) ACTION / EXPECTED RESPONSE RESR)NSE NOT OBTAINED
- 11. ALIGN For Overpressure Protection:
- a. Disable both SI pumps by opening their DC control power switches and hang CAUTION tag to SFM (VB2)
- b. Disable all but one centrifugal charging pump by opening DC control power switch and hang CAUTION tag to SFM (VB2)
- c. PZR lower setpoint overpressure protection: (VB2)
- 1) Check PI-403 and PI-405 - LESS THAN 400 PSIG
- 2) Cut in low setpoint protection for:
o PCV 455C e PCV-456
- 12. PLACE RHR Systen In Service:
- a. Check RCS WR Hot Let Temp - LESS a. Return to Step 3. OBSERVE THAN 350 F (VB2) CAUTION PRIOR TO STEP 3.
- b. Check RCS pressure - LESS THAN b. Return to Step 3. OBSERVE 390 PSIG CAUTION PRIOR TO STEP 3.
- c. Implement OP B-2:V, RHR PLACE IN SERVICE DURING PLANT C00LDOWN, to place RHR in service
- 13. CONTINUE RCS Cooldown To Cold Shutdown DC0414 81V O
i
NUMBER EP E-0.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 PAGE 9 0F 19 k NATURAL CIRCULATION C00LDOWN WITH STEAM TITLE VOID IN VESSEL (WITH RVLIS) ACTION / EXPECTED RESPONSE RESR)NSE NOT OBTAlhE) CAIJTION: Depressurizing the RCS before the ENTIRE RCS is belov 200*F may result in void formation in the RCS.
- 14. CONTINUE Cooldown Of Inactive Portions Of RC5:
- a. Cool upper head region using CRDM a. E all CRDM fans NOT fans available.
THEN 00 NOT depressurize RCS until: e Upper head TCs LESS THAN 200*F (U-l only)
- OR -
e 29 hour soak time has
- b. Cool SG by dumping steam from all SGs:
- 1) Maintain SGs within chemistry specifications
- 2) Dump steam until SGs have stopped steaning O
DC0414 91V
NUMBER EP E-0.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 PAGE 10 0F 19 NATURAL CIRCULATION C00LDOWN WITH STEAM TITLE - VOID IN VESSEL (WITH RVLIS) ACTION /EXRCTED RESR)NSE RESfGSE NOT OBTAINED CAUTION: Do not depressurize RCS until: e Upper head temperature - LESS THAN 200'F (Unit 1 only) e SGs stopped steaming e RVLIS Upper Range - GREATER THAN 95% e Entire RCS less than 200*F
- 15. CONTINUE RCS Cooldown:
- a. Implement OP L-5, PLANT C00LDOWN FR0i! MINIMUM LOAD TO COLD SHUTDOWN, Part C and review for applicable actions
- b. Complete applicable portions of OP L-5 as conditions permit
- c. Check RCS and upper vessel head c. Maintain RCS pressure s 350 temperature - LESS THAN 200 F psig (VB-2/P250)
- AND -
Peturn to Step 14. OBSERVE CAUTION PRIOR TO STEP 14. i i
- END -
DC0414 10lv l l
NUMBER EP E-0.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 O TITLE. NATURAL CIRCULATION C00LDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS) PAGE 11 0F 19 ATTACHMENTS
- 1. Data Sheet No. 69-10851, Natural Circulation Cooldown, 9/84
- 2. Plant Cooldown Curve
- 3. Foldout Page 4
A O DC0414 111V
NUMBER 2P E-0.3 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/7/85 PAGE 12 0F 19 NATUPAL CIRCULATION C00LOCWN WITH STEAM TITLE. VOID IN VESSEL (WITH RVLIS) APPENDIX C 2600 .t.= =.;== = .= c = = : = c== = -: ._ u;==:=/e..J.=, -- /. --
.=:=: =_ u =:= :____ _ e _ ._ ._- _. . _ _ = -=_.u__.
4._._
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=t_= -- r= . .= u===:==1= = """=lp~ ll - *
=:
2400 . == ; = -
. = . . ='~~.2 := = a c_ _ _ ;. _ . ! __ . . - - r-- - _~~._~l =-
_== -- : =-. =:=l====== b=- -:;:/ w a_ : .xtf=.=
= . - - - - - + - -_. -f =p'/= ' ~ ^ - ~:=g i_ --~
= . . _,
-~
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~~
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-i.-- r. -.. ._:
.._____4_..__ , _ ,; _ .. .
(1 = :._.. ...
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_ _ _ . . . _ . _ _ . .- EE_= = i c 2000 _ _ . _ . ~ . . . _ _ ,
+
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. _ i: =_ . _ _. Te _=t.=___.=__-.. .
._. = _: . = :-=~-_- .._
~ -
n .= = . = = t = . = j~== j==~~"- t = :"- 1800
-.. . ~._~~#'~~~ ~
= '
~
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!_i--!=+ _!i.sl_:_%s:=... __==_,ise.4. pJ. .h- .!=_ .
- = :=_ == ; = = = - = t.g= 3 3: _5:___ g _--t= =f; . . . ._3 55=
~ - ..
+ :_- y=---
= = : = = -y=- _. -_=:= : ; - -. t =: . : = i = = V_= l=- =: l'.- - - --
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. ._ t == SATURATION CURVE =-~-4= - SATURATICN :=
~~
5 --: .- . . - CORRECTED FOR _..
- CURVE
= ~ ~~'~~ *' ~=1 ==
1000 INSTRUMENT ERROR =
"a g -:- __=_.r. = - - - --
- r_ . ___ _ ;__.. _. .12 . _. g. _. . z./- _/3
==t=: _. : - .;_ _ _
-- - - - -- - - i
___._._-.__r.___.t---. .___= m --- {_=_. ;- ;/+ _- /___ _.r: g- == 4' __ _ r. - - g _ m - 4 _ = _ _ ;;. .:_ .. . __: . . i .-. .- r
.-. . __ . . . .:= 2 : 2_ . . .
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- _1. =/ ;/. : e .=. . _. ::
= ..._
=---F = _t : n---
_...__ ,_ -.._ _ ,. _.__ ;; ._. g_ _ _ __ _ i .=j -. - ,,r . =. . ;;. .. _ p.._ ;._..
= =.
=.._ + --4_ i /=-/. ._. _ _L _ __.; t- ::=_ _ _
600 . . . . _ _ _ . _ . _ . . _ .. _= :.;_...+ _ _ _ _._== =..__..g__::].._:/. -~-- . _ [g_.=_~..u
= =, =.:..y = =_
_ . + ygj--f- . :_u=
+-- '
400
._.==_=..i===_.i_----
. - -t=--- f; f_:/. - %, ,- - . = = i. - A s.= t h .= t._.h.. .-. t:. .
~
---- i ~=#= = ~~ ~ ~ = % g.' PRESSURE ERROR + 65 psig' .
200 TEfPERATURE ERROR I 24 F C _ : 1= p__= _-
- * * *--- T - = . ~ q . . _ . o. ..
t.-..=__._; '"
......_.4_..;----
- t. _4._. ._4.._.__4 ..._.4
. .;^ .bb . f : b.$ kh.-'[:b2.bE-5.'" . _b ' .; :$ li 200 300 400 500 600 700 CORE EXIT T/C TEMPERATURE (*F)
O DCC414 121V
NUMBER EP E-0.3 DIAsto CANYON POWER PLANT UNIT NJ(S) 1 AND 2 REVISION O DATE 3/7/85 g) i PAGE 13 0F 19 d NATURAL CIRCULATION C00LDOWN WITH STEAM TITLE. VOID IN VESSEL (WITH RVLIS) APPENDIX N ENERGIZING NON-VITAL 480V BUSSES WITH DIESEL GENERATOR SCOPE The purpose of 1.his procedure is to make available selected non-vital systems to lessel the restriction og recovery until normal 0FF-SITE power is restored. This procedure deals with the situation when both Units are down. All 5 emergency diesel generators may not be available. In this case one unit will be deprived of the swing diesel generator. The selected non-vital systems which are desired to be returned to service are plant instrument air, service cooling water, CRDM shroud cooler fans, Turbine Generator lift pump and turning gear drive, 230KV and 500KV switchyard. DISCUSSION This procedure deals with both units since the plant air compressors are powered from either unit and are normally cross connected such f)V that it is corron to both units. Therefore, the unit to which the swing diesel 13 is omittec will be responsible for re-energizing the compressed air systems. Unit 1 is responsible to re-energize the 230 and 500KV switchyard. Any accitional loading will be done by Shift Foreman evaluation for remaining diesel generators capacity. The following is a list of the minimum number of loads required for plant cooldown.
- a. 1 Centrifugal Charging -
507KW
- b. 1 Component Cooling Water -
324KW
- c. 1 Auxiliary Salt Water -
321KW
- d. 3 Containment Fan Coolers -
660KW
- e. 1 Auxiliary Fcedwater -
429KW
- f. 1 Pressurizer Heater Group * -
483/207
- g. 2 480V Motor Control Centers -
Refer to STP M-9M for Individual Loads and Intermittent Leads
- 483KW for 7 Heaters; 207 for 3 Heaters V
DC0414 131V
NUMBER EP E-0.3 1 AND 2 OlABLO CANYON POWER Pt. ANT UNIT NO(S) REVISION 0 DATE 3/7/85 PAGE 14 0F 19 NATURAL CIRCULATION C00LDOWN WITH STEAM TITLE. VOID IN VESSEL (WITH RVLIS) APPENDIX N (Continued) PROCEDURE
- 1. Determine which diesel generator will be used as source for the non-vital busses,
- a. On the Unit which has the 13 swing diesel generator available, transfer the maximum number of essential loads to the 4KV bus F and remove all non-essential loads from bus G.
- b. On the Unit which does not have the 13 swing diesel generator availab'e, transfer the maximum number of essential loads to bus G and*
remove all non-essential loads from bus H.
- 2. Cut out the Auto Transfer FC0's for all 4KV busses and 12KV busses.
- 3. Cepress all Atte Transfer Reset Push Buttons.
fCTE: The Auto Transfer Reset will NOT reset and the BLUE light will NOT de-energize for the F bus 7 the 13 diesel generator is operating on the other unit. 4 OPEN or verify OPEN all vital bus 4KV auxiliary feeder breakers, 52-HH-13, 52-HG-13 and 52-HF-13.
- 5. OPEf; cr verify OPEh all vital bus 4KV startup feeder breakers, 52-HH-14, 52-HG-14 and 52-HF-14.
- 6. OPEN or verify OPEN startup power to vital busses F, G,1.
52-HG-15.
- 7. OPEN or verify OPEN auxiliary feeder to 4KV non-vital busses D and E.
Utili 1 UNIT 2 52-HE-2 and 52-HD-15 52-He-14 and 52-HD-4 O 000414 141V
1 AND 2 NUMBER EP E-0.3 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 9 TITLE NATURAL CIRCULATION C00LDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS) PAGE 15 0F 19 APPENDIX N (Continued)
- 8. OPEN or verify OPEN startup feeder to 4KV non-vital busses D and E.
UNIT 1 UNIT 2 52-HE-3 and 52-HD-14 52-He-13 and 52-HD-5
- 9. OPEN or verify OPEN startup transformer feeder breaker.
UNIT 1 UNIT 2 52-VU-14 52-VU-23
- 10. OPEN ALL 4KV feeder breakers to 480 volt busses and 4KV busses D and E.
- 11. At SFit discretion cut in the FC0 to place all Diesel Generator Protection in service for the Diesel Generator selected to power the non-vital busses.
- 12. Verify all Concersate/ Booster pump stand-by switches are set in PANUAL.
- 13. Verify the Nash Vacuum purp is 0FF and the No. 2 Heater Drip Purp is OFF.
14 CLO5E the star tup feeder breaker to the vital bus.
- c. If the r.cr.-vital bus povier source is UNIT 1 UNIT 2 D/C CLOSE BREAAER D/G CLOSt BREALER 11 52-HH-14 22 52-HH-14 12 55.-HG-14 21 52-HG-14 13 L2-HF-14 13 52-HF-14 O
DC0414 151V
NUMBER EP E-0.3 1 AND 2 REVISION 0 OIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/7/85 PAGE 16 0F 19 NATURAL CIRCULATION C00LDOWN WITH STEAM TITLE V0ID IN VESSEL (WITH RVLIS) APPENDIX N (Continued) CAUTION: If the diesel generator appears unstable during the performance of Step 15 or at any time beyond this point in the procedure, immediately OPEN 52-HG-15 to separate the diesel from the non-vital system.
- 15. CLOSE startup power to vital busses F, G, H, 52-HG-15.
f0TE: There will be short load surge on the Diesel Generator as the startup transfomer 12 is energized.
- 16. CLOSE startup feeder to 4KV bus D.
UNIT 1 UNIT 2 52-HD-14 52-HD-5
- 17. CLOSE startup feeder to 4KV bus E.
UNIT 1 UNIT 2 52-HE-3 52-HE-13 f0TE: Evaluate the load on the diesel generator prior to energizing each additional load to ensure its reserve capdcity is not exceeced. As each additional load is added if the diesel generator overloads it may only be necessary to trip the last load acced rather than tripping the entire bus.
- 18. On the Unit which has the 13 swing diesel generator carryir,g the F vital bus energize the following 480V busses,
- a. Energize the following non-vital busses.
UNIT 1 UNIT 2 BUS CLOSE BREAKER BUS CLOSE BREAKER 150 52-HD-6 25D 52-HD-13 110 52-HD-10 210 52-HD-9
- 19. Return the instrument air system to service as per OP K-1.
O DC0414 161V
NUMBER EP E-0.3 otAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 r"' DATE 3/7/85 ()s NATURAL CIRCULATION C00LDOWN WITH STEAM PAGE 17 0F 19 TITLE. VOID IN VESSEL (WITH RVLIS) APPENDIX N (Continued)
- 20. Energize the 500KV switchyard 4KV bus CLOSE 52-HE-7 (U-1 only),
- a. Dispatch an Operator to the 500KV switchyard to verify CLOSED or CLOSE the local 4KV bus feeder breaker in the 500KV switchyard.
- b. Operator should also verify 480V bus is energized and 500KV switchgear compressed air system is available.
- c. Operator should verify 230KV yard 4KV bus is energized via the emergency tie cable and its compressed air system is available.
- 21. Additional loads such as CRDM shroud coolers, turbine generator lif t purrp and turning gear drive riay be made available and their 480V busses energized at the discretion of the Shift Foreman, dependent on diesel generator reserve capacity.
O O DC0414 171V l
NUMBER EP E-0.3 1 AND 2 REVISION 0 OtABLO CANYON POWER PLANT UNIT NO(S) DATE 3/7/85 PAGE 18 0F 19 NATURAL CIRCULATION C00LOOWN WITH STEAM TITLE- VOID IN VESSEL (WITH RVLIS) APPENDIX N diCM RATot EV. %
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I?L - r . s8 - - - I a. 1 . i Gh4 e6**e. - e FIGURE ONE: DIESEL GENERATOR LOAD LIMITS h DC0414 181V 1 _
NUM'BER EP E-0.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 fm DATE 3/7/85 l PAGE 19 0F 19
- O NATURAL CIRCULATION C00LDOWN WITH STEAM TITLE VOID IN VESSEL (WITH RVLIS)
APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency proceaure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Notify the Plant Superintendent, Supervisor of Operations and Plant Manager or their designated alternates.
- b. Designate this event a Notification of Unusual Event.
Notify plant staff and response organizations required for this classification by implementing Emergency Procedures G-2
" Establishment of the Organization" and G-3 " Notification of Off-Site Emergency Organization" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plant Activation."
- c. When the cause of the natural circulation cooldown has been determined, this and the subsequent plant conditions should (n) be reviewed against the classification criteria in Erergency v Procedure G-1 " Accident Classification and Emergency Plan Activation."
O DC0414 191V
PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIA8LO CANYON POWER PLANT UNIT N05. 1 AND 2 DATA SHEET - NATURAL CIRCULATION C00LDOWN t O Note: Record values approximately every 30 minutes. Date started: By l RCS (3) PZR LOWEST RCS (2) COOL COOL LOOP 1 (1) LOOP 2 (1) LOOP 3 (1) LOOP 4 (1) RCS SG SUB DOWN HEAD PZR 00'a'N TIME WR TEMP ('F) WR TEMP (*F) WR TEMP ('F) WR TEMP ('F) PRESS PRESS COOLING RATE TC TEMP RATE Th\Tc Ava Th\Tc Ava Th \ Tc A=a Th A Tc Ave (osic) (psic) ('F) ('F/hr) ('F) ('F) 0F/HR i N N N N N N N N N N N N , N N N N ! N N N N l N N N N N N N N N N N N j N N N N I N N IN N I I N N N N O N N' N N I I I i I N N N N N N N N N NI N N ; ! I N N N N ) N N N N I I I N N N N
, N N N N N N N N N N N N
- 1. Values from $F05 preferred. Calculate average from Th 8 Tc values.
2. If using subcooling eenitor, defeat head TCs ween measuring (toggle switch par.el RNICA).
- 3. Cooldown rate should be calculated for one hour period. M the instantanecus value.
COM?ENTS: DC0010 1711! !
. - _ _ - - - _ . . _ . - ~ - - _ _ , , _ . . . . - - .- _ . . _ . . , , .
FOLDOUT PAGE FOR E-0.3 NATURAL CIRCULATION C00LDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS) i ADMINISTRATIVE FUNCTIONS l
- l
- 1. Notify STA (Monitor Critical Safety Function Status Trees-and SPDS) i
- 2. Refer to Appendix Z.
1 t MAINTAIN ThE FOLLOWING DURING C00LDOWN AND DEPRESSURIZATIONS:
- 1. PZR cooldown rate - LESS THAN 200'F IN ONE HOUR PERIOD.
- 2. RCS temperature and p: essure - WITHIN LIMITS OF TECH SPEC PLANT C00LD0WN CURVE.
- 3. RCS subcooling based on core exit TCs 40*F.
- 4. SG tube primary to secondary pressure differential - LESS THAN 1600 PSIO.
i
- 5. SG NR level - 4% to 331.
- 6. Monitor voiding in the vessel upper head:
i o Locations for upper head TCs: (Unit 1 only) 1 . point core location
*16 H-8 j *21 K-3 25 M-5 i 29 H-5 e PZR level - 20*. to 90%
e RVLIS Full Range - GREATER OR EQUAL TO , IF voiding exceeds RVLIS linit, TREN repressurize RCS to recover RVLIS level. i AFW SUPPLY SWITCHOVER CRITERION l Switch to alternate AFW wacer supply when CST level decreases to less than 10t. Refer to EP E-2.1, ALTERNATE AFW SUPPLIES. I r
- Upper vessel head TCs 60 (H-S) and 21 (K-3) can be selected to the subcooling monitor, if desired. (U-1only)
DC0414 21III
NUMBER EP E-0.4 3 @;i3 Pacific Gas and Electric Company REVISION 0 m DATE 3/7/85 DEPARTMENT OF NUCLEAR PLANT OPERATIONS 1 AND 2 N I F 22 f DIABLO CANYON POWEA PLANT UNIT NO(S) EMERGENCY PROCEDURE l NATURAL CIRCULATION C00LDOWN 41TH STEAM VOID -- If TITLE IN VESSEL (WITHOUT RVLIS) W
, IMPORTANT APPROVED if f Mm 46 DATE TO PLANTMANAdp SAFETY SCOPE This procedure provides actions to continue plant cocidown and depressurization to cold shutdown, with no accident in progress, under conditions that allow for the potential formation of a void in the upper head region without RVLIS available to monitor void growth.
This procedure and changes thereto requires PSFC review. SYMPTOPS OR ENTRY CON]ITIONS This procedure is entored from EP E-0.2, NATURAL CIRCULATI0t. C00LDOWN, af ter cer:pieting the first thirteen steps. O DC0257 11V i _.
NUMBER EP E-0.4 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 PAGE 2 0F 22 TITLE NATURAL CIRCULATION C00LD0WN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS) g ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED_ CAUTION: e If SI actuation occurs during this procedure, E-0, REACTOR TRIP OR SAFETY INJECTION should be performed, e The first thirteen steps of E.0.2, NATURAL CIRCULATION C00LDOWN should be performed before continuing with this procedure, e This procedure is not for use with an accident in progress. N]TE: e Foldout page should be Opeo e it co.ct'or s can be established for starting an RCP during this procedure, Step 1 shculd be repeated, e RCF f;c. 2 (preferred) cr FCP f.o. I should be giver, pricrity tc provide r.crral PZR spray.
- 1. TP Y To P e,s t a r,t, ,An f,C P : (VB2)
- a. Establish cer,ditiens for starting e. Go to Step 2. OBSERVE NOTE an RCP. (Refer tc CP A-6, PRIOR TO STEP 2.
PCPs - PLACE IN SERVICE)
- b. Check PZR level - 6fEATER TFA*. b. Ccr tr ol cta rgir s and letdcv;c as necessary to increase U_! lesel to greater ttan q-TIT T. " ~ "' WIY Y " "
_ _ . . _ g. ...........y..g.......
~6Tu **
i5% ~~**
. . . . . .~~.". .'.:. . - . .-
- c. RCS subccoling . GkEATER THAN c. Establish subcooling based 40'F on core exit TCs greater than 40 F using steam dump.
- d. Start one RCP d. Go to Step 2. OBSERVE NOTE PRICR TO STEP 2.
1H15 STEP CONTINUED ON NEXT PAGE O DC0257 ?!V
NUMBER EP E-0.4 OlA3LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION O DATE 3/7/85 q PAGE 3 0F 22 mg NATL'RAL CIRCULATION C00LDOWN WITH STEAM V0ID IN VESSEL (WITHOUT RVLIS) ACTION / EXPECTED RESPONSE RESFUiSE ff]T OBTAltED
- e. Go to appropriate plant procedure e OP L-1 PLANT HEATUP FROM COLD SHUTDOWN TO HOT STANDBY
-0R-e 0P L-5 PLANT C00LDCWN FROM MINIMUM LOAD TO COLD SHUTDOWN NOTE: Saturated conditions in the PZR should be established before trying to decrease PZR level.
- 2. ESTABLISH PZR Level To Accorrecate voic Growtn:
- a. Check PZR level - EETWEEN 20t AC a. Control charging and letdown 25% (CC2/VE2) as necessary.
- b. Place PZR level contrci in manual (CC2)
- 3. DECREASE RCS Hot Lec Temperatures To 500;F:
- a. Maintain cocidown rate in RCS colc legs - LESS THM, ECJF/HR
- b. Painteir RCS pressurc - (T 1865 PSIG C. Maintain CColdown and depressurization criteria listed on the foldout par,e
- d. Maint61n stable PZR level using charging between 20% and 25%
- e. Check RCS het leg terceratures - c. Return to Step 3a.
LESS THAN 5'10*F
- f. Stop RCS cooldown O
DC0257 31V
NUMBER EP E-0.4 1 AND 2 otABLO CANYON POWED PLAttT UNIT NO(S) REVISION 0 ; DATE 3/7/85 PAGE 4 0F 22 7,7 g NATURAL CIRCULATION C00L00WN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS) h ACTION / EXPECTED ESP 0fGE ESPONSE NOT OBTAINED CAUTION: Auxiliary spray flow to the PZR shall not be initiated if the delta-T between the PZR and the spray fluid exceeds 560*F. Spray flow should not be initiated if the delta-T exceeds 320*F.
- 4. DEPRESSURIZE RCS To 1600 PSIG: (VB2)
- a. Verify both trains of PZR Icw a. Block low pressure SI (CC2) pressure BLOCKED (PK8 16 per SI Blocked)
- b. Verify high steam flow SI-blocked b. Block when P-12 activated.
(PK8-17 Hi Stm Flo SI blocked)
- c. Check letdcwn - IN SERVICE (VB2) c. Try to establish letdown.
- d. Use auxiliary spray to IF auxiliary spray is NOT depressurize as follows: (VB2) IIisired, THEN use nne PZR PORV. Go to
- 1) C;en 8145 or 8148, PZR aux Step 4e.
spray vivs
- 2) Close both PCV-455 A and B.
PZR r:rral spray sivs
- 3) Close 8146 and 8147, nomal and alt charg to LP4 and LP3 cold leg vivs
- 4) Control RCS pressure by adjusting Charging flow or by bypassing auxiliary spray with PCV.455 A/B (VB2)
- 5) Deenergize PZR heaters as recessa ry
- e. Check RCS pressure - LESS THAN e. Return to Step 4a.
1600 PSIG (CC2/VB2)
- f. Stop RCS depressurization DC0257 4IV
1 AND 2 NUMBER EP E-0.4 0:AsLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 i I I PAGE 5 0F 22 7,7g ~ NATURAL CIRCULATION C00LDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS) ACTION /EXPECTRg.S.fUsf RESPONSE f0J.0ATAJ1EL f0TE: RCS hot leg temperature will decrease after cooldown is stopped due to decrease in loop AT.
- 5. DECREASE RCS Hot Leg Temperatures To 450*F: (VB2)
- a. Maintain cooldown rate in RCS cold legs - LESS THAN 100* in any one hour period
- b. Maintain RCS pressure . AT 1600 PSIG
- c. Maintain cooldown and depressurization criteria listed on foidout page
- d. Maintain stable PZR level using l l cha cing
- e. Check RCS hot leg terperatures - e. Return to Step Sa.
LESS THAN 450'F
- f. Stop PCS coS1d ur POTE: PZR level is being used to conitor RCS vessel void growth. Tnis requires mair.tairirg ficw into the RCS equal to flew cut of the RCS.
- 6. EOUALIZE Chargirc Ard Le:dcvtr Flows:
(VB2/CC2)
- a. Place charging in manual
- b. Control charging and seal iniection flows to equal letdown and seal leakoff ficws l
(I DC0257 51V
NUMBER EP E-0.4 1 AND 2 REVISION O OIABLO CANYON POWE] PLANT UNIT NO(S) DATE 3/7/85 PAGE 6 0F 22 TITLE NATURAL CIRCULATION C00LDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS) h ACTION /EXWCTED RESPONSE RESPONSE NOT OBTAINED
- 7. MAINTAIN RCP Seal Injection Flow:
- a. Adjust HCV-142 as necessary to maintain s 8 gpm (6 - 12 gpm)
(CC2) POTE: The upper head region may void during depressurization. This will result in a rapid?y increasing PZR level.
- 8. DEPRESSURIZE PCS: (VB2)
- a. Check letdewn . IN SERVICE a. Try to establish letdown.
- b. Use auxiliary spriy, while b. ,I_F, auxiliary spray is f.0T maintaining charging and Itdn desired, balance THEN use o,e PZR PORV.
Go to Step 8c.
- c. Cepressurize RCS until either of the folicwing conditions are satisfied:
e RCS pressure . LESS THAN 600 PSIG
. (J .
e PZR level - GREATEA TPAN 90;
- d. Stop RCS depressurizatio.i O
nx
NUMBER EP E-0.4 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 4 g PAGE 7 0F 22 TITLE. NATURAL CIRCULATION C00LDOWN WITH STEAM V0ID IN VESSEL (WITHOUT RVLIS) ACTION /EXECTED RESPONSE RESPONSE NOT OBTAINEI) g: In order to continue overall system depressurization, it may be necessary to cycle PZR level (cycle pressure). This will enhance upper head cooling by forcing cooler water into upper head area.
- 9. CHECKp2RLevel-LESSTHAN'90%(VB2) Increase RCS pressure by 100 psi using PZR heaters. Return to Step 8. Observe NOTE prior to Step 8.
- 10. CHECK If Accumulators Can Be Isolated:
- a. Check FCS pressure - LESS THAN a. Continue with Step 11.
1000 PSIG (VB2) Perform Step 10 when pressure decrease to <1000 psig.
- b. Restore power to 880e A B C and i ) 0, accur cisch isc vivt (V22) v '
- c. Cicse 880? A, F. C ard D c. -
!F any accun disch isc viv does NOT close, THEN perform the following:
- 1) Cicse FCV.8380 accum 42 fill iso viv.
- 2) Open 857E A, P C, 0 accum f.2 supply vent te affected accur.
- 3) Open HCV 943 accure N2 supply vent UNTil accum is depressurized.
I o DC0257 71Y l
1 AND 2 NUMBER EP E-0.4 OIABLO CANYON POWE] PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 PAGE 8 0F 22 TiTu' NATURAL CIRCULATION COOLDOWN WITH STEAM V010 IN VESSEL (WITHOUT RVLIS) ACTION / EXPECTED ESFff]SE ESPONSE f0T OBTAINED
- 11. DECREASE RCS Hot Leg Temperatures To 400"F:
- a. Maintain cooldown rate in RCS cold legs - LESS THAN 100' in any one hour period (VB2)
- b. Maintain RCS pressure . STABLE
- c. Maintain cooldown and depressurization criteria listed on foldout page
- d. Maintain stable PZR level using charging
- e. Check RCS not leg temperatures . e. Return to Step 11a.
LESS TPAN 400'F
- f. Stop RCS cooldcan g
- 12. ECUALIZE Charging And Letdown Flows;
- a. Open additional letdown crifice valves as necessary to maintain letdan flow (VB2)
- b. Centrol chargirg and seal injection flows to equal letdcwn and seal leakoff flows (CC2)
- c. Adjust HCV-142, to maintain N 8 (6-12) GPM to each RCP (CC2)
DC0257 81V O
NUMBER EP E-0.4 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 (~) g PAGE 9 0F 22 7,7g ~ NATURAL CIRCULATION C00LDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS) ACTION /EXPECTE RESPONSE RESPONSE NOT OBTAINED
- 13. DEPRESSURIZE RCS: (VB2)
- a. Check letdown - IN SERVICE a. Try to establish letdown.
- b. Use auxiliary spray b. E auxiliary spray is NOT desired, THEN use ONE PZR 00RV.
Go to Step 13c.
- c. Depressurize RCS until either of the following conditions satisfied:
e RCS pressure - LESS THAN 600 PSIG
- GR -
e PZR level . GREATEP THAN 90%
- d. Stop RCS depressurization
- 14. CHECK PZP Level - LESS THAN 90i (VB2) Increase RCS pressure by 100 psi using PZR heaters. Return to Step 13.
1 l I O l l DC0257 91V
Nt'MBER EP E-0.4 1 AND 2 otAsLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 PAGE 10 0F 22 7,7g' NATURAL CIRCULATION C00LDOWN WITH STEAM VOID g IN VESSEL (WITHOUT RVLIS) W ACTION / EXPECTED PESPONSE RESPONSE NOT OBTAINED
- 15. ESTABLISH the Following Conditions:
- a. Maintain cooldown rate in RCS cold legs - LESS THAN 100* in any one hour period (VB3/CC3)
- b. Maintain RCS pressure - STABLE (VB3)
- c. Maintain cooldown and depressurization criteria listed on foldout page
- d. Maintain stable PZR level using charging (VE2)
- e. Check RCS hot leg temperature - e. Go to Step 15a.
LESS THAN 350 F (VB2)
- f. Check RCS celd leg terperature -
GREATER THAN 323 F
- f. Go to Step 159.
h
- g. Stcp RCS Cooldcwn
- 16. VERIFY RHR Scrcr Concentration GREATER Tr1AN OR EQUAL TO RC5 Concentration:
- a. Inplement OP B-2:V, RHR - PLACE Ib SERVICE DURING PLANT C00LDOWN, part A only O
DC0257 10lV
NUMBER EP E-0.4 DIAsLO CANYON POWER PUNT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 PAGE 11 0F 22 7,7g' NATURAL CIRCULATION C00LDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS) ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 17. EQUALIZE Charging And Letdown Flows: (V52)
- a. e Check :harging controls in manual e Adjust PCV-135 as necessary
- b. Oper. additional letdown orifice i isolation valves to maintain charging flow and seal injection flow to equal letdown or seal leakoff ficws
- 18. DEPRESSURIZE RCS: (VB2)
- a. Check letdown - If4 SERVICE a. Try to establish letdown.
D. Use auxiliary spray b. IF_ auxiliary spray is NOT desired, THEN use one PZR PORV. Go to step 18c.
- c. Cepressurize RCS ur,til either of the following conditions satisfied:
e RCS pressure - LESS THAN 390 PSIG
- OR -
e PZR level - GREATER THAN 90%
- d. Stop RCS depressurization 1
A U DC0257 111V ;
~
l t l
NUMBER EP E-0.4 OlABLO CANYON POWER PLANT UNIT NO(S) 1 AhD 2 REVISION 0 DATE 3/7/85 PAGE 12 0F 22 7,7 g NATURAL CIRCULATION C00LDOWN WITH STEAM V0ID IN VESSEL (WITF0VT RVLIS) h ACTION / EXPECTED RESFU GE RESF0NSE NOT OBTAINED
- 19. CHECK PZR Level - LESS THAN 90% Increase RCS pressure by 100 psi (VS2/CC2) using PZR heaters. Return to Step 18.
- 20. ALIGN For Overpressure Protection:
- a. Disable both SI pumps by opening their DC control power switches and hang CAUTION tag to SFM
- b. Disable all but one centrifugal charging pump and hang CAUTION tag to SFN
- c. PZR low setpoint overpressure protection: (VB2)
- 1) Check PI-403 and PI 405 - LESS THAN 400 PSIG
- 2) Cut in icw setpoint protection for:
o PCV 455C e PCV-456
- 21. PLACE RHR Systen In Service:
- a. Check RCS hot leg tenp - LESS a. Return to Step 15.
THAN 350;F (V82)
- b. Check RCS pressure - LESS THAN b. Return to Step 18.
390 PSIG (VB2)
- c. Refer to OP B-2:V, RHR PLACE IN SERVICE DURING PLANT C00LD0WN, for details l ..
O DC0257 12!V I 1
NUMBER EP E-0.4 l 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0
- DATE 3/7/85 PAGE 13 0F 22 7,7 g NATURAL CIRCULATION C00LDOWN WITH STEAM V0ID IN VESSEL (WITHOUT RVLIS)
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. CONTINUE RCS Cooldown To Cold Shutdown CAUTION: Depressurizing the RCS before the ENTIRE RCS is below 200 F may result in void additional formation in the system.
- 23. CONTINUE Cooldown of The Foilowing Inactive Portions Of RC5:
- a. Cool upper head region using CRDM a. E all CRDM fans NOT fans available, THEN 00 NOT depressurize RCS until:
e Upper head TCs - LESS THAN 200 F (Unit I only),
-0R-e 29 hour soak time has elapsed.
- t. Cool SG U *ut.es by cur 4ing steam from all SGs:
- 1) Maintain SG within chemistry specifications
- 2) Dump steam until SGs have .
stopped steaming
- c. Maintain PZR level GREATER THAN 20%
! DC0257 131V ( l
NUMBER EP E-0.4 1 AND 2 DIABLO CANYON POWER PLANT UMT NO(S) REVISION 0 DATE 3/7/85 PAGE 14 0F 22 7,7 g NATURAL CIRCULATION C00LDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS) ACTION / EXPECTED RESR)NSE RESPONSE NOT OBTAINED CAUTION: Do not depressurize RCS to atmosphere until: e Upper head temperature - LESS THAN 200*F e SGs stopped steaming.
- 24. CONTINUE RCS Cooldown:
- a. Implement OP L-5, PLANT C00LDOWN FROM MINIMUM LOAD TO COLD SHUTDOWN, Part C and review for applicable actions
- b. Check RCS and upper vessel head b. Maintain RCS pressure s 350 tenperature - LESS THAri 200 F psig At;D Return to Step 23. OBSERVE CAUTION PRIOR TO STEP 23.
O
- Et.D -
DC0257 14IV l
1 i 1 AND 2 NUMBER EP E-0.4 I DIAstO CANYON POWER PLANT UNIT NO(S) REVISION 0 O DATE PAGE 3/7/85 15 0F 22 1 7,7g~ NATURAL CIRCULATION C00LDOWN WITH STEAM V0ID IN VESSEL (WITHOUT RVLIS) APPENDIX C 2600 . . _
. ._ - , _ ah_ . I-----
. - -_ 4 _.._. . .__]_. . .
t .._ - _d_ =_. =_ . . . . .
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. ._EE. Ei - 1. E__=_-EZ-- ..
_4 L _=__E_=_. :. =2=EN-~.~._._21=__.-/..F./.E_.~.
. = n _u n == =t- n- -._ ==--pn= :=f'=a t}'==
- i. =- =:=r _a _=
gg00 . = 7 = = , , , , _ p_ _ _ . _;_ =_j=j - : -
-> : -i .
4-.-.--.- _
=g{ --
2000
- - - - - - " - - --' - " - ' - ~ " '~~'~
..=_2.-- - - ---4 . q _ =_n: - 22. . 4 <- #-4
==_: = . _ . _ .m ___ ___ w t__
_t:_.___3__ . __r./_/24 _ :3_ .: -- + = q __:4__:= ; g p = 22.2 x =__ ; ==r _r =.u----
---._--'--~~:-----"---". :
^
- - ~
- 1800 .. ..-
e _ =_ _. :a r.2 = a= =; - -- -i=2_2}:_ u=p
- - -- /j=/ -- t---'
__.-...1.'t.. _4 ~ ~ -- : : .- r . _ :-. -- 3. _ _ . _ j ._ _ [" * -. / =-- ; =--- : +
- n. p -~ ~ ~ ~~~~~ " ~~ ~
" ~ ~j "*;g".
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. 2 ---J =
(v,
- 1600 4
==- 2 - - - - -
m . :_._
=.1._ r= .. = a =.2: :a2- .J=_ ===_2 = _ . 4_ :_ . q _= - -+ - /(._=t i. /2..;..
. _ _ __.9. _._ 22 _ _-
e _ _ . _ _ . . _ _ _ , . _ . . . _ . _ _ _ . . i __f ._ . _ ;______. 3 m 1400
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g ___4 _3___=_+-_._____....___,._.~"-~ i_ -2 _ _. ,_
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- c. ; :-. r.c=-
w ..~ " ~ " - - - " --#~"~ -*-~ ~ j r : :~ ~'~_-~ f_ ~ " ~
=
/ =n t..... 4~ ~ ~T="
. n --
1200 '- E y =...r. ' r. - SATURATION CURVE - __:_/- SATURATION _= m .:..... ...a_r....... CORRECTED FOR --
.2 CURVE w ., " . . ~ ~ . ~ = INSTRUMENT ERROR __./_. =
c 1000 .7
} :.5 5 t 5 ? r ~~.~ 1 d. _ _- C-'_ i&T ~~A \_ 'Y.__. ...
- .'= .= :=_nt - - - --- n == - * - - - 1==: = 'J.= /_: 1 :=
d =i. t . - nd : =. - !=J-- . }- : ---t - =K =. p-/----1. i_. 7 e ...........-+....,__...3...._. -. f
,__ , =. _:g n 7
=~-f -
4- -
, f=
'~~ ' "
- - + - - -
= y'=/r ~ -- - ;==_ __. =_. . .-
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600
- g 3 _. 3 == = r _=:a --- -
_1 , . _. ___ l 400
~"-- #-- ~
__...__:.. .. ._._ g ._ : . _g_ p" _,__,--r-- r-- .4 l --~ i- c;Eh==277=- TE PRESSURE ERROR + 65 psig! 200 -- MPERATURE ERROR I 24 *F I l -;_;= t= g ,-
- . _y /; _.. , = _r__
.== = _. .a. - -
g 1-i:E p- .d: . iE=p-i- .i= = i p -' 200 300 400 500 600 700 C ( b CORE EXIT T/C TEMPERATURE (*F) DC0257 151V
NUMBER EP E-0.4 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/7/85 PAGE 16 0F 22 7,7 g NATURAL CIRCULATION C00LDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS) APPENDIX N ENERGIZING NON-VITAL 480V BUSSES WITH DIESEL GENERATOR SCOPE The purpose of this procedure is to make 3vailable selected non-vital systems 'co lessen the restriction on recovery until normal 0FF-SITE power is restored. This procedure deals with the situation when both Units are down. All 5 emergency diesel generators may not be available. In this case one unit will be deprived of the swing diesel generator. The selected non-vital systems which are desired to be returned to service are plant instrument air, service cooling water, CRDM shroud cooler fans, Turbine Generator lif t pump and turning gear drive, 230KV and 500KV switchyard. DISCUSSION This procedure deals with both units since the plant air compressors are powered from either unit and are normally cross connected such that it is common to both units. Therefore, the unit to which the swing diesel 13 is omitted will be responsible for re-energizing the compressed air systems. Unit 1 is responsible to re-energize the 230 and 500KV switchyard. Any additional loading will be done by Shift Foreman evaluation for remaining diesel generators capacity. The following is a list of the minimum number of loads required for plant cooldewn.
- a. 1 Centrifugal Charging - 507KW
- b. 1 Comperent Cooling Water - 324KW
- c. 1 Auxiliary Salt Water -
321KW
- d. 3 Containment Fan Coolers -
660KW
- e. 1 Auxiliary Feedwater - 429KW
- f. 1 Pressurizer Heater Group * -
483/207
- g. 2 480V Motor Control Centers -
Refer to STP M-9M for Individual Loads and Intermitter.t loads
- 483KW for 7 Heaters; 207 for 3 Heaters DC0257 16IV
1 AND 2 NUMBER EP E-0.4 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 0 DATE PAGE 3/7/85 17 0F 22
"# NATURAL CIRCULATION C00LD0WN WITH STEAM V0ID IN VESSEL (WITHOUT RVLIS)
APPENDIX N (Continued) PROCEDURE
- 1. Determine which diesel generator will be used as source for the non-vital busses,
- a. On the Unit which has the 13 swing diesel generator available, transfer the maximum number of essential loads to the 4KV bus F and remove all non-essential loads from bus G.
- b. On the Unit which does not have the 13 swing diesel generator available, transfer the maximum number of essential loads to bus G and remove all non-essential loads from bus H.
- 2. Cut out the Auto Transfer FC0's for all 4KV busses and 12KV busses.
- 3. Depress all Aute Transfer Reset Push Buttons.
f0TE: The Auto Transfer Reset will NOT reset and the BLUE light will NOT de-energize for the F bus if the 13 diesel generator is operating on the other unit. 4 OPEN or verify OPEN all vital bus 4KV auxiliary feeder breakers, 52-HH-13, 52-hG-13 and 52-HF-13.
- 5. OPEN or verify OPEN all vital bus 4KV startup feeder breakers, 52-hH-14, 52-HG-14 and 52-HF-14
- 6. OPEi or verify GPEh startup power to vital busses F, G, H, 52-HG-15.
- 7. OPEN or verify OPEN auxiliary feeder to 4KV non-vital busses D and E.
Uhli 1 UNIT 2 52-HE-2 and 52-HD-15 52-He-14 and 52-HD-4 e DC0257 171V l
NUMBER EP E-0.4 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/7/85 PAGE 18 0F 22 TIT g* NATURAL CIRCULATION C00LDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS) g APPENDIX N,(Continued)
- 8. OPEN cr verify OPEN startup feeder to 4KV non-vital busses D and E.
UNIT 1 UNIT 2 52-HE-3 and 52-HD-14 52-He-13 and 52-HD-5
- 9. OPEN or verify OPEN startup transformer feeder breaker.
UNIT 1 Ut4IT 2 52-VU-14 52-VU-23
- 10. OPEN ALL 4KV feeder breakers to 480 volt busses and 4KV busses D and E.
- 11. At SFM discretion cut in the FC0 to place all Diesel Generator Protection in service for the Diesel Generator selected to power the non-vital busses.
- 12. Verify all Condensate / Booster pump stand-by switches are set in MANUAL.
- 13. Verify the fiash Vacuum purp is OFF and the No. 2 Heater Drip Pump is 0FF.
14 CLOSE the startup feeder breaker to the vital bus.
- a. If the non-vital bus power source is UI.II 1 Uf.IT 2 D/G CLOSE BREAKER D/G CLOSE BREAt.ER 11 52-hh-14 22 52-HH-14 12 52-HG-14 21 52-HG-14 13 52-HF-14 13 52-HF-14 O
DC0257 181V
NUMBER EP E-0.4 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 r3 DATE 3/7/85 V PAGE 19 0F 22 7,7 g NATURAL CIRCULATION C00LDOWN WITH STEAM V0ID IN VESSEL (WITHOUT RVLIS) APPENDIX N (Continued) CAUTION: If the diesel generator appears unstable during the performance of Step 15 or at any time beyond this point in the procedure, imediately OPEN 52-HG-15 to separate the diesel from the non-vital system.
- 15. CLOSE startup power to vital busses F, G, H, 52-HG-15.
POTE: There will be short load surge on the Diesel Generator as the startup transformer 12 is energized.
- 16. CLCSE startup feeder to 4KV bus D.
UNIT 1 UNIT 2 52-ND-14 52-HD-5 r~g 17. CLOSE startup feeder to 4KV bus E. O UNIT 1 UNIT 2 52-HE-3 52-HE-13 IOTE: Evaluate the load on the diesel generator prior to energizirg each additional load to ensure its reserve capacity is not exceeded. As each additional load is added if the diesel generatcr overloaas it may only be necessary to trip the last load added rather than tripping the entire bus. le. Or. the Unit which has the 13 swing diesel generator carrying the F vita' bus energize the following 480V busses.
- a. Energize the following non-vital busses.
UNIT 1 UNIT 2 BUS CLOSE BREAKER BUS CLOSE BREAKER 15D 52-HD-6 25D 52-HD-13 11D 52-HD-10 21D 52-HD-9
- 19. Return the instrument air system to service as per OP K-1.
O DC0257 191V
NUMBER EP E-0.4 1 AND 2 O!ABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 PAGE 20 0F 22 7,7 g NATURAL CIRCULATION C00LDOWN WITH STEAM V0IO IN VESSEL (WITHOUT RVLIS) APPEhDIX N (Continued)
- 20. Energize the 500KV switchyard 4KV bus CLOSE 52-HE-7 (U-1 only).
- a. Dispatch an Operator to the 500KV switchyard to verify CLOSED or CLOSE the local 4KV bus feeder breaker in the 500KV switchyard,
- b. Operator should also verify 480V bus is energized and 500KV switchgear compressed air system is available.
- c. Operator should verify 230KV yard 4KV bus is energized via the emergency tie cable and its compressed air system is available.
- 21. Additional loads such as CRDM shroud coolers, turbine generator lif t pump and turning gear drive may be made available and their 480V busses energized at the discretion of the Shift Foreman, dependent on diesel generator reserve capacity.
O O DC0257 20!V l
NUMBER EP E-0.4 DIABLo CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 /m DATE 3/7/85 C PAGE 21 0F 22 TITLE NATURAL CIRCULATION C00LDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS) APPENDIX N (e4 N t 4 At ot gV. w
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t FIGURE ONE: DIESEL GENERATOR LOAD LIMITS DC0257 211V
NUMBER EP E-0.4 1 AND 2 REVISION 0 oiAsLO CANYON POWER PLANT UNIT NO(S) DATE 3/7/85 PAGE 22 0F 22 NATURAL CIRCULATION C00LDOWN WITH STEAM V0ID Triut IN VESSEL (WITHOUT RVLIS) APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Notify the Plant Superintendent, Supervisor of Operations and Plant Manager or their designated alternates.
- b. Designate this event a Notification of Unusual Event.
Notify plant staff and response organizations required for this classification by implementing Emergency Procedures G-2
" Establishment of the Organization" and G-3 " Notification of Off-Site Emergency Organization" in accordance with Energency Procedure G-1 " Accident Classification and Ecergency Plant Activation."
- c. When the cause of the natural circulation cooldown has been determined, this and the subsequent plant conditiens should be reviewed against the classification criteria in Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation."
O DC0257 22IV
PACIFIC GAS AND ELECTRIC COMPANY { DEPARTMENT OF NUCLEAR PLANT OPERATIONS ' DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 DATA SHEET - NATURAL CIRCULATION COOLDOWN O Note: Record values approximately every 30 minutes. Date started: By RCS (3) P2R LWEST RCS(2) COOL COOL LOOP 1 (1) LOOP 2 1) LOOP 3 (1) LOOP 4 (1) RCS SG SUB DOWN HEAD PIR DOWN 4 TIME WR TEM; ('F) WR TEMP 'F) WR TEMP ('F) WR TEMP (*F) PRESS PRESS COOLING RATE TC TEMP RATE In\Tc Avg In\ Tc Avg In\Tc Avg In\ Tc Avg (psig) (psig) (*F) ('F/hr) ('F) (*F) 0F/HR N N N N I N N N N i N N N N N N N' N N N N N N N N N N N N N N N N N N N N N . N N N N ! N N N N i l o N N N N ! I I V N N N N I I i NJ fN N N I I I N N N N I ! ! I Ni FN N N I i ! i i N Ni N N l i
- N N N N I IN N N N I I I N N N N I N N N N N N N N N N N N
- 1. Values from SPOS preferred. Calculate average from Th & Tc values.
- 2. If using subcooling ecnitor Cefeat head TCs when measuring (toggle switch panel RNICA).
- 3. Cecidewn rate should be calculated for one hcur period, ng the instantar. ecus value.
COV?E'iTS: O DC0010 17111
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I FOLD 0VT PAGE FOR E-0.4
, NATURAL CIRCULATION C00LD0WN WITH STEAM VOID VESSEL (WITHOUT RVLIS)
ADMINISTRATIVE FUNCTIONS l
- 1. Notify STA (Monitor Critical Safety Function Status Trees and SPDS)
- 2. Refer to Appendix Z.
I ; MAINTAIN THE FOLLOWING DURING t C00LDOWN AND DEPRESSURIZATIONS: i
- 1. PZR cooldown rate - LESS THAN 200*F IN ONE HOUR PERIOD.
- 2. RCS temperature and pressure - WITHIN LIMITS OF TECH SPEC PLANT C00LDOWN CURVE.
- 3. RCS Subcooling Based on Core Exit TC's 20*F.
- 4. SG tube primary to secondary pressure differential - LESS THAN 1600 PSID.
; 5. SG NR level - 4i to 33%.
- 6. Monitor voicing in the vessel upper head:
] () e Locations for upper head TC's: poi r.t core location (Unit 1 only)
*16 H-8
, *21 K-3 25 M-5 29 H-5 l e PZR level - 20i TO 90: 6
- 7. De not allow the PZR level to decrease below 20%.
AFW SUPPLY SWITCHOVER CRITERION l J Switch to alternate AFW water supply when CST level decreases to less than 10%. Refer to EP E-2.1, ALTERNATE AFW SUPPLIES. 1 i
- Vessel upper head TC's 16 (H-8) and 21 (K-3) car be selected to the subcooling (Unit 1 only)
^ monitor,1f desired. O , V DC0257 25111
NUMBER EP E-1 33V43 Pacific Gas and Electric Company REVISION 0 A DATE 3/11/85 DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 31 D:ABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 I EMERGENCY PROCEDURE LOSS OF REACTOR OR SECONDARY COOLANT - TITL E IMPORTAN i' APPROVED ' 6 46 TO PLANTMANAGERg DATE SAFETY - SCOPE This prccedure provides instructions to be taken in response to a loss of reactor or secondary coolant. It is assumed that a Safety Injection actuation has occurred and that the irrediate operator actions and diagnostics of E-0, REACTOR TRIP OR SAFETY INJECTION, have been performed. This procedure and changes thereto requises PSRC review. SYMPTOMS OR ENTRY CONDITIONS This procecure is entered from the following procedures:
- 1. E-0, REACIOR TRIP OR SAFETY INJECTION, Step 18, and FR -H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 24, when a PZR PORV is stuck open and its stop valve cannot be closed.
- 2. E-0, REACTOR TRIP OR SAFETY INJECTION, Step 22, with any of the following symptoms: high containment radiation, high containment pressure, or high containment recirculation sump level.
- 3. E-0, REACTOR TPIP OR SAFETY INJECTICN, Step 33, and ECA-2.1.
UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATIONS, Step 6, when WR RCS pressure is less than the shutoff head pressure of the RHR pumps. 4 E-1.1, SI TERMINATION, Step 5, if RCS pressure decreases after stopping all but one charging pump.
- 5. E-2, FAULTED STEAM GENERATOR ISOLATION, Step 5, after identification and isolation of a faulted SG.
- 6. ECA-0.2 LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, Step 9, after normal injection mode conditions are established.
O V
; DC0436 IVIX i'
NUMBER EP E-1 1 AND 2 REVISION O DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 TITLE. LOSS OF REACTOR OR SECONDARY COOLANT
- 7. FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, Step 17 and Step 24; and FR-C.2, RESPONSE TO DEGRADED CORE COOLING, Step 19, when core cooling conditions are established.
- 8. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 1, if RCS pressure is less than all non-faulted SG(s) pressure.
- 9. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 24, when all PORVs are closed and the criteria for establishing normal charging are not satisfied.
- 10. FR-I.2, RESPONSE TO LOW PRESSURIZER LEVEL, Step 4, when pressurizer level cannot be restored.
O O DC0436 2VIX
l 1 1 AND 2 NUMBER EP E-1 ' DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/11/85 ' C PAGE 3 0F 31 (.-)' 7gg LOSS OF REACTOR OR SECONDARY COOLANT ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: e Fold Out page should be open. e Seal injection flow should be maintained to all RCPs. CAUTION: If subcooling monitor becomes inoperable, determine subcooling by using WR RCS pressure and core exit TCs (Refer to APPENDIX C).
- 1. CHECK If RCPs Should Remain In Service:
- a. Check WR RCS pressure a. -
IF pressure less than 1275
- GREATER THAN 1275 PSIG (VB2) psig, THEN close cent charg pp min-flow recirc vlvs 8105 and 8106 AND IF either one charging pp or one SI pp running THEN stop all RCPs and go to Step 2.
- b. Check Phase B - NOT ACTUATED b. IF either charg pp or SI (V51, pp RUN!:ING, THEN stop all RCPs
- 2. CHECK If SGs Are Not Faulted: (VB3)
- a. Check pressures in all SGs: a. -
IF a faulted steam generator is identified e NO SG PRESSURE DECREASING IN and E-2, FAULTED STEAM A:; UNCONTROLLED MANNER GENERATOR ISOLATION has NOT been performed on e NO SG COMPLETELY the faulted SG, DEPRESSURIZED THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION. O DC0436 3VIX
NUMBER EP E-1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/11/85 PAGE 4 0F 31 TITLE LOSS OF REACTOR OR SECONDARY COOLANT ACTION / EXPECTED RESPONSE RESR)NSE NOT OBTAINED CAUTION: Alternate water sources for AFW pumps will be necessary if CST level decreases to less than 10% (Refer to E-2.1, ALTERNATE AUXILIARY FEEDWATER SUPPLIES).
- 3. CHECK Intact SG(s) Level:
- a. Intact SG(s) NR level a. Maintain total feed flow
-GREATERTHAN4%[205.] greater than 460 gpm (VB3)
UNTIL NR SG level is greater than 4% [20%] in at least one SG.
- b. Control feed flow to maintain NR b. -
IF NR level in any SG SG level between 4% [20%] and 331 continues to increase (CC3/VS2) in an uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE.
- c. Stop TD AFW cun unless needed for RCS heat removal (VB3) 4 CHECK Secondary Radiation e R-15, condenser air ejecter Go to E-3, STEAM GEf4ERATOR TUEE process monitor - fiORfiAL RUPTURE.
(RMS CAS II) e R-19, steam generator blowdcwn liquid process monitor
- NORMAL (RMS CAB II) e R-71 thru 74, main steamline process monitors - NORMAL ----------------
(PK 11-18) O DC0436 4VIX
NUMBER EP E-1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 ' i 3/11/85 p DATE 5 0F 31 Q PAGE l TnLE: LOSS OF REACTOR OR SECONDARY COOLANT l l ACTION / EXPECTED RESFONSE RESFONSE NOT OBTAINE_D_ CAUTION: If any PZR PORV opens because of high PZR pressure, Step Sb should be repeated after pressure decreases to less than 2335 psig.
- 5. CHECK PZR FORVs and Stop Valves:
(V52)
- a. Power to stop valves - AVAILABLE a. Restore power to stop valves.
- b. PZR PORVs - CLOSED b. -
IF RCS pressure is less than 2335 psig o PCV.474, PORV A THEN manually close PORVs e PCV-455C, PORV B or associated stop e PCV-456, PORV C vivs. e 8000A, stop viv A. e 8000B, stoo viv 8 e 8000C, stop viv C
- c. Stop valves - AT LEAST ONE OPEN c. Open any stop vivs not used to isolate an open PORV.
O DC0436 5VIX l l
I AND g E P E-1 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 PAGE 6 0F 31 7 LOSS OF REACTOR OR SECONDARY COOLANT ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. CHECK If Containment Spray Should Be Stopped:
- a. Verify containment spray a. Go to Step 7.
actuation - PK 01-18 IN ALARM (VB1)
- b. Verify containment radiation b. -
IF containment radiation levels - NORMAL levels are above e R-2, containment area monitor normal, (RMS CAB I) THEN ensure spray system is e R-30, containment area monitor still in operation and (Hi Range, PAM 2) go to Step 7. o R-31, containment area monitor (Hi Range, PAM 2)
- c. Verify containment pressure c. Perform the following:
- LESS THAN 20 PSIG (VB1) 1) Open FCV-128 to provide &
seal flow. W
- 2) Shutdown the PD charg pp
- 3) Reset containment spray trains A & B.
- 4) Close 8994 A & B spray additive tank outlet valves,
- 5) Ensure spray system is still in operation
. AND _
continue with Step 7. WHEN cnmt press <20 psig IIIEII stop both containment spray pumps.
- d. Reset containrrent spray trains A and B (VB1)
- e. Stop containment spray pumps and close 90003A & 8, RHR pp to spray rings (VB1)
- f. Close sprah additive tank outlet valves, 8994A & B (VB1)
O DC0436 6VIX l l
NUMBER EP E-1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 l'~') DATE 3/11/85
\s PAGE 7 0F 31 7,7ts LOSS OF REACTOR OR SECONDARY COOLANT I
ACTION / EXPECTED RESPONSE RESFONSE NOT OBTAINED
- 7. CHECK If ECCS Flow Should Be Reduced:
- a. RCS Subcooling a. Go to Step 9. OBSERVE
- GREATER THAN 20 F (VB2) CAUTION PRIOR TO STEP 9.
l
- b. Secondary heat sink: (VB3) b. Jjr_ neither condition is satisfied, e Total feed ficw to intact SGs THEN Go to Step 9. OBSERVE
- GREATER THAN 460 GPM CAUTION PRIOR TO STEP 9.
_0R_ e SG NR level in at least one intact SG
-GREATERTHAN4-[20L]
- c. WR RCS Pressure c. Go to Step 9. OBSERVE
- STABLE OR IhCREASING (VB2) CAUTION PRIOR TO STEP 9.
- d. PZR Level - GREATER THAN 4% [20t] d. Attempt to stabilize RCS (VS2/CC2) pressure and recover PZR level with normal PZR sprey.
AND Go to Step 9. OBSERVE CAUTION PRIOR TO STEP 9.
- 8. GO To E-1.1, SI TERMINATION i
O DC0436 7VIX
NUMBER EP E-1 1 AND 2 otABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/11/85 PAGE 8 0F 31 7gy LOSS OF REACTOR OR SECONDARY COOLANT ACTION / EXPECTED RESFONSE RESPONSE t0T OBTAINED CAUTION: e If offsite power is lost after SI is reset, manual action will be required to restart some safeguards equipment. If in recirculation mode charging pumps should be held in the 0FF/ RESET position until an RHR pump is in service. Refer to Appendix A for guidance if this condition occurs, e WR RCS Pressure should be monitored. If WR RCS pressure decreases to less than 300 psig, the Residual Heat Removal pumps must be manually restarted to supply water to the RCS.
- 9. CHECK If RHR Puros Shauld Be Stococc:
- a. Check WR RCh pressure: (VB2)
- 1) Prcssure - GREATER THAN 300 1) Go to Step 11.
PSIG
- 2) Pressure - STABLE OR 2) Go to Step 10.
IhCREASING
- b. Reset SI (NB1)
- c. Stcp both RHR pumps (VB1)
- 10. CFECK IF SGs *RE NOT FAULTED IF ANY SG _ FAULTED, THEN return to Step 1. OBSERVE
- a. Check pressures in all SGs: CAUTIONS PRIOR TO STEP 1.
e NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER e h0 SG COMPLETELY DEPRESSCRIZED O DC0436 SVIX
NUMBER EP E-1 1 AND 2
- DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/11/85 PAGE 9 0F 31 7,7 g LOSS OF REACTOR OR SECONDARY COOLANT ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 11. CHECK If Diesel Generators Should Be Stooped:
- a. Verify Vital Buses F G, and H a. Try to restore offsite power,
- ENERGIZED BY OFFSITE POWER either Startup or Auxiliary, (VB4) to the vital buses (Refer to ECA-0.3, RESTORE VITAL BUS).
- b. Reset SI (VB1)
- c. Stop any unloaded diesel generator and place in AUTO (VB4)
- 12. IMTI ATE Evaluation of Flant Status:
O a. Verify cola leg recirculation capability: (VB1)
- a. I F_ cold leg recirculation capability can NOT be verified,
- 1) Power to at least one RHR THEN go to ECA-1.1, LOSS pump. . AVAILAELE OF EMERGENCY COOLANT RECIRCULATIC1..
- b. Check auxiliary building b. Try to identify and isolate raciation - NORMAL (RMS CAE !) leakage.
- 1) R-4, recip charging pp roon -
IF an LOCA cutside cnmt is area monitor - NORMAL indicated, THEN implement ECA-1.2 LOCA
- 2) R.6, NSSS sampling room OUTSIDE CONTAINMENT.
area monitor - NORMAL
- 3) R-10, auxiliary building area monitor - NORMAL (located in Unit I racks)
THIS STEP CONTINUED ON NEXT PAGE l DC0436 9VI1 l l
NUMBER EP E-1 1 AND 2 otAsLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/11/85 PAGE 10 0F 31 TiTts LOSS OF REACTOR OR SECONDARY COOLANT h ACTION / EXPECTED RESR)NSE RESRJNSE NOT OBTAINED
- c. Contact Chem Rad Dept to obtain samples:
- 1) Containment sump
- 2) RCS coolant activity
- d. Evaluate plant equipment:
- 1) If RHR pumps are in service and no flow is indicated, open FCV-365 and FCV.364, CCW cut vivs from RHR Hx's (VB1)
- e. Place in service additicnal nonitoring devices:
- 1) Energize RE.32, Plant Vent 115' MID-Range Iodine Process Monitor (refer to EP RB.12 MID AND HIGH RANGE PLANT VENT RADIATION MONITORS) (PAM 2)
- 2) Energize PE-33, Plant Vent 115' MID-Range Nctie Gas Process Monitor (refer to EP RB-12) (PAM 2)
- 3) Notify Chem Rad Dept to place containment hydrogen analyzer in service f rom the POST-LOCA sample room
- f. Monitor turbine status:
'. ) Start the turbine AC ECP and 1) Start DC pps, the HP seal oil backup purps (VB4)
THIS STEP CONTINUED ON NEXT PAGE i - l DC0436 10VIX l
NUMBER EP E-1 1 AND 2 IA8LO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/11/85 PAGE 11 0F 31 .,7g LOSS OF REACTOR OR SECONDARY COOLANT ACTION /EXRCTED RESPONSE RESPONSE NOT OBTAINED
- 2) Monitor turbine coastdown per OP C-4:IV, MAIN UNIT TURBINE - TURBINE SHUTDOWN (VB4/CC3)
- 3) Ensure that main and feed pump turbines are on turning gear at 0 RPM (VB3/VB4)
- 13. CHECK If RCS Cooldown And Depressurization Is Required: (VB2)
- a. Check WR RCS pressure a. -
IF RHR flow (FI-970/971)
- GREATER THAN 300 PSIG greater than 200 gpm, THEN Go to Step 14
- b. Go to E-1.2, POST-LOCA C00LDOWN AND DEPRESSURIZATION O
DC0436 11VIX 1 8
l NUMBER EP E-1 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 PAGE 12 0F 31 h,l LOSS OF REACTOR OR SECONDARY COOLANT Tar a ACTION / EXPECTED ESPONSE ESPONSE NOT OBTAINED
- 14. CHECK If Transfer To Cold leg Recirculation Is Required:
RWST level - LESS THAN 33% (VB1) a. IF RWST level is greater
- a. -
than 33%, THEN perform the following while continuing to monitor plant status: e Monitor injection flow e Monitor RWST level e Moititor containment recirc sump level f4 RT $LDLEG RECIRCULATION WHEN RWST level is less than 33% THEN go to Step 14b.
- b. Ensure RHR pumps stopped at 33; RWST level (VB1)
- c. Check containment recirc sump c. Go to ECA-1.1, LOSS OF level - GREATER THAN 45 (VB1) EMERGENCY COOLANT RECIRCULATION
- d. Go to E-1.3, TRANSFER TO COLD LEG RECIRCULATION O
DC0436 12V!X f
NUMBER EP E-1 1 AND 2 DtABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 cT DATE 3/11/85
\s_) PAGE 13 0F 31 TITLE:
LOSS OF REAC70R OR SECONDARY COOLANT ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 15. CHECK If Intact SGs Should Be Depressurized To RCS Pressure:
- a. Check RCS pressure - LESS THAN a. Go to Step 16.
INTACT SG PRESSURES (VB2/VB3)
- b. Check SGs radiation: b. Do not dump steam from a SG wi'th high radiation, e RM 71-74, Main Steam Line Isolate feed flow to a SG Process Monitors - NORMAL with high radiation.
(PK11-18) e P-19, steam generator blowdown i liquid process menitor - NORMAL I (RMS CAS II) () c. Dump stean to condenser from intact SGs until SG pressure is
- c. Dump steam using intact SG(s) 10'. steam dumps until less than RCS pressure SG pressure is less than RCS pressure.
- 1) Steam dump mode selector switcn - STEAM PRESSURE MODE
- 2) Steam cump interlock selectors
- BYPASS INTERLOCK
- 3) HC-507 pressure controller in
- MANUAL or AUTO
- d. Check intact SGs pressure d. Continue steam dump until SG
- LESS THAN RCS PRESSURE pressure is less than RCS pressure.
- e. Stop dumping steam l
l l l O () i DC0436 13VIX l
1 AND 2 S ON otAsLO CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 PAGE 14 0F 31 7,7 g LOSS OF REACTOR OR SECONDARY COOLANT g ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 16. Determine If Reactor Vessel Head Should Be Vented:
- a. Consult TSC (Refer to FR I.3 RESPONSE TO V0ID IN THE VESSEL)
- 17. At 19 Hours After Event Initiation Prepare For Hot Leg Recirculation:
Go to E-1.4 TRANSFER TO HOT LEG RECIRCULATI0ti
- END -
O O DC0436 14VIX
NUMBER EP E-1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/11/85 { } PAGE 15 0F 31 7,7tg LOSS OF REACTOR OR SECONDARY COOLANT APPENDIX A BLACK 0UT EMERGENCY LOADING 0F VITAL BUSSES
- 1. If the vital busses lose voltage prior to resetting the safety injection signal, the vital busses will automatically load the vital equipment given below. Verify the equipment has been loaded by observing breaker lights on the control board.
- 2. If the vital busses lose voltage after the safety injection signal has been reset, load or verify loaded the equipment given below cnto the vital busses manually. Allow approximately 4 seconds between loading of each piece of equipment onto a given vital bus. Load or verify that the CFCU are running in Low Speed.
VITAL EUS F VITAL SUS G VITAL BUS H U-1 (D/G 1-3) U-1 (D/G No. 2) U-1 (D/G No. 1) { } U-2 (D/G 1-31 U-2 (D/G No. 1) U-2 (D/G No. 2) MCC F MCC G MCC H CCPp ho. 1 RHR Pp. No. 1 SI Pp No. 1 CFCU No. 3 SI Pp No. 2 CFCU No. 2 CFCU No. 5 RHP Pp No. 2 CFCU No. 1 CCW Pp No. 2 CFCU No. 4 CCW Pp Nc. 1 ASW Pp No. 2 CCW Pp no. 3 ASW Pp ha. 1 CCPp No. 2 AFW Pp No. 2 AFW Pp Nc. 3
- 3. Load the containment spray Pumps only if they were running prior to the blackout.
VITAL BUS G VITAL BUS H Cont Spray Pp No. 1 Cont Spray Pp No. 2 l l DC0436 15VIX i
l 1 l l Nt.MBER EP E-1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/11/85 PAGE 16 0F 31 , LOSS OF REACTOR OR SECONDARY COOLANT y7g APPENDIX C 2600 .
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300 400 500 600 700 200 CORE EXIT T/C TEMPERATURE ('F) 0 0C0436 16VIX
NUMBER EP E-1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 g) ,,v DATE PAGE 3/11/85 17 0F 31 7,7 g LOSS OF REACTOR OR SECONDARY COOLANT APPENDIX H VERIFICATION OF ESF FUNCTIONING AND EFFECTIVENESS DURING LOCA The primary function of the Shift Technical Advisor during any emergency is to evaluate plant conditions and advise the Shift Foreman on recovery procedures or actions to be taken to mitigate the consequences of the emergency. This appendix provides a method of evaluating the effectiveness of the ESF system during any LOCA and provides guidance on reclassifying the accident from a Site Emergency to a General Emergency should conditions warrant. The on shift Shift Technical Adviser (or his designated alternate if additional manpower is available) will make this evaluation as the event progresses and will make the necessary recommendations to the Shif t Foreman based on his findings. For all accidents except the LOCAL, the maximum amount of activity whicn could be released is low enough so that persons located beyond the site boundary are not in immediate jeopardy even under the worst In the case of the LOCA, however, it is theoretically p) s circumstances. possible that a large fraction of the core inventory of the volatile fission products (noble gases and iodines) could be released if one assumes multiple failure of the various engineered safety features. In such a case, doses within the LPZ could be very high, particularly to the thyroid gland. Loss of life is possible. As a result, it is imperative that downwind areas of the LFZ be evacuated as soor as possible in a LOCA situation where the functioning and/or effectiveness of the engineered safety feature systems is in doubt. In tne case of the LOCA with inadequate core cooling, the major release would not be expected for a least two hours due to thC time required to melt a large fraction of the core and the expected time before any containment failure would be likely. Thus, early recognition of the signs of ESF malfunction and prompt action in this event can prevent most, if not all, of the exposure of persons within the LPZ. 1 Which includes loss of the primary system heat sink and resultant expulsior of coolant from the primary system to the extent that i safety injection is required. l l l l / k <G DC0436 17VIX
NUMBER EP E-1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION O DATE 3/11/85 PAGE 18 0F 31 7g LOSS OF REACTOR OR SECONDARY COOLANT APPENDIX H (Cont'd) In the event of a LOCA, the Evaluations Coordinator should pay particular attention for signs that the ESF systems have malfunctioned, and if their effectiveness is in doubt, classify the accident as a General Emergency and have the Emergency Coordinator immediately notify those agencies given in General Appendix 2 of the emergency procedure and the NRC Operation Center. This Appendix and worksheets provide a checklist of three major categories of items to look for, and provides criterion to indicate that the various ESF have or have not functioned. In several cases there is more than one indicator to verify the functioning of a particular safety feature. For example, SI pump flow is measure directly by a flow indicator, but can also be inferred from pump operation and valve position indicators. If the various indications do not agree, a judgment must be made on the basis of what is considered to be the best evidence. Normally, however, the conservative course of action should be followed.
- 1. Worksheet for Verification of ESF Functioning and Effectiveness During a LOCA This worksheet is to be used first to check that the minimum components in each of the ECCS and containment cooling systems have operated correctly. Although this does not guarantee that they will be effective, it provides reasonable assurance.
Conversely, their failure vastly increases the chance of fuel melting or overheating and overpressurization of the containment (thereby jeopardizing its ability to retain fission products). Therefore, classify the accident as a General Emergency unless the minimun recuired components in each of the categories have functionec or are imreciately initiated manually. The worksheet applies only to the injection phase. Although it is also necessary to maintain core cooling during the recirculation phase, the speed with which it must be restored is less critical. However, if the ability to cool the core is lost, and is not likely to be restored rapidly, a General Emergency is justified. O OC0436 18VIX
1 AND 2 S ON DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 rN PAGE 19 0F 31 b) LOSS OF REACTOR OR SECONL)ARY COOLANT riytg. APPENDIX H (Cont'd) Included on the worksheet is the verification of containment isolation valve closure. Post-accident dose calculations are based upon the assumption that containment leakage rate is 0.1% day. If the leakage rate exceeds this, the off-site dose will increase proportionally. Although it is not possible to rapidly measure the leak rate, if all major penetrations that lead directly to the atmosphere are closed by at least one valve, the leak rate is probably reasonably low. If at least one valve in each of the paths on the worksheet (Page 20), Item 7, is not closed either automatically or by operator action within about 15 minutes, consider the accident a General Emergency.
- 2. Worksheet for Verification of Containment Pressure Less than Design Pressure This worksheet is used to determine if the internal containment pressure significantly exceeds the design pressure of the
- structure. Doubts are cast about the ability of the containment to retain the fission products (at least a maximum leakage rate of 0.15/ day) if design pressure is exceeded. It also indicates that the ESF are not functioning properly, since the pressure shoula never get that high if a minimurr safeguards train vorks correctly.
The containment is designed for 47 psig coincident with the forces caused by a double design earthquake (0.49 ). With no earthquake (or following a completion of an earthquake), the containment can withstand 1.5 times the previous pressure, or 70 psig. Figure 1 on the worksheet shows the maximum allowable containment pressure as a function of the earthquake strength. If the curve is exceeded, the accident must be considered a General Emergency. l [ t0 V DC0436 19VIX
1 AND 2 NME P E-1 DIABLO CANYON POWER Pt. ANT UN4T NO(S) R DATE 3/11/85 m LOSS OF REACTOR OR SECONDARY COOLANT APPENDIX H (Cont'd)
- 3. Worksheet for Verification of Containment Radiation Level Within Excectations This worksheet is used to determine the extent of core damage.
Two high range gama instruments (RE-30 and RE-31) have been installed to measure the internal containment radiation level following a LOCA. Figure 1 on the worksheet shows the calculated respo'1se of these instruments as a function of time after a LOCA assuming various degrees of core damage. Any LOCA would be expected to release the activity contained in the coolant and so a reading of this magnitude should not be cause for concern. Similarly, in a major LOCA some cladding failure may oc::ur due to the combined effects of DNB, depressurization, and metal-water reaction. Cladding failure will release some of the activity contained in the gap between the pellet and the cladding. However, the amount of cladding failure should be small. Thus, if the activity in the containment reaches the line labeled "100% gap release," it is indicative of gross core damage and/or the onset to fuel melting. It either case, the ECCS has failed to function as expected and the accident should be considered as a General Emergency. That is, if the containment radioactivity reaches or exceeds the value on Figure 1 for 100s gap release, censider tne accident as a General Emergency. If there is any question about the validity of the readings, or if the above instruments have failed, readings can be taken at the containment exterior with portable radiation protection equipment. Specifically, Figure 2 on the worksheet shows similar data for a CP type instrument located at the exterior surface of the steel liner (but inside the movable concrete shield) at the equipment hatch. Figure 3 on the worksheet shows the dose rate outside the containment concrete wall. The readings at the equipment hatch can be made with an extention probe on a Victoreen Rad Gun. The HPI-1010 would be an appropriate instrument to use for measurements external to the concrete containment wall. TOTE: Normal background is about 0.0!5 mR/hr on the HPI-1010. DC0436 20VIX l
NUMBER EP E-1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 ,m DATE 3/11/85 ( PAGE 21 0F 31 7,7 g LOSS OF REACTOR OR SECONDARY C0OLANT ! WORKSHEET 1 - APPENDIX H WORKSHEET FOR VERIFICATION OF ESF FUNCTIONING AND EFFECTIVENESS DURING A LOCA PERFORMED BY DATE TIME
- 1. -BASIC ACCIDENT INFORMATION UNIT DESCRIPTION DATE/ TIME OF OCCURRENCE /
- 2. CENTRIFUGAL CHARGING PUMPS
- a. Pump suction valve coen .. 8805A [~ 1' 8805B
- b. EIT inlet valve ocen 8803A 8803B
- c. BIT outlet valve c;en 8801A 8801E
- d. Charging pump ON *5No.1['No.2 o e. . Flow thrcugh FF917 gpm Q f. At least one train must be verified in service by L j Yts verifying ar. cperable ficv: path and the pump ON, L j h0 or by verifying flow through FI-917.
BY TIME
- 3. SAFETY IhJECTION PUMPS
- a. Pump supply valve fron RWST open ,, 8976
- b. Pump sucticn valve open 8923A[]8923B
- c. Pump discna ge crosstie valve open ~
i 8821A [ ] 8821B
- d. Pump cold leg discharge open 8835
- e. SIS purp ON : ,l No. 1 [ ] No. 2
- f. RCS pressiire <1500 psig [ ] YES []N0 psig
- g. Flow established FI-918 gpm FI-922 gpm
- h. If RCS <1500 psig, at least train must []h/A L ] YES [ j h0 be verifiec in service by verifying an operable flow path and the pump ON, or by verifying flow established through the FI.
BY TIME O DC0436 21VIX
NUMBER EP E-1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/11/85 PAGE 22 0F 31 7,7g LOSS OF REACTOR OR SECONDARY C0OLANT WORKSHEET 1 - APPENDIX H (CONTINUED)
- 4. ACCUMULATORS
- a. Accumulators discharge (LI's show low level)
No. 2 [ ' LI-952 or 953
~ ~
No. 1 LI-950 or 951 No. 3 l ' LI-954 or 955 No. 4 [ ' LI-956 or 957
- b. RCS pressure <600 psig? ,,
YES ,, N0 asig
- c. At least one LI per accumulator L YES ,
NO ]N/A indicates discharge, if RCS
<600 psig.
BY TIME
- 5. RESIDUAL HEAT REMOVAL PUMPS
- a. Pump supply valve from RWST open []'8980 87006
- b. Pump suction valve open ,
8700A [
- c. HX outlet flow control valve open HCV-638 [ HCV-637
- d. Cold leg injecticn valve open [,, 8009A [ ] 88098
- e. RHR pump ON ,
No. 1 [ ] No. 2
- f. RCS pressTre <170 psig [ ] YES [ N0 psig
- g. Flow established [ ] FI-970 gpm [ ] FI-971 gpm &
- h. If RCS <170 psig, at least one train W must be verified in service by verifying one operable flow path and the pump ON, or by verifying flow through the FI. [ ] N/A [ ] YES [ ] NO BY TIME
- 6. C0t;TAlt.NEtiT SPRAY AND C00LIf;G
- a. Spray additive tank valve ocen [,8994A 8992
- b. Spray additive tank valve open ,, ,)89946
- c. Spray pump discharge valve open 9001A 90018
[ , No. 2
- d. Spray pump ON [, ' , .
- e. Fan coolerslN: No. 1 [ ] No. 2 [ ] No. 3 ' No. 1No. 4 [ ] fo. 5 [ ]
- f. Containment III-Hi pressure singal received l YES []N0
- g. At least two spray pumps have functioned OR one spray pump and three fan coolers Tunctioned if a containment Hi-Hi pressure signal received. [ ] N/A [ ] YES [ ] N0 BY TIME i DC0436 22VIX 1
NUMBER EP E-1 1 AND 2 StABLO CANYON POWER PLN4T UNIT NO(S) REVISION 0 ( DATE PAGE 3/11/85 23 0F 31 7,7 g LOSS OF REACTOR OR SECONDARY COOLANT WORKSHEET 1 - APPENDIX H (CONTINUED)
- 7. CONTAINMENT ISOLATION VALVE CLOSURE INSIDE CONT. OUTSIDE CONT.
~ '
- a. Pressure / Vacuum relief closed FCV-662 l FCV-663 and 664
- b. Purge supply closed lFCV-660 l'I FCV-661
- c. Purge exhaust closed ] RCV-11 .i RCV-12
- d. At least one valve in each of the above flow paths must be closed within 15 minutes [ ] N/A [ ] YES [ ] N0 BY TIME
- 8. If item 2.f, 3.h, 4.c, 5.h, 6.g, OR 7.d, is N0, consider the accident as a GeneraT Erergency.
BY TIME O l l l l i O DC0436 23VIX l
I ANO 2 REV S ON DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 LOSS OF REACTOR OR SECONDARY COOLANT 7 rts WORKSHEET 2 - APPENDIX H WORKSHEET FOR VERIFICATION OF CONTAINMENT PRESSURE LESS THAN DESIGN PRESSURE PERFORMED BY DATE TIME
- 1. BASIC ACCIDENT INFORMATION UNIT DESCRIPTION
/
DATE/ TIME OF OCCURRENCE
- 2. EARTHQUAKE FORCE MONITOR (EFM-1)
Peak Earthquake EFM-1 Indicator Peak Reading Acceleration
- a. Longitudinal x 0.01 = g
- b. Vertical x 0.01 = g
- c. Transverse x 0.01 = g
- 3. CONTAINMENT PRESSURE PR 938 or 939 OPEMBLE ,
G 70 - 5
- N/
5 N c h 60 \
- l!
E W PR 938 or 5 939 Ili0PEMBLE 50 7
/ \
40 0 0.1 0.2 0.3 0.4 l PEAK EARTHOUAKE ACCELERATION Figure 1 Internal Pressure Capability of the Containment
- Versus Earthquake Acceleration DC0436 24V!X l
1
l l l NUMBER EP E-1 I 1 AND 2 otAsLO CANYON POWER PLANT UNIT NO(S) REVISION 0 l DATE 3/11/85 l l PAGE 25 0F 31 LOSS OF REACTOR OR SECONDARY COOLANT mm WORKSHEET 2 - APPENDIX H
- a. Using the largest acceleration in g's from the EFM-1 (item 2 above) and Figure I determine:
- 1) Maximum allowable pressure with PR-938/939 operable psig
- 2) Maximum allowable pressure without PR-938/939 operable psig
- b. Using either containment pressure indicator PR-938 or 939, or any 2 of 4 of the following indicators PI-934, 935, 936, 937, record containtrent pressure every two or three minutes for the first 15 minutes of the accident.
INSTRUMENT ID TIME PRESSURE (PSIG) e BY TIME 4 DESIGT. LIMITATION (complete 3.a OR 3.b)
- a. If PR-938/939 was used in item 3.b to determine containment pressure, are any pressure readings greater than the maximum allowable pressure with PR-938/939 operable (iten 3.a.1):
YES [] NO [] 0 R,
- b. If any 2 of 4 of the following indicators, PI-934, 935, 936 or 937, were used to determine containment pressure, are any pressure readings greater than the maximum allowable pressure without PR-938/939 operable (item 3.a.2):
YES [] NO []
- 5. If iter 3.a of 3.b is YES, consider the accident as a General Emergency.
BY TIVE DC0435 25V!X i
NUMBER EP E-1 1 AND 2 OIABLO CANYON POWEFI PLANT UNIT NO(S) REVISION O DATE 3/11/85 PAGE 26 0F 31 LOSS OF REACTOR OR SECONDARY COOLANT tit m WORKSHEET 3 - APPENDIX H WORKSHEET FOR VERIFICATION OF CONTAINMENT RADIATION LEVELS PERFORMED BY DATE TIME
- 1. BASIC ACCIDENT INFORMATION UNIT DESCRIPTION DATE/ TIME OF OCCURRENCE /
- 2. Using the lowest reading on one of the following, RE-30, RE-31, (in the Control Room), the Victoreen Rad Gun (between the equipment hatch steel door and movable concrete shield), or a HPI-1010 (at the containment concrete wall), determine the radiation level following an accident approxicately every 15 minutes for 2 hours.
INSTRUMENT ID TIME DOSE RATE (R/HR) BY O O DC0436 26VIX
NUMBER EP E-1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 gN DATE 3/11/85 PAGE 27 0F 31 () 7,7a LOSS OF REACTOR OR SECONDARY COOLANT WORKSHEET 3 - APPENDIX H (CONT.)
- 3. Determination of Expected Radiation Level
- a. Using Figure 1, the time after the accident and readings from RE-30 and RE-31 (Item 2), are radiation levels equal to or higher than expected for 100% gap release.
[]N/A [ ] YES [ ] NO
- b. Using Figure 2, the time after the accident and readings from the Victoreen Rad Gun (Item 2), are radiation levels equal to or higher than expected for 100% gap release.
[ ] N/A [ ] YES [;N0
- c. Using Figure 3, tne time af ter the accident and readings from the HPI-1010 (Item 2), are radiation levels equal to or higher than expected for 100' gap release.
[ ] N/A [ ] YES [ ] N0
- 4. If Item 3.a 3.b. , OR 3.c. is YES, consider the accident as General Emergency.
BY TIME O DC0436 27V!X l
NUMBER EP E-1 I ANO 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION O DATE 3/11/85 PAGE 28 0F 31 7,7tg LOSS OF REACTOR OR SECONDARY COOLANT APPENDIX H WORKSHEET 3 FIGURE 1 OOSE RATE INSIDE CONTAINMENT AFTER LOCA RE 30 AND 31
. . . . . . , . . . e s , e . ,... s . . . ..... '
i . F s GAP BELEASE , t ,- a 3:_
e ! 102 e e
7 e i _ e 1004 GAP ! 303LE GASES s GENERAL s EME:3 N v Lf? k I R/ER g i 10 e l i e i 7 e 8 10% GAP . 30sLE GASES s if ; j e 9 s , e
; 14 GAP
- l g 30tLE GAsts s
- 1
= ' l
.= 0.124 GAP __. I
- Bonet. au C001AarT
. _ - 3. _.:
0.5 1.0 2.0 4.0 6 8 12 24 240 H0'JRS
NUMBER EP E-1 1 AND 2 DIA8LO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/11/85 s, PAGE 29 0F 31 7,7 g LOSS OF REACTOR OR SECONDARY COOLANT APPENDIX H - WORKSHEET 3 - FIGURE 2
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+. #i i t_ -
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ili:..; a 4 c i 2 3 s a s Tint AFTE'4 a: !:D:7 (HOURS) ricuu a DOSE RATE OUTSIDE EQUIPMENT HATCH LINER FOLLOWING LOCA DC0436 29VIX ; l
EP E-1 ! NUMBER 1 AND 2 DIAsLO CANYON POWER Pt. ANT UNIT NO(S) REVISION O ; DATE 3/11/85 l PAGE 30 0F 31 J 7,7 2 LOSS OF REACTOR OR SECONDARY COOLANT APPENDIX H WORKSHEET 3 FIGURE 3 10t . . . . . _. .y . r - - - - - - . .: - y.-
- r_r at. sco x . z u w t n - :'
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GENERAL EMERGENCY e ABOVE THIS LINE
. .. ;8ltl. l ,., .lg,'4 8 .
, i..o ... . ii . .
g,gj
.. 6 3.0 8 g .: 1 ' l
.*!! *I.*
o n 2 3 4 6 e i a TCtt AFTER 1*cittkT (MOIP.5) F17J"43 DOSE RATE OUTSIDE OF C0f4TAINMENT SHIELD WALL FOLLOWING LOCA DC0436 30V!X l I
NUMBER EP E-1 I ANO 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) I7 DATE 3/11/85 O PAGE 31 0F 31 TITLE. LOSS OF REACTOR OR SECONDARY COOLANT APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Designate this event a Notification of Unusual Event.
- b. If a steam line break is accompanied with a known primary to secondary leakage >10 gpm as indicated by high radiation alarms on the air ejector, steam generator blowdown, sample or by an increase in stean generator water level in an unexpected manner, designate this event as an Alert.
- c. If the primary to secondary leakage is estimated at >50 gpm with fuel damage evident from a gross failed fuel monitor alarm or primary sample, designate this event as a Site Area Emergency.
fl d. SI with high or increasing levels of containment pressure, area V radiation or recirculation sump level. Designate this event a Site Area Emergency.
- e. In the event inadequate core cooling is verified per Critical Safety Function Status or the verification of the ESF Functioning and Effectiveness during LOCA, Appendix H, indicates ESF failure, reclassify this event as a General Emergency.
- 2. Notify plSnt staff and response organizations in accordance with EP G-2 and EP G-3 and implement the instruction in EP G-1 regarding on and off-site protectise actions.
l O (U DC0436 31VIX l
FOLDOUT FOR E-1 ADMINI5TRATIVE FUNCTIONS l Notify STA (Monitor SPDS and Critical Safety Function Status Trees, Perform 9 1. 2. Appendix H) Refer to Appendix Z I SI REINITIATION CRITERIA l Manually operate ECCS pumps as necessary if EITHER condition listed below occurs: e RCS subcooling - LESS THAN 20 F. e PZR level - CANNOT BE MAINTAINED GREATER THAN 4[20%] J CHARGIN3 PUMP MINIFLOW ALIGNMENT CRITERION l Ensure Charging Pump Miniflow Valves 8105 and 810E OPEN if RCS Pressure is GREATER THAN 2000 PSIG. E-3 TRANSITION CRITERIA l Gc to E-3, STEAM GENERATOR TUBE RUPTURE, Step 2, if any SG level increases in an ur. controlled manner or any SG has abnormal radiation. CO 0 LE5 FECIRCc A'10N SalTCHUsER CRITEkl0h I Gc :: E-1.3, TPA.'.SFER TO COLC LEG RECIRCULATION, if RWST level decreases to LESS THAN
,m 33 .
l ' i A F a' 5tCFLv SWITCv6.EA CRITERICN l 5 witch to alterrate AFW water supply if CST level decreases to LESS THAN 10;. Refer te EP E-2.1, ALTERNATE AUXILIARY FEEDWATER SUPPLIES. 5 E CO*,; A ra J.TEGe T, CF ITEei A l Go to E-2, FAULTED STEAM GENERATOR ISOLATION if any SG is decreasing in an unccntrolled rar,ner cr has been corpletely depressurized and has not been isolated. ABNURMAL CCNTAif. MENT CRITERIA I Containment Pressure - GREATER THAN 3 psig
-CR-Containment Radiatier Oose Rate 105 R/hr
-CR-Containrer.t Fadiaticr. Dose 1Cf R j PRIMARf TO SECONCAFV DIFFEREhi!AL FFE55cRE l Depressurize the RCS to raf rtain the primary to secordary pressure difference less than 1600 psid, prcvided RCS subcooling is GREATER THAf, 20*F AND PZR level is GREATEF THAN 4% [20i].
( CNf1T SPRAf INITIATION CRITERIA l Initiate CNMT spray when ChMT pressure is greater than C2 psig. DC0436 321V
NUMBER EP E-1.1 T 3%G Pacific Gas and Electric Company REVISION 0 DEPARTMENT OF NUCLEAR PLANT OPERATIONS 1 AND 2 PAGE 1 0F 25 DIABLO CANYON POWER PLANT UNIT NO(S) EMERGENCY PROCEDURE SI TERMINATION TITLE IMPORTANT APPROVED 72 6 95-M TO PLANTMANAGEg) DATE SAFETY SCOPE This procedure provides the necessary instructions to terminate safety injection and stabilize plant conditions. This procedure and changes thereto requires PSRC review. SYMPTCMS OR ENTRY CONDITIONS This procedure is entered from the following procedures:
- 1. OP-0, REACTOR TRIP OR SAFETY INJECTION, Step 24, when specified temination criteria are satisfied.
- 2. OP-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 7, when specified termination criteria are satisfied.
- 3. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 30, af ter Seccncary Heat Sink has been re-established and SI is terminated.
O DC0436 IXI
NUMBER EP E-1.1 1 AND 2 otAsto CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/11/85 7,7 2 SI TERMINATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: If offsite power is lost after 51 reset, manual action will be required to restart some safeguards equipment. Refer to Appendix A for guidance if this condition occurs. 00TE: e Foldout page should be open. e if subccoling monitor becomes inoperable, determine subcooling by using WR RCS pressure and core exit TCs (refer to Appendix C).
- 1. RESET SI
- 2. RESET Both Trains of Containment Isolation Fnase A and Phase 6 At val
- 3. ESTABLISH Instrument Air To Try to establish air. Refer to containment: OP AP-9, LOSS OF INSTRUMENT AIR, while continuing. Avoid excessive
- a. Open FCV-584, cnmt inst air 150 cycling of valves that have backup viv (VB4) air bottles.
- b. Ensure at least one air compressor - IN SERVICE 4 ALIGN CHARGING
- a. Check any cent charg pp . RUNNING a.1) Ensure PD charging puro running.
(VB2)
- 2) Control charging pump speed and HCV-142 to maintain e Seal Injection e PZR Level
- 3) Go to Step 5.
- b. Open FCV.128 (CC2)
- c. Stop the PD charg pp (VB2)
- d. STOP one of two running cent charg pp (VB2)
O DC0436 2XI
NUMBER EP E-1.1 1 AND 2 REVISION 0 OtA8LO CANYON POWER PLANT UNIT NO(S) 3/11/85 Q b DATE PAGE 3 0F 25 7,7a SI TERMINATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. CHECK WR RCS Pressure Go to E.1, LOSS OF REACTOR OR
- 5 TABLE OR IhCREASING SECONDARY COOLANT.
- 6. ESTABLISH Charging Flow: (CC2/VB2)
- a. Throttle HCV-142 to 50t
- b. Manually open FCV.128
- c. Open 8105 and 8106, charg pps c. IF 8105 OR 8106 will not min flow recirc open, THEN maintain a minimum of 60 gpm charging.
- c. IF SG 4 intact, d. IF SG 4 NOT intact,
~
IITEN open 8146, normal charg to TREN close lit 46 and open 8147, p LP 4 cold leg. alt chg to LP 3 cold leg, V and go to Step 6f.
- e. Close 8145 and 8148, charge lir.e to PZR au spray and bypass viv
- f. Open 6107 and 8108, normal charg to regen hx stop vivs
- 7. ISCLATE BIT: (VB2)
- a. Close 8803 A & B, BIT supply vivs
- b. Close 8801 A & B, BIT outlet vivs a
DCC436 3XI
NUMBER EP E-1.1 I AND 2 REVISION 0 otAat.o CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 7g SI TERMINATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. CONTROL Charging Flow To Maintain PZR Level: (CC2/VBZ)
- a. Adjust charging flow and HCV-142 a. E PZR level continues to decrease, to maintain:
THEN realign charging through e PZR level - 17% [40',] to 607, BIT e Regen hx cooling AND e Seal injection to each RCP go to E-1.2, POST LOCA 8 (6-12) GPM C00LDOWN AND DEPRESSURIZATION.
- 9. CHECK If SI Furcs Should Ee Stocped:
- a. Check Pressure: a. IF any SG is faulted.
TREN do NOT proceed until e WR RCS pressure - STABLE OR INCREASING (VB2) faulted SG depressurization stops. h e WR ACS pressure - - IF no SG is faulted or criteria for stopping GREATEA THAN 1650 PSIG S! curro can NOT be sat'sfied after
- AND - faulted SG depressurization stops, f.D SI FLCW IN3!CATED (VC1) THEN go to E-1.2, POST-LOCA COCLCOWN AND DEPRESSURIZATICf..
- b. Stop both SI purps (VB1)
- 10. STOP Both FHR Puros (VBl)
O l DC0436 4XI
NUMBER EP E-1.1 1 AND 2 REVISION 0 OLABLO CANYON POWER PLANT UNIT NO(S)
,o DATE 3/11/85 5 0F 25 V PAGE 7gg SI TERMINATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 4
- 11. VERIFY ECCS Flow Not Required:
- a. RCS Subcooling a. -
IF RCS subcooling less than
. GREATER THAN 20*F (VS2) 20*F, THEN realign the charging pump through the BIT and manually operate ECCS pumps as necessa ry. Go to E-1.2, POST LOCA C00LD0WN AND DEPRESSURIZATION.
- b. PZR Level - GREATER THAN b. Control charging flow to 4;[20;](CC2/VB2) maintain PZR level.
IF PZR level can NOT be maintained,
- THEN realign the charging pump through the BIT q and manually operate ECCS pumps as necessary. Go to E-1.2, POST LOCA C00LDOWN AND DEPRESSURIZATMN.
- 12. VEE Ff PZR Level Established To Place Letorwn In Service:
- a. PZR level - GREATER THAN a. increase charging flow to 17'4 [40t](CC2/VB2) establish pressurizer level greaterthan17%[40%).
v) DC0436 Sr!
NUMBER EP E-1.1 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 7,7 g SI TERMINATION ACTION /EXECTED ESPONSE ESRJNSE NOT OBTAINED NOTE: A maximum temperature of 380*F on the letdown outlet of the regenerative heat exchanger (TI-127) should not be exceeded.
- 13. ESTABLISH RCS Letdown And No Load Pressurizer Level:
ESTABLISH Excess Letdown:
- a. Open FCV-355, CCW hdr C iso 1) Place 8143, excess Itdn to seal valve (VB1) wtr hx or RCDT valve, in the NORMAL position,
- b. Position to 20 TCV-130, LTDN teg cont viv (VB2) 2) Open FCV-361, CCW from excess Itdn hx iso viv.
- c. Position to 40% PCV-135, letecwn pressure cent viv (VB2) 3) Close HCV-123, excess letdown pressure control valve.
- d. Open LCV *59 and LCV 460, Itdn stop vivs (VB2) 4) Open 8166, RCS excess ltdn isol viv, and 8167, excess ltdn stop
- e. Manually control charging flow viv.
through regenerative beat HX - GREATER THAN 45 GPM (CC2) 5) Open 8100 and 8112, RCP seal water return step viv.
- f. Ensure ir. AUTO, LCV-112A, VCT Ivl control vis (VB2) 6) Slowly open HCV-123, to establish excess letdown flow,
- g. Open 8152, letccwn iso viv OC Do not exceed 190'F on TI-122, (VB2) excess letdown temp.
- h. Ocen Itdn orifice stop vivs, as THEN do Step 13j.
necessary (VB2) e 8149A - 45 gpm e 81498 - 75 gpm e 8149c - 75 gpm
- 1. Control PCV-135, to maintain 350 PSIG upstream of valve (VB2)
- j. Manually control charging to maintain PZP level between 17%
[40~,]and.60tandlessthan 380*F on TI-127 (CC2/VB2)
- k. Control PZR heaters as necessa ry DC0436 6XI
NUMBER EP E-1.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION O DATE 3/11/85 PAGE 7 0F 25 [Gl 7,7 g SI TERMINATION ACTION / EXPECTED RESPONSE RESPONSE f0T OBTAINED 14 PLACE VCT Makeup System In Service: (CC2)
- a. Ensure makeup set for . GREATER THAN RCS CONCENTRATION OR 2000 PPM (7 turns)
- b. Refer to OP B.1A:VII "CVCS b. IF AUTO makeup is NOT
. MAKEUP CONTROL SYSTEM operable, OPERATION" Part A THEN refer to OP 8-1A:VII
. PLACE IN AUTOMATIC Part B, CVCS REACTOR COOLANT DEGASSIhG . MANUAL OPERATION.
- 15. AllGN Charging Pumo Suction Frcm ine VCI: (VEc)
- a. Check VCT level >10i a. Go to Step 16
- AND -
WHEN VCT level >105 THEN align charg pp suction to VCT by performing steps 15b anc c,
- b. Open LCV.112C and LCV-112C, VCT outlet vivs
- c. Close 8805A and 8605B, charg pp suct from RWST vivs
- 16. CHECK If RCP Seal Return Flow Snculd Be Established:
- a. Check: a. Go to Step 17. OBSERVE NOTE PRIOR TO STEP 17.
e Open FCV-355, CCW hdr C iso viv (VE1)
- b. Open 8100 & 8112, RCP seal
() water return stop valves (V82) DC0436 7/I
i NUMBER EP E-1.1 1 1 AND 2 REVISION 0 f DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 7,7 7 SI TERMINATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: If Main Steam Isolation Signal verify steam piping downstream of MSIVs before opening MS!V bypass viv.
- 17. CHECK IF Condenser Steam Dump IF Condenser Steam Dump is NOT Should Be In Pressure Control Mode: Available,
_THEN,use SG 107, steam dumps
- AND -
Go to Step 18.
- a. Check MSIVs - NOT ISOLATED (VB3)
- b. Check C-9 status light on (VB3)
- c. Set HC-507 at 8.38 turns (CC3)
- d. Check 05 demand en HC.507 (CC3) d. Increase setting on HC-507 to achieve Ot demand g
- OR .
Transfer HC-507 to manual and decrease demand to 0*.
- e. Transfer to PRESSURE CONTROL MODE on Steam Dump Selector Switch (CC2)
- f. Control Condenser Steam Dump Controller HC-507 to inaintain Stean pressure s1005 psig (CC3/VB3) 9 Place to CONT Of.LY, LCV-12 Selector Switch (VB3)
O DC0436 8XI
NUMBER EP E-1.1 I AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 PAGE 9 0F 25 7,7tg SI TERMINATION ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED
- 18. CHECK RCS Hot Leo Temperatures Control feed flow as necessary to
- STABLE (VB2) stabilize RCS temperature.
CAUTION: Auxiliary spray flow into the PZR shall not be initiated if the aT between the pressurizer and the spray fluid exceeds 560*F. Spray flow should not be initiated if the AT exceeds 320*F. _. t0TE: If PZR auxiliary spray is used, it may be necessary to close normal spray PCV-455A and B and charging valves 8146 and 8147.
- 19. CONTR01 PZP Pressure: (CC1/VB2)
- a. Turn on heaters and operate a. -
IF normal sprays are NOT normal spray as necessary to available and letdown is in ' mair.tain pressure stable service, THEN use aux spray, clcse norn.al spray and charging valves. IF aux spray is NOT available, TiiEN use one PZR P'CXV. fh Y s l DC0436 9XI l
NUMBER EP E-1.1 1 AND 2 REVISION 0 otAsto CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 7,7 g SI TERMINATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: Alternate water sources for AFW pu'nps will be necessary if CST level decreases to less than 10%. (Refer to E-2.1, ALTERNATE AUXILIARY FEEDWATER SUPPLIES).
- 20. CHECK Intact SG Levels: (V83/CC3)
- a. Check NR Level - GREATER THAN a. Maintain total feed flow greater 4%[20%] than 460 GPM until SG NR level greater than 4% [20%] in at least one SG.
- b. Control feed flow to maintain NR b. -
IF NR level in any SG continues level between 4; [20;] and 33'. to increase, THEN secure feed flow to that SG.
- c. Stop TD AFW pp if NOT needed for RCS heat renoval i
O DC0436 10XI 1
NUMBER EP E-1.1 DiAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/11/85 O 7,7g SI TERMINATION eact it or 28 ACTION / EXPECTED RESFONSE RESPONSE NOT OBTAINED
- 21. Verify RCP Cooling ALIGNMENT: (VB1)
- a. Verify CCW - ALIGNED To RCPs a. IF CCW NOT aligned to Os TiiEN ensure Phase B %.ni e Open FCV-355, CCW hdr C iso viv reset and manually open CCW valves.
o Open FCV-356, CCW to RCP oil coolers, therm bar & sup clrs e Open FCV-357, CCW from F.CP thermal barrier, OC e Open FCV-363, CCW from RCP oil clrs & sup cles, OC e Open FCV-749, CCW from RCP oil c1rs & sup clrs, IC e Open FCV-750, CCW from RCP thermal barrier IC
- b. Verify RCP seal injecticn flow to b. Adjust HCV-142 to maintain each RCP 8 (6 '2) GPM (VS2)
_ 8(6 - 12) gpm to each RCP. O DC0436 11XI i
NUMBER E? E-1.1 1 AND 2 REVISION 0 OtABLO CANYON POWER PLANT UNIT NO(S) 3/11/85 DATE PAGE 12 0F 25 g 7gg SI TERMINATION ACTION / EXPECTED ESPONSE RESPONSE NOT OBTAINED
- 22. VERIFY ALL AC Buses Try to restore offsite power.
- ENERGIZED BY OFF5ITE POWER IF power can NOT be restored, TffEN manually load the following equipment on the vital buses within DG capacity:
o PZR heaters (Refer to OP A-4A:I PZR-Make Available) e TSC
- 1) Open 52-22 J-40.
- 2) Open 52-2F-47.
- 3) Open 52-1F-67.
- 4) Switch EPTSN to vital power.
IF D/G 13 on U1 F bus,
- 5) TIIEN switch EPTSC to U-1 (52-1F-68) and CLOSE 52-1F-67.
IF D/G 13 on U2 t'us,
- 6) TiiEN switch EPTSC to U-2 (52-2F-47) and CLOSE 52-2F-47.
Transfer switches EPTSN and EPTSC are located in Unit 2 BUS 2F 480 Volt Switchgear Room. e Instrument Air O l DC0436 12XI
NUMBER EP E-1.1 DLABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/11/85 { } PAGE 13 0F 25 7,7 g SI TERMINATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: e If seal cooling had previously been lost, the affected RCP(s) should not be started prior to a status evaluation. e On natural circulation, RTD bypass temperatures and associated interlocks will be inaccurate. f0TE: RCP No. 2 (preferred) or RCP No. I should be given priority for purposes of normal PZR spray.
- 23. CHECK RCP Status - AT LEAST ONE Refer to appendix B to establish Rut.NING (V52) conditions for starting an RCP.
Check normal PZR spray vivs in AUTO AND { t Start one RCP . IF an RCP CANNOT be started, TiiEN operate steam dump from intact SG(s) to ensure:
- 1) RCS subcooling greater than 20;F.
- 2) SG pressures stable er decreasing.
- 3) RCS hot leg temperatures stable or decreasing.
- 4) Core exit TCs stable or decreasing.
- 5) RCS cold leg temperatures at saturation temperature for SG pressure.
I l l DC0436 13XI l
NUMBER IP E-1.1 1 AND 2 REVISION 0 DIABLO CANYON POWER Pt. ANT UNIT NO(S) DATE 3/11/85 PAGE 14 0F 25 SI TERMINATION Tira RESPONSE NOT OBTAINED ACTION /EXRCTED RESfGSE
- 24. CHECK If SR Detectors should Be Energized: (VS1)
- a. Continue with step 25.
- a. Check IR Flux - LESS THAN 10 10 amps WHEN flux is less than 10 10 amps, THEN complete Step 24b and c.
- b. Verify both SR detectors b. Manually reset and energize
- ENERGIZED both SR detectors.
- c. Select highest SR and IR detector on NR-45
- 25. CHECK If Diesel Generators Should Be Stocced: (v64)
- a. Verify vital busses F, G, and H a. -
IF any vital bus NOT energized
- ENERGIZED BY OFFSITE POWER by offsite power, THEN attempt to restore offsite power, either STARTUP or AUXILIARY, to the vital busses.
- b. Stop any unloaded DG and place in AUTO l
O DC0436 14XI l l
1 AND 2 NUMBER EP E-1.1 OtABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 A DATE 3/11/85 V PAGE 15 0F 25 TITLE. SI TERMINATION ACTION / EXPECTED RESFONSE RESPONSE NOT OBTAINED
- 26. Monitor Turbine Status: (VB3/CC3)
- a. Start AC turbine bearing oil a. Start DC pps.
pump and high pressure seal oil backup pump
- b. Monitor Turbine Coastdown per OP C-3:lv Main Unit Turbine -
Turbine Shutdown
- c. Ensure that main and feedpump turbines are on turning gear once 0 RPM is reached
- d. Break condenser vacuun if circ water pump NOT running J
POTE: Perform caly those portions of Steps 27 and 28 deemed necessary by
, the Shift Foreman
- 27. Shutdown the Followinc Eouionent If NOT Recu1 rec For Fost Accicent Recove ry:
- a. Reset auto ous transfer relay and shutdown one auxiliary saltwater pJmp if desired
- b. Close FCV-360 and FCV-366 CFCU .
maxiflow valves and then shutdown 1 CCW pump if desired (VB1)
- c. Remove 2 CFCU's from service and place the running CFCU's on fast speed if desired (VB1)
- d. Stop TD AFW pump if not need for RCS heat removal (VB3) l l
l DC0436 15XI l
b' UMBER EP E-1.1 1 AND 2 REVfSION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 PAGE 16 0F 25 7,7 g SI TERMINATION ACTION / EXPECTED RESR)NSE ESPONSE NOT OBTAINEI)
- 28. PERFORM The Following To Return Equipment To Pretrip Status If NOT Tecuired For Post Accident Recovery:
- a. Backfeed Unit Auxiliary Transformers from 500 KV system (refer to J-2:E CODE ORDER TO BACKFEED N0. 1 UNIT MAIN AND AUXILIARY Tr.ANSFORMERS FROM THE 500 KV SYSTEM AFTER THE MAIN UNIT HAS BEEN REMOVED FROM SERVICE)
- b. Reset containment ventilation isolation Train A and Train B:
- 1) Open the folicwing valves:
a) FCV-678, contmt air monitor suct viv IC b) FCV-679 & FCV-681, contmt air monitor suct/disch viv's OC
- 2) Reset R-11 purp and verify normal readings on R-11, containrent air particulate process monitor and R-12, containment radiogas process monitor
- c. Return the auxiliary building ventilation system to normal by resetting the "S" signal on both POV cabinets and selecting BUILDING ONLY Mode (V8-4), refer to OP H-1:1, section D, AUXILIARY BUILDING VENTILATION SYSTEM MAKE AVAILABLE AND SYSTEM OPERATION THIS STEP CONTINUED ON NEXT PAGE O
DC0436 16XI l l l l l 1
NUMBER EP E-1.1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 F DATE 3/11/85 PAGE 17 0F 25 7,72 SI TERMINATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- d. If the gross failed fuel detector had been in service prior to the SI, open RCS sample iso vivs FCV-9356A and FCV-9356B: (VB1)
- 1) Verify flow returns on the GFFD flowmeter
- 2) Verify the GFFD countrate returns on scale and stabilizes at a value below the pre-SI countrate on the recorder (VB1)
- e. Open FCV-9354A and FCV-9354B, PZR steam sample iso vivs (VBI)
() f. Open FCV-9355A and E, PZR lig sample Isb viv IC and OC
- g. Open 8880 Accum Fill gN Iso vlv
- h. Reset radwaste isolation valve reset switches: (VB2)
- 1) Rad Waste Isol Train A, IC
- 2) Rad Waste Isol Train B, OC
- i. Open 8045, PRT N 2 supply isol viv (VB2)
- j. Open FCV-8034A, PRT gas sample isol viv, IC (VB2)
- k. Open FCV-633, fire water to cnmt iso viv, and 8029, enmt primary wtr isol viv (VB2/3)
O THIS STEP CONTINUED ON NEXT PAGE U DC0436 17XI
NUMBER EP E-1.1 l 1 AN) 2 REVISION 0 i OtABLO CANYON POWER PLANT UNIT NO(S) ' DATE 3/11/85 7,7 g SI TERMINATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. If the incore chiller had been in service prior to the SI, open incore cooler chilled wtr isol valves FCV-655, FCV-657, FCV-654 and FCV-656 (VB4)
- m. Reset both Units 1 and 2 control room ventilation systems on Unit 2 radiation control board and verify both Units 1 and 2 ventilation systems return to the normal mode of operation
- n. Flush BIT outlet lines to cold legs for 20 minutes by opening the flush valve from charcing pumps discharge, 51-8969(el 109',185*)
- o. Return BIT to operable status per procedure OP B-1C:IV, 12".
h B0i!IC ACID SYSTEM - Restoring Boron Injection Tank After Safety Injectior.
- 29. MAINTAIN Plant Ccr.ditions Stable:
o PZR pressure o PZR level e RCS temperatures e Intact SG 1evels O DC0436 18XI
NUMBER EP E-1.1 1 AND 2 OLABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/11/85 (j) fm PAGE 19 0F 25 7,7 a SI TERMINATION ACTION / EXPECTED RESRASE RESPONSE NOT OBTAINED
- 30. VERIFY SI Flow Not Required:
- a. RCS Subcooling a. Isolate Letdown, realign the
- GREATER THAN 20*F charging pump through the (VB2) (Refer to Appendix C) BIT and manually operate pumps as necessary. Go to E-1.2, POST LOCA C00LDOWN AND DEPRESSURIZATION.
- b. PZR level - GREATER THAN b. Control charging flow to maintain 4 [20]%(VB2/CC2) PZR level.
IF PZR level can NOT be maintained, THEN Isolate Letdown, realign the charging pump through the BIT, and manually operate O- ECCS pumps as necessary. Go to E-1.2, POST LOCA C00LDOWN AND DEPRESSURIZATION. O DC0436 19XI 1 l
NUMBER EP E-1.1 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 PAGE 20 0F 25 7,7 g SI TERMINATION ACTION /EXRCTED RESPONSE RESPONSE NOT OBTAINED NOTE: An inadvertant safety injection will place the plant in one or more of the following Tech Spec Actions. e T.S. 3.3.2 Engineered Safety Features Actuation System Instrumentation e T.S. 3.5.2. ECCS Subsystems e T.S. 3.5.4. Boron Injection System o T.S. 3.5.5. Refueling Water Storage Tank
- 31. GO To Acolicable Plant Procedure
- a. IF inadvertant SI, TiIEN reset reactor trip breakers to enable auto SI
- b. Make out trip report (Refer to AP-10051 - REACTOR TRIP REPORT)
- c. Perform STP M-55 O
- c. Perform STP V-5 within 24 hours followinc the ECCS actuation for any valve listed on Table 3.4-1 of T.S. 4.4.6.2.2 if there was flow through the valve
- e. Notify:
- 1) Chem / Rad Department of l sampling requirements
- 2) I&C Department to perform STP I-3A: NUCLEAR INTERMEDIATE RANGE CHANNEL ANALOG CHANNEL CPERATIONAL/ FUNCTIONAL TEST
~
THIS STEP CONTINUED ON NEXT PAGE l O
- DC0436 20XI l
NUMBER EP E-1.1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/11/85 O- PAGE 21 0F 25 7,7g SI TERMINATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- f. Go to OP L-2, HOT STANDBY TO MINIMUM LOAD
- OR-OP L-5, PLANT C00LDOWN FROM MINIMUM LOAD TO COLD SHUTDOWN and review for applicable actions
- END -
O O DC0436 21XI i
-.- --.----.--,--v-, ---,,--,,..-..---.,e-...,,-w.,---y .---+,,,---.-we-..,--,..--
NUMBER EP E-1.1 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 7,7 7 SI TERMINATION APPENDIX A BLACK 0UT EMERGENCY LOADING 0F VITAL BUSSES
- 1. If the vital busses lose voltage prior to resetting the safety injection signal, the vital busses will automatically load the vital equipment given below. Verify the equipment has been loaded by observing breaker lights on the control board.
- 2. If the vital busses lose voltage after the safety injection signal has been reset, load or verify loaded the equipment given below onto the vital busses manually. Allow approximately 4 seconds between loading of each piece of equipment onto a given vital bus. Load or verify that the CFCU are running in Low Sceed.
VITAL BUS F VITAL BUS G VITAL BUS H U-1 (0/G l-3) U-1 (D/G No. 2) U-l (D/G No. 1) U-2 (D/G l-3) U-2 (D/G No. 1) U-2 (D/G No. 2) MCC F MCC G MCC H CC Pp No. 1 RHR Pp No. 1 SI Pp No. 1 CFCU No. 3 SI Pp No. 2 CFCU No. 2 CFCU No. 5 RHR Pp No. 2 CFCU No. 1 CCW Pp No. 2 CFCU No. 4 CCW Pp No. 1 ASW Pp No. 2 CCW Pp No. 3 ASW Pp No. 1 CC Pp No. 2 AFW Pp No. 2 AFW Pp No. 3 O DC0436 22XI i
NUMBER EP E-1.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 I REVISION O DATE 3/11/85 I I PAGE 23 0F 25 7,7a SI TERMINATION APPENDIX B Restart of Reactor Coolant Pump
- 1. Start oil lift pump, run for 2 minutes.
- 2. Verify CCW available to thermal barrier, oil coolers, seal water HX.
- 3. Verify seal dp greater than 215 psid, depressurize VCT as necessary.
4 Verify seal injection flow 8 (6 to 12) gpm.
- 5. Verify seal leak off flow within limits shown on graph.
- 6. Ensure closed 455A and B, normal PZR spray vivs (auto optionel).
j l ALLOWABLE RCP #1 SEAL LEAK RATES 5 4 ! l .
' l I f SHUTDOWN RCP WITH]N i ONE HALF H3UR .
3 1 ' I i i l I , i r , j r . I i i :
. I l
{ ' 0 I ' I i ! - i' ' l- ! l SAFE OPERATING REGION ' {E ' l . l I i l l l , ! r 5 l j I i REGIO 1 l REGION g 2 I i i g
' f 1 t !
I l
/ 00 NOT START RCP M i 0
200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 l RCF 81 Stat nIrrtpENTI AL PRESS'$E P5ID REGION 1 NO PHASE- A SIGNAL, dp=RCS -VCT press pru s PHASE.A PRESENT, dp=RC5 -150psig DC0436 23XI RtG108zuSrINSTI((ED6pGAUGES
NUMBER EP E-1.1 1 AND 2 REVISION 0 ; otAsto CANYON POWER PLANT UNIT NO(S) 1 DATE 3/11/85 7,7 g SI TERMINATION APPENDIX C 2MO . _ g. __ .._q, ____ .g__ g; . j. _ _=_ &. __ _ __. _. .{ _ . =. . ._____ ;, =._ ; = , =;_=_ :g _; g =_.,. . ___ 4 . _
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= = = , _ = . == = {-= .- . =:_
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.- - =_. = .=
- - - - - - : -2. _ _= = 2-. 2-. _ _ _ _ _ _ _ _ _ -
2200 _._ _ _ _ . _3.__,__ __.f_=._ ;
, - 1 _1
- - - - , -+--- _ _ _ _ .- 1 . ._
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- .= =~ - . __._ _,_; :.. . - _ = -
2000 ;;= ==_ ,_= 7; = . =y= = ;=x=4_ . ._ _ . _; _ _ __;. , _ f;3 __ _ .
- _ - . _ _ . _ . 2 [=1 - e
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" " -h " ~ ~*~ ~ * -'- ~
- 4._.c ""= - -t*2~2- 1:. - . g~ ~=~~.;' - - ~ ~ ~
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I800 L-n._2, F_-- ._ . .
=_ __.__ .n.. __. i.'__: !,: ._
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- h.x_ ._=_ =_ _d_. ic_ i._=._j= == F --
e . . _. u=;= ;_ m
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' 1600 == = =
=t.=-= == -- - -p--~ = ._ ~_,r- =
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_== =2 =. 1
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m 1400 _,_...; . 7-_ _..,_...= 4 i , g -
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- ..]. "" : . t . ---[#[-~ " # ~~~~1""-
1200 ~~~ E .t. 2 G~ j /: SATURATION ~~ I :- _=_Id[$$
~[~"'~ ; CORRECTED Z f_if_2 FOR~.'E'E CURVE SATURATION
~2 ~ CUR w 1000
--~ INSTRUMENT ERROR =T=T
---+-
;/g g --- p__y .
t = g._.; g - . = . , _ P-0
. _.-2t----'-b------- '~
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e 800 "._._~~_.*=_____*.,__~~'_q"_..=.'r.'.._;='._-".,-- _ _ g . . ._ 3 . _ _ __, ' .,__."n_ w _ _ - ._.- _ a _- . _ _ . i -, .
. . n-. _ -__ i
=-____: ..______.._L_.=_
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600 . ; .. _ y __ __ _ _ _ . _ _ . p . _ ;_. . . _ _ . _ . I Ei _ _1 1
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400 2_ _ .... p __2_ af-_=.__.".-2fg-,. ; =_ .=._ ; ; =q__ p., . .n .
- c. -
-r 200 t 65 W~
- .. q. -
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--_._s-- _._=.. ._. ..a 2 : _ y . ._.a___.._.
'I-~ .. - -~f ' 3 ._._ _..-~~ '-
- - 3' "'
200 300 400 500 600 700 CORE EXIT T/C TEMPERATURE (*F) O DC0436 24XI I
NUMBER EP E-1.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 g) DATE 3/11/85 25 0F 25 (G SI TERMINATION PAGE m LE: APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Designate this event a Notification of Unusual Event.
- b. If a steam line break is accompanied with a known primary to secondary leakage >10 gpm as indicated by high radiation alarms on the air ejector, steam generator blowdown, sample or by an increase in steam generator water level in an unexpected manner, designate this event as an Alert.
- c. If plant conditions indicate the required conditions for reactor trip have occurred or the required coincidence of bistables have tripped, or trip is manually activated, and nuclear instrumentation indicate the reactor is not subtritical (e.g., non-negative startup rate) designate this
(],s event an Alert.
- 2. Notify plant staff and response organizations required for this classification by implemer. ting Procedures EP G-2 " Establishment of the On-Site Emergency Organization" and EP G-3 " Notification cf Of f-Site Organizatior.s" in accorcance with EP G-1 " Accident Classification and Emergency Plant Activation."
DC0436 25XI 1
FOLD 0VT FOR E-1.1 l ADMINISTRATIVE FUNCTIONS l O 1. 2. Notify STA (Monitor SPDS and Critical Safety Function Status Trees) Refer to Appendix Z l ' ~~ SI REINITIATION CRITERIA l 4 Manually operate ECCS pumps as necessary if EITHER condition listed below occurs: e RCS subcooling - LESS THAN 20*F e PZR level - CANNOT BE MAINTAINED GREATER THAN 4% [20%] CHARGING PUMF MINIFLOW ALIGNMENT CRITERION l i Ensure Charging Pump Miniflow Valves 8105 and 8106 OPEN If RCS Pressure is GREATER THAN 2000 PSIG. ! i j E-3 TRAN5ITION CRITERIA l Go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 2, if any SG level increases to an uncontrolled manner or any SG has abnormal radiation. I COLD LEG RECIRCULATION SWITCHOVER CRITERION l Go to E-1.3, TRANSFER TO COLD LEG iiCIRCULATION, if RWST level decreases to less than 336. AFv; SUPPLf SWITCHOVER CRITERION l i Switch to alternate AFW water supply if CST level decreases to less than 10i. Refer to E-2.1 ALTERNATE AFW SUPPLIES. 4 SEC0hDARY INTEGRITY CRITERIA l ) Go to E-2, FAULTED STEAM GENERATOR ISOLATION if any SG is decreasing in an j- uncontrolled manner or has been completely depressurized and has not been isolated. i l ADVERSE CONTAINMENT CRITERIA l e Containment pressure GREATER THAN 3 psig o Containment radiation GREATER THAN 105 R/hr dose rate o Containment radiation GREATER THAN 106 R dose PRIMARY TO SECONDAR'Y PRES 5URE DIFFERENTJAL CRITERIA l Depressurize the RCS to maintain primary to secondary pressure difference less than 1600 psid provided RCS subcooling is greater than 20*F and PZR level is greater than 4% [20%). l
- DC0436 '26X
l NUMBER EP E-1.2
, 3 G v4 3 Pacific Gas and Electric Company REVISION 0 l A DATE 3/12//85 DEPARTMENT OF NUCLEAR PLANT OPERATIONS I ' l PAGE 1 0F 28 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE POST LOCA C00LDOWN AND DEPRESSURIZATION l- TITLE W IMPORTANT APPROVED YS PLANTMANAp DATE SAFETY SCOPE This procedure provides direction to cool down and depressurize the RCS to cold shutdown conditions following a loss of reactor coolant inventory. This procedure and changes thereto requires PSRC review.
SYMPTOMS OR ENTRY CONDITIONS This procedure is entercd fron the following procedures:
- 1. E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 15, when RCS pressure is greater than the shutoff head pressure of the RHR purps.
- 2. E-1.1, SI TERMINATION, Step 8 and Step 30, when PZR level cannot be maintair.ed with rcrmai charging,
- 3. E-1.1, SI TERMINATI0h, Step 9, when LR RC5 pressure is less than the shutoff head pressure of the SI pumps.
4 E-1.1, SI TEPRINATION, Step 11 and Step 30, when RCS subcooling is less than 20'F. O DC0436 IVIV i _
NUMBER E) E-1.2 1 AND 2 REVISION 0 OIAB'.O CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 2 0F 28 mi POST LOCA C00LD0WN AND DEPRESSURIZATION ACTION XPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: e If RWST level decreases to less than 33%, the ECCS System should be aligned for cold leg recirculation using E-1.3, TRANSFER TO COLO LEG RECIRCULATION. e If offsite power is lost after SI reset, manual action will be required to restart some safeguards equipment. Refer to Appendix A if this condition occurs. If in Recirculation Mode charging pumps should be held in the OFF/ RESET position until an RHR pump is in service, e If subcooling monitor becomes inoperable, determine subcooling by using WR RCS pressure and core exit TCs (Refer to APPENDIX C). f0TE: e Foldout page should be open.
- 1. RESET SI
- 2. RESET Both Trains of Containment Isolation Pnase A and Fnase B At (V51)
- 3. ESTABLISH Instrument Air To Containment:
- a. Open FCV-584, CNMT inst air iso viv (VE4)
- b. Open 8E80, CNMT N ISO VI* (v01) 2
- c. Ensure at least one air c. Start at least one instrument air compressor - IN SERVICE (VB4) compressor.
IF instrument air can NOT be restored, THEN refer to OP AP-9, LOSS OF INSTRUMENT AIR, while continuing in this procedure. O DC0436 2VIV l l
NUMBER EP E-1.2 1 AND 2 DLABLO CANYON POWER PLANT UNIT NO(S) REVISION 0
/'"N DATE 3/12/85 '
() PAGE 3 0F 28 7,7 a POST LOCA C00LDOWN AND DEPRESSURIZATION ACTION / EXPECTED RESPONSE RESPONSE t0T OBTAINED 4 VERIFY All AC Busses . ENERGIZED BY Try to restore offsite power. OFF5ITE POWER: (VB4/VB5) IF power can NOT be restored, TREN manually load the following equipment on the vital buses within DG capacity (2.6 MW): o PZR heaters (Refer to OP A-4A:I, PZR MAKE AVAILABLE). e TSC
- 1) Open 52-22J-40.
- 2) Open 52-2F-47.
- 3) Open 52-IF-67.
- 4) Switch E PTSN to vital power.
- 5) IF D/G 13 on U1 F bus, TREN swit h EPTSC to U-1 (52-1F-67) and CLOSE 52-1F-67.
- 6) IF D/G 13 on U2 F bus, THEN switch EPTSC tc U-2 (52-2F-47) and CLOSE 52-2F-47.
Transfer Switches eptsn and eptsc are located in unit 2 , bus F 480 volt switchgear room, e Instrument air
- a. Stop any unicaded DG and place in AUTO (VBa)
O l l i DC0436 3VIV
oiAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 fff0N DATE 3/12/85 PAGE 4 0F 28 TITLE. POST LOCA C00LDOWN AND DEPRESSURIZATION ACTION /EXPEutu RESf0NSE RESPONSE POT OBTAINED CAlJTION: RCS Pressure should be monitored. If WR RCS pressure decreases to less than 300 psig, the Residual Heat Removal pumps must be manually restarted to supply water to the RCS. S. CHECK If RHR Pumps Should Be Stopped:
- a. Check WR RCS Pressure: (VB2) a. Go to Step 6. OBSERVE CAUTION PRIOR TO STEP 6.
9 STABLE OR INCREASING e WR RCS Pressure
- GREATER THNi 3C0 PSIG
- b. Check RHE, b. Go to Step 6. CBSERVE CAUTION
- ALIGNED FOR ECCS INJECTION PRIOR TO STEP 6.
- c. Stop botn REF. pumps (VB1)
O DC0436 4VIV
NUMBER EP E-1.2 ILO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0
'~N DATE 3/12/85 (d PAGE 5 0F 28 f_ POST LOCA C00LDOWN AND DEPRESSURIZATION ACTION /EXRCTED ESPONSE ESPONSE NOT OBTAINED AUTION: Alternate water sources for AFW pumps will be necessary if CST level decreases to less than 10% (refer to E-2.1 ALTERNATE AUXILIARY FEEDWATER SUPPLIES).
CHECK Intact SG Levals: (VB3)
- 3. Check intact SG(s) NR level a. Ensure total feed ficw
- GREATER THAN 4t [20L] greater than 460 gpc UNTIL NR level is greater than 4% (20!] in at least one intact SG. /} . Control feed flow to maintair. b. IF NR level in any intact SG \s / SG NR level between 4% [20!) and continues to increase in an 33% uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTur,E.
- c. Stcp TD AFW pc if NOT needed for RCS heat remov61 O\
V DC0436 SVIV l l
NUMBER EP E-1.2 1 AN> 2 REVISION 0 otAsto CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 6 0F 28 POST LOCA C00LDOWN AND DEPRESSURIZATION TsT u ACTION / EXPECTED RESPONSE ESR)NSE NOT OBTAINED Condenser Steam Dump is NOT
- 7. CHECK IF Condenser Steam Dump Should E available, Be In Pressure Control Mode:
THEN use SG 10% Steam Dumps
- AND -
Go to Step 8. Observe CAUTION prior to Step 8.
- a. Check HSIVs - NOT ISOLATED (VB3)
- b. Check C-9 status light on (VB3)
- c. Set HC-507 at 8.38 turns (CC3)
- d. Check 0; demand on HC-507 (CC3) d. Increase setting cn HC-507 to achieve 0% derrand
- OR -
Transfer HC-507 to manual and decrease demand to O',
- e. Transfer to PRESSURE CONTROL MODE cr: Stean Durp Selector Switch (CC2)
- f. Control Condenser Steam Durp Controller HC-507 to maintain steam pressure s1005 psig (CC3/VB3) 9 Place to CONT ONLY, LCV-12 selecter switch (VB3)
O CC0436 6VIV
NUMBER EP E-1.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 (~'% DATE 3/12/85 U PAGE 7 0F 28 TITLE. POST LOCA C00LDOWN AND DEPRESSURIZATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: e Shutdown margin should be monitored during RCS cooldown. e Select bypass on steam dump interlock / bypass switch when P-12 actuates (PK 08-06).
- 8. INITIATE A Continuous RCS Cooldown To Colc Shutdown:
- a. Maintain cooldown rate in RCS cold legs - LESS THAN 100 in any one hour period
- b. Use RHR System if in service
- c. Dump stean to condenser from c. Dump steam using intact intactSG(s) SG(s) 10*. steam dumps.
() 9. CHECK RCS Subcooling
- GREATER INAr. 20'F Go to Step 23.
(VB2) O( DC0436 7V!V
NUMBER EP E-1.2 1 AND 2 REVISION 0 otABLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 8 0F 28 7,7g. POST LOCA C00LOOWN AND DEPRESSURIZATION ACTION /EX KCTED RESFONSE RESRESE NOT OBTAINED IF ECCS is NOT in service,
- 10. CHECK If ECCS Is In Service: TREN go to Step 19.
(V81/ VB2) e BIT - NOT ISOLATED
-0R-e Check any SI Pump - RUNNING
- 11. PLACE All PZR Heaters In Off Position (CCl)
O O DC0436 8VIV l l
NUMBER EP E-1.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 ('- s_ PAGE 9 0F 28 TITLE. POST LOCA C00LDOWN AND DEPRESSURIZATION ACTION /cXPECTED RESf0NSE RESPONSE NOT OBTAINED CAUTION: e Voiding may occur in the RCS during RCS depressurization. This will result in a rapidly increasing PZR level. e Auxiliary spray flow into the PZR shall not be initiated if the delta T between the pressurizer and the spray fluid excels 560'F. Spray flow should not be initiated if the delta T exceeds 320 F. NOTE: If auxiliary spray is used, it may be necessary to close normal spray PCV-45SA and B and charging valves 8146 and 8147.
- 12. DEPRESSURIZE RCS To Refill PZR To IF PZR level >17% [40],
Greater inan 17t L40aj: TREN go to step 13. OBSERVE THE tiOTE AND CAUTION PRIOR TO STEP 13. ( a. Use normal PZR spray (CC2) a. Use auxiliary spray. Ij_ auxiliary spray NOT available THEN use one PZR PORV.
- b. Check PZR level - GREATER THAN b. Continue with Step 13. OBSERVE 17% [40t] (CC2/VB2) NOTES AND CAUTIONS PRIOR TO STEP 13
- AND -
WHEN PZR level is greater than 17% [40t], THEN to 90 step 12c.
- c. Perform the following:
- 1) Stop RCS depressurization
- 2) Maintain RCS pressure stable S
s) DC0436 9VIV
NUMBER EP E-1c2 1 AND 2 REVISION 0 0iAsto CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 10 0F 28 TITLE: POST LOCA C00LDOWN AND DEPRESSURIZATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: e If seal cooling has previously been lost, the affected RCP(s) should not be started prior to status evaluation, e On natural circulation, RTD bypass temperatures and associated interlocks for Feed Line Iso, Hi Stm Flow SI and Steam Dump will be inaccurate. t0TE: All but one RCP may be stopped to minimize pump heat input. If maintaining a 100 F/hr cooldown, running 2 RCPs is desirable; RCP 1 or 2 (#2 preferred) for normal PZR spray and RCP 3 or 4 to maximize MD AFW pump capacity.
- 13. CHECK If An RCP Should Be Started:
(VB2/CC2)
- a. Check All RCPs - STOPPED a. Stop all but cr.e RCP if desired and go to Step 14.
- b. e RVLIS Full range greater than 100%
- 1) Check RCS subcooling 1) Go to Step 24
- GREATER THAh 20 F
- 2) Check PZR level - GREATER 2) Return to step 12. Observe THAN 176 [40i] NOTE and CAUTIONS prior to
- OR - Step 12.
e RVLIS Full Range LESS THAN ---------------- 100N or RVLIS not available
- 1) Check PZR level - 1) Go to Step 24 GREATER THAN
- 2) Return to Step 12 UNIT 1 UNIT 2 65% [d0;j 75: L90tj ----------------
- 2) Check RCS subcooling -
GREATER THAN 40'F.
- c. Operate PZR heaters as necessary to heat PZR water to saturation temp for RCS hot leg pressure (CC1) ,,
- d. Establish conditions for d. Go to Step 14.
starting an RCP as per APPENDIX B
- e. Start at least one RCP nww me r v
l DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 DN 3/12/85 (/) DATE PAGE 110F 28 TITLE: POST LOCA C00LDOWN AND DEPRESSURIZATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: e After stopping any ECCS pump, WR RCS pressure should be allowed to stabilize before stopping another ECCS pump. e The charging pumps and SI pumps should be stopped on alternate ECCS trains when possible.
- 14. CHECK If One Centrifugal Charoing Pump Should Be Stopped: (VB2)
- a. Verify both cent charging pumps - a. I F_ both cent charging RUNNING pumps NOT running, THEN go to Step 15.
- b. Determine required RCS subcooling from table:
SI RCS SUSC00LIhG ("F) Pumo Status Ary RCP Running No PCP Running None Running 58*F 73 F One Running 52'F 55'F Two Running 52 55*F
- c. Verify RCS subcooling c. Go to Step 23.
. GREATER THAN REQUIRED SUSC00LINC
- d. Verify PZR level d. Return to Step 12. OBSERVE
-GREATERTHAN17%[40:3 NOTES AND CAUTIONS PRIOR TO STEP 12.
- e. Stop one cent charging pump l
l [\~ /) ) i { l . l DC04?6 11VIV ! l l
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 f0N l I DATE 3/12/85 PAGE. 12 0F 28 l TITLE. POST LOCA C00LD0WN AND DEPRESSURIZATION l 1 1 ACTION /EXPEutu RESPONSE RESPONSE NOT OBTAINED
- 15. CHECK If One SI Pump Should Be Stopped:
- a. Verify any SI pump a. -
IF no SI pumps are
- RUNNING (VB1) running, THEN go to Step 16.
- b. Detemine required RCS subcooling from table SI PUMP RCS SUBC00 LING (*F)
STATUS One Cent. Charging Pump Running No Cent. Charging Pump Running Any RCP Running No RCP Running Any RCP Running No RCP Running One Do not Do not Punning 9a F 117*F stop SI PP stop SI PP Two Running 29 F 33*F 37 F 46*F
- c. Check RCS Subcccling c. Go to Step 23.
- GREATER THAN REQUIRED SUSC00 LING (VB2)
- d. Check PZR level d. Return to step 12. OBSERVE
- GREATER THAN 17% [40t] NOTES AND CAUTIONS PRIOR T0 (VB2/CC2) STEP 12.
- e. Stop one additicnal SI pump (VB1)
- f. Go to Step 23 O
DCC436 12VIV
DIABLO CANYON POWER PLANT UNIT NO(S) NUMBER EP E-1.2 1 AND 2 REVISION 0 DATE 3/12/85 O' PAGE 13 0F 28 TITLE. POST LOCA C00LDOWN AND DEPRESSURIZATION ACTION / EXPECTED RESF0NSE RESPONSE NOT OBTAINED
- 16. CHECK If Norval Charging Should Be Established: (VBl/VB2)
- a. Verify ECCS pump status: a. Go to Step 23.
e Both SI pumps - STOPPED e Centrifugal charging pumps
- ONE RUNNING
- b. Verify RCS subcooling: b. Go to Step 23.
- GREATER THAN E4*F IF ANY RCP RUNNING
- OP -
- GREATER THAN 101'i IF hG RCP RUNNING
- c. Check PZP level c. Return to Step 12. OBSERVE
-GREATERTHAN17%[40k] NOTE AND CAUTIONS PRIOR TO STEP 12.
O DC0436 13VIV
NUMBER EP E-1.2 1 AND 2 REVISION 0 otABLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 14 0F 28 7,7 g POST LOCA C00LDOWN AND DEPRESSURIZATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 17. ESTABLISH Charging Flow: ,
- a. Throttle HCV-142 to 50% (CC2)
- b. Open FCV-128 (CC2)
- c. Open 8105 & 8106, charg c. E 8105 or 8106 will NOT open, pps min flow recirc vlvs THEN maintain a minimum of 60 gpm charging flow.
- d. IF SG 4 intact d. IF SG 4 NOT intact, TiIEN open 8146, normal charg to TREN Open EIT7 alt charg to LP 4 cold leg viv and close LP 3 cold leg viv and 8147, alternate charg to close 8146.
LP3 cold leg viv
- e. Close 8145 and 8148, charg line to PZR aux spray and bypass vivs (VB2)
- f. Open 8107 and 8108, normal charging to regen hx stop vivs (V82)
- 18. ISOLATE BIT: (VE2)
- a. Close 8803A & B, BIT supply vivs
- b. Close 8801A & B,. BIT outlet vivs O
DC0436 14VIV
NUMBER EP E-1.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 04 PAGE 15 0F 28 7,7g. POST LOCA C00LDOWN AND DEPRESSURIZATION ACTION /EXhuw RESFONSE RESPONSE NOT OBTAINED
- 19. CONTROL Charging Flow To Maintain PZR Level: (CC2)
- a. Control charging flow & HCV-142 to maintain:
o PZR level >17% [40%] e Seal injection to each RCP 8 (6-12) GPM, unless isolated due to a hot seal O O l DC0436 15VIV i
NUMBER EP E-1.2 1 AND 2 REVISION 0 otAsLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 16 0F 28 7,7 g POST LOCA C00LDOWN AND DEPRESSURIZATION ACTION /EXRCTED RESPONSE RESFONSE NOT OBTAINED CAUTION: e If RCP seal cooling had previously been lost, the affected RCP(s) should not be started prior to a status evaluation. e On natural circulation, RTD bypass temperatures and associated interlocks for Feedline Iso, Hi Stm Flow SI and Steam Dump will be inaccurate. f0TE: All but one RCP may be stopped to minimize pump heat input. If maintaining a 100*F/hr cooldown, running 2 RCPs is desirable; RCP 1 or 2 for normal PZR spray and RCP 3 or 4 to maximize MD AFW pump capacity.
- 20. CHECK RCP Status: (VB2)
- a. Check RCPs a. Try to start one RCP.
- AT LEAST ONE RUNNING
- 1) Establish conditions for starting an RCP per Appendix B.
- 2) Start one RCP.
IF an RCP can NOT be started. THEN cperate steam dump to ensure; e RCS subcooling greater than 20"F. e SG pressures stable or decreasing. e RCS hot leg temperatures stable or decreasing, e Core exit TCs stable or decreasing. e RCS cold leg temperatures at saturation temperature for SG pressure.
- 3) Continue with Step 21.
- b. Stop all but one or two RCPs, if desired DC0436 16VIV I I
NUMBER EP E-1.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 ( PAGE 17 0F 28 TITLE: POST LOCA C00LDOWN AND DEPRESSURIZATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: Voiding may occur in the RCS during RCS depressurization. This will result in a rapidly increasing PZR level.
- 21. DEPRESSURIZE RCS To Minimize Break Flow;
- a. Use normal PZR spray (CC2) a. Use aux spray.
E aux spray NOT available, THEN use one PZR PORV. t, . Turn on PZR heaters as necessary (CC1)
- c. Depressurize RCS until either of the following conditions satisfied: (CC2/VB2) e PZR level
- GREATER THA'. 77k [70'.]
-OR-e RCS subcoolirg
- LESS THAN 20'F
(~') v DC0436 17VIV l l
NUMBER E? E-1.? DIABLO CANYON POWER PLANT vNIT NO(S) 1 AND 2 REVISION O DATE 3/12/85 18 0F 28 PAGE llll POST LOCA C00LDOWN AND DEPRESSURIZATION TITLE: ACTION /EXKdw RESF0NSE RESFONSE NOT OBTAINED
- 22. VERIFY Adequate Shutdown Margin:
- a. Sample RCS
- b. Shutdown margin . b. Borate as necessary.
ADEQUATE (Implement STP R-19, SHUTDOWN MARGIN CALCULATION)
- 23. VERIFY ECCS Flow Not Required:
(VB2)
- a. Verify RCS Subcooling a. Manually operate ECCS
- GREATER THAN 20 F pumps to restore RCS subcooling to greater than 20 F AND go to Step 24
- b. Verify PZR level b. Manually operate ECCS
- GREATER THAN 4% [20S] pumps to restore PZR level GND return to Step 12. OBSERVE NOTE AND CAUTION PRIOR TO STEP 12.
w O IC0436 18VIV ;
NUMBER EP E-1.2 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/12/85 O PAGE 19 0F 28 U 7,7,y POST LOCA C00LDOWN AND DEPRFSSURIZATION ACTION / EXPECTED RESPCNSE RESPONSE NOT OBTAINED
- 24. CHECK If Accumulators should Be Isolated:
- a. Verify RCS pressure <1000 psig a. Go to Step 25
- b. Verif y RCS subcooling b. -
IF RCS hot leg temperature
- GR$TER THAN 70*F (VB2) greater than 400*F, THEN go to Step 25.
IF RCS hot leg temperature less than 400*F, THEN complete Steps 24c and d.
- c. Check pcwer to accumulator disc c. Restore power to isolation .
isc vivs - AVAILABLE (VB1) valves.
) ________________
- d. Close all accumulator disch iso d. -
IF any accumulator vivs (VB1) discharge isolation valve does NOT close, 6805 A, B, C & D THEN perform the following to depressurize the accumulator:
- 1. Close FCV-8880 accum N2 fill iso viv.
- 2. Open 8835 A, B C or D accum N2 cupply viv to affected accum.
- 3. Open HCV-943 N2 vent from accum until accumulator is depressurized, and continue in this procedure.
l (3 uj l DC0436 19VIV
NUMBER EP E-1.2 1 AND 2 REVIS10N 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 7g POST LOCA C00LDOWN AND DEPRESSURIZATION ACTION /EXhtiw RESPONSE RESPONSE NOT OBTAINED
- 25. CHECK If Diesel Generators should Be Stopped: (VB4)
- a. Check vital buses F, G and H a. -
IF any vital bus NOT
- ENERGIZED BY OFFSITE POWER energized by oTTsite power, THEN attempt to restore offsite power, either STARTUP or AUXILIARY, to the vital busses.
(Refer to ECA-0.3, RESTORE VITAL BUS)
- b. Stop any unloaded OG and place in AUTO
- 26. VERIFY RCP Cooling:
- a. Verify CCW - ALIGNED TO RCPs a. IF CCW NOT aligned to RCPs (VBI) TfiEN ensure Phase B Isolation is reset and
- 1) Open FCV-355, ccw hdr C iso manually open CCW viv valves.
- 2) Open FCV-356, CCW to PCP oil coolers, therm bar & sup coolers
- 3) Open FCV-749, CCW from RCP oil coolers & sup cirs IC
- 4) Open FCV-750, CCW from RCP thermal bar IC
- 5) Open FCV-363, CCW from RCP oil coolers & sup clrs 0C
- 6) Open FCV-357, CCW from RCP 1 therm bar, OC
- b. Verify RCfseal injection flow b. Adjust HCV.142, to maintain l to each RCP 8 (6 TO 12) GPM (VB2) 8 (6 to 12) gpm to each RCP, J (CC2) i e1 DC0436 20VIV
NUMBER EP E-1.2 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S)
/~'N DATE 3/12/85 k) PAGE 210F 28 s
TITLE: POST LOCA C00LDOWN AND DEPRESSURIZATION f ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 27. CHECK If RCP Seal Return Flow Should Be Established:
- a. Check open FCV-355 CCW hdr C iso a. Go to Step 28.
viv (VBI) .....___________
- b. Open 8100 & 8112, RCP seal water Return Stop Valve (VB2)
- 28. CHECK If S.R. Detectors Should Be Energized: (CCl)
- a. Check IR Flux a. Continue with Step 29 and
- LESS THAN 10~10 AMPS WHEN flux less than 10~10 amps, THEN complete Steps 28b and C.
- b. Verify both SR detectors b. Manually energize SR
- El.ERGIZED detectors.
- c. Select highest SR and IR detector on NR 45 i
O DC0436 21VIV l
' NUMBER EP E-1.2 1 ANU 2 REVISION 0 OIABLO CANYON POWER PLANT UNIT NO(S)
DATE 3/12/85 7,7g, POST LOCA C00LD0WN AND DEPRESSURIZATION ACTION / EXPECTED RESF0NSE RESPONSE tot OBTAINED
- 29. EVALUATE Plant Equipment Status:
- a. Start AC turbine B0P and H.P. a. Start DC pumps, seal oil backup pump if not running (VB4)
- b. Refer to OP L-5, PLANT C00LD0WN FROM MINIMUM LOAD TO COLD SHUTDOWN, for applicable actions while continuing In this procedure
- 30. CHECK If RCPs Must Be Stopped:
(VB2)
- a. Check the following: a. Go to step 31.
e Number 1 ser.1 differential pressure
- LESS THAN 215 PSID
- OR -
e Number 1 seal leakoff flow outside limits of Appendix B
- b. Stop affected RCP(s)
O DC0436 22VIV
NUMBER EP E-1.2 DIABLO CANYON POWER PLANT UNIT NO(S) I AND 2 REVISION 0 DATE 3/12/85 I I PAGE 23 0F 28 TITLE. POST LOCA C00LDOWN AND DEPRESSURIZATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 31. CHECK If RHR Systen Can Be Placed In Service:
- a. Check RCS conditions to place a. Go to Step 32.
RHR system - IN SERVICE e RCS temperature
- LESS THAN 350 F (VB2) e RCS WR pressure
- LESS THAN 390 PSIG (VB2)
- b. Consult TSC to determine if cut in of the low setpoint overpressure protection system is desired l I c. Consult plant engineering staff c. Go to Step 32.
s determine if RHR System should be placed in service
- d. Implement 0F B-2:V, RHR - PLACE IN SERVICE DURING PLANT CCOLDOWN
- 32. CHECK RCS Temperature Return to Step 5. OBSERVE
- LE55 InAN 200;F CAUTION PRIOR TO STEP 5.
- 33. DETERMINE If Reactor Vessel Head Snould Be Vented
- a. Consult TSC for venting a. Go to Step 34.
approval
- b. Implement FR-I.3, RESPONSE TO j VOIDS IN REACTOR VESSEL l I l
- DC0436 23VIV
l l r NUMBER EP E-1.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 7,7g, POST LOCA C00LD0WN AND DEPRESSURIZATION ACTION / EXPECTED RESPONSE RESFONSE NOT OBTAINED
- 34. EVALUATE Long Tem Plant Status:
- a. Maintain cold shutdown conditions:
e RCS temp < 200*F e K,ff < .99
- b. Check cor.tainment atmosphere to detemine if hydrogen recombiners or if hydrogen purge should be placed in service
- c. Implement OP L-5 PLANT C00LDOWN FROM MINIMUM LOAD TO COLD SHUTDOWN and review of applicable actions
- d. Consult plant engineering staff in TSC
- END -
O DC0436 24VIV
NUMBER EP E-1.2 1 AND 'o OIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 G DATE 3/12/85 h PAGE 25 0F 28 rir e POST LOCA C00LDOWN AND DEPRESSURIZATION APPENDIX A BLACK 0UT EMERGENCY LOADING OF VITAL BUSSES
- 1. If the vital busses lose voltage prior to resetting the safety injection signal, the vital busses will automatically load the vital equipment given below. Verify the equipment has been loaded by observing breaker lights on the control board.
- 2. If the vital busses lose voltage after the safety injection signal has been reset, load or verify loaded the equipment given below onto the vital busses manually. Allow approximately 4 seconds between loading of each piece of equipment onto a given vital bus. Load or verify that the CFCU are running in Low Speed.
VITAL BUS F VITAL BUS G VITAL BUS H q U-1(D/G1-3) U-1 (D/G No. 2) U-1 (D/G No. 1) Q U-2 (D/G 1-3) U-2 (D/G No. 1) U-2 (D/G No. 2) MCC F MCC G MCC H CCPp Nc. 1 RHR Pp No. 1 SI Pp No. 1 CFCU No. 3 51 Pp No. 2 CFCU No. 2 CFCU No. 5 RHR Pp No. 2 CFCU No. 1 CCW Pp No. 2 CFCU No. 4 CCW Pp No. 1 ASW Pp No. 2 CCW Pp No. 3 ASW Pp No. 1 CC Pp No. 2 AFW Pp No. 2 AFW Pp No. 3
- 3. Load the containment spray Pumps only if they were running prior to the blackout.
VITAL BUS G VITAL BUS H Cont Spray Pp No. 1 Cont Spray Pp No. 2 (3 V DC0436 25VIV l i
NUMBER EP E-1.2 1 AND 2 REVISION 0 l DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 26 0F 28 POST LOCA C00LDOWN AND DEPRESSURIZATION TITa l APPENDIX B RESTART OF REACTOR COOLANT PUMP
- 1. Start oil lift pump, run for 2 minutes.
- 2. Verify CCW available to thermal barrier, oil coolers, seal water HX.
- 3. Verify seal dp greater than 215 psid, depressurize VCT as necessary.
4 Verify seal injection flow 8 (6 to 12) gpm.
- 5. Verify seal leak off flow within limits shown on graph.
- 6. Ensure closed 455A and B, normal PZR spray valves (auto optional).
ALL0hABLE RCP #1 SEAL LEAK RATES 5
' I
, [
)
i i i I i i l SHUTDOWN RCP WITHIN
' i i
; ONE HALF HOUR 3
b , SAFE OPERATING REGION "2 : i l I
! ! j REGION ,
REGION g I f g 2 : i
' 00 NOT START RCP O
200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400
~
RCP 81 SFAL DIFFERENTIAL PRE 55L1C P5ID REGION 1 NO PHASE.A SIGNAL, dp=RC5 press -VCT press PHASE-A PRESENT, dp=RC5 press -150psig DC0436 26VIV
NUMBER EP E-1.2 1 AND 2 OIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/12/85 i PAGE 27 0F 28 7,u POST LOCA C00LDOWN AND DEPRESSURIZATION APPENDIX C 2600 .. . -. . . . _ . 51__.;a4_:'21:___jr: Q _. .- _ _ _
- c -
_ . _ .= E__.:_:_-. :r:[ c: ._ - .v
"*_'=
"f b _
~ ~ ~ ~.. l ,
2" ~
"- ~ ' -
2400 I"'[ni.!-=iS5E.l.'= :=E._: 5 _d : L. - MS/c.l:/ . .
~
2200 r :=q==.=q ---: . . . ..1=..=--= =:= : .-. r -: ___4- , ..____ =.__=.._.. . . _ _ . __ _ . .___
. _ . . ... .__...__...- _. . _ _ . . e. _ . ...... .
. . _ . . _ _ .=~ := g _g=_ = . =
2000 _==u.__.---~'=.=-._.:==~- -::: .-- : - " ,.
-- * - - - "--' '--~ - -
I. ---- x - 2:5 5 - S="i:Edri+5t=--51=i =E.~,l:-$-i=-E/5/:d"~ : -
= -!_; : r.j= - != 3.---l : :=--f uf:i= :l =c.q . if _[ j l=--
g - + = ) _:#-E - ui-L =- & .i :=: Y - Q :i -
- ...--. .. . j 1. 'p'~".c- [ .. .. .i m -
d~~"".'. ~~ ; -- 9 w E y M 1600 , " ~ ~-' ~,..~ "
. . .= _ _ ! __2 . . _ _ h J __ J.i_.
~ x . - *. _=_c-i: . ~ . =1-
[ .. _
' ' ' ^ ~ ~ F"
. . _ _ _ . . .: . : 1_. .
=ff . . . . . {
* * "--' ' ~ ~ ~ ~ -
- - - =l 5: ' - _.j :2 1400 m
g
--.4.-- = :a ; ;--
2: . f c,, . W 1200
#~ '" ~
b * ' #" "
'--" " ~ ~
E ~
~-~l'~
~
SATURATION CURVE T SATURATION E .
. . _. . . A CORRECTED FOR i. --j- -- CURVE
---~ " "'= =2 ='--1=' 'I '
8 1000 INSTRUMENT ERROR - g ._ . I :i: .! EUH . tmr.lil - i > E -E: :b =- Z i _
. _ ._ r t . g~~-~ p~--
m
- - - -]~ ~ 4 ~ ~
- t; ;.-.u
"";'- j =_: :.:~*p' 800
= t ur =_ j == =
=_c = = . _ . . _ _ _ .____; == : ._ m _ .. . _;.__ w ._== :.1 :--
4__
-- _ _ % __.__ . 3 .
j_._ 600 t - ,- = n .r r - - - -' -
. ------i --- iFt 73 Br 7"
_ _. :- . a._.i = r =, ..: =2= ==
.7_._.__ ;
. == =-1 ::-- - n
.___.___.---..r== =.cr-:= =. -t---tr
-- -* =
- -- = r - - + - - - , - - :~- f=r = =4 =- -
400 . _ , __._4._.. f_ _, l ._ . . . _.1- t._._ Y=x u'"- El -r:f=== * - - - - - - -__: . i: - PRESSURE ERROR + 65 i 200 - - - - -
=_\_
. .m..:; . - -
. :_. t . .
._.=.1, TEMPERATURE ERROR
- - r- ,
I 24 ...,_'. F :--- ' i _ f; l ' 1-di ;- . 1 1- l {- m 200 300 400 500 600 700 l ..A-> CORE EXIT T/C TEMPERATURE (*F) DC0436 27VIV
NUMBER EP E-1.2 . 1 AND 2 l DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/12/85 PAGE 28 0F 28 POST LOCA C00LDOWN AND DEPRESSURIZATION Tita APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Designate this event a Notification of Unusual Event.
- b. If a steam line break is accompanied with a known primary to secondary leakage >10 gpm as indicated by high radiation alanns on the air ejector, steam generator blowdown, sample or by an increase in steam generator water level in an unexpected manner, designate this event as an Alert,
- c. If the primary to secondary leakage is estimated at >50 gpm with fuel damage evident from a gross failed fuel monitor alarm or primary sample, designate this event as a Site Area Emergency.
- d. SI with high or increasing levels of containment pressure, area radiation or recirculation sump level. Designate this event a Site Area Emergency.
- e. In the event inadequate core cooling is verified per Critical Safety Function Status or the verification of the ESF Functioning and Ef fectiveness during LOCA, Appendix H, (EP E-1-1), indicates ESF failure, reclassify this event as a General Emergency.
- 2. Notify plant staff and response organizations required for this classification by implementing Procedures EP G-2 " Establishment of the On-Site Emergency Organization" and EP G-3 " Notification of Off-Site Organizations" in accordance with EP G-1 " Accident Classification and Emergency Plan Activation."
O DC0436 28VIV
FOLD 0VT FOR E-1.2 ADMINISTRATIVE FUNCTION 5 l
- 1. Notify STA (!!onitor SPDS and Critical Safety Function Status Trees)
- 2. Refer to Appendix Z SI REINITIATION CRITERIA l Manually start ECCS pumps, if EITHER condition listed below occurs:
e RCS subcooling - LESS THAN 20*F. e PRZ 1evel - CANNOT BE MAINTAINED GREATER THAN 4% [20%) AFW SUPPLY SWITCHOVER CRITERION l Switch to alternate AFW water supply when CST level decreases to less than 10%. (Refer to E-2.1, ALTERNATE AFW SUPPLIES CHARGING PUMP MINIFLOW ALIGNMENT CRITERION l Ensure Charging Pump Miniflow Valves 8105 and 8106 OPEN if RCS Pressure is GREATER THAN 2000 PSIG. E-3 TRANSITION CRITERIA l Go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 2, if any SG level increases in an uncontrolled manner or any SG has abnormal radiation. COLD LEG RECIRCULATION SWITCH 0VER CRITERION l Go to E-1.3, TRANSFER TO COLD LEG RECIRCULATION, if RWST level decreases to less than 331. SEcotOARy I t.TEGR I T ) CRITERIA l Go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1, if any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, unless needed for cooldown. ADVERSE CONTAINMENT CRITERIA l e Containment pressure greater than 3 psig e Containment radiation greater than 105 R/M dose rate o Containment radiation greater than 106 R dose , CNMT SPRAY INITIATION CRITERIA l Initiate CNMT spray when CNMT pressure is greater than 22 psig. DC0436 29VIII
i NUMBER EP E-1.3 FGW3 Pacific Gas and Electric Company REVISION 0 I DEPARTMENT OF NUCLEAR PLANT OPERATIONS I I PAGE 1 0F 11 DIABLO CANYOf4 POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE ~ TRANSFER TO COLD LEG RECIRCULATION TITLE IMPORTANT APPROVED 7e d 39546 To PLANTMANAGEp) DATE SAFETY SCOPE This procedure provides the necessary instructions for transferring the safety injection system and containment spray system to the recirculation mode. This procedure and changes thereto requires PSRC review. SYMPTOMS OR ENTRY CONDITI0t.S This procedure is entered from the following procedures when RWST O level reaches 33S:
- 1. E-1, LOSS OF REACT 0P OR SECONDARY COOLANT, Step 16 and foldout.
- 2. E-1,1, SI TERMINATION, FOLD 0VT.
- 3. E-1.2, POST LOCA C00LDOWN AND DEPRESSURIZATION, Step 1 CAUTI0tl and FOLD 0UT.
4 E-3, STEAM GENERATOR TUBE RUFTURE, FOLCOUT.
- 5. ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS, Step 8 and FOLDOUT.
- 6. ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED REC 0VERY DESIRED, Step 1 CAUTION and FOLD 0VT.
- 7. ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT - SATURATED RECOVERY DESIRED, Step 1 CAUTION and FOLD 0UT.
- 8. FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, Step 1 CAUTION.
- 9. FR-C.2, RESPONSE TO DEGRADED CORE COOLING, Step 1 CAUTION.
O i DC0436 IVIV
NUMBER EP E-1.3 l 1 AND 2 REVISION 0 CIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 ! 7,7 g TRANSFER TO COLO LEG RECIRCULATION PAGE 2 0F 11 hl
- 10. FR-C.3, RESPONSE TO SATURATED CORE CONDITIONS, Step 1 CAUTION.
- 11. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 18 CAUTION.
O O OC0436 2Viv
1 AND 2 NUMBER EP E-1.3 OIA8LO CANYON POWER PLANT UNIT Nots) REVISION 0 O DATE 3/11/85 h TRANSFER TO COLD LEG RECIRCULATION PAGE 3 0F 11 7, ACTION /DPECTED RESPONSE RESPONSE NOT OBTAINCD CAUTION: e Steps 1 through 6 should be performed without delay. e SI recirculation flow to the RCS must be maintained at all times. e If offsite power is lost after SI reset, manual action will be required to restart RiiR, SI and Containment Spray pumps. Refer to Appendix A for guidance if this condition occurs. If in Recirculation Mode, charging pumps should be held in the 0FF/ RESET position until an RHR pump is in service. e IF at least one flow path from the sump to the RCS can NOT be established or maintained, THEN go to ECA-1.1, LOSS OF IRTRGENCY COOLANT RECIRCULATION. Nr)TE: Foldcut page for should be open. A C1 ,
- 1. PESET SI (VE1)
- 2. RESET Both Trains of Containment Isclation Fnase A and Pnase B (VS1)
- 3. SHUTDOWN Ary Runninn RPR Pumos and the PU Charging Pump (VBl/VB2)
O b ! OC0436 3VIV l
NUMBER 'P E-1 3 1 AND 2 OIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/11/85 TRANSFER TO COLD LEG RECIRCULATION Tir a ACTION / EXPECTED RESPONSE RESRJNSE NOT OBTAINED CAlJTION: e Any pumps taking suction from the RWST should be stooped on RWST Lo-Lo level alarm (PK03-1, 4%). ECCS pumps should be restarted after suction supply is restored. e SI pumps should be stopped if RCS pressure is greater than 1650 psig.
- 4. ISOLATE RHR Train Discharge Headers:
(VBl)
- a. Close 8716A & B, RHR pp a. E 8716A B 8716B does NOT close, crosstie vivs THEN ensure 8703 is closed.
RHR to hot legs 1 & 2. t0TE: 8700A, RWST to RHR pp 1 suction should be closed at this time to allcw for long stroke tire.
- 5. PLACE RHR Train 8 In Service To SI Pumo Suction:
- a. Close 6700 8, RWST to RHR pump a. -
IF 87008 will NOT close suction viv from RWST (V81) electrically, THEN perform the following:
- 1) Close 8700A.
- 2) Close series contactor and close 8974A and 8, SI pps rectre viv. (VB2)
- 3) Go to Step 6 AND WHEN 87008 closed.
TR M perform step Sb,c,d, and e. me THIS STEP CONTINUED ON NEXT PAGE DC0436 4VIV
NUMBER EP E-1.3 otAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/11/85 9 TITLE. TRANSFER TO COLD LEG RECIRCULATION PAGE 5 0F 11 ACTION /EKRCTED RESPONSE RESPONSE TOT OBTAlfED
- b. Close series contactor and open b. IF
~~'
8982B can NOT be 89825, RHR pp2 suct from contmt opened either remotely recirc sunp (VB2/VB1) or locally, (VB1) THEN Close series contactor and close 8974A and B. SI pps recirc stop vlvs, and proceed to Step 6. (VB2)
- c. Open FCV-364, CCW out viv fcom RHR c. Locally open FCV.364 (VB1) hu No. 2 (VB1)
- d. Start RHR pp2 and check for d. IF
~~~
No. 2 RHR pump can NOT ficw to the reector vessel (VE1) be started remotely, THEN close 8974A & B, 51 pps recirc stop 7-~ i vlvs, and proceed to \/ Step 6. (VB2)
- e. Close series contactor and close e. Locally close at least one 8974A & S, SI pps recirc stop of these vivs.
vivs (VB2) NOTE: The Si pp flow and dis;hargc pressure increases are expected onl/ if an RHR pp and an SI pp are in service,
- f. Check for increased SI pp flow f. IF
~~~
8804B can NOT be and pressure while performing opened, either remotely or locally,
- 1) Open 8804B RHR HX No. 2 THEN proceed to Step 6.
disch,157 to SI pps Suction ( YB ', ,' LJ DC0436 SV!V
N'JMBER EP E-1.3 1 AND 2 DIABLO CANYON POWER PLANT UNT NO(S) REVISION 0 , l DATE 3/11/85 TRANSFER TO COLD LEG RECIRCULATION Tir a ACTION / EXPECTED RESPONSE RESFONSE NOT OBTAINED g: The charging pp (BIT) flow and discharge pressure increase are expected only if an RHR pp and a charging pp are in service.
- 6. CROSS-TIE Charging Pump Suction To SI Pump Suction:
- a. Check for increased charging pump a. Locally open at least one of (BIT) flow and pressure while these valves.
performing
- 1) Open 8807A & B, RHR hx No. 1 to SI pp suction vivs (V81)
- b. Throttle HCV-637, RHR hx No. 2 outlet flow control, to establish RHR discharge pressure approximately 20 psig greater than cnet pressure (to provide adequate suction to charging and SI pps) while maintaining RHD pp No. 2 :..otor current less than 57 amps (V31)
O DC0436 6VIV
NUMBER EP E-1.3 1 AND 2 OtA8LO CANYON POWER PLAT 4T UNIT NO(S) REVISION 0 r DATE 3/11/85 V) PAGE 7 0F 11 TRANSFER TO COLD LEG RECIRCULATION TITLE. ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. PLACE RHR Train A In Service To Charging Pump Suction: (VBl/VB2)
- a. Close 8700A, RHR pp No. 1 a. Locally close 8700A.
suction viv from RWST
- b. Close series contactor and open b. -
IF at least one flow path 8962A, RHR pp No. I suct from from the sump to the
- cont recirc sump RCS can NOT be established or maintained, THEN go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION.
- c. Open FCV-365, CCW out viv from RHR c. Locally open FCV-365.
O hx No. 1
- d. Start RHR pp No. I and check for d. IF RHR pp 1 can NOT be flow to the reactor vessel started, either remotely or at breaker, THEN go Step 8 and read note.
I
- e. Open 8804A, RHR hx No. I to chrg pp suction
- 1) Check for charging pump (BIT) flow and SI pp flow if pps are in operation
- 2) Throttle HCV-638 to ensure adequate suction to charging and SI pps (approx. 20 psig above containment pressure) while maintaining RHR pp 1 motor current less than 57 amps O
DC0436 7VIV
OlA8LO CANYON POWER PLANT UNIT NO(S) 1 ANJ 2 S ON DATE 3/11/85 PAGE 8 0F 11 7,7 g TRANSFER TO COLD LEG RECIRCULATION 9 ACTION /EXRCTED RESPONSE RES M SE NOT OBTAINED OTE: If Containment Spray was actuated it must remain in service for a minimum of 2 hours after initiation of Cold Leg Recirculation. Consult Plant staff in TSC.
- 8. ALIGN Containment Spray From RHR System If Required:
- a. Containment Spray-ACTUATED a. Go to Step 9.
(PK01-18)
- OR -
Containment Pressure-GREATER THAN 22 PSIG (VB1)
- b. Check RWST level - LESS THAN 4% b. Continue with Step 9 and (V82) WHEN RWST is less than 4%.
TIIET do Step 8.c,d,e,f, and 9
- c. Reset containment spray (VB1)
- d. Stop both centainment spray pps (VE1)
- e. Close 9001A & B, containment spray pump discharge Vivs (VB1)
- f. Verify both RhR trains - IN f. IF two RHR trains are SERVICE (VB1/2) NOT in service, THEN throttle to 50% HCV-637 or HCV-638, RHR hx E tlet flow control viv, for the operable RHR pp AND open 90U3X or 9003B, RHR pp to spray ring vivs, for the operable RHR pp. Throttle HCV-637 or HCV-638 to maintain THR pp motor
. current less than 57 amps. Continue with Step 9.
e THIS STEP CONTikUED ON NEXT PAGE i DCC436 8V!V i I l
l NUMBER EP E-1,3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 j DATE 3/11/85 p) i t . PAGE 9 0F 11
%J Tite TRANSFER TO COLD LEG RECIRCULATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- g. Close series contactor and close 8809A, RHP. to cold legs 1 & 2
- g. E 8809A does NOT close, (VB1) -M-AND 9003A does NOT open, THEN verify 8809A open.
Open 9003A, RHR pp 1 to spray rings 1 & 3 (VB1) Close 88098, RHR to cold legs 3 & 4 AND open 90038, RHR pp 2 to spray rings 2&4
- 9. Close RWST Suction Valves: (VB2)
- a. Locally close the breakers for the following valves:
e 8976, SI pp suction from RWST UNIT 1 UNIT 2 52-1H-20 52-2F-20 e 52-F-31 for 898C, RHR pp suction fren RWST I UNIT 1 UNIT 2 52-lF-31 52-2F-31
- b. Close the following valves:
e 8805 A & B, charg pp suct from RWST e 8976, SI pp suction from RWST e 8980, RHR pp suction from RWST
- 10. RETURN to Procedure and Step In Effect
- END -
DC0436 9Viv
1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) RE S ON DATE 3/11/85 7 TRANSFER TO COLD LEG RECIRCULATION i APPENDIX A BLACK 0UT EMERGENCY LOADING OF VITAL BUSSES
- 1. If the vital busses lose voltage prior to resetting the safety injection signal, the vital busses will automatically load the vital equipment given below. Verify the equipment has been loaded by observing breaker lights on the control board.
- 2. If the vital busses lose voltage after the safety injection signal has been reset, load or verify loaded the equipment given below onto the vital busses manually. Allow approximately 4 seconds between loading of each piece of equipment onto a given vital bus. Load or verify that the CFCU are running in Lcw Soeed.
VITAL BUS F VITAL BUS G VITAL BUS H U-1 D/G 1-3 !!-1 (D/G No. 2) U-l (D/G No. 1 U-2 D/G 1-3 U-2 (D/G No. 1) U-2 (D/G No. 2 MCC F MCC G MCC H O CC Pp No. 1 RHR Pp No. 1 SI Pp No. 1 CFCU No. 3 SI Pp No. 2 CFCU No. 2 CFCU No. 5 RHR Pp No. 2 CFCU No. 1 CCW Pp No. 2 CFCU No. 4 CCW Pp No. 1 ASW Pp No. 2 CCW Pp No. 3 ASW Pp No. 1 CC Pp No. 2 AFW Pp No. 2 AFW Pp No. 2
- 3. Load the Containment Spray Pumps only if they were running prior to the blackout.
VITAL BUS G VITAL BUS H Cont Spray Pp'No. 1 Cont Spray Pp No. 2 1 l l DC0436 10VIV
DIABLO CANYON POWER PLANT UNIT NO(S) I AND 2 S ON DATE 3/11/85 I I PAGE 11 0F 11 7,7 g TRANSFER TO COLD LEG RECIRCULATION APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. Use of this procedure does not affect the emergency classification.
l I l I l l DC0436 11VIV
O FOLD 0VT FOR E-1.3 l \ ) ADMINISTRATIVE FUNCTIONS I Monitor SPDS and Critical Safety Function Status Trees CHARGING PUMP MINIFLOW ALIGNMENT CRITERION l Ensure Charging Pump Miniflow Valves 8105 and 8106 OPEN if RCS Pressure is GREATER THAN 2000 PSIG. AFW SUPPLY SWITCHOVER CRITERION l Switch to alternate AFW water supply if CST level decreases to LESS THAN 101. Refer to E-2.1, Alternate Auxiliary Feedwater Supplies. l RHR PUMP SUCTION CRITERION / LOSS OF EMERGENCY, COOLANT RECIRCULATION I Refer to EP ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, if at least one flow path from the containment recirculation sump cannot be established or maintained. E-3 TRAh51 TION CRITERIA l Go to E-3, STEAI: GENERATOR TUBE RUPTURE, Step 2, if any SG level increases in an uncontrolled manner or any SG has abnormal radiation. SEC0hDARY It.TEGRITY CRITERIA l Go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1, if any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, unless needed for RCS cooldown. ADVERSE C0f.iAINMENT CRITERIA l Containment pressure - GREATER THAN 3 PSIG
- OR -
Containment Radiation Dose Rate 105R/hr
- OR -
Containment Radiation Dose Rate 106R O I DC0412 12VII -
l l
\
NUMBER EP E-1.4
~ c.
._ ~. w W 3 Pacific Gas and Electric Company REVISION 0 1 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 3/11/85 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 9 l
~
l EMERGENCY PROCEDURE TITLE ' TRANSFER TO H0T LEG RECIRCULATION IMPORTANT APPROVED. iC C' 7 Yd646 TO l PLANTMANAGERg) DATE SAFETV l SCCPE l This procedure provides the necessary instructions for transferring the safety injection system to hot leg recirculation. This procedure and changes thereto requires PSRC review. SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from E-1, LOSS OF REACTOR OR SECONDARY C00LAf.T. Step 18, when the specified time interval has elapsed. l l DC0412 IX
- i
N DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 3/11/85 1 TITLE TRANSFER TO HOT LEG RECIRCULATION s ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: If offsite power is lost after SI is reset, manual action will be required to restart some safeguards equipment. If in Recirculation Mode, charging pumps should be held in the OFF/ RESET position until an RHR pump is in service. Refer to Appendix A for guidance if this condition occurs. NOTE: It is important during this phase to ensure that two separate and redundant trains of recirculation outside containment are established unless an inoperable 4160 volt vital bus prevents total separation.
- 1. At 19 Hours After Event Initiation Prepare For hot Leg Recirculation:
- a. Check the following control a. Place the valve control switches in their required switches in the required position: position.
e 8802A - CLOSED, SI to hot leg 1 & 2 e 8835 - OPEN, SI purrp to cold leg e 8703 - CLOSED, PFR to hot leg 1 & 2 e 88028 - CLOSED, SI to hot leg 3 & 4 ---------------.
- b. Close the folicwing 480 volt breakers:
UNIT 1 UNIT 2 52-1F-48, 8802A 52-2F-48, 8802A 52-1G-24, 8835 52-2G-24, 8835 52-1G-56, 8703 52-2G-56, 8503 52-1H-26, 8802B 52-2H-26, 8802B O DC0412 2X
NUMBER EP E-1.4 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 HEVISION 0
/' DATE 3/11/85 PAGE 3 0F 9 TITLE. TRANSFER TO HOT LEG RECIRCULATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. At 19.5 Hours ALIGN SI Pump 1 For Hot Leg Recirculation: (VB1)
- a. Verify both RHR pps are in a. Manually start any shutdown operation RHR Pump.
g RHR pp 1 is NOT operabl e, THEN close 8804A and proceed to Step le. E RHR pp 2 is NOT operable. THEN proceed with Step lb.
- b. Verify open 8804A, RHR Hx No. I to chrg pp suction Viv
- c. Close series contactor and close 8809A, RHR to cold legs 1 & 2
- d. Close 9003A, RHR pp 1 to spray rings 1 & 3
- e. Stop or verify stopped 51 pp ho. I
- f. Close 8821A, S: pp crosstie viv
- g. Open 8802A, SI to hot legs 1 & 2
- h. Perform the-following IF SI pp 1 is NOT operable, TIIEN go to Step IJ.
- 1) Start 51 pp No. 1 ----------------
- 2) Adjust HCV-638 RHR Hx 1 outlet flow control viv to ensure adequate suction to SI pps and to maintain RHR pp 1 motor current less than 57 amps
- i. Verify SI pp No. I flow on FI-918 i. Ensure flow path.
THIS STEP CONTINUED ON NEXT PAGE l DC0412 3X
DLABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/11/85 PAGE 4 0F 9 g TITLE TRANSFER TO HOT LEG RECIRCULATION ACTION / EXPECTED RESPWSE RESPONSE NOT OBTAINED
- j. Verify BOTH RHR pps are in J. E either RHR pp 1 or RHR operation pp 2 is NOT in operation, THEN go to Step 2.
- k. Close 8923A, SI pp No. 1 RWST suction
- 3. ALIGN SI Pump 2 for Hot leg Recirculation: (VB1)
- a. Verify RHR Pump No. 2 is in a. E RHR pp No. 2 is NOT operable, operation THEN close 8804B and proceed to step 2.e.
- b. Verify open 8804B, RHR Hx 2 to SI pp suction viv
- c. Close series contactor and close 88098, RHR to cold legs 3 & 4
- d. Verify closed 9003B, RHR 2 to spray rings 2 & 4
- e. Stop or verify stopped SI pp No.
2
- f. Close 8821B, SI pp cross tie viv
- g. Close 8835, SI pp cold legs viv
- h. Open 8802B, SI to hot legs 3 & 4 THIS STEP CONTINUED ON NEXT PAGE O
DCC412 4X
NUMBER EP E-1.4 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/11/85 q 5 0F 9 PAGE TITLE TRANSFER TO HOT LEG RECIRCULATION ACTION / EXPECTED RESPONSE REsPONsENOTOBTAINED
- 1. Perform the following 1. IF SI pp No. 2 is NOT operable,
- 1) Start SI pp No. 2 THEN go to Step 2.k.
- 2) Adjust HCV 637 RHR Hx No. 2 outlet flow control viv to ensure adequate suction to SI pps and to maintain motor current less than 57 amps
- j. Verify SI pp No. 2 flow on FI-922 j. Ensure flow path
- k. Verify BOTH RHR pps are in k. I_F_ either RHR pp 1 or RHR operation pp No. 2 is NOT in operation,
- 1. Cicse 8923B, SI pp No. 2 RWST suction 4 VERIFY RhR Pumo No. 2 Is In Operatier. IF RHR pp No. 2 is NOT (VB1) 5erable, THEN 90 to step 6.
- 5. ALIGN RHR Pump No. 2 For Hot leg Recirculation: (vbi)
- a. Open 87165, RHR pp No. 2 cross tie
- b. Open 8703, RHR to hot legs 1 & 2
- c. Adjust HCV-637 RHR Hx No. 2 outlet flow control vlv to ensure adequate suction to SI pp(s) and to maintain motor current less than 57 amps
- d. Proceed to Step 7. OBSERVE NOTE PRIOR TO STEP 7.
e l DC0412 5X
NUMBER EP E-1.4 OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/11/85 PAGE 6 0F 9 TITLE- TRANSFER TO HOT LEG RECIRCULATION ACTION /EXPEuw RESPONSE RESPONSE f0T OBTAINED
- 6. ALIGN RHR Pump No. I for Hot Leg Recirculation: (VB1)
- a. Open 8716A, RHR pp No. 1 cross tie
- b. Open 8703, RPR to hot legs 1 & 2
- c. Adjust HC1-638, RHR Hs 1 outlet flow control viv to ensure adequate suction to SI pp(s) and to maintain RHR pp No. 1 motor current less than 57 amps NOTE: Do not perforn steps 7 or 8 if there is an inoperable CCW or ASW pump.
- 7. ESTABLISH ASW Traia Separation:
- a. Place any idle purp in MANUAL t- :1 v,2 FCV-495 & 496, aux salt wtr no r.rt.!!-tie vivs (VS1)
- c. Oper. FCV-602 or 603, aux salt wtr op to idle CCW Hx viv (VB1)
- d. Start idle ASW pp
- e. Verify ASW pp motor current is e. Throttle (ASW 65 or ASW 66) less than 5a arps CCW Hx auxiliary saltwater outlet viv for the pump with high amps. (at Hx)
O DC0412 6X , l
NUMBER EP E-1.4
%BLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/11/85
{' s PAGE 7 0F 9
'LE. TRANSFER TO HOT LEG RECIRCULATION ACTION /EXPECTEDRESPONsE REsPONsENOTOBTAINR Establish CCW Train Separation
- a. Open FCV-430 or 431, the idle CCW Hx outlet stop vlv
- b. Ensure CCW pp No. 1 AND either CCW pp No. 2 OR,CCW pp No. 3 in operation
- c. Open FCV-335, CCW header C iso viv
- c. Locally close CCW-1-4, the suction header cross-tie v1v between CCi: headers B and C
- e. Lccally close CCW-1-18, CCW pp 1 discharge viv to CCW header A
- f. Locally close CCW-1-16, CCW pp 2 discharge viv tc CCW header B
- g. Locally close CCW-1-17, CCW pp 3 discharge viv to CCW header B
- h. Locally close CCW-1-24, CCW header B to C iso viv EVALUATE Lona Term plant Status
- a. Consult plant engineering staff in the Technical Support Center
- END -
l
/~N l O i
I DC0412 7X
NUMBER EP E-1.4 OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 I"TE 3/11/85 7,7tg. TRANSFER TO HOT LEG RECIRCULATION APPENDIX A BLACK 0UT EMERGENCY LOADING OF VITAL BUSSES
- 1. If the vital busses lose voltage prior to resetting the safety injection signal, the vital busses will automatically load the vital equipment given below. Verify the equipment has been loaded by observing breaker lights on the control board.
- 2. If the vital busses lose voltage after tFe safety injection signal has been reset, load or verify loaded the equipment given below onto the vital busses manually. Allow approximately 4 seconds between loading of each piece of equipment onto a given vital bus. Load or verify that the CFCU are running in Low Speed. Load RHR Pumps before loading Safety Injaction Fumps.
VITAL BUS F VITAL BUS G VITAL BUS H U-l (D/G l-3) U-l (D/G No. 2) U-1 (0/G No. 1) U-2 (0/G 1-3) U-2 (0/G No. 1) U-2 (D/G No. 2) MCC F MCC G MCC H CC Pp No. 1 RHR Pp No. 1 SI Pp No. 1 CFCU No. 3 SI Pp No. 2 CFCU No. 2 CFCU No. 5 RHR Pp No. 2 CFCU fio. 1 CCW Pp No. 2 CFCU fio. 4 CCW Pp No. 1 ASW Pp No. 2 CCW Pp No. 3 ASW Pp f;o. 1 CC Pp No. 2 AFW Pp No. 2 AFW Pp No. 3 t O i DC04I2 8X l l l
N DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 3/11/85 O' PAGE 9 0F 9 TITLE TRANSFER TO HOT LEG RECIRCULATION APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS l
- 1. Use of this procedure does not affect the emergency classification.
O l O DC0412 9X l l i l
NUMBER EP E-2 ew,m W3 Pacific Gas and Electric Company REVISION 0 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 3/11/85 4 g PAGE 1 0F 6 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE TITLE. FAULTED STEAM GENERATOR ISOLATION IMPOR I ANT APPROVED wr& 3'd546 TO l PLANIMENAGER f.) DATE SAFETY PURPOSE This procedure provides instructions to identify and isolate faulted steam generator (s). This procedure and changes thereto requires PSRC review. SYMPTOMS OR ENTRY CONDITIONS
- 1. E-0, REACTOR TRIP OR SAFETY INJECTION, Step 20, with the following symptoms:
- a. Any SG pressure decreasing in an uncontrolled manner.
- b. Any SG ccmpletely depressurized.
- 2. E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 2 and FOLD 00T; E-1.1, SI TERMINATION, FCLDOUT; ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED REC 0VERY DESIRED, FOLDOUT; anc ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, FOLD 0VT, with the following symptoms:
- a. Any SG pressure decreasing in an uncontrolled manner and has j not been isolated. !
- b. Any SG completely depressurized and has not been isolated.
o V i DC0413 IIV l
N otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 3/11/85 7:rts. FAULTED STEAM GENERATOR ISOLATION
- 3. E-1.2, POST LOCA C00LDOWN AND DEPRESSURIZATION, FOLD 0VT; E-1.3, TRANSFER TO COLD LEG RECIRCULATION, FOLD 0VT; E-3, STEAM GENERATOR TUBE RUPTURE, Step 6 and FOLD 0VT; ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SU8C00 LED REC 0VERY DESIRED, Step 8; and ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT - SATURATED RECOVERY DESIRED, Step 3 and FOLDOUT, with the following symptoms:
- a. Any SG pressure decreasing in an uncontrolled manner, has not been isolated, and is not needed for RCS cooldown.
- b. Any SG completely depressurized, has not been isolated, and is not needed for RCS cooldown.
4 ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS, Step 1 CAUTION and FOLDOUT, when any SG pressure increases during the procedure. O O DC0413 2IV
I DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON O DATE 3/11/85 V PAGE 3 0F 6 TITLE. FAULTED STEAM GENERATOR ISOLATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAljTION: e At least one SG must be maintained available for RCS cooldown, e Any faulted SG or secondary break should remain isolated during subsequent recovery actions unless needed for RCS cooldown. NOTE: e Refer to Appendix Z. e Depressurize the RCS to maintain primary to secondary pressure difference less than 1600 psi provided RCS subcooling greater than 20"F and PZR level is greater than 4% [20%).
- 1. CHECK MSIV And Bypass Vivs Of Manually Close Valves. (VB3)
Affected SGs - CLOSED (VB3)
- 2. CHECK If Any SG Is Not Faulted:
[3 (v63) V
- a. Check pressures in all SGs - ANY a. IF~~~ all SG pressures STAELE OR INCREASING decreasing in an uncontrolled manner, THEN 90 to ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS.
- 3. IDENTIFY Faulted SG(s): (VB3)
- a. Check pressures in all SGs ,- a. Search for initiating break:
ANY SG PRESSURE DECREASING IN AN e Main steamlines UNCONTROLLED MANNER e Main feedlines
. OR -
e Other secondary piping ANY SG COMPLETELY DEPRESSURIZED Go to Step 5. O G DC0413 31V ? . _ __ ._ _- ._-- .-.
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON 0 DATE 3/11/85 TITLE FAULTED STEAM GENERATOR ISOLATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. ISOLATE Faulted SG(s): (VB3) Manually close valves e Isolate Main Feedline IF valves can NOT be closed.
TREN dispatch operators to e Isolate AFW flow locally close valves or block valves. e Close steam supply valves to the TD AFW pump from faulted SG e Verify SG 10% steam dumps - CLOSED e Isolate SG Blowdown Valves
- 5. CHECK Condensate Storage Tank Level: Switch to alternate AFW supply
- GREATER TnAN 10a (V63) (Refer to E-2.1 ALTERNATE AUXILIARY FEEDWATER SUPPLIES).
- 6. CHECK Secondary Radiation - NORMAL Go to E-3, STEAM GENERATOR TUBE RUPTURE.
e R-71 thru R-74, Main Steamline Process Monitor - NOT IN ALARM (PK11-18) e R-19, Steam Generator Blowdown Liquid Process Monitor - NOT IN ALARM (PK11-17) e R-15, Condenser Air Ejector Process Monitor - NOT IN ALARM (PK11-21/P250)
- 7. ESTABLISH INSTRUMENT AIR TO CNMT:
(V54) e Try to establish instrument
- a. Open FCV-584 CNMT inst air iso air (refer to OP AP-9).
viv e Avoid excessive cycling of
- b. Verify at least one air valves that have backup air, compressor - IN SERVICE
. e Continue in this procedure.
1 O DC0413 4IV
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON O DATE PAGE 3/11/85 5 0F 6 TITLE FAULTED STEAM GENERATOR ISOLATION ACTION /EXPECTEDRE5PONSE RE5PON5ENOTOBTAINED
- 8. Place to the LOOP OUT position the RCS Loop WR T Input to the subcooledmarhfIlmonitorfor'anySG isolated TE 413 for SG-1 TE 423 for SG-2 TE 433 for SG-3 TE 443 for SG-4
- 9. GO To E-1, LOSS OF REACTOR OR SECONDARY COOLANT O
i
- END -
I l O DC0413 SIV
N DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 3/11/85 TITLE FAULTED STEAM GENERATOR ISOLATION APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Designate this event a Notification of Unusual Event.
- b. If a steam line break is accompanied with a known primary to secondary leakage >10 gpm as indicated by high radiation alarms on the air ejector, steam generator blowdown, sample or by an increase in steam generator water level in an unexpected manner, designate this event as an Alert.
- c. If there is primary to secondary leakage and it is estimated at >50 gpm with fuel damage evident from a gross failed fuel monitor alarm or primary sample, designate this event as a Site Area Emergency.
- 2. Notify plant staff and response organizations required for this classification by implementing Procedures FP G-2
" Establishment of the On-Site Emergency Organization" and EP G-3 " Notification of Off-Site Organizations" in accordance with EP G-1 " Accident Classification and Emergency Plan Activation."
O DC0413 6IV l
~ .m NUMBER EP E-2.1
._. #wL2.3
- Pacific Gas and Electric Company REVISION 0 O DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 3/11/85 I # 9 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2
~
EMERGENCY PROCEDURE TITLE ALTERNATE AUXILIARY FEEDWATER SUPPLIES IMPORTANT APPROVED ? ?. d 3-545 To PLANTMANACf3 I DATE SAFETY PURPOSE This procedure provides the necessary instructions for supplying sources of feedwater to the auxiliary feedwater system. These sources of auxiliary feedwater are listed in preferred order of use. This procedure and changes thereto requires PSRC review. SYMPTOMS OR ENTRY CONDITIONS
, This procedure is referred to whenever low CST level is a concern and \ auxiliary feedwater to the steam generators is required.
1 LC00A9 IV
I DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h DATE PAGE ON 3/11/85 2 0F 9 g TITLE ALTERNATE AUXILIARY FEEDWATER SUPPLIES PROCEDURE A. Auxiliary Feedwater PP Raw Water Supply
- 1. Open FCV-436 for AFW Pp No.1 (VB3)
- 2. Open FCV-437 for AFW Pp No. 2 and No. 3 (VB3)
- 8. Auxiliary Feed Pump Suction Supply from Fire Water Tank If the AFW pumps are being supplied from the raw water reservoir and a seismic event occurs with resultant loss of AFW suction, see figure one in conjunction with the following procedure to supply the AFW pump suction from the fire water tank.
- 1. Close or check closed MU-0-325.
- 2. Close or check closed MU-0-477
- 3. Open or check open FP-0-306 and FP-0-307 (Normally locked closed).
4 Close or check closed MU-0-284 and MU-0-286.
- 5. Close or check closed; UNIT 1 UNIT 2 MU-2-298 MU-1-297
- 6. Notify the control room that the suction for the AFW pumps is ncw available from the fire water tank.
- 7. Open or check open FCV-436 and 437.
- 8. If suction to the AFW pumps was lost vent the AFW pump casings as necessary to remove trapped air.
l l 1 O DC00A9 2V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON e
/ml DATE 3/11/85 V PAGE 3 0F 9 1
TITLE ALTERNATE AUXILIARY FEEDWATER SUPPLIES 1 C. Make up to the Condensate Storage Tank from the Condenser Hotwell. If the conciensate pumps are available, refill the CST from the condenser hotwell via the condensate reject path. (Referto l Drawing 107031 Sheets 5, 6, 7, & 8). This path may not be available if off site power is not available.
- 1. Take manual control of LCV-12 Cond Hotwell Rejection Cont at VB3 and fully open LCV-12.
- 2. Start a condensate pump.
- 3. Monitor increasing CST (VB3) and decreasing hotwell level (VB3).
- 4. Monitor condensate pump amps. If pump cavitation is suspected STOP the condensate pump.
- 5. Use normal AFW pump suction supply.
D. Supply AFW pump suction from the Makeup Water Transfer Tank via the Make Up Water Transfer Pumps. (Refer to Drawing 107031, O Sheets 10 and 11, and Appendix F: Figure Three for Unit 1 or V Appendix F: Figure Four for Unit 2.
- 1. Stop the Make up Water Transfer Pumps
- 2. Open or check open MU-0-696, M.U. Demin Outlet Iso-Valve to X-fer Tank 0-1
- 3. Open or check open MU-0-698, M.U. Demin Outlet Iso-Valve to X-fer PP Suction
- 4. Open or check open MU-0-715 and 0-710, M.U. Wtr X-fer PP Suction Iso Valve from X-fer Tank 0-1.
- 5. Close or check closed MU-0-712, Makeup WTR transfer PP 0-1 Disch Iso-Valve to Transfer TK 0-1, 1-1 Main Condenser Makeup and Rejector line or 2-1 Condensate Storage Tank and MU-0-713 Makaup WTR Transfer PP 0-1 Disch Iso-Valve to 1-1 or 2-1 Condensate Storage Tanks.
- 6. Close or check closed MU-0-709, Makeup WTR transfer PP0-2 Disch Iso-Valve to Transfer TK 0-1, 2-1 Main Condenser j Makeup and Rejector line or 1-1 Condensate Storage Tank and l MU-0-708 Makeup WTR Transfer PP 0-2 Disch Iso-Valve to 1-1 l or 2-1 Condensate Storage Tanks.
! 7. Close or check closed MU-0-714 and MU-0-711, M.U. Water l Transfer pump suctions from U-1 and U-2 CST's. ! 8. Open or check open MU-0-727, Makeup WTR Transfer PP 0-1 l Disch Iso-Valve to RAW WTR RESERVOIR, CCW Surge Tanks or ! Makeup Demineralizers and MU-0-728, Makeup WTR Transfer PP-0-2 Disch Iso-Valve to RAW WTR RESERVOIR, CCW Surge Tanks or Makeup Demin. (3 l b DC00A9 3V
otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 V ON DATE 3/11/85 PAGE 4 0F 9 TITLE ALTERNATE AUXILIARY FEE 0 WATER SUPPLIES
- 9. Open or check open MU-1-743, Makeup WTR Transfer PPS Disch Hde Iso-Valve to RAW WTR RESERV0IR.
- 10. Open or check open MU-0-278, Crosstie valve between 6 inch and 8 inch headers.
- 11. Close or check closed MU-277, 6 inch header isolation.
- 12. Close or check closed MU-0-280, 8 inch header Iso-Valve downstream of domestic water treatment system tap.
- 13. Open or check open MU-0-283, Strainer 97 Inlet Iso-Valve.
14 Open or check open MU-0-284, Strainer 97 Outlet Iso valve.
- 15. Open or check open Iso valve to Aux feedwater pumps suction from 8' header.
ChlT 1 UNIT 2 MU-1-297 MU-2-298
- 16. Notify the control room that the suction for the AFW pumps is now available from the Make Up Water Transfer Tank.
- 17. Open or verify open FCV-436, AUX FW PP No.1 RAW WTR SUPPLY and FCV-437, AUX FW PP No. 2 and No. 3 RAW WTR SUPPLY.
- 16. Start a Makeup Water Transfer pump to supply AFW pump suction.
- 19. If suction to the AFW pumps was lost vent the AFW pump casings es necessary to remove trappec air.
E. Auxiliary Feed Fwp Suction Supply From the Fire Water Tank using the Portable Diesel Powered Firewater Pump.
- 1. Lineup the Firewater tank to tne AFW pump suction as per section 8 of this procedure.
- 2. Refer to Operating Procedure OP K-2A to fill the fire water tank using the firewater yard loop from the main condenser hotwell.
- 3. If the condenser hotwell is not available refer to OP K-2A to establish a siphon from the raw water reservoir to the makeup water header to the AFW pump suction.
NOTE: Upon depletion of the raw water reservoir refill the raw water reservoir from Diablo Creek using the portable diesel driven fire-water pump (Refer to Drawing 107031, Sheet 26).
- 4. Upon exhaustion of all other water sources refer to OP K-2A to establish makeup to the firewater tank from the Auxiliary SaTtwater System.
O DC00A9 4V
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OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 [fSf0N DATE 3/11/85 O TITLE: ALTERNATE AUXILIARY FEEDWATER SUPPLIES PAGE 9 0F 9 l l l
)
APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. Use of this procedure does not affect the emergency l classification.
O O DC00A9 9V
NUMBER EP E-3
%m%G
#J Pacific Gas and Electric Company REVISION 0 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 3/8/85 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AhD 2 PAGE 1 0F 47
~
EMERGENCY PROCEDURE TITLE g STEAM GENERATOR TUBE RUPTURE IMPORTANT APPROVED. ?f 7 @ TO PLANT MANAGER S/ DATE SAFETY SCOPE This procedure covers the operating steps to be taken in the event of a steam generator tube rupture. It is assumed that reactor trip and safety injection actuations have occurred. The operator should have already perfomed Emergency Operating Procedure E-0. This procedure and changes thereto requires PSRC review. SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from the followirg procedures:
- 1. EP E-0, REACTOR TRIP OR SAFETY INJECTION, Step 21, when steamline radiation, condenser air ejector radiation, or SG blowdown radiation is abnormal.
- 2. E-0, REACTOR TRIP OR SAFETY INJECTION, Step 27; E-1, LOS5 OF REACTOR OR SECONDARY COOLANT, Step 4; E-2, FAULTED STEAM GENERATOR ISOLATION, Step 6; and FR-H.3, RESPONSE TO STEAM GENERATOR HIGH LEVEL, Step 7, when secondary radiation is abnormal.
- 3. E-0, REACTOR TRIP OR SAFETY INJECTION, Step 26; and E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 3, when NR level in any SG continues to increase in an uncontrolled manner.
- 4. E-1.2, POST LOCA C00LD0hN AND DEPRESSURIZATION, Step 6; ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED REC 0VERY DESIRED, Step 9; ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT - SATURATED RECOVERY DESIRED, Step 4; and ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE C0hTROL, Step 6, when NR level in any intact SG continues to increase in an uncontrolled manner. ;
v l l DC0407 IIV l
DiAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 3/8/85 Tirts. STEAM GENERATOR TUBE RUPTURE l
- 5. E-1, LOSS OF REACTOR OR SECONDARY COOLANT, FOLD 0UT; E-1.1, SI TERMINATION, FOLDOUT; E-1.2, POST LOCA C00LDOWN AND :
DEPRESSURIZATION, FOLD 0VT; and E-1.3, TRANSFER TO COLD LEG RECIRCULATION, FOLD 0VT, whenever any SG level increases in an uncontrolled manner or any SG has abnonnal radiation.
- 6. ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Steps 3, 4, and 5, when pressurizer pressure control is restored.
O O DC0407 2IV
l DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h ON DATE 3/8/85 PAGE 3 0F 47 ( Tirts. STEAM GENERATOR TUBE RUPTURE l ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i NOTE: e Foldout page should be open. e Personnel should be available for sampling during this procedure. o Seal injection flow should be maintained to all RCPs. e If subcooling monitor becomes inoperable, determine subcooling by using WR RCS pressure and core exit TCs (Refer to APPENDIX C).
- 1. CHECK If RCPs Should Remain in Servjce:
- a. Check WR RCS pressure - GREATER 1. -
IF RCS pressure less than THAN 1275 PSIG (VB2) 1275 psig, THEN close charging purrp mini-flow valves 8105 and 8106.
- 2. IF either one charoing or k one SI pump running, THEN stop all RCPs and go to Step 2.
- b. Check Phase B - NOT ACTUATED b. IF Phase B ACTUATED, (Vbl/PK01-18 contmnt spray TiiEN stop all RCPs.
actuation) ------------------
- 2. IDENTIFY Ruptured SG(s): Continue with Steps 5 through 12 e High radiation from any SG - AND -
steamline rad monitor, (RE 71 74) WHEN ruptured SG(s) identified.
-0R- TITOi do Steps 3 and 4. OBSERVE CAUTION PRIOR TO STEP 3.
e Unexpected increase in any SG 1evel _0R-e Radiation survey of main steam lines indicates high radiation level DC0407 31V
NUMBER EP E-3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 PAGE 4 0F 47 7,7 g STEAM GENERATOR TUBE RUPTURE h ACTION /EXRCTED RESPONSE RESPONSE NOT OBTAINED CAUTION: e If the TD AFW pump is the only available source of feed flow, steam supply to the TD AFW pump must be maintained from at least one SG. e At least one SG must be maintained available for RCS cooldown.
- 3. ISOLATE Flow FROM Ruptured SG(s):
- a. Ruptured SG(s) 10% Stm Dump controller in AUTO set to 1050 PSIG (8.75 turns /VB3)
- b. Close ruptured SG(s) MSIV and b. Perform the following:
bypass v1vs (VB3)
- 1) Verify the following:
e Stm Dump Mode Selector
- 0FF g e MSR Stm Supply - T ISOLATED e Cylinder Heating Stn -
ISOLATED e Gland Sealing Stm - IS0 LATED e Aux Stm - ISOLATED Unit 1 Shut AA5-1-3 and AAS-1-75, Aux Stm Red Sta PCV Outlet viv and equal viv (Outside 35% Dump Rm El 140) Unit 2 Shut AX5-2-3 and AX5-2-75 Aux Stm Red Sta PCV Outlet viv and Equal viv (Outside 35% Dump Rm El 140) e Stm Traps To Condenser - ISOLATED THIS STEP CONTINUED ON NEXT PAGE DC0407 4IV
NUMBER EP E-3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 0 7,7 g STCAM GENERATOR TUBE RUPTURE PAGE 5 ' 0F 47 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2) Close all remaining MSIV and bypass vivs.
- 3) Use intact SG(s) 10% Stm Dump Vlvs for steam dump.
IF any ruptured SG can NOT be isolated from at least one intact SG, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED REC 0VERY DESIRED.
- c. Check ruptured SG(s) c. WHEN ruptured SG pressure less 10% stm dap viv CLOSED than 1050 psig, THEN verify SG 10% stm dump Os (VB3) viv closed.
IF NOT closed, TREN place 10% stm dump controller in mar.ual and close viv. IF 10% stm dump can NOT be closed, THEN locally isolate 101 stm dump. THIS STEP CONTINUED ON NEXT PAGE bv DC0407 SIV
NUMBER EP E-3 1 AND 2 REVIS10N 0 DIABLO CANYON' POWER PLANT UNIT NO(S) DATE 3/8/85 PAGE 5 0F 47 7,7 g STEAM GENERATOR TUBE RUPTURE h ACTION /EXRCTED RESMSE RESMSE f0T OBTAINED
- 2) Close all remaining MSIV and bypass vlvs.
- 3) Use intact SG(s) 10% Stm Dump Vivs for steam duno.
~
IF any ruptured SG can NOT be isolated from at least one intact SG, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED REC 0VERY DESIRED.
- c. Check ruptured SG(s) c. WHEN ruptured SG pressure less 10% stm dmp vlv CLOSED than 1050 psig, (VB3) -
THEN verify SG 10% stm dump viv closed. IF NOT closed, TIIEN place 10% stm dump controller in marual and close viv. E 10% stm dump can NOT be closed, THEN locally isolate 10% stm durrp. THIS STEP CONTINUED ON NEXT PAGE O DC0407 SIV i
NUMBER EP E 3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 , DATR 3/8/85 \ PAGE 7 0F 47 TITLE STEAM GENERATOR TUBE RUPTURE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: If any PZR PORV opens because of high PZR pressure, Step Sb should be repeated after pressure decreases to less than the PORV setpoint.
- 5. CHECK PZR PORVs And Stop Valves:(VB2)
- a. Power to stop vivs a. Restore power to stop valves.
- AVAILABLE
- b. PORV's - CLOSEC b. IF RCS pressure is less than 2335 psig, o PCV 474 PORV - A THEN manually close FORV or e PCV 455C PORV - B associated stcp vivs.
e PCV 456 PORV - C e 8000A Stop Vlv A \. e 80008 Stop Viv B e 8000C Stop Viv C IF PORV and associated stop valve can NOT be clostd, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT, SUBC00 LED REC 0VERY DESIRED.
- c. POEV stop vivs - AT LEAST ONE c. Open stop viv unless it was OPEN used to isolate an open FORV.
- 6. CHECK If SGs Are Not Faulted:(VB3)
- a. Check pressures in all SGs a. Verify all faulted SGs isolated unless needed for RCS cooldown:
e NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER e Steamlines
- OR - e Feedlines e NO SG COMPLETELY DEPRESSURIZED IF NOT, THEN 00 to E-2, FAULTED 3 TEAM GENER TdR ISOLATION.
O V DC0407 71V
DMBLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 ON DATE 3/8/85 TITLE. STEAM GENERATOR TUBE RUPTURE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: Alternate water sources for AFW pumps will be necessary if CST level decreases to less than 10%. (Refer to E_2.1, ALTERNATE AUXILIARY FEEDWATER SUPPLIES.)
- 7. CHECKIntactSGLevels:(VB3)
- a. NR level - GREATER THAN 4%[20%] a. Maintain total feed flow greater than 460 gpm UNTIL NR level is greater than 4%[20%]inatleast one SG.
- b. Centrol feed flow to maintain b. IF
-~
NR level in any intact SG SG NR level between 4%[20%] and continues to increase in 33% an uncontrolled manner, THEN return to Step 1. NOTE PRIOR TO STEP 1. OBSERVE h
- c. Stop TD AFW pp if NOT needed for
-~
RCS heat removal CAUTION: If offsite power is lost after SI reset, manual action will be required to restart RHR, SI and Containment Spray pumps. Refer to Appenaix A for guidance if this conditions cccurs.
- 8. RESET SI (VBI)
- 9. RESET Both Trains Of Containment Isolation Phase A AND Phase B (VB1)
O DC0407 81V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 S}0N
<- DATE 3/8/85
(% PAGE 9 0F 47 TITLE STEAM GENERATOR TUBE RUPTURE ACTION /E)otutv RESPONSE RESPONSE NOT OBTAINED
- 10. ESTABLISH Instrument Air To Containment: (VB4)
- a. Open FCV 584 Cnmt Inst Air Iso Viv
- b. Ensure at least one air b. Start at least one inst air compressor - IN SERVICE compressor.
IF inst air can NOT be restored, THEN Refer to OP AP-9 LOSS OF INST AIR while continuing in this procedure.
- 11. VERIFY All AC Busses - Try to restore offsite power,
- EhERGlZED 6Y OFFSITE POWER g3 IF power can NOT be restored,
) (VB4)
TREN manually load the following ecuipment on te the vital buses within DG capacity (2.6 MW): o PZR Heaters (refer to OP A-4A:I PZR MAKE AVAILABLE) e TSC
- 1) OPEN 52-22J-40.
- 2) OPEN 52-2F-47,
- 3) OPEN 52-1F-67.
- 4) Switch EPTSN to Vital Power.
IF D/G 13 on U1 F bus
- 5) TREN Swtich EPTSC to U-1 (52-1F-67) and CLOSE 52-1F-67.
IF D/G on U2 F bus
- 6) TREN Switch EPTSC to U-2 (52-2F-47) and CLOSE 52-2F-47.
q e Instrument Air Compressor (s) t DCC407 91V ; i
N 0AsLo CANYON POWER PLANT UNIT NO(S) 1 AND 2 RV ON DATE 3/8/85 , PAGE 10 0F 47 1 TITLE STEAM GENERATOR TUBE RUPTURE ACTION / EXPECTED RESPmSE RESPONSE NOT OBTAINED CAUTION: RCS pressure should be monitored. If RCS pressure decreases to less than 300 psig, the RHR pumps must be manually restarted to supply water to the RCS.
- 12. CHECK If RHR Pumps Should Be Stopped:
- a. WR RCS pressure - GREATER THAN a. Go to Step 13. OBSERVE CAUTION 300 PSIG (VB2) PRIOR TO STEP 13.
- b. Stop both RHR pumps (VB1)
CAUTION: All attempts to isolate flow FROM the ruptured SG(s) should be complete before continuing to Step 13 unless a ruptured SG is needed for RCS cooldown. O
- 13. CHECK Ruptured SG(s) Pressure Go to ECA-3.1, SGTR WITH LOSS OF
- GREATER THAN 600 PSIG (V63) REACTOR COOLANT-SUBCOOLED REC 0VERY DESIRED.
j O DC0407 10!V l I i
i l DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 fSf0N
DATE 3/8/85 '
( PAGE 11 0F 47 TITLE. STEAM GENERATOR TUBE RUPTURE ACTION /EXFtutu RESRASE RESPONSE NOT OBTAINED
- 14. INITIATE RCS Cooldown:
- a. Determine required core exit temperature from table below:
(provides 20*F min subcooling) RUPTURED SG PRESSURE (PSIG) REQ'D CORE EXIT TEMPERATURE ( F) 1050 504 1030 502 1000 498 900 485 C 800 471 700 456 600 438 THIS STEP CONTINUED ON NEXT PAGE l lO DC0407 111V I
NUMBER EP E-3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 l DATE 3/8/85 ! PAGE 12 0F 47 TITLE: STEAM GENERATOR TUBE RUPTURE h ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- b. Dump steam to condenser from b. Manually or locally dump intact SG(s) at maximum rate and steam at maximum rate from avoid main steam iso intact SG(s) with SG 10% Stm
- 1) Transfer Steam Dump Mode Selector to the steam IF no intact SG available, pressure mode (CC2) TREN perform the following:
- 2) Place to CONT ONLY, LCV-12 e Use faulted SG, selector switch 0R_
- 3) Place the steam pressure controller in MANUAL and e Go to ECA-3.1, SGTR WITH increase demand OR leave in LOSS OF REACTOR COOLANT -
AUTO and decrease pressure SUBC00 LED REC 0VERY DESIRED. set (CC3)
- 4) When P-12 is reached, select BYPASS INTERLOCK on the Stean Dump Train A & B selector switches and continue cooldown (PK8-06/CC2)
- c. Core exit TCs - LESS THAN c. Return to Step 14b.
REQUIRED TEMPERATURE (SPDS/PAMS 3/4)
- d. Stop RCS cooldown, maintain RCS temperature with steam dump O
DC0407 12!V ! l
NUMBER EP E-3 1 AND 2
.ABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 p DATE 3/8/85 Q PAGE 13 0F 47 7a STEAM GENERATOR TUBE RUPTURE ACTION / EXPECTED RESPONSE RESPONSE f0T OBTAINED CAUTION: RCS cooldown in Step 14 should be completed before continuing to Step 15, unless SG overfill is iminent.
- 15. CHECK Ruptured SG(s) Pressure IF ruptured SG pressure continues
- STABLE OR INCREASING (VB3) to decrease, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED REC 0VERY DESIRED.
- 16. CHECK RCS Subcooling Based On Core Go to ECA-3.1, SGTR WITH LOSS OF Exit ICs - GREATER THAN 40:F REACTOR COOLANT - SUBC00 LED (SPDS/PAMS 3/4) RECOVERY DESIRED O
O DC0407 131V
NUMBER EP E-3 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/8/85 PAGE 14 0F 47 7,7 g STEAM GENERATOR TUBE RUPTURE g ACTION /EX RCTED RESPONSE RESPONSE NOT OBTAINED
- 17. DEPRESSURIZE RCS To Minimize Break Flow And Refill PZR:
- a. Normal PZR spray - AVAILABLE a. Close PCV-455 A&B and
[PCV-455A(LP-1)or455B Go to Step 18. OBSERVE (LP-2)] CAUTIONS AND NOTES PRIOR TO STEP 18.
- b. Close any idle loop spray viv
- c. Spray PZR with maximum available spray until ANY of the following conditions satisfied:
e BOTH of the following:
- 1) RCS pressure - LESS THAN RUPTURED SG PRESSLRE,
- AND -
- 2) PZR level - GREATER THAN 4%[20]%
- OR -
e RCS subcooling based on core exit TCs- LESS THAN 20*F
- GR -
e PZR level - GREATER THAN 77%[70]%
- d. Close PZR spray valve (s): d. J,F, spray vivs will NOT close, (CC2)
THEN 1) Stop RCP(s) supplying Normal spray vivs [PCV-455A failed spray viv(s). 1) (LP-1) and PCV-455B
- 2) Close charge line iso (LP-2)]. viv 8108 and 8107.
isolate normal Htd ar.d
- 2) Aux. Spray - 8145 and initiate excess Itdn.
2148 charge line to PZR aux spray and bypass vivs
- e. Go to-Step 20. OBSERVE CAUTION PRIOR TO STEP 20.
O DC0407 141V
NUMBER EP E-3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 p) y DATE PAGE 3/8/85 15 0F 47 TITLE. STEAM GENERATOR TUBE RUPTURE ACTION /EXPECTEDREsPONSE RE5PONSE NOT OBTAlfE CAUTION: e The PRT rupture disc may rupture if a PZR PORV is used to depressurize the RCS. This may result in abnonnal containment conditions, e Cycling of the PZR PORV should be minimized. e Auxiliary spray flow into the PZR shall not be initiated if the delta-T between the PZR and the spray fluid exceeds 560 F. NOTE: e The upper head region may void during RCS depressurization if RCPs are not running. This will result in a rapidly increasing PZR level, e If PZR Auxili6ry spray is used it may be necessary to close normal spray PCV 455A & B and charging valves A0V 8146 and 8147.
- 18. DEPRESSURIZE RCS Usinc PZR PORV To Minimize break Flow Anc Retill PZR:(VE2)
- a. PZR PORV - AT LEAST a. Establish aux spray and ONE AVAILABLE (ibz) return to Step 17b.
IF PZR press control can NOT be established, THEN go to ECA-3.3 SGTR KITHOUT PRESSURIZER PRESSURE CONTROL. THIS STEP CONTINUED ON NEXT PAGE DC0407 151V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 3/8/85 mm STEAM GENERATOR TUBE RUPTURE ACTION /EXftutu RESPONSE RESPONSE NOT OBTAINE
- b. Open one PZR PORV until ANY of the following conditions satisfied:(VB2) e BOTH of the following:
- 1) RCS pressure - LESS THAN RUPTURED SG PRESSURE
- AND -
- 2) PZR level
- GREATER THAN 4%[20]%
- OR -
e PZR level - GREATER THAN 77t[70]%
- OR -
e RCS subcooling based on core exit TCs - LESS THAN 20 F
- c. Close PZR PORV (VB2) c. Close PZR PORV stop valve.
e PCV-474 - CLOSED PORV - A e 8000A PORV Stop Viv A e PCV-455C - CLOSED PORV - B e 80008 PORV Stop Viv B e PCV-456 - CLOSED PORV - C e 8000C PORV Stop Vlv C O DC0407 161V i
NUMBER EP E-3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0
'N DA7E 3/8/85 4 PAGE 17 0F 47 TITLE. STEAM GENERATOR TUBE RUPTURE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 19. CHECK RCS Pressure Close PZR PORY stop valve.
- INCREASIhG (VB2)
IF RCS pressure continues to decrease, THEN perform the following:
- 1) Monitor following conditions for indication of leakage from PZR PORV: (VB2) e PRT Pressure Increasing e PRT Level Increasing e PRT Temp Increasing e PORV Tailpipe Temp Elevated
- 2) Go to ECA-3.1, SGTR WITH
,- LOSS OF REACTOR COOLANT -
SUBC00 LED RECOVERY DESIRED. O l DC0407 171V i l
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/8/85 PAGE 18 0F 47 TITLE STEAM GENERATOR TUBE RUPTURE llll ACTION /EXPECTEDRE$PCNSE RESPONSE f0T OBTAINED CAUTION: ECCS FLOW MUST BE TERMINATED when termination criteria are satisfied to prevent overfilling of the ruptured SG(s).
- 20. CHECK If ECCS Flow Should Be Terminated:
- a. RCS subcooling based on core a. Go to ECA-3.1, SGTR WITH LOSS exit TCs- GREATER THAN 20*F 0F REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED.
- b. Secondary heat sink: (VB3) b. IF neither condition sa tis fied ,
Total feed flow to SG(s) THEN go to ECA-3.1, SGTR
- GREATER THAN 460 GPM WITH LOSS OF REACTOR AVAILABLE COOLANT - SUBC00 LED REC 0VERY DESIRED.
- OR _
Narrow range level in at least one intact SG - GREATER THAN 4%[20]
- c. RCS pressure - STABLE OR c. Go to ECA-3.1, SGTR WITH LOSS OF INCREASING (VB2) REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED.
- d. PZR level - GREATER THAN d. Return to Step 13. OBSERVE 4%[20]%(VB2) CAUTION PRIOR TO STEP 13.
O DC0407 18IV
1 l NUMBER EP E-3 i DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 O DATE PAGE 3/8/85 19 0F 47 TiTts: STEAM GENERATOR TUBE RUPTURE ACTION /EXECTED ESPONSE ESPONSE NOT OBTAINED
- 21. STOP ECCS Pumps And Place in Stby:
- a. Stop SI Pumps (VB1)
- b. Check any cent charg pp - b. 1) Ensure PD charging pump RUNNING running.
'2) Control charging pump speed FCV-128, and HCV-142 to maintain:
e Seal Injection e PZR Level
- 3) Go to Step 22.
- c. Open FCV-128
- d. Stop the PD charg pp
- e. STOP one of two running cent charg pp O
DC0407 191V
NUMBER EP E-3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 m LE STEAM GENERATOR TUBE RUPTURE h ACTION /EXPECTEDREsPONsE RESPONSE NOT OBTAINED
- 22. ESTABLISH Charging Flow:
- a. Throttle to 50%-HCV-142 RCP Seal Backpress cont viv (CC2)
- b. OPEN FCV-128 cent charg pps flow cent viv
- c. OPEN 8105 & 8106 charg pps c. -
IF 8105 or 8106 will NOT 11 and 12 min flow vlvs (VB2) open, THEN maintain a minimum of 60 gpm charging flow.
- d. IF SG 4 Intact d. IF SG 4 NOT Intact, TEEN e Open 8146 normal TREN e Opeii 3147 alt charg to LP 4 cold leg charg to LP 3 cold leg viv viv, e Close 8147 alt charg to LP3 cold leg e CLOSE 8146 normal charg to LP 4 cold leg h
viv. (VB2)
- e. Cicse 8145 & 8148 charg line to PZR aux spray viv and bypass (VB2)
- f. Open 8108 & 8107 normal charg to regen hx stcp vlvs 1 & 2 (VB2)
- 9. Ensure one cent charg pp -
RUNNING (VB2)
. OR -
e Ensure CCW flow to PD charg pp (FCV-355 open) e Start PD charg pp (VB2) THIS STEP CONTINUED ON NEXT PAGE O DC0407 20!V
NUMBER EP E-3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 o DATE 3/8/85 b) PAGE 21 0F 47 7,7a STEAM GENERATOR TUBE RUPTURE ACTION /EXECTEDRESPONSE RESPONSE NOT OBTAINED
- h. Adjust charging flow and HCV-142 RCP Seal Inj Back press cont viv to maintain:
(CC2/VB2) e PZR level - STABLE e Seal Injection to each RCP 8 (6-12) GPM
- 23. ISOLATE BIT (VB2)
- a. Close 8803A & B BIT supply vivs
- b. Close 8801A & B BIT outlet vivs
- 24. CONTROL Charging To Mair.tain PZR Level Greater tnan 4k [20LJ(CC2)
- 25. VERIFY ECCS Flow Not Recuired:
- a. RCS subcooling based cr. core exit a. Manually operate ECCS purps TCs - GREATER THAN 20'F (VB2) as necessary. Go to ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANT - SUSC00 LED REC 0VERY DESIPED.
- b. PZR level - GREATER THAN 4t[20E] b. Manually operate ECCS pumps (VB2/CC2) as necessary. (VB1)
IF level can NOT be maintained, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT
- SUBC00 LED REC 0VERY DESIRED.
DC0407 21IV
1 NUMBER EP E-3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 22 0F 47 l Tirts. STEAM GENERATOR TUBE RUPTURE ACTION /EXPEutv RESP 0 HSE RESPONSE NOT OBTAINED
- 26. CHECK VCT Makeup Control System: Adjust as necessary.
o Ensure makeup set for - GREATER THAN RCS BORON CONCENTRATION OR SET AT 2000 PPM (7 turns) (CC2) e Nakeup set for automatic: (Refer to OP B-1A:VII CVCS - MAKEUP CONTROL SYSTEM OPERATION Part A - PLACE IN AUTOMATIC)
- 27. CHECK If Letdown Can Be Established:
- a. PZR level - GREATER THAN 17%[40%] a. Continue with Step 28, (V82/CC2)
- AND -
WHEN PZR level increases to greater than 17%[4Ut]
- b. Establish letdown as follows: b. Establish excess letdown as follows:
- 1) Open FCV-355 CCW hdr C iso viv 1) Place charg pp control in manual and reduce charg
- 2) Position to 40% TCV-130. LTON ficw to min.
Temp Cont viv
- 2) Close 8107 and 8108
- 3) Position to 20% PCV 135 ltdn charg hdr iso vivs.
press cent viv (V82)
- 3) Adjust Charging to
- 4) Open LCV 459 and 460 Itdn stop Maintain Seal Injection Vivs(VB2) 6-12 GPM.
- 5) Ensure 45 GPM charg flow through regen hx (CC2)
- 6) Place in auto LCV 112A VCT ivi cont divert viv (VB2)
- 7) OPEN 8152 ltdn iso viv OC(V82)
THIS STEP CONTINUED ON hEXT PAGE DC0407 22IV l
N DIABLO CANYON POWER PLANT UNIT NC(S) 1 AND 2 R ON S DATE 3/8/85
> PAGE 23 0F 47 TITLE. STEAM GENERATOR TUBE RUPTURE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAlfE 8)OPEN: (VP2) 4) IF_ 8100 and 8112 open, e 8149A 45 GPM THEN Place 8143 In normal position (VCT)
. AND/0R - - excess Iton to seal wtr hx or RCDT viv, e 8149B 75 GPM o IF 8100 and 8112
- AND/0R - closed, THEN Place 8143 in e 8149C 75 GPM RCDT position.
- 9) Maintain 350 psig on PI-135 5)OPEN:
with PCV-135 ltdn press cont viv e FCV 355 CCW hdr C iso viv. e Set PCV-135 controller to 350 psig (5.83 turns, VB2) e FCV 361 CCW from excess AND Place in AUTO if desired
- 6) Close HCV 123 excess Itdn flow cont viv.
- 7) Open 8166 ar.d 8167 excess Itdn stop vivs.
- 8) Open HCV 123 as necessary To Maintain:
o PZR Iv1. e LESS THAN 190*F on TI-122.
- c. Manually control charging to establish: (CC2) e PZR LVL between 17% [401] and 60%(VB2/CC2) e LESS THAN 380*F on Regen Hx LTONTemp(TI-127)(VB2) e Seal injection to each RCP 8 (6-12)gpm C)
DC0407 231V
NUMBER EP E-3 DIABLC CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 24 0F 47 r:Tts. STEAM GENERATOR TUBE RUPTURE h ACTION /EMtuw RESPONSE RESPONSE NOT OBTAINED
- 28. ALIGN Charging Puma Suction To The VCT, If Desired (V32)
- a. Check VCT level >10% a. Go to Step 29
- AND .
WHEN VCT level >10% TiiER Align charg pp suction to the VCT by performing steps 28b and c.
- b. Open LCV.112B & C VCT cutlet vivs
- c. Close 68CSA & B charg pp suct frcm RWST vivs CAUTION: e RCS and ruptured SG(s) pressures must be maintained less than 1050 psig.
e Auxiliary spray flow into the pressurizer shall not be initiated it the temperature difference between the pressurizer and the spray fluic exceeds 560*F. Spray flow should not be initiated if the temperature difference exceeds 320*F.
- 29. CONTROL RCS Pressure And Makeup Flow To Minimize RCS-To-Secondary Leakage
- a. Control RCS pressure and makeup flow per decision table
- b. Use normal PZR spray b. E normal spray is NOT AVAILABLE or desired.
THEN use Aux spray
- OR .
One PZR PORV. THIS STEP CONTIhuED ON NEXT PAGE O DC0407 241V l
NUMBER EP E-3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 O DATE 3/8/85 (d PAGE 25 0F 47 TITLE. STEAM GENERATOR TUBE RUPTURE ACTION / EXPECTED RESPONSE RESP 0l4SE NOT OBTAINED
- c. Decision table:
RUPTURED SG LEVEL INCREASING DECREASING OFFSCALE PZR LEVEL HIGH e Increase RCS Increase RCS e Increase RCS Makeup Flow Makeup Flow Makeup Flow LESS THAN - AND - - AND - 17%[401] e Depressurize o Maintain RCS RCS And Ruptured SG(s) Pressures Equal BETnEEh i bl40kJ e Depressurlie Ensure PZh Maintain RCS AND 50% RCS Heaters - ON And Ruptured SG(s) Pressures pd Equal BETWEEh 50a e Depressurize Ensure PZR Maintain RCS Af;D77%[70i] RCS Heaters - ON And Ruptured SG(s) Pressures Equal
- AND -
e Decrease RCS Makeup Flow GREATER THAN Decrease RCS Ensure PZR Maintain RCS 77'[70%]
, Makeup Flow Heaters - ON And Ruptured SG(s)
Pressures Equal O v I DC0407 251V l
NUllBER EP E-3 OlABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 26 0F 47 TITLE STEAM GENERATOR TUBE RUPTURE ACTION /EXFtutu RESPONSE RESPONSE t0T OBTAINED
- 30. CHECX If Diesel Generators Should Be Stopped: (VB4)
- a. Verify vital buses F, G and H - a. IF-any vital bas NOT ENERGIZED BY OFFSITE POWER energized by oTfsite power, THEN attempt to restore offsite power, either STARTUP or AUXILIARY, to the vital buses.
- b. Stop any unloaded diesel generator and place in - AUT0
- 31. MINIMIZE Secondary System Contamination:
- a. Isolate reject as follows:
- 1) Clos,eLCV-12 condensate reject viv
- 2) Sample the hotwell
- 3) Use reject, in manual, based on hatwell sample results
- 4) Maintain CST level below the overficw THIS STEP CONTINUED ON NEXT PAGE O
OC0407 261V
NUMBER EP E-3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 (Q) PAGE 27 0F 47 TITLE. STEAM GENERATOR TUEE RUPTURE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- b. Isolate condensate polisher demins: (VB2)
- 1) Open FCV-230 CNDS polisher bypass viv
- 2) Close FCV.231 CNDS polisher inlet valve
- c. Transfer aux steam supply to aux boiler (Refer to OP X-5 IV, Part 5)
- d. Ensure MSRs isolated (VB3)
- e. Ensure main feed pumps glar.c seals are supplied from aux boiler
- f. Manually transfer blowdown tank outlet from outfall to EDRT (FCV-498 closed and FCV.499 opened) (VB3)
- 9. Verify blowdown and sartple 9. Manually isolate blowdown.
blowdown isolation has occurred (VB3)
- 32. TURN On PZR Heaters As Necessary To Saturate PZR Water At Ruptured SG(s)
Pressure (CCl) DC0407 271V I
NUMBER EP E-3 1 AND 2 REVIS10N 0 DIABLO CANYON POWER PLANT UNIT NO(S) l DATE 3/8/85 STEAM GENERATOR TUBE RUPTURE TITLE. ACTION /EXWCTED RESPONSE RESRJNSE NOT OBTAINED
- 33. CHECK RCP Cooling - NORMAL:
- a. RCP Seal Ret and Lower Rad Brg a. Perform the following Temp <225'F(V82)
- 1) Trip the affected RCPs.
- 2) Refer to Appendix R.
- 3) Go to Step 35. OBSERVE CAUTION PRIOR TO STEP 35.
- b. Verify CCW - ALIGNED TO RCPs b. IF CCW NOT aligned to RCPs, (V81) TIIEN
- 1) RESET phase B e Oper FCV-355, CCW hdr C 150 viv isolation.
e Open FCV-356, CCW to RCP oil 2) manually open CCW clrs therm bar & sup clrs valves, e Open FCV-357, CCW frorr RCP therm bar 0C e Open FCV-363, CCW f rcrr RCP oil cles & sup c1rs 0C e Open FCV-749, CCW frcm RCP oil
& sup cirs e Open FCV-750, CCW f ron RCP therm bar IC
- c. Verify RCP seal injection flow 8 c. Adjust HCV-142 as necessary.
(6-12) GPM to each RCP (VB2) RCP seal inj back pressure viv. O OC0407 281V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 fE ON DATE 3/8/85 l I PAGE 29 0F 47 TITLE. STEAM GENERATOR TUBE RUPTURE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 34. CHECK If RCP Seal Return Flow Should Be Established:
- a. Initiate seal return as follows:
- 1) Close ANY #1 seal return iso vlv with GREATER THAN 6 GPM seal return flow indicated (VS2)
RCP #1 Seal Ret Viv 1 A0V-8141 A 2 A0V-8141 B 3 A0V-8141 C 4 A0V-8141 D
- 2) Open FCV-355 CCW hdr C iso viv I I 3) Open 8100 and 8112 RCP seal ret iso vivs (VB2) l I I DC0407 29:V
i DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 3/8/85 I PAGE 30 0F 47 TITLE STEAM GENERATOR TUBE RUPTURE h RESPONSE NOT OBTAINED , ACTION / EXPECTED RESPONSE CAUTION: e If RCP seal cooling had previously been lost, the affected RCP should not be started prior to status evaluation, e On natural circulation, RTD bypass temperatures and associated interlocks for Feedline Iso., Steam Dump and Hi Stm Flow SI will not be accurate. NOTE: All but one RCP may be stopped to minimize pump heat input. If maintaining a 100*F/hr cooldown, running 2 RCPs is desirable; RCP 1 or 2 (#2 preferred) for normal PZR spray and RCP 3 or 4 to maximize MD AFW pump capacity.
- 35. CHECK RCP Status: (VB2)
- a. RCPs - AT LEAST ONE RUNNING a. Try to start one RCP as follows:
- 1) IF RVLIS full range indicaticn less than 100%,
THEN perform the following: e Increase PZR level greater than UNIT 1 UNIT 2 67%[90%] 75% [90%] e Increase RCS subcooling greater than 40*F e Ensure close PCV 455A and B, normal PZR spray vivs. e Establish PZR temp at saturation for RCS pressure.
.. 2) Establish conditions for starting an RCP per Appendix B.
THIS STEP CONTINUED ON NEXT PAGE ( DC0407 30lv
NUMBER EP E-3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 p V DATE PAGE 3/8/85 31 0F 47 TITLE. STEAM GENERATOR TUBE RUPTURE ACTION / EXPECTED RESR)NSE RESPONSE NOT OBTAINED
- 3) Start one RCP.
IF a RCP can NOT be started, THEN operate steam dump to ensure Natural Circulation: e RCS subcooling GREATER THAN 20 F. e Intact SG pressures STABLE OR DECREASING. e RCS hot leg temperatures and Core Exit TCs - STABLE OR DECREASING. e RCS cold leg temperatures AT SATURATION TEMPERATURE O FOR INTACT SG PRESSURE
- AND -
go to Step 36.
- b. Stop all but one or two RCPs at SFM discretion (VB2)
- c. Close normal PZR spray viv on ANY idle loop (CC2) e PCV-455A for loop 1 e PCV-4558 for loop 2 l
lo l DC0407 31IV
OtABLO CANYON POWEA PLANT UNIT NO(S) 1 AND 2 ON DATE 3/8/85 PAGE 32 0F 47 TITLE . STEAM GENERATOR TUBE RUPTURE llg) ACTION /EXFtutu RESPONSE RESPONSE f0T OBTAINED
- 36. CHECK If SR Detectors Should Be Energized: (CC1)
- a. Continue with Step 37.
- a. Check IR Flux - LESS THAN 10 10 amps WHEN flux is less than 10 10 amps.
THEN do Step 36b and c.
- b. Verify both SR detectors - b. Manually reset and energize ENERGIZED both SR detectors.
- c. Select highest SR and IR detector on NR 45 recorder
- 37. SHUT DOWN Any Running Plant Equipment Not Requirec For Post Accident Recovery (Refer to OP L-5 PLANT C00LDOWN FRCM MINIMUM LOAD TO COLD SHUT DOWN)
- 38. CHECK If SI Accumulators Should Be Isolated:
- a. Check the following: (VB2) a. IF subcooling OR PZR 1evel is low, o RCS pressure <1000 psig THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT e RCS subccoling - SUBC00 LED REC 0VERY
- GREATER THAN 20*F DESIRED.
e PZR 1evel
-GREATERTHAN4%[20%]
THIS STEP CONTINUED ON NEXT PAGE O' l DC0407 321V
NUMBER EP E-3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 I (* DATE 3/8/85 t PAGE 33 0F 47 I mLE STEAM GENERATOR TUBE RUPTURE ACTION / EXPECTED ESPONSE EsPONsE NOT OBTAINED
- b. Power to accumulator disch iso b. Make power available to vivs - AVAILABLE accumulator iso vivs.
- c. Close all accumulator disch iso c. IF- any accumulator vlvs: (VB2) isolation valve does NOT Close, 8808A, B, C, D THEN perform the following:
- 1) Close FCV-8880 eccumulator N fill isol viv 2)Ohen8835A,B, Cord accumulator N, supply vent to affected accumulator.
- 3) Open HCV 943 accumulator N2 supply vent UNTIL accumulater is depressurizeo while continuing in the procedure.
- 39. VERIFY Acequate Shutdown Margin:
- a. Sample ruptured SG(s)
- b. Sample RCS Hot Legs anc PZR
- c. Implement shutdown margin - c. Borate as necessary.
ADEQUATE (implement STP R-19 SHUTDOWN MARGIN CALCULATION)
- d. Periodically sample RCS and ruptured SG to confirm SDM (approx every half hour)
[G DC0407 331V l
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 f0N DATE 3/8/85 m tE. STEAM GENERATOR TUBE RUPTURE ACTION /EXFtutu RESPONSE RESPONSE NOT OBTAINED CAUTION: Alternate water sources for AFW pumps will be necessary if CST level decreases to less than 10%. (Refer to EP E-2.1 ALTERNATE AUXILIARY FEE 0 WATER SUPPLIES).
- 40. CHECK Intact SG Levels: (VB3)
- a. Check intact SG(s) NR level - a. Ensure total feed flow GREATER THAN 4%[20%] greater than 460 gpm until NR level is greater than 4%[20%]
in at least one SG.
- b. Control AFW flow to maintain NR b. IF- NR level in any intact level between 4%[201] and 33% SG continues to increase in an uncontrolled manner, ThEN return to Step 1.
O' DC0407 34IV
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/8/85 (m) PAGE 35 0F 47 TITLE STEAM GENERATOR TUBE RUPTURE ACTION /EXPECTEDRESPON5E RE5PONSENOTOBTAINED NOTE: Since ruptured SG(s) may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should be completed as quickly as possible, not to exceed 100*F in any one hour period.
- 41. INITIATE RCS Cooldown To Cold Shutdown:
- a. Maintain RCS cooldown rate in RCS cold legs - LESS THAN 100 F in any one hour period (CC2/VB2)
- b. Use RHR system if in service (VB2)
- c. Dump steam to condenser from c. Manually or locally durnp intactSG(s)(CC2) steam from the intact SG 10i p steam dump (s).
IF no intact SG available and RHR system NOT in service, THEN perform the following: e Use faulted SG _ OR - e Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED REC 0VERY DESIRED. DC0407 35IV
DIABLO OANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 3/8/85 PAGE 36 0F 47 Tirte STEAM GENERATOR TUBE RUPTURE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to Step 29 to minimize RCS to SG flow, if desired. Observe CAUTION prior to Step 29.
- 42. CHECK Rustured SG(s) NR Level Refill ruptured SG to 67% using
- GREATER THAN 4%L20%j(VB3) feedflow.
E either of the following conditions occur, e Ruptured SG pressure decreases in an uncontrolled manner
- OR -
o Ruptured SG pressure increases to 1010 psig THEN stop feed flow to ruptured SG.
- 43. CONTROL RCS Makeup Flow And Letdown To Maintain PZR Level: (VB2/CC2)
- a. PZR level a. Increase RCS makeup flow
-GREATERTHAf;17'<[40Q
- AND .
Go to Step 44. OBSERVE CAUTION PRIOR TO STEF 44
- b. PZR level - LESS THAN 77%[70%] b. Decrease RCS makeup flow to control level and decrease RCS pressure
- AND -
Go to Step 45.
.e O
DC0407 361V
NUMBER EF E-3 OlABLO CANYON POWEA PLANT UNIT NO(S) 1 AND 2 REVISION 0 q' DATE 3/8/85 37 0F 47 Gr PAGE TiTa STEAM GENERATOR TUBE RUPTURE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAljTION: e Auxiliary spray flow into the PZR shall not be initiated if the delta-T between the PZR and the spray fluid exceeds 560 F. Spray flow should not be initiated if the delta-T exceeds 320*F. NOTE: e The upper head region may void during RCS depressurization if RCPs are not running. This may result in a rapidly increasing PZR level, e CRDM cooling fans should be in operation. e If PZR aux spray is used it may be necessary to close normal spray PCV 455A & B and charging valves 8146 and 8147.
- 44. DEPRESSURIZE RCS To Backfill From -
IF cooldown of ruptured SG NOT Ruotureo SG For Rupturea 56 Cooloown desired, IF DESIRED THEN go to Step 45. f'N Q a. Use: e Normal Spray (CC2) IF backfill method, is not desired, THEN minimize breakflow per Step
- AND/0R - 29 AND Bleed and feed the ruptured e Auxiliary Spray (VS2) SG using SG Blowdown as follows:
- AND/0R -
- 1) Verify blowdown tank e One PZR PORV (VBE) transferred to EDRT (FCV-498 closed. FCV-499
- b. Turn on PZR heaters as necessary open).
- c. Maintain RCS subcooling - GREATER 2) Monitor EDRT level, THAN 20*F temperature and plant vent activity.
- 3) Maintain:
e SG Ivl 20% to 70%. e PZR lvl 40% to 70%. e Subcooling >20*F.
- 4) Override any high rad isolation signal by placing the SG Blowdown hq Hi Rad switch in the CUT IN position. (VB-3)
THIS STEP CONTINUED ON NEXT PAGE l DC0407 371V l l
NUMBER EP E-3 DiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 m LE. STEAM GENERATOR TUBE RUPTURE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED IF blowdown is NOT possible. THEN vent steam from ruptured SG to condenser (preferred) or to atmosphere as follows:
- 1) Vent steam only if:
e no water is suspected in the steam line. e SG lvl can be maintained <90%. e 10CFR20 release limits are met. e all releases are monitored.
- 2) Maintain:
e SG Iv1 20% to 70%. e PZR lvl 40% to 70%.
- 45. CHECK If RHR Systen Can Be Placed in Service: (V82)
- a. Check the following: a. Go to step 46.
e Check RCS temperature
- LESS THAN 350 F e Check RCS pressure
- LESS THAN 390 PSIG
- b. Place RCS over pressure protection system IN SERVICE
- c. Implement OP B-2:V, RHR - PLACE IN SERVICE DURING PLANT C00LDOWN
+*
DC0407 38IV l
NUMBER EP E-3 DIABLO CANYON POWER PLANT UNIT NO(S) I AND 2 REVISION 0 DATE 3/8/85 C PAGE 39 0F 47 7 rte: STEAM GENERATOR TUBE RUPTURE 1 I ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 46. CHECK If RCP Must Be Stopped: (VB2) l l
- a. Check the following a. Go to Step 47.
e Number one seal differential pressure - LESS THAN 215 PSID
- OR -
e Number one seal leakoff flow out of limits of Appendix B
- b. Stop affected RCP(s)
- 47. CHECK RCS Temperature Return to Step 41. OBSERVE NOTE
- LESS THAN 200'F (VB2) PRIOR TO STEP 41.
- 48. EVALUATE Long Term Plant Status:
- a. Maintain cold shutdown conditions:
e RCS terp <200 F eKeff * '99
- b. Check containment atmosphere to determine if hydrogen recombiners or if hydrogen purge should be placed in service
- c. Implement OP L 5 PLANT C00LDOWN FROM MINIMUM LOAD TO COLD SHUTDOWN and review for applicable actions
- d. Check STP M 55 CYCLIC REVIEW
- e. Consult plant engineering staff
- END -
O DC0407 39IV l 1 __ _ - - - - - . - . -
1 AND 2 ON otABLO CANYON POWER PLANT UNIT NO(S) DATE 3/8/85 PAGE 40 0F 47 h m LE: STEAM GENERATOR TUBE RUPTURE APPENDIX A BLACK 0UT EMERGENCY LOADING 0F VITAL BUSSES
- 1. If the vital busses lose voltage prior to resetting the safety injection signal, the vital busses will automatically load the vital equipment given below. Verify the equipment has been loaded by observing breaker lights on the control board.
- 2. If the vital busses lose voltage after the safety injection signal has. been reset, load or verify loaded the equipment given below onto the vital busses manually. Allow approximately 4 seconds between loading of each piece of equipment onto a given vital bus. Load or verify that the CFCU are running in Low Speed.
VITAL BUS F VITAL BUS G VITAL BUS H U-1(D/G 1-3) U-1(0/G No. 2) U-1(D/G No.1) U-2(D/G 1-3) U-2(D/G No. 1) U-2(0/G No. 2) MCC F MCC G MCC H CCPp No. 1 RHR Pp No. 1 SI Pp No. 1 CFCU No. 3 SI Pp No. 2 CFCU No. 2 CFCU No. 5 RHR Pp No. 2 CFCU No. 1 CCW Pp No. 2 CFCU No. 4 CCW Pp No. 1 ASW Pp No. 2 CCW Pp No. 3 ASW Pp No. 1 CC Pp No. 2 AFW Pp No. 2 AFW Pp No. 3
- 3. Load the containment spray Pumps only if they were running prior to the blackout.
VITAL BUS VITAL BUS G H Cont Spray Pp No. 1 Cent Spray Pp No. 2 O l DC0407 40lv l
NUMBER EP E-3 1 AND 2 ILO CANYON POWER PLANT UNIT NO!S) REVISION 0 m DATE 3/8/85 PAGE 41 0F 47 f STEAM GENERATOR TUBE RUPTURE APPENDIX B Restart of Reactor Coolant Pump
- 1. Start oil lift pump, run for 2 minutes.
- 2. Verify CCW available to thermal barrier, oil coolers, seal water HX.
- 3. Verify seal dp greater than 215 psid, depressurize VCT as necessa ry.
- 4. Verify seal injection flow 8 (6 to 12) gpm.
- 5. Verify seal leak off flow within limits shown on graph.
- 6. Ensure closed PCV-455A and B, Normal PZR spray vivs ( AUTO c;;tional ) .
O ALLOWABLE RCP #1 SEAL LEAK RATES Cl 5 I 6 , I l f t l l a . i ,
* ?
SHUTDOWN RCP WITHlh j j ,
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! ONE HALF HOUR j
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2 I DO NOT START RCP . 0 l Ml . 6 , I t 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 8 RCP 81 SFAL DIFFERENTIAL PRE 55U9E PSID N. REGION 1 NO PHASE-A SIGNAL, dp*PC5 -VCT press oress PHASE-A PRESENT, dp*RC5 press -150psig REGION 2 USE INSTALLED do GAUGES DC040' 411V I L_--____ . - - - _ -
NUM3ER EP E-3 f.O CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 42 0F 47 STEAM GENERATOR TUBE RUPTURE APPENDIX C 2600
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300 400 500 600 700 200 CORE EXIT T/C TEMPERATURE (*F) , 1 t l DC0407 42IV 1
l NUMBER EP E-3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0
/3 DATE 3/8/85 l V PAGE 43 0F 47 TITLE: STEAM GENERATOR TUBE RUPTURE l
l APPENDIX R l 1 IF RCP SEAL RETURNS OR LOWER RADIAL BEARING TEMP HAS BEEN OR IS >225*F l PERFORM THE FOLLOWING: ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. CHECK RCP Seal Isolation Status:
- a. Verify seal injection iso ylvs a. IF valves open or position OC - CLOSED not known, THEN check centrifugal CVCS-8369A, B, C & D - CLOSED RCP charging pump status:
seal water cont isol vivs (100' GE - 127 to 137 ) IF pump running,
- 1) TiiEN return to Step 33 CHECK RCP COOLING -
NORMAL . IF pump NOT running,
- 2) TITEN manuaHy or locally close seal injection vlvs 0C.
- b. FCV-35/ CLOSEC RCF ther bar b. IF- valve is open or CCW return i;n viv OC (100' position not known, GE-166*) THEN check CCW pump status:
IF a pump is running,
- 1) TiiEN go to Step 2B.
IF pump NOT running,
- 2) TiiEN manuaTTP or locally close FCV-357.
IF FCV-357 can NOT be closed, THEN manually close FCV-750, CCW return viv IC. s DC0407 431V
.O CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 S ON DATE 3/8/85 PAGE 44 0F 47 STEAM GENERATOR TUBE RUPTURE O APPENDIX R (CONTINUED) ACTION /EXhutu RE5PON5E REsPONSENOTOBTAINED UTION: e RCP thennal barrier cooling should be established slowly to minimize potential introduction of steam into the CCW system. e RCP seal injection should be established slowly to minimize RCP thermal stresses and potential seal failures. e As part of subsequent recovery actions, RCPs should not be started prior to a status evaluation, unless responding to Inadequate Core Cooling FR-C.1. ESTABLISH RCP Seal Cooling:
- a. Establish CCW ficw to RCP thermal barriers (100', GE-166*)
- 1) Establish communications between the control room and 100' Aux. Bldg. Pent Area near FCV-357 CCW from RCP Therm Bar 0C
- 2) Monitor RCP lower bearing temperature (TI 155, 154, 153, 152 on VS2 ant T0417A, T0437A, T0457A, T0477A on the P250)
- 3) Cneck FCV-357 - CLOSED RCP 3) Close FCV-357 therm bar CCW return iso viv OC - OR -
CCW-267.
- 4) Check FCV-750 - OPEN RCP 4) IF ~
FCV-357 or CCW-267 therm bar CCW return iso viv CLOSED IC THEN open FCV-750. THIS STEP CONTINUED ON NEXT PAGE DC0407 441V O
CANYON POWER PLANT UNIT NO(S) 1 AND 2 h0N 0 G DATE 3/8/65 i V PAGE 45 0F 47 STEAM GENERATOR TUBE RUPTURE APPENDIX R (CONTINUED) ACTION / EXPECTED RE$PONsE RESPONSE NOT OBTAINED NOTE: Monitor flow on FI-90 (PNL 184 locally at FCV-357) and temperature on TI-1004 (locally at FCV-357). Initiate flow to the thermal barrier slowly reducing lower bearing temperature (TI 155, 154, 153, 152 on VB2 and T0417A, T0437A, T0457A, T0477A on the P250) at a maximum rate of 1*F per minute until full thermal barrier flow is returned to normal. Some local boiling may occur in the CCW lines giving a closed signal to FCV-357.
- 5) Locally crack open FCV-357 or CCW-267
. Establish Seal Injection Flow to RCPs (100', GE-127* - 137')
d ) Wait until seal leak off water V temperature (TI-148, 146, 132, 125) has decreased to 235 F
- 2) Establish contrunicatior.s between control room and the 100' Aux Bldg Pent Area near the RCP seal water injection flow control valves CVCS-8369A, B, C & D NOTE: Monitor RCP Seal Inj Flow No. I seal leak off temperature and lower RCP bearing temperature. Reduce each respective RCP bearing temperature at a maximum rate of 1*F per minute until bearing temperature is less than 225*F, then normal seal injection flow can be established.
- 3) Crack open CVCS-8369A, B, C and D one at a time
, DC0407 451V
l NUMBER EP E-3 ! DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 ) DATE 3/8/85 i PAGE 46 0F 47 TITLE STEAM GENERATOR TUBE RUPTURE h APPENDIX R (CONTINUED) ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. AFTER RCP Seal Cooldown - VERIFY Normal RCP Cooling Alignment:
- a. Verify CCW a. IF CCW NOT aligned to RCPs TREN ensure Phase B Isolation e FCV-355 - OPEN CCW to RCP oil is reset and manually clrs, therm BAR & SUP CLRS open CCW valves.
e FCV-357 - OPEN CCW from RCP therm bar. OC e FCV-363 - OPEN CCW from RCP oil clrs 7 sup clrs, OC e FCV-749 - OPEN CCW from RCP oil cirs & sup clrs IC e FCV-750 - OPEN CCW from RCP therm bar IC
- b. Verify RCP sol injecticn flew to b. ADJUST charging flow and each RCP - 8 (6 to 12) GPM HCV *.42 to maintain 8 (6 to
- 12) gpm to each RCP.
- 4. REFER To Step 34 - CHECK If RCP Seal IF seal return is NOT desired, Return Flow Should Be Established - THEN return to procedure step in In This Procedure effect.
O DC0407 461V
NUMBER EP E-3 otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 l l PAGE 47 0F 47 T6TLE STEAM GENERATOR TUBE RUPTURE APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman proceed as follows:
- a. Designate this event an Alert. Notify plant staff and response organizations required for this classification by Emergency Procedure G-2 " Establishment of On-Site Organization" and Emergency Procedure G-3 " Notification of Off-Site Organization" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation."
- b. Designate this event a Site Area Emergency if steam generator tube rupture coincides with a loss of off-site power indicated by the inability to restore power to the l l non-vital 12KV and 4KV busses (D and E). Notify plant staff and response organizations required by EP G-2 and EP G-3 in accordance with EP G-1.
- c. If the primary to secondary leakage is estimated at >50 gpm with fuel damage evident from a gross faileo fuel monitor alarm or primary sample, designate this event a Site Area Emercency.
- d. In the event inadequate core cooling is verified per Critical Safety Function Status Trees, reclassify this event as a General Emergency. Notify plant staff and response organizations required by EP G-2 and EP G-3 in accordance with EP G-1.
I I DC04L7 471V i i
FOLD 0VT FOR EP E-3 PROCEDURES ISTRATIVE FUNCTIONS l
- 1. Notify STA and monitor Critical Safety Function Status Trees and SPDS
- 2. Refer to Appendix Z CONDARY INTEGRITY CRITERIA l Go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1, if any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, unless needed for RCS cooldown.
ILD LEG RECIRCULATION SWITCHOVER CRITERION 1 Go to E-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1 if RWST level decreases to less than 33*. W SUPPLY SWITCH 0VER CRITERION I Switch to alternate AFW water supply if CST level decreases to less
--than 10'J. Refer to E-2.1 ALTERNATE AUXILIARY FEEDWATER SUPPLIES.
VERSE CONTAlhMENT CRITERIA l Containment pressure - GREATER THAN 3 PSIG
- OR -
Containment Radiation Ocse Rate 105R/hr
- OR -
Containment Radiation Dose 106R \~_j DC0407 48II
- .A _ - , - - - - - -
O' I I l l l l l l O I
)
I we O l 1 1
- - - - - - - - - - - - ..- . . _ _ _ _ _ __ - _ _ - - - - - - ~ - - - . . _. . ___ __ ___,__ __ __ __ __ _
NUMBER EP ECA-0.0 l 3GW3 Pacific Gas and Electric Company REVISION 0 DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 31 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE ~ LOSS OF ALL AC POWER TITLE IMPORTANT APPROVED h'. C 5 45 To PLANTMANAGERg DATE SAFETY SCOPE This procedure provides actions to respond to a complete loss of ALL AC power. This procedure and changes thereto requires PSRC review. SYMPTOMS OR ENTRY CONDITIONS
- 1. Loss of All AC Power is indicated by all main and emergency 4 kV busses being de-energized.
- 2. This procedure is entered from E-0, REACTOR TRIP OR SAFETY INJECTION, Step 3, on the irdication that all busses are de-energized.
l O l DC0404 1111
NUMBER EP ECA_0.0 1 AND 2 otAsLO CANYON POWER PLANT UNIT NO(S) REVIS10N 0 DATE 3/7/85 PAGE 2 0F 31 ygg LOSS OF ALL AC POWER ACTION /EX CTED RESPONSE RESPONSE NOT OBTAINED CAUTION: If offsite power is lost after SI reset, manual action will be required to restart some safeguards equipment. If in Recirculation Mode charging pumps should be held in the STOP/ RESET position to prevent Auto-Restart until the RHR pumps are restarted. Refer to Appendix A for guidance if this condition occurs. t0TE: e IMMEDIATE ACTION steps are designated by circled steps. e CSF Status Trees should be monitored for information only. FRs should not be implemented. VERIFY Reactor Trip: Manually or locally trip reactor. e Reactor trip and bypass breakers
- OPEN (VB2) e Neutron flux - DECREASING (CC1)
VERIFY Turbine Trip: Manually trip turbine. O (VB2 Bistable Lignts/CC3)
- a. All turbine stop vivs - CLOSED IF Turbine will NOT trip, TiiEN close MSIVs and bypass vivs. (VB3) l O
l DC0404 2111 1
NUMBER EP ECA-0.0 OlABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION O DATE '3/7/85 { s PAGE 3 0F 31 TITLE. LOSS OF ALL AC POWER ACTION /EX CTED RESPONSE RESPONSE NOT OBTAlfED hVERIFYRCSIsIsolated: (VB2)
- a. PZR PORVS - CLOSED a. IF- RCS pressure less than 2335 psig (VB2),
THEN manually close PORVs.
- b. Letdown isolated. b. Manually close valves.
e 8149A, B, and C - CLOSED
-OR-e LCV 459 and 460 - CLOSED e c. Excess letdcwn isolation valves - c. Manually close valves.
CLOSED e 8166 - CLOSEC _ OR - e 8167 - CLOSED
- d. 8141A, B, C, D selected to d. Manually position viv control l Closed, RCP *1 seal ret isc vivs switch to closed.
l i 1 I l O l DC0404 3III
NUMBER EP ECA-0.0 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 LOSS OF ALL AC POWER Tite ACTION /EXECTED RESPONSE RESPONSE NOT OBTAINED IF AFW flow NOT established, 04.VERIF7TotalAFWFlow-GREATER TRAT 460 GPM: (VB3) TREN at VB3 and/or locally perform the following as necessa ry:
- 1) Open FCV-95.
- 2) Open FCV-37 and FCV-38.
- 3) Open as necessary:
Discharge header vivs LCV-106, 107, 108 & 109.
- 4) Locally reset TD AFW purrp trip throttle viv.
(Refer to OP D-1:IV TD AFW pp - RESTART OR MAKE AVAILABLE AFTER OVERSPEED TRIP)
- 5) Locally verify TD AFW pp valve alignment. (Refer to OP D-1:II AFS -
ALIGNMENT VERIFICATION FOR PLANT STARTUP) O DC0404 4III
NUMBER EP ECA-0.0 OlABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 n DATE 3/7/85 (j PAGE 5 0F 31 7,7 2 LOSS OF ALL AC POWER ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. TRY To Restore Power To Any Vital l 4KV Bus: (VB4)
- a. Start any emergency diesel a. Start any emergency diesel generator generator manually at local station.
- 1) IF the emergency diesel generator will NOT start, THEN refer to OP J.6, DIESEL GENERATOR -
MAKE AVAILABLE, to verify system lineup.
- b. Verify automatic loading of the b. Manually load safeguards
% 4KV vital busses (refer to equipment on the 4KV vital Appendix Al busses. (Refer to Appendix A.)
F I F, the emergency diesel generator can NOT be loaded, THEN continue attempts to energize the 4KV Vital Buses from the diesel or any available power supply:
- 1) Reset SI if actuated.
- 2) If the 500KV system is available (refer to OP J-2, TO BACK FEED UNI" AUXILIARIES FROM THE 500KV SYSTEM).
- 3) If the other onit 12 KV startup bus is energized, close crosstie breaker (52-VU-11).
THIS STEP CONTINUED ON NEXT PAGE DC0404 5111
NUMBER EP ECA-0.0 , DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 i DATE 3/7/85 PAGE 6 0F 31 TITLE. LOSS OF ALL AC POWER ACTION / EXPECTED ESPONSE RESPONSE NOT OBTAINED I
- c. Check 4KV Vital Busses - AT LEAST c. Continue attempts to energize l ONE ENERGIZED a 4KV Vital Bus, l Continue with Step 6. l OBSERVE THE CAUTIONS PRIOR TO STEP 6.
- d. Check 4KV Vital Busses - AT LEAST d. Go to Step 24 TWO ENERGIZED
- e. Refer to appendix R to restore RCP seal cooling
- AND -
Return to procedure and step in effect O O CC0404 61!!
NUMBER EP ECA-0.0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 g t' ATE 3/7/85 g PAGE 7 0F 31 TITLE . LOSS OF ALL AC POWER ACTION / EXPECTED RESFONSE RESPONSE NOT OBTAINED CAUTION: e When power is restored to any 4KV Vital Bus, go to Step 24. e If an SI signal exists or if SI is actuated prior to restoring power, reset the SI signal to permit manual loading of 4KV Vital Bus.
- 6. ISOLATE Safeguards Loads From The Vital Busses:
- a. Open or check open the breakers and open breaker DC control power to the following loads:
CC pp No. 1 SI pp No. 1 p CCW pp No. 1 ASW pp No. 1 AFW pp No. 3 CC pp lio. 2 RHR No. 1 CCW pp ho. 2 ASW pp No. 2 Cor.t Spray pp No. 1 CC pp No. 3 SI pp to. 2 RHR pp No. 2 CCW pp No. 3 AFW pp No. 2 Cont Spray pp No. 2
- b. Maintain communication between the 4KV Vital bus switchgear and the control room
- c. Select all CFCUs to LOW Speed (VB1)
O DC0404 7III ;
NUMBER EP ECA-0.0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 PAGE 8 0F 31 - 7,7 a LOSS OF ALL AC POWER ACTION /EX CTED RESPONSE RESPONSE NOT OBTAINED
- 7. DISPATCH Personnel To Locally Restore AC Power, (Implement OP J-6A:I, 4160 Volt SYSTEM - MAKE AVAILABLE)
- 8. DISPATCH Personnel To Locally Close Valves To Isolate RCP Seals:
- a. Close 8100, RCP seal water return stop viv OC (VB2)
- b. Close CVCS-8369A, B, C & 0, RCP seal inj iso vivs OC (10')',
GE-127* to 137 )
- c. Close FCV-357, RCP therm bar CCW return iso viv OC (100', GE-166 )
- 9. ISOLATE The Hotwell From The Concensate Storage Tank:
(VB3)
- a. Close LCV-8 a. Close CND-1-507 (hotwell makeup iso 85' turbine bldg SE of main condense U-1; 85' turb bldg NE of condenser,U-2).
- 10. CHECK Steam Generator Isolation: Manually close vivs.
- a. MSIVs - CLOSED -
IF valves can NOT be (VB3) manually closed, THEN locally close vlvs.
- b. MSIV bypass valves - CLOSED (VB3)
- c. Blowdown iso valves OC - CLOSED (VB3)
O DC0404 8I11 l
\
NUMBER EP ECA-0.0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 i DATE 3/7/85 PAGE 9 0F 31 7,y a LOSS OF ALL AC POWER ; ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: A faulted or ruptured steam generator that is isolated should remain isolated. Steam supply to the turbine-driven AFW pump must be maintained from at least one steam generator.
- 11. CHECK If SGs Are Not Faulted:
(VB3)
- a. Check pressures in all SGs a. Isolate faulted SG(s):
e NO SG PRESSURE DECREASING IN AN e Isolate AFW flow. UNCONTROLLED MANNER e Close steam supply viv to e NO SG COMPLETELY DEPRESSURIZED TD AFW pp. e Verify 101 steam dump viv(s) closed on faulted g SG(s). IF NOT, TiiEN manually close.
- 12. CHECK SG Tubes Are Not Ruotured: Try to identify ruptured SG(s). Continue with Step 13 e Steanline radiation PK 11-18 while checking for ruptured (RM-71,72,73,74)- NOT IN ALARM SG(s).
e SJAE Radiation (R-15) - NOT IN - IF a ruptured SG(s) is ALARM identified, isclate the ruptured SG(s): e SG blowdown radiation (R-19) - NOT IN ALARM e Isolate AFW flow; e Close steam supply valve to TD AFW pump; e WHEN SG pressure is less than 1035 psig (VB3). THEN verify SG 10k Steam Dunp closed.
) IF NOT, TiIEN manually close.
l I
- DC0404 9111 l
l NUMBER EP ECA-0.0 1 AND 2 otABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 PAGE 10 0F 31 LOSS OF ALL AC POWER tit a ACTION / EXPECTED RESPONSE ESR)NSE NOT OBTAINED
- 13. CHECK Intact SG Levels:
(VB3)
- a. Narrow Range Level a. Maintain maximum AFW flow ,
GREATERTHAN4%[20%) until narrow range level is greater than 4%[20%] in at least one SG.
- b. Locally control AFW Flow to b. IF- Narrow Range Level in maintain NR SG Level between any SG(s) continues to 4t[201]and33% increase in an uncontrolled manner, THEN isolate ruptured SG(s):
e Isolate AFW flow; e Close steam supply valve to TD AFW pp. e WHEN SG pressure is less thar. 1035 psig, THEN verify SG 10% steam dump Closed. IF NOT, TiiEN manually clcse. O DC0404 10!II
NUMBER EP ECA-0.0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85
*O- PAGE 11 0F 31 mg. LOSS OF ALL AC POWER ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 14. CHECK DC Bus Loads:
- a. Check the following:
e DC Air Side Seal Oil Pump - RUNNING e Turb. Gen Emerg DC Brg oil pump - RUNNING if necessary e MFP DC oil pumps - RUNNING if necessa ry
- b. Monitor voltage and current on 125 VDC busses
- c. Consider shedding any unnecessary S DC loads (O e DC oil pps after equipment coast down e DC Air side Seal oil pp after Main Generator Degassification
- 15. CHECK CST Level - GREATER THAN 10L Continue to monitor CST (VB5) level.
WHEN CST level is less ther. 10%, THEN switch to alternate AFW pp water supply. (Refer to E-2.1, ALTERNATE AFW SUPPLIES.) O i l l DC0404 11111
NUMBER I P ECA-0.0 1 AND 2 REVISION 0 OIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/7/85 7gg LOSS OF ALL AC POWER ACTION /EXRCTED ESPONSE ESRJNSE NOT OBTAINED CAUTION: SG pressures should not be decreased to less than 160 psig to prevent injection of accumulator nitrogen into the RCS. N)TE: e The SGs should be depressurized at maximum rate to minimize RCS inventory loss due to anticipated RCP seal failures. e PZR level may be lost and reactor vessel upper head voiding may occur due to depressurization of SGs. Depressurization SHOULD NOT be stopped to prevent these occurrences.
- 16. DEPRESSURIZE Intact Steam Generators To 260 PSIG To Inject SI Accumulators:
- a. Check SG NR levels - GREATER THAN a. Perform the following:
4%[20%] IN AT LEAST ONE SG (VB3)
- 1) Maintain maximum AFW ficw until NR Level greater than 4%[20%] in at least one SG.
- 2) Continue with Step 17 and WHEN Narrow Range Level is greater than 4t[20%]
in at least cne SG, THEN do Steps 16b, c, d and e. THIS STEP CONTINUED ON NEXT PAGE I j DC0404 12III ! 1
NUMBER EP ECA-0.0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 O 7gg LOSS OF ALL AC POWER e^ce 13 or 31 ACTION /EXPEQtv RESPONSE RESPONSE NOT OBTAINED
- b. Manually dump steam at maximum b. Locally dump steam using 10%
rate using SG 10% steam dumps steam dumps. (VB3)
- c. Check RCS cold leg temperatures - c. Perform the following:
GREATER THAN 265 F (VB2)
- 1) Control SG 10% Steam Dumps to stop SG depressurization.
- 2) Continue with Step 17.
- d. Check SG pressures - LESS THAN d. Continue with Step 17 and 260 PSIG (VB3)
WHEN SG pressures decreased to less than 260 psig,
- e. Manually control SG 101- steam e. Locally control SG 10*; steam dumps at 260 osig dumps to maintain SG pressures at 260 psig.
O DC0404 131II
- . _ . - _ _ _ - - . . _ _ _ . _ _ _ - ~ . _ . - , - -
L
!! UMBER EP ECA-0.0 l 1 AND 2 REVISION 0 l OlABLO CANYON POWER PLANT UNIT NO(S)
DATE 3/7/85 PAGE 14 0F 31 7,7 a LOSS OF ALL AC POWER ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED Control SG 10% steam dumps to
- 17. CHECK Reactor Subcritical:
STOP SG depressurization and e IR channels - ZERO OR NEGATIVE aTTow RCS to heat up. STARTUP RATE e SR channels - ZERO OR NEGATIVE STARTUP RATE NOTE: Depressurization of SGs will result in SI actuation. SI should be reset to permit manual loading of equipment on the 4KV Vital Busses when they are returned to service.
- 18. CHECK SI Sicral Status:
- a. SI - HAS BEEN ACTUATED a. Go to Step 22 and (PK~08-21)
WHEN SI actuated. THEE do Steps 18b, 19, 20 and ____ '.......___ lh
- b. Reset SI if necessary (VB1)
- 19. VERIFY Containment Isolation Phase A:
(Monitor Lignt Sox 5)
- a. Phase A - Actuated a. Manually actuate Phase A Isc.
e Red Activated Light - ON e White Status Lights - CFF
- b. Phase A Vivs - CLOSED b. Manually close valves IF
--~
vivs can NOT be manually closed, THEN locally close the OC vivs. ee O DC0404 14III
l NUMBER EP ECA-0.0 DIABLO CANYON POWER PL NT UNIT NO(S) I AND 2 REVISION 0 p DATE 3/7/85 PAGE 15 0F 31 () LOSS OF ALL AC PodR l 7,7a l l ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 20. VERIFY Containment Ventilation Manually close CVI vivs Isolation: (Monitor Light Box B)
IF CVI vivs can NOT be e Red Activated Light - ON manually closed, THEN locally close CVI vivs. e White Status Lights - 0FF ----------------
- 21. CHECK Containment Pressure - Perform the following:
HAS REMAlt4ED LESS THAN 22 PSIG (PAM 1) a) Verify containment spray signal actuated. (VB1) IF NOT, TIIEN manually actuate. b) Verify containment isolation Phase B valves closed. (Monitor light Box D) IF NOT, TREN manually close vlvs. IF vivs can NOT be manually closed, THEN locally close vivs. c) Reset containment spray signal. (VB1) U i DC0404 15111 i
NUMBER EP ECA-0.0 DIABLO CANYON POWER PLANT UNIT NO(S) i AND 2 REVISION 0 DATE 3/7/85 LOSS OF ALL AC POWER TIT E ACTION / EXPECTED RESPONSE RESRWSE NOT OBTAINED
- 22. CHECK Containment Radiation Manually actuate containment iso Phase A. Manually e R_11 Cnmt Particulate <2.6 x 105 close Phase A and CVI vlvs cpm (RMS CAB II) as necessary.
e R30/R31 - NORMAL - IF vlvs can NOT be manually closed, THEN locally close vivs.
- 23. CHECK If 4KV Vital AC Power Restored: (VB4)
- a. Verify at least one 4KV Vital Bus a. Continue to control RCS energized conditions and monitor plant status:
- 1) Check status of local actions:
e AC power restoration O e RCP seal isolation e DC power supply
- 2) Check status of auxiliary boration systems:
a) BIT temperature greater than 145*F (Aux Cont Bd data logger) b) BAST temperature greater than 145*F THIS STEP CONTINUED ON NEXT PAGE O CC0404 16!!!
NUMBER EP ECA-0.0 otA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 p sj DATE PAGE 3/7/85 17 0F 31 ma LOSS OF ALL AC POWER I ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED c) If auxiliary boration systems temperature less than 145 F, consider methods of reducing boron concentration: (1) Draining tanks to the auxiliary building sump. (2) Diluting by adding water from the primary water tanks via a portable diesel powered fire pp.
- 3) Check status of spent fuel O pool cooling:
a) Spent fuel pool level greater than 23 feet above irradiated fuel . b) IF spent fuel pool level less thar o
, feet above irradiated fuel, THEN dispatch personnel to fill spent fuel pool via the fire water system hose l reel in the Fuel <
Handling Building. !
- 4) Return to Step 15. l l
- 24. STABILIZE SG Pressures:
- a. Manually control SG 101; stean Locally control SG 100 steam I dumps dumps.
c) l DC0404 17III l l
NUMBER EP ECA-0.0 1 AND 2 DIABLO CANYON POWER Pt. ANT UNIT NO(S) REVISION 0 . DATE 3/7/85 j PAGE 18 0F 31 7,7g LOSS OF ALL AC POWER ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: The loads placed on the energized 4KV vital bus should NOT exceed the capacity of the power source.
- 25. VERIFY Following Equipment Loaded Manually load equipment as On 4KV Vital Bus: (Refer to necessa ry.
Appendix X for Diesel Loading Curve) e 480 volt busses e Battery chargers e Emergency Lighting e Communications
- 26. CHECK ECCS Capabilities _:
- a. Verify at least two 4KV Vital a. IF- only ONE 4KV vital bus busses - ENERGIZED energized, THEN perform Appendix X to crosstie two 4KV vital busses from the operable diesel, and Continue with Step 27.
04 O DC0404 1811! I
NUMBER EP ECA-0.0 1 AND 2 DIAaLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 0 7,7g . LOSS OF ALL AC POWER PAGE 19 0F 31 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 27. SELECT Recovery Procedure: (VB2)
- a. Check RCS subcooling monitor a. Go to ECA-0.2, LOSS OF ALL AC greater than 20*F POWER REC 0VERY WITH SI REQUIRED.
- b. Check PZR level - GREATER THAN b. Go to ECA-0.2, LOSS OF ALL AC 4%[20%] POWER REC 0VERY WITH SI REQUIRED.
- c. Check SI equiprrent . HAS NOT c. IF- SI equipment has ACTUATED UPON AC POWER actuated, RESTORATION THEN go to ECA_0.2, LOSS OF ALL AC POWER REC 0VERY WITH SI REQUIRED.
- c. Go to ECA-0.1, LOSS OF ALL AC
- POWEP PEC0VERY WITHOUT SI REQUIRED
- END -
O DC0404 19?II
NUMBER EP ECA-0.0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 PAGE 20 0F 31 TITLE. LOSS OF ALL AC POWER APPENDIX A BLACK 0UT WITH SAFETY INJECTION EMERGENCY LOADING OF VITAL BUSSES
- 1. If the vital busses regain voltage rior to resetting the safety injection signal, the vital busses w1 automatically load the vital equipment given below. Verify the equipment has been loaded by observing breaker lights on the control board.
- 2. If the vital busses regain voltage after the safety injection signal has been reset, load or verify loaded the equipment given below onto the vital busses manually, as required. Allow approximately 4 seconds between loading of each piece of equipment onto a given vital bus. Load or verify that the CFCU are running in Low Speed. A CCW pump and ASW pump (if available) should be started first.
VITAL BUS F VITAL BUS G VITAL BUS H U-l (D/G 1-3) U-1 (D/G No. 2) U-1 (D/G No. 1) U-2 (D/G l-3) U-2 (D/G No. 1) U-2 (D/G No. 2) MCC F *MCC G *MCC H RHR Pp No. 1 SI Pp No.1 *CFCU No. 3 SI Pp No. 2
*CFCU No. 2 *CFCU No. 5 RHR Pp Nc. 2
*CFCU No. 1 *CCW Pp No. 2 *CFCU No. 4
*CCW Pp No. 1 *ASW Pp No. 2 *CCW Pp No. 3
*ASW Pp No. 1 *AFh Pp No. 2
*AFW Pp No. 3 NOTE: CCPs should be restarted LAST. Seal injection should be isol6 tea prior to CCP restart it RCP seal temp is >225 F.
VITAL BUS F VITAL BUS G CC Pp No. 1 CC Pp No. 2
- Loading of Vital Bus when NO Safety Injection.
O DC0404 20III l l .
NUMBER EP ECA-0.0 l OIABLO CANYON POWER P! ANT UNIT NO(S) 1 AND 2 REVISION 0 i DATE 3/7/85 pd PAGE 21 0F 31 7,7a LOSS OF ALL AC POWER APPENDIX R IF RCP SEAL RETURNS OR LOWER RADIAL BEARING TEMP HAS BEEN OR IS 2225 F PERFORM THE FOLLOWING: ACTION / EXPECTED RESRESE RESPONSE NOT OBTAINED
- 1. CHECK RCP Seal Isolation Status:
- a. Verify seal injection iso v1vs a. IF- valves open or position OC - CLOSED not known, THEN check centrifugal CVCS-8369A, B, C & D - CLOSED RCP charging pump status:
Seal Water Containnent Isol Vivs (100' Aux Bldg Pent Area GE - IF pump running, 127 to 137') 1) TiiEN return to Step 33 CHECK RCP COOLING - NORMAL. IF pump NOT running, q 2) TIIEN manuaTf7 or locally b close seal injection vlvs 0C
- b. FCV-357 - CLOSED RCP therm bar b. IF valve is open or CCW return isc viv OC (100' position not known, Aux Bldg Pent Area GE-166*) (VB1) THEN check CCW pump status:
- 1) IF a pump is running, TiiEN go to Step 1B Appendix R.
- 2) IF pump NOT running, TIIEN manuaTTF or locally close FCV-357.
IF FCV-357 can NOT be closed, THEN manually close FCV-750, CCW return viv IC. O v DC0404 21111
NUMBER EP ECA-0.0 o,Asto CANYON POWER Pt ANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/65 PAGE 22 0F 31 TITLE LOSS OF ALL AC POWER ACTION / EXPECTED RESPONSF. RESPONSE NOT OBTAINED CAUTION: e RCP thermal barrier cooling should be established slowly to minimize potential introduction of steam into the CCW system. e RCP seal injection should be established slowly to minimize RCP thermal stresses and potential seal failures, e As part of subsequent recovery actions, RCPs should not be started prior to a status evaluation, unless responding to Inadequate Core Cooling FR-C.1. . 1 1
- 2. ESTABLISH RCP Seal Cooling:
- a. Establish CCW flow to RCP thermal barriers (100' Aux Bldg Pent Area GE-166')
- 1) Establish communications between the control room and 100' Aux Bldg Pent Area near llh FCV-357 CCW from RCP Inerm Bar OC.
- 2) Mcniter RCP lower bearing temperature (TI-155, 154, 153, 152 on VB1 and T0417A, T0437A, T0457A and T0477 on the P250)
- 3) Check FCV-357 - CLOSED RCP 3) Close FCV-357 Therm Bar CCW Return Iso Viv OC (VB1) - OR -
CCW-267.
- 4) Checx FCV-750 - OPEN RCP Therm 4) IF- FCV-357 or CCW-267 Bar CCW Return Iso Viv IC CLOSED (V81) THEN open FCV-750.
THIS STEP CONTINUED ON NEXT PAGE O DC0404 22III
NUMBER EP ECA-0.0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 /] DATE 3/7/85 V PAGE 23 0F 31 mLE LOSS OF ALL AC POWER ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Monitor flow on FI-90 (Locally at TCV-357) and temperature on TI-1004 (locally at FCV-357). Initiate flow to the thermal barrier slowly reducing lower bearing temperature (TI 155, 154, 153, 152 on VB2 and T0417A, T0437A, T0457A, T0477A on the P250 at a maximum rate of 1 F per minute until full thermal barrier flow is returned to normal. Some local boiling may occur in the CCW lines giving a closed signal to FCV-357.
- 5) Locally crack open FCV-357 or CCW-267
- b. Establish Seal Injection Flow to RCPs (100' Aux Bldg Pent Area GE-127' - 137')
- 1) Wait until seal leak off water temperature (TI-148,146,132, Q
V 125) has decreased to 235*F
- 2) Establish communications between control room and the 100' Aux Bldg Pent Area near the RCP seal water injection flow centrol valves CVCS-8369A, B, C & D TOTE: Monitor RCP Seal Inj Flow No. 1 seal leak off temperature and lower RCP bearing temperature. Reduce each respective RCP bearing tenperature at a maximum rate of 1 F per minute until bearing tenperature is less than 225 F, then normal seal injection flow can be established.
- 3) Crack open CVCS-8369A, 8, C and D one at a time O
v DC0404 231:1
NUMBER EP ECA-0.0 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 TITLE LOSS OF ALL AC POWER ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. AFTER RCP Seal Cooldown - VERIFY hormal RCP Cooling Alignment:
- a. Verify CCW (VB1) a. IF CCW NOT aligned to RCPs TREN ensure Phase B Isolation e FCV-355 - OPEN CCW to RCP oil is reset and manually CLRS, therm BAR & SUP CLRS open CCW valvec.
e FCV-357 - OPEN CCW from RCP THERM BAR OC e FCV-363 - OPEN CCW from RCP OIL. CLRS & SUP CLRS OC e FCV-749 - OPEN CCW from RCP OIL CLRS & SUP CLRS IC e FCV-750 - OPEN CCW from RCP THERM BAR IC - OPEN
- b. Verify RCP seal injection flow to b. ADJUST FCV-128 cent chg Pps each RCP - AT 8 (6 to 12) GPM flow control viv/PD Charg Pp (VB2) speed and RCP seal inj back press viv and HCV-142 to naintain 6 tc 12 gpm to each RCP.
C CC0404 24III
NUMBER EP ECA-0.0 otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 l l PAGE 25 0F 31 TITLE. LOSS OF ALL AC POWER APPENDIX X CROSSTIE OF VITAL BUSSES SCOPE Implementation of this appendix requires the plant superintendent or his designate's approval. This appendix should be performed if only one vital bus is energized (from its associated diesel generator). Since safeguard trains would be cross connected and redundancy jeopardized. If two vital busses are energized, enough equipment would be available to establish one train of ESF equipment. DISCUSSION As a general guideline, in this situation several options may be available depending on plant conditions and RCS status. If SI is not recuired, the shift foreman may elect to stay in a hot shutdown status awaiting restoration of offsite power or he may decide to cooldown. If SI is required, a minimum of one ECCS flow path must be l l established. The type of ECCS flow path desired would depend on RCS conditions. PRECAUTIONS AND LIMITATIONS
- 1. Some equipment may have to be operated on a continuous basis anc sone or an "as needed" basis. Existing conditions will determine which equipment is needed (plant cooldown, SI, etc.).
- 2. The maximum capacity of the diesel generator should not be exceeded. Figure 1 identifies the diesel generator load limits.
Table 1 provides loads for various vital 4KV and 48] volt equipment. STP M-9M also supplies specific loads on all 480 volt vital equipment.
- 3. Start only one piece of equipment at a time since starting current may cause bus failure (0C) when the diesel is near maximum load.
PROCEDURE
- 1. Obtain permission from the Plant Superintendent or his designate.
l l DC0404 25III
NUMBER EP ECA-0.0 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 rirls. LOSS OF ALL AC POWER APPENDIX X (continued)
- 2. Reset SI (if applicable) so that the affected bus will not try to auto load when the bus becomes energized. (VB1)
- 3. Cutout the AUTO Transfer FCO's for 4KV busses and 12KV busses.
(VB4/5) NOTE: e If the D/G associated with the inoperable bus is running, it must be shutdown to permit the Auto Transfer Relay to be reset. NOTE: e The Auto Transfer Reset will NOT reset and the BLUE light will NOT de-energized for theTbus if the 13 diesel generator is operating on the other unit. 4 Depress all AUTO Transfer Reset Push Buttons.
- 5. This step is only used to energize the 4KV F vital bus when the 13 diesel generator is operating on the other unit.
- a. Dispatch an Operator to the 4KV Bus F Switchgear Cubicle 7, to overvoltage relay 59HFG1/59HFG2
- 1) Remove the cover
- 2) Pull dcwn on the 2 " RED" handled switches (Terminal 5 and 10).
- b. THEN at the Main Ccntrol Board, depress the Auto Transfer Reset Push Button for the 4KV F vital bus. Notice the
" BLUE" light goes "OUT".
- 6. OFEN or verify OPEN all vital bus 4KV auxiliary feeder breakers, 52-HH-13, 52-HG-13 and 52-HF-13.
- 7. OPEN or verify OPEN all vital bus 4KV startup feeder breakers, 52-HH-14, 52-HG-14 and 52-HF-14.
- 8. OPEN or verify 0 PEN startup feeder breaker 52-HG-15 to the vital busses F, G and H.
- 9. OPEN of verify OPEN the 4KV to 480V bus feeder breaker,
- a. If bus F is to be re-energized OPEN 52-HF-10.
O l OC0404 26III
NUMBER EP ECA-0.0 DiAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 (] DATE 3/7/85 t/ PAGE 27 0F 31 Tai LOSS OF ALL AC POWER
=
APPENDIX X (continued)
- b. If bus G is to be re-energized OPEN 52-HG-10.
- c. If bus H is to be re-energized OPEN 52-HH-10.
- 10. CLOSE the 4KV startup feeder breaker for the bus that will be supplying power to the inoperable bus.
OPERATING D/G UNIT 1 CLOSE UNIT 2 CLOSE No. 1 52-HH-14 52-HG-14 No. 2 52-HG-14 52-HH-14 No. 3 52-HF-14 52-HF-14 CAUTICG: If the diesel generator appears unstable during the performance of Step 11 or at any titre beyond this point in p (j the procedure, immediately open startup feeder breaker for the inoperable bus to separate the diesel from the inoperable bus,
- 11. CLOSE the 4KV startup feeder breaker for the inoperable bus,
- a. If bus F is to be re-energized CLOSE 52-HF-14
- b. If bus G is to be re-energized CLOSE 52-HG-14
- c. If bus H is tc be re-energized CLOSE 52-HH-14 CAUTION: Station an operator at the VB4 to monitor the diesel generator. If an SI should occur, immediately open the 4KV startup feeder breaker for the bus with the operable diesel generator to prevent overloading the operable diesel generator when the SI loads sequence on the bus.
- 12. If Step 5 was used to energize the 4KV F vital bus when the 1-3 diesel generator is supplying the other unit, the Operator at the 4KV Bus F Switchgear may now return the 2 " RED" handled switches to their normal position and replace the cover.
O DC0404 27III
NUMBER EP ECA-0.0 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 tit m LOSS OF ALL AC POWER APPENDIX X (continued)
- 13. Operate only the equipment as directed in the appropriate recovery procedure. Evaluate the load on the ciesel generator prior to energizing each additional load to ensure its capacity limit is not exceeded (figure 1). Refer to table 1 to identify expected loads for each piece of equipment. If the diesel overloads, it may only be necessary to trip the last load added rather than the entire bus.
O O DC0404 28III l l
NUMBER EP ECA-0'0 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 lI DATE 3/7/85 V PAGE 29 0F 31 TITLE: LOSS OF ALL AC POWER APPENDIX X (continued) etMERa?ot E V. %
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r l's,a t 1 1 i-8.52s e6 - - 1 FIGURE ONE: DIESEL GENERATOR LOAD LIMITS
]_
DC0404 291TI
HUMBER EP ECA-0.0 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 PAGE 30 0F 31 7,7 g LOSS OF ALL AC POWER APPENDIX X (Continued) TABLE 1: EQUIPMENT LOADS Rating Max Demand in Kw Load Sty (Each) Bus F Bus G Bus H
- 1. Centrifugal Charging Pumps 2 600Hp 495 507 ---
- 2. Safety Injection Pumps 2 400Hp 303 --- 303
- 3. Lor,tainnert Spray Pumps 2 400Hp ---
350 350 4 Residual Heat Rencvil Pumps 2 400Hp --- 325 333
- 5. Containment Fan Cooler 5
- a. Slow Speed 100Hp 73 ea 73 ea 73 ea
- b. Fast Speed 300Hp 220 ea 220 ea 220 ea
- 6. Component Cooling Water Pumps 3 400Hp 314 314 314
- 7. Auxiliary Saltwater Pumps 2 400Hp 321 321 ---
- 8. Auxiliary Feedwater Pumps 2 600Hp 410 --- 410
- 9. Fire Pumps 2 200Hp 150 --- 150
- 10. Pressurizer Heaters
- 2 483/207 483/207
- 11. Remaining 460 volt loads are - --- --- --- ---
extensive (Refer to STP M-9M for a specific listing) O I DC0404 30lII l 1
NUMBER EP ECA-0.0 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) p DATE 3/7/85 Q 31 0F 31 PAGE 7,7 a LOSS OF ALL AC POWER APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When the emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Designate this event an Alert. Notify plant staff and response organizations required for this classification by implementing Emergency Procedure G-1 " Establishment of the On-Site Emergency Organizations" and Emergency Procedure G-3
" Notification of Off-Site Organization" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Implementation.
- b. Designate this event a Site Area Emergency if AC power cannot be restored to at least one vital bus (F, G or H) by either Diesel Generators or off-site power within 15 minutes l of the total loss. Notify plant staff and response organizatior.s required by EP G-2 and EP G-3 in accordance O
with EP G-1. l l i iO V DC0404 311II
NUMBER EP ECA-0.1
~
f@w W .m3 Pacific Gas and Electric Company REVISION 0 DATE 3/7/85 DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 23 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE ~ LOSS OF ALL AC POWER REC 0VERY TITLE WITHOUT SI REQUIRED IMPORTANT APPROVED rE TA 3 TO PLANTEANAGER,.) DATE SAFETY SCOPE This procedure provides actions to use nonnal operational systems to stabilize plant conditions following restoration of 4KV vital AC power. This procedure and changes thereto requires PSRC review. S WPTGMS DA ENTRY CONDITIONS This procecure is entered from ECA-0.0, LOSS OF ALL AC POWEk, Step 27, Os wher 4VV vital pcwer is restcred ana SI is not requirec. l l { i DC0404 IIV
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON 0 DATE 3/7/85 PAGE 2 0F 23 TITLE. LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED z ACTION / EXPECTED RESPONSE PJSPONSENOTOBTAINED CAUTION: The load placed on the energized 4KV vital busses should not exceed the capacity of the power source. NOTE: o CSF status trees should be monitored for inforuation only. FRs should not be implemented until Step 9 is complete. e The respective DC control power switch may have to be closed at the 4KV switchgear to start desired equipment.
- 1. CHICK RCp Seal Isols' ion Status:
- a. Locally verify Ci0$C a. IF
~
v&)ves open or position CVCS-8369 A, B, C 5's c ' sN i not known, water cent iso $1.s THEN check centrifugal (100', GE- 127 to 1D l charging pp status: IF pp running,
- 1) TREN go to Step 2.
IF pp NOT running,
- 2) TEEN locaTTy close seal injection vlvs 0C before starting a charging pp.
- b. Verify CLC o' % /-357,t ? thern b. IF valve is open or bar CCW rt '..n 3 viv OL (VBI) position not known, THEN check CCW pump status:
IF a pump is running,
- 1) TREN go to Step 2.
IF pp NOT running,
- 2) TEEN manuiaT1y or locally close FCV-357.
(100' GE-166") THIS STEP CONTINUED ON NEXT PAGE DC0404 211!
NUMBER EP ECA-0.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 OATE 3/7/85 Os PAGE 3 0F 23 TITLE LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED ACTION / EXPECTED RESPONSE RESPG4SE NOT OBTAINED IF
~~
FCV-357 can NOT be closed. THEN manually close FCV.750, CCW return viv, IC.
- c. Verify CLOSED 8100, RCP seal c.. Manually or locally close return stop viv OC (VBE) valve.(100',GE-103*)
- 2. CHECK Containment Isolation Phase A: Reset Containment Isolation
- NOT ACTUATED (V61) Phase A and Phase B.
- 3. MAN'JALLY Lead Followina Ecuipment Or. The Available 4KV V1tal Busses:
- a. Check instrurert air . AVAILABLE a. Establish instrument air (VB4) before continuing in p rocedure, e Open FCV-584, enmt inst air iso viv, e Establish power to anc start one air compressor and one SCW pp. Refer to Appendix N to crcsstie the diesel generators to a non-vital bus, and/or OP AP-9 LOSS OF INST AIR, if necessary.
- b. Start CCW pp(s) (VB1)
THIS STEP CONTINUED ON NEXT PAGE O \_sl DC0404 31I1 i
~ - -
DIABLO CANTON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 3/7/85 PAGE 4 0F 23 TITLE. LOSS OF ALL AC POWER REC 0VERY WITHOUT SI REQUIRED ACTION / EXPECTED RESPCt4SE RESPONSE NOT OBTAINED
- c. Aligncharging(VB2/CC2) c. Check vlv alignrrent Step 3.c.
I through 8. IF No charging pp running:
- 1) Check valve alignment and Manually or locallyVB2) vivs as necessary: (align start charging pump: (VB1)
IF
~~
VCT or BAST NOT e LCV-112 B&C - open charg pp available, suct viv from VCT (VB2) THEN establish suction from RWST: e VCT makeup control system - SET FOR AUTOMATIC CONTROL e Open 8805 A&B charg pp AND GREATER THAN RCS BORON suct from RhST. CONCENTRATION OR 2000 PPM (7 TURNS) (CC2) e Close LCV 112 B&C, charg pp suct from VCT.
- 2) Throttle to 50% HCV-142 (CC2)
- 3) Open FCV-128 (CC2)
- 4) Open 8105 and 8106 cent charg pps min flow vlvs (VB2)
- 5) Open 8146 normal charg to LP 4 cold leg viv (VB2)
- 6) Close 6147, alt charg to LP 3 ccid leg viv (VB2)
- 7) Close 8145 and 8148, charg line to PZR aux spray viv and bypass (VB2)
- 8) Open 8108 and 8107, normal l
charg to recen hx stop vivs 1 a 2 (VB2)
- 9) Start one cent charg pp (VB2) 9) Ensure CCW flow to PD
! charg pp oil coolers (FCV-355 open), j THEN start PD charg pp. THIS STEP CONTINUED ON NEXT PAGE CCC404 4III
~
l I
i l N O!ABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON R (') V DATE PAGE 3/7/d5 5 0F 23 l TITLE. LOSS OF ALL AC POWER REC 0VERY ; WITHOUT SI REQUIRED j 1 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- d. Start ASW pps (VBI)
- e. Start CFCU(s) as necessary (VBI)
- 4. ESTABLISH 60 GPM Charging Flow:
(CC2)
- a. Adjust charging flow and HCV-142 a. Cut in inst air back-up for to establish 60 GPM charging HCV.142 if necessary.
flow (CC2)
- 5. VERIFY ECCS Flow Not Recuired:
(VB2/CC2)
- a. RCS subcooling based on core exit a. Go to ECA-0.2, LOSS OF ALL AC TCs . GREATER THAh 2C'F POWER RECOVERY WITH SI REQUIRED.
- b. PZR level - GREATEP ThAh 4'4[20i] b. Control charging flow to (VB 2) maintain PZR level.
IF PZR level car NOT be maintained, THEN go to ECA-0.2, LOSS OF ALL AC POWEk REC 0VERY WITH SI REQUIRED.
- 6. CHECK P2R Level - GREATER THAN Control charging flow, as 171[40J (VB2/CC2) necessary.
/ Y DC0404 SIII
04ABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/7/85 PAGE 6 0F 23 Titte LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED g ACTION / EXPECTED RESPONSE RESPONSE __NOT OBTAINED CAljTION: e If CST level (v83) decreases to 10%, it will be necessary to switch to an alternate AFW pump water source. (Refer to E-2,1, ALTERNATE AFW SUPPLIES). e If SG NR level (VB2) decreases to less than 4%[20%] and total AFW flow is less than 460 GPM (VB3), the motor driven AFW pumps should be manually loaded on 4KV bus to supply SG's. NOTE: If motor driven AFW pump flow is not required, maintain the motor-driven AFW pumps disabled to prevent auto start until adequate power supplies are returned to service.
- 7. CHECK Intact SG Levels (VB3):
- a. NR level - GREATER THAN 4t[20%] a. Maintain total AFW flow greater than 460 GPM until NR level greater than 4%[20*] in at least one SG.
IF total AFW flow NOT greater than 460 gpm, ThEN e Verify proper valve lineup of AFW System to SG(s). e Manually load a motor drive AFW pump on the available 4KV vital bus.
- b. Control AFW flow to maintain NR levelbetween4%[20%]and33%
O DC0404 6III
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h0N DATE 3/7/85 l O' PAGE 7 0F 23 l TITLE. LOSS OF ALL AC POWER REC 0VERY j WITHOUT SI REQUIRED ACTION / EXPECTED ESPONSE RESPONSE NOT OBTAINCD NOTE: Maintain balanced 10: steam dumps to prevent steam line AP SI. i
- 8. ESTABLISH SG Pressure Control: (CC3) l
- a. Set each SG 10% steam dump valve a. Maintain SG pressure in controller to maintain existing manual or local steam dump SG pressure, and place in AUTO control and go to Step 9.
- b. Return SG 10% steam dumps control b. Maintain 10% SG dumps on to 10% controller from backup air backup air.
if necessary.
- c. Balance 10!. steam dumps to prevent steam line AP SI
- 9. ALIGN The Following Pumps Fcr Auto Start: (Vb1)
- a. SI pps
- b. RhR pps
- c. Cent Spray pps l
l l 1 O l i l DC0404 7III
NUMBER EP ECA-0.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 PAGE 8 0F 23 TITLE LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: e RCP thermal barrier cooling should be established slowly to minimize potential introduction of steam into the CCW system. o RCP seal injection should be established slowly to minimize RCP thermal stresses and potential seal failures. e As part of subsequent recovery actions, RCPs should not be started prior to a status evaluation. NOTE: FR Procedures may now be implemented as necessary.
- 10. ESTABLISH RCP Seal Cooling:
- a. Locally establish CCW flow to RCP thermal barriers (100', GE-166$)
- 1) Establish ccmmunications between the control room and 100' aux bldg pent area near FCV-357. CCW from RCP therm bar, OC
- 2) Moniter RCP lower bearing temperature (TI 155, 154, 153, 152 on VB2 and T0417A, T0437A, T0457A, T0477A on the P250)
- 3) Check CLOSED FCV-357, RCP 3) Close FCV-357 therm bar CCW return iso viv OC (VB1) - OR -
CCW-267.
- 4) Check OPEN FCV-750, RCP therm 4) IF- FCi-357 or CCW-267 bar CCW return iso viv IC CLOSED, (V61) ThEN open FCV-750.
.e
' THIS STEP CONTINUED ON NEXT PAGE gg DC0404 8III
I l DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON
^ ' '
Cs) PAGE 9 0F 23 j TITLE - LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Monitor flow on FI-90 (locally at FCV-357) and ally temperature on TI-1004 (Locat FCV-357). Initiate flow to the thermal barrier slowly reducing lower bearing temperature (TI 155,154,153,152 on VB2 and T0417A, T0437A, T0457A, T0477A on the P250) at a maximum rate of l'F per minute until full thermal barrier flow is returned to normal. Some local boiling may occur in CCW lines giving a closed signal to FCV-357.
- 5) Locally crack open FCV-357 or CCW-267
- b. Establish seal injection flow to RCPs (100', GE-127 -137')
- 1) Wait until seal leak off water temperature (TI-148, 146, 132, 125) has decreasec to 235'F O 2) Establish communications betweer cortrol roon and the area near the RCP seal water injecticr. flow control valves CVCS-8369A, B, C & D NOTE: Monitor RCP seal inj flow No.1 seal leak off temperature and lower RCP bearing temperature. Recuce each respective RCP bearing terrperature at a maximuc rate of 1 F per rrinute until bearing temperature is less than 225'F, then normal seal injection flow can be established.
- 3) Crack open CVCS-8369 A, B, C and D one at a tirre a
DC0404 9111
l N DIABLO CANYON PCWER PLANT UNIT NO(S) 1 AND 2 R ON 3/7/85 DATE TITLE. LOSS OF ALL AC PCWER RECOVERY WITHOUT SI REQUIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 11. CHECK If RCP Seal Return Flow Should i i
Be Established:
- a. Verify Open FCV-355 CCW to seal a. Go to Step 12.
water return HX (VB1)
- b. Verify #1 seal return flow less b. Close RCP #1 seal ret iso viv than 6 GPM (VB2) for effected RCP: (VB2)
RCP 1 - 8141A RCP 2 81418 RCP 3 8141C RCP 4 - 8141D IF all RCPs effectec, TiiEN 90 to Step 12. IF NOT,
.. . . S'......
- c. Open 8100 and 8112 RCP seal ret isc vivs (VB2)
O DCC404 10111
NUMBER EP ECA-0.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 C DATE 3/7/85 ( PAGE 11 0F 23 TITLE. LOSS OF ALL AC POWER REC 0VERY WITHOUT SI REQUIRED ACTION /EXECTED RESPONSE RESPONSE NOT OBTAINED
- 12. ESTABLISH Letdown:
- a. Open FCV-355, CCW hdr C iso viv IF
~~
normal letdown NOT (VB2) available, THEN establish excess Itdn as
- b. Position to 50% PCV-135, Itdn follows:
press cont viv (VB2)
- 1) Place charg pp control in
- c. Open LCV-459 ano 460, Itdn stop manual and reduce charg vivs (VB2) flow to min.
- d. Ensure 45 GPM charg flow through 2) Close 8107 and 8108, regen hx (CC2) charg hdr iso vivs.
- e. Place in auto LCV-112A, VCT lvi 3) Adjust charg to cont divert viv (\B2) maintain seal injection approx gpm (6-12) GPM.
A f. Open 8152, itdn iso viv OC (VB2) b 9. OPEN as necessary: (VB2) IF 8100 and 8112 open
- 4) TiiEN place 8143 in normal position (VCT),
e 8149A 45 GPM excess ltdn to seal e 8149B 75 GPM wtr hx or RCDT viv. e bl49C 75 GPM e IF 8100 and 8112 -
- h. Mair.tain 350 psig on PI-135 with closea, PCV-135 (VB2) THEN place 8143 in RCDT position.
- i. Adjust charging flow to maintain letdown temp LESS THAN 380*F on 5)Open: ,
TI-127(VB2/CC2) e FCV-355, CCW hdr C iso viv. e FCV-361 CCW from excess Itdn hx.
- 6) Close HCV-123 excess Itdn flow cont viv. 1 1
i .
'I l
l p THIS STEP CONTINUED ON NEXT PAGE I l l G' l
- DC0404 11111 1
l
)
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON 0 DATE 3/7/85 TITLE: LOSS OF ALL AC POWER REC 0VERY PAGE 12 0F 23 h WITHOUT SI REQUIRED ACTION / EXPECTED ESPONSE ESPONSE NOT OBTAINED
- 7) Open 8166 and 8167 excess itdn stop vivs.
- 8) Open HCV-123 as necessary to maintain:
o PZR LYL. e LESS THAN 190*F as on TI-122 excess ltdn temp.
- 13. CONTROL Charging And Letdown Flow To Maintain PZR Level Between 1h[40tj And 50% (CC2)
CAUTION: Auxiliary spray flow into the PZR shall not be initiated if the celta-T between the PZR and the spray fluid exceeds 560*F. Spray flow should not be initiated if the delta-T exceeds 320*F. NOTE: e If PZR Auxiliary spray is used it may be necessary to close normal spray PCV-455A & B and charging valves 8146 & 8147. o It may be necessary to strip some load from the vital bus on which the pressurizer emergency backup heaters are to be loaded to prevent exceeoing the maximum capability curve of the Diesel Generator of Appencix N.
- 14. ESTABLISH PZR Pressure Control:
- a. Transfer pressurizer heaters on the available 4KV vital bus and operate as necessary (CC1)
- b. Close PCV 455A & B normal spray b. Use one PZR P0kV to maintain vivs and use aux spray as RCS pressure. Go to Step 15.
necessary for pressure control OBSERVE CAUTION PRIOR TO STEP (CC2/VB2) 15. ee O DC0404 12III o
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/7/85 I I PAGE 13 0F 23 TITLE - LOSS OF ALL AC POWER REC 0VERY WITHOUT S1 REQUIRED ACT10tUEXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTI0th On natural circulation, RTD bypass temperatures and associated interlocks for Steam Dump, Feed Line Iso and High Stm Flow SI will be inaccurate.
- 15. VERIFY Natural Circulation: Increase dumping steam from intactSG(s).
e RCS su'bcooling based on core exit TC's . GREATER THAh 20 F (VB2) e SG pressures - STABLE OR DECREASihG (VB3) e RCS hot leg temperature - STABLE OR DECREAS't.G
. (VB2) e e Core exit TCs . STABLE OR DECREASING (FAMS 3/4) s RCS cold leg temp - AT SATURATION TEMPERATURE FOR SG PRESSURE (VB2)
- 16. CEELK If Source Range Detectors Shculd Ee Energized: (CCl)
- a. Check IR Flux - LESS THAN 10 10 a. Continue with Step 17.
an.ps WHEN flux is less than 10 10 amps, THEN do Steps 16b ano c.
- b. Verify SR detector - ENERGlZED b. Manually energize SR detectors.
- c. Select highest IR & SR detector i on NR-45 l
{ DC0404 13111 l l
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 fE ON DATE 3/7/85 . PAGE 14 0F 23 TITLE. LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 17. VERIFY Adequate Shutdown Margin:
- a. Sample RCS hot legs and PZR
- b. Ensure shutdown margin . ADEQUATE b. Borate as necessary.
(Implement STP R-19 SHUTDOWN MARGIN CALCULATION)
- 18. MAINTAIN Plant Conditions - STABLE e RCS pressure e PZR level e RCS temperature e Intact SG levels
- 19. VERIFY ECCS Flow Not Required: (VB2)
- a. RCS subcooling - GREATER THAN a. Go to ECA-0.2, LOSS OF ALL AC 20 F POWER REC 0VERY WITH SI REQUIRED.
- b. Pressurizer level - GREATER THAN b. Control charging flow to 4%[20$] maintain PZR level.
IF PZR level can NOT be maintained, THEN go to ECA-0.2, LOSS OF ALL AC POWER REC 0VERY WITH SI REQUIRED. i ee O DC0404 14III
NUMBER EP ECA-0.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 ()N
% PAGE 15 0F 23 TirtE: LOSS OF ALL AC POWER REC 0VERY WITHOUT SI REQUIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: Crosstie of vital and non-vital 480 volt busses shall not be accomplished without the approval of the Plant Superintendent.
- 20. TRY To Restore Power To All AC Maintain stable plant conditions Busses: (VB4/5) on emergency power.
e From 230 KV startup power - IF all sources of off-site (refer to OP J-3, 230 KV SYSTEM) power - UNAVAILABLE
. OR - THEN use Appendix N to energize e From the 500 KV system the non-vital 480 volt (refer to OP J.2, 500 KV SYSTEM) busses, with the diesel generators, if desired.
- 21. DETERMINE If Natural Circulation Coolcown Recuirec:
- a. Consult plant staff (TSC) to a. Plant is to be cool,:d down.
determine tle cesirability of remaining in Hot Stancby 1) If an RCP can be started, go to OP L-5, PLANT C00LDOWN FROM MINIMUM LOAD TO COLD SHUTDOWh
- 2) If RCPs can NOT be started, go to E-0.2, NATURAL CIRCULATION C00LDOWN.
- b. Maintain stable plant conditions NOTE: Check STP M-55 CYCLIC REVIEW, if aux spray was used.
- END .
A V DC0404 15II: 1
tiUMBER EP ECA-0.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 PAGE 16 0F 23 TITLE. LOSS OF ALL AC POWER REC 0VERY WITHOUT SI REQUIRED APPENDIX C 2600 .. . . - . .
- + _2. . :
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I 200 _ 300 400 500 600 700 ! CORE EXIT T/C TEMPERATURE ('F) O DC0404 16III
NUMBER EP ECA-0.1 i DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION O - DATE 3/7/85 J PAGE 17 0F 23 TITLE- LOSS OF ALL AC POWER REC 0VERY WITHOUT SI REQUIRED APPENDIX N ENERGIZING h0N-VITAL 480V BUSSES WITH DIESEL GENERATOR SCOPE The purpose of this procedure is to make available selected non-vital systems to lessen the restriction on recovery until normal 0FF-SITE power is restored. This procedure deals with the situation when both Units are down. All 5 emergency diesel generators may not be available. In this case one unit will be deprived of the swing diesel generator. The selected non-vital systems which are desired to be returned to service are plant instrument air, service cooling water, CRDM shroud cooler fans, Turbine Generator lift pump and turning gear drive, 230KV and 500KV switchyard. DISCUSSION This procedure deals with both units since the plant air compressors are powerec from either unit and are normally cross connected such pd that it is common to both units. Therefore, the unit to which the swing diesel 13 committec will be responsible for re-energ41ing the compressed air systerns. Unit 1 is responsible to re-energize the 230 and 500KV switchyard. Any additional loaaing will be done by Shif t Foreman evaluation for remaining diesel generators capacity. The following is a list of the minimum number of loads required for plant cooldown,
- a. 1 Centrifugal Charging - 507KW
- b. 1 Component Cooling Water -
324KW
- c. 1 Auxiliary Salt Water -
321KW
- d. 3 Centainment Fan Coolers - 660K!J
- e. 1 Auxiliary Feedwater -
429KW
- f. 1 Pressurizer Heater Group * -
483/207
- g. 2 480V Motor Control Centers -
Refer to STP M-9M for Individual Loads and Intermittent Loads
- 483KW fcr 7 Heaters; 207 for 3 Heaters o
DC0404 17III
NUMBER EP ECA-0.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE PAGE 3/7/85 18 0F 23 - g TITLE- LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED APPENDIX N (Continued) PROCEDURE
- 1. Determine which diesel generator will be used as source for the non-vital busses.
- a. On the Unit which has the 13 swing diesel generator available, transfer the maximum number of essential loads to the 4KV bus F and remove all non-essential loads from bus G.
- b. On the Unit which does not have the 13 swing diesel generator available, transfer the maximum number of essential loads to bus G and remove all non-essential loads from bus H.
- 2. Cut out the Auto Transfer FC0's for all 4KV busses and 12KV busses.
- 3. Depress all Auto Transfer Reset Push Buttons.
NOTE: The Auto Transfer Reset will NOT reset and the BLUE light will NOT de-energize for the Nus if the 13 diesel generator is operating on the other unit.
- 4. OPEN or verity OPEN all vital bus 4KV auxiliary feeder breakers, 52-HH-13, 52-HG-13 and 52-HF-13.
- 5. OPEh or verify OPEN all vital bus 4KV startup feeder breakers, 52-HH-14, 52-h6-14 anc 52-HF-14.
- 6. OPEN or verify OPEN startup power to vital busses F, G, H, 52-HG-15.
- 7. OPEN or verify OPEN auxiliary feedwater to 4KV non-vital busses D and E.
UNIT 1 UNIT 2 52-HE-2 and 52-HD-15 52-HE-14 and 52-HD-4 O DC0404 18III
,, AND 2 NUMBER EP ECA-0.1 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0
(') V DATE PAGE 3/7/85 19 0F 23 TITLE. LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED APPENDIX N (Continued)
- 8. OPEN or verify OPEN startup feeder to 4KV non-vital busses D and E.
UNI'l 1 UNIT 2 52-HE-3 and 52-HD-14 52-HE-13 and 52-HD-5
- 9. OPEN or verify OPEN startup transformer feeder breaker.
UtilT 1 UNIT 2 52-VU-14 52-VU-23 (] 10. OPEN ALL 4M feeder breakers to 480 volt busses and 4KV busses D U and E.
- 11. At the SFM discreticn cut in the FC0 to place all Diesel Generator Protection in service for the Diesel Generator selected to power the non-vital busses.
- 12. Verify all Condensate / Booster pump stand-by switches are set in FANUAL.
- 13. Verify the Nash Vacuum pump is 0FF (U-1) and the No. 2 Heater Dr ip Pump is 0FF.
- 14. CLOSE the startup feeder breaker to the vital bus,
- a. If the non-vital bus power source is UNIT 1 UNIT 2 D/6 CLOSE BREAKER D/G CLOSE BRE/KER 11 52-HH-14 22 52-HH-14 12 52-HG-14 21 52-HG-14 13 52-HF-14 13 52-HF-14 DC0404 19III l - .- . __. _ _ . _ . . . - _ _ . _ _ ,
N DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON 0 DATE 3/7/85 PAGE 20 0F 23 g ,
)
TITLE. LOSS OF ALL AC POWER REC 0VERY WITHOUT SI REQUIRED APPENDIX N (Continued) CAIJTION: If the diesel generator appears unstable during the performance of Step 15 or at any time beyond this point in the procedure, immediately OPEN 52-HG-15 to separate the diesel from the non-vital system.
- 15. CLOSE startup power to vital busses F, G, H, 52-HG-15.
NOTE: There will be short load surge on the Diesel Generator as the startup transfonner is energized.
- 16. CLOSE startup feeder to 4KV bus D.
UNIT 1 UNIT 2 52-HD-14 52-HD-5
- 17. CLOSE startup feeder to 4KV bus E.
0 UNIT 1 UNIT 2 52-HE-3 52-HE-13 O DC0404 20III
I I NUMBER EP ECA-0.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION O 1 I 1 DATE 3/7/85 D PAGE 21 0F 23 TiTts. LOSS OF ALL AC POWER REC 0VERY WITHOUT SI REQUIRED _ APPENDIX N (Continued) NOTE: Evaluate the load on the diesel generator prior to energizing each additional load to ensure its reserve capacity is not exceeded. As each additional load is added if the diesel generator overloads it may only be necessary to trip the last load added rather than tripping the entire bus.
- 18. On the Unit which has the 13 swing diesel generator carrying the F vital bus energize the following 480V busses.
- a. Energize the following non-vital busses.
UNIT 1 UNIT 2 D/G CLOSE BREAKER D/G CLOSE BREAKER ISD 52-HD-6 25D 52-HD-13 11D 52-HD-10 21D 52-HD-9
- 19. Return the instrument air system to service as per OP K-1.
- 20. Er.ergize the 500KV switchyard 4KV bus CLOSE 52-HE-7. (U-1 only)
- a. Dispatch an Operator to the 500KV switchyard to verify CLOSED or CLO'E the local 4KV bus feeder breaker in the 500VsV switchy+ c.
- b. Operater should also verify 480V bus is energized ar.d 500KV switchgear compressed air system is available.
- c. Operator shoulo verify 230KV yard 4KV bus is energized via the emergency tie cable and its compressed air system is available.
- 21. Additional loaos such as CRDM shroud coolers, turbine generator lift pump and turning gear drive may be mace available and their 480V busses energized at the discretion of the Shift Foreman, dependent on diesel generator reserve capacity.
C' J DC0404 21III f
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otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 N ON DATE 3/7/85 s PAGE 23 0F 23 TITLE. LOSS OF ALL AC POWER REC 0VERY WITHOUT SI REQUIRED APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When the emergency procedure has been activated and upon direction of the Shift Foreman, proceed as follows:
- a. Designate this event an Alert. Notify plant staff and response organizations required for this classification by implementing Emergency Procedure G-2 " Establishment of the On-Site Emergency Organization" and Emergency Procedure G-3
" Notification of Off-Site Organization" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Implementation'.
- b. Designate this event an Site Area Emergency if AC power was not restored to at least one vital bus (F, G or H) by either Diesel Generators or off-site power within 15 minutes of the total loss. Notify plant staff and response organizations recuired by EP (2-2 and EP G-3 in accordance with EP G-1.
O l DC04C4 23III l
NUMBER EP ECA-0.2 3GW3 Pacific Gas and Electric Company REVISION 0 DEPARTMENT OF NUCLEAR PLANT OPERATIONS 1 AND 2 PAGE 1 0F 9 DIABL J CANYON POWER PLANT UNIT NO(S) EMERGENCY PROCEDURE LOSS OF ALL AC POWER REC 0VERY - TITLE WITH SI REQUIRED IMPORTANT APPROVED. 7- 7 l TO PLANTMANAGEh DATE SAFETY SCOPE This procedure provides actions to use engineered safeguards systems to recover plant conditions following restoration of 4KV Vital AC power. This procedure and changes thereto requires PSRC review. SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from the following procedures:
- 1. ECA-0.0, LOSS OF ALL AC POWER, Step 27, when 4KV vital AC power is restored and SI is required.
- 2. ECA-0.0, LOSS OF ALL AC POWER REC 0VERY WITHOUT SI REQUIRED, Steps 5 and 19, if SI is required.
l i O DC0436 IVI
NUMBER EP EC#-0.2 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/11/8' 7,7g LOSS OF ALL AC POWER REC 0VERY WITH SI REQUIRED ACTION / EXPECTED RESFONSE RESPONSE NOT OBTAINED CAUTION: The loads placed on the energized bus should not exceed the capacity of the power supply, t0TE: o CSF status trees should be monitored for information only. FR Procedures should not be implemented prior to completion of Step 7. e AFW flow must be controlled to prevent RCS overcooling and Hi Stm Flow or SG delta-P SI signal actuation.
- 1. CHECK RWST Level - GREATER THAN 33% Align valves to establish (VB2) cold leg recirculation alignment (refer to E-1.3, TRANSFER TO COLD LEG RECIRClLATION, PLACE RHR Train B In Service) and go to Step 3.
- 2. MANUALLY Align The SI Valves To Establisn Injection Alignment:
(VBl/VB2)
- a. Refer to Appendix I for valve list with desired position
- 3. CHECK RCP Thermal Barrier CCW Isolation Status: (VB1)
- a. e CLOSE FCV-357 - CCW f rom RCP a. Locally close FCV-357.
therm bar iso viv, OC (100',GE-166')
- OR -
e CLOSE FCV-750 - CCW from RCP them bar iso viv, IC
+e O
DC0436 2VI
NUMBER EP ECA-0.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/11/85 { } PAGE 3 0F 9 TITLE LOSS OF ALL AC POWER REC 0VERY WITH SI REQUIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: DC control power switches should be closed only on those Safeguards components required to be placed in service.
- 4. MANUALLY Load The Following Safeguards Eauipment On The Available 4KV Vital Busses': (VBI)
- a. ASW pp
- b. CCW pp b. I F. CCW pp trips on overcurrent, THEN isolate Header C and restart CCWpp.
- c. RHR pp
- d. SI pos
- e. CFCUs (Slow Speed)
{ }
- 5. CHECK If Charging Puro(s) Should Be Started:
- a. Go to Step 6.
~
- a. Check charging pumps - ALL OBSERVE STOPPED (VB2) CAUTION AND NOTE PRIOR TO STEP 6.
- b. Check CVCS-8369 A, B, C & D _ b. IF--- vivs open or position CLOSED, RCP seal water not known, containment iso vivs (100', THEN locally close vivs.
GE-127 to 137 ) Continue with Step 6, and , WHEN vivs closed, l TEDi do Step Sc.
- c. Start one cent charging pp c. IF-- CCW available to PD (VB2) charging pp, THEN start PD charging pp.
l IF NOT, i q g TR'EN go to Step 6. OBSERVE CAUTION AND NOTE PRIOR TO STEP 6. nrna's avt
NUMBER EP ECA-0.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVIS10N 0 DATE 3/11/85 PAGE 4 0F 9 4 1 TITLE. LOSS OF ALL AC POWER REC 0VERY WITH SI REQUIRED O ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: e Alternate water sources for AFW pumps will be necessary if CST level decreases to less than 10%. (Refer to E-2.1, ALTERNATE AUXILIARY FEEDWATER SUPPLIES). e If SG NR level decreases to less than 4%[20%] and AFW flow is less than 460 GPM, the motor driven AFW pumps should be manually loaded on 4KV bus to supply water to the SGs. N)TE: If motor driven AFW pump is not required, maintain the AFW pumps disabled to prevent auto start until adequate power supplies are returned to service.
- 6. CHECK Intact SG Levels: (VB3)
- a. Narrow range level - GREATEP THAN a. Maintain AFW flow greater 44[20k] than 460 gpm to non-faulted SG(s) until NR level is greater than 4LL20t] in at least one SG.
E AFW flow NOT greater than 460 gpm, THEN e Manually load a motor driven AFW pp on the available 4KV vital bus. e Establish required AFW viv alignment to SG(s).
- b. Control AFW flow to maintain NR level between 4%[20%] and 33%
- 7. MAKE Containment Spray Pumps Available For Auto Start
- a. Ensure DC control power is available to containment spray pumps DC0435 4VI -
1 AND 2 otAsLO CANYON POWEA PLANT UNIT NO(S) S ON 0 DATE 3/11/85 PAGE 5 0F 9 TITLE. LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i CAUTION: e RCP thermal barrier cooling should be established slowly to minimize potential introduction of steam into the CCW system. RCP thermal barrier cooling should not be established to an RCP with excessive seal leakage, e RCP seal injection should be established slowly to minimize RCP thermal stresses and potential seal failures, e As part of subsequent recovery actions, RCPs should not be started prior to a status evaluation. NOTE: FR Procedures may now be implemented as necessary.
- 8. ESTABLISH RCP Seal Coolinc:
Continue with Step 9 while establishing RCP seal cooling
- a. Check Phase B - NOT INITIATED a. Go to Step 9.
- b. Establish CCW flow to RCP thermal barriers (100', GE-166 )
- 1) Establish communications between the control room and area near FCV-357, CCW from RCP therm bar, OC
- 2) Monitor RCP lower bearing temperature (TI-155, 154, 153, 152 on VB2 and T0417A, T0437A, T0457A, T0477A on the P250)
- 3) Ensure FCV-357 - CLOSED, 3) Close FCV-357 RCP therm bar CCW return iso viv, OC (VB1) - OR -
CCW-267. THIS STEP CONTINUED Oh NEXT PAGE l DC0435 SVI i j
NUMBER EP ECA-0.2 OfABLO CANYON POWER PLANT UNIT NO(S) I ANO .. REVISl0N O DATE 3/11/85 PAGE 6 0F 9 7gg LOSS OF ALL AC POWER REC 0VERY WITH SI REQUIRED ACTION /EXECTED RESf0NSE RESPONSE NOT OBTAINED
- 4) Ensure FCV-750 - OPEN, 4) IF FCV-357 or CCW-267 RCP therm bar CCW return iso CLOSED, viv,IC(VB1) THEN OPEN FCV-750.
N0'IE: Monitor flow on FI-90 (Locally at FCV-357) and temperature on TI-1004 (Locally at FCV-357). Initiate flowto the thermal barrier slowly reducing lower bearing temperature (TI-155,154,153,152 on VB2 and T0417A, T0437A, Tr:57A, T0477A on the P250) at a maximum rate of 1*F per minute until full thermal barrier flow is returned to normal. Some local boiling may occur in the CCW lines giving a closed signal to FCV-357.
- 5) locally crack open FCV-357 or CCW-267
- c. Establish seal injection flow to RCPs (100', GE-127 -137 ):
- 1) Wait until seal leak off water temperature (TI-148, 146, 132, 125) has decreased to 235cF (VB2)
- 2) Establish communications between control room and the area near the RCP seal water injection flow control vivs CVCS-8369 A, B, C, & D NOTE: Monitor RCP Seal Inj Flow No. I seal leak off temperature and lower RCP bearing temperature. Reduce each respective RCP bearing temperature at a maximum rate of l'F per minute until bearing temperature is less than 225 F. Then adjust seal injection flow as necessary.
- 3) Crack open CVCS-8369 A, B, C and 0 one at a time
- 9. GO To E-1, LOSS CF REACTOR OR SECONDARY COOLANT ?
- END -
1 O DC0436 6VI
NUMBER EP ECA-0.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 fm DATE 3/11/85 Q LOSS OF ALL AC POWER REC 0VERY WITH SI REQUIRED PAGE 7 0F 9 m LE. APPENDIX I SI VALVE ALIGNMENT FOR INJECTION MODE *
- 1. CCW HDR A MAX FLOW (FCV-366) OPEN
- 2. CCW HDR B MAX FLOW (FCV-360) OPEN
- 3. SPRAY ADD TK OUT (8992) OPEN
- 4. RHR HX 1 & 2 TO CONT SPRAY (9003 A & B) CLOSED
- 5. RHR INJ TO LOOP 1 & 2 HOT LEG: (8703) CLOSED
- 6. SI PPS TO HOT LEGS (8802 A & B) CLOSED
- 7. SI PPS TO COLD LEGS (8835) OPEN
- 8. 51 PPS XTIE (8821 A & B) OPEN
- 9. RHP HX 1 & 2 TO COLD LEG (8809 A & B) OPEN
- 10. SI PPS SUCTI0t; (8923 A & B) OPEN
- 11. RHP HX 1 & 2 TO SI PPS (8804 A & B) CLOSED
- 12. RHR PPS XTIE TO CHG PP SUCTION (8807 A & B) CLOSED
- 13. CNT SUMP TO RHR (8982 A & B) CLO5ED 14 RHR HX 1 OUT (HCV-638) OPEN
- 15. RHR HX 2 OUT (HCV-637) OPEN
- 16. RHR PPS SUCTION (8700 A & B) OPEN
- 17. SI PPS RECIRC TO RWST (8974 A & B) OPEN
- 18. RWST TO RHR PPS (8980) OPEN
- 19. LOOP 4 TO RHR SUCTION (8701 & 8702) CLOSED
- 20. RWST TO SI PPS (8976) OPEN
- may be checked using mer.itor light box SI section.
DC0436 7VI
T NUMBER EP ECA-0.2 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/11/85 7,7 g LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED APPENDIX I (Continued) SI VALVE ALIGNMENT FOR INJECTION MODE
- 21. BIT TO BASY RECIRC ISO (8870A&B) CLOSED
- 22. BIT TO BAST RECIRC ISO (8911) CLOSED
- 23. BIT OUTLETS (8801A&B) OPEN
- 24. BIT INLETS (8803 A&B) OPEN
- 25. NORMAL CHG LINE ISO (8107) CLOSED
- 26. NORMAL CHG LINE ISO (8108) CLOSED
- 27. RWST TO CHG PPS (8805 A&B) OPEN
- 28. VCT TO CHG PPS (LCV-112 B&C) Cf.0 SED
- 29. CHG PPS MINI FLOW (8106) OPEN
- 30. CHG PPS MINI FLOW (8105) OPEN
?
O DC0436 8VI
NUMBER EP ECA-0.2 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/11/85 PAGE 9 0F 9 TITLE LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED APPENDIX Z 5 EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When the emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Designate this event a Alert. Notify plant staff and response organizations required for this classification by implementing Emergency Procedure G-2 " Establishment of the On-Site Emergency Organization" and Emergency Procedure G-3
" Notification of Off-Site Organization" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Implementation."
- b. Designate this event a Site Area Emeraency if AC power was not restored to at least one vital bus (f. G or H) by either Diesel Generators or off-site pcwe.r within 15 minutec cf the total loss. Hiotify plant staff and response organizatioris required by EP G-2 and EP G-3 in accordance with EP G-1.
- c. If AC was not restored to at least two vital busses (F, G or.
H) by either Diesel Generator or off-site power.within 15 minutes of the total loss and a SI occurred with'high or increasing levels of containment pressure, area radiation or recircu htion sump level. Designate this event a General' Emerceg. I
- 1. _
( 4 ! O DC0436 9VI l_-----_.____
NUMBER EP ECA-0.3 2 69/3 Pacific Gas and Electric Company REVISICN 0 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 3/11/85 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 10
- l EMERGENCY PROCEDURE TITLE g RESTORE VITAL BUS IMPORTANT APPROVED. T6 &B TO PLANTMANhR DATE SAFETY SCOPE This procedure provides guidance for restoring power to a de-energized vital bus. If ALL three vital busses are de-energized, ECA-0.0, LOSS OF ALL AC POWER must be used.
SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from E-0, REACTOR TRIP OR SAFETY INJECTION, O Step 3, if only one or two vital busses are de-energized. i l l l l . O I DC0415 IV
NUMBER EP ECA-0.3 olABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/11/85 PAGE 2 0F 10 7,7 7 RESTORE VITAL BUS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. CHECK For Vital Bus Fault: (VB4)
- a. Feeder bkr overcurrent blue light a. IF bus in NOT faulted,
_ ON TREN go to Step 2. _ OR - Bus differential blue light - ON (87X Relay for F, G, H) , b. Investigate cause of bus fault and attempt to clear
- c. Consider having electrical department connect a jumper from a good bus (spare breaker) to needed equipment on the faulted bus
- d. Return to procedure and step in effect
- 2. CHECK Diesel Generator Status:
- a. Identify problem:
e D/G breaker trip alarm - ON (PK16-14,17-14,18-14) e D/G shutdown relay trip alarm-0N (PK16-15,17-15,18-15) e D/G engine trip alarm - ON (PK 16-13, 17-13, 18-13) e D/G DC control UV - ON (PK 16-4, 17-4, 18-4)
- b. Contact electrical department for assistance
- c. If necessary reset the engine -
failure alarm and the D/G voltage shutdown re]ay (VB4) THIS STEP CONTINUED ON NEXT PAGE O DC0415 2V
I DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 3/11/85 (' ( PAGE 3 0F 10 RESTORE VITAL BUS TITLE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED . i l
- d. Try to start and load D/G from d. IF D/G NOT operable, control room or at local THEN consider the following stations options:
- 1) Backfeed from 500 KV system if available per OP J-2 (place cutout auto transfer feature cutout switen to CUTOUT and reset 4 KV auto transfer) (VB5)
- OR -
- 2) Have electrical department connect a jumper from a good bus (spare bkr) to needed equipment on the affected bus,
- OR -
- 3) Crosstie the affected bus to an already energized bus per Appendix X.
- 3. RETURN To Procecure And Step In Effect
- END .
O DC0415 3V _ w -
otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/11/85 PAGE 4 0F 10 7,7g RESTORE VITAL BUS APPENDIX X CROSSTIE OF VITAL BUSSES SCOPE Implementation of this appendix requires the plant superintendent or his designates approval. This appendix should be performed to energize two vital busses, from one diesel. The reason is that safeguard trains would be cross connected threatening the operability of the diesel generator. If two vital busses are found energized, enough equipment would be energized to establish one trein of ESF equipment. DISCUSSION As a general guideline, in this situation several options may be available depending on plant conditions and RCS status. If SI is not required, the shift foreman may elect to stay in a hot shutdown status awaiting restoration of offsite power or he may decide to cooldown. If SI is required, a minimum of one ECCS flow path must be established. The type of ECCS flowpath desired would depend on RCS conditier.s. PRECAUTIONS AND LIMITATIONS
- 1. Some equipment may have to be operated on a continuous basis and some on an "as needed" basis. Existing conditions will determine which equipment is needed (plant cooldown, SI, etc.).
- 2. The maximum capacity of the diesel generator should not be exceeded. Figure 1 identifies the diesel generator load limits.
Table 1 provides loads for various vital 4KV and 480 volt equipment. STP M-9M also contains specific loads on all 480 volt vital equipment.
- 3. Start only one piece of equipment at a time since starti'ng current may cause bus failure.
?
O DC0415 4V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON O C/ DATE PAGE 3/11/85 5 0F 10 7,7 a RESTORE VITAL BUS
. APPENDIX X (Continued)
PROCEDURE
- 1. Obtain permission from the Plant Superintender;t or his designate.
- 2. Reset SI (if applicable) so that the affected bus will not try to auto load when the bus becomes energized. (VB1)
- 3. Cutout the AUTO Transfer FCO's for 4KV busses and 12KV busses.
(VB4/VBS) NOTE: e The Auto Transfer Reset will NOT reset and the BLUE light will NOT de-energize for the F bus if the W diesel generator is operating on the other Unit. e If the D/G associated with the inoperable bus is running, it must be shutdown to permit the Auto Transfer Relay to be reset. 'u 4. Depress all AUTO Transfer Reset Push Buttons. (VB4/VBS)
- 5. This step is only used to energize the 4KV F vital bus when the 1-3 diesel generator is operating on the other unit.
- a. Dispatch an Operator to the 4KV Bus F Vital Switchgear room, to overvoltage relay 59HFG1/59HFG2, on the Diesel Generator 13 breaker cubical.
- 1) Remove the cover
- 2) Pull down on the 2 " RED" handled switches (Terminal 5 and 10).
- b. THEN at the Main Control Board, depress the Auto Transfer Reset Push Button for the 4KV F vital bus. Notice the
" BLUE" light goes "0UT".
(VB4)
- 6. OPEN or verify OPEN all vital bus 4KV auxiliary feeder breakers, i 52-HH-13, 52-HG-13 and 52-HF-13. (VB4)
- 7. OPEN or verify OPEN all vital bus 4KV startup feeder breakers, 52-HH-14, 52-HG-14 and 52-HF-14. (VB4)
O C/ DC0415 5V l
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 3/11/85 PAGE 6 0F 10 7gg RESTORE VITAL BUS APPENDIX X (Continued)
- 8. OPEN or verify OPEN startup feeder breaker 52-HG-15, to the vital busses F, G and H. (VB4).
- 9. OPEN or verify OPEN the 4KV to 480V bus feeder breaker. (VB4)
- a. If bus F is to be re-energized OPEN 52-HF-10.
- b. If bus G is to be re-energized OPEN 52-HG-10.
- c. If bus H is to be re-energized OPEN 52-HH-10.
- 10. CLOSE the 4KV startup feeder breaker for the bus that will be supplying power to the inoperable bus.
OPERATING D/G UNIT 1 CLOSE UNIT 2 CLOSE No. 1 52-HH-14 52-HG-14 No. 2 52-HG-14 52-HH-14 No. 3 52-HF-14 52-HF-14 CAlJTION: If the diesel generator appears unstable during the performance of Step 11 or at any time beyond this point in the procedure, immediately open startup feeder breaker for the inoperable bus to separate the diesel from the inoperable bus.
- 11. CLOSE the 4KV startup feeder breaker for the inoperable bus.
(VB4)
- a. If bus F is to be re-energized CLOSE 52.HF-14.
- b. If bus G is to be re-energized CLOSE 52-HG-14.
- c. If bus H is to be re-energized CLOSE 52-HH-14.
?
O DC0415 6V I
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 f0N DATE 3/11/85 PAGE 7 0F 10 TITLE. RESTORE VITAL BUS l l APPENDIX X (Continued) l i l CAUTION: Station an operator at the VB4 to monitor the diesel I generator. If an SI should occur, immediately open the 4KV startup feeder breaker for the bus with the operable diesel generator to prevent overioading the operable diesel generator when the SI loads sequence on the bus.
- 12. If Step 5 was used to energize the 4KV F vital bus when the 1-3 diesel generator is supplying the other unit, the Operator at the 4KV Bus F Switchgear may now return the 2 " RED" handled switches to their normal position and replace the cover.
- 13. Operate only the eouipment needed for the existing conditions.
Evaluate the load on the diesel generator prior to energizing each additional load to ensure its capacity limit is not exceeded (figure 1). Refer to table 1 to identify expected loads for each piece of equipment. If tne diesel overloads, it may only be necessary to trip the last load added rather than the entire bus. m %J DC0415 7V
(UMBER EP ECA-0.3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/11/85 PAGE 8 0F 10 RESTORE VITAL BUS 7 APPENDIX X (Continued) UN14Atot E.V. w
,.J_
? ..
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@l DC0415 8V l
l I
1 NUMBER EP ECA-0.3 i DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/11/85 O' ' 7,7 g RESTORE VITAL BUS
. APPENDIX X (Continued)
TABLE 1: EQUIPMENT LOADS Rating Max Demand in Kw Load Qty, (Each) Bus F Bus G Sus H
- 1. Centrifugal Charging Pumps 2 600 Hp 495 507 ---
- 2. Safety Injection Pumps 2 400 Hp 303 --- 303
- 3. Containment Spray Pumps 2 400 Hp --- 350 350
- 4. Residual Heat Removal Pumps 2 400 Hp --- 325 333
- 5. Containment Fan Cooler 5
- a. Slow Speed 100 Hp 73 ea 73 ea 73
- b. Fast Speed 300 Hp 220 ea 220 ea 220
- 6. Component Cooling Water Pumps 3 400 Hp 314 314 314
- 7. Auxiliary Saltwater Pun,ps 2 400 Hp 321 321 ---
- 8. Auxiliary Feedwater Pumpe 2 600 Hp 410 --- 410
- 9. Fire Pumps 2 200 Hp 150 --- 150
- 10. Pressurizer heaters
- 2 483/207 483/207
- 11. Remaining 480 volt loads are - --- --- --- ---
extensive (Refer to STP M-9M for a specific listing)
- 483 KW for 7 Heaters; 207 for 3 Heaters
-) DC0415 9V
DIABLO CANYON POWER PLANT ONIT NO(S) 1 AND 2 R ON DATE 3/11/85 PAGE 10 0F 10 7,7 g RESTORE VITAL BUS APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS I
- 1. When the emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. If a plant shutdown is initiated in accordance with Technical Specifications 3.8.2.1 or 3.8.2.2, designate this as a Notification of Unusual Event. Notify plant staff and response organizations required for this classification by implementing Emergency Procedure G-2 " Establishment of the On-Site Emergency Organization" and Emergency Procedure G-3
" Notification of Off-Site Organization" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Implementation."
O O DC0415 10V
NUMBER EP ECA-1.1
}GW3 Pacific Gas and Electric Company REVISION 0 DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 23 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE
~
LOSS OF EMERGENCY COOLANT RECIRCULATION TITLE
- IMPORTANT APPROVED W- - 'E TO PLANTMANy!R DATE SAFETY SCOPE This procedure provides actions to restore emergency coolant recirculation capability, to delay depletion of the RWST by adding makeup and reducing outflow, and to depressurize the RCS to minimize break flow. This procedure and changes thereto requires PSRC review.
SYMPT 0MS OR ENTRY CONDITIONS This procedure is entered from the following procedures:
- 1. E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Steps 12 and 14, when cold leg recirculation capability cannot be verified.
- 2. E-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1 CAUTION and FOLDOUT, when at least one flow path from the sump cannot be established or maintained.
- 3. ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 3, when a LOCA outside containment cannot be isolated.
l i o l DC0436 IV l l l
l NUMBER EP ECA-1.1 1 AND 2 REVISION 0 0iAsLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 2 0F 23 7gg LOSS OF EMERGENCY COOLANT RECIRCULATION ACTION /EX CTED RESR)NSE RESPONSE NOT OBTAINED I CAUTION: e If emergency coolant recirculation capability is restored during this procedure, further recovery actions should continue by returning to procedure and step in effect. o If suction source is lost to any Charging, SI, RHR, or Containment Spray pump, the pump should be stopped.
- 1. TRY To Restore Emergency Coolant Recirculation Equipment:
- a. Cneck power available to RHR Pump a. Energize vital bus. (Refer 1 and 2 (VB1) to ECA_0.3, RESTORE VITAL BUS)
- b. Manually close RHR Pump Breaker b. Locally operate braaker if power is available but breaker will NOT operate remotely.
IF breaker will not close, TREN attempt to replace with another breaker.
- c. Check power available to valves c. Manually or locally operate required for recirculation swap valves.
over. (Refer to E-1.3, TRANSFER TO COLD LEG RECIRCULATION or E-1.4, TRANSFER TO HOT LEG RECIRCULATION for valve list)
?
O DC0436 2V l l
NUMBER EP ECA-1.1 1 1 AND e' DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 1 DATE 3/12/85 PAGE 3 0F 23
~
7,7 a LOSS OF EMERGENCY C0OLANT RECIRCULATION ACTION / EXPECTED RESPONSE RESR)NSE NOT OBTAINED f0TEfContinuewithStep3whileAddingMakeuptotheRWST.
- 2. ADD Makeup To The RWST:
- a. Makeup to RWST from SFP using Appendix X -AND/0R-Makeup to RWST from CVCS blend system as follows:
- 1) Place makeup mode selector switch in MANUAL (CC2)
- 2) Locally perform the following:
e Open CVCS-8466, blender outlet to LHUT and RWST (100', blender rm) e Open CVCS-8467, blender outlet to RWST (100', blender rm) s e Close CVCS-8258, blender to LHUT inlet (100', outside LHUT No. 2 rm)
- 3) Se'iect to CLOSE FCV-110B and FCV-111B (VB2)
- 4) Verify FCV-110A and FCV-111A control switches in AUTO (VB2)
- 5) Set batch integrators as follows: (CC2)
(Boric Acid conc. 1100 ppm) Primary water - 100,000 gal. Boric Acid - 5,555 gal.
- 6) Turn makeup control switch to START (CC2)
- 7) Adjust flow as follows: (CC2) e 180 gpn Primary Water Flow (FCV-111A controller HC-111) e 10 gpm Boric Acid Flow p]
N. (FCV-110AcontrollerHC-110) DC0436 3V
NUMBER EP ECA-1.1 DIABLO CANYON POWER PLANT UNIT NO(S) I AND 2 REVIS10N 0 DATE 3/12/85 PAGE 4 0F 23 l TITLE: LOSS OF EMERGENCY COOLANT RECIRCULATION ll ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Shutdown margin should be monitored during RCS cooldown.
- 3. INITIATE RCS Cooldown To Cold Shutdown:
- a. Maintain cooldown rate in RCS cold legs - LESS THAN 100 F in any one hour period
- b. Dump steam to condenser from b. Manually or locally dump intact SG(s) (CC3) steam from intact SG(s) using 10% Steam Dumps. (VB3)
IF no intact SG available, TREN use faulted SG.
- 4. VERIFY Containment Fan Coolers - Manually start fan coolers in RUNNING IN EMERGENCY MODE slow speed.
(Monitor lignt box C, VB1)
- 5. CHECK RWST Level - GREATER THAN 4% Go to Step 14.
(kB2)
?
i O l DC0436 4V
~
DIABLO CANYON POWER F uNT UNIT NO(S) 1 AND 2 R S ON DATE 3/12/85 PAGE 5 0F 23 k LOSS OF EMERGENCY COOLANT RECIRCULATION 7gg ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 6.5ETERMINEContainmentSaray Requirements: (Suction ; rom RWST)
- a. Determine number of spray pumps required using table:
RWST CONTAINMENT NUMBER OF FAN NUMBER OF SPRAY LEVEL PRESSURE C0OLERS RUNNING IN- PUMPS REQUIRED EMERGENCY MODE
. GREATER THAN 47 PSIG . -__ 2 GREATER THAN BETWEEN 22 PSIG AND 0,1 or 2 2 l'e 47 PSIG 3 or 4 1 5 0 LESS THAN 22 PSIG ----- 0 LESS THAN 41 ----- ----- O
- b. Spray pumps running - EQUAL T0 b. Manually operate pumps as NUM3ER REQUIRED necessary to obtain number required. (VB1)
_I_F spray pumps can NOT be o?erated, THEN continue efforts to establish containment fan cooler operation if all fan coolers are not running. O DC0436 SV l I
NUMBER EP ECA-1.1 l 1 AND 2 REVIS10N 0 OIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 6 0F 23 TITLE. LOSS OF EMERGENCY COOLANT RECIRCULATION '{ll ACTION / EXPECTED RESFONSE RESPONSE NOT OBTAINED CAUTION: If offsite power is lost after SI is reset, manual action will be required to restart some safeguards equipment. 7.RESETSI(VB1)
- 8. CHECK RWST Level - LESS THAN 33% Go to Step 11.
(VB2) ________________
- 9. VERIFY NO Backflow From RWST To Containment Sump: (VB1)
- a. Containment Sump Recirculation a. IF ---
both sump recirculation Valves - ANY OPEN lines are isolated, THEN go to Step 10.
- b. Isolate Flow Path to Sump:
- 1) For 8982A open - CLOSE 8700A
- 2) For 8982B open - CLOSE 87008
- 10. ESTABLISH Minimum ECCS Flow Required I F, RWST level greater than To Remove Decay heat (RWST Level 33%,
Less Than 33t): (Val) THEN go to Step 11.
- a. Ensure One SI pump and One cent a. Align suction of one SI and charging pump - SUCTION ALIGNED one cent charging pp to TO RWST RWST.
- b. Determine minimum ECCS flow required using Appendix G.
- c. Establish minimum ECCS Flow:
e manually operate pumps as necessary e manually or locally throttle flow as necessary
- d. Go to Step 12
,DC0436 6V t
I 1 AND 2 NUMBER EP ECA-1.1 1 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 ' DATE 3/12/85 PAGE 7 0F 23 LOSS OF EMERGENCY COOLANT RECIRCULATION TiTm. ACTION /EXRCTED RESPONSE RESPONSE t0T OBTAINED
- 11. STABLISH One Train Of ECCS Flow IF RWST level less than 33%,
(RWST Level Greater Than 33%):(VB1) TREN return to Step 9.
- a. Operate ECCS pumps as follows:
- 1) Cent charging pump - ONE RUNNING
- 2) SI pump ONE RUNNING
- 3) WR RCS pressure - LESS THAN 3. Stop RHR pumps. Go to Step 300 PSIG 12.
- 4) RHR pump - ONE RUNNING
- 12. VERIFY Adecuate ECCS Flow:
- a. RVLIS full range indication - a. Increase ECCS flow to
\ GREATER THAN 63% (PAM3/4) maintain RVLIS full range - greater than 63%.
- b. Core exit TCs - STABLE OR b. Increase ECCS flow to DECREASING maintain TCs stable or decreasing.
- 13. CHECK RWST Level - Less Than 4%(VB2) Return to Step 1. OBSERVE CAUTION PRIOR TO STEP 1.
v DC0436 7V
NUMBER EP ECA-1.1 1 AND 2 REVISION O DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 8 0F 23 LOSS OF EMERGENCY COOLANT RECIRCULATION Tir a ACTION /EX CTED RESPONSE RESPONSE NOT OBTAINED
- 14. STOP All Pumps Taking Suction From RWST (VB1) e Residual Heat Removal Pumps e Safety Injection Pumps e Charging Pumps (Remove DC power to disable pump auto start on blackout sequence until suction aligned to adequate suction source) e Containment Spray Pumps (Remove DC power to disable pump auto start on High Containment Pressure)
- 15. TRY To Add Makeup To RCS From Alternate Source:
- a. Makeup to RCS from VCT through a. Go to Step 16.
normal charging line (refer to Appendix W)
- 16. OEPRESSURIZE All Intact SG(s) To 680 PSIG At The Maximum Rate:
- a. Dump stean to condenser (CC3) a. Manually or locally dump steam at maximum rate from intact SG(s) using 10% Steam Dump or any other steam vent path. -
- b. Check SG pressures - LESS THAN b. Return to Step 16a.
680 PSIG (VB3)
- c. Stop SG depressurization (CC3)
O DC0436 8V l
NUMBER EP ECA-1.1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0
~'s OATE 3/12/85 C PAGE 9 0F 23 TITLE LOSS OF EMERGENCY COOLANT RECIRCULATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 17. DEPRESSURIZE All Intact SG(s) To Inject Accumulators As Necessary:
- a. Dump steam to condensor as a. Manually or locally dump necessary to maintain RVLIS full steam from intact SG(s) as range at 63% (CC3) necessary to maintain RVLIS full range indication at 63%
using 10% Steam Dumps.
- b. Check SG pressures - LESS THAN b. Return to Step 17a.
160 PSIG (VB3) ----------------
- c. Stop SG depressurization (CC3)
- 18. ISOLATE All SI Accumulators: (VB1)
- a. Check power to accum disch iso a. Restore power to valves (7s,) valves - AVAILABLE UNIT 1 UNIT 2 e 52-lF-46 52-2F-46 e 52-1G-07 52-2G-07 e 52-1H-14 52-2H-14 e 52-1G-05 52-2G-05
- b. Close all SI accumulator b. IF--' any accumulator can NOT discharge isolation valves: be isolated, THEN vent the accumulator:
8808A 88088 1) Close FCV-8880 accum N2 8808C fill iso viv. 8808D 2) Open 8875 A, B, C, 0 accum N2 supply and vent. to affected accum
- 3) Open HCV-943 accum N2 supply vent.
UNTIL accum is depressurized. and continue in this procedure. U DC0436 9V
l NUMBER EP ECA-1.1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 l DATE 3/12/85 l PAGE 10 0F 23 l i LOSS OF EMERGENCY COOLANT RECIRCULATION Tir a ACTION /EXRCTED RESPONSE RESPONSE NOT OBTAINED
- 19. CHECK If RCP(s) Must Be Stopped:
(VB2)
- a. Check the following: a. Go to Step 20.
e Number 1 seal differential pressure - LESS THAN 215 PSID
- OR -
e Number 1 seal leakoff flow - LESS THAN Appendix 8 curve
- b. STOP affected RCP(s)
- 20. DEPRESSURIZE All Intact SG(s) To Atmosonere Pressure:
- a. Maintain cooldown rate in RCS cold legs - LESS TPAN 100 in any one hour period
- b. Dump stean to condenser (CC3) b. Manually or locally dump O steam from intact SG(s). Use 107. Steam Dump or other steam '.
vent path. (VB3)
- 21. CHECK If RHR System Should Be Placed In Service: (VB2)
- a. Check the following:
e RCS temperature - LESS THAN 350 F e WR RCS pressure - LESS THAN 390 PSIG
- b. Consult with TSC to determine if ,
the RHR system should be placed - in service (Refer to OP B-2:V, RHR - PLACE IN SERVICE DURING C00LDOWN) O DC0436 10V
NUMBER EP ECA-1.1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/12/85 PAGE 11 0F 23 (~')s E 7,7 g LOSS OF EMERGENCY COOLANT RECIRCULATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 22.5AINTAINRCSHeatRemoval:
- a. Use RHR system if in service (VB1)
- b. Dump steam to condenser from b. Manually or locally dump intact SG (CC3) steam from intact SG(s) using 10% Steam Dump.
IF no intact SG available and RHR system NOT in service. THEN use faulted SG.
- 23. CCf;SULT Plant Engineering Staff:
- a. Evaluate long term plant status:
f3 Q 1) Maintain cold shutdown conditions e RCS temp <200'F eKeff * '99
- 2) Check containment atmosphere to determine if hydrogen recombines or hydrogen purge should be placed in service (PAM 1)
- 3) Implement OP L.5 PLANT C00LDOWN FROM MINIMUM LOAD TO COLD SHUTDOWN ind review for applicable actions
- 4) Check STP M-55 CYCLIC REVIEW
- END -
O DC0436 11V
NUMBER EP E(A-1.1 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 12 0F 23 7yg LOSS OF EMERGENCY COOLANT RECIRCULATION APPENDIX B RESTART OF REACTOR COOLANT PUMP
- 1. Start oil lift pump, run for 2 minutes.
- 2. Verify CCW available to thermal barrier, oil coolers, seal water HX.
- 3. Verify seal dp greater than 215 psid, depressurize VCT as necessa ry.
- 4. Verify seal injection flow 8 (6 to 12) gpm.
- 5. Verify seal leak off flow within limits shown on graph.
- 6. Ensure closed PCV 455A & B, Normal PZR Spray vivs.
ALLOWABLE RCP #1 SEAL LEAK RATES 5 i
; i 4 .
i I i SHUTDOWN RCP WITH N ONE HALF HOUR 3
' l I I l l .
I 4 l 6 I i i l g
' I Eg i l SAFE OPERAT,1NG RE,GION l
= l t l' I ! I l g ;
5 [ I l l I
> REGION l REGION g i
1
' i i 00 NOT START RCP j i
Ml i i {i
. 4 i i i 1 i , t 7 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2100 RCP 81 Sral DIFFERENTIAL PDE55URE P5ID REGION 1 NO PHASE A SIGNAL.
do=RCS press -VCi press PHASE A PRESENT. do=RC$ press-150psfg REGION 2 USE INSTALLED do GAUGES l DC0436 ID
1 AND 2 NUMBER EP ECA-1.1 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 3/12/85 O DATE PAGE 13 0F 23 7,7 2 LOSS OF EMERGENCY COOLANT RECIRCULATION
. APPENDIX G v
MINIMUM ECCS FLOW RATE AFTER TRIP 800 p. . . _ _ _ , _ . _ _ _ _ . .
\_ _.._. .___. _
700 i_ !
$ ~~._.-~~~_--'_'-'~---_-d_._ _
i y 600 _ _ _ _ _ . _ , _ _ _ _ _ _ _ _ _ . , _ , _
, x . . . . _ . _ _ . - _ _ _ _ ., __ . _ _ , _.___.__. _____ .
~ '" ~ ~ ~ ~ ~ ~ ~
h 500 . [ ~,'__,, ~~ ~ ~ ~ ~ ~ c
~ _... .__.. _.'.
+.
1 i_.__.______. ta E . : - - . . _ . - ._ . ._ ...
*A me 400 _ . . . _ . _ . _ _ . _ _ . . . . . _ _ _ _ _ . .__ _ . . _ . .
o __._._____;. ...__a.__.____ . _ . . . . _ _ _ _ _ O . . . .. . _ ! _ _ . g . . . _ . . ..
._ j .._...{_ . . _ . . . . . _ _ _ _ _ _
E . . .. p . . . . _ _ _ .. ., E ._ . .. .
...___.4 . . . . _ _ __. ..
E 200 -
._ ~
E . . _ _ , ._ . , . ._..____ 100 - __._.4 _ _ _ ._ .. _ .J, ._ ___; . l e 1 10 100 1000 10000 TIME AFTER TRIP MINUTES l i O DC0436 13V
NUMBEP. EP ECA-1.1 1 AND 2 REVISION 0 DIABLO CANYON POW l.R PLANT UNIT NO(S) DATE 3/12/85 PAGE 14 0F 23 7,7g LOSS OF EMERGENCY COOLANT RECIRCULATION APPENDIX K TRANSFER WATER FROM SPENT FUEL P0OL TO RWST
- 1. Verify Spent Fuel Pit pump 0FF.
- 2. Close SFS-8762, SFP pp disch viv to SFP hx.
- 3. Close SFS-8771A, SFP filter inlet.
- 4. Ensure SFS-8756 OPEN, SFP pp suction viv.
- 5. Ensure SFS-14 OPEN, SFP pp disch to filter & demin.
- 6. OPEN SFS-8774, SFP demin bypass viv.
- 7. Ensure SFS-8775 OPEN, SFP demin resin trap outlet to SFP filter.
- 8. Close SFS-87898, SFP resin trap outlet.
- 9. Ensure 51-8973 OPEN, refuel wtr perif pp disch to RWST iso viv.
- 10. Start Spent Fuel Pit Pump. g
- 11. If makeup to the SFP is required:
- a. Refer to OP B-7:V, SDENT FUEL POOL MAKEUP.
- b. Add 11 pounds of boric acid to the SFP for every 100 gallons of water transferred.
- c. If makeup from the transfer tank or demineralizers is not possible, use local fire water for makeup.
- 12. Stop SFP pump when suction line becomes uncovered.
?
i DC0436 14V 9
,-m_ . em
1 AND 2 NUMBER EP ECA-1.1 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 m DATE 3/12/85 (j PAGE 15 0F 23 7,7g. LOSS OF EMERGENCY COOLANT RECIRCULATION APPENDIX R RCP HOT SEAL C00LDOWN If RCP seal returns or lower radial bearing temp has been or is >225*F perform the following: ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. CHECK RCP Seal Isolation Status:
- a. Verify seal injection iso a. -
IF valves open or position vivs CVCS - 8369A, B, C & D not known,
- CLOSED THEN check centrifugal charging pump status:
e located 100' aux bida pent area (GE,127' - 1) IF pump running, 137') TiiEN return to step in effect.
- 2) IF pump NOT running, TIIEN r,anuaTTF or locally close seal injection vivs, OC.
v DC0436 15V
NUMBER EP ECA-1.1 1 AND 2 REVISION 0 oiABLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 16 0F 23 7,7a LOSS OF EMERGENCY COOLANT RECIRCULATION APPENDIX R (Continued) ACTION /EXRCTED ESPONSE ESPONSE NOT OBTAINED
- b. FCV-357 - RCP therm bar CCW b. -
IF valve is open or return iso viv OC - CLOSE0 position not known, (100',GE-166*,VB1) THEN check CCW pump status: IF a pump is running,
- 1) TREN go to Step 2b.
IF pump NOT running,
- 2) TREN manuaTTy or locally close FCV-357.
(100',GE-166*). IF FCV-357 can NOT be closed, THEN manually close FCV-750, CCW return viv IC.
................ g O
DC0436 16V
NUMBER EP ECA.1.1 Dusto CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85
, PAGE 17 0F 23 7g LOSS OF EMERGENCY COOLANT RECIRCULATION APPENDIX R (Continued)
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: e RCP thermal barrier cooling should be established slowly to minimize potential introduction of stean into the CCW system, e RCP seal injection should be established slowly to minimize RCP thermal stresses and potential seal failures. e As part of subsequent recovery actions, RCPs should not be started prior to a status evaluation, unless responding to Inadecuate Core Cooling FR-C.1.
- 2. ESTABLISH RCP Seal Coolina:
. O, a. Establish CCW flow to PCP v' thermal barriers (100', GE-166c)
- 1) Establish comunications between the control room and area near FCV-357
- 2) Monitor RCf l ov.e r bearing temptirature (TI-155,154,153,152 on VB2 and T0417A, T0437A, T0457A, T0477A on the P250) -
- 3) Check FCV-357 - CLOSED, 3) Close FCV-357 (VB1)
-0R-CCW-267.
- 4) Check FCV-750 - OPEN, 4) IF FCV-357 or l RCP therm CCW return iso CCW-267 closed, l
vlv, IC (VB1) THEN open FCV-750. bl
'v' THIS STEP CONTINUED ON NEXT PAGE j
l DC0436 17V
NUMBER EP ECA-1.1 1 AND 2 REVISION 0 D'Asto CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 18 0F 23 7g LOSS OF EMERGENCY COOLANT RECIRCULATION APPENDIX R (Continued) ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Monitor flow on FI-90 (Locally at FCV-357) and temperature on TI-1004 (Locally at FCV-357). Initiate flow to the thermal barrier slowly reducing lower bearing temperature. (TI-155, 154. 153, 152 on VB2, and T0417A, T0437A, T0457A, T0477A on the P250) at a maximum rate of l'F per minute until full thennal barrier flow is returned to normal. Some local boiling may occur in the CCW lines giving a closed signal to FCV-357.
- 5) Locally crack open FCV-357 or CCW-267
- b. Establish seal injection flow to RCPs (100',
GE-127'-137*) (VB2)
- 1) Wait until seal leak off water temperature (TI-148,146,132,125) has decreased to 235 F
- 2) Establish ccreunications between control room and the 100' aux bldg. Pent Area near the SCP seal water injection flow control valves CVCS-8369A, B, C & D f0TE: Monitor RCP Seal Inj Flow No.1 seal leak off temperature and lower RCP bearing temperature. Reduce each respective RCP bearing temperature at a maximum rate of l'F per minute until bearing temperature is less than 225'F, then normal seal injection flow can be established.
I l 3) Crack open CVCS-8369 A, B, C and D one at a , tirre - me 1 1 O DC0436 18V
1 AND 2 NUMBER EP ECA-1.1 DIAsLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/12/85 ( i PAGE 19 0F 23 7,7g LOSS OF EMERGENCY COOLANT RECIRCULATION APPENDIX R (Continued) ACTION / EXPECTED ESPONSE ESPONSE NOT OBTAINED
- 3. AFTER RCP Seal Cooldown -
VERIFY Normal RCP Cooling Alignment: (VB1)
- a. Verify CCW a. IF CCW NOT aligned to RCPs,
- ALIGNED TO RCPs THEN ensure Phase B Isolation is reset and a FCV-355 - OPEN, CCW to manually open CCW RCP oil clrs, therm bar & valves.
sup clrs e FCV-357 - OPEN, CCW f rom RCP therm bar, OC e FCV-363 - OPEN, CCW from l RCP cil clrs & sup cirs, OC e FCV-749 - OPErd, CCW from RCP oil c1rs & suo clrs IC e FCV-750 - OPEN, CCW from RCP therm bar IC
- b. Verify RCP seal injection b. Adjusting charging and flow to each RCP - AT 8 (6 HCV-142 to maintain 6 to 12 to 12) GPM gpm to each RCP.
- 4. Return to step in effect t
9 DC0436 19V l
NUMBER EP ECA-1.1 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 20 0F 23 7,7g LOSS OF EMERGENCY COOLANT RECIRCULATION APPENDIX W: RCS Makeup From VCT ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. Align VCT makeup system:
- a. Place makeup mode selection switch in MANUAL (CC2)
- b. Locally CLOSE:
CVCS-8466 and CVCS-8467 (Blender to RWST)
- c. Place control switches in AUTO (VB2):
e FCV-1108 e FCV-111B e FCV-110A e FCV-111A e Primary M/V Water Pumps e Boric Acid Transfer Pumps
- 2. Align Charging Pump Suction to VCT (VS2):
- a. OPEN LCV-112B and LCV-112C, charg purp suction from VCT
- b. CLOSE 8805 A and B, charg pump suction from RWST
- 3. Align Charging Pump Discharge To Loops (VB2):
- a. IF- RCP(s) off and *1 seal return or lower rad brg temp greater than 225 F, THEN locally CLOSE CVCS-8369A, B, C and D. RCP seal inj conmt iso viv(s) (100', GE-166 ) ?
(Refer to Appendix R for hot RCP seal cooldown, if desired). OC0436 20V l
NUMBER EP ECA-1.1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION O DATE 3/12/85 () PAGE 21 0F 23 7,7 g LOSS OF EMERGENCY COOLANT RECIRCULATION APPENDIX W (Continued) I ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- b. Throttle to 50% HCV-142
- c. OPEN FCV-128 (CC2)
- d. LP 3 and 4 SG INTACT - OPEN 8146 and d. IF LP 4 SG Intact.
8147 Normal and Alt Charging Vivs TiiEN open 8146, normal (VB2) charg to LP 4 ccid leg viv. IF LP 4 SG NOT intact, TiiEN e open 8T47, alt charg to LP 3 cold leg viv. e close 8146, norr.al charg to LP 4 cold leg O viv. V
- e. OPEN 8105 and 8106, cent cnarg pps mir flow vivs (VE2)
- f. CLOSE 8145 and 8148, charg line to PZR aux spray viv ar.d bypass (VEE)
- 9. OPEN 8105 and 8107, normal charg to regen hx stop vlvs 1 & 2 (VB2)
- h. CLOSE 8803A and 8803B, BIT inlet vivs (VB2)
- 1. Set makeup batch integrators for primary water and boric acid to maximum (all 9s) (CC2)
O l DC0436 21V I l l l
NUMBER EP ECA-1.1 1 AND 2 REVISION 0 OIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 22 0F 23 LOSS OF EMERGENCY C0OLANT RECIRCULATION tit a APPENDIX W (Continued) ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- j. Select manual on makeup mode selector and turn makeup control switch to START (CC2)
- k. Adjust ficw as follows: (VB2) e 200 gpm primary water flow e 10 gpm Boric Acid Flow
- 4. Start charging pumps and adjust flow as necessary:
- a. Start cent charg pp(s) (V62)
- AND/0R -
e Ensure CCW flow to PD charg pp h e Start PD charg pp
- 2) ADJUST charging and HCV-142 to maintain VCT level l
1 O DC0436 22V
1 AND 2 NUMBER EP ECA-1.1 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/12/85 O) PAGE 23 0F 23 7,7 g LOSS OF EMERGENCY COOLANT RECIRCULATION APPENDIX Z E EMERGENCYPROCEDURENOTIFICATIONINSTRUCTIOM
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows.
- a. In the event that inadequate emergency coolant recirculation is verified, reclassify this event as a General Emergency,
- b. Notify plant staff and response ~ organizations required for this classification by implementing Procedures EP G-2
" Establishment of the On-Site Emergency Organization" and EP G-3 " Notification of Off-Site Organizations" in accordance with EP G-1 " Accident Classification and Energency Plan Activation.
A b l l l l O 0C0436 23V i
1 l
-e m NUMBER EP ECA-1.2 ( ._r e VJ d- Pacific Gas and Electric Company REVISION 0 l DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 3/11/85 OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 4 ,
l j EMERGENCY PROCEDURE TITLE LOCA OUTSIDE CONTAINMENT b IMPORTANT i AnPROveo X C TMm 32515 SAFET/ To PLANTMANAGERM DATE l l SCOPE This procedure provides directions to identify and isolate a LOCA outside containment. This procedure and changes thereto requires PSRC l review. ; SYMPTOMS OR ENTRY CONDITIONS This procedure is entered f rom E-0, REACTOR TRIP OR SAFETY INJECTION, Step 28, cr. abnormal radiation in the auxiliary building due to a loss L of RCS inventory outside containment. O DC0417 IV
NUMBER EP ECA-1.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/11/85 PAGE 2 0F 4 TITLE. LOCA OUTSIDE CONTAINMENT ACTION XPEuw RESPONSE RESPONSE NOT OBTAINED
- 1. VERIFY Proper Valve Alignment: Manually close bkrs and valves.
Verify the following valves - CLOSED E valves can NOT be manually be closed, 8702, RCS LP 4 hot leg THEN locally close valves. to RHR 1st off (VB2) 8701, RCS LP 4 hot leg to RHR 2nd off (VB2) 8703, RHR to hot legs 1 & 2 (VB1) 8802A, SI to hot legs 1 & 2 (VB1) 8802B, SI to hot legs 3 & 4 (VB1)
- 2. TRY To identify And Isolate Break:
- a. Sequentially close and reopen each of the valves listed below.
After each valve closure, monitor RCS pressure to see if it stops decreasing. Leave valve closed if pressure stabilizes or starts increasing. Manually close valve bkrs or series contactors as necessary. 8809A, RHR to cold legs 1 & 2 (VB1) 88098, RHR to cold legs 3 & 4 (VB1) 8835, SI pump to cold legs (VB1) 8700A, RHR pp No. I suct (VB1) 87008, RHR pp No. 2 suct (VB1) ? IF
-~
break was found in RHR suction line, THEN close 8980 RWST suction to RHR pps (VB2) O DC0417 2V l
i DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON 0 DATE 3/11/85 i PAGE 3 0F 4 TITLE LOCA OUTSIDE CONTAINMENT l ACTION /EXPECTEDREsPONsE RESPONSE NOT OBTAINED i
- 3. CHECK If Break Is Isolated:
- a. RCS Pressure - INCREASING a. Go to ECA-1.1, LOSS OF (VB2) EMERGENCY COOLANT RECIRCULATION.
- b. Go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT
- END -
O DC0417 3V
otABLO CANYON POWEA PLANT UNIT NO(S) 1 AND 2 5 ON DATE 3/11/85 PAGE 4 0F 4 TITLE LOCA OUTSIDE CONTAINMEN1 O APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows.
- a. Classify this event as a SITE AREA EMERGENCY.
- b. In the event that the LOCA outside containment cannot be isolated or inadequate core cooling is verified, reclassify this event a GENERAL EMERGENCY.
- c. Notify plant staff and response organizations required for this classification by implementing Procedures EP G-2
" Establishment of the On-Site Emergency Organization" and EP G-3 " Notification of Off-Site Organizations" in accordance with EP G-1 " Accident Classification and Emergency Plan Activation.
O 1 O DC0417 4V
NUMBER EP ECA-2.1 7 Gut 3 Pacific Gas and Electric Company REVISION 0 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 3/12/85 I PAGE 1 0F 27 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2
. EMERGENCY PROCEDURE
.1 TITLE UNCONTROLLED DEPRESSURIZATION OF U ALL STEAM GENERATORS IMPORTANT APPROVED PLANT MANAGER CI DATE SAFETY PURPOSE This procedure provides actions for a loss of secondary coolant which affects all steam generators. This procedure and changes thereto requires PSRC review.
SYMPTOMS OR ENTRY CONDITIONS This guideline is entered from E-2, FAULTED STEAM GENERATOR ISOLATION, STEP 2, when an uncontrolled depressurization of all stearr generators O CCCurs. O DC0411 11V
1 AND 2 S ON DIABLO CANYON POWER PLANT UNIT NO(S) OATE 3/12/85 PAGE 2 0F 27 UNCONTROLLED DEPRESSURIZATION OF M LE ALL STEAM GENERATORS ACTION / EXPECTED RESPONSE ESPONSE NOT OBTAltE CAllTICth e If any SG pressure increases at any time during this procedure, E-2, FAULTED STEAM GENERATOR ISOLATION, should be performed. e FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, should be implemented only if a total feed flow capability of 460 gpm is not available at any time during this procedure. o If the turbine-driven AFW pump is the only available source of feed flow, steam supply to the turbine-driven AFW pump must be maintained from one SG.
- 1. CHECK Secondary Pressure Boundary: Manually close valves.
e Main steamline isolation and IF valves can NOT be closed
~
bypass valves - CLOSED (VB3) TFEN dispatch operator to locally close valves, one loop at a e FW control and bypass valves - time. CLOSED (CC3/VB3) e FW isolation valves - CLOSED (VE3) O e Steam supply valves to turbir.e-driven AFW pumps - CLOSED (VE3) e SG blowdown isolation valves - CLOSED (VB3) ...__............. O DC0411 2!V
1 AND 2 ME P Ed-2.1 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 UNCONTROLLED DEPRESSURIZATION OF TITLE ALL STEAM GENERATORS ACTION / EXPECTED RESPONSE RESPONSE t0T OBTAINED i CAUTION: A minimum feed flow of 25 gpm must be maintained to each SG with a narrow range level less than 4%[20%).
- 2. CONTROL Feed Flow To Minimize RCS Cooldown:
- a. Check cooldown rate in RCS cold a. Decrease feed flow to 25 gpm to legs - LESS THAN 100*F in a ore each SG. Go to Step 2c.
HR period (VB2)
- b. Check narrow range level in all b. Control feed ficw to maintain SGs - LESS THAN 50% (VB3) narrow range level less than 50% in all SGs.
- c. Check RCS hot leg temperatures - c. Control feed flow or dump steam
{ } STABLE OR DECREASING (VB2) to stabilize RCS hot leg temperatures. NOTE: Seal injection flow shculd be maintained to all RCPs.
- 3. CHECK If RCPs should Be Stopped:
- a. ECCS pumps . AT LEAST ONE RUNN!hG a. Go to Step 4.
e One Cent Charging Pump (VB2)
. OR .
e One SI pump (V81)
- b. RCS pressure LESS THAN 1275 b. Go to Step 4.
psig (VB2)
- c. Stop all RCPs (VB2) i I OC0411 31V
NUMBER EP ECA 2.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 PAGE 4 0F 27 UNCONTROLLED DEPRESSURIZATION OF TITLE ALL STEAM GENERATORS ACTION / EXPECTED RESPONSE RE5PON$ENOTOBTAINED
- 4. CHECK CST Level . GREATER THAN 10%: Switch to alternate AFW water (VB3) supply. (Refer to E.2.1)
CAUTION: If any PZR FORV opens because of high PZR pressure, Step Sb should be repeated after pressure decreases to less than PORV setpoint.
- 5. CHECK PZR PORVs And Stop Valves:
(VB2)
- a. Pcwer to stop valves - AVAILABLE a. Restore power to stop valves.
- b. PORVs . CLUSED b. IF PZR pressure less than 2335 psig, THEN manually close PORVs IF any valve can NOT be closed.
THEN manually close its stop valve.
- c. Stcp valves - AT LEAST ONE OPEN c. Open one stop valve unless it was closed to isolate an open PORV.
O DC0411 4IV
NUMBER EP ECA-2.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 UNCONTROLLED DEPRESSURIZATION OF M LE. ALL STEAM GENERATORS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i CAllTION: e If offsite power is lost af ter SI reset, manual action may be required to restart safeguards equipment. Refer to Appendix A if this condition occurs, e RCS pressure should be monitored. If RCS pressure decreases to less than 300 psig, the RHR pumps must be manually restarted to supply water to the RCS.
- 6. CHECK If RHR Pumps Should Be StopDed
- a. Check RCS pressure: (V82)
- 1) Pressure - GREATER THAN 300 1) Go to E-1, LOSS OF REACTOR OR PSIG SECONDARY COOLANT.
- 2) Pressure - STABLE OR 2) Go to Step 7.
( ) INCREASINd
- b. Reset SI it necessary (VB1)
- c. Stop RHR purrps and place in standby (VB1)
- 7. CHECK If Containment Spray Shculd Be Stopped: (v81)
- a. Spray purrps . RUMilhG a. Go to Step 8.
- b. Containment pressure - LESS THAN b. Continue with Step 8.
20 PSIG WHEN containment pressure less than 20 psig THEN do Steps 7c and d.
- c. Reset containment spray
- d. Stop containment spray pumps l I DC0411 SIV
NUMBER EP ECA.2.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 PAGE 6 0F 27 TITLE UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS g ACTION /EXRCTED RESFU4SE RESPONSE NOT OBTAINED
- 8. CHECK RWST Level - GREATER THAN 33%: Go to E.1.3, TRANSFER TO COLD LEG (VB2) RECIRCULATION.
- 9. CHECK If ECCS Flow Should Be Reduced (VB2)
- a. RCS subcooling based on core exit a. Return to Step 2. OBSERVE TCs - GREATER THAN 20*F CAUTION PRIOR TO STEP 2.
- b. RCS pressure - STABLE OR b. Return to Step 2. Observe INCREASING CAUTION prior to step 2.
- c. PZR level - GREATER THAN 4;[20%] c. Try to stabilize RCS pressure with norral FZR spray. Return to Step 9a.
CxfTION: If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment. Refer to Appendix A if this g condition occurs.
- 10. RESET SI (VB1)
- 11. RESET Containrent Isolation Phase A Arc Fnase B (VBlj
- 12. ESTABLISH Instrurent Air To Start one air compressor (Refer to Containc.ent (VB4) OP AP-9, LOSS OF INST AIR) and continue in this procedure.
e Open FCV 584 Containment Inst Air Iso Viv e Check one Inst Air Compressor Running
- 13. STOP All But One Cent Charging Pump
?
(iB2)
- 14. CHECK RCS Pressure - STABLE OR Return to Step 2. OBSERVE CAUTICN IhCREASING (VB2) PRIOR TO STEP 2.
O DC0411 6!V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 y gg DATE 3/12/85 O PAGE 7 0F 27 UNCONTROLLED DEPRESSURIZATION OF TITLE ALL STEAM GENERATORS ACTION / EXPECTED RESPmSE RESPONSE NOT OBTAINED
- 15. ESTABLISH Charging Flow:
- a. Throttle to 501 HCV-142 RCP Seal Backpress Cont Viv (CC2)
- b. OPEN FCV-128 Cent Charg Pps Flow Cont Viv (CC2)
- c. OPEN 8105 and 8106 Cent Charg Pps c. IF 8105 or 8106 will NOT open Min Flow Vivs (VB2) TiiEN maintain a minimum of 60 gpm charging flow.
- d. IF- LP 4 SG Intact d. !F LP 4 SG NOT Intact TiiEN 1) OPEN CTCT 6147 Alt THEN OPEN CVCS-8146 Normal Charg to LP 3 Cold leg Charg to LP 4 Cold Leg Viv.
Viv(VS2)
- 2) CLOSE CVCS 8146 Normal
- e. CLOSE CVCS-8145 and 8148 Charg Charg to LP 4 Cold Leg Line to PZR Aux Spray Vlv and Viv.
Bypass (VS2)
- f. OPEN CVCS-8108 and 8107 Normal Charg to kegen Hx Stop Vivs 1 & 2 (VE2)
- g. Start One Cent Charg Pp (VB2)
- OR .
e Ensure CCW Flow to PC Charg Pp e Start PD Charg Pp (V52) .
- h. ADJUST FCV-128 Cent Chg Pps Flow Control /PD Charging Pump speed and HCV.142 RCP Seal Inj Back press cont viv to maintain 60 gpm charging flow (CC2)
DC0411 71V
NUMBER EP ECA.2.1 CIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 PAGE 8 0F 27 UNCONTROLLED DEPRESSURIZATION OF TITLE ALL STEAM GENERATORS O ACTION /EXPtiuw RESPONSE RESPONSE f0T OBTAINED
- 16. ISOLATE BIT: (VB2)
- a. Close 8803A & B BIT supply vivs
- b. Close 8801A & B BIT outlet vivs
- 17. CONTROL Charoino Flow To Maintain -
IF PZR level continues to PZR Level: (CC2) decrease, THEN realign charging flow path through BIT. Return to step
- 2. OBSERVE CAUTION PRIOR TO STEP 2.
- 18. CHECK If SI Purnps Sheuld Be Stopped:
- a. Check RCS pressure: (VB2) a. Return to Step 2. Observe CAUTION prior to Step 2.
e Pressure - GPEATER ThAN 1650 PSIG e Pressure - STABLE OR INCREASING
- b. Stop SI pumps (VB1) g
- 19. STOP PHR Purcs (VB1)
- 20. VERIFY ECCS Flow hot Required: (VB2)
- a. RCS subcooling based on core exit a. Manually operate 51 pumps as TCs - GREATER THAN 20'F necessary. Return to Step 2.
OBSERVE CAUTION PRIOR TO STEP 2.
- b. PZR level - GREATER THAN 41[20t] b. Control charging flow to maintain PZR level
~
IF PZR level can NOT be maintained, THEN manually operate ECCS pumps as necessary. ? Return to Step 2. OBSERVE CAUTION PRIOR TO STEP 2. DC0411 8!V
NUMBER EP ECA-2.1 1 AND 2 DIAsLO CANYON POWER PLANT UNIT NO(S) REVISION 0
.DATE 3/12/85 O PAGE 9 0F 27 'd TITLE UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 21.bHECKRCSHotLegTemperatures- Control feed flow or dump steam to STABLE OR DECREASIhG (VB2) stabilize RCS hot leg temperatures.
- 22. CHECK Narrow Range Level In All SGs Control feed flow to maintain
- LESS THAN 50% (VB3) narrow range level less than 50%
in all SGs.
- 23. CHECK PZR Level - GREATER THAN Control charging as necessary.
17%L40'.J (VB2)
- 24. ESTABLISH Letdown:
- a. OPEN FCV-355 CCW Hdr C Iso Viv 1) PLACE Charg Pp Control in (VB1) Manual and Recuce Charg Flcw to Min.
- b. Position to 50% PCV 135 Lten Press Cent Viv (\B2) 2) CLOSE CVCS-8107 and 8108 Charg p)
( c. OPEii LCV-459 and 460 Lten Stop Hdr Iso Vivs. Vivs (VB2) 3) Adjust Charging to Maintain Seal Injection 6-12 GFM.
- d. ENSURE 45 gpm Charg Ficw through Regen Hx (CC2) 4) e IF MOV-8100 and 8112 OPEN, TREN Place CVCS-8143 In
- e. PLACE IN AUTO LCV-112A VCT Lvl Normal Position (VCT)
Cont Divert Viv (VB2) Excess Ltdn to Seal Wtr Hx or RCOT Viv.
- f. 0FEfe CVCS-8152 Ltdn Iso Vlv OC (VB2) e IF MOV-8100 and 8112 CLOSED.
THEN Place CVCS-8143 in RCOT Position. THIS STEP C0flTINUED ON NEXT PAGE O DC0411 91V
NUMBER EP ECA-2.1 otAsto CANYON POWEd Pt. ANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 PAGE 10 0F 27 UNCONTROLLED DEPRESSURIZATION OF TITLE ALL STEAM GENERATORS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- g. OPEN: 5)OPEN:
e 8149A 45 GPM e FCV-355 CCW Hdr C Iso Viv.
- AND/0R -
e 81498 75 GPM e FCV-361 CCW From Excess LTON
- AND/0R - HX.
e 8149C 75 GPM (VB2) 6) CLOSE HCV-123 Excess Ltdn Flow Cont Viv.
- h. Maintain 350 psig on PI-135 with PCV-135 Ltdn Press Cont Viv 7) OPEN CVCS.8166 and 8167 Excess Ltdn Stop Vivs.
o Set PCV-135 controller to 350 psig 8) OPEN HCV-123 As Necessary To Maintain: AND Place in AUTO if desired (VS2) e PZR LVL.
- 1. Adjust charging flow to maintain LESS THAN 380*F on TI-127 (VS2) e LESS THAN 190'F as TI-122.
- 25. CHECK VCT Makeup Control System: Adjust controls as necessary.
e Ensure makeup set for - GREATER THAN RCS BORON CONCENTRATION OR 2000 PFP (7 turns /CC2) e Makeup set for automatic: (Refer to OP B.1A:VII CVCS - PAKEUP CONTROL SYSTEM OPERATION Part A . PLACE IN AUTOMATIC) e Instrument air - AVAILABLE
?
O OC0411 10!V
i OlABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 1 ON DATE 3/12/85 O TITLE UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS PAGE 11 0F 27 ACTION / EXPECTED ESPONSE ESPONSE t0T OBTAINED 26.kLIGNChargingPumpSuctionToVCT (VB2) IF VCT and makeup system - AVAILABLE THEN ALIGN Charging Pump Suction From the VCT if desired: a) Open VCT outlet valves LCV-1128 and LCV-112C b) Close Charg Pp Suct from RWST vivs 8605A and 8805B
- 27. CHECK If RCP Seal Return Flow Shculd Be Established;
- a. Verify: a. Go to Step 28.
C e No core clad damage e RCP Seal Return NOT isolated due to suspected seal damage
- b. Initiate Seal Return as follows:
- 1) CLOSE any RCP al Seal Ret Iso Viv with GREATER THAN 6 gpm Return Flow Indicated:
8141A RCP 1 8141B RCP 2 8141C RCP 3 81410 RCP 4 (VB2)
- 2) OPEN FCV-355 CCW Hde C !so Viv (VB1)
- 3) OPEN M0V.8100 and 8112 RCP Seal Ret Iso Vlvs (VB2) t sa
- DC0411 111V l
l .
NUMBER EP ECA-2.1 DIAsto CANYON POWED PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 PAGE 12 0F 27 M LE UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS h ACTION / EXPECTED RESPONSE RESP 0f6E NOT OBTAINED
- 28. CONTROL PZR Pressure:
- a. Turn en heaters and operate a. IF nonnal spray NOT available normal spray as necessary to and letdown is in service, maintain pressure stable THEN use auxiliary spray.
IF NOT, TREN use one PZR PORV.
- 29. CHECK RCP Cooling . NORMAL
- a. RCP el Seal Ret and Lower Radial a. Refer to Appendix R for RCP Brg Temp <225'F (VB2) seal cooldown.
- b. Verify CCW - ALIGNED To RCPs b. IF CCW NOT ALIGNED TO RCPs
(', B 1) TREN ensuFPhase B isolation
- reset and manually cpen e FCV-355, CCW HDR C ISO VLV - CCW valves.
OPEN e FCV.356, CCW TO RCP OIL COOLERS, THERM BAR & SUP CLRS - OPEN e FCV-357, CCW FROM RCP ThEPPAL BAPRIER, OC - OPEN e FCV-363, CCW FROM kCP OIL CLRS
& SUP CLRS, OC - OPEN e FCV-749, CCW FROM RCP OIL CLRS
& SVP CLRS, IC - OPEN e FCV-750, CCW FROM RCP THERFAL BARRIER IC - OPEN
- c. Verify RCP seal injection flow to c. Adjust HCV-142 to maintain 6-12 each RCP - At 8 (6-12) GPM (V82) gpm to each RCP.
O DCC411 121V
NUMBER EP ECA-2.1 DIAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/65 PAGE 13 0F 27
~/ UNCONTROLLED DEPRESSURIZATION OF TITLE:
ALL STEAM GENERATORS ACTION / EXPECTED RESPWSE RESPONSE NOT OBTAINED
- 30. ERIFY All AC Busses - ENERGlZED BY Try to restore offsite power.
OFF5ITE POWER (VB4) IF power can NOT be restored. TREN manually load the following equipment on the vital busses within DG capacity (2.6 MW): o PZR heaters (Refer to OP A-4A:1,PZRMAKEAVAILABLE) e TSC
- 1) OPEN 52-22J-40.
- 2) OPEN 52-2F-47.
- 3) OPEN 52-1F-67.
O' 4) SWITCH EPTSN to VITAL POWER.
- 5) IF D/G 13 on U1 F bus, TREN switch EPTSC te U-1 (52-1F-67) and CLOSE 52-1F-67.
IF 0/G 13 on U2 F bus,
- 6) TREN switch EPTSC to U-2 (52-2F-47) and CLOSE 52-2F-47.
TRANSFER SWITCHES EPTSN and EPTSC are located in UNIT 2 BUS F 480 Volt Switchgear Room, e Instrument Air l l DC0411 13IV i i
1 1 AND 2 ON OtABLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 14 0F 27 TITLE UNCONTROLLED DEPRESSURIZATION OF PAGE g' l ALL STEAM GENERATORS ACTION /EXFtuto ESPONSE RESPONSE NOT OBTAINED CAUTION: e If RCP seal cooling had previously been lost, the affected RCP(s) should not be started prior to a statas evaluation. (Refer to Appendix R for hot, > 225'F, RCP seal cooldown) e On natural circulation, RTO bypass temperatures and associated interlocks for Steam Dump Feed Line Iso and High Stm Flow SI will be inaccurate. NOTE: RCP No.1 (preferred) or No. 2 should be run to provide nonnal PZR spray.
- 31. CHECK RCP Status - AT LEAST ONE Try to start one RCP:
AUY l M (VS2) a. Establish conditions in App B for starting an RCP.
- b. Start one RCP.
IF an RCP can NOT be started TIIEN verify natural circulation: e RCS subcooling based on core exit TCs - GREATER THAN 20*F. (VB2) e SG pressures - STABLE OR DECREASING.(VB3) e RCS hot leg temperature - STABLE OR DECREASING. (VB2) e Core exit TCs - STABLE OR DECREASING. (PAMS 3/4/SP05) e RCS cold leg temp - AT SATURATION TEMPERATURE FOR SG PRE 55URE. (VB2/VB3) ? IF natural circulation NOT
- verified, THEN increase feed flow or dumping steam.
O OC0411 141V , i
l l NUMBER EP ECA.2.1 otAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION O 7- s DATE 3/12/85 Q PAGE 15 0F 27 UNCONTROLLED DEPRESSURIZATION OF mLE ALL STEAM GENERATORS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 32. CHECK If SR Detectors Should Be Energized: (CCl)
- a. Check IR Flux - LESS THAN 10~10 a. Continue with Step 33.
amps WHEN flux is less than 10 10 amps, THEN do Step 32b, c and d.
- b. Verify both SR detectors - b. Manually reset and energize ENERGIZED both SR detectors.
- c. Select highest SR ar.d IR detector en NR-45 recorcer
- d. If desired place SR audio count O rate circuit in operation
- 33. CHECK If Diesel Generators should Be Stopped: (VE4)
- a. Verify ac emergency busses - a. Try to restore offsite power to EhERGIZED BY OFFSITE POWER ac emergency busses.
- 34. SHUT Down Unnecessary Plant Ecuipment (Refer to OP L-5 PLANT FROM MIhIMUM LOAD TO COLD SHUTDOWN)
- 35. MAINTAIN Plant Conditions . STABLE e PZR pressure e PZR level e RCS temperatures O
m DC0411 ISIV
NUMBER EP (CA-2.1 DiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 PAGE 16 0F 27 UNCONTROLLED DEPRESSURIZATION OF TITLE- ALL STEAM GENERATORS ACTION / EXPECTED RESPONS~ RESPONSE NOT OBTAINED
- 36. VERIFY ECCS Flow Not Required: (VB2)
- a. RCS subcooling based on core exit a. Manually operate ECCS pumps as TCs - GREATER THAN 20*F necessary.' Return to Step 2.
OBSERVE CAUTION PRIOR TO STEP 2.
- b. PZR level - GREATER THAN 4%[20%) b. Controi charging flow to maintain PZR level IF PZR level can NOT be maintained.
THEN manually operate ECCS pumps as necessary. Return to Step 2. OBSERVE CAUTION PRIOR TO STEP 2.
- 37. CHECK If SI Accumulators Shculd Be Isolatea:
- a. Check the following: a. Go to Step 38.
(V82) e RCS subccoling based on core exit TCs . GREATER THAN 20*F e PZR level . GREATER THAN 4%[20%]
- b. Check power to isolation valves . b. Restore power to isolation AVAILABLE valves.
THIS STEP CONTINUED ON NEXT FAGE O DC0411 161V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Y ON DATE 3/12/85 PAGE 17 0F 27 fi v' UNCONTROLLED DEPRESSURIZATION OF TRE ALL STEAM GENERATORS ACTION / EXPECTED RESPChSE RESPONSE NOT OBTAINED
- h. Close all SI accumulator isolation c. Vent any unisolated valves 8808A, B, C & D (VB1) accumulators:
- 1) Close accumulator N IIII isol viv FCV.8880. 2 2)OpenaccumulatorN2 supply vent to affected accumulator.
3)Openaccumulatorh2 supply vent HCV-943 UNTIL accumulator is depressurized.
- 38. CHECK RCS het Leo Temperatures Control feed ficw and dump steam
. LESS THAN 350"F (V62) to establish a cooldown rate less than 100'F/HR in RCS cold legs.
- 39. CHECK RCS - LESS THAN 390 PSIG (VB2) Use normal PZR spray.
IF normal spray NOT available and letdown is in service, THEN use auxiliary spray. IF NOT, TREN use one PZR FORV. - a e DC0411 171V l
NUMBER EP ECA-2.1 otAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 PAGE 18 0F 27 UNCONTROLLED DEPRESSURIZATION OF m LE. ALL STEAM GENERATORS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 40. CHECK If RHR System Can Be Placed in Service: (VB2)
- a. Check the following: a. Return to Step 36.
e RCS temperature - LESS THAN 350*F e RCS pressure - LESS THAN 390 PSIG
- b. Place RHR System in service using OP B 2:V, RHR _ PLACE IN SERVICE DURING PLAr,T C00LDOWN
- 41. CONTINUE Cooldcwn To Cold Shutdown:
- a. Maintain cooldown rate in RC cold legs - LESS THAN 100*F in any one HR period
- b. Check narrow range level in all b. Control feed flow to maintain O
SGs . LESS THAN 50% narrow range level less than 50% in all SGs.
- 42. CHECK RCS Temperatures - LESS THAN Return to Step 41.
200'F (VB2) l l l O DC0411 181V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h ON 0 DATE 3/12/85 PAGE 19 0F 27 O. TiTa UNCONTROLLED DEPRESSURIZATION OF i ALL STEAM GENERATORS ; l ACTilW/ EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 43. VALUATE Long Term Plant Status:
- a. Maintain cold shutdown conditions e RCS temp < 200*F e K,ff < .99
- b. Check containment atmosphere to determine if hydrogen recombiners or if hydrogen purge should be placed in service
- c. Implement OP L-5 PLANT C00LDOWN FROM MINIMUM LOAD TO COLD SHUTDOWN and review for applicable actions
- d. Check STP M-55 CYCLIC REVIEW
- e. Consult plant engineering staf t
- END -
O l DC0411 191V l l l
I l OlA3LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 [V ON ' DATE 3/12/85 PAGE 20 0F 27 UNCONTROLLED DEPRESSURIZATION OF TITLE ALL STEAM GENERATORS ! APPENDIX A BLACK 0UT EMERGENCY LOADING OF VITAL BUSSES
- 1. If the vital busses lose voltage prior to resetting the safety injection signal, the vital busses will automatically load the vital equipment given below. Verify the equipment has been loaded by observing breaker lights on the control board.
- 2. If the vital busses lose voltage after the safety injection signal has been reset, load or verify loaded the equipment given below onto the vital busses manually. Allow approximately 4 seconds between loading of each piece of equipment onto a given vital bus. Load or verify that the CFCU are running in Low Speed.
VITAL BUS VITAL BUS VITAL BUS F G H U-1 (D/G 1-3) U-1 (D/G No. 2)- U-1 (D/G No. 1) U-2 (D/G 1-3) U-2 (D/G No.1) U-2 (D/G No. 2) MCC F MCC G MCC H CCPp No. 1 RHR Pp No. 1 SI Pp No. 1 CFCU No. 3 SI Pp No. 2 CFCU No. 2 CFCU No. 5 RHR Pp No. 2 CFCU No. 1 CCW Pp No. 2 CFCU No. 4 CCW Pp No. 1 ASW Pp No. 2 CCW Pp No. 3 ASW Pp No.1 CC Pp No. 2 AFW Pp No. 2 AFW Pp No. 3
- 3. Load the containment spray Pumps only if they were running prior to the blackout.
VITAL BUS VITAL BUS G H Cont Spray Pp No. 1 Cont Spray Pp No. 2
?
O DC0411 20!V
N DIABLO CANYON POWER PL. ANT UNIT NO(S) 1 AND 2 R ON 0 DATE 3/12/85 [' PAGE 21 0F 27 UNCONTROLLED DEPRESSURIZATION OF TITLE. ALL STEAM GENERATORS APPENDIX B Restart of Reactor Coolant Pump
- 1. Start oil lift pump, run for 2 minutes.
- 2. Verify CCW available to thennal barrier, oil coolers, seal water HX.
- 3. Verify seal dp greater than 215 psid, depressurize VCT as necessary.
- 4. Verify seal injection flow 8 (6 to 12) gpm.
- 5. Verify seal leak off flow within limits shown on graph.
- 6. Ensure Closed PCV-455A & B, Normal PZR Spray Vivs.
ALL0hABLE RCP #1 SEAL LEAK RATES i . j r
' +
I ! , I ; ' 4 i ;
- i
, SHU'DOWN RCP WITHlN f
; ONE HALF HOUR l l l l
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00 NOT START RCP i f l i f '
! I i 0
200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 RCP #1 SF.4L DIFFERENTIAL PRESSURE PSID REGION 1 NO PHASE-A $1GNAL, dp=RCS press -VCT,,,,, PHASE A PRESENT. do=RC5 press -150psig REGION 2 USE INSTALLED dp GAUGES DC0411 21IV t l l
MB U ECA-2.1 otAst.o CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 PAGE 22 0F 27 TITL.E. UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS g APPENDIX C 2600
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.-- 1- ' !
200 300 400 500 600 700 CORE EXIT T/C TEMPERATURE (*F) i O DC0411 22IV 1 1 i
DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 ON l l DATE 3/12/85 UNCONTROLLED DEPRESSURIZATION OF N ALL STEAM GENERATORS APPENDIX R IF RCP SEAL RETURNS OR LOWER RADIAL BEARING TEMP HAS BEEN OR IS >225 F PERFORM THE FOLLOWING: ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. CHECK RCP Seal Isolation Status:
- a. Verify seal injection iso ylvs a . ]_F valves open or position OC - CLOSED not known, THEN check centrifugal CVCS-8369A, B. C & D - CLOSED RCP charging pump status:
Seal Water Containment Isol Vivs (100' Aux Bldg Pent Area GE - !F pump running, 127' tc 137') 1) TREN return to Step 33 CHECK RCP COOLING - NORMAL.
- 2) IF pump NOT running,
{ } TEENmanuaITForlocally close seal injection vivs 0C.
- b. FCV-357 - CLOSED RCP therm bar b. IF- valve is open or CCW return isc viv OC (100' position not known, Aux Bldg Pent Area, GE-166') ThEN check CCW pump status:
(VEI) IF a pump is running,
- 1) TREN go to Step 1B Appendix R.
IF pump NOT running,
- 2) TREN manuaIG or locally close FCV-357.
IF FCV-357 can NOT be closed, THEN manually close FCV-750, CCW return viv IC. 6 DC0411 23IV
NUMBER EP ECA-2.1 otAato CANYON P0WER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 PAGE 24 0F 27 UNCONTROLLED DEPRESSURIZATION OF TIRE: ALL STEAM GENERATORS ACTION /EXPEutD RESPONSE RESPONSE NOT OBTAINED CAUTION: e RCP thermal barrier cooling should be established slowly to minimize potential introduction of steam into the CCW system. e RCP seal injection should be established slowly to minimize RCP thermal stresses and potential seal failures. e As part of subsequent recovery actions, RCPs should not be started prior to a status evaluation, unless responding to Inadequate Core Cooling FR-C.I.
- 2. ESTABLISH RCP Seal Cooling:
- a. Establish CCW flow to RCP thermal barriers (100' Aux Bldg Pent Area GE-166*)
- 1) Establish ccmunications between the control room and 100' Aux Bldg Pent Area near FCV-357 CCW from RCP Thern Bar, OC
- 2) Mcnitor RCP lower bearing temperature (TI-152,153,154, 155/VB2)
- 3) Check FCV-357 - CLOSED RCP 3) Close FCV-357 Therm Bar CCW Return Iso Viv - OR -
OC (VB1) CCW-267.
- 4) Check FCV-750 - OPEN. RCP 4) IF-- FCV-357 or CCW-267 Therm Bar CCW Return Iso Viv CLOSED, IC (VB1) THEN open FCV-750.
i l t THIS STEP CONTINUED ON NEXT PAGE O DC0411 241V
i DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/12/85 PAGE 25 0F 27 UNCONTROLLED DEPRESSURIZATION OF TITLE- ALL STEAM GENERATORS ACTION / EXPECTED RESRESE ESPONSE NOT OBTAINED EN)TE: Monitor flow on FI-90 (Locally at TCV-3567) and temperature on TI-1004 (locally at FCV-357). Initiate flow to the thermal barrier slowly reducing lower bearing temperature (TI 155, 154, 153, 152 on VB2 and T0417A, T0437A, T0457A, T0477A on the P250) at a maximum rate of l'F per minute until full thennal barrier flow is returned to normal. Some local boiling may occur in the ECW lines giving a closed signal to FCV-357.
- 5) Locally crack open FCV-357 or CCW-267
- b. Establish Seal Injection Flow to RCFs (100' Aux Bldg Pent Area GE-127* - 137')
- 1) Wait until seal leak off water temperature (TI-148, 146, 131, 125) has decreased to 235'F
- 2) Establisn communications between control room and the 100' Aux Bldg Pent Area near the RCP seal water injection flow control valves CVCS-8369A, B, C & D N)TE: Monitor RCP Seal Inj Flow No. I seal leak off temperature and lower RCF bearing temperature. Reduce each respective RCP bearing temperature at a maximum rate of 1 F per minute until bearing temperature is less than 225*F, then nonnal seal injection flow can be established.
- 3) Crack open CVCS-8369A, B, C and D one at a time i O,,
DC0411 25IV
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/12/85 PAGE 26 0F 27 UNCONTROLLEO DEPRESSURIZATION OF TITLE. ALL STEAM GENERATORS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. AFTER RCP Seal Cooldown - VERIFY Normal RCP Cooling Alignment:
- a. IF CCW NOT aligned to RCPs,
- a. Verify CCW (VB1)
TREN ensure Phase B Isolation is reset and manually e FCV-355 - OPEN CCW to RCP oil CLRS, therm BAR & SUP CLRS open CCW valves. e FCV-357 - OPEN CCW from RCP THERM BAR, OC e FCV-363 - OPEN CCW from RCP OIL CLRS & SUP CLRS, OC e FCV-749 - OPEN CCW from RCP OIL CLRS & SUP CLRS IC e FCV-750 - GPEN CCW from RCP THERM BAR IC - OPEN
- b. Verify RCP seal injection flow to b. ADJUST FCV-128 cent chg Pps each RCP - AT 8 (6 to 12) GPM flow control viv/PD Charg Pp (VB2) speed and RCP seal inj back press viv and HCV-142 to maintain 6 to 12 gpm to each RCP.
- 4. REFER To Step 34 - CHECK If RCP Seal Return Flow Should Be Establishea -
In Inis Procedure i 1 l ? OC0411 26IV g
N ' DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON O DATE 3/12/85 27 0F 27 - C~ UNCONTROLLED DEPRESSURIZATION OF PAGE M LE: ALL STEAM GENERATORS APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Designate this event a Notification of Unusual Event.
- b. If the depressurization of all steam generators is accompanied with a known primary to secondary leakage >10 gpm as indicated by high radiation alarms on the air ejector, steam generator blowdown, sample or by an increase in steam generator water level in an unexpected manner, designate this event as an Alert.
- c. If primary to secondary leakage exists and is estamated at
>50 gpm with fuel damage evident from a gross failed fuel monitor alarm or primary sample, designate this event as a Site Area Emergency. ~
- d. In the event inadequate core cooling is verified per Critical Safety Function Status or the verification of the ESF Functioning and Effectiveness during LOCA, Appendix H of procedure EP E-1, indicates ESF failure, reclassify this event as a General Emergency.
- 2. Notify plant staff ano response organizations in accordance with EP G-2 and EP G-3 and implement the instruction in EP G-1 regarding onsite and offsite protective actions.
DC0411 271V
. .._ _ _ _ _ _ __ _. . . _ = _ _ _ _ . _ _ _ . _ . _ .. _ . - _ _ - _ . . ..-
i i j FOLD 0VT FOR ECA-2.1 , ADMINISTRATIVE FUNCTION 5 l 4 1. Notify STA and monitor CSF and SPDS
- 2. Refer to Appendix Z 1
SI REINITIATION CRITERIA l
- Manually operate ECCS pumps as necessary if EITHER condition listed below occurs:
e RCS subcooling based on core exit TCs - LESS THAN 20*F e PZR level - CANNOT BE MAINTAINED GREATER THAN 4%[20%] E-2 TRANSITION CRITERION l Go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1, if any SG pressure increases at any time. COLD LEG RECIRCULATION SWITCHOVER CRITERION l i 1 Go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION Step 1, if RWST level decreases to less than 335. AFW SUPPLY SWITCHOVER CRITERION l Switch to alternate AFW water supply if CST level decreases to less than 10% (Refer to E-2.1 Alternate Auxiliary Feedwater Supplies) ADVERSE C0hTAIhMEhT I , GREATER THAN 3 psig Containment Pressure
! GREATER THAN 105 R/hr Containment Rad. Dose Rate GREATER THAN 106 R Containmant Rad Dose N WY TO SECONDARY DIFFEREhTIAL PRE 55URE l Depressurize the RCS to maintain the primary to secondary pressure difference less than 1600 psid, provided RCS subcooling is GREATER
, THAN 20*F AND PZR level is GREATER THAN 4%. [20%] i DC0411 281
^~3'I 33%G Pacific Gas and Electric Company REVISION 0 7
DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 3/12/85 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 41 EMERGENCY PROCEDURE
~
4 SGTR WITH LOSS OF REACTOR COOLANT - TITLE SUBC00 LED RECOVERY DESIRED IMPORTANT APPROVED W l 6 TO PLANT MANAGF& DATE SAFETY SCOPE This procedure provides actions to cool down and depressurize the RCS to cold shutdown conditions while minimizing loss of RCS inventory and voiding in the RCS. This procedure and changes thereto requires PSRC review. SYMPTOMS OR ENTRY CONDITIONS Q This procedure is entered from the following procedures: V
- 1. E-3, STEAM GENERATOR TUBE RUPTURE, Step 3, if a ruptured SG can not be isolated from any intact SG.
- 2. E-3, STEAM GENERATOR TUBE RUPTURE, Step 5, if PZR PORV cannot be isolated by closing its stop valve.
- 3. E-3, STEAM GENERATOR TUSE RUPTURE, Step 13, if a ruptured SG pressure is less than the low steamline pressure SI setpoint.
- 4. E-3, STEAM GENERATOR TUBE RUPTURE, Step 14, if no intact SG is available for RCS cooldown.
- 5. E-3, STEAM GENERATOR TUBE RUPTURE, Step 15, if a ruptured SG pressure continues to decrease following RCS cooldown.
- 6. E-3, STEAM GENERATOR TUBE RUPTURE, Step 16, if RCS subcooling is less than required.
- 7. E-3, STEAM GENERATOR TUBE RUPTURE, Step 19, if RCS pressure does not increase after closing PZR PORV and stop valve.
- 8. E-3, STEAM GENERATOR TUBE RUPTURE, Step 20, and ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 6, if SI can not be terminated.
l f3 V DC0402 IIV i
NUMBER EP ECA-3.1 l 1 AND 2 REVISION 0 l OIABLO CANYON POWER Pt. ANT UNIT NO(S) DATE 3/12/85 PAGE 2 0F 41 l SGTR WITH LOSS OF REACTOR COOLANT - TITLE. SUBC00 LED REC 0VERY DESIRED l
- 9. E-3, STEAM GENERATOR TUBE RUPTURE, Step 25 and ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 12, if SI flow is required.
- 10. ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 23, if RCS pressure is less than technical specification for the maximum SI accumulator nitrogen pressure.
O
?
O DC0402 2IV
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON o DATE 3/12/85 PAGE 3 0F 41 SGTR WITH LOSS OF REACTOR COOLANT . I'T1 SUBC00 LED REC 0VERY DESIRED
. ACTION / EXPECTED RESPCriSE RESPONSE NOT OBTAINED i
CAUTION: e If RWST level decreases to less than 33%, the SI System should be aligned for cold leg recirculation using E-1.3, TRANSFER TO COLD LEG RECIRCULATION. e If offsite power is lost after SI reset, manual action will be required to restart some safeguards equipment. Refer to Appendix A if this condition occurs. e If subcooling monitor becomes inoperable, determine subcooling by using WR RCS pressure and core exit TCs (Refer to APPENDIX C). NOTE: Foldout page should be open.
- 1. RESET SI (VB1)
- 2. RESET Both Trains of Containment Isolation Phase A anc Phase B (VB1)
- 3. ESTABLISH Instrument Air to Try to establish air. (Refer to Containment: (V64) 0F AP-9, LOSS OF INSTRUMENT AIR.) Avoid excessive cycling
- a. Open FCV-584 CNMT inst of valves that have backup air.
air iso viv
- b. Verify at least one air compressor - IN SERVICE o
l l DC0402 31V 1 I
NUMBER EP ECA-3.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 PAGE 4 0F 41 m LE: SGTR WITH LOSS OF REACTOR COOLANT . SUBC00 LED REC 0VERY DESIRED g ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. VERIFY All AC Busses Try to restore offsite power.
- ENERGIZED BY OFFSITE POWER (VB4) E power can NOT be restored.
THEN manually load the following equipment on the vital buses within DG capacity (2.6 MW): o PZR heaters (Refer to OP A-4A:1, PZR MAKE AVAILABLE) e TSC
- 1) OPEN 52-22J-40.
- 2) OPEN 52-2F-47.
- 3) OPEN 52-1F-67.
- 4) SWITCH EPTSN TO VITAL POWER.
- 5) E 0/G 13 on U1 F bus, THEN switch EPTSC to U-1 (52-1F-67) and CLOSE 52-1F-67.
- 6) IF 0/G 13 on U2 F bus, THEN switch EPTSC to U-2 (52-2F-47) and CLOSE 52-2F-47.
e I.nstrument Air Compressor
- 5. CHECK If Containment Spray Snouia Be 5 topped:
- a. Verify Containment Spray a. -
IF Containment Spray was Actuation - PK 01-18 IN NOT actuated, ' ALARM THEN go to Step 6. OBSERVE CAUTION PRIOR TO STEP 6. THIS STEP CONTINUED ON NEXT PAGE g DC0402 4IV
OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON n DATE 3/12/85 PAGE 5 0F 41 l SGTR WITH LOSS OF REACTOR COOLANT - 1 TITLE: SUBC00 LED REC 0VERY DESIRED ' 1
, ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- b. Verify containment b. -
IF containment radiation radiation levels - NORMAL levels are above normal, e R-2, Containment Area THEN ensure spray system is Monitor (RMS I) still in operation and go to Step 6. OBSERVE e R-30, Containment Area CAUTION PRIOR TO STEP Monitor (PAM 2) 6. (Hi Range) e R-31, Containment Area Monitor (PAM 2) (Hi Range)
- c. Verify containment c. IF
~-
pressure is greater pressure - LESS THAN 20 than 20 psig, s) psig(VB1) THEN perform the following:
- 1) Reset Containment Spray Trains A & B.
- 2) Close Spray Additive Tank Outlet Valves, MOV-8994 A & B.
- 3) Ensure Spray System is still in operation and continue with Step 6.
- 4) Stop both containment spray pumps when containment pressure is less than 20 psig.
THIS STEP CONTINUED ON NEXT PAGE i l O l t DC0402 SIV l
NUMBER EP ECA-3.1 O!AsLO CANYON POWER rLU4T UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 PAGE 6 0F 41 SGTR WITH LOSS OF REACTOR COOLANT - TITLE. SUBC00 LED REC 0VERY DESIRED ACTION / EXPECTED RESPCNSE RESPONSE NOT OBTAINED
- d. Stop containment spray pumps (VB1)
- 1) Reset Containment Spray Trains A & B
- 2) Stop Containment Spray Pumps
- 3) Close Spray Additive Tank Outlet Valves, 8994 A & B CAUTIC6: RCS Pressure should be monitored. If WR RCS pressure decreases to less than 300 psig, the RHR pumps must be manually restarted to supply water to the RCS.
- 6. CHECK If RHR Pumos Should Be Stopped:
- a. Check WR RCS Pressure: a. Go to Step 7.
(VB-2) e STABLE OR INCREASIhG e kk RCS Pressure - GREATER THAN 300 PSIG e RHR pumps not supplying containment spray
- b. Stop both RHR pumps (VB1)
?
O l DC0402 6IV l
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/12/85 SGTR WITH LOSS OF REACTOR COOLANT - TITLE SUBC00 LED REC 0VERY DESIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. INITIATE Evaluation Of Plant 5tatus:
- a. Evaluate RCS Leakage c.s -
IF Any RCS leakage follows: indications ABNORPAL, THEN evaluate sources of e Check PRT pressure and leakage and isolate, if level - BELOW HIGH ALARM possible. SET POINT (VB2) e Check containment structure sump level - BELOW HIGH ALARM SET POINT (PAM1) e Check radiation monitors for RCS leakage outside cor.tainment - GREATER THAN ALARM SET F0 INT { I) (RMS-I, II & III/PAM 2';
- 1) R-4 Recip.
Charging Pump Roen
- 2) R-6 NSSS Sampling Room
- 3) R-10 Auxiliary Building (Unit 1 only) ----------------
- b. Samole the RCS:
- 1) For activity
- 2) For boron (implement 2) Borate as necessary.
STP R-19, Shutdown Margin Calculation) DC0402 71V
l l DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h0N DATE 3/12/85 PAGE 8 0F 41 SGTR WITH LOSS OF REACTOR COOLANT - l TITLE l SUBC00 LED REC 0VERY DESIRED ACTION /D?ECTED RESPONSE RESPONSE NOT OBTAINED
- 8. CHECK If SGs Are Not Faulted:
- a. Check pressures in all a. Verify all faulted SG(s)
SGs(VB3) isolated unless needed for RCS cooldown: e N0 SG PRESSURE DECREASING IN AN e Steamlines UNCONTROLLED MANNER e Feedlines e NO SG COMPLETELY DEPRESSURIZED - IF a faulted SG is NOT isolated. THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION. O-DC0402 8IV O
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/12/85 (O,) PAGE 9 0F 41 SGTR WITH LOSS OF REACTOR COOLANT - TITLE: SUBC00 LED RECOVERY DESIRED
, ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: Alternate water sources for AFW pumps will be necessary if CST level decreases to less than 10% (Refer to E.2.1, ALTERNATE AUXILIARY FEE 0 WATER SUPPLIES).
- 9. CHECK Intact SG Levels: (VB3)
- a. Check intact SG(s) NR a. Maintain total feed flow level - GREATER THAN greater than 460 gpm 4%[20%]
UNTIL NR level is greater than 4%[20%] in at least one SG.
- b. Control feed flow to b. -
IF NR level in any intact maintain SG NR level SG continues to ,~ between4%[20i]and33% increase in an uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE.
- c. Step TD AFW PP if NOT needed for RCS heat removal DC0402 91V
P ECA-3.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 g DATE 3/12/85 PAGE 10 0F 41 SGTR WITH LOSS OF REACTOR COOLANT - TITLE: SUBC00 LED REC 0VERY DESIRED ACTION / EXPERTED ESPONSE RESPONSE NOT OBTAINED NOTE: e Shutdown margin should be monitored during RCS cooldown. (Refer to STP R-19 Shutdown Margin Calculation.)
- 10. INITIATE RCS Cooldown To Cold Shutdown:
- a. Maintain cooldown rate in RCS cold legs - LESS THAN 100*F in a one hour period (SPOS Panel B)
- b. Use RHR ff in service
- c. Dump steam to condenser c. Manually or locally dump from intact SG(s) steam from intact SG(s) 10%
Steam Dump Valves.
- 1) Check ALL MSIVs NOT ISOLATED IF no intact SG available, TREN perform the following:
- 2) Check C-9 condenser available PK08-14 status e Use faulted SG light - ON
-0R-
- 3) Set HC-507 at 8.38 turns IF RHR system NOT in
- 4) Transfer Steam Dump Mode service, Switch to Steam Pressure THEN use ruptured SG.
Mode
- 5) Place to CONT ONLY, LCV-12 selector switch
- 6) Adjust controller setpoint or manually adjust steam pressure controller to establish desired cooldown rate
- 7) At P-12 activation ?
select BYPASS INTERLOCK on both selector switches DC0402 10lv 1 l
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 f0N DATE 3/12/85 PAGE 11 0F 41 I'I # SGTR WITH LOSS OF REACTOR COOLANT . SUSC00 LED REC 0VERY DESIRED ACTION /EXPEuto RESPONSE RESPONSE NOT OBTAINED
+
- 11. CHECK RCS Subcooling: (VB2) Go to Step 26. '
- GREATER THAh 20"F
- 12. CHECK If Subcooled Recovery Is Appropriate:
- a. Check RWST level . a. Refer to Appendix E to GREATER THAN 60% (VB2) determine expected containment sump level.
IF containment sump level less than expected. THEN go to ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT SATURATED REC 0VERY DESIRED.
- b. Check ruptured SG narrow b. Consult plant engineering rance level - LESS THAN staff to determine if 96%[90i](VB3) recovery should be completed using ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT -
SATURATED RECOVERY DESIPED.
- 13. CHECK If ECCS Is In Service: Go to Step 22.
e Charging flow through BIT - NOT ISOLATED (VB2)
-OR-e SI Pumps - AftY RUNNING (VBI)
- 14. PLACE All PZR Heater Switches In OFF Positior. (CCl) l O l i DC0402 111V i I
l OtAB:.0 CANYON POWED PLANT UNIT NO(S) 1 AND 2 ON j DATE 3/12/85 1 PAGE 12 0F 41 SGTR WITH LOSS OF REACTOR COOLANT - I' M SUBC00 LED RECOVERY DESIRED ACTION /EXFECTED RESPCNSE RESPONSE NOT OBTAINED CAUTION: e Voiding may toccur in the RCS during RCS depressurization. This will result in a rapidly increasing PZR level. e Auxiliary spray flow into the PZR shall not be initiated if the delta-T between the PZR and the spray fluid exceeds 560 F. Spray flow should not be initiated if the delta.T exceeds 320 F. NOTE: When PZR Auxiliary spray is used it may be necessary to close normal spray PCV 455A & B and charging valves A0V-8146 and 8147.
- 15. DEDRESSURIZE RCS To Refill PZR:
- a. Use normal PZR spray (CC2) a. F I F, normal PZR spray E available, THEN use Auxiliary Spray.
(VE-2) g Auxiliary Spray NOT available or desired, THEN use one PZR PORV. (VB2)
- b. PZR level - GREATER THAN b Continue with RCS 17%[40i] (VB2) depressurization.
WHEN PZR level is greater 17%[40%], THEN go to Step 15c.
- c. Stop RCS depressurization AND Maintain RCS pressure -
- STABLE Using PZR Heaters, spray and FORVs as neces.sary 9
l DC0402 121V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 V _ ON DATE 3/12/85 FN PAGE 13 0F 41 SGTR WITH LOSS OF REACTOR COOLANT - TITLE. SUBC00 LED REC 0VERY DESIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: e If seal cooling has previously been lost, the affected RCP(s) should not be started prior to status evaluation, e On natural circulation, RTD bypass temperatures and associated interlocks for feedline Iso, Steam Dump and High Steam Flow SI will be inaccurate. ETE: All but one RCP may be stopped to minimize pump heat input. If maintaining a 100*F/hr cooldown, running 2 RCPs is desirable; RCP 1 or 2 (#2 preferred) for normal PZR spray and RCP 3 or 4 to maximize MD AFW pump capacity. In addition it is desirable to have an RCP running in a nonfaulted loop.
- 16. CHECK If An RCP Should Be Startec: (Vb-2)
- a. Check All RCFs . STOPPED a. Perform the following:
- 1) Stop all but one or two RCPs.
- 2) Close normal spray viv on any idle loop.
- 3) Go to Step 17. OBSERVE NOTES PRIOR TO STEP 17.
- b. Check RCS Subcooling - b. Go to Step 26.
GREATER THAN 20*F
- c. Check PZR level GREATER c. Return to Step 15. OBSERVE THAN 17%[401] NOTE AND CAUTIONS PRIOR TO STEP 15.
THIS STEP CONTINUED ON NEXT PAGE O DC0402 131V
DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 fSf0N DATE 3/12/85 PAGE 14 0F 41 I tit e SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED REC 0VERY DESIRED ACTION /EX CTED RESPONSE RESPONSE NOT OBTAINED
- d. Try to start an RCP: d. Go to Step 17. OBSERVE NOTES PRIOR TO STEP 17.
- 1) Establish conditions for starting an RCP as per Appendix B
- 2) Start one RCP POTE: e After stopping any ECCS pump, WR RCS pressure should be allowed to stabilize before stopping another ECCS pump.
(Approximately 5 minutes) e The Cent, charging pumps and SI pumps should be stopped on alternate ECCS trains when possible.
- 17. CHECK If One Cent Charcing Puac 5hould Be Stooped:
- a. Two Cent charging pumps - a. Go to Step 18.
RUNNING (VB2)
- b. Determine required RCS subcooling from table:
SAFETY INJECTION REOUIRED RCS SUBC00 LING (*F) Pumo Status Any RCP Running No RCP Running hone Running 58cF 73 F One Running 52 F 55*F Two Running 52*F 55*F
- c. RCS subcooling - GREATER c. Go to Step 26.
THAN REQUIRED SUBC00 LING (VB2) ,
- d. PZR level - GREATER THAN d. Return to Step 15, 17'a[40%] (V82)
- e. Stop cne cent charging pump (VB1)
DC0402 141V
N 1 AND 2 REV S ON ; omsLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 (O
'd TITLE-SGTR WITH LOSS OF REACTOR COOLANT .
SUBC00 LED REC 0VERY DESIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OETAIN9
- 18. CHECK If One SI Pump Should Be Stopped:
- a. Any SI pump - RUNNING a. Go to Step 19.
(VB-1)
- b. Detemine required RCS subcooling from table:
51 PUMP REQUIRED RCS SUBC00 LING ("F) STATUS One Cent. Charging No Cent. Charging Pump Running Pumo Running Any RCP No RCP Any RCP No RCP Running Running Running Running One Do not Do not
/~ Funning 94*F 117*F stop SI PP Stop SI FP
( Two Running' 29'F 33*F 37 F 46*F
- c. Check RCS Subcooling - c. Go to Step 26.
GREATER THAN RECUIDED SUSC00 LING (VE2)
- d. Cneck PZR level - GREATER d. Return to Step 15. OBSERVE THAN 17%[40*] (VB2) NOTE AND CAUTIONS PRIOR TO STEP 15.
l
- e. Stop one additional SI pump (VBI)
- f. Go to Step 26 I
DC0402 151V
P ECA-3.1 otABLo CANYON POWER PLANT UNIT NO(S) 1 AND 2 [V ON DATE 3/12/85 PAGE 16 0F 41 SGTR WITH LOSS OF REACTOR COOLANT - TITLE. SUBC00 LED RECOVERY DESIRED ACTION /EXftutu RESPONSE RESPONSE NOT OBTAINED
- 19. Check If Normal Charging Should Be Established:
- a. Verify ECCS pump status: a. Go to Step 26.
(VB1/VB2) e Both SI pumps - STOPPED e Cent charging pumps - ALL BUT ONE STOPPED
- b. RCS subcooling based on b. Go to Step 26.
core exit TCs - (PAM3/4) GREATER THAN 84*F IF ANY RCP RUNNING
-CR-GREATER THAN 101*F IF NO O
RCP RUNNING
- c. PZP level - GREATER THAN c. Return to Step 15. CBSERVE 175[40t](VB2) NOTE AND CAUTIONS PRIOR TO STEP 15.
- 20. ESTABLISH Charging Flow:
(VB-1)
- a. Throttle to 50% HCV_142 RCP Seal Backpress Cont Viv
- b. Open FCV-128 Cent Charg Pps Flow Cont Viv
- c. Open MOV 8105 and 8106 c. IF
~~~
8105 or 8106 will NOT Charg Pps 11 and 12 Min open, Flow Recirc Vivs THEN maintain a minimum of 60 gpm charging flow. THIS STEP CONTINUED ON NEXT PAGE I I l 1 DC0402 161V
DIABLO CANYON POWER PLANT UNIT NO(Si 1 AND 2 [0N DATE 3/12/85 PAGE 17 0F 41 (- % M LE. SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED REC 0VERY DESIRED ACTION / EXPECTED RESPONSE EsPONSE NOT OBTAINED
- d. Check LP 4 SG Intact d. IF LP 4 SG NOT Intact.
TREN e Open 8T47 Alt Charg e OPEN 8146 Normal Charg to LP 3 Cold Leg Vlv. to LP 4 Cold Leg Viv , o Close 8146 Normal e Close 8147 Alt Charg to Charg to LP 4 Cold LP3 Cold Leg viv Leg Viv.
- e. Close 8145 and 8148 Charg Line to PZR Aux Spray Viv and Bypass
- f. Open 8108 and 8107 Normal Charg to Regen Hx Stop Vivs 1&2
- 21. ISOLATE BIT: (VB-2)
- a. Close 8803A and B BIT supply vivs
- b. Close 8801A and B BIT outlet vivs
- 22. Control Charoina Flow To Maintain PZR Level (CC2) i V
DC0402 171V
NUMBER EP ECA-3.1 l DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ' REVISION 0 DATE 3/12/85 PAGE 18 0F 41 SGTR WITH LOSS OF REACTOR COOLANT - TH LE-SUBC00 LED REC 0VERY DESIRED 1 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAtJTION: e If RCP seal cooling has previously been lost, the affected RCP(s) should not be started prior to a status evaluation. e On natural circulation, RTD bypass temperatures and associated interlocks for Feedline Iso, Steam Dump and High Stm Flow SI will be inaccurate. NOTE: All but one RCP may be stopped to minimize pump heat input. If maintaining a 100*F/hr cooldown, running 2 RCPs is desirable; RCP 1 or 2 (#2 preferred) for nomal PZR spray and RCP 3 or 4 to maximize MD AFW pump capacity.
- 23. CHECK RCP Status:
- a. RCPs - AT LEAST ONE RUNNING a. Try to start one RCP.
- 1) Check RCP seal ret and lower Rad Brg Temp
<225'F. (VB2)
IF >225 F, Refer to Appendix R and go to Step 24.
- 2) ESTABLISH PZR conditions l as follows:
i e PZR level - 67i;[90%] for RVLIS Full range l
<95%
- OR -
e PZR level - 17*,[40%] l for RVLIS Full range . >95% l - AND - e PZR Temp - At , saturation for RCS Hot - Leg Temp. THIS STEP CONTINUED ON NEXT PAGE l t O DC0402 181V
NUMBER EP ECA-3.1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/12/85 PAGE 19 0F 41 O SGTR WITH LOSS OF REACTOR COOLANT -
>O TITLE SUSC00 LED REC 0VERY DESIRED ACTION /EXECTED RESPONSE RESFONSE NOT OBTAINED
- 3) Close Normal Spray Vlvs PCV-455A and B. (CC2)
- 4) Establish RCS Subcooling based on core exit TCs -
35'F.
- 5) Establish conditions for starting an RCP per Appendix B.
- 6) Start one RCP.
IF an RCP can NOT be started, THEN manually close both normal PZR spray vivs and verify natural circulation: e RCS subcooling based on core exit TCs GREATER THAN 20*F. e SG pressures-STABLE OR DECREASING. e RCS hot leg temperatures-STABLE OR DECREASING. e Core exit TCs STABLE OR DECREASING. 1 e RCS cold leg i temperatures-AT l SATURATION TEMPERATURE FOR SG PRESS. e Dump steam from intact 1 I SGs to maintain adequate RCS heat removal.
- b. Stop all but one RCP (VB2)
- c. Close the normal spray v1v I on any idle loop (CC2) j l
l DC0402 191V
= - -
l
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/12/85 PAGE 20 0F 41 SGTR WITH LOSS OF REACTOR COOLANT - I' " SUBC00 LED RECOVERY DESIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: e Voiding may occur in the RCS during RCS depressurization. This will result in a rapidly increasing PZR level. e Auxiliary spray flow into the PZR shall not be initiated if the delta-T between the PZR and the spray fluid exceeds 560'F. Spray flow should not be initiated if the delta-T exceeds 320*F. NOTE: When PZR Auxiliary spray is used it may be necessary to close nonnal spray PCV 455A & B and charging valves A0V 8146 and 8147.
- 24. DEPRESSURIZE RCS To Minimize RCS Subcooling:
- a. Use normal PZR spray (CC-2)
- AND/0R -
auxiliary spray O
- AND/0R -
PZR PORV
- b. Turn on PZR heaters as necessary (CC1)
- c. Depressurize RCS until EITHER of the following conditions satisfied:
(VB2) e PZR level
- GREATER THAN 77%[70%)
-0R- ,
o RCS subcooling
- LESS THAN 20 F DC0402 20lv
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/12/85 b 'd SGTR WITH LOSS OF REACTOR COOLANT - PAGE 21 0F 41 M LE. SUSC00 LED RECOVERY DESIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
> 25. VERIFY Adequate Shutdown Margin:
- a. Sample ruptured SG
- b. Sample RCS
- c. Determine shutdown margin c. Borate as necessary (Refer ADEQUATE (Implement STP to B-1A:VIII - CVCS - MAKEUP R-19, SHUTDOWN MARGIN CONTROL SYSTEM OPERATION.)
CALCULATION)
- 26. VERIFY ECCS Flow Not Recuired:
- a. Verify RCS Subcooling - a. hanually operate ECCS pumps GREATER THAN 20*F as necessary to maintain RCS O subcooling 20*F i AND '
Go to Step 27.
- b. Verify PZR level - GREATER b. Manually operate ECCS pumps THAN 4'.[20%] as necessary to restore PZR level AND Return to Step 15. OBSERVE NOTE AND CAUTIONS PRIOR TO STEP 1S.
O DC0402 21IV
NUMBER EP ECA-3.1 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/12/85 PAGE 22 0F 41 SGTR WITH LOSS OF REACTOR COOLANT - TITLE. SUBC00 LED REC 0VERY DESIRED ACTION / EXPECTED RESRESE RESPONSE NOT OBTAINED
- 27. CHECK If SI Accumulators Should Be Isolated:
- a. RCS pressure >1000 psia a. Go to Step 28.
- b. RCS subccoling based on b. IF
~~'
RCS hot leg temperature core exit TCs - GREATER GREATER THAN 400 F, THAN 70*F (VB2) THEN go to Step 28.
- c. Check power to accum disch c. Restore power to isolation iso vlvs - AVAILABLE valves.
- d. Close all accum disch iso d. IF any accumulator vivs (VB1) isolation valve does NOT close, 8808A THEN Perform the folicwing:
88088 1) Close FCV 888Q accumulator N' 8808C fill iso viv.
- 2) Open 8875A, B, C, or 8808D D accum N 7 supply and vent viv to affected accum.
- 3) Daen HCV 943 accum N' supply line vent UNTIL accumulator is depressurized and continue in this procedure.
O DC0402 22IV
m - N DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R S ON DATE 3/12/85 PAGE 23 0F 41 f) v SGTR WITH LOSS OF REACTOR COOLANT - M LE. SUBC00 LED RECOVERY DESIRED ACTION / EXPECTED ESPONSE ESPONSE NOT OBTAINED
> 28. CHECK If Diesel Generators Should Be Stopped: (VB4)
- a. Check vital busses F, G and a. Try to restore offsite H - ENERGIZED BY OFFSITE power, either STARTUP or POWER AUXILIARY, to the vital busses.
- b. Stop any unloaded diesel gene:ator and place in -
AUTO O O DC0402 231V
u otAs O CANTON POWER PLANT UNIT NO(S) 1 AND 2 pEV ON DATE 3/12/85 I PAGE 24 0F 41 l SGTR WITH LOSS OF REACTOR COOLANT -
"- SUBC00 LED REC 0VERY DESIRED l ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 29. MINIMIZE Secondary System contamination:
- a. Isolate reject as follows: a. Locally close CND-49 or 52.
- 1) Manually close LCV-12 condensate reject viv
- 2) Sample the hotwell
- 3) Use reject, in manual, based on hotwell sample results
- 4) Maintain CST level below the overflow
- b. Isolate condensate polisher demins: (VB3)
- 1) Open FCV-230 CNDS Polisher bypass viv
- 2) Close FCV-231 CNDS Polisher inlet valve
- c. Transfer aux steam supply to aux boiler (Refer to OP K-5 IV, Part B)
- d. Ensure MSRs isolated
- e. Ensure main feed pumps e. Transfer MFP gland seal to gland seal supplied from Aux Boiler.
Aux Boiler
- f. Manually transfer blowdown tank outlet from outfall to EDRT (FCV-498 closed and FCV-499 opened)
- g. Verify blowdown and sample g. Manually isolate blowdown.
blowdown isolation has occurred O DC0402 24!V l 1
NUMBER EP ECA-3.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 PAGE 25 0F 41 (N (,) SGTR WITH LOSS OF REACTOR COOLANT - ) TITLE: SUSC00 LED RECOVERY DESIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 30. CHECK RCP Cooling Normal:
- a. RCP Seal Return and Lower a. Refer to Appendix R and go Rad Brg Temp < 225 F (VB2) to Step 32.
- b. Verify CCW - ALIGNED T0 b. IF
~~~
CCW NOT aligned to RCPs (VB1) RCPs: THEN 1) RESET Phase B e Open FCV-355, CCW HDR C isolation. (VB1) 150 VLV 2) Manually open CCW e Open FCV-356, CCW TO RCP valves. OIL CLRS THERM BAR & SUP CLRS e Open FCV-357, CCW FROM RCP THE RM EAR OC e Cpen FCV-363, CCW FROM RCP OIL CLRS & SUP CLRS ,O s/ CC e Open FCV-749, CCW FRCM RCP OIL & SUP CLRS e Open FCV-750, CCW FROM RCP THE RM BAR IC
- c. Verify RCP seal injection c. Adjust HCV-142 as necessary, flow 8 (12) GPM to each RCP seal inj back pressure RCP (VE2) viv.
v DC0402 251V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h ON DATE 3/12/85 PAGE 26 0F 41 SGTR WITH LOSS OF REACTOR COOLANT - TITLE- SUBC00 LED RECOVERY DESIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 31. CHECK If RCP Seal Return Flow Should Be Established:
- a. Check RCP seal return was a. Go to Step 32.
NOT isolated due to suspected seal damage
- b. Initiate seal return as follows:
- 1) Close ANY #1 seal ret iso ylv with GREATER THAN 6 GPM seal ret flow indicated (VB2)
RCP #1 Seal Ret Vlv 1 8141A 2 8141B 3 8141C 4 81410
- 2) CPEN FCV 355 CCW hdr C is ily (V61)
- 3) Ensure CCW flow to the seal ret hx
- 4) OPEN 8100 and 8112 RCP seal ret iso vivs (VB2)
?
9 DC0402 261V
1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) h0N DATE 3/12/85 m PAGE 27 0F 41 gd m LE-SGTR WITH LOSS OF REACTOR COOLANT - SUSC00 LED RECOVERY DESIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 32. CHECK If S.R. Detectors Should Be Energized: (CC1)
- a. Check IR Flux a. Continue with Step 33.
- LESS THAN 10~10 AMPS WHEN flux less than 10 10 amps, THEN complete Steps 32b and c.
- b. Verify both SR detectors - b. Manually reset and energize ENERGIZED both SR detectors.
- c. Select highest SR & IR detectors on NR 45
- 33. Shut Down Unnecessary Plant Eauipment:
- a. Stop any running plant equipment not required for post accident re:overy (Refer to OP L-5 PLANT COOLDOWN FROM MINIMUM LOAD TO COLD SHUTDOWN)
O DC0402 271V
otAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/12/85 PAGE 28 0F 41 I'7
- SGTR WITH LOSS OF REACTOR COOLANT -
SUBC00 LED REC 0VERY DESIRED g ACTION / EXPECTED PESPONSE RESPONSE NOT OBTAINED CAlfTION: Feed flow should not be established to any ruptured SG which is also faulted unless needed for RCS cooldown.
- 34. CHECK Ru3tured SG(s) NR Level Refill ruptured SG to 67%
- GREATEl THAN 4%L20tj (VB3) using feed flow unless faul ted.
IF either of the following conditions occurs, e Ruptured SG pressure decreases in an uncontrolled manner,
-OR-e Ruptured SG pressure increases to 1010 psig, THEN stop feed flow to the ruptured SG unless needed for RCS cooldown.
O DC0402 28IV , i
l N OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 RV ON O DATE 3/12/85 s PAGE 29 0F 41 s SGTR WITH LOSS OF REACTOR COOLANT - TITLE SUBC00 LED REC 0VERY DESIRED l
. ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEL
- 35. CHECK If RCPs Must Be Stopped:
- a. Check the following: (VB2) a. Go to Step 36.
e Number 1 seal differential pressure
- LESS THAN 215 PSID 0R.
e Number 1 seal leakoff flow outside limits of Appendix B
- b. Stop affected RCP(s)
(VB2)
- c. Close normal spray ylv en
' - any idle loop (CC2) a DC0432 291V
NUMBER EP ECA-3.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 PAGE 30 0F 41 SGTR WITH LOSS OF REACTOR COOLANT . T'T'E SUBC00 LED REC 0VERY DESIRED gg ACTION /EMutD RESPONSE RESPONSE NOT OBTAINED
- 36. CHECK If RHR System Can Be Placed In cervice:
- a. Check RCS conditions to a. Go to Step 37.
place RHR system and overpressure protection
- IN SERVICE e RCS temperature
- LESS THAN 350 F e RCS cold leg temp -
GREATER THAN 323*F e RCS WR pressure
- LESS THAN 390 PSIG
- b. Place overpressure protection system - IN SERVICE
- c. Consult plant engineering c. IF RHR is NOT to be placed staff to determine if RHR in service, system should be placed in THEN go to Step 37.
service
- d. Implement OP B-2:V, RHR .
PLACE IN SERVICE DURING PLANT C00LDOWN
- 37. CHECK RCS Temperature Return to Step 9. OBSERVE
- LESS ThAN 200*F CAUTION PRIOR TO STEP 9.
O DC0402 30IV
1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) [V ON DATE 3/12/85 p PAGE 31 0F 41 V N SGTR WITH LOSS OF REACTOR C0OLANT - SUBC00 LED RECOVERY DESIRED ACTION / EXPECTED ESPONSE ESPONSE NOT OBTAINED
- 38. EVALUATE Long Term Plant Status:
- a. Consult plant staff in Technical Support Center for venting approval.
(Refer to FR-I.3, RESPONSE TO V0 IDS IN REACTOR VESSEL)
- b. Maintain cold shutdown conditions:
e RCS temp < 200*F eKeff * '99
- c. Check containment atmosphere to determine if O\ hydrogen recombiners or it hydrogen purge should be placed in service
- d. Implement OP L-5 PLANT C00LDOWN FROM MINIMUM LOAD TO COLD SHUTDOWN and review for applicable actions
- e. CHECK STP M-55 cyclic review
- f. Consult plant engineering staff
-END-i DC0402 31IV
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 I ON DATE 3/12/85 PAGE 32 0F 41 SGTR WITH LOSS OF REACTOR COOLANT - TITLE SUBC00 LED REC 0VERY DESIRED APPENDIX A BLACK 0UT EMERGENCY LOADING OF VITAL BUSSES
- 1. If the Vital busses lose voltage prior to resetting the safety injection signal, the vital busses will automatically load the vital equipment given below. Verify the equipment has been loaded by observing breaker lights on the control board.
- 2. If the vital busses lose voltage after the safety injection signal has been reset, load or verify loaded the equipment given below onto the vital busses manually. Allow approximately 4 seconds between loading of each piece of equipment onto a given vital bus. Load or verify that the CFCU are running in Low Speed.
VITAL BUS F VITAL BUS G VITAL BUS H U-1 (D/G 1-3) U-l (D/G No. 2) U-l (D/G No. 1) U-2 (D/G 1-3) U-2 (D/G No. 1) U-2 (0/G No. 2) MCC F MCC G MCC H CCPp No. 1 RhR Pp No .1 SI Pp No.1 CFCU No. 3 SI Pp No. 2 CFCU No. 2 CFCU No. 5 RHR Pp No. 2 CFCU No. 1 CCW Pp No. 2 CFCU No. 4 CCW Pp No. 1 ASW Pp No. 2 CCW Pp No. 3 ASW Pp No. 1 CCPp No. 2 AFW Pp No. 2 AFW Pp No. 3
- 3. Load the containment spray Pumps only if they were running prior to the blackout.
VITAL BUS G V!TAL BUS H Cont Spray Pp No. 1 Cont Spray Pp No. 2 s 1 . 1 1 O DC0402 321V
E DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 S ON DATE 3/12/85 p< SGTR WITH LOSS OF REACTOR COOLANT - PAGE 33 0F 41 I'7* SUSC00 LED RECOVERY DESIRED
, APPENDIX B Restart of React r Coolant Pump
- 1. Start oil lift pump, run for 2 minutes.
- 2. Verify CCW available to thermal barrier, oil coolers, seal water HX.
- 3. Verify seal dp greater than 215 psid, depressurize VCT as necessary.
4 Verify seal injection flow 8 (6 to 12) gpm.
- 5. Verify seal leak off flow within limits shown on graph.
- 6. Ensure Closed 455A and 8, Normal PZR spray vlvs (Auto Optional).
ALL0wAELE RCP #1 SEAL LEAK RATES i I 4 SHUTDCwN RCP WITHIN ONE MALF HOUR , . . 3 l i r i I I ! .
^
3 ; j l ,
, l 1 y2
; l SAFE OPERAf!NG RE,GION l . l i ;
! l 1 I ,
iREGION . REGION g l , 2 I I g !
/ 00 NOT STA8T RCP l l ' i 0
200 400 600 800 1000 1200 1400 1600 1800 2000 2200 240v RCF 81 SF4L O!FF(RINTIAL PR(55Lt P510 m REGION 1 NO PHA$(.A $!GNAL, \-) dp*RCS,,,,,-VCT,,,,, PHA5(.A FR[5[NT, press -150psig dp*RC5 REGION 2 Uit INSTALLED dp GAUGts i DC0402 331V
NUMBER EP ECA-3.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 PAGE 34 0F 41 SGTR WITH LOSS OF REACTOR C00LANI - TITLE SUSC00 LED REC 0VERY DESIRED g APPENDIX C 2600 _
. . . _._ . _._.._._.._.._......_._L._._.<_
==. ==-1r-[.5
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. __ __i _ _ _
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. _ _ _ . . _ . '__. . _ . . _' _ _ . , _ _ . _ . . _ ~ -- #,
* ~= -- ~ 7'
~ _ ' _ . . _;_._ .
2400 _ _- -
- =E_f=_"; .; .
___. l -- _ _ _ . - -._-_--- = - .,=g+=1 = l -]=, _: =_ - 2200 _ . . . _ , _ _ . _ _ . . _ . . - . _ _ _ . _ ____._. .__. . _ , . 1 __ __ /==f, :=2- -. f.=_'" -f =*& .
~~
-.'__..___.c._'.__-,j_[..f..~._."._. ~'"
2000 r"" __t-
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=__ . : '* ~ _ . .
___. f-.=_ 1 t __- _=_ __t, : : _;-_ =. _ =. ._:_-t V r. _r. . _- : .t ~.~.=.=. : . f.=__ 1800 g r " [ 5 _".. $ - ._".d [_-~_ 3 l E=F.2:-i =-E.! :'- j;.-h J _ii - - t { _-- 4
- _ _: =___=_ _2. ==. _=._;: =__.=. =._ _ _g_=_. . ;. _=_:._.=_
.} r. =. . =.d._;.=y.
f,.i . 1600 .
.._.______.__......__.__.,___._...[...._,._.._.._..g:-~.r.i..:.:.:=
___.___=_-t_..__t.=_=.__3_._.._-._-..__g_.--+-.}=._' y . _. x - y
,---- - + ---. -- g -- _;- --- + = ; _-- ; = = ; = z.-'-~"~~*==$=~-_~;_ ~
a
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g 1400 . . ._...7___._.".__...______~.._._.___",_;____; . _ ; __ . . . '_q_ , m . Q. D ___.i___.t_.4__.t'.....:.__t_....._
.t 2 _. _2.__ ._. . {'. _.__
..;_._._p______ . . i _; .__
_ .. .f' ._ === f'_r:r*- !=*p-- .,* _ ,- E --- 1 !_ SATURATION CURVE _=./:fr i SATURATION = 5 A M.-T.~n~.iET_T CORRECTED FOR
= f:7 m CURVE w t-~--~*~~-- I ~~~~~~?-'
g 1000 =:r - - p= = = INSTRUMENT 4-ERROR .__ p ~~~==g=. ~~*t=;=s_ _._ I--~- ~ '; -~ o c f. .=.u ;' ;~_.2..*~"# -~ = '* 1
~
m 800 -~ , _ , = t;- _ "_ _; - -_~ = -_~~
=_;_;~^~ gl s , = ;_; ___ ; .;._
~ _ _ _
--.=2=p -
- ;-- ' ~ 7_/ . ;- -- - I:_._. ._._=. . __=_.2;=
___;_- + /r. f . _ _ _ .__ .. 600 __ _. _.;___ _; . __ _ _ _ _ _=_. _f~5}jr ~---
~ '
7
+
-=.y -
400
- ._:. : 3-1 = =_
gg___~_._ gg .t==:==p_.g4g'g _
~~
200
~~ ~- ' t /=~"f# : PRESSURE ERROR + 65 Psi9 !t .
-__. _--*,_ _ ....-. _- .- +1 ... '._7 --.. .. TEMPERATURE ERROR I
. o
- p.._ 2 _..p _ . _ 4 _ . 24 *FT--';
+
.=.=.__t.__.._.t-- _=_.__._..__..=..~.: .. .
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- _-~--- ' ; : ;;;
. =J. = " :*,. __. ;.J. !. r in. :2_ - n : =. ..ja . ; . .; .
200 300 400 500 600 700 CORE EXIT T/C TEMPERATURE ('F) O DC0402 341V I
l NUMBER EP ECA-3.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/12/85 PAGE 35 0F 41
*( TITLE.
SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED APPENDIX E t RWST LEVEL VS RECIRCULATION SUMP LEVEL FOR SATURATEC VS SUBC00 LED REC 0VERY 100 , , ; t ; .. . : i . j : : .: i 90 ' t t j -j -- - -- i - - .i . . :
! ~~~
80 ! . I i . 70 . _. . _ _ _i _. . _-. _ _ _ _ _ - - e U '
! ; i g 50 ,
3 _ _. ; _ . . . . _ _ _ . . _ 40
..\.\. i 30 STGR W/LOCA'
____Subcooled , recovery
.] l . . ._- . _
10 " to STGR W/ LOCA; Saturated.. \ - . recovery \i ! 20 30 40 50 60 70 80 90 100 0 10 l RECIRCULATION SUMP LEVEL !O DC0402 ^51V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/12/85 PAGE 36 0F 41 I'T 1 SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED h APPENDIX R RCP HOT SEAL C00LDOWN IF RCP SEAL RETURNS OR LOWER RADIAL BEARING TEMP HAS BEEN OR IS >225'F PERFORM THE FOLLOWING: ACTION / EXPECTED RESPONSE RESP 0f6E NOT OBTAINED
- 1. CHECK RCP Seal Isolation Status:
- a. Verify seal injection 150 a. -
IF valves open or position vivs CVCS - 8369A, B, C & D not known,
- CLOSED THEN check centrifugal charging pump status:
e located 100' aux bldg pent area, GE,127* - IF pump running, 137
- 1) TiiEN return to step in effect.
IF pump NOT running,
- 2) TfiEN manuaTTF or locally close seal injection vivs 0C.
O DC0402 36IV _
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3'12/85 PAGE 3/ OF 41 O SGTR'WITH LOSS OF REACTOR COOLANT - O I' M - SUBC00 LED REC 0VERY DESIRED APPENDIX R ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- b. FCV-357 - RCP therm bar CCW b. -
IF valve is open or return iso viv OC - position not known, CLOSED THEN check CCW pump status: IF a pump is running, 1)THEN90toStep2b. IF pump NOT running, 4
- 2) TREN manuaTTi or locally (100',GE-166')
close FCV-357.
~
IF FCV-357 can NOT be Closed, THEN manually close FCV-750, CCW return viv IC. O DC0402 371V
NUMBER EP ECA-3.1 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/12/35 PAGE 38 0F 41 SGTR WITH LOSS OF REACTOR COOLANT - TITLE. SUBC00 LED RECOVERY DESIRED 9 APPENDIX R ACTION / EXPECTED RESRJNSE RESPONSE NOT OBTAINED CAUTION: e RCP thermal barrier cooling should be established slowly to minimize potential introduction of steam into the CCW system. e RCP seal injection should be established slowly to minimize RCP thermal stresses and potential seal failures, e As part of subsequent recovery actions, RCPs should not be started prior to a status evaluation, unless rasponcing to Inadequate Core Cooling FR-C.1.
- 2. ESTABLISH RCP Seal Coolinc:
- d. E5*.?blish CCW flow to RCP thermal barriers (100' Aux Bldg Pent Area GE-166")
- 1) Establish communications between the cortrol room and 100' Aux Bldg Pent Area near FCV-357 CCW f rom RCP Thern Bar, OC
- 2) Ponitor RCP lower bearing temperature (T!
155, 154, 153, 152 on VB2 and T0417A, T0437A, T0457A, T0477A on the P250)
- 3) Check FCV-357 - CLOSED 3) Close FCV-357 RCP Therm Bar CCW Return Iso Viv OC -OR-CCW-267.
- 4) Check FCV-750 - OPEN. 4) IF FCV-357 or RCP Therm Bar CCW Return CCW-267 CLOSED Iso Viv IC THEN open FCV-750.
THIS STEP CONTINUED ON NEXT PAGE O OC0402 38IV l
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 f ON DATE 3/12/85 PAGE 39 0F 41 T [d TITLE SGTR WITH LOSS OF REACTOR COOLANT - SUSC00 LED REC 0VERY DESIRED APPENDIX R ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Monitor flow on FI-90 (PNL 184 Locally at TCV-3567) and temperature on TI-1004 (Locally at FCV-357). Initiate flow to the thermal barrier slowly reducing lower bearing temperature. (TI 155,154,153,152 on VB2 and T0417A, T0437A, T0457A, T0477A on the P250) at a maximum rate of l'F per minute until full thermal barrier flow is returned to normal. Some local boiling may occur in the CCW lines giving a closed signal to FCV-357.
- 5) Locally crack open FCV-357 or CCW-267
- b. Establish Seal Injection Flcw to RCPs (100' Aux Bldg. Pent Area GE-127 -137')
p 1) Wait until seal leak off U water temperature (TI-148,146,132,125) has decreased to 235'F
- 2) Establish com;nications between control room and the 100' Aux Bldg Pent Area near the RCP seal water injection flow control valves CVCS-8369A, B, C & D NOTE: Monitor RCP Seal Inj Flow ho. I seal. leak off temperature and lower RCP bearing temperature. Reduce each respective RCP bearing temperature at a maximum rate of 1*F per minute until bearing temperature is less than 225'F, then normal seal injection flow can be established.
- 3) Crack open CVCS-8369 A, B, C and D one at a time O
DC0402 391V
NUMBER EP ECA-3.1 DIAsco CANYON POWED PLANT UNIT NOfS) 1 AND 2 REVISION O DATE 3/12/85 PAGE 40 0F 41 SGTR WITH LOSS OF REACTOR COOLANT - TITLE. SUBC00 LED REC 0VERY DESIRED APPENDIX R ACTION /EXPEutu RESPONSE RESPONSE NOT OBTAINED
- 3. AFTER RCP Seal Cooldown -
VERIFY Normal RCP Cooling Alignment:
- a. Verify CCW a. IF
~~
CCW NOT aligned to RCPs,
- ALIGNED TO RCPs THEN ensure Phase B Isolation is reset and e FCV-355 - OPEN CCW to RCP manually open CCW oil CLRS therm BAR & SUP valves.
CLRS e FCV-357 - OPEN CCW from RCP THERM BAR, OC e FCV-363 - OPEN CCW from RCP OIL CLRS & SUP CLRS, OC g e FCV-749 - CPEN CCW from RCP OIL CLRS & SVP CLRS IC e FCV-750 - OPEN CCW from RCP THERM BAR IC - OPEN
- b. Verify RCP seal injection b. Adjust charging ficw and flow to each RCP 8 (6 to HCV-142 to maintain 8 (6 to
- 12) GPM 12) gpm to each RCP.
4 Return to step in effect i O DC0402 40!V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 V ON (7 DATE 3/12/85 () PAGE 41 0F 41
$GTR WITH LOSS OF REACTOR C0OLANT -
- SUSC00 LED REC 0VERY DESIRED APPENDIX Z t
EMERGENCY PROCEDURE NOT:'ICATION INSTRUCTIONS
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Designate this event an Alert.
- b. Designate this event a Site Area Emergency if steam generator tube rupture coincides with a loss of off-site power indicated by the inability to restore power to the non-vital 12KV and 4KV busses (D and E).
- c. If the primary to secondary leakage is estimated as >50 gpm with fuel damage evident from a gross failed fuel monitor alarm or primary sample, designate this event as a Site Area Emergency.
r d. SI with high or increasing levels of containtrent pressure, C- area radiation or recirculation sump level. Designate this event a Site Area Emergency.
- e. If the ruptured SG is faulted outside of containment and clad damage is evident from a primary sarrple, designate this event as a General Emergency.
- f. In the event inadequate core cooling is verified per Critical Safety Function Status or the verification of the ESF functioning and Effectiveness during LOCA, Appendix H.
(EP OP-1), indicatea ESF failure, reclassify this event as a General Emergency.
- 2. Notify plant staff and response organizations required for this classification by implementing Procedures EP G-2 "Establishrrent of the On-Site Emergency Organizations" and EP G-3 " Notification of Off-Site Organizations" in accordance with EP G-1 " Accident Classification and Emergency Plan Activation".
O O DC0402 411V
FOLD 0VT FOR EP ECA-3.1 PROCEDURE ADMINISTRATIVE FUNCTION 5 l
- 1. Notify STA and monitor CSF status trees and SPDS
- 2. Refer to Appendix Z SI RE-IN;TIATION CRITERIA l Manually start ECCS pumps if El ER condition listed below occurs:
e RCS subcooling - LESS THAN 20*F. e PRZ level - CANNOT BE MAINTAINED GREATER THAN 4%[20]% AFW SUPPLY 5WITCHOVER CRITERION l Switch to alternate AFW water supply when CST level decreases to less than 10t. Refer to E-2.1, ALTERNATE AFW SUPPLIES. SECONDARY INTEGRITY l Go to E-2, FAULTED STEAM GENERATOR ISOLATION if any SG is decreasing in an ur. controlled tranner or has been completely depressurized, and has not been isolated O COLD LE6 hECIRCULATION SWITCHOVER CRITERION I i Go to E-1.3 TRANSFER TO COLD LEG RECIRCULATION, Step 1, if RWST level decreases to less than 331. i ADvER5E C0hTAIhMENT CRITERIA l l teruir.r.er.t pressure - GREATER THAN 3 PSIG
-Oh-Ccr ttiertrt Radiation Dose Rate 10$R/hr
-OR.
Contaiament Radiation Dose 106R SI ACCUMULATOR ISOLATION CRITERIA l Isolate or vent SI Accumulators per Step 27 if the follrwing conditions exist: e Hot Leg Temperature < 400'F - OR - RCS subcoolinc >70*F e RCS pressure < 1000 psig CNMT SPRAY INITIATION CRITERIA l Initiate CNMT spray when CNMT pressure >22 psig l l DC0403_ 42111________
EP ECA-3.2 NUMBER 3GW3 Pacific Gas and Electric Company REVISION 0
' DEPARTMENT OF NUCLEAR PLANT OPERATIONS 1 AND 2 PAGE I 0F 32 DIABLO CANYON POWER PLANT UNIT NO(S)
EMERGENCY PROCEDURE SGTR WITH LOSS OF COOLANT - -
. TITLE SATURATED REC 0VERY DESIRED W
IMPORTANT APPROVED. YbW b'd5-f6 TO PLAM MANAGEgl DATE SAFET( i SCOPE
! This procedure provides actions to cool down and depressurize the RCS to cold shutdown conditions while minimizing loss of RCS inventory.
This procedure and changes thereto requires PSRC review. ] _ SYMPTOMS AND ENTRY CONDITIONS This procedure is entered from:
- 1. ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED FEC0VERY DESIRED. Step 12, when RWST level is low without a corresponding i increase in containrent surnp level, i
- 2. ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED RECOVERY
, DESIRED, Step 12, when the ruptured SG level is high and plar.t
- staff selects saturated recovery method.
i l O DC0401 IV i . _ . - _ _ _
NUMBER EP ECA.3.2 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 PAGE 2 0F 32 SGTR WITH LOSS OF COOLANT - TITLE. SATURATED RECOVERY DESIRED ACTION / EXPECTED RESRASE RESR)NSE NOT OBTAINED CAlJTION: e If RWST level decreases to less than 33% the ECCS System shot.ld be aligned for cold leg recirculation using E.1.3, TRANSFER TO COLD LEG RECIRCULATION. e RCS pressure should be monitored,. If RCS pressure decreases to less than 300 psig, the RHR pumps must be manually restarted to supply water to the RCS. TOTE: e The first TWELVE steps of ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED, should be perfortned before continuing with this procedure. e If subcooling monitor becones inoperable, determine subcooling by using WR RCS pressure and core exit TCs (refer to Appendix C). e Foldout page should be open
- 1. A00 Makeup to RWST As Necessary:
- a. Refer to Appendix M, and continue in this procedure
- 2. CHECK If PHR PunDs Should Be Stopped:
- a. Check RCS pressure: (VB2) a. Go to Step 3.
- 1) Pressure - GREATER THAN 300 psig
- 2) Pressure - STABLE OR INCREASING
- b. Stop both RHR pumps (VB1) s O
DC0401 2V l
NUMBER EP ECA-3.2 OIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 Cx PAGE 3 0F 32 U TITLE SGTR WITH LOSS OF COOLANT . SATURATED RECOVERY DESIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEI)
- 3. CHECK If SGs Are Not Faulted:
- a. Check pressures in all SGs - a. Verify all faulted SGs (VB3) isolated unless needed for RCS cooldown:
e NO SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER e Steamlines, e NO SG COMPLETELY DEPRESSURIZED e Feedlines. IF NOT, TiiEN go to E-2, FAULTED STEAM GENERATOR ISOLATION. s @ TION: Alternate water sources for AFW purps will be necessary if CST V) decreases to less than 10'.. (Refer level to E-2,1 ALTERNATE FEE 0 WATER SUPPLIES) AUXILIARY 4 CHECK Intact SG Levels:
- a. Narrow rarge level - GREATED THAN a, Maintain total feed ficw 4t [20',] (VB3) greater than 460 gpm until narrow range level greater than41[20%)inatleast one SG.
- b. Control feed flow to maintain b. !F
~~~
narrow range level in rarrow range level between 41 any intact SG continues [201]ard33%(CC3/VB3) to increase in an uncontrolled manner, THEN go to E.3, STEAM GEhERATOR TUBE RUPTURE.
- c. Stop TO AFW pp if NOT needed for RCS heat removal N'O DC0401 3V
1 AND 2 V S ON OlABLO CANYON POWER PLANT UNIT NO(S) DATE 3/8/85 SGTR WITH LOSS OF COOLANT - TITLE. SATURATED REC 0VERY DESIRED ACTION / EXPECTED RESR)NSE RESPONSE NOT OBTAINED TOTE: e Shutdown margin should be monitored during RCS cooldown. (Refer to STP R-19 SHUTOOWN MARGIN CALCULATION.)
- 5. INITIATE RCS Cooldown To Cold Shutdown
- a. Maintain cooldown rate in RCS cold legs - LESS THAN 100'F in any one hour period
- b. Use RHR System if in service
- c. Dump steam to condenser from c. Manually or locally dump intact SG(s) (CC2) steam from intact SG(s) 10%
steam dump valves. Balance
- 1) Check AIL MSIVs NOT Isolated use of dumps to avoid 100 psid SIS.
- 2) Check C-9 condenser available no intact SG available, status light (PK08-14) - ON IF TREN perform the following:
- 3) Set HC 507 at 8.38 e Use faulted SG
- 4) Transfer Steam Dump Made Switch to Steam Pressure Mode -OR-
- 5) Adjust controller setpoint or o E RHR system NOT in manually adjust steam service, pressure controller to THEN use ruptured SG.
establish desired cooldown rate
- 6) Place CONT ONLY, LCV-12 selector switch
- 7) At P-12 activation (CC2) e Select BYPASS INTERLOCK on both selector switches s
e Block both trains of high steam flov SI
~
O l DC0401 4V
1 AND 2 NUMBER EP ECA-3.2 OIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0
' DATE 3/8/85 '
PAGE 5 0F 32 (-)N SGTR WITH LOSS OF COOLANT - TITLE. SATURATED REC 0VERY DESIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. CHECK RCS Subcooling Based On Core Go to Step 20.
Exit TCs . GREATER THAN 20"F (VB2)
- 7. CHECK If ECCS Is In Service: Go to Step 16.
(VB1/VB2) e BIT - NOT ISOLATED 0R-e SI pumps - ANY RUNNING
- 8. PLACE All PZR Heater Switches In OFF Position (CCl)
O l l l v DC0401 SV
NUMBER EP ECA-3.2 1 AND 2 REVISION 0 oiAsto CANYON POWER PLANT UNIT NO(S) DATE 3/8/85 PAGE 6 0F 32 SGTR WITH LOSS OF COOLANT - i TITLE- SATURATED REC 0VERY DESIRED ACTION / EXPECTED RESPONSE RESf0NSE NOT OBTAINED CAUTION: e Voiding may occur in the RCS during RCS depressurization. This will result in a rapidly increasing PZR level. e Auxiliary spray flow into the PZR shall not be initiated if the delta -T between the PZR and the spray fluid exceeds :i60 F. Spray flow should not be initiated if the delta-T exceeds 320*F. t0TE: e CRDM cooling fans should be in operation. e If PZR Aux spray is used it may be necessary to close normal spray PCV 455A & B and charging valves 8146 and 8147.
- 9. DEPRESSURIZE RCS To Refill PZR:
- a. Use normal PZR spray (CC2) a. E normal PZR spray NOT available, THEN use auxiliary spray.
(VB2) E auxiliary spray NOT available, THEN use one PZR PORV (VB2)
- AND -
Place all PZR heater switches in 0FF. (CC1)
- b. PZR level - GREATER THAN 17% [40%] b. Continue with RCS (CC2/VB2) depressurization.
WHEN PZR level is greater than 17% [40%], THEN do step 9.d.
- c. Deenergize PZR heaters as ,
necessary
- d. Stop RCS depressurization
- AND -
maintain RCS pressure - STABLE using PZR heaters, spray and q g PORV's as necessary DC0401 6V
NUMBER EP ECA-3.2 l DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 l DATE 3/8/85 . PAGE 7 0F 32 ! IT SGTR WITH LOSS OF COOLANT - l
\ssl TITLE SATURATED RECOVERY DESIRED ACTI0tuEX KCTED RESPONSE RESPONSE NOT OBTAINED CAUTION: e If seal cooling has previously been lost, the affected RCP(s) should not be started prior to status evaluation.
e On natural circulation, RTD bypass temperatures and associated interlocks for Feedline Iso, Steam Dump and High Steam Flow SI will be inaccurate. NOTE: All but one RCP may be stopped to minimize pump heat input. If maintaining a 100*F/hr cooldown, running 2 RCPs is desirable; RCP 1 or 2 (*2 preferred) for normal PZR spray and RCP 3 or 4 to maximize MD AFW pump capacity.
- 10. CHECK If A RCP Should Be Started:
D52)
- a. Check All RCPs _ STOPPED a. Perform the following:
r e Stoo all but one RCP. ( .'u T) e Close normal spray valve on any idle loop. (CC2) e Go to Step 11.
- t. Check RCS subccolir.g - GREATER b. Go to Step 20.
THAN 20*F
- c. Check PZR level - GREATER THAN c. Return to Step 9.
17% [40%] i
- d. Try to start a RCP: d. Go to Step 11. OBSERVE NOTE PRIOR TO STEP 11.
, 1) Establish conditions for i starting a RCP per APPENDIX B
- 2) Close normal spray vivs (CC2) l
- 3) Start one RCP (VB2) t
-n DC0401 7V
otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/8/85 PAGE 8 0F 32 7gg.~ SGTR WITH LOSS OF COOLANT _ SATURATED REC 0VERY DESIRED ACTION /EXPEcits RESPONSE RESPONSE t0T OBTAINED NOTE: e After stopping any ECCS pump, RCS pressure should be allowed to stabilize before stopping another ECCS pump. (Approximately 5 minutes) e The ECCS pumps should be stopped on alternate ECCS trains when possible.
- 11. CHECK If One Cent Charging Pump Should Be Stopped:
- a. Two cent charging pumps - a. Go to step 12.
RUNNING (VB2)
- b. Determine required RCS subcooling from table:
SI PUMP RCS SUBC00 LING ( F) NONE RUNNING 48"F ONE RUNNING 47'F TWO RUNNING 47 F
- c. RCS subcooling based on core c. Go to Step 20.
exit TCs - GREATER THAN REQUIRED SUSC00 LING (VB2)
- d. PZR level - GREATER THAN 17% d. Return to Step 9. OBSERVE
[40%](VB2) NOTES AiiD CAUTIONS PRIOR TO STEP 9.
- e. Stop one cent charging pump (VB2)
O DC0401 8V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 O! DATE 3/8/85
/O PAGE 9 0F 32 7,7 g SGTR WITH LOSS OF COOLANT -
SATURATED RECOVERY DESIRED ACTION /EXRCTED RESPONSE RESPONSE NOT OBTAINED
- 12. CHECK If One SI Pump Should Be Stopped: (VB1)
- a. Any SI pump - RUNNING a. Go to Step 13.
- b. Determine required RCS subcooling from table:
RCS SUBC00 LING ( F) SI PUMP STATUS ONE CENT CHARGING PUMP RUNNING NO CENT CHARGIfiG RUNNING ONE 79 F Do NUT stop SI pump RUNNING TWO 26"F 33*F RUNNING
- c. RCS subcooling based on core Go to Step 20.
exit TCs - GREATER THAN REQUIRED SUBC00 LING (VB2)
- d. PZR level - GREATER THAN 17'e d. Return to Step 9.
[40%] (VB2)
- e. Stop one additional SI pump (VB1)
'f. Go to Step 20 1
DC0401 9V 1 1
NUMBER EP ECA-3.2 DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 10 0F 32 SGTR WITH LOSS OF COOLANT - TITLE: SATURATED REC 0VERY DESIRED llll ACTION /EX CTED RESF0NSE RESPONSE f0T OBTAINED
- 13. CHECK If Normal Charging Should E-Established:
- a. Verify ECCS pump status: a. Go to step 20.
(VB1/VB2) o Both SI pumps - STOPPED o Cent charging pumps - ALL BUT ONE STOPPE0
- b. RCS subcooling based on core b. Go to Step 20.
exit TCs - GREATER THAN 74*F
- c. PZR level - GREATER THAN Return to Step 9. OBSERVE NOTES 17% [40'e] (VB2) AND CAUTIONS PRIOR TO STEP 9.
- 14. ESTABLISH Charging Flow: (VB2)
- a. Throttle to 50% HCV-142.
- b. Open FCV-128
- c. Open 8105 and 8106, cent charg c. IF 8105 or 106 will NOT pps nin1 flow recirc vivs open, THEN maintain a minimum of 60 gpm charging.
- d. Check SG 4 Intact d. IF SG 4 NOT intact, TITEN o Opeii 6147, alt o Open 8146, normal charg to charg to LP 3 cold LP 4 cold leg viv leg viv.
o Close 8147, Alt charg to LP3 o Close 8146, normal cold leg charge to LP 4 cold leg viv. THIS STEP CONTINUED ON NEXT PAGE llll
- DC0401 10V l
l
NUMBER EP ECA-3.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 O TITLE. SGTR WITH LOSS OF COOLANT - SATURATED REC 0VERY DESIRED PAGE 11 0F 32 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
'e. Close 8145 and 8148, charg line to PZR aux spray viv and bypass
- f. Open 8108 and 8107, normal charg to regen hx stop vlvs 1&2
- g. Stop PD charging pump if desired (VB1)
- 15. ISOLATE BIT: (VB2)
- a. Close 8803 A and B, BIT supply viv
- b. Close 8501A and B, BIT outlet viv
- 16. CONTROL Charging Flow To Maintain Reactor Coolant Inventory: (PAM3/4) e RVLIS full range greater than 76%
if no RCP running
- OR -
e RVLIS dynamic range greater than 33% if one RCP running l i O DC0401 11V
/ NUMBER EP ECA-3.2 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 PACE 12 0F 32 SGTR WITH LOSS OF COOLANT - & l TITLE SATURATED RECOVERY DESIRED W l l l ACTION / EXPECTED RESPONSE RESPONSE t#1T OBTAINED
-CAUTION: e If RCP seal cooling hac previously been lost, the affected RCP(s) !
should not be started prior to a status evaluation. I e On natural circulation, RTD bypass temperatures and associated interlocks for Feedline Iso Steam Dump and High Steam Flow SI will be inaccurate. t0TE: All but one RCP may be stopped to minimize pump heat input. If maintaining a 100 F/hr cooldown, running 2 RCPs is desirable; RCP 1 or 2 (*2 preferred) for normal PZR spray and RCP 3 or 4 to maximize MD AFW pump capacity. 17 CHECK RCP Status: (VB2)
- a. RCPs - AT LEAST ONE RUNNING a. Try to start one RCP.
- 1) Check RCP seal ret and lower rad brg temp less than 225 F. (VB2)
IF greater than 225 F refer to Appendix R and continue in this procedure.
- 2) Establish PZR (VB2) conditions as follows:
e IF- RVLIS full range <95%, THEN ESTABLISH PZR level at
>67%[90%].
e IF- RVLIS full range > 95%, THEN establish PZR level at
>17% [40%). '
s Control PZR temp at saturation for RCS hot leg temp. THIS STEP CONTINUED ON NEXT PAGE l DC0401 12V
'N NUMBER EP ECA-3.2 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 ,.s DATE 3/8/85 PAGE 13 0F 32
('d) SGTR WITH LOSS OF COOLANT - TIT'.E . SATURATED REC 0VERY DESIRED ACTION / EXPECTED RESRESE RESPONSE NOT OBTAINED
- 3) Close normal spray vivs, PCV 455-A and B. (CC2)
- 4) Establish RCS subcooling based on core exit TCs 35'F.
- 5) Establish conditions for starting a RCP per Appendix B.
- 6) Start one RCP.
IF an RCP can NOT be started, THEN manually close both normal PZR spray A vivs and verify V natural circulation based on: e SG pressures stable or decreasing. e RCS hot leg temperatures-stable or decreasing, e Core exit TCs stable or decreasing. e RCS cold leg temperatures-at saturation temperature for SG press, e Dump steam from intact SGs to maintain adeouate RCS heat removal.
- b. Stop all but one or two RCPs (VB2)
- c. Close the normal spray viv on any idle loop (CC2)
DC0401 13V i
t' DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 RE S ON DATE 3/8/85 PAGE 14 0F 32 TITLE. SGTR WITH LOSS 0'F COOLANT - SATURATED REC 0VERY DESIRED g ACTION / EXPECTED RESf0NSE RESf0NSE NOT OBTAINED
}
CAUTION: e Voiding may occur in the RCS during RCS depressuriz& tion. This will result in a rapidly increasing PZR level, e Auxiliary spray flow into the PZR shall not be initiated if the delta-T between the PZR and the spray fluid exceeds 560*F. Spray flow should not be initiated if the delta-T exceeds 320*F. NOTE: If PZR Auxiliary spray is used it may be necessary to close normal spray PCV 455A & B and charging valves 8146 and 8147.
- 18. DEPRESSURIZE RCS Tc Saturation At Core Exit:
- a. Determine saturation pressure for core exit TCs (Refer to Appendix C)
- b. Use: Normal PZR spray (CC2) '
l
- AND/0R -
Auxiliary spray (VB2)
- AND/0R -
One PZR PORV (VB2)
- c. Turn on PZR heaters as necessary (CC1)
- d. Depressurize RCS until EITHER of the following conditions satisfied:
o PZR level-GREATER THAN 77%[70%]
- OR - '
s RCS pressure-AT SATURATION FROM STEP 18a l l l l 1 DC0401 14V i I
NUMBER EP ECA-3.2 OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 15 0F 32
S SGTR WITH LOSS OF COOLANT -
(V TITLE: SATURATED REC 0VERY DESIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 19. 9ERIFY Adecuate Shutdown Margin:
- a. Sample ruptured SG(s)
- b. Sample RCS
- c. Shutdown margin - ADEQUATE c. Borate as necessary.
(Refer to STP R-19, SHUTDOWN MARGIN CALCULATION)
- 20. VERIFY ECCS Flow Not Required:
(PAM3/4)
- a. Core exit TCs - DECREASING a. Increase dumping sitam.
(CC2) IF core exit TCs do NOT decrease, THEN manually operate ECCS 0, _________________ pumps as necessary.
- b. Check RVLIS indication: b. Manually operate ECCS pumps
~
e Full range - GREATER THAN 76L IF NO RCP RUNNING
- OR -
e Dynamic range - GREATER THAN 33% IF ONE RCP RUNNING l l l DC0401 15V
NUMBER IP ECA-3.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION O DATE 3/8/85 PAGE 16 0F 32 SGTR WITH LOSS OF COOLANT - TITLE: SATURATED RECOVERY DESIRED O ACTION / EXPECTED RESPONSE ESPONSE NOT OBTAINED
- 21. CHECK If SI Accumulators Should Be Isolated:
- a. Check RCS pressure <1000 psig a. Go to Step 22.
- b. RCS subcooling based on core b. IF RCS hot leg temperature exit TCs - GREATER THAN 20 F GREATER THAN 400*F, (V82) THEN go to Step 22.
- c. Check power to accum disch iso c. Restore power to 1 solation vlvs - AVAILABLE valves
- d. Close all accum disch iso vivs d. IF
~~~
any accumulator (VB1) isolation valve does NOT close,
'8808A, B, C, D THEN perform the following:
(VB1)
- 1) Close FCV 8880, accumulator N2 fill iso viv.
- 2) Open 2875A, B, C or D, accum N2 supply to affected accum.
- 3) Open HCV 943, accum N2 supply line vent, UNTIL accumulator is depressurized and continue with procedure.
DC0401 16V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 S ON DATE 3/8/85 } PAGE 17 0F 32 l SGTR WITH LOSS OF COOLANT - ' TITLE: SATURATED RECOVERY DESIRED ACTION / EXPECTED ESPONSE RESPONSE NOT OBTAINED
- 22. ' CHECK If Diesel Generators Should Be Stopped: (VB4)
- a. Check vital busses F, G and H - a. Try to restore offsite ENERGIZED BY OFFSITE POWER power, either STARTUP or AUXILIARY, to the vital busses.
- b. Stop any unloaded DG and place in AUTO
- 23. MINIMIZE Secondary System Contamination:
- a. Isolate reject as follows:
s 1) Close LCV-12, condensate reject viv
- 2) Sample the hotwell.
- 3) Use reject, in manual, based on hotwell sample results.
- 4) Maintain CST level below the overflow
- b. Isolate condensate polisher demins: (VB3)
- 1) Open FCV 230, cond polisher bypass viv
- 2) Close FCV 231, cond polisher inlet valve
- c. Transfer aux steam supply to aux boiler (Refer to OP K-5:IV, Part B)
THIS STEP CONTINUED ON NEXT PAGE O DC0401 17V
IlUMBER EP ECA-3.2 1 AND 2 REVISION 0 OIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/8/85 PAGE 18 0F 32 SGTR WITH LOSS OF C0OLANT - TITLE. SATURATED REC 0VERY DESIRED lll ACTION /EXRCTED RESPONSE RESPONSE NOT OBTAINED
- d. Ensure reheaters isolated (VB3)
- e. Ensure main feed pumps gland seal supplied from aux boiler
- f. Manually transfer blowdown tank outlet switch frc., outfall to EDRT (FCV-498 closed and FCV-499 opened)
- g. Verify blowdown and sample 9 Manually isolate blowdown.
blowdown isolation has occurred O O DC0401 18V l
NUMBER EP ECA-3.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 SGTR WITH LOSS OF COOLANT - f) b TITLE ' SATURATED REC 0VERY DESIRED ACTION /EXRCTED ESPONSE ESPONSE NOT OBTAl@
- 24. THECK RCP Cooling - NORMAL
- a. RCP seal ret and lower rad brg a. Refer to Appendix R and go temp less than 225 'F (VB2) to step 26.
- b. Verify CCW - ALIGNED TO RCPs b. -
IF CCW NOT aligned to (VB1) RCPs. THEN RESET phase B isolation e Open FCV-355, CCW hdr C iso and manually open CCW viv valves. (VB1) e Open FCV-356, CCW to RCP oil clrs therm bar & sup clrs e Open FCV-357, CCW from RCP therm bar, OC p e Open FCV-363, CCW from RCP Q oil clrs & sup clrs, OC e Open FCV-749, CCW from RCP oil & sur clrs, IC e Open FCV-750, CCW f rom RCP therm bar, IC
- c. Verify RCP seal injection flow 8 c. Adjust HCV-142 as necessary.
(6-12) GPM to each RCP (VB2) lO ( DC0401 19V ; 4
.-, .~ .--- _ .___ - _ ___ ,.- , ... _ ___.__ ______ _..._._... _ _ .._ _ __.._ __ _ ._
NUMBER EP ECA-3.2 1 Af.D 2 OlABLO CANYON POWER PLANT UNIT NO(S) REVIS10N 0 DATE 3/8/85 PAGE 20 0F 32 SGTR WITH LOSS OF COOLANT - TITLE. SATURATED REC 0VERY DESIRED ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 25. CHECK If RCP Seal Return Flow Should Be Established:
- a. Check RCP seal return not a. Go to step 26.
isolated due to suspected seal damage
- b. Initiate seal return as follows:
- 1) Close ANY #1 seal ret iso viv with GREATER THAN 6 GPM seal ret-flow indicated (VB2)
- 2) Open FCV 355, CCW hdr C iso viv (V51)
- 3) Open 8100 ana 8112, RCP seal ret iso vivs (VS2)
- 26. CHECK If SR Detectors Should Be Energized: (CCl)
- a. Check IR Flux a. Continue with Step 27.
- LESS THAN 10~10 AMPS WHEN flux less than 10~10 anps, THEN complete Steps 26b and c.
- b. Verify both SR detectors - b. Manually reset and energize ENERGIZED both SR detectors. (CC1)
- c. Select highest SR & IR detectors on AR 45 s
r 1 OC0401 20V l l i l
m NUMBER EP ECA-3.2 1 AND 2 OIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 x PAGE 21 0F 32 SGTR WITH LOSS OF COOLANT - TITLE- SATURATED RECOVERY DESIRED ACTION /EXKCTED RESPONSE RESPONSE f0T OBTAINED
- 27. ' SHUT Down Unnecessary Plant Equipment:
- a. Stop any running plant equipment not required for post accident recovery (Refer to OP L-5 PLANT C00LDOWN FROM MINIMUM LOAD TO COLD SHUTDOWN)
CAUTION: Feed flow should not be initiated to any ruptured SG if it is faulted unless needed for RCS cooldown~.
- 28. CHECK Ruptured SG(s) Narrow Range Refill ruptured SG to 67% using Level - GREATEF. THAN 4a L20kJ (v63) feed flow.
~~
IF either of the following conditions occurs, (} e Ruptured SG pressure decreases in an uncontrolled manner
- OR -
e Ruptured SG pressure increases to 1010 psig, THEN stop feed flow to the ruptured SG unless needed for RCS cooldown. o DC0401 21V l
. - - - - . . . - - - - .. . . . .. _ ~ - - . . ._.
NUMBER EP ECA-3.2 OlA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 22 0F 32 SGTR WITH LOSS OF COOLANT - TITLE. SATURATED RECOVERY DESIRED llll ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 29. CHECK If RCPs Must Be Stopped: (VB2)
- a. Check the following: a. Go to Step 30.
e No. 1 seal delta-P
-LESS THAN 215 PSID
- OR -
e No. 1 seal leakoff flow outside limits of Appendix B
- b. Stop affected RCP(s)
- c. Close normal spray viv on any idle loop (CC2)
- 30. CHECK If RHR Systen Can Be Placed In Service: (V62)
- a. Check the following: a. Go to Step 31.
e RCS temperature - LESS THAh 350*F e RCS pressure - LESS THAN 390 psig
- b. Consult TSC to determine if the low setpoint overpressure protection system should be cut in
- c. Consult TSC to determine if RHR c. IF RHR is NOT to be placed System should be placed in in service, service THEN 90 to Step 31.
. . _ . . . . . . . . . . .s .
- d. Implement OP B-2:V, RHR - PLACE IN SERVICE DURING PLANT C00LDOWN O
DC0401 22V
I DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R S ON DATE 3/8/85 PAGE 23 0F 32
/3 SGTR WITH LOSS OF COOLANT -
V TITLE: SATURATED REC 0VERY DESIRED ACTION /EXRCTED RESFONSE RESPONSE NOT OBTAINED
- 31. ' CHECK RCS Temperatures - LESS THAN Return to Step 4 Observe 200"F CAUTION prior to Step 4.
- 32. EVALUATE Long Term Plant Status:
- a. Consult plant staff in Technical Support center for RV venting approval (refer to FR-I.3 RESPONSE TO V0 IDS IN REACTOR VESSEL)
- b. Maintain cold shutdown conditions:
e RCS temp less than or equal to 200 F e K eff less than .99
- c. Check containment atmosphere to determine if hydrogen recombiners or if hydrogen purge should be placed in service
- d. Implement OP L-5 PLANT C00LDOWN FROM MINIMUM LOAD TO COLD SHUTDOWN and review for applicable actions
- e. CHECK STP M-55 cyclic review
- f. Consult plant engineering staff
- END -
lO DC0401 23V l _
NUMBER EP ECA-3.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 24 0F 32 SGTR WITH LOSS OF COOLANT - TITLE. SATURATED RECOVERY DESIRED g APPENDIX B Restart of Reactor Coolant Pump
- 1. Start oil lift pump, run for 2 minutes.
- 2. Verify CCW available to thermal barrier, oil coolers, seal water HX.
- 3. Verify seal dp greater than 215 psid, depressurize VCT as necessa ry.
4 Verify seal injection flow 8 (6 to 12) gpm.
- 5. Verify seal leak off flow within limits shown on graph.
- 6. Ensure closed 455A and B. Normal PZR spray vivs (Auto Optional).
ALLO 4ASLE RCP #1 SEAL LEAK RATES e 5 i I l l f i 4 , SHJTDCWN RCP WITHIN CNE HALF HO'JD 3 .
! f ,
l l l l
. i r 1
SAFE OPERATING REGION I (2 1 i
' i
# i >
. I +
t j i : RES!0N l , i REGION [ I 2 i 00 NOT START RCP g
, f I I i l I I 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 RCP 81 SFAL O!FFERENTIAL PRESSL'QE PSID REGION 1 NO PHASE-A SIGNAL, dp=RCS,,,,,-VCT oress PHASE-A PRESENT, dp=RCS press -150psig REGION 2 USE INSTALLED dp GAUGES
NUMBER EP ECA-3.2 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 PAGE 25 0F 32 ) O D TITLE. SGTR WITH LOSS LF C0OLANT - SATURATED REC 0VERY DESIRED APPENDIX C s 2600 J.
=.._..].._.J_.2 : ;. t=r.r. :_: = . I . . . . . . ' .___t_ _ - - . . L _ . . : ._. . - =:: -"g -.-.. - : . J1.==..- + 3 n. _ :. 1:
= ;=~= :z. ;:-.=
~'= = i = = .q . _ - *. = , . j . = . 2 y ~=~: ". _j = :'; ~ "- = p = r_f'I'=u / ":_ 2.
~
2400
~ " ' __ _ _. _~ g' ". _~_.~._~_;._ _2: _ 7.g_ _ ' .._ y __ ._ _..._
_=_c_-l..=.......=
- =._. , _. := -=. _ .- t =_=. _::: =. _ =. . .=_=__. =_ ].
.=.__._._t._.--._--. = =.. =_
gg == r.= : ___c-
. -- - - - :;= =...: .
-4 +--- -- --
- r. - -". __ f _._ e..l= ==_ =
--~~ ~ ----
- i
* - - - ' - - ~~~# =-:
^
- =n =
-~~
2000 .. = :.=_ :=: = .=_ ._ : _= + _ ===
. -j =
. _= =:= = _r - =2 - _---i:__ .= . _. _ __= _ . ;, -- _- _r_ i
_9_
---I--
. =_ :: _. =_ --
4 - _ l _ = i r: ;_
^ * - - -
._ _ . : _ __ ._ n 2 ;- .T _a
- - - ____ r- - .}. - = = =1' . .= L._ .
- - _=r - = . . ._ -
18G0 g :En-5-l- =: : C = Y-d Nd=5 $ h =i k =/.D -i ~k;:
- : . _ = _. : .; . = .-.: _.=_.r ..._5 ::g g p ;7_ =
w 1. ; .. .; .!_a_ _= m ': : :. . . . _ _t . = : ._t. - _:- j _---u . : ;:_i== . -~2 O' = :=t -- u:2 = == - - m '
= :____
_% ' ~ ~ "._bj._-
- -- .=. _ . _ .. . :_: i r== ;= = --i _ _ _ .
S 2 ~="~*""~"~='"~~="-~ ~ '"~"'=2 1400 m w e
=---+-__: -- --
22 = ._..
,/=
- _ - .= _: ==_
j =:. _-t- 1: .k==_::{_whi===L:==t=?5 . J.__}.__. .=._= . , se . _ : -- rc
. _ = : := - _ _.- ~- :p :: - SATURATION CURVE :_ :. = :: : SATURATION .
p -
. ==
= ___. . ="a n= - -- n - - - CORRECTED FOR :_:=/2.2 _- CURVt ;;
w -~ = a 1000 _ _ _ _ _ _ - " . . . . = . . . . = . _ = .~ INSTRUMENT ERROR =_ I= . . , _ _ _ _ _ . y ~ 2----_. ~ 2- -- =:- + J. . M . _ _ -I w $
.r...-._.9.._._._.-...__ 1. ____ . f _ . __. _.
$ "*"*~ #"' '
~ ~
a 800
= = : = = . 2= = =q==,-f==:
r------
- = = a __._.___-t._
--+-
- -_ _._ .:_ _ _ =c--- _::=_ _ . . .- := .
_ : __ _ __ m _ _ . . _- -n -
. _ t =_ __2_ 2_.__._.
600 ___ ___=.._=;._.._;_=. . , 1_ _ , _ _ __._ s _a . 400
- " - - - " - ~ " - T-- '-
- - - - - + - - - - - " - - -
2- r= 2 = r: -- = - uf = a - - .=
~- --- OR i 65 p W 200
..- ; =: = = = p- q
- i=; TEMPERATURE ERROR I 24 'F ~
= = ,t.: .n _a .--rt=i- a _ ..
- _w___.
f- i . _ _.r,. =_ _=.;;_4-. =.__.__=. E= ;~_ =. . t. =. i g r..J
-- = +3 u.._= t_ x- . -
200 300 400 500 600 700 m th CORE EXIT T/C TEMPERATURE (*F) DC0401 25V j
NUMBER EP ECA-3.2 1 AND 2 OIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 PAGE 26 0F 32 SGTR WITH LOSS OF COOLANT - TITUE. SATURATED REC 0VERY DESIRED APPENDIX M: RWST MAKEUP Two methods are provided in this appendix. If necessary, both methods can be performed at the same time. A. Makeup to RWST From Blender:
- 1. Place makeup control switch (1/Ma) in STOP position.
- 2. Place makeup mode selector (43/mu) in MANUAL mode.
- 3. Locally perform the following:
e Open CVCS-8466, blender outlet to LHUT and RWST (100', blender rm) e Open CVCS-8467, blender outlet to RWST (100', blender rm) e Close CVCS-8258, blender to LHUT inlet (100', outside LHUT 12 rm)
- 4. Place the control switches for FCV-110B and FCV-1118 in CLOSE and ensure that they are closed.
- 5. Place the control switches for FCV-110A and FCV-111A in AUTO.
- 6. Manually adjust HC-111 for 200 gpm and HC-110 for 10 gpm.
- 7. SET BATCH integrators for 100,000 gallons primary water and 5,000 gallons boric acid.
- 8. Turn makeup control switch to START position.
- 9. Verify approxinately 200 gpm flow at FI-111 and 10 gpm at FI-110.
s l .. l DC0401 26V i 5 1
NUMBER EP ECA-3.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 7 PAGE 27 0F 32 (d TITLE. SGTR WITH LOSS OF COOLANT - SATURATED REC 0VERY DESIRED APPENDIX M (Continued)
'B. Makeup to RWST From SFP:
- 1. Verify Spend Fuel Pit pump 0FF.
- 2. Close SFS-8762, SFP pp disch vlv to SFP hx.
- 3. Close SFS-8771A, SFP filter inlet.
4 Ensure SFS-8756 OPEN, SFP pp suction viv.
- 5. Ensure SFS-14 OPEN, SFP pp disch to filter & demin.
- 6. OPEN SFS-8774, SFP demin bypass viv.
- 7. Ensure SFS-8775 OPEN, SFP demin resin trao outlet to SFP filter.
- 8. Close SFS-87898, SFP resin trap outlet.
O 9. Ensure 51-8973 OPEN, refuel wtr purif pp disch to RWST iso viv.
- 10. Start Spent Fuel Pit Pump.
- 11. If rrakeup to the SFP is required:
- a. Refer to OP B-7:V, SPENT FUEL P00L MAKEUP
- b. Add 11 pounds of boric acid to the SFP for every 100 gallons of water transferred.
- c. If makeup from transfer tank or demineralizer is not possible, use local fire water for makeup.
- 12. Stop SFP pump when suction line becomes uncovered.
1 l DC0401 27V 1
NUMBER EP ECA-3.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 28 0F 32 SGTR WITH LOSS OF COOLANT - TITLE: SATURATED RECOVERY DESIRED g A'PPENDIX R - RCP HOT SEAL C00LDOWN If RCP seal returns or lower radial bearing temp has been or is greater than 225 F perform the following: ACTION /EX CTED RESPONSE RESPONSE NOT OBTAINED
- 1. CHECK RCP Seal Isolation Status:
- a. Verify CVCS-8369 A, B, C & D - a. -
IF valves open or position CLOSED, RCP seal water not known, containment iso vivs (100', THEN check centrifugal GE-127' to 137*) charging pump status: (VB2)
- 1) IF pump running, E EN return to step in effect.
- 2) IF pump NOT running, EEN manually or locally close seal injection
- b. Cicse FCV-357, RCP therm bar b. IF valve is open or CCW return iso viv, OC (VB1) ii6sition not known, THEN check CCW pump status:
- 1) IF a pump is running, W EN go to step 2b.
- 2) IF pump NOT running, WEN manuaTTy or locally close FCV-357.
(100', GE-166 ) IF FCV-357 can NOT be closed, THEN manually close FCV-750, CCW return viv IC.
...............s.
Ol DC0401 28V !
NUMBER EP ECA-3.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 29 0F 32 (mj SGTR WITH LOSS OF COOLANT - TITLE: SATURATED REC 0VERY DESIRED APPENDIX R (continued) ACTION / EXPECTED RESPONSE RESF0NSE NOT OBTAINED CAlJTION: e RCP thermal barrier cooling should be established slowly to minimize potential introduction of steam into the CCW system. e RCP seal injection should be established slowly to minimize RCP thermal stresses and potential seal failures. e As part of subsequent recovery actions, RCPs should not be started prior to a status evaluation.
- 2. ESTABLISH RCP Seal Cooling:
- a. Establish CCW flow to RCP thermal barriers (100', GE-166*)
- 1) Establish commur.ications A between the control room and area near FCV-357
- 2) Monitor RCP lower bet. ring temperature (TI-155,154, 153, 152 on VB2 and T0417A, T0437A, T0457A, T0477A on the P250)
- 3) Check FCV-357 - CLOSED 3) Close FCV-357
- OR -
CCW-267.
- 4) Check FCV-750 - OPEN, RCP 4) IF - FCV-357 or CCW-267 therm bar CCW return 150 viv, closed, IC THEN open FCV-750.
THIS STEP CONTINUED ON NEXT PAGE O v OC0401 29V
NUMBER EP ECA-3.2 1 AND 2 REVISION 0 OlABLO CANYON POWER PLANT UNIT NO(S) DATE 3/8/85 PAGE 30 0F 32 SGTR WITH LOSS OF COOLANT - TITLE. SATURATED RECOVERY DESIRED APPENDIX R (continued) ACTION /EX CTED RESf0NSE RESFONSE NOT OBTAINED NOTE: Monitor flow on FI-90 (PNL 184 locally at FCV-357) and temperature on TI-1004 (Locally at FCV-357). Initiate flow to the thermal barrier slowly reducing lower bearing temperature (TI-155, 154, 153, 152 on VB2 and T0417A, T0437A, T0457A, T0477A on the P250) at a maximum rate of 1*F per minute until full thermal barrier flow is returned to normal. Some local boiling may occur in the CCW lines giving a closed signal to FCV-357.
- 5) Locally crack open FCV-357 or CCW-267
- b. Establish seal injection flow to RCPs (100', GE-127 -137*)
- 1) Wait until seal leak off water temperature (TI-148, 146,132,125) has decreased to 235*F
- 2) Establish communications between control room and the 100' aux b1dg pent area near the RCP seal water injection flow control valves CVCS-8369A, B, C & D TOTE: Monitor RCP Seal Inj Flow No. 1 seal leak off temperature and lower RCP bearing temperature. Reduce each respective RCP bearing temperature at a maximum rate of 1*F per minute until bearing temperature is less than 225'F, then normal seal injection flow can be established.
- 3) Crack open CVCS-8369 A, B, C and D one at a time s
O DC0401 30V l
NUMBER EP ECA-3.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 f) PAGE 31 0F 32 's SGTR WITH LOSS OF C0OLANT - TITLE: SATURATED REC 0VERY DESIRED APPENDIX R (continued) ACTION / EXPECTED RESFONSE RESPONSE NOT OBTAINED
- 3. AFTER RCP Seal Cooldown - Verify hormal RCP Cooling Alignment: (VBl)
- a. Verify CCW a. -
IF CCW NOT aligned to RCPs,
- ALIGNED TO RCPs THEN ensure Phase B Isolation is reset and e FCV-355 - OPEN, CCW to RCP manually open CCW oil clrs, therm bar & sup valves.
Clrs e FCV-357 - 0?EN, CCW from RCP therm bar, OC e FCV-363 - OPEN, CCW f rorr, RCP oil clrs & sup cirs, OC e FCV-749 - OPEN, CCW from RCP oil c1rs & sup clrs, IC e FCV-750 - OPEN, CCW from RCP therm bar, IC
- b. Verify RCP seal injection flow b. Adjust charging and HCV-142 to each RCP - AT 8 (6 to 12) GPM to maintain 8 (6 to 12) gpm to each RCP.
- 4. Return to step in effect O
G DC0401 31V
4 1 AND 2 NUMBER IP ECA 3.2 1 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION O I DATE 3/8/85 PAGE 32 0F 32 SGTR WITH LOSS OF COOLANT - TITLE: SATURATED RECOVERY DESIRED h APPENDIX Z j l l EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS J
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Designate this event an Alert.
- b. Designate this event a Site Area Emergency if steam generator tube rupture coincides with a loss of off-site power indicated by the inability to restore power to the
,non-vital 12KV and 4KV busses (D and E).
- c. If the primary to secondary leakage is estimated at greater than 50 gpn with fuel damage evident from a gross failed fuel monitor alarm or primary sample, designate this event as a Site Area Emergency.
- d. SI with high or increasing levels of containment pressure, area radiation or recirculation sump level. Designate this event a Site Area Emergency.
- e. In the event inadequate core cooling is verified per Critical Safety Function Status or the verification of the ESF Functioning and Effectiveness during LOCA, Appendix H, (EP OP-1), indicates ESF failure, reclassify this event as a General Emergency.
- 2. Notify plant staff and response organizations required for this classification by implementing Procedures EP G-2 " Establishment of the On-Site Emergency Organizations" and EP G-3 " Notification of Off-Site Organizations" in accordance with EP G-1 " Accident -
Classification and Emergency Plan Activation".
\
DC0401 32V
m . , _ _ .- - _ _ ._ - . _ _ _ _ _ i FOLD 0VT FOR ECA-3.2 PROCEDURE 1 ADMINISTRATIVE FUNCTIONS l
- 1. Notify STA AND MONITOR CSFs and SPDS
- 2. Refer to Appendix Z ,
4
- SI REINITIATION CRITERIA l Manually operate SI pumps as necessary if EITHER condition listed below occurs:
]
'- e RCS pressure - LESS THAN 200 PSIG
- e Core exit TCs - INCREASING e RVLIS - FULL RANGE LESS THAN 76% IF NO RCP RUNNING
- OR -
- DYNAMIC RANGE LESS THAN 29% IF ONE RCP RUNNING i
SECONDARY INTEGRITY CRITERIA l Go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1, if any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, unless needed for RCS cooldown. i O COLO LEG RECIRCULATION SWITCHOVER CRITERION l Go to E-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1, if RWST level decreases to less than 33'.. f AFW SUPPLY SWITCHOVER l Switch to alternate AFW water supply if CST level decreases to less than 10%. (Refer to E-2.1 Alternate Auxiliary Feedwater Supplies) l ADVERSE CONTAINMENT INDICATION l Containment Pressure Greater than 3 PSIG Containment Radiation Dose Rate 105R/hr Containment Radiation Dose 106R CNMT SPRAY INITIATION CRITERIA l Initiate CNMT spray when CNMT pressure >22 psig DC0401 33V
NUMBER EP ECA-3.3 yGsG Pacific Gas and Electric Company REVISION 0 m DATE 3/8/85 DEPARTMENT OF NUCLEAR PLANT OPERATIONS I I 1 AND 2 PAGE 1 0F 35 DIABLO CANYON POWER PLANT UNIT NO(S) EMERGENCY PROCEDURE l SGTR WITHOUT PRESSURIZER PRESSURE CONTROL .. l TITLE l O IMPORTANI APPROVED Y ' PLANT MANAGERg,I DATE SAFETY SCOPE This procedure provides for a SGTR with coincident loss of normal and auxiliary pressurizer sprays and PORVs. This procedure and changes thereto requires PSRC review. SYMPTOMS OP ENTRY CONDITIONS This procedure is entered f rom E-3, STEAM GENERATOR TUBE RUPTURE, Step 18, when pressurizer pressure control is not available. b DC0403 IIV
NUMBER ECA-3.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVlS10N 0 , l DATE 3/8/85 PAGE 2 0F 35 7,7g SGTR WITHOUT PRESSURIZER PRESSURE CONTROL l l ACTION /EX CTED RESPONSE RESPONSE NOT OBTAINED FOTE: e Foldout page should be open. e CRDM fans should be operating.
- 1. CHECK Ruptured SG(s) Narrow Go to Step 8.
Range Level - LESS THAN 67%: (V53)
- 2. ESTABLISH Instrument Air To Containment: (VB4)
- a. Open FCV-584, cnmt inst air iso viv
- b. Verify at least one air b. Start at least one instrument compressor . IN SERVICE air compressor.
IF inst air can NOT be restored, THEN Refer to OP AP-9, LOSS OF INST AIR, while continuing in this procedure. O OC0403 2IV l
NUMBER ECA-3.3 I AND 2 DIABLo CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 PAGE 3 0F 35 7,7 a SGTR WITH0llT PRESSURIZER PRESSURE CONTROL ACTION /EXPECED RESPONSE RESfGSE NOT OBTAINED
- 3. TRY To Establish Normal PZR Spray:
- a. Check RCP status - RCP No. a. Try to start one RCP in loop 2 or No.1 RUNNING (VB2) with operable spray line and perform the following:
- 1) Check RCP seal ret and lower rad brg temp <225 F.
IF >225*F, TIIEN refer to Appendix R and continue in this procedure.
- 2) Normal spray viv(s)
PCV-455 A or B - OPERABLE. p) (_. E (CC2) PCV-455A and B are not operable, THEN go to Step 4
- 3) IF no RCPs are running, TiiEN establish PZR conditions as follows:
- a. PZR level:
e for RVLIS Full Range
<95, establish PZR level 67% [90t]. .
e for RVLIS Full Range
>95, establish PZR Tevel 17 [40t].
- b. PZR temp - at saturation for RCS hot leg press.
- 4) Close PCV-455 A and B.
- 5) Establish RCS subcooling based on core exit TCs 35*F. (VB2)
THIS STEP CONTINUED ON NEXT PAGE i DC0403 31V l
NUMBER ECA-3.3 1 AND 2 OtABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 SGTR WITHOUT PRESSURIZER PRESSURE CONTROL TIT E ACTION /EX CTED RESR)NSE RESPONSE NOT OBTAINED
- 6) Establish conditions for starting an RCP per Appendix B.
- 7) Start RCP in loop with operable spray valve.
IF an RCP can NOT be started to an operable spray valve, THEN go to Step 4.
- b. Nonral spray . AVAILABLE b. Go to Step 4
- 1) Close normal spray viv in any idle loop (CC2) e PCV-455A Loop 1 a PCV-4558 Loop 2
- c. Go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 17; DEPRESSURIZE RCS To Mininize Break Flow And Refill PZR
- 4. TRY To Restore PZR PORV:
- a. Power to stop valves - a. Restore power to stop AVAILABLE valves.
- b. Verify at least one PZR b. Open one stop valve unless it PORV stop valve - OPEN was used to isolate an open PORV.
IF no PZR PORV can be opened, THEN go to Step 5. OBSERVE NOTE AND CAUTION PRIOR TO STEP 5. THIS STEP CONTINUED ON NEXT PAGE DC0403 41V
NUMBER ECA-3.3 1 AND 2 DIABLO CANYON POWER PLANT 'JNIT NO(S) REVISION 0 DATE 3/8/85 PAGE 5 0F 35 7,7g SGTR WITHOUT PRESSURIZER PRESSURE CONTROL ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- c. Go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 18 DEPRESSURIZE RCS Using PZR PORY To Minimize Break Flow And Refill PZR CAUTION: Auxiliary spray flow into the PZR shall not be initiated if the delta-T between the PZR and the spray fluid exceeds 560 F. Spray flow should not be initiated if the delta-T exceeds 320 F.
f0TE: If PZR Auxiliary spray is used it may be necessary to close normal spray PCV 455A & B and charging valves 8146 and 8147.
- 5. TRY To Establish Auxiliary m Soray:
' a. SI pumps - ALL RUNNING a. Try to start pumps. (VB1) IF any SI pump can NOT be started, THEN go to Step 6. OBSERVE CAUTION PRIOR TO STEP 6.
- b. Cent charging pumps - AT b. Try to start one cent LEAST ONE RUNNING (VB2) charging pump.
IF no pump can be started, TIIEN establish CCW to PD PUMP and start PD pump. E PD pump can NOT be started, THEN 90 to Step 6. OBSERVE CAUTION PRIOR TO STEP 6. THIS STEP CONTINUED ON NEXT PAGE O DC0403 SIV -
NUMBER ECA-3.3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 6 0F 35 7,7 g SGTR WITHOUT PRESSURIZER PRESSURE CONTROL ACTION /EXH CTED RESPONSE RESPONSE t0T OBTAINED
- c. Establish 60 GPM charging flow:
- 1) Throttle to 50% HCV-142 (CC2)
- 2) Open FCV-128 (CC2)
- OR -
adjust PD pump speed
- 3) Open 8105 and 8106 cent 3) IF 8105 OR 8106 will not charg pps min flow open, recirc vivs (V82) THEN maintain a minimum of 60 gpm charging flow.
- 4) Check SG 4 Intact 4) IF SG 4 NOT intact, e Open 8146, normal TiiEN e Open 8147, alt charg to LP 3 cold g
charg to LP 4 cold leg viv. leg vlv (VB2) e Close 8146, normal charg to LP 4 cold leg viv.
- 5) Close 8145 and 8148, charg line to PZR aux spray viv and bypass (VB2)
- 6) Open 6108 and 8107, normal ciarg to regen hx stop vivs 1 & 2 (VB2)
- 7) Establish 60 GPM.
Adjust charging and HCV-142 to maintain ' e PZR Level e Seal Injection i THIS STEP CONTINUED ON NEXT PAGE h l DC0403 6IV
i l NUMBER ECA-3.3 1 otAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 i DATE 3/8/85 PAGE 7 0F 35 7,7g. SGTR WITHOUT PRESSURIZER PRESSURE CONTROL ACTION /EXRCTED RESPONSE RESPONSE NOT OBTAINED
- d. Isolate BIT (VB2):
- 1) Close 8803A and B, BIT inlet valves
- 2) Close 8801A and B, BIT outlet valves
- e. Establish aux spray flow: e. Go to Step 6. Observe
- 1) Open aux spray vivs as necessary: (VB2) e 8145 e 6148
- 2) Close normal charging and normal spray vivs as Os necessary: (VB2/CC2) e 8146 e PCV-455A e 8147 e PCV-455B
- f. Go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 17c spray PZR With Maximum Available Spray Until ANY Of The Following Conditions Satisfied O
DC0403 71V
NUMBER ECA-3.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 PAGE 8 0F 35 TITLE SGTR WITHOUT PRESSURIZER PRESSURE CONTROL O ACTION / EXPECTED RESRASE RESPONSE NOT OBTAINED CAlJTION: Alternate water sources for AFW pumps will be necessary if CST level decreases to less than 10% (Refer to E-2.1 ALTERNATE AUXILIARY FEEDWATER SUPPLIES).
- 6. CHECK Intact SG Levels: (VB3)
- a. Narrow range level - a. Maintain total feed flow GREATER THAN 4t[20%] greater than 460 GPM until narrow range level greater than 4%[20%] in at least one SG.
- b. Control feed flow to b. IF- narrow range level in maintain narrow range level any intact SG continues between 4k[20;] and 33t to increase in an uncontrolled manner,
- c. Stop TD AFW pp if not needed for RCS heat removal
- 7. CHECK PZR Level - GREATER Return to Step 1.
IhAf 4 ei_20; j: I 1 O DC0403 8IV
v NUMBER ECA-3.3 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 ~ DATE 3/8/85 PAGE 9 0F 35 TITLE. SGTR WITHOUT PRESSURIZER PRESSURE CONTROL ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. CHECK If ECCS Can Be Te rmina ted:
- a. RCS subcooling based on a. Go to ECA-3.1, SGTR WITH LOSS core exit TCs - GREATER OF REACTOR COOLANT -
THAN 20 F (VB2/PAM3/4) SUBC00 LED RECOVERY DESIRED.
- b. Secondary heat sink: (VB3) b. IF neither condition satisfied, e Total feed flow to SGs - THEN go to ECA-3.1, SGTR WITH GREATER THAN 460 GPM LOSS OF REACTOR COOLANT AVAILABLE - SUBC00 LED REC 0VERY DESIRED.
- OR -
e Narrow range level in at 7- s least one intact SG - ( ,) GREATER THAN 41[20*,]
- c. RVLIS full range indication c. Go to ECA-3.1, SGTR WITH
- GREATER THAN (PAMS 3/4) LOSS OF REACTOR COOLANT -
SUBC00 LED REC 0VERY DESIRED. RCPs ON RANGE LEVEL 0 RCP Full Range 63% 1 RCP Dynamic Range 28% 2 RCP Dynamic Range 35% 3 RCP Dynamic Range 46% 4 RCP Dynamic Range 63%
- d. Any ruptured SG narrow d. Return to Step 3.
range level - INCREASING IN AN UNCONTROLLED MANNER OR OFFSCALE HIGH m DC0403 91V
NUMBER ECA-3.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 PAGE 10 0F 35 7,7 g SGTR WITHOUT PRESSURIZER PRESSURE CONTROL ACTION /EXRCTED RESPONSE RESPONSE NOT OBTAINED 1 l
- 9. STOP ECCS Pumps: ,
- a. Stop SI pumps i
- b. Check any cent charg pp - 1) Ensure P0 charging pump RUNNING running
- 2) Control charging pump speed, FCV-128 and HCV-142 to maintain:
e Seal Injection. e PZR Level. ,
- 3) Go to Step 10.
- c. Open FCV-128
- d. Stop the PD charg pp
- e. STOP one of two running cent charg pp s
O DC0403 10lV
NUMBER ECA-3.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 7,7 g SGTR WITHOUT PRESSURIZER PRESSURE CONTROL ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
' 10. ESTABLISH Charging Flow:
- a. Throttle to 50% - HCV-142 (CC2)
- b. Open FCV-128 (CC2)
- c. Open 8105 and 8106, cent c. IF- 8105 OR 8105 will NOT charg pps min flow vivs open (VB2) THEN maintain a minimum of 60 gpm charging flow
- d. IF SG 4 intact d. IF SG 4 NOT intact, E EN open 8146, norrr.al WEN e Open 6147, alt charg charg to LP 4 cold leg to LP 3 cold leg viv.
vlv e Close 8146, normal charg to LP 4 cold O v leg viv.
- e. Close 8145 and 8148, charg line to PZR aux spray viv and bypass (VB2)
- f. Open 8108 and 8107, normal charg to regen hx stop vivs
; 1 & 2 (VB2)
- 9. Start one cent charg pp (VB2)
- OR -
- 1) Ensure CCW flow to PD charg pp
- 2) Start charg PD pp (VB2)
O v DC0403 111V l l
NUMBER ECA-3.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 PAGE 12 0F 35 7,7 g SGTR WITHOUT PRESSURIZER PRESSURE CONTROL ACTION /EX CTED RESPONSE RESPONSE NOT OBTAINED
- h. Adjust charging and HCV-142 to maintain: (CC2) e PZR level e Seal injection to each RCP 8 (6-12) GPM
- 11. ISOLATE BIT (VB2)
- a. Close 8803 A & B, BIT supply Vlvs
- b. Close 8801 A & B, BIT outlet vivs
- 12. VERIFY ECCS Flow Not Recuired: Manually operate ECCS pumps as necessary. Go to ECA-3.1, e RCS subcooling based on core SGTR WITH LOSS OF REACTOR exit TCs - GREATER THAN COOLANT - SUBC00 LED REC 0VERY 20 F (VB2) DESIRED.
e RVLIS full range indication
- GREATER THAN (PAM 3/4)
RCPs ON RAtiGE LEVEL 0 RCP Full Range 63% 1 RCP Dynamic Range 31% 2 RCP Dynamic Range 35% 3 RCP Dynamic Range 46% 4 RCP Dynamic Range 63%
~
I S DC0403 12IV
NUMBER ECA-3.3 I AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/8/85 T'N PAGE 13 Of 35 U 7,7g SGTR WITHOUT PRESSURIZER PREE5URE CONTROL ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 13. CHECK VCT Makeup Control -
IF VCT makeup control Systems: unavailable, THEN maintain RWST suction. e Ensure makeup set for - GREATER THAN RCS BORON CONCENTRATION OR 2000 PPM (7.0 turns) e Makeup set for automat-ic: (Refer to OP B-1A:VII CVCS - MAKEUP CONTROL SYSTEM OPERATION Part A - PLACE IN AUTOMATIC) e Instrument air AVAILABLE
- 14. ESTABLISH Letdown:
- a. Establish normal letoown: -
IF normal letdown NOT available,
- 1) Check PZR level >17% THEN establish excess letdown as
[40] follows:
- 2) Open FCV-355 CCW, hdr C a) Place charg pp control iso viv in manual and reduce charg flow to min.
- 3) Position to 20',TCV-130, LTDN temp Cont viv b) Close 8107 and 8108, charg hdr iso vivs.
- 4) Position to 40% PCV 135, Itdn press cont viv c) Adjust charging to maintain seal injection
- 5) Open LCV 459 and 460, 8 (6-12) GPM.
itdn stop vivs
- 6) Ensure a minimum of 45 gpm charg flow through regen hx
- 7) Place in AUTO LCV 112A, VCT Ivl cent divert viv THIS STEP CONTINUED ON NEXT PAGE
! DC0403 13IV i
Nt;MBER ECA-3.3 1 ANO 2 OLABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 PAGE 14 0F 35 7,7 2 SGTR WITHOUT PRESSURIZER PRESSURE CONTROL O ACTION / EXPECTED RESPONSE RESfm SE NOT OBTAINED
- 8) Open 8152, Itdn iso viv OC
- 9) Open as necessary to d. E 8100 and 8112 open, establish adequate letdown: THEN place 8143 in nomal position e 8149A 45 GPM (VCT), excess Itdn to seal wtr hx or RCOT
- AND/0R - viv.
e 81498 75 GPM e IF
--~
8100 and 8112 closed.
- AND/0R - THEN place 8143 in RCDT position.
e 6149C 75 GPM
- e. Open FCV-355, CCW hdr C
- 10) Maintain 350 psig on PI iso viv.
135 with PCV-135
- f. Open FCV-361, CCW from excess Itdn hx.
- g. Close HCV-123, excess Itdn flow cont viv.
- h. Cpen 8166 and 8167, excess Itdn stop vivs.
- i. Open HCV-123 as necessary to maintain:
o PZR LVL. e Less than 190*F on TI-122. O DC0403 141V
I NUMBER ECA-3.3 l 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 TITLE SGTR WITHOUT PRESSURIZER PRESSURE CONTROL ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
' 15. ALIGN Charging Pump Suction Maintain charging pump To VCT: (VB2) suction to RWSI.
- a. Check VCT level >10%
- b. Open LCV 112 B & C, VCT cutlet valves
- c. Close 8805A & B charg pp suct from RWST
- 16. EOUALIZE Charaing And Letdown Flows: (CC2/V64)
- a. Take manual control of charging and letdown O b. Control charging and seal injection flows to equal letdown and seal leakoff flows
- 17. CHECK If Diesel Generators Should Be Stooped:
- a. Check vital busses F, G and a. Try to restore offsite power, H - ENERGIZED BY OFFSITE either STARTUP or AUXILIARY, POWER (VB4) to the vital busses.
- b. Stop any unloaded diesel generator and place in AUTO O
DC0403 ISIV
NUMBER ECA-3.3 1 AND 2 OlASLO CANYON POWE'l PLANT UNIT NO(S) REVISION 0 DATE 3/8/8S PAGE 16 0F 35 7g SGTR WITHOUT PRESSURIZER PRESSURE CONTROL ACTION /EXECTED RESPONSE ESPONSE NOT OBTAINED
- 18. MINIMIZE Secondary System Contamination:
- a. Isolate reject as follows:
- 1) Close LCV-12, condensate reject vlv
- 2) Sample the hotwell
- 3) Use reject, in manual, based on hotwell sample results
- 4) Maintain CST level below the overflow
- b. Isolate condensate polisher demins: (VB3)
- 1) Open FCV 230, cond polisher bypass viv
- 2) Close FCV 231, cond polisher inlet valve
- c. Transfer aux steam supply to aux boiler (Refer to OP K-5 IV, Part B)
- d. Ensure MSR isolated
- e. Ensure main feed pumps gland seal supplied from aux boiler
- f. Manually transfer blowdown tank outlet from outfall to EDRT (FCV-498 closed and FCV-499 opened) '
- g. Verify blowdown and sample 9. Manually isolate blowdown.
isolation has occurred 9 l DC0403 161V a
NUMBER ECA-3.3 1 AND 2 DIA8LO CANYON POWER P T UNIT NO(S) REVISION 0 DATE 3/8/85 l PAGE 17 0F 35 7,7 a SGTR WITHOUT PRESSURIZER PRESSURE CONTROL ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 19. CHECK If RCP Seal Return Flow Should Be Established: ,
- a. Check RCP seal return was a. Go to Step 20. ,
not isolated due to suspected seal damage
- b. Establish seal return flow:
- 1) Reset SI (VB1)
- 2) Reset Phase A and B Isolation (VB1) ,
- 3) Close any RCP *1 seal ret iso viv with GREATER THAN 6 GPM (n) return flow indicated (VB2) 8141A RCP 1 8141B RCP 2 8141C RCP 3 81410 RCP 4
- 4) Open FCV-355. CCW hdr C iso viv (VB1)
- 5) Ensure CCW flow to the seal ret hx
- 6) Open 8100 and 8112, RCP seal ret iso vivs O
V 0C0403 17IV
NUMBER ECA-3.3 1 AND 2 REVISION 0 OIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/8/85 PAGE 18 0F 35 TITLE. ACTION /DTECTED RESPONSE RESPONSE NOT OBTAINED
- 20. CHECK RCP Cooling - NORMAL:
- a. RCP seal ret and lower rad a. Refer to Appendix R and go to brg temp <225*F Step 21.
- b. Verify CCW - ALIGNED TO RCPs (VBI) e Open FCV-355, CCW hdr C iso viv e Open FCV-356, CCW to RCP cil cles therm bar & sup Clr5 e Coen FCV-357, CCW from RCP therm bar 0C e Open FCV-363, CCW from RCP eil cirs & sup c1rs llll OC s Open FCV-749, CCW from RCP cil & sup cles IC 1
e Open FCV-750, CCW from RCP therm bar IC l c. Verify RCP seal injection c. Adjust HCV-142 as necessary, RCP seal inj back pressure flow 8 (6-12) GPM to each RCP(VB2) viv. DC0403 181V
NUMBER ECA-3.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 O PAGE 19 0F 35 (/ SGTR WITHOUT PRESSURIZER PRESSURE CONTROL TIT E ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAltED s
- 21. CHECK If SR Detectors Should Be Energized: (CCl)
- a. Check IR Flux a. Continue with Step 22.
- LESS THAN 10 10 AMPS WHEN flux less than 1010 amps.
THEN complete Steps 21b and C.
- b. Verify both SR detectors - b. Manually reset and energize ENERGIZED both SR detectors.
- c. Select highest SR & IR detectors on NR 45
- 22. SHUT Down Unnecessary Plant Equipment:
- a. Stop any running plant equipment not required for post accident recovery.
(Refer to OP L-5 PLANT C00LDOWr4 FROM MINIMUM LOAD TO COLD SHUTDOWN) O DC0403 191V
NUMBER ECA-3.3 1 AND 2 REVISION 0 DIABLO CANYON POWE] PLANT UNIT NO(S) DATE 3/8/85 PAGE 20 0F 35 7gg SGTR WITHOUT PRESSURIZER PRESSURE CONTROL h ACTION /EX CTED ESPONSE RESPONSE NOT OBTAINE POTE: Plant staff should decide whether to repair PZR pressure control systens or continue with this procedure. If PZR pressure control is established, further recovery should continue with E-3, STEAM GENERATOR TUBE RUPTURE, Step 29, CONTROL RCS Pressure And Makeup Flow To Minimize RCS-to-Secondary Leakage:
- 23. CHECK If SI Accumulators Shculd Be Isolated:
- a. Check RCS pressure <1000 a. Go to Step 24, psig
- b. RCS subcooling basec on b. Go to ECA-3.1, SGTR WITH LOSS ccre exit TCs - GREATER OF REACTOR COOLANT -
THAN 20 F (VB2) SUBC00 LED REC 0VERY DESIRED.
- c. Check pcwer to accum disch c. Restore power to isolation 150 vivs . AVAILABLE valve.
- d. Close all accum disch iso d. IF-any accum 150 valve does vivs(VBI) NOT close, THEN perfom the following:
8808 A, B, C & D
- 1) Close FCV-8880 accum N2, fill iso viv.
- 2) Open 8875 A, B, C, or D accum N2 supply to affected accum.
- 3) Open HCV-943 accum N2 supply line vent, UNTIL accumulator is depressurized and '
continue in this procedure. e DC0403 20!V l
i NUMBER ECA-3.3 f 1 AND 2 i DiAsLO CANYON POWER Pt. ANT UNIT NO(S) REVISION O DATE 3/8/85
,q PAGE 21 0F 35 j U 7,7a SGTR WITHOUT PRESSURIZER PRESSURE CONTROL ACTION /EXRCTED RESR)NSE RESRESE t0T OBTAINED
' 24. VERIFY Adequate Shutdown Margin:
- a. Sample ruptured SG(s)
- b. Sample RCS
- c. Shutdown margin - ADEQUATE c. Borate as necessary.
(Refer to STP R-19 SHUTDOWN
, MARGIN CALCULATION)
- 25. MAINTAIN Reauired RCP Seal Injection Flow;
- a. Adjust charging and HCV-142 to maintain seal injection to each RCP 8 (6-12) GPM (CC2)
- 26. INITIATE RCS Cooldown To 350 F:
- a. Maintain cooldown rate in RCS cold legs LESS THAN 100 F in any one hour period (VB2, VB3, CC2)
- b. Dump steam to condenser b. Manually or locally durp from intact SG(s) (VB3) steam from intact SG(s) IM steam dumps.
IF no intact SG available. TiiEN use faulted SG. O o DC0403 21IV r i
NUMBER ECA.3.3 1 AND .' REVISION 0 DIA81C CANYON POWE] PLANT UNIT NO(S) DATE 3/8/85 PAGE 22 0F 35 7g.gg SGTR WITHOUT PRESSURIZER PRESSURE CONTROL ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAIJTION: RCS and ruptured SG(s) pressures must be maintained less than the ruptured SG(s) 10% Steam Dump setpoint.
- 27. CONTROL Charging Flow To Maintain RCS Subcooling:
- a. RCS subcooling based on a. increase charging ficw to core exit TCs - GREATER maintain subcooling greater THAN 40*F (VB2) than 40*F. Go to Step 29
- b. Any ruptured SG narrow b. Control charging flow to rance level . LESS THAN maintain RCS pressure at 96;[90t](VB3) ruptured SG(s) pressure. Go to Step 28.
- c. Ruptured SG(s) narrow range c. Decrease charging flow to level'. STABLE OR stabilize level. Maintain DECREASING (VB3) RCS subcooling greater than 40'F.
- 28. CHECK If RCS Cooldcan Should Be Stopcec:
- a. RCS temperatures - LESS a. Return to Step 24 THAN 350*F (V02)
- b. Stop RCS cooldown
- 29. CHECK RCS Pressure . GREATER Go to Step 32.
THAt. 390 P5IG: (VB2) k 9 OC0403 22!V i
NUMBER ECA-3.3 l 1 AND 2 DBASLO CANYON POWER PLANT UNIT NO(S) REVISION 0 i DATE 3/8/85 q PAGE 23 0F 35 b 7,7 3 SGTR WITHOUT PRESSURIZER PRESSURE CONTROL ACTION / EXPECTED ESPONSE RESPONSE NOT OBTAINED
' 30. CHECK Ruptured SG(s) Narrow Refill ruptured SG to 67:
Range Level - GREATER THAN using feed flow. 4t[20%J: (VB3)
~
IF either of the following conditions occurs, o Ruptured SG pressure decreases in an uncontrolled manner
- OR -
e Ruptured SG pressure increases to 1010 psi 9. THEN stop feed flow to ruptured SG O DC0403 231V
NUMBER ECA-3.3 1 AND 2 REVISION 0 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 3/8/85 7g SGTR WITHOUT PRESSURIZER PRESSURE CONTROL ACTION /EX RCTED RESPONSE RESPONSE NOT OBTAINED CAUTION: e Steam should not be released from a ruptured SG if water may exist in its steamline. e Ruptured SG pressure may decrease rapidly when steam is released. N)TE: The upper head region may void during RCS depressurization if RCPs are not running. This may result in a rapidly increasing PZR level.
- 31. DEPPESSURIZE RCS And Ruptured SG(sI To 390 PSIG:
- a. Perform the following:
e Decrease charging and increase letdown to initiate backfill
. OR .
e Initiate blowdown from ruptured SG(S)
. OR .
e Dump steam f rom ruptured SG(s)
- b. Check RCS pressure - LESS b. Return to Step 30.
THAN 390 PSIG
- c. Stop RCS depressurization s
O DC0403 24IV L
NUMBER ECA-3.3 1 AND 2 OtA8LO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 () TITLE. SGTR WITHOUT PRESSURIZER PRESSURE CONTROL PAGE 25 0F 35 ACTION / EXPECTED RESFONSE RESPONSE NOT OBTAINED
' 32. CHECK If RHR System Can Be Placed In Service: (VB2)
- a. RCS temperature - LESS THAN a. Return to Step 26.
350'F
- b. RCS pressure - LESS THAN b. Return to Step 30.
390 PSIG
- c. Consult with TSC to determine if the low setpoint over
! pressure protection system should be cut in
- d. Place RHR Systeta in service (Implement OP B.2:V RPR -
O. PLACE IN SERVICE DURING PLANT C00LDOWN) i l O DC0403 251V
NUMBER ECA-3.3 DtABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISION O DATE 3/8/85 PAGE 26 0F 35 SGTR WITHOUT PRESSURIZER PRESSURE CONTROL g g TITLE ACTION /EXPE N D RESPONSE RESPONSE NOT OBTAINED
- 33. VERIFY Adequate Shutdown Ma rgin:
- a. Sample ruptured SG(s)
- b. Sample RCS
- c. Shutdown margin - ADEQUATE c. Borate as necessary.
(Refer to STP R-19 SHUTDOWN MARGIN CALCULATION)
- 34. INITIATE RCS Cooldown To Cold Shutdown:
- a. Maintain cooldown rate in RCS cold legs LESS THAN 100 F in any one hour period
- b. Use RHR System
- c. Place to CONT ONLY, LCV-12 selector switch
- c. Dump steam to condenser d. Manually or locally dump from intact SG(s) steam from intact SG(s) with 10% Steam Dumps IF no intact SG available and RHR systen NOT in service, THEN use faulted SG.
OC0403 26IV l
NUMBER ECA-3.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 7,7g SGTR WITHOUT PRESSURIZER PRESSURE CONTROL ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
' 35. CONTROL Charging Flow To Maintain RCS Subcooling:
- a. RCS subcooling based on a. Increase charging flow to core exit TCs - GREATER maintain subcooling greater THAN 40*F (VB2) than 40*F. Go to Step 36.
- b. Any ruptured SG narrow b. Control charging flow to range level - LESS THAN maintain RCS pressure equal 96%[90%](VB3) to ruptured SG(s) pressure.
Go to Step 36.
- c. Ruptured SG(s) narrow range c. Decrease charging flow te level -- STABLE OR stabilize level. Maintain DECREASING (VB3) RCS subcooling greater than 40 F.
I ________________
- 36. CHECK If RCPs Must Be Stopped:
- a. Check the following: (VB2) a. Go to Step 37, e Number 1 seal differential pressta 2
- LESS THAN 215 PSID
- OR -
e Number 1 seal leakoff flow outside limits of Appendix B
- b. Stop affected RCP(s) (VB2)
- c. Close normal spray viv in anyidleloop(CC2)
- 37. CHECK RCS Teyperatures - LESS Return to Step 33.
THAN 200"F: (VB2) DC0403 271V l __-- i
- ~ - _
NUMBER ECA-3.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 PAGE 28 0F 35 tit a SGTR WITHOUT PRESSURIZER PRESSURE CONTROL g ACTION /EXRCTED RESPONSE RESPONSE NOT OBTAINED
- 38. EVALUATE Long Term Plant Status:
- a. Consult plant staff in TSC for RV venting approval (Refer to FR-I.3, RESPONSE TO Y0 IDS IN REACTOR VESSEL)
- b. Maintain cold shutdown conditions:
e RCS temp <,200 F eKeff * '99
- c. Check containment atmosphere to determine if hydrogen recombiners or if hydrogen purge should be placed in service g
- d. Implement OP L-5 PLANT C00LD0WN FROM MINIMUM LOAD TO COLD SHUTDOWN and review for applicable actions
- e. CHECK STP M-55 CYCLIC REVIEW
- f. Consult plant engineering staff
- END -
O DC0403 281V ;
NUMBER ECA-3.3 1 AND 2 REVISION 0 l DIABLO CANYON POWER PL. ANT UNIT NO(S) DATE 3/8/85
, PAGE 29 0F 35 7,7 g SGTR WITHOUT PRESSURIZER PRESSURE CONTROL APPENDIX B i
Restart of Reactor Coolant Pump
- 1. Start oil lift pump, run for 2 minutes.
- 2. Verify CCW available to thermal barrier, oil coolers, seal water HX.
- 3. Verify seal dp greater than 215 psid, depressurize VCT as necessary.
- 4. Verify seal injection flow 8 (6 to 12) gpm.
- 5. Verify seal leak off flow within limits shown on graph.
- 6. Ensure closed 455A and B, normal PZR spray vivs (Auto Optional).
ALLOWABLE RCP #1 SEAL LEAK RATES
] S
! I f
! l l
! l ! I i i ! l l i 4 i .
! I j i i SHUTDOWN RCP WITHIN .
i l
; ONE HALF HOUR l r ; '
3 ! l l l l l i i
! i i
i , i I I I l 5 i ; i ! i i O 4
- i' SAFE OPERATING REGION 52 ' I l ! l . I ; {
# j i i
i 3 i g ;
' REGION i REGION g 2 :
I 8 i
- I ,
, ,D0 NOT START RCP O
( 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 2400 RCP #1 SFat DIFFERENTIAL PRE 55UoE PSID i REGION 1 NO PHASE.A $1GNAL. dp=RCS,mg,.VCT, 3, PHASE.A PRESENT, dp*RCS,ygg-150psig REGION 2 USE INSTALLED dp GAUGES DC0403 291V
NUMBER ECA-3.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 PAGE 30 0F 35 SGTR WITHOUT PRESSURIZER PRESSURE CONTROL g APPENDIX C 2600 __._. . .. , _ _ . ;___ . .;= _. _{i= ,j _; _ x __3__ _, . . . _ . _ _
. --t- - :--l .
_ _ . . - _ .--._-..y_-_._.- -a__ . . _ . .
- - + . = = :== = . . _ _ . _ .. = - - t t== -- - - - - - --
rur:
~*"
2400
~ q" ..*. . _. _.~ = ~ ~ . .
=
4 -_ ,- - - - . .--., J g _
-. :I; :
==.t---~-1_-~-
L _ . . [.: ==- == := - - f.__ yl__ _ __ t . _ s g .=__;. . . r_
- . . - . _ _ = . _= _ . . . _ .
_ . ; -g -.-
- -1:
.;_ = i=1 ._
- ~ ^ - - - -
2000 . - . _ . , ..-._ ; _._ _ _ . , . - ,'=,'_-..-. --
. 2 , _.1._ +
. _ . _ . _ . . ._.a __ ._ . _ . . . . _ _ _ _ . . _ . . _ . _ .
-~~ " = ~ ~ ~ ~ ~ - - ~ ' - " ~~~~ * -" --~'='"~- #~
1800 r=_;2 3_..j;__= ;=- =. . _ _ _2 p. ._. . . e
..=_. ____.....__._
u: _x - -- _p_u_.p_.__.._.m..._.,..__..__.___ g == .2===; --- - : u- ; - g 3 - ;= - .
~
c- 1600
~ -r- -
- - r
_:2___n y -
. _- _j . _. _ . _ +:_=:=
_ =; r-- - --- . --. = ;=:r_=. _ __
^^ ~ ]
., '~~~[..~~_ --I C~Z~
m 1400 m - , - - - - , : : -+ w e
' ;" . :_.:._-._C.-_'
---*-~~~[ L.;.__j - * -
C- ' L1= l . --' 2 T. 2;.._. w 1200 E 9=R=;=[.2-~iE- SATURATION CURVE ---
/ SATURATION i.~.
F , /;d
~- ~ -
E -
-- , E CORRECTED FOR CURVE ~s_ .
~-^--*= INSTRUMENT ERROR =/=I
~
8 W 1000 I y 2 . t_____-
, = - - - q="": =*r--
j~_~_'y --.=
- ~
E" 800 /. -/. p .
+-- _-_h--
600 ~- 1 j-j
= _ . .. . , . -:
400
~~
N ~2= ____ _ ; q.__.__.
+ 65 psi !,~
! P - ~~r~-~
+ - - - - - + - ' - - .
= PNSSURE ERROR ,
200 TEMPERATURE ERROR I 24 'F u ---&.-,--' 2 ._t--,- _ =._ _ . .
=:
~
,g.
- ~ '
200 300 400 500 600 700 CORE EXIT T/C TEMPERATURE (*F) { } DC0403 30IV 1
NUMBER ECA-3.3 l 1 AND 2 OtABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 j DATE 3/8/85 j
] /
7,7g SGTR WITHOUT PRESSURIZER PRESSURE CONTROL PAGE 31 0F 35 l 1 APPENDIX R
- l RCP HOT SEAL C00LDOWN l If RCP seal returns or lower radial bearing temp has been or is >225 F l perform the following:
ACTION /EXPEuw RESPONSE RESR)NSE NOT OBTAINED i
- 1. CHECK RCP Seal Isolation Status;
- a. Verify seal injection iso a. -
IF valves open or position vivs CC - CLOSED not known, THEN check centrifugal charging pump status:
- 1) IF pump running, WEN return to step in effect.
IF pump NOT running,
- 2) W EN manuaTTy or locally close seal injection vivs 0C.
- b. FCV-357 - CLOSED, RCP therm b. -
IF valve is open or bar CCW return iso viv, position not known, OC THEN check CCW pump status: IF a pump is running,
- 1) WEN go to Step 2b.
- 2) IF pump NOT running, W EN manually or locally close FCV-357.
(100',GE-166*) IF FCV-357 can NOT be closed, THEN manually close FCV-750, CCW return l viv IC. 1 l 1 l o i { l DC0403 311V
l l NUMBER ECA-3.3 1 DIABLO CANYON POWER Pt. ANT UMT NO(S) 1 AND 2 REVISION 0 DATE 3/8/85 PAGE 32 0F 35 Taa SGTR WITHOUT PRESSURIZER PRESSURE CONTROL h APPENDIX R (Continued) ACTION! EXPECTED RESfGSE RESPONSE NOT OBTAlfED CAUTION: e RCP thermal barrier cooling should be established slowly to minimize potential introduction of steam into the CCW system. e RCP seal injection should be established slowly to minimize RCP therral stresses and potential seal failures. e As part of subsequent recovery actions, RCPs should not be started prior to a status evaluation.
- 2. ESTABLISH RCP Seal Coolina:
- a. Establish CCW flow to RCP thermal barriers (100',
GE-166 ) h
- 1) Establish comunications between the control room and 100' area near FCV-357
- 2) Moniter RCP lower .
bearing temperature (TI-155,154,153,152 on V82 and T0417A, T0437A, T0457A, T0477A on th,e P250)
- 3) Check FCV-357 - CLOSED 3) Close FCV-357
-0R-CCW-267.
s
- 4) Check FCV-750 - OPEN, 4) IF, FCV-357 or RCP therm bar CCW return CCW-267 CLOSED, iso viv IC THEN open FCV-750.
THIS STEP CONTINUED ON NEXT PAGE l DC0403 32IV l l
NUMBER ECA-3.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85
/~T PAGE 33 0F 35 i'~/ SGTR WITHOUT PRESSURIZER PRESSURE CONTROL 7,72 APPENDIX R (Continued) s ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Monitor flow on FI-90 (locally at FCV-357) and temperature on TI-1004 (Locally at FCV-357). Initiate flow to the thennal barrier slowly reducing lower bearing temperature (TI-155,154,153,152 on VB2 and T0417A, T0437A, T0457A, T0477A on the P250) at a maximum rate of 1*F per minute until full thermal barrier flow is returned to normal. Some local boiling may occur in the CCW lines giving a closed signal to FCV-357.
- 5) Locally crack open FCV-357 or CCW-267
- b. Establish Seal Injection Flow to RCPs (100',
m GE-127 -137*):
- 1) Wait until seal leak off water temperature (TI-148,146,132,125) has decreased to 235'F
- 2) Establish communications between control room and the 100' area near the RCP seal water injection flow control valves CVCS-8369A, B, C & D M)TE: Monitor RCP Seal Inj Flow No. I seal leak off temperature and lower RCP bearing temperature. Reduce each respective RCP bearing temperature at a maximum rate of l'F per minute until bearing temperature is
- less than 225 F, then nonnal seal injection flow can l be established.
- 3) Crack open CVCS-8369 A, B, C and D one at a time DC0403 331V
NUMBER ECA-3.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/8/85 PAGE 34 0F 35 . in E SGTR WITHOUT PRESSURIZER PRESSURE CONTROL 4h 1 APPENDIX R (Continued) ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. AFTER RCP Seal Cooldown .
VERIFY Normal RCP Cooling Alignment:
- a. Verify CCW (VB1) a. IF CCW NOT aligned to
- ALIGNED TO RCPs RCPs, THEN ensure Phase B e FCV-355 - Open CCW to RCP Isolation is reset and oil clrs, therm bar & sup manually open CCW clrs valves.
e FCV-357 - Open CCW from RCP therm bar, OC e FCV-363 - Open CCW from RCP oil cirs & sup c1rs, OC e FCV.749 - Open CCW from RCP oil clrs & sup c1rs IC e FCV-750 - Open CCW from RCP therm bar, IC
- b. Verify RCP seal injection b. Adjust charging HCV-142 to flow to each RCP - AT 8 (6 maintain 8(6 to 12) gpm to to 12) GPM (V82) each RCP.
- 4. Return to step in effect s
O 1 l DC0403 34IV
NUMBER ECA-3.3 1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 0
- DATE 3/8/85 PAGE 35 0F 35 7,7g SGTR WITHOUT PRESSURIZER PRESSURE CONTROL APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION
- 1. When this emergency procedure has been activated upon direction from the Shif t Foreman proceed as follows:
- a. Designate this event an Alert. Notify plant staff and response organizations required for this classification by Emergency Procedure G-2 " Establishment of On-Site Organization" and Emergency Procedure G-3 " Notification of Off-Site Organization" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation".
P
- b. Designate this event a Site Area En rgency if steam genertor tube rupture coincides with a loss of Msite pwoer indicated by the inability to restore power to non-vital 12KY and 4KV busses (D and E). Notify plant staff and response organizations required by EP G-2 and EP G-3 in V accordance with EP G-1.
- c. If the primary to secondary leakage is estimated at >50 gpm with fuel damage evident from a gross failed fuel monitor alarm or primary sample, designate this event a Site Area Emergency.
- d. In the event inadeqaute core cooling is verified per Critical Safety Function Status Trees, reclassify this event as a General Emergency. Notify plant staff and response organizations required by EP G-2 and EP G-3 in accordance with EP G-1.
O v l l l DC0403 35IV
FOLD 0VT FOR EP ECA-3.3 PROCEDURE p O ADMINISTRATIVE FUNCTIONS l
- 1. Notify STA Monitor CSFs and SPDS -
- 2. Refer to Appendix Z b
SI REINITIATION CRITERIA l Manually operate SI pumps as necessary if EITHER condition listed below occurs: e RCS subcooling based on core exit TCs - LESS THAN 20*F e RVLIS full range indication - LESS THAN 63% SECONDARY ItiTEGRITY CRITERIA l Go to EP E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1, if any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated. O AFH SUPPLY SWITCHOVER CRITERION l Switch to alternate AFW water supply if CST level decreases to less than 10%. (Refer to E-2.1, ALTERNATE AUXILIARY FEEDWATER SUPPLIES.) ADVERSE CONTAINMENT INDICATION l Containment pressure greater than 3 psig Containment radiation dose rate 105R/hr Containment radiation dose rate 106R/hr EXCESS LTDN AND RCP SEAL RETURN ISO CRITERIA l Excess LTDN and seal return should be isolated if PZR level is less than 4% [20%]. r' ( 1 l DC0403 3611
NUMBER EP F-0 , 7Gui3 Pacific Gas and Electric Company REVISION 0 DEPARTMENT OF NUCLEAR PLANT OPERATIONS 1 AND 2 PAGE 1 0F 7 DIABLO CANYON POWER PLANT UNIT NO(S) EMERGENCY PROCEDURE CRITICAL SAFETY FUNCTION STATUS TREES - O IMPORTANT APPROVED. - PLANTMANAGgl DATE SAFETY SCOPE This procedure contains the six (6): Critical Safety Function Status Trees (CSFSTs). These CSFSTs are used in monitoring those safety functions related to the maintenance of the various barriers to the release of radioactive caterial to the environment. This procedure and changes thereto require PSRC review. SYMPTOMS CR ENTRY CONDITIONS
- 1. E-0, REACTOR TP.IP OR SAFETY INJECTION, has been implemented.
- 2. ECA-0.I, LOSS OF ALL AC POWER REC 0VERY WITHOUT SI REQUIRED, Step 9.
- 3. ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, Step 7.
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NUMBER EP FR-S.1 7 Gui3 Pacific Gas and Electric Company REVISION O DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 3/7/85 4 PAGE 1 0F 9 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE TITLE l RESPONSE TO NUCLEAR POWER GENERATION /ATWS lMPORTANT APPAOVED M I 89545 TO ! PLANT MANAGE;R DATE SAFETY SCOPE This procedure provides actions to add negative reactivity to the core if it is observed to be critical when expected to be shut down. This procedure and changes thereto requires ?SRC review. SYMPTOMS OR ENTRY CONDITIONS
- 1. E-0, REACTOR TRIP OR SAFETY INJECTION, Step 1, when reactor trip is not verified and manual trip is not effective.
J
- 2. F-0.1, SU5 CRITICALITY Critical Safety Function Status Tree on either a RED or ORANGE condition.
i i l l l O DC0273 IVI
i i DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON ; DATE 3/7/85 TITLE: RESPONSE TO NUCLEAR POWER GENERATION /ATWS ACTION / EXPECTED RESP 06E RESPONSE NOT OBTAINED NOTE: Imediate actions are designated by circled steps. VERIFY Rasctor Trip e Reactor Trip and Bypass e Manually Trip reactor (CC1/VB2) Bkrs - OPEN (VB2) e Rod Bottom Lights - lit - OR - (VB2) e Manually de-energize 480V busses feeding rod drive MGs* UNIT 1 De-energize 13D & 13E (VBS) UNIT 2 De-energize 230 & 23E (VB5) IF Reactor will h0T trip THEN
- Verify control rods inserting at maximum rate in AUTO
- OR -
Manually insert control rods while continuing with Step 2. IF Reactor will trip TiiEN Perform the following:
- 1) e Manually Trip Turbine.
e Trip Both Main Feed Purrps. e Dispatch personnel to open Reactor trip BKRS locally. e Re-energize 130 & E
- AND - s
- 2) Go to E-0 REACTOR TRIP OR
. SI Step 2.
O DC0273 2VI
P FR-5.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/7/85 (] TITLE. RESPONSE TO NUCLEAR POWER GENERATION /ATWS PAGE 3 0F 9 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED VERIFY Turbine Trip: Manually trip turbine. (CC3/VB3) e Turbine SVs . IF turbine will NOT trip, CLOSED (CC3/VB1) TREN manually run back turbine. IF turbine can NOT be run back, THEN close all MSTFs and bypass
- valves.
CHECK AFW Pumps Running: (VB3)
- a. Both MD AFW pumps - RUNNING a. Manually start MD AFW PPS.
- b. TD AFW PP RUNNING IF EITHER b. Manually open steam supply MD AFW PP NOT RUNNIhG valves.
1 h INITIATE Beration Of RCS:
- a. Initiate SI a. Borate through 8104 Emergency Borate Viv:
- 1) Start Charging Pump (s).
- 1) Verify flow through BIT
- 2) Verify boric acid purrp in low speed or tratsfer the running boric acid purp to low speed. (VB2)
- 3) Open 8104 Emergency Boratevalve.(VB2)
- 4) Manually increase charging to > 95 gpm.
(CC2) IF 8104 Emergency Borate Viv is NOT available THEN Refer to OP XF6 Emergency Boration while continuing in this procedure. _ STEP 4 CONTINUED ON NEXT PAGE - DC0273 3VI l
NUMBER EP FR-5.1 O!ABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 PAGE 4 0F 9 Titts. RESPONSE TO NUCLEAR POWER GENERATION /ATWS llk ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- b. Check PZR pressure-LESS b. Perform the following:
THAN 2335 PSIG (VB2)
- 1) Verify PZR PORVs and stop valves open.
IF NOT, THEN open PZR PORV's and stop valves as necessary until PZR pressure less than 2135 psig.
- 2) Verify containment ventilation isolation on monitor light box B.
IF valves NOT closed. TREN manually or locally close.
- 5. VERIFY FW Isolation - ACTUATED AT TAVG LESS THAN 554*F (VB1)
- a. Feedline FCVs and bypass a. Manually close FCVs and viss - CLOSED bypass or Feedline isolation valves,(VB3)
- 6. CHECK If The Folicwing Trips Have Occurred:
- a. Reactor trip EKRs - OPEN a. Dispatch operator to (VB2) locally open reactor trip BKRS.
- b. Turbine stop valves - b. Dispatch operator to CLOSED locally trip turbine at turbine pedestal.
O l l DC0273 4VI g i
1 l l i DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/7/85 1 () PAGE 5 0F 9 TITLE RESPONSE T0 NUCLEAR POWER GENERATION /ATWS ! 1 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED s
- 7. VERIFY REQUIRED AFW Flow
- a. IF an ATWS is NOT in a. IF an ATWS is in progress progress TREN Ensure total AFW flow THEN e Verify one SG NR greater than 920 gpm level >4% [20%)
- AND -
- OR -
go to Step 8. e Total AFW flow at ------------------------------------ 460 gpm
- 8. VERIFY All Dilution Paths -
ISOLATED
- a. Verify autcmatic anc a. Stop manual and automatic manual dilutior, not in dilution.
r service
! IF
~~
flow continues on FI-111, THEN perform as necessary:
- 1) e Ensure FCV-111A closed.
e Stcp pri wtr pps. e Dispatch personnel to close CVCS-8469, pri wtr supply iso viv (outside blender rm) while continuing in this procedure. P
- b. Refer to Appendix 0 while continuing in this procedure l
0C0273 SVI l
m FUMBER EP FR-S.1 OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 TITLE: RESPONSE TO NUCLEAR POWER GENERATION /ATWS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. CHECK For Reactivity Insertion IF
~"
uncontrolled cooldown NOT in Trom Uncontrolled Cooldown: progress, THEN go to Step 13. a RCS temperature - DECREASING IN AN UNCONTROLLED MANNER (VB2)
- 0R -
e Any S/G pressure - DECREASING IN AN UNCONTROLLEDMANhER(VB3)
- 10. CHECK MSIVs And Their Bypan~~ Manually close MSIVs and bypass Valves - CLOSED (V83) valves.
- 11. 10ENTIFY Faulted SG(s): (VB3)
- a. Check pressures in all SGs. a. If NONE are faulted, go to Step T3.
e Any SG pressure decreasing in an , uncontrolled manner OR - e Any SG completely cepressurized
- 12. ISOLATE Faulted SG(s): (VB3) Manually close any valves which will not isolate.
- a. Ensure main feedwater isolated IF valves can NOT be closed.
TiiEN dispatch operator to locally
- b. Close AFW LCV(s) to any close valves or block valves.
faulted SG(s)
- c. If SG No. 2 is faulted, close FCV.37. If SG No. 3 ,
is faulted, close FCV-38 to isolate to TD AFW pp i
- d. Ens 0re faulted SG(s) 10%
l steam dump valve closed
- e. Ensure blowdown isolated on
! any faulted SG(s) ! DC0273 6VI 1
l NUMBER EP FR-S.1 i DIABLO CANYON POWER PLANT UNIT NO(S) 1 AhD 2 REVISION 0 1 C' DATE 3/7/85 PAGE 7 0F 9 TITLE. RESPONSE TO NUCLEAR POWER GENERATION /ATWS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED s
- 13. CHECK 480V Busses Feeding Rod Re-energize busses.
Drive MG Sets - Energized (VBS) UNIT 1 130 & 13E UNIT 2 23D & 23E 14 VEPIFY Reactor Subcritical: Continue to borate. (CCl) IF boration NOT available, TiiEN allow RCS to heat up. Perform . e Power range channels - LESS actions of other FR procedures T THAN 5:L in effect which do not cool down or otherwise add positive o Intermediate range channels reactivity to the core. Return
- NEGATIVE STARTUP RATE to Step 4.
FOTE: Boration should continue to obtain adequate shutdown roargin curing subsequent actions.
- 15. Go To Applicable Plant Procedure
- a. Refer to OP AP.6, Emergency Boration, to Stop Boration
- b. Go to E-0 Reactor Trip or Safety Injection, if SI was actuated
- END .
0C0273 7v!
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 N[V R ON DATE 3/7/85 PAGE 8 0F 9 TITLE: RESPONSE TO NUCLEAR POWER GENERATION /ATWS g APPENDIX D NOTE: If letdown temperature decreases the mixed bed DI's will remove boric acid from the letdown stream.
- 1. Check letdown temperature:
If less than normal manually operate TCV-130 or locally throttle CCW to the letdown Hx to maintain letdown temperatures in the normal range.
- 2. Dispatch operators to check and isolate any dilution paths to the RCS.
Ensure primary water supply valves to the demineralizers are closed.
- a. Mixed bed No. 1, CVCS-8539
- b. Mixed bed No. 2, CVCS-8538
- c. Cation Demin No. 1, CVCS-8519 h
- d. Deborating Demin No. 1. CVCS-8500A.
- e. Deborating Demin No. 2, CVCS-8500B.
Ensure primary water supply valves to boric acid transfer pumps are closec.
- a. EA pump No. 1, CVCS-8464A
- b. BA pump No. 2, CVCS-84648
- 3. Return primary water pumps to service as needed.
s O DC0273 8VI
NUMBER EP FR-S.I DIAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0
- DATE 3/7/85 PAGE 9 0F 9 TITLE RESPONSE TO NUCLEAR POWER GENERATION /ATWS APPENDIX Z s
EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When the emergency procedure has been activated and upon direction from the Shift Foreman proceed as follows:
- a. Designate this event an Alert. Notify plant staff and response organizations required for this classification by Emergency Procedure G-2 " Establishment of On-Site Organization" and Emergency Procedure G-3 " Notification of Off-Site Organization" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation."
- b. Designate this event a Site Area Emergency if safety injection was initiated before rods were Inserted into the core but no core damage is evident (no abnormal increase in RCS coolant activity and no abnormal increase in gross O failed fuel indication). Notify plant staff and response b organizaticns required by EP G-2 and EP G-3 in accordance with EP G-1.
- c. Designate this event a General Errergency if one of the following conditions exist:
- 1) Core damage is evident by:
a) Reactor coolant activity greater than 300 uCi/cc equivalent I-131, ,o_r b) Radiation levels indicate greater than 100s gap release (Refer to Appendix H of EP OP-1).
- 2) Complete loss of safe shutdown system simultaneous with i rods not inserted in the core.
- 3) Loss of CVCS capability to increase boric acid ;
concentration in the RCS simultaneous with rods not , inserted into the core. '
- 2. Notify plant staff and response organizations required by EP G-2 and EP G-3 in accordance with EP G-1.
p ! O l DC0273 9VI l
NUMBER EP FR-S.2
%GW3 e Pacific Gas and Electric Company REVISION O DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 3/7/85 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 6 i l
~
EMERGENCY PROCEDURE TITLE RESPONSE TO LOSS OF CORE SHUTDOWN IMPORTANT APPROVED W-3% TO PLANT MANAGEP DATE SAFETY SCOPE This procedure provides actions to restore the core to an adequately shutdown condition. This procedure and changes thereto requires PSRC review. SYMPTOMS OR ENTRY CONDITIONS F-0.1, SUSCRITICALITY Critical Safety Function Status Tree, on either O YELLOW cor,dition. l O l DC0417 111I
NUMBER EP FR-S.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 PAGE 2 0F 6 m LE. RESPONSE TO LOSS OF CORE SHUTDOWN g ACTION /EXPEutD RESPONSE RESPONSE NOT OBTAINED
- 1. CHECK Intermediate Range Flux:
- a. Flux constant or decreasing a. IF flux is decreasing, less than 10 10 amps (CC1/NIS) TREN continue to monitor flux k'RER less than 10 10 amps TREN do Steps Ib, c.
Check for loss of compensating voltage: o PK 03-06 in alann-NIS DETECTOR VOLTAGE LOSS e Bistable Light - ON LOSS OF COMPENSATING VOLTAGE (NIS Cab I&II IR35/36 Drawer) IF compensating voltage is lost, THEN manually energize SR detectors and do step 1c. (CC1) h IF NOT undercompensated, TREN Emergency Borate per OP AP-6 (VS2) and go to step 3. OBSERVE NOTE PRIOR TO STEP 3.
- b. Verify source range detectors b. Marually energize SR energized (CC1) detectors.(CC1)
- c. Transfer one pen of the N-45 Recorder to highest SR and IR channel (CC1) s I
S l l DC0417 2III
1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) Nf0N DATE 3/7/85 PAGE 3 0F 6 TITLE. RESPONSE TO LOSS OF CORE SHUTDOWN ACTION / EXPECTED ESPONSE ESP 0t8E NOT OBTAINED
- 2. CHECK Source Range Channels Emergency Borate (per OP AP-6) until source range
- a. e SR sustained SUR Zero or startup rate is zero or Negative negative and go to step 3 (VB2). OBSERVE NOTE PRIOR TO
- AND - STEP 3.
e Flux decreasing
- OR -
Flux constant at a nonnal shutdown value
- b. Return to procedure and step in effect O
O l DC0417 3III
- l
NUMBER EP FR-S.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVIS10N 0 DATE 3/7/85 PAGE 4 0F 6 m LE. RESPONSE TO LOSS OF CORE SHUTDOWN ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Boration should continue to obtain adequate shutdown margin during subsequent actions.
- 3. VERIFY All Dilution Paths -
ISOLATED:
- a. Verify no flow on FI-111 (CC2) a. Manually stop dilution (CC2/VB2).
IF Flow continues on FI-111, TiiEN Perform the following:
- 1) Stop Pri Wtr Pumps.
- 2) Locally close CVCS-8469 Pri Wtr Inlet to blender (outside blender room).
- 3) Refer to OVID:
UNIT 1 106708 Sh. 5 UNIT 2 107708 Sh. 5 and isolate source of dilution,
- 4) WHEN dilution source isolated THEN Return Pri Wtr line-up to normal and return to procedure and step in effect.
- b. Check letdown temperature normal b. E letdown temperature is (VB2) less than normal, THEN manually control TCV-130 or locally throttle CCW to NRHX to normalize letdown temperature.
- c. Stop both primary water pumps (VB3) ,
THIS STEP CONTINUED ON NEXT PAGE O DC0417 4III i
- 1
NUMBER EP FR-S.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISI0h 0 DATE 3/7/85 PAGE 5 0F 6 TITLE. RESPONSE TO LOSS OF CORE SHUTDOWN j l l ACTION / EXPECTED ESPONSE ESPONSE NOT OBTAINED
- d. Dispatch operator (s) to check and isolate any dilution paths Ensure primary water supply valves to the demineralizers are
~
closed:
- 1) Mixed bed No. 1, CVCS-8539
- 2) Mixed bed No. 2, CVCS-8538
- 3) Cation demin No. 1, CVCS-8519
- 4) Deborating demin No. 1, CVCS-8500A
- 5) Deborating demin No. 2, CVCS-85008 Ensure primary water supply valves to the boric acic transfer pumps are closed
- 1) BA Pump No. 1. CVCS-8464A
- 2) BA Pump No. Z, CVCS-8464B
- e. Start pri wtr pumps as needed
- 4. RETURN To Procedure and Step in Effect:
(Refer to OP AP-6 EMERGENCY BORATION to stop boration)
- END -
l G l DC0417 SIII
, ,w
OtA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 f0N CATE 3/7/85 PAGE 6 0F 6 TITLE: RESPONSE TO LOSS OF CORE SHUTDOWN f APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. Designate this event a Notification of Unusual Event if no other emergency condition exists. Notify plant staff and response organizations required for this classification by implementing Emergency Procedure G-2 Establishment of the On-Site Emergency Organization" and Emergency Procedure G-3
" Notification of Off-Site Organization" in accordance with Emergency Procedure G-1 " Accident Classification and Emergency Plan Activation".
O l l O DC0417 6III
NUMBER EP FR-C.1
}SW3 Pacific Gas and Electric Company REVISION 0 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 3/7/85 DIABLO CANYON POWER PLANT UNIT NO(S)
PAGE 1 0F 16 1 AND 2 EMERGENCY PROCEDURE - l TITLE RESPONSE TO INADEQUATE CORE COOLING IMPORTANT
- APPROVED 77 6 T TO PLANT MANAGER g) DATE SAFETY SCOPE This procedure provides actions to restore core cooling. This procedure and changes thereto requires PSRC review.
SYMPTOFS OR ENTRY CONDITIONS F-0.2, CORE COOLING Critical Safety Function Status Tree, on either RED condition. O DC0296 IIV
,.,___.,_,_.<._.m._ _ . - _ - - - _ _ , , , . . . , ,_-..,,_____-_,_,.-____,._-_,--._..m. . _ . _ . , _ - - . _ ..r__--. ,, _ , _ _ _ .--_ _ -
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/7/85 PAGE 2 0F 16 TITLE. RESPONSE TO INADEQUATE CORE COOLING h ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: e If RWST level decrease to 33%, the SI system should be aligned for cold leg recirculation using E-1.3, TRANSFER TO COLD RECIRCULATION. e RHR pumps should not be run on recirculation longer than 30 minutes without CCW to the RHR heat exchangers.
- 1. CHECK ECCS Valve Alignment - PROPER Manually or locally align valves EMERGENCY ALIGNMENT as necessary.
c Activate postage stamp monitor lights by turning the Monitor Test Light Switch to ON (VB1) Use postage stamps to verify ECCS valve alignment (VB1)
-0R-e Use Control Board mimic bus to verify ECCS valve alignment
- 2. VERIFY ECCS Flow In All Trains:
- a. BIT flow; FI-917 - check for a. Perform as NECESSARY:
flow (VB2) e Verify ECCS valve alignment on monitor light box A.C. e Manually or locally start pumps, a Verify manual valve alignment.(refer to OPK-10G1) e Establish alternate injection (PDPP, BIT , bypass, normal charging), THIS STEP CONTINUED ON NEXT PAGE O DC0296 2IV
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/7/85 N PAGE 3 0F 16 RESPONSE TO INADEQUATE CORE COOLING ACTION / EXPECTED ESPONSE ESPONSE NOT OBTAINED
. RCS WR pressure - LESS THAN 1650 b. Go to Step 3 PSIG(VB2)
- c. SI pump flow (FI-918/922, VB2) - c. Perfom as necessary:
CHECK FOR FLOW e Verify ECCS valve alignment on monitor light box A.C. e Manually or locally start pps. e Verify manual valve alignment.(refer to OPK-10G1)
- d. RCS WR pressure - LESS THAN 300 d. Go to Step 3.
PSIG (VE2)
- e. RHR pump plow (FI-970/971,VB1) - e. Perform as necessary:
CHECK FOR FLOW e Verify ECCS valve alignment on monitor light box A.C. e Manually or locally start PPs. e Verify manual valve alignment.(refer to OP K-10G1) b
\. s DC0296 31V
NUMBER EP FR.;.1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 PAGE 4 0F 16 TITLE. ACTION / EXPECTED RE5PONSE RE5PONSENOTOBTAINED CAUTION: DO NOT initiate LTD or RCP seal return to the VCT if core damage is suspected or is imminent.
- 3. CHECK RCP Support Conditions - Try to establish support AVAILABLE conditions for running an RCP.
Refer to Appendix B. Continue e Refer to Appendix 8 with procedure while doing this step. e Continue with this instruction 4 CHECK SI Accumulator Isolation Valve Status:
- a. Restore power to accum discharge iso vivs UNIT 1
- 1) 52-lF-46 for 8808A
- 2) 52-1G-07 for 880f58
- 3) 52-1H-14 for 8808C
- 4) 52-1G-05 for 88080 UNIT 2
- 1) 52-2F-46 for 8808A
- 2) 52-2G-07 for 8608B
- 3) 52-2H-14 for 8808C
- 4) 52-2G-US for 88080
- b. Isolation valves - OPEN (VB1) b. Open isolation valves unless closed af ter accumulator discharge.
- 5. CHECK Core Exit TCs - LESS THAN Go to Step 8.
1200*F (PAM 3/4) O DC0296 4IV l -
DIABLO' CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/7/85 5 0F 16 p) ( RESPONSE TO INADEQUATE CORE COOLING PAGE ACTICN/EXPEutD RESPONSE RESPONSE tK)T OBTAINED
- 6. CHECK RVLIS Level Indication (PAM 3/4):
- a. Full Range >39% a. IF increasing, TiiEN return to Step 1.
IF NOT, TIIEN: e Verify ECCS valve alignment per X 10G1
-AND-e Go to Step 7.
- b. Return to procedure and step in effect
- 7. CHECK Core Exit (PAM 3/4)
- a. Temperature - LESS THAN 700*F a. IF decreasing, TiiEN return to Step 1.
E NOT, THEN go to Step 8.
- b. Return to procedure and step in effect DC0296 SIV
b DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 3/7/85 PAGE 6 0F 16 RESPONSE TO INADEQUATE CORE COOLING ACTION /EXftutD RESPONSE RESPONSE NOT OBTAINED NOTE: This procedure should be continued while obtaining a hydrogen sample in Step 8.
- 8. CHECK Containment Hydrogen Concentration (PAM 1):
- a. Check H2 analyzer IN SERVICE a. Contact Chem / Rad to place in service.
- b. Observe containment hydrogen monitor (PAM 1)
- c. Hydrogen concentration - LESS c. Consult plant engineering THAN a.0*, IN DRY AIR staff for additional recovery actions. Go to Step 9.
- d. Hydrogen concentration - LESS d. Turn on hydrogen recombiner THAN 0.5% IN DRY AIR system. Refer to OP H-9.
s l S DC0296 61V l
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/7/85 O v RESPONSE TO INADEQUATE CORE COOLING PAGE 7 0F 16 ACTICN EXPECTED RESPONSE REsPONSENOTOBTAINED s CAUTION: o Alternate water sources for AFW pumps will be necessary if CST level decreases to less than 10%. Refer to E-2.1, ALTERNATE AUXILIARY FEEDWATER SUPPLIES. e A faulted or ruptured SG should not be used in subsequent steps unless no intact SG is available.
- 9. CHECK Intact SG Levels (VB3):
- a. NR Level - GREATER THAN 4%[20%] a. Increase total feed flow to restore NR level greater than4%[201].
IF total feed flow less than 460 GPM, THEN go to Step 18. OBSERVE y NOTE PRIOR TO STEP 18. i
- b. Control feed flow te maintain NR level 20% to 33%
O ! DC0296 71V
N DIABLO CANYON POWER P;,. ANT UNIT NO(S) 1 AND 2 RV ON DATE 3/7/85 RESPONSE TO INADEQUATE CORE COOLING g ACTION / EXPECTED RESPONSE REsPC14SE NOT OBTAINED
- 10. CHECK RCS Vent Paths:
- a. Power to PZR PORV stop valves - a. Restore power to stop valves AVAILABLE (VB2)
UNIT 1 e 52-1F-40 for 8000A e 52-1G-46 for 80008 e 52-1H-33 for 8000C UNIT 2 e 52-2F-40 for 8000A e 52-2G-46 for 80008 e 52-2H-33 for 8000C
- b. PZR FORVs - CLOSED (VB2) b. Manually close PZR PORVs OR associated stop valves:
e 8000A for PCV-474 e 80008 for PCV-455C e 8000C for PCV-456 - - - -
- c. Stop valves - AT LEAST ONE OPEN c. Open stop valve unless it (VB2) was closed to isolate an open PZR PORV.
- d. Verity RCS head vent 8708 A, d. Close RCS head vent path.
B, C and 0 - CLOSE0 (PAM 1) s O DC0296 61V
NUMBER EP FR-C.1 l DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 l l DATE 3/7/85 3 PAGE 9 0F 16 i () TITLE RESPONSE TO INADEQUATE CORE COOLING I ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOT$: Partial uncovering SG tubes is acceptable in the following steps. >
- 11. DEPRESSURIZE ALL Intact SG(s) To j 160 PSIG:
- a. Dump steam to the main condenser a. Dump steam at maximum rate at maximum rate (CC3) using SG 10% steam dump (VB3).
- b. Check SG pressures - LESS THAN b. IF SG pressure decreasing, 160 PSIG (VB3) TREN return to Step 9.
E SG pressure NOT decreasing, THEN go to Step 18. OBSERVE NOTE PRIOR TO STEP 18.
- c. Check RCS Hot Leg Temperatures c. -
IF RCS Hot Leg (VE2) - AT LEAST TWO LESS THAN temperatures decreasing 400*F(VB2) THEN return to Step 9. E RCS temperatures NOT decreasing, THEh go to Step 18. OBSERVE NOTE PRIOR TO STEP 18.
- d. Stop SG depressurization (VB3/CC3)
O DC0296 91V
OlABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/7/85 PAGE 10 Or 16 RESPONSE TO INADEQUATE CORE COOLING l h TITLE. ACTION / EXPECTED RESPONSE R5SPG6ENOTOBTAINED
- 12. CHECK If SI Accumulators Should Be Isolated:
- a. At least two RCS hot leg a. IF hot leg temperatures temperatures - LESS THAN 400*F greater than 400*F, (VB2) THEN go to Step 18. OBSERVE NOTE PRIOR TO STEP 18.
- b. Close all accum disch iso b. IF any accum iso viv does vivs(VBI): NOT close, THEN perform the following:
8808A, B, C, D 1) Close FCV 8880, accum N2 fill header iso viv.
- 2) Open 8875 A, B, C, D accum N2 supply vent to affected accum. &
- 3) Open siCV-943 accum W N2 supply vent, UNTIL accumulator is depressurized and l
continue in this procedure. I ________________ f j 13. STOP ALL RCPs (VB2)
- 14. DEPRESSURIZE Ali Intact SGs To Atmospheric Pressure:
- a. Dump steam to the main condenser a. Dump steam at maximum rate at maximum rate (CC3) using SG 10% steam dumps (VB3) 1 l
l % I DC0296 10Iv
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 V ON DATE 3/7/85 PAGE 11 0F 16 RESPONSE TO INADEQUATE CORE COOLING TITLE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAlte
- 15. ' VERIFY ECCS Flow: Continue efforts to establish ECCS flow.
e BIT flow, FI 917 - CHECK FOR FLOW (VB2) - IF core exit TCs LESS THAN 1200 F (PAMS 3/4),
- OR - THEN return to Step 14.
e SI pump flow, FI-918/922 - IF core exit TCs greater than CHECK FOR FLOW (RCS WR Pressure 1200 F (PAMS 3/4), less than 1650 psig, VB2) THEN go to Step 18. OBSERVE NOTE PRIOR TO STEP 18.
- OR _
e RHR pump flow, FI-970/971 - CHECK FOR FLOW (RCS WR Pressure less than 300 psig VEI)
- 16. CHECK Core Cooling:
- 6. Core exit TCs - LESS THAN 1200*F a. -
IF a core exit TCs greater (PAM 3/4) than 1200*F, THEN go to Step 18. OBSERVE NOTE PRIOR TO STEP 18.
- b. At least two RCS Hot Leg b. -
IF hot leg temperatures Temperatures - LESS THAN 350*F greater than 350 F, (VS2) THEN return to Step 14
- c. kVLIS FULL RANGE - GREATER THAN c. IF RVLIS LESS THAN 63%,
63% (PAMS 3/4) TiiEN return to Step 14. DC0296 111V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 S ON DATE 3/7/85 PAGE 12 0F 16 TITLE ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 17. Go To E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 12, INITIATE Evaluation of Plant Status NOTE: Normal conditions are desired but not required for starting the RCPs.
- 18. CHECX Core Exits TCs Start RCP(S) one at a time until
- LESS THAN 1200*F (PAMS 3/4) core exit TCs are less than 1200*F (use loop 2 RCP last).
IF core exit TCs GREATER THAN 1200*F and all available RCPs running, THEN open all PZR FORVs and block valves. IF
~-
core exit TCs GREATER THAN 1200 F and all PZR PORVs and block valves are open, THEN open the reactor vessel g head vents.
- 19. Try to Locally DEPRESSURIZE All Use Faulted or Ruptured SG.
Intact SGs To Atmospheric Pressure IF NECES$ARY: e Locally Open all intact SG(s) 10% steam dumps (VB3) e Open any other vent path from main steam header s O DC0296 121V
NUMBER EP FR-C.1 otAstO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 p V RESPONSE TO INADEQUATE CORE COOLING PAGE 13 0F 16
. ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED s
- 20. CHECK If SI Accumulators Should Be Isolated:
- a. RHR pump flow (FI-970/FI-971) - a. -
IF RHR flow is NOT AT LEAST INTERMITTENT FLOW (VB1) indicated at any time, THEN return to Step 18. - -
- b. Close all accum iso b. -
IF any accum iso viv does vivs (VB]) NOT close, THEN perform the following: 8808A 1) Close FCV 8880 88088 accum N2 fill 8808C header iso viv. 88080
- 2) Open 8875 A, 6, C, D accum N 2 supply vent to aTfected accum.
" 3)OpenHCV943,accum N2 supply vent.
UNTIL accumulator is depressurized and continue in this procedure. - - - - - -
- 21. Check If RCPs Should Be Stopped (VEE);
- a. At least two RCS Hot Leg a. -
IF hot leg terrperatures temperatures - LESS THAN 350*F GREATER THAN 350*F, THEN go to Step 22.
- b. Stop all RCPs 1
DC0296 131V I
)
L
NUMBER EP FR-C.1 0.ABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 PAGE 14 0F 16 RESPONSE TO INADEQUATE CORE COOLING TITLE. ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. VERIFY ECCS Flow: IF ECCS flow NOT verified, TiiEN continue eTforts to e BIT flow FI-917, establish ECCS Flow
- CHECK FOR FLOW (V82)
AND
- OR -
return to Step 18. e SI pump flow FI-918/922 - CHECK FOR FLOW (VBI)
- OR -
e RHR pump flow FI-970/971 - CHECK FOR FLOW (VB1)
- 23. CHECK Ccre Cooling Established IF
~~
core ccoling NOT (PAMS 3/4) established, THEN return to Step 18. e RVLIS FULL RANGE - GREATER THAN g 63% w e At least two RCS hot leg temperatures - LESS THAN 350 F
- 24. Go To E-1, LOSS OF REACTOR OR SECONDARY COOLANT, STEP 12, INITIATE Evaluation of Plant Status
- END -
l l l l l l l > DC0256 141V
NUMBER EP FR-C.1 1 AND 2 OlABLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 3/7/85 O d RESPONSE TO INADEQUATE CORE COOLING PAGE 15 0F 16 TITLE. APPENDIX B s Restart of Reactor Coola,it Pump
- 1. Start oil lift pump, run for 2 minutes.
- 2. Verify CCW available to thermal barrier, oil cooler, seal water HX.
- 3. Verify seal dp greater than 215 psid, depressurize VCT as neces sa ry.
- 4. Verify seal injection flow 8 (6 to 12) gpm.
- 5. Verify seal leak eff flow within limits shown on graph.
- 6. Ensure closed PCV-455A and B, Normal PZR spray vivs (AUTO cptieral).
ALL0 wag ([ pCP #1 $EAL LEAK RATES k 5 i 4 i , 9 SHUTDOWN RCP WITHIN ONE HALF HOUR c i i !
' i t 3 l l [
I "2 ! l SAFE OPERAT,1NG R[GION
! I I !
5 l ' REGION l REGION l E D DO NOT STAR RCP
/
0 200 400 600 800 1000 -1200 1400 1600 1800 2000 2200 2400 RCP 81 $F4L DIFFERENTIAL PRES $URE PSID REGION 1 NO PHASE A SIGNAL, dp=RCS,,,gg VCforess PHA5[.A PRtS[NT. do=RCS,,,gg 150psig REGION 2 US[ INSTALLED do GAUGl$ i DC0296 151V
NUMBER EP FR-Col CIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 PAGE 16 0F 16 RESPONSE TO INADEQUATE CORE COOLING TITLE APPENDIX Z EMERGENCY PROCEDURE NOTIFICATION INSTRUCTIONS
- 1. When this emergency procedure has been activated and upon direction from the Shift Foreman, proceed as follows:
- a. In the event that inadequate core cooling is verified, reclassify this event as a General Emergency,
- b. Notify plant staff and response organizations required for this classification by implementing Emergency Procedure G-2
" Establishment of the On-Site Emergency Organization" and Emergency Procedure G-3 " Notification of Off-Site Organization" in accordance with Emergency Procedure G-1
" Accident Classification and Emergency Plan Activation".
O l % O DC0296 16IV
l
-m w u i s- NUMBER EP FR-C.2 y Pacific Gas and Electric Company REv:SION 0 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 3/7/85 I
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 12
~
EMERGENCY PROCEDURE
.6 TITLE RESPONSE TO DEGRADED CORE COOLING W IMPORTANT APPROVED 7. 6 M1 3 645 To SAFET(
PLANT MANAGER M DATE SCOPE This procedure provides actions to restore adequate core cooling. This procedure and changes thereto requires PSRC review. SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from F-0.2, CORE COOLING CRITICAL SAFETY FUNCTION STATUS TREE, on either ORANGE ccndition. O O
- DC0296 IV
NUMBER EP FR.C.2 OlABLO CANYON POWE] PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 PAGE 2 0F 12 mtg RESPV SE TO DEGRADED CORE COOLING g ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUT10fh e If RWST level decreases to less than 33%, the ECCS system should be aligned for cold leg recirculation using E-1,3, TRANSFER TO COLD LEG RECIRCULATION. e RHR pumps should not be run longer than 30 minutes without CCW to RHR heat exchangers.
- 1. VERIFY ECCS Valve Alignment . PROPER Manually or locally align valves EMERGENCY ALIGSMENT as necessary.
e Activate postage stamp monitor lights by turning the Monitor Test Light Switch to ON (VBI) e Use postage stamps to verify ECCS valve aligreent (V81)
- CR - g e Use control board mimic bus to verify ECCS valve alignment OC0296 2V
1 l l DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R f DN DATE 3/7/85 J PAGE 3 0F 12 RESPONSE TO DEGRADED CORE COOLING l Tirts. ACTION / EXPECTED RESPONSE RESPONIE NOT OBTAINED i
- 2. VERIFY ECCS Flow In All Trains:
- a. BIT Flow, FI-917 - CHECK FOR FLOW a. Perform as necessary:
(VB2) o Verify ECCS valve alignment on monitor light box A.C. e Manually or locally start pumps, e verify manual valve alignment (refer to GP K-10 GI). e Establish alternate injection (PD pp, BIT bypass, normal charging).
- b. RCS WR pressure - LESS THAN 1650 b. Go to Step 3.
. 3) PSIG (VB2)
- c. SI purrp flow, FI-918/922 - c. Perform as necessary:
CHECK FOR FLOW (VB-2) e Verify ECCS valve alignment on acnitor light bcx A.C. e Manually or locally start PPs. e Verify manual valve alignment (refer to OP K.10G1).
- d. RCS WR pr(isure - LESS THAN 300 d. Go to Step 3.
PSIG(VB2) THIS STEP CONTINUED ON NEXT PAGE O I V l l DC0296 3V
NUMBER EP FR-;.2 OtABLo CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/65 PAGE 4 0F 12 TITLE- F.ESPONSE TO DEGRADED CORE COOLING llll ACTION / EXPECTED ESPONSE RESPONSE tot OBTAINED
- e. RHR pump flow, FI-970/971 - e. Perform as necessary:
CHECK FOR FLOW (VB1) e verify ECCS valve alignment on monitor light box A.C. e Manually or locally start pps. e Verify manual valve alignment (refer to OP K.10 GI).
- 3. CHECK RCS Vent Paths:
- a. Power to PZR PORY stop valves - a. Restore power to stop AVAILABLE (V22) valvec:
UNIT 1 UNIT 2 VALVE 52-2F-40 8000A o 52-lF.40 e 52-lG-46 e 52-1H-33 52 2G-46 52-2H-33 80008 8000C g
- b. PZR PORVs . CLOSED (VB2) b. Manually close PZR PORVs
-OR-associated stop valves e 8000A f or PCV-474 e 8000B for PCV.455C e 8000C for PCV-456
- c. Stop valves . AT LEAST ONE OPEN c. Open stop valees unless (VB2) closed to isolate an open PZR FORV.
- d. Verify RCS head vent . CLOSED d. Close RCS head vent path.'
(PAM 1) e O DC0296 4V
DIABLO CANYON POWER Pt. ANT UNii NO(S) 1 AND 2 ON 0 DATE 3/7/85 TiTts. RESPONSE TO DEGRADED CORE COOLING ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED s CAlITION: 00 NOT initiate letdown or RCP seal return to VCT if core damage is suspected or iminent. NOTE: Normal conditions for running RCPs are desired, but RCPs should not be tripped if normal conditions cannot be established or maintained.
- 4. CHECK RCP Status:
- a. At least one RCP - RUNNING (VB2) a. Go to Step 7.
- b. Verify support conditions for RCP b. Try to establish support operation are being maintained. conditions for running an Refer to Appendix B and continue RCP. Refer to Appendix B in this procedure and continue in this
- 5. CHECK RVLIS Dynamic Head Indication (PAFS 3/4):
- a. IF increasing,
- a. Indicaticr. - GREATER ThAN: TREN return to Step 1.
RCPs IF NOT, ON RANGE LEVEL TiiEN go to Step 6. 1 Dyn >22% 2 Dyn >26% 3 Oyn >35% 4 Dyn >46%
- b. Return to procedure and step in effect DC0296 SV
PUMBER EP FR-C.2 D'ABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 PAGE 6 0F 12 TITLE. RESPONSE TO DEGRADED CORE COOLING ACTION / EXPECTED RCSPONSE RESPONSE NOT OBTAINED
- 6. CHECK If One RCP Should Be Stopped:
- a. All RCPs - RUNNING a. Go to Step 8.
- b. Stop LP2 RCP and nanually close PCV.4558
- c. Go to Step 8
- 7. CHECK Core Cooling (PAMS 3/4):
- a. RVLIS Full Range - GREATER THAN a. IF increasing, 39'. TREN return to Step 1.
IF NOT, TREN go to Step 8.
- b. Core exit TCs - LESS THAh 700 F b. IF decreasing, TiiEN return to Step 1.
IF NOT, TiiEN go to Step 8.
- c. Return to procedure and step in effect
- 8. CHECK SI Accumulator Isolation Valve Status (VB1):
- a. Restore power td accum discharge iso valves:
UNIT 1 UNIT 2 VALVE 52-1F-46 52-2F-46 8606A 52-1G-07 52-2G-07 8808B 52-1H-14 52-2H-14 8808C ' 52-1G-05 52-2G-05 88080
- b. Isolation valves - OPEN b. Open isolation valves unless closed after accum discharge.
l l 9 DC0296 6V
DIABLO CANYON POWER PLdNT UNIT NO(S) 1 AND 2 [0N DATE 3/7/85 q PAGE 7 0F 12 'g TITLE RESPONSE TO DEGRADED CORE COOLING ACTION / EXPECTED RESP 0fiSE RESPONSE NOT OBTAINED CAUTION: e If CST level decreases to less than 10%, refer to E-2.1, ALTERNATE XTW SUPPLIES. e A faulted or ruptured SG should not be used in subsequent steps unless no intact SG is available.
- 9. CHECKIntactSGLevels(VB3):
- a. NR Level - GREATER THAN 4%[201) a. Increase total AFW flow to restore NR level in at least one SG to greater than 40[20%).
- b. Control AFW to mainteir NR level p between 20% and 33%
V
- 10. DEPRESSURIZE All Intact SGs To 160 PSIG
- a. Maintain cooldown rate in RCS cold legs - LESS ThAN 100'F/HR IN ANY ONE HOUR PERIOD
- b. Dump steam to the main condenser, b. Dump steam using SG 10%
if available (CC3) Steam Dumps. Manually or locally durrp steam from any vent path. (VB3)
- c. Check SG pressures - LESS THAN c. Return to step 9. OBSERVE 160 PSIG (VB3) CAUTION PRIOR TO STEP 9.
- d. STOP SG depressurization O
I DC0296 7V i
NUMBER EP FR-C.2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 3/7/85 PAGE 8 0F 12 Tirts. RESPONSE TO DEGRADED CORE COOLING ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION: RHR pumps should not be run on recirculation longer than 30 minutes without CCW to the RHR Heat Exchanger.
- 11. CHECK RHR Pumps - RUNNING (VB1) Start RHR pumps as necessary.
- 12. CHECK If SI Accumulators should Be Isolated:
- a. At least two RCS Hot Leg a. Go to Step 14.
temperatures - LESS THAN 400 F (VBZ)
- b. Close all Si accun disch iso vlvs b. IF any accum iso viv does 8808A, B, C, D (VB1) NOT close, THEN perform the following:
- 1) Close FCV 8880, accum N fill isolati$nvalve.
(VB1)
- 2) Open 8875A, B, C, or D accum vent udN fill 7
viv, to affected accum. (VB1)
- 3) Open HCV-943 accum N2 vent.(VB1)
UNTIL accum is depressurized and continue in this procedure. O DC0296 8V ; i}}