ML20206N523
| ML20206N523 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/16/1998 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20206N476 | List: |
| References | |
| S023-12-1, S23-12-1, NUDOCS 9905170254 | |
| Download: ML20206N523 (26) | |
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NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 1 0F 25 COMPLETE REVISIO1 l EFFECTIVE DATE P" 1 A mno_,
t l
STANDARD POST TRIP ACTIONS TABLE OF CONTENTS I
SECTION PAGE PURPOSE 2 ENTRY CONDITIONS 2 EXIT CONDITIONS 2 OPERATOR ACTIONS 3 ATTACHMENTS 1 Worksheet 17 2 Recovery Diagnostic 19 3 Diesel Generator failure Followup Actions 20 4 Administrative Actions 25 l
RECENEDCDM MAR 161998 SITEFil.E00PY l
S1-15.W61 QA PROGRAM AFFECTING 9905170254 990513 PDR P
ADOCK 05000361 PDR
, NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 2 0F 25 STANDARD POST TRIP ACTIONS PURPOSE 1 To provide entry into the Emergency Operating Instruction System for any event that actuates or requires a Reactor trip.
The actions specified: j o Verify actuation of automatic systems that should occur.
o Include other appropriate post trip actions that set the plant up to respond to the event.
ENTRY CONDITIONS Any of the following symptoms of a Reactor trip exist:
1 Any valid Reactor Trip annunciator initiated.
2 Any parameter requiring a Reactor Trip by exceeding limits.
3 Rapid reduction in Reactor power.
4 All CEAs fully inserted.
EXIT CONDITIONS The following conditions met:
1 Steps 2 through 12 - completed.
AND 2 Steps 13 through 17 - initiated.
AND 3 Steps 3 through 11 expected responses - met or recovered.
OR An alternate procedure has been designated by the SRO Operations Supervisor.
~
NUCLEAR ORGAN 8ZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 3 0F 25 l STANDARD POST TRIP ACTIONS l 1
OPERATOR ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 ENSURE innediate actions (steps 2 through 12) completed:
- a. TREND at least two indications for each criterion until satisfied, or action is taken,
- b. VERIFY non-1E indications by using IE where available, ,
2 INITIATE Attachment 1. WORKSHEET:
- a. RECORD time of Reactor trip and other significant events.
1 b.
ANNOUNCE Reactor trip via PA System.
- c. EVALUATE Safety function i status. I 3 VERIFY Reactivity Control criteria satisfied:
- a. VERIFY: a. 1) TRIP the Reactor.
- 1) All CEAs - fully inserted 2) DE-ENERGIZE 480V load centers B15 !
and B16.
- 3) IF two or more CEAs still NOT
- 2) Only one CEA - Not fully fully inserted, I inserted.
THEN a) INITIATE Emergency Boration.
b) Record time of Emergency baration initiation on Attachment 1, WORKSHEET.
c) OPEN all TCBs locally.
d) OPEN all M/G set input and output breakers.
. NUCLEAR ORGANIZATION EMERGENCV OPERATING INSTRUCTION 5023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 4 0F 25 STANDARD POST TRIP ACTIONS OPERATOR ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 VERIFY Reactivity Control criteria satisfied: (Continued)
- b. VERIFY Reactor power o a INITIATE Emergency Boration.
- lowering.
- Record time of Emergency Boration
- c. VERIFY startup rate - negative. initiation on Attachment 1, WORKSHEET.
4 VERIFY Vital Auxiliaries functioning properly: {
- a. VERIFY Main Turbine tripped: a. 1) TRIP Main Turbine.
- 1) HP and LP Stop and Governor 2) IF MWe output - NOT lowering, Valves - closed THEN close the MSIVs.
- 2) MWe output - lowering.
- b. VERIFY Unit Output Breakers b. 1) OPEN Unit Output' Breakers.
- open.
- 2) IF Unit Output Breaker (s)
- NOT open, THEN ENSURE closed Unit Output Breaker (s) isolated by:
a) LBFBU OR b) Manual Operator Action.
- c. VERIFY Main Turbine speed c. CLOSE the MSIVs.
- lowering.
- d. VERIFY both IE 4 kV Buses - d. INITIATE Attachment 3, DIESEL l energized. GENERATOR FAILURE FOLLOWUP ACTIONS, for de-energized bus,
- e. VERIFY 6.9 kV and Non-1E 4 kV e. TRANSFER 6.9 kV and Non-1E 4 kV Buses Buses - transferred to Reserve to available Reserve Auxiliary XFMRs.
Auxiliary XFMRs.
- f. VERIFY all 1E 125 VDC f. TRANSFER Vital 120 VAC Buses to Instrument Buses - energized, available alternate power supplies.
NUrtr5R ORGANZZATION EMERGENCY OPERAT!NG INSTRUCTION S023-12-1 U; I~S ' AND 3 REVISION 15 PAGE 5 0F 25 STANDARD POST TRIP ACTIONS OPERATOR ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 YERIFY RCS Inventory Control criteria - satisfied:
- a. VERIFY PZR level a. ENSURE PZR Level Control System
- operating in AUTO or MANUAL to
- between 10% and 70% restore PZR level.
AND
- trending to between 30%
and 60%.
- b. VERIFY Core Exit Saturation Margin - greater than 20*F: )
j QSPDS page 611 CFMS page 311.
6 VERIFY RCS Pressure Control I criteria satisfied:
- a. VERIFY PZR pressure (WR and a. 1) ENSURE PZR Pressure Control NR): System - operating in AUTO or MANUAL to restore PZR pressure.
- 1) - between 1740 PSIA and 2380 PSIA 2) IF PZR pressure less than PZR Pressure Control System Setpoint AND and lowering,
- controlled. THEN ENSURE Normal and Auxiliary Spray Valves - closed.
AND
- 3) IF PZR pressure (WR) less than
- 2) - trending to between 1740 PSIA, 2025 PSIA and 2275 PSIA.
THEN a) ENSURE SIAS - actuated, b) RECORD SIAS actuation on Attachment 1, WORKSHEET.
- 4) IF PZR pressure less than or equal to 1430 PSIA (WR),
l THEN ENSURE at least one RCP in each loop - stopped.
NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 6 0F 25 STANDARD POST TRIP ACTIONS OPERATOR ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED ;
NOTE: Low flow during natural circulation slows RCS response to temperature changes. Loop transit time rises to between 5 minutes and 10 minutes.
7 VERIFY Core Heat Removal criteria satisfied:
- operating. Attachment 1, WORKSHEET. I
- 2) ENSURE Natural Circulation in at least one loop establishing:
a) CHECK operating loop AT (TH-TC ) - less than 58*F.
b) CHECK Ty and Tc - NOT rising.
c) CHECK operating loop Tu and REP CET - within 16*F:
QSPDS page 611 l CFMS page 311.
~
d) CHECK Core Exit Saturation Margin - greater than 20*F:
e) CHECK Reactor Vessel level (Plenum) - greater than or equal to 100%:
1
- 3) GO T0 step 8.
- b. VERIFY core ai (Tn-Tc) - less than 10 F.
- c. VERIFY Core Exit Saturation Margin - greater than 20 F: )
QSPDS page 611 l CFMS page 311. !
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4 NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 7 0F 25 STANDARD POST TRIP ACTIONS OPERATOR ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINEO 8 VERIFY RCS Heat Removal criteria satisfied:
- a. VERIFY feedwater adequate: a. 1) IFanyS/Glevellessthan21%,
- 1) Level in both S/Gs THEN ENSURE EFAS - actuated.
- greater than 40% NR
- 2) ENSURE MFW pump Miniflow Valves AND in MODULATE.
Feedwater - available to 3) OPERATE feedwater systems to bothS/Gs. raise level in at least one S/G to 40% NR at greater than or OR equal to 200 GPM.
- 2) Auxiliary Feedwater flow to eachS/G-greaterthanor l
equal to 200 GPM.
OR 1
- 3) Main Feedwater flow to each '
S/G:
a) At least one MFW Pump
- operating, b) RTO - actuated to both S/Gs.
c) MFW Pump discharge to !
S/G differential I pressure - greater ;
than 25 PSID. '
- b. PREVENTS /Ghighlevel:
- 1) CLOSE MFW Block Valves:
HV-4047 HV-4051.
- 2) VERIFY both S/G 1evels 2) ENSURE Main Feedwater RTO
- less than 80% NR. - actuated.
NUCLEAR ORGANIZATION EMERGENCY OPERATING ENSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 8 0F 25 STANDARD POST TRIP ACTIONS OPERATOR ACTIONS ACTION / EXPECT D RESPONSE RESPONSE NOT OBTAINED 8 VERIFY RCS Heat Removal criteria satisfied: (Continued)
- c. VERIFY heat removal adequate: c. 1) OPERATE SBCS to maintain Tc
- between 545'F and 555"F.
- 1) Tc - less than 555"F.
- 2) IF SBCS NOT maintaining Tc.
- 2) S/Gpressures
- approximately 1000 PSIA. THEN OPERATE ADVs to maintain Tc
- between 545*F and 555*F.
- d. VERIFY Tc d. 1) ENSURE SBCS valves - closed.
- greater than 545 F 2) ENSURE ADVs - closed.
OR 3) CHECKS /GSafetyValves-closed.
- controlled. 4) ENSURE S/G Blowdown Valves
- closed:
E-088 HV-4054 E-089 HV-4053
- 5) a) ENSURE Moisture Separator Reheater isolation valves
- closed:
HV-2703 HV-2721 HV-2704.
b) IF MSR isolation valves CANNOT be verified closed AND Tc uncontrolled, THEN CLOSE MSIVs.
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c:
NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 9 0F 25 STANDARD POST TRIP ACTIONS OPERATOR ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 VERIFY RCS Heat Removal criteria satisfied: (Continued) d. (Continued)
- 6) IF S/G levels (WR) rising, l l
?
THEN a) VERIFY RTO response 4
- satisfactory J AND EVALUATE feeding via 3 Condensate Pumps and 1 MFW ]
Pump.
b) VERIFY AFW Valves - closed. ]
c) IF Steam-Driven AFW Pump operating, THEN OVERRIDE and STOP Electric AFW Pumps. )
d) ENSURE step 8a criteria for adequate feedwater
- satisfied.
- 7) IF Tc less than 500*F, THEN ENSURE at least one RCP
- stopped.
- e. VERIFY S/G pressures - greater e. 1) ENSURE MSIS - actuated.
than 740 PSIA.
- 2) RECORD MSIS on Attachment 1, I WORKSHEET.
1 1
. huCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 10 0F 25 STANDARD POST TRIP ACTIONS OPERATOR ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 VERIFY Containment Isolation criteria satisfied:
- a. VERIFY Containment pressure a. IF Containment pressure greater than
- less than 1.5 PSIG. 3.4 PSIG, THEN
- 1) ENSURE CIAS - actuated.
- 2) ENSURE all RCPs - stopped.
- 3) RECORD CIAS actuation on Attachment 1, WORKSHEET.
- b. VERIFY Containment Area b. RECORD Containment Area radiation Radiation Monitors - NOT alarms on Attachment 1. WORKSHEET.
alarming or trending to alarm:
RT7820 Containment (high)
RT7820 Containment (high)
RT7845 - Access Hatch RT7848 - General Area j
- c. VERIFY Secondary Plant c. RECORD Secondary Plant Radiation Radiation Monitors - NOT alarms on Attachment 1, WORKSHEET.
alarming or trending to alarm: ,
RT7870 - Air Ejector, WRGM RT7818 - Air Ejector RT6753 - E089 Blowdown RT6759 - E088 Blowdown RT7874A B - Steamline (low) !
RT7875A B - Steamline (high) !
NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 11 0F 25 STANDARD POST TRIP ACTIONS OPERATOR ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 VERIFY Containment Temperature and Pressure criteria satisfied:
- a. VERIFY Containment average o
- ENSURE proper functioning of temperature - less than 120"F. Normal Containment Cooling,
- b. VERIFY Containment pressure a ENSURE at least two Dome Air
- less than 1.5 PSIG. Circulators - operating.
- IF Containment pressure greater than 3.4 PSIG, THEN a) ENSURE CCAS - actuated.
b) RECORD CCAS actuation on Attachment 1, WORKSHEET.
b) ENSURE Containment Spray Header flow - greater than 1625 GPM.
c) RECORD CSAS actuation on Attachment 1, WORKSHEET.
11 VERIFY Containment Combustible Gas Control criteria satisfied:
- a. VERIFY Containment average o a ENSURE proper functioning of temperature - less than 120"F. Normal Containment Cooling,
- b. VERIFY Containment pressure
- ENSURE at least two Dame Air
- less than 1.5 PSIG. Circulators - operating. i l
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1 NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION IS PAGE 12 0F 25 STANDARD POST TRIP ACTIONS OPERATOR ACTIONS ACTION / EXPECTED RESPONS_E RESPONSE NOT OBTAINED 12 DIAGNOSE Event in Progress:
- a. CHECK all safety function a. 1) INITIATE steps 13 through 17.
criteria per Attachment 1 WORKSHEET - recovered. 2) COMPLETE Attachment 2, RECOVERY DIAGNOSTIC.
- 3) GO TO E01 indicated in Attachment 2 REC 0VERY l DIAGNOSTIC. l
- b. INITIATE steps 13 through 17.
- c. GO TO S023-12-2, REACTOR TRIP RECOVERY.
13 COMPLETE Administrative Actions: l l
- a. NOTIFY personnel of event in !
progress.
- b. DESIGNATE SRO-in-charge.
- c. INITIATE Attachment 4 ADMINISTRATIVE ACTIONS.
NUCLEAR ORGAN 1ZATION EMERGENCY OPERATING INSTRUCT 10N S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 13 0F 25 STANDARD POST TRIP ACTIONS OPERATOR ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 ENSURE the following loads restored:
- a. VERIFY 480 V Load Centers a. TRANSFER Non-1E Instrument Bus Q0612
- energized: to its emergency supply:
Unit 2/3-810 1) SELECT VS612, Q0612 Instrument Unit 3 - 3809. Bus #2 Transfer Switch, to EMERGENCY.
- b. VERIFY 480V Load Centers b. 1) VERIFY $6A20, REACTOR TRIPPED
- energized: CEDMCS DE-ENERGIZE 0 - alarming.
BIS 2) VERIFY CEDM M/G Set Output 816. Breakers - open.
- 3) IF power is available, THEN a) ENSURE B16 - energized.
b) ENSURE B15 - energized.
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NUCLEAR ORGANIZAT!0N EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 14 0F 25 STANDARD POST TRIP ACTIONS OPERATOR ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 CHECK Main Turbine Coastdown: l l
- a. ENSURE the following valves a. IF MSR isolation valves CANNOT be I closed: verified closed
- 1) Extraction Steam Block AND Valves (8):
TC uncontrolled, HV-8800 HV-8812 HV-8804 HV-8810 THEN SHUT MSIVs.
HV-8808 HV-8820 HV-8806 HV-8816
- 2) Main Steam to Reheater Block, Bypass and Warmup Valves (4):
HV-2721 HV-2703 HV-2704 HV-2751
- 3) HV-2712A/BBledSteamto Reheaters Block Valves,
- b. CLOSE HV-2702, Main Steam to Reheaters Control Valve.
- c. VERIFY Generator kV lowering c. TRIP Main Generator Field HS-2981,
- less than 24 kV. Generator Field Trip.
- d. VERIFY annunciators - NOT d. CONTROL lube oil temperature locally.
alarming:
99A26 TURBINE LUBE OIL TEMP HI i 99A46 TURBINE BRG OIL DRAIN TEMP HI l
NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 15 0F 25 STANDARD POST TRIP ACTIONS OPERATOR ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 CHECK Main Turbine Coastdown:
(Continued) i
- e. VERIFY automatic actions l between indicated speeds:
- 1) 1230 and 1240 RPM: 1) TRIP Main Generator Field i HS-2981, Generator Field Trip. f a) Generator kV - lowers '
to zero, i
- 2) 240 and 250 RPM: 2) a) IF Turning Gear failed, a) Turning Gear - starts. THEN HAND BAR the Main
)
]
Turbine, l b) Jacking Oil Pumps
- start. b) If Jacking 011 Pumps
- NOT started, j i
THEN START Jacking Oil Pumps.
- 3) Approximately 26 RPM: 3) IF Turning Gear clutch - NOT a) Turning Gear clutch
- engages and speed THEN HAND BAR the Main Turbine, remains constant.
16 ESTABLISH desired Condensate and Feedwater status:
- a. STOP 3rd Point Heater Orain Pumps.
- b. MAINTAIN at least one MFW pump b. ENSURES /Glevels-beingmaintained and three Condensate pumps in by AFW pumps.
operation.
- c. CLOSE discharge valve on idle Condensate Pump.
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o NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 16 0F 25 STANDARD POST TRIP ACTIONS OPERATOR ACTIONS ACTION / EXPECTED RESPONSE LESPONSE NOT OBTAINED 16 ESTABLISH desired Condensate and !
Feedwater status: (Continued) j
- d. CHECK S023-12-2, REACTOR TRIP d. 1) ENSURES /GBlowdow'nvalves RECOVERY being implemented. - closed:
E-088 HV-4054 E-089 HV-4053.
- 2) GO T0 step 17.
- e. CHECKS /GBlowdownvalves e. GO T0 step 17.
- open:
E-088 HV-4054 E-089 HV-4053.
- f. INITIATE THROTTLING S/G Blowdown flow to 75 GPM or as directed by SR0 OPS Supervisor.
17 CHECK Start-Up Range Channels:
- a. VERIFY BOTH Start-up a. If BOTH Start-Up Range channels are Range channels not Operable,
- operable.
THEN NOTIFY WO-in-charge of TS 3.3.13 And LCS 3.3.111 entry.
-END-l l
i S1-1S.W61:dpowers l
l
=
NUCLEAR ORGAN!ZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 17 0F 25 ATTACHMENT 1 STANDARD POST TRIP ACTIONS WORKSHEET SAFETY FUNCTION SAFETY FUNCTION CRITERIA CRITERIA RECOVERED
- 1. Reactivity Control Maximum of one CEA Not fully inserted Power lowering SUR negative [] Yes [] No
" At least one vital DC bus energized One Non-1E 4 kV bus energized [] Yes [] No
- 3. RCS Inventory Control f PZR Level recovering Saturation Margin >20"F [] Yes [] No
- 4. RCS Pressure Control
[] Pressure recovering [] Yes [] No
- 5. Core Heat Removal
[~f RCP running Core AT <10*F
[ Saturation Margin >20*F [] Yes [] No
[~ Tc controlled S/G Pressures >740 psia [] Yes [] No
- 7. Containment Isolation ,
Cntmt Pressure <1.5 psig i Cntmt Radiation Monitors NOT alarming or '
trending to alarm l
[] Secondary Radiation Monitors NOT alarming or trending to alarm [] Yes [] No
- 8. Containment Temperature & Pressure Control
[: Cntmt Average Temperature <120*F
[; Cntmt Pressure <1.5 psig [] Yes [] No
- 9. Containment Combustible Gas Control
" Cntmt Average Temperature <120'F Cntmt Pressure <1.5 psig [] Yes [] No ATTACHMENT 1 PAGE 10F 2
NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 18 0F 25 ATTACHMENT 1 STANDARD POST TRIP ACTIONS WORKSHEET UNIT DATE RECORD Clock Times: Coments:
Reactor Trip Emergency Boration Initiated SIAS All RCPS Off MSIS CIAS CNTMT Area Radiation Alarms Secondary Plant Radiation Alarms CCAS CSAS S1-15.W61 ATTACHMENT 1 PAGE 2 0F 2 l
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NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION IS PAGE 20 0F 25 ATTACHMENT 3 STANDARD POST TRIP ACTIONS DIESEL GENERATOR FAILURE FOLLOWUP ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED SM.I.l.QM Upon loss of either IE 4kV Bus A04 (A06), a load reduction of the 1E Batteries 03 (D4) should be performed within 30 minutes.
1 CNECK Required Diesel Generator operating:
- a. Voltage - approximately o a START NOT operating Diesel 4360 volts AC. Generator from electrical control
- b. Frequency - 60 HZ.
- IF Diesel Generator WILL NOT start from Control Room, THEN a) INITIATE battery load reduction:
Diesel Generator G-002 step 3 OR Diesel Generator G-003 step 4.
b) START NOT operating Diesel Generator locally per 5023-2-13, DIESEL GENERATOR OPERATION, Attachment on DIESEL GENERATOR MANUALLY INITIATED OPERATION.
- IF Diesel Generator WILL NOT start, THEN REQUEST Shift Superintendent /OperationsLeader j provide support for Diesel l Generator repair. ;
i I
ATTACHMENT 3 PAGE 1 0F 5 i
l NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 210F 25 ATTACHMENT 3 STANDARD POST TRIP ACTIONS ,
I DIESEL GENERATOR FAILURE FOLLOWUP ACTIONS !
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 CHECK 1E 4 kV buses A04 and A06 l energized:
- a. Voltage - approximately a. 1) IF 1E 4 kV bus A04 or A06 4360 volts AC de-energized j AND AND Frequency - 60 Hz. Associated Diesel Generator breaker DID NOT close, THEN fAU.T.1.0E 00 NOT OPERATE OPEN pushbuttons for tripped breakers.
Operation of OPEN pushbuttons will reset overcurrent protection allowing Diesel Generator output breaker to close to a fault.
ENSURE affected bus supply breakers - open:
a) A04:
2A0417/3A0416-A04BusTie A0418 - Reserve AUX XFMR A0419 - Unit AUX XFMR b) A06:
A0616 - Unit AUX XFMR A0618 - Reserve AUX XFMR 2A0619/3A0603-A06BusTie ATTACHMENT 3 PAGE 2 0F 5
a NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 22 0F 25 ATTACHMENT 3 STANDARD POST TRIP ACTIONS l
l DIESEL GENERATOR FAILURE FOLLOWUP ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 CHECK 1E 4 kV buses A04 and A06 '
energized: (Continued)
- a. (Continued)
- 2) IF overcurrent/ ground annunciators alarming:
a) A04:
63B15 - SUPPLY BKR A0419 OC 63B25 - SUPPLY BKR A0418 OC 63B35 - TIE FDR 2A0417 (3A0416) OC l b) A06: '
63C15 - SUPPLY BKR A0616 0C 63025 - SUPPLY BKR A0618 OC 63035 - TIE FDR 2A0619 (3A0603) OC THEN a) INITIATE S023-6-9, 6.9 kV, 4 kV AND 480 V FEEDER FAULTS, to return affected bus to service.
b) STOP Diesel Generator by placing in MAINTENANCE LOCK 0UT.
- 3) ADJUST Diesel Generator output to establish:
a) Voltage - approximately 4360 volts AC AND b) Frequency - 60 Hz.
ATTACHMENT 3 PAGE 3 0F 5
NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 23 0F 25 ATTACHMENT 3 STANDARD POST TRIP ACTIONS DIESEL CENERATOR FAILURE FOLLOWUP ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 CHECK 1E 4 kV buses A04 and A06 energized: (Continued) a. (Continued)
- 4) CHECK Diesel Generator output breaker to affected bus - closed.
- 6) IF Diesel Generator output breaker NOT closed, THEN a) STOP Diesel Generator by placing in MAINTENANCE LOCK 0UT b) REQUEST Shift Superintendent /
Operations Leader provide support for Diesel Generator repair.
3 CHECK Shutdown Cooling Suction Valve Inverter Y-006 energized from DC Bus D3:
- 1) D3 Battery
- 2) OPEN the following breakers to AND reduce D3 Battery load:
Y03-13 Y03-14.
- 3) REQUEST Shift Superintendent /
Operations Leader to evaluate restoring power to MCC BE.
ATTACHMENT 3 PAGE 4 0F 5
NUCLEAR ORGAN!ZATION EMERGENCY OPERATING INSTRUCTION S023-12-1 UNITS 2 AND 3 REVISION 15 PAGE 24 0F 25 ATTACHMENT 3 STANDARD POST TRIP ACTIONS DIESEL GENERATOR FAILURE FOLLOWUP ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 CHECK Shutdown Cooling Suction Valve Inverter Y-007 energized from DC Bus D4:
- 1) D4 Battery
- 2) OPEN the following breakers to AND reduce D4 Battery load:
YO4-13 YO4-14.
- 3) REQUEST Shift Superintendent /
Operations Leader to evaluate restoring power to MCC BJ.
- END -
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51-15 W61 ATTACHMENT 3 PAGE 5 0F S I
l
r NUCLEAR ORGANIZATION EMERGENCY OPERAT!NG INSTRUCTION S023-12-1
.' UNITS 2 AND 3 REVISION 15 PAGE 25 0F 25 ATTACHMENT 4 STANDARD POST TRIP ACTIONS ADNINISTRATIVE ACTIONS 1 NOTIFY the following personnel:
- a. Duty Division Manager or Plant Superintendent
- b. Shift Technical Advisor
- c. System Operating Supervisor.
2 INITIATE the following procedures:
- a. S0123-VIII-1, Recognition and Classification of Emergencies i
- b. 50123-0-14, Notification and Reporting of Significant Events.
3 REQUEST Chemistry Di!partment initiate the followir.g procedures:
- a. 50123-III-5.1.23, Unit 2/3 Effluent Sampling and A a 'ysis
- b. S0123-III-1.1.23, Units 2/3 - Chamical Control r .imary Plant and Related Systems
- c. 50123-III-8.(series), PASS Operation.
4 WHEN event has been terminated, THEN INITIATE the following procedures:
- a. S0123-0-25, Trip /TransientReview
- b. 50123-0-42, Cumulative Equipment Hours, Inoperability and Design Cycles.
I 1
SI-15.W61 ATTACHMENT 4 PAGE 1 0F 1
II f
I Attachment D - Emergency Operating Instruction SO23-12-7 " Loss of Forced Circulation / Loss of 0ff Site Power"(pages 1,3,18, 39, and 122) i