ML101970321
| ML101970321 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/28/2010 |
| From: | NRC/RGN-II |
| To: | Progress Energy Carolinas |
| References | |
| 50-261/08-301 50-261/08-301 | |
| Download: ML101970321 (92) | |
Text
I Appendix Appendix D D Scenario Outline Scenario Outline Form ES-D-1 Form ES-D-1 Facility:
Facility: HB ROBINSON HB ROBINSON Scenario No.:
Scenario No.: 11 Op Test No.:
Op Test No.:
Examiners:
Examiners: Operators:
Operators: SRO -
SRO -
RO-RO BOP BOP-Initial Conditions:
Initial ** 68% EOL, 17,000 MWD/MTU, 106 106 ppm Boron.
0o LCO 3.7.7 3.7.7-A
-A has been entered and is in hour 18 18 of a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement.
0o Expected return is within -18 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
- . Main Turbine Vibration for #2, 3 and 4 bearings is elevated.
Turnover: ** Returning to RTP following a short Maintenance Outage. Awaiting results of post-outage testing. Maintain power at current level.
Critical Task: ** Manually restart SW pump to provide cooling to only running EDG before damaging the EDG.
prior to transitioning to PATH-1, Event MaIf.
Malf. Type*
Event Type* Event No.
No. No. Description 11 (C) BOP, SRO HVH-9A/B AIR FLOW LOST alarm.
2 (TS) SRO PR N-42 Upper Detector Fails Low.
3 (I) BOP, SRO Feed Flow Channel FT-477 Fails High.
(TS) SRO 4 (R) RO Plant down power resulting from loss of Condensate Pump which (N) SRO, BOP trips Main Feed Pump.
55 (I) RO, SRO PT-444, Controlling PZR Pressure channel fails High.
66 (C) RO, SRO RCP C "C" #2 Seal fails, requiring a Reactor Trip.
77 (M) ALL Steam Break from S/Gs B "B" and C "C" on the Reactor Trip.
88 (C) BOP EDG A"A" fails to start on the Safety Injection.
99 (M) ALL Loss of Off-Site power. (Loss of SUT) 10 10 (C) BOP SW Pumps fail to start following restoration of power.
- (N)ormal, (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix Appendix D D NUREG-i NUREG-1 021,021, Rev.
Rev. 9, 9, Supp.
Supp. 11
I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 1 1
SUMMARY
DESCRIPTION The crew will assume the watch with the plant at 68% RTP. The previous shift identified increased vibration on Main Turbine bearing #3 and has taken all necessary actions to inform station management. Service Water Booster Pump "A" A is under clearance for Motor Coupling Alignment. Shift instructions are to maintain power at current level.
On cue from the Chief Examiner, APP-01APP-010-A7, HVH-9NB AIR FLOW LOST/OVLD alarm will 0-A7, HVH-9A/B illuminate. The BOP will reference APP-01 0-A7 and stop Concrete Shield Cooling Fan HVH-9A and start HVH-9B.
On cue from the Chief Examiner, PR N-42 Upper Detector will fail low. The RO should identify that it is an instrument failure, NOT a dropped rod and respond lAW APP-005-A3. The crew will NOT remove the instrument from service, but the SRO will enter LCO 3.3.1 Conditions D, E, S and T for the failed instrument.
After ITS has been addressed for the N-42 detector failure, the Chief Examiner can cue the FT- FT 477, S/G "A"A Feed Flow instrument failure. The BOP should respond by taking Manual control of SIG "A" S/G A FRV and controlling S/G SIG level within normal parameters. An alternate instrument will be placed in service and the FRV will be returned to automatic control. The crew should respond lAW AOP-025, RTGB INSTRUMENT FAILURE and remove the instrument from service. The SRO should enter LCO 3.3.1, Condition E E for the failed instrument.
On cue from the Chief Examiner, Condensate Pump "A" A will trip causing Feedwater Pump "A" A to trip. This will result in an entry into AOP-O10, AOP-010, MAIN FEEDWATER /I CONDENSATE MALFUNCTION. The crew should reduce Turbine load to less than 50% RTP lAW Attachment 1 1 of AOP-010.
When the Chief Examiner is satisfied with the power reduction, he can cue the PT-444, PZR Pressure controlling channel failure. PZR PORV PCV-455C and PZR Spray valves will open causing pressure to decrease. The RO will manually close PCV-455C and take manual control of PZR pressure and return it to the normal control band. If pressure decreases below 2205 PSIG, the crew will enter LCO 3.4.1, Condition A for the Low Pressure condition.
On cue from the Chief Examiner, the RCP "C" C #2 seal leak will begin. The crew should respond using AOP-01 AOP-018,8, REACTOR COOLANT PUMP ABNORMAL CONDITIONS, calculating a high seal leakoff and determine a plant shutdown lAW GP-006, NORMAL PLANT SHUTDOWN sealleakoff FROM POWER OPERATION TO HOT SHUTDOWN is required. At that time seal leakage will degrade to the point where the SRO will direct a Reactor Trip.
PATH-i will be entered and on the Reactor Trip a Steam Break will develop in S/Gs PATH-1 B and "C".
SIGs "B" C.
After the Safety Injection has been reset and S/Gs B and "C" SIGs "B" C have been isolated, the Chief Examiner can cue the Loss of Off-Site power. The Start-Up Transformer will be lost and EDG "B" B will load to the bus. Auxiliary Feedwater and Component Cooling Water loads will be restored.
The crew should respond lAW PATH-1PATH-i and restart safeguards equipment (SI pump, RHR pump, HVH units and SW pumps) manually.
The Chief Examiner may terminate the scenario at any time after the S/Gs SIGs have been isolated and Service Water cooling to the EDG has been restored.
Appendix D NUREG-102i, Rev. 9, Supp. 11 NUREG-1021,
I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 11 SIMULATOR SETUP IC/SETUP
- SON: 006_Sim_1.
IC-601, SCN:
- SW Booster Pump "A"A is OFF, breaker OPEN and switch is RED CAPPED.
- Main Turbine Bearing #2 is OFFSET by 1.5, #3 by 2.3 and #4 by 1.7.
- 10-17.
Status board updated to reflect IC-17.
PRE-LOADED EVENTS:
The following events should occur on the reactor trip:
- Event 7: Steam Break from S/Gs "B" B and "c" C on the Reactor Trip.
- A fails to start on the Safety Injection.
Event 8: EDG "A"
EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:
EVENTSITRIGGERS
- HVH-9NB AIR FLOW LOST alarm.
Event 1: HVH-9A/B
- Event 2: PR N-42 Upper Detector fails low.
- Event 3: Feed Flow channel FT-477 fails high.
- Event 4: Plant down power from Condensate Pump "A" A and Feedwater Pump A "A" trip.
- Event 5: PT-444, Controlling PZR pressure channel fails High.
- Event 6: RCP "c" C #2 Seal fails, requiring a Reactor Trip.
- Event 9: Loss of Off-Site Power. (Loss of SUT)
EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
AOP-025, Section E; OWP-026, FWF-2; AOP-01 AOP-010;0; AOP-025, Section C; AOP-01 8; PATH-1; AOP-018; PATH-i; EPP-i 1; EPP-7; Supplement G.
Foldouts A & B; EPP-11; Appendix D NUREG-i NUREG-1 021, Rev. 9, Supp. 11
Appendix DD Appendix Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 11 Event ##
Event 1 Page Page 44 of of 29 29
--..;.....- ~-------- ~~----~I Event
Description:
Event
Description:
HVH-9AIB AIR HVH-9A/B AIR FLOW FLOW LOST LOST alarm.
alarm.
Time Time II Position Position ~ Applicants Actions Applicant's Actions or or Behavior Behavior BOOTH OPERATOR:
BOOTH OPERATOR: When When directed directed by the Chief by the Chief Examiner, Examiner, insert insert Event Event 1, 1, HVH-9A1B HVH-9NB AIR FLOW LOST AIR FLOW LOST alarm. alarm.
EVENT INDICATIONS:
EVENT INDICATIONS:
APP-O1O-A7; HVH-9A1B APP-010-A7; HVH-9AIB AIR AIR FLOW FLOW LOST/OVLD LOST/OVLD BOP BOP Recognizes APP-010-A?
Recognizes APP-O10-A7 alarm and references references actions.
BOP IF the IF the operating operating fan has has NOT NOT tripped, THEN perform the following:
- Stop the running fan.
- Start the standby fan.
- 0-A7 clears.
Verify APP-01 O-A?
Appendix Appendix DD NUREG-1 NUREG-1 021, 021, Rev. 9, Supp.
Rev. 9, Supp. 11
Appendix D D Operator Action Operator Form Form ES-D-2 ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 1 Event ##
Event 22 Page Page 55 of of 29 29
~--------- ~~------~I Event
Description:
Event
Description:
PR N-42 PR N-42 Upper Upper Detector Detector fails fails Low.
Low.
Time III Position Position II Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 2, PR N-42 Upper Detector fails low.
EVENT INDICATIONS:
APP-003-B6; Overpower LlT APP-003-86; T APP-003-C6; Overtemp LlT tT APP-005-A3; PR Dropped Rod APP-005-C3; PR Channel Dev Dcv OThT/OPT Turbine Runback Rod Stop APP-005-D5; OTLlT/OPLlT APP-005-F3; PR Upper Ch Hi Flux Dev I Auto Defeat APP-005-D6; Ll t Flux Warning I Status (later)
(Nl-42C) pegged LOW t Flux meter (NI-42C)
N-42 Ll Upper Detector (A) on N-42 Drawer indicates low On NR-45 and NR-47 Recorders, N-42 reads lower than other Power Range Nls NIs Recognizes that N-42 has failed and there is NO dropped rod.
RO References APPs to determine actions or recommendations.
Reviews, briefs and directs taking N-42 instrument out of service using SRO OWP-011, NI-2.
Reviews ITS for applicable LCOs
. Table 3.3.1-1, #2 - Condition D; Place channel in Trip within 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br />.
. Table 3.3.1 -1,, #5 and 6 - Condition E: Place channel in Trip 3.3.1-1 -
SRO within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
. Table 3.3.1-1, #17c - Condition T; Verify interlock is in required state within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
. Table 3.3.1-1, ItemItem #17d - Condition
- Condition S: Verify interlock isis in required state within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
NOTE:
NOTE: As soon as the Chief Examiner Examiner is is satisfied with the SRO SRO referencing ITS, ITS, the next next event can be inserted.
The OWP doesdoes NOTNOT need need to be implemented in in order to continue with the scenario.
Appendix Appendix DD NUREG-1 NUREG-1 021, 021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix D D Operator Action Operator Form Form ES-D-2 ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 11 Event ##
Event 3 _ _ _ _ Page
_3;;..-. Page 66 of of .....:2~9 29_ _ _-I1 Event
Description:
Event
Description:
Feed Flow Feed Flow channel channel FT-477 FT-477 fails fails high.
high.
Time Position Position AApplicants licant's Actions or Behavior Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 3, Feed Flow channel FT-477 fails high.
EVENT INDICATIONS:
APP-006-A1; S/GSIG A FW > STM FLOW FLOW (Clears on lamp Lamp Acknowledge)
APP-006-A2; S/GSIG A STM STM> > FW FLOW APP-006-A3; S/G LVL DEV SIG A lVl APP-006-D1: S/GSIG A NAR RANGE lO/lO-lO LO/LO-LO lEVEL LEVEL FR-478 Green Pen goes high and FCV-478 closes BOP Recognizes FT-477 has failed and performs Immediate Actions for AOP-025, RTGB INSTRUMENT FAILURE.
SRO Enters AOP-025, RTGB INSTRUMENT FAILURE, Section E.
Immediate Action Step:
BOP Place the affected FRV (FCV-478 for S/G "A") A) in MAN.
Immediate Action Step:
BOP Restore Affected S/G Level To Between 39% And 52%.
RO/BOP ROIBOP Make PA announcement for entry into AOP-025.
Place the affected SIG S/G Feed Flow Selector Switch to the alternate BOP channel. (CH-476, FR478 FR-478 recorder pen will return to normal status)
Continuous Action Step:
Restore Affected Controller To Automatic:
BOP BOP *
- Check Check S/G level within +/- +/- 11%
% of of programmed programmed level. (If (If YES, place in in Auto Auto and and Go To Step 6) 6)
WHEN S/G S/G level level is is within within +/- +/- 11% % ofof programmed level, level, THEN place the affected affected Controller in in AUTO.
Appendix Appendix D D NUREG.1O21, NUREG-1021, Rev. Rev. 9, 9, Supp.
Supp. 11
Appendix DD Appendix Operator Action Operator Action Form ES-D-2 Form ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 11 Event ##
Event 33 Page Page 77 of of 29 29
......;...- ~-------- ~------~I Event
Description:
Event
Description:
Feed Flow Feed Flow channel channel FT-477 FT-477 fails high.
fails high.
Time Time III Position Position ~ Applicants Actions Applicant's Actions oror Behavior Behavior Reviews, briefs Reviews, briefs and and directs directs taking taking FT-477 FT-477 instrument instrument out out of of service service SRO using OWP-026, FWF-2.
OWP-026, FWF-2 OWP-026, FWF-2 actions Precautions:
- . Ensure FR-478 Feed Flow Selector switch on the RTGB is selected to FT-476 prior to flow transmitter isolation.
- . Refer to ITS Table 3.3.1-1 Item 14 14 for Feedwater flow OPERABILITY and applicability requirements.
- . With Reactor Trip Breakers closed, ensure "A" A S/G level channels LT-474 AND LT-475 are in service.
- Maintain S/G "A" A level above Lo Level setpoint.
BOP Remove the affected transmitter from service using OWP-026, FWF-2.
- . FR-478 selector switch selected to CH-476.
- Delete input FT-477 from CALO processing. (FWF0404A) (FWFO4O4A)
(May be removed by using the "DR" DR Delete/Restore function of ERFIS)
(APP-036-L11 will be received when Hagan Rack door is opened)
(APP-036-L
. Trip bistable FC-478B-1, STM-FW FLO DEV.
(APP-006-A2 and B/S STATUS LIGHT SG NO 11 STM-FW FLO DEV FC-478B1 will be received)
SRO Go To Procedure (AOP-025) Main Body, Step 2.
SRO SRO Review LCO 3.3.1-1, #14 #14 Condition E E - Trip bistable
- bistable within 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br />.
SRO SRO Return Return to to procedure procedure andand step step inin effect.
effect.
Appendix Appendix D D NUREG-1 NUREG-1 021, 021, Rev. 9, Supp.
Rev. 9, Supp. 11
Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # _4~
4 ____ Page 8 of _2_9;.....-_
29 _.....,1 Event
Description:
Plant down power from Condensate Pump "AnA trip which tripped Feedwater Pump "An.A.
Time ! Position ! Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 4, Condensate Pump "A"A trips which results in the tripping of MFP "A". A.
EVENT INDICATIONS:
APP-007-A1; COND PMP A MOTOR OVLDrrRIP OVLD)TRIP (Extinguishes on Lamp acknowledge)
APP-006-A3; S/G SIG A LVL DEV, APP-006-B3; S/G SIG B LVL DEV, APP-006-C3; S!G S/G C LVL DEV (later)
Condensate Pump "A" A and Main Feedwater Pump "A" A breaker open.
Recognizes loss of Condensate/Feed Pump and performs immediate BOP AOP-0i0, MAIN FEEDWATER/CONDENSATE actions of AOP-010, MALFUNCTION.
Immediate Action Step:
BOP Check Feedwater Regulating Valves Operating Properly in Manual OR Auto. (YES)
Continuous Action Step:
Check Reactor Trip Setpoint Being Approached. (NO)
SRO IF a Reactor Trip Setpoint is approached, THEN trip the Reactor and PATH-i. (Go To Step 4)
Go To PATH-1..(Go RO Make PA Announcement for Procedure Entry into AOP-Oi AOP-01 O.0.
SRO Go to appropriate step: Condensate AND Feed Pump Trip, Step 10.
RO Check Reactor Power less than 70%. (YES)
RO Check Reactor Power greater than 50%. (YES)
Reduce Turbine load at 1 i%/MIN
%/MIN to 5%/MIN to achieve less than 50%
BOP Reactor Power using Attachment 1 i..
Appendix D D NUREG-102i, NUREG-1 021, Rev. 9, Supp. 1 1
Appendix 0D Operator Action Form ES-D-2 Op Test No.:
Scenario # 1 1 Event # 4
~--------
Page 9 of 29
~------~I Event
Description:
Plant down power from Condensate Pump "An A trip which tripped Feedwater Pump "An.
A.
Time Position Aoolicants A licant's Actions or Behavior Attachment 11 - Turbine Load Reduction
- Check Turbine Control Mode in automatic. (YES)
- . Depress the IMP IN Pushbutton.
- Set the desired load in the SETTER.
- . Set desired load rate.
- . Depress the GO Pushbutton.
NOTE: OP-301, Section 8.2.8 Quick Boration Checklist (shaded area) is included in the following steps, but may be used following the commencement of the plant down power.
The crew should add - 100 gallons of Boric Acid for the 18%
down power. (The crew will add Boric Acid in 2-4 batches)
DETERMINE the amount of Boric Acid to add to the RCS and RD RO OBTAIN an independent check of the volume required.
RD RO OBTAIN permission from the CRSS OR the SSO to borate.
RD RO PLACE the RCS MAKEUP MODE selector switch to BORATE.
RD RO YIC-1 13, BORIC ACID TOTALIZER to desired quantity.
SET YIC-113, IF desired, THEN PLACE FCV-113A,FCV-1 13A, BORIC ACID FLOW, in MAN RD RO AND_ADJUST_using_the_UP_and_DOWN_pushbuttons AND ADJUST using the UP and DOWN pushbuttons.
RD RO Momentarily PLACE the RCS MAKEUP SYSTEM switch to START.
IF any of the below conditions occur, THEN momentarily place the RD RO .,
RCS MAKEUP SYSTEM switch in the STOP position:
ReS
- Rod Motion is blocked OR is in the wrong direction
- T increases AvGincreases TAVG
- Boric Acid addition exceeds the desired value Appendix 0D NUREG-1021, Rev. 9, Supp. 1 1
Appendix D 0 Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 1 Event # 4 Page 10 10 of 29
-- ---------- ~---~I Event
Description:
Plant down power from condensate Condensate Pump A "A" trip which tripped Feedwater Pump A."A".
Time ~ Position ~ Applicants Applicant's Actions or Behavior WHEN the desired amount of Boric Acid has been added, THEN verify the following:
RD RO ** FCV-113A, BORIC ACID FLOW, closes.
FCV-1 13A, BORIC
- . FCV-113B, FCV-1 13B, BLENDED MU TO CHG SUCT, closes.
- . IF in Auto, THEN the operating Boric Acid Pump stops.
- . The RCS MAKEUP SYSTEM is OFF.
IF desired, THEN FLUSH the Boric Acid flow path as follows:
- . SETYIC-114, PRIMARY WTR TOTALIZERto SET YIC-114, PRIMARYWTR TOTALIZER to 15-20 gallons.
- PLACE FCV-114B, BLENDED MU TO VCT VCTto to CLOSE.
- Momentarily PLACE the RCS MAKEUP SYSTEM switch to the START position.
- IF any of the below conditions occur, THEN momentarily place RO the RCS MAKEUP SYSTEM switch in the STOP position:
0o Unanticipated Rod Motion 0o Primary Water addition reaches the desired value
- WHEN the desired amount of Primary Water has been added to the RCS, THEN verify the following:
0o FCV-ll4Acloses.
FCV -114A closes.
0o FCV-1 13B closes.
FCV-113B 0o IF in Auto, THEN the operating PW Pump stops.
0o The RCS MAKEUP SYSTEM is OFF.
RETURN the RCS Makeup System to automatic as follows:
- VERIFY FCV~114A FCV-1 1 4A is in AUTO.
- PLACE FCV-114B FCV-1 14B to the AUTO position.
RD RO ** PLACE the RCS MAKEUP MODE switch in AUTO.
- VERIFY FCV-113A is in AUTO.
FCV-1 13A isin
- Momentarily PLACE the RCS MAKEUP SYSTEM switch in the START position.
RECORD, in AUTO LOG, as indicated by PRIMARY WATER RD RO TOTALIZER, YIC-1 14 AND Boric Acid TOTALIZER, YIG YIC-1 13 the total
.. 113 amount of Primary Water AND Boric.Acid Boric Acid added during the boration.
MONITOR parameters for the expected change in reactivity AND RD RO the_results_of the_boration.
inform_the_CRSS_OR_the_SSO_of inform the CRSS OR the SSO of the results of the boration.
Appendix 0 D NUREG-1 021, Rev. 9, Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 11 Event ##
Event 4
_4..:.....-_ _ _ _ Page Page 11 11 of 29_ _ _-lI of ...,;2;;.;;.9 Event
Description:
Event
Description:
Plant down Plant down power power from from Condensate Condensate Pump Pump "Au A trip trip which which tripped tripped Feedwater Feedwater Pump Pump "Au. A.
I Time Time I Position Position I Applicants Actions Applicant's Actions oror Behavior Behavior BOP BOP Check at Check at least least 11 Main Main Feed Pump running.
Feed Pump running. (YES, (YES, Go Go To To Step Step 37) 37)
BOP Check S/G Level at or trending to program. (YES)
RO RO Check T AVG at or trending to T TAVG REF. (YES)
TREF.
SRO Contact Maintenance to troubleshoot and correct Feedwater problem.
Check current loading for the following pumps less than maximum.
- . Condensate Pump - 370 AMPS
- Heater Drain Pumps - 90 AMPS BOOTH 800TH OPERATOR: When contacted, wait 3 minutes and report that Main Feedwater Pump B "8" is 530 AMPS, Condensate Pump "8" B is 320 AMPS and Heater Drain Pumps are 80 AMPS each.
Determine Iodine Sampling Requirements:
RO Check Power change> 15% 15% in one hour. (NO, Go To Step 43)
Continuous Action Step:
Check Check APP-005-B5, ROD BANKS BANKS A/B/C/D AlB/C/D LO LIMIT extinguished.
extinguished.
RO (YES)
IF IF alarm alarm isis illuminated, illuminated, THEN THEN Borate Borate to to clear thethe alarm alarm using using OP-301 OP-301 while while continuing continuing in in this this procedure procedure.
RO RO Monitor Monitor Axial Axial Flux Flux Difference Difference to ensure ensure compliance compliance with LCO 3.2.3 3.2.3 Appendix Appendix D D NUREG-1021, NUREG-1 021, Rev. 9, Supp.
Rev. 9, Supp. 11
Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # ~44 _________ Page Page 12 of _2;;;.;9~
29 _ _---I1 Event
Description:
Plant down power from Condensate Pump "A"A trip which tripped Feedwater Pump "A".
A.
Time II Position ! Applicants Applicant's Actions or Behavior SRO units load capability.
Notify Load Dispatcher of the unit's SRO Return to procedure and step in effect.
At the discretion of the Chief Examiner, insert Event 5.
Appendix D NUREG-1 021, Rev. 9, Supp. 1 1
Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 1 Event # 5 Page 13 of 29
~-------- ~------~I Event
Description:
PT-444, Controlling PZR pressure channel fails High.
Time ~ Position ~ Applicants Applicant's Actions or Behavior BOOTH OPERATOR: When directed, insert Event 5, PT-444 failed high.
EVENT INDICATIONS:
APP-003-D8, PZR CONTROL HIILO HI/LO PRESS APP-003-F3, CHG PMP LO SPEED APP-003-E6, APP-003-ES, PZR PORV LN HI TEMP APP-003-F6, APP-003-FS, PZR SAFETY LINE HI TEMP APP-003-C3, PRT HIGH PRESS APP-003-C7, PZR PRESS CONTROLLER HI OUTPUT Recognizes that PT-444 is failed high and performs Immediate Actions RO of AOP-025.
SRO Enters AOP-025, RTGB INSTRUMENT FAILURE, Section C.
Immediate Action Step:
Determine if PORVs should be closed.
- Check Pressurizer pressure less than 2335 psig (YES) (YES)..
- . Verify both PORVs CLOSED (NO, PCV-455C OPEN) OPEN)..
NOTE: May use PC-444J or Close PORV & & Spray Valves in Manual.
Immediate Action Step:
RO Control Pressurizer Spray Valves and Pressurizer Heaters to restore RCS pressure to the desired control band.
NOTE: 3.4.1 .A if pressure decreases < 2205 PSIG.
Crew will enter LCO 3.4.1.A restored > 2205 PSIG within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Pressure must be restored>
RO/BOP Make PA announcement for entry into AOP-025.
SRO/RO Check PT-444 is the failed transmitter. (YES)
Appendix D NUREG-1 021, Rev. 9, Supp. 1 1
Appendix 0D Appendix Operator Action Operator Action Form Form ES-D-2ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 11 Event ##
Event 5
_5;;;..-.____ Page Page 14 14 of _2;;;;.;9~
of 29 _ _--I1 Event
Description:
Event
Description:
PT-444, Controlling PT-444, Controlling PZR PZR pressure pressure channel channel fails fails High.
High.
Time Time J Position Position III Applicants Actions Applicant's Actions oror Behavior Behavior Control Pressurizer Control Pressurizer pressure pressure controller controller PC-444J:
PC-444J:
- Place PC-444J in MAN.
RO *. Verify PZR SPRAY VALVES IN AUTO.
- . Verify PZR PZR Heaters Heaters energized as desired.
- . Restore Restore PZR PZR Pressure to the desired control band.
Pressure band.
Verify PCV-455C Verify Selector Switch PM-444 is selected to operable channel:
- REC-445.
SRO Informs SSO to implement EAL's. EALs.
SRO Enters LCO 3.4.1 3.4.1,, Condition A.
NOTE: Crew should notify WCC SRO and/or I&C l&C to write a work request, investigate and initiate repairs, and notify the Operations Manager.
At Chief Examiner's Examiners discretion after ITS is addressed, proceed to Event 6.
Appendix Appendix D0 NUREG-1 NUREG-1 021, 021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Test No.:
Op Test No.: Scenario ##
Op Scenario 11 Event ##
Event 6, 77 && 88 6,
~~~---
Page Page 15 15 of of 29 29
~---~I Event
Description:
Event
Description:
- 2 Seal Seal fails, requiring aa Reactor fails, requiring Reactor Trip.
Trip.
Steam Break Steam Break from from S/Gs S/Gs "B"B and and "C" C on the Reactor on the Trip.
EDG "A" EDG A fails to start fails to start on Safety Injection.
on Safety Injection.
Time Time II Position Position ~fi Applicants Actions Applicant's Actions or or Behavior Behavior BOOTH OPERATOR:
BOOTH OPERATOR: When When directed directed by the Chief by the Chief Examiner, Examiner, insert insert Event Event 6,6, RCP RCP "C" C #2
- 2 Seal failure requiring Seal requiring Reactor Reactor Trip.
EVENT INDICATIONS:
EVENT INDICATIONS:
APP-OO1-C5; RCP APP-001-C5; RCP STANDPIPE STAN DPIPE HI/LOHI/LO LVL LVL (RCP (RCP C C STP STP HI)
HI)
FR 154A, FR 154A, Pen Pen 3 (Blue), C RCP Seal LeakoffLeakoff decreasing RO Recognizes decreasing seal leakoff and references APP-001-C5. APP-O01 -C5.
IF Standpipe level is High, THEN check for rising level in the Reactor RO Coolant Drain Tank.
OPERATOR: When requested by the crew wait 3 minutes and inform the crew BOOTH OPERATOR:
that RCDT level is slowly rising. (1 (1% % in the last 3 min.)
mm.)
SRO AOP-01 8, RCP ABNORMAL Enters AOP-018, ABNORMAL CONDITIONS, CONDITIONS, Section A.
Continuous Action Step:
RO Check any RCP #1 Sealleakoff Seal leakoff flow> 5.7 GPM. (NO, Go To Step 8) seal leakoff exceeds 5.7 GPM, THEN Go To Step 2.
IF sealleakoff Continuous Action Step:
RO Check indicated #1 Seal Leakoff << 0.8 GPM. (NO, Go To Step 14) 14)
IF Seal Leakoft Leakoff decreases to << 0.8 GPM, GPM, THEN Go To Step 9.
RO Check RCP Check RCP #2 #2 Seal Seal problem suspected.
suspected. (YES) (YES)
Check Check RCP #2 Seal Seal Leakoff rate known. known. (NO)
SRO Dispatch an operator to perform Att. Att. 2, 2, RCP Seal Leak Rate Calculation.
Calculation. WHEN WHEN calculation is is complete, complete, THENTHEN GoGo To To Step Step 16.
16.
Appendix Appendix D D NUREG-1 NUREG-1 021, 021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 11 Event ##
Event 6, 7 & 8
_6;...:.,..;..7...;;&;....;;8;....-__ Page Page 16 16 of ..,;2:;;,;9:...-_
of 29 _--11 Event
Description:
Event
Description:
RCP "e" Rep c #2
- 2 Seal Seal fails, requiring aa Reactor fails, requiring Reactor Trip. Trip.
Steam Break from Steam Break from S/Gs S/Gs "B"B and c and "e" onon thethe Reactor Reactor Trip. Trip.
EDG "A" EDG A fails fails to to start start onon Safety Safety Injection.
Injection.
Time Time II Position Position [
II Applicants Actions Applicant's Actions or or Behavior Behavior BOOTH OPERATOR:
BOOTH OPERATOR: When requested requested to perform perform Leak Leak Rate Rate Calculation, Calculation, wait 55 minutes minutes and inform the crew crew that RCP #2 Seal leakoff is 1.3 1.3 GPM.
Continuous Action Step:
Check calculated RCP #2 Sealleakoff Seal leakoff < < 1.11 .1 GPM. (NO)
RO Place the plant in Mode Mode 3 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> using GP-006. WHEN the plant is in Mode 3, THEN stop stop the affected RCP.
BOOTH OPERATOR: The crew will make the decision to shut down the plant lAW GP- GP 006. As soon as Step 16 (above) is performed, insert the higher RCS leak rate.
The crew will identify the increased leakage and return to Continuous Action Step 1.
EVENT INDICATIONS:
APP-OO1-B2; RCP LABYRTH SEAL LO DP APP-001-B2; APP-OO1-D2; APP-001-D2; RCP #1 SEAL LEAKOFF HI FLOW APP-OO1-E2; APP-001-E2; RCP #1 SEAL LEAKOFF LO FLOW PZR level decreasing, Charging Pump Speed increasing FR 154A; 154A; A and B Pens decreasing, C C Pen pegged HIGH.
Continuous Action Step:
RO Check any RCP #1 Seal leakoff flow> 5.7 GPM. (YES)
Sealleakoff Check Check RCP #1 seal leakoff flow on unaffected sealleakoff unaffected RCP(s) - DECREASED DECREASED (YES)
RO OR RCP Thermal Barrier tP boP on affected RCP(s) - DECREASED - DECREASED (YES)
RO RO Check Check PlantPlant in in MODE MODE 1. 1. (YES)
(YES)
Perform Perform the the following:
RO RO ** Trip Trip the the reactor.
reactor.
- TrifJ RCP "C" .
- __Trip_RCP_C.
Appendix Appendix DD NUREG-1021, Rev.
NUREG-1021, Rev. 9, 9, Supp.
Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 11 Event ##
Event _6;,:,'...;..7..;;.;&;..;;8~
6, 7 & 8 _ _ Page Page 17 17 of ....::2:.;;.9 of 29_ _ _-11 Event
Description:
Event
Description:
RCP "e" Rep C #2
- 2 Seal Seal fails, requiring aa Reactor fails, requiring Reactor Trip. Trip.
Steam Break from Steam Break from S/Gs S!Gs "B"B and and "e" C onon the the Reactor Reactor Trip.Trip.
EDG "A" EDG A fails fails to to start start onon Safety Safety Injection.
Injection.
Time Time II Position Position II Applicants Actions Applicant's Actions or Behavior or Behavior
- Go To Go Path-i while To Path-1 while continuing continuing with with this this procedure procedure..
NOTE: Following the performance Following performance and verification of PATH-1 PATH-i Immediate Immediate Actions, the crew will continue with AOP-018. These steps may be be handed off to the RO/BOP to perform independently.
The remaining steps of AOP-018 AOP-0i8 are listed here.
PATH-i actions begin on Page 18.
PATH-1 i8.
PHASE B isolation has occurred, so ALL RCPs will be secured.
AOP-018 actions WHEN at least 3 minutes have elapsed since tripping the affected RO RCP, THEN Close Sealleakoff Seal leakoff valve for RCP "C". C. (CVC-303C)
RO Check RCP "B" B or "C" C running. (NO)
RO Check RCP seal injection flow between 8 and 13 GPM. (YES)
RO Check FCV-626, THERM BAR FLOW CONT CO NT Valve CLOSED. (YES)
Continuous Action Step:
Check Check Thermal Barrier intact. (YES)
RO WHEN this procedure is completed, THEN Go To AOP-014, CCW SYSTEM SYSTEM MALFUNCTION.
RO Check APP-002-D2, CV ISOL PHASE B B extinguished. (NO)
SRO SRO Implement Implement EAL5. EALs.
Review Review ITS ITS for for applicable LCOs:
SRO SRO LCO 3.4.13, LCO 3.4.13, Condition Condition A A - Reduce
- Reduce leakage leakage to to within within limits limits within within 44 hrs.hrs.
Appendix Appendix D D NUREG-i021, NUREG-1021, Rev. Rev. 9, 9, Supp.
Supp. 11
Appendix D Operator Action Form ES-D-2 Op Test Op Test No.:
No.: 1 Scenario #
Scenario 11 Event #
Event 6,,_7_&_8
_6..... 7 & 8_ _ _ Page Page 18 18 of ....;2::.;9:.....-_
of 29 _---11 Event
Description:
Event
Description:
RCP "C" RCP C #2 Seal Seal fails, requiring requiring aa Reactor Reactor Trip.
Trip.
Break from S/Gs Steam Break S/Gs "B" and "C" B and C on the Reactor Reactor Trip.
Trip.
EDG "A"A fails to start on Safety Injection.
Time II Position I Applicants Actions or Behavior Applicant's BOOTH OPERATOR: Steam break for SIGs "8" 800TH B and "e" C are triggered to occur when the Reactor Trip 8reakers Breakers open. Verify steam break malfunction is inserted.
SRO Directs tripping the Reactor, tripping Rep RCP "enC and enters PATH-1.
PATH-i.
PATH-i actions PATH-1 Immediate Action Step:
RO Reactor Tripped. (YES)
Immediate Action Step:
BOP Turbine Tripped. (YES)
Immediate Action Step:
BOP energized (YES)
E-1 AND E-2 energized.
Immediate Action* Action Step:
NOTE: Phase B 8 isolation has occurred; the crew will stop ALL Reps RCPs due to a loss of RCP Rep cooling.
When Foldout A is addressed the crew may isolate SIGs S/Gs B "8" and "e" using Foldout A.
C SI will have to be reset prior to manipulating manipulating valves.
SRO Open Foldout A.
. RCP Rep Trip criteria. IF BOTH conditions are met, THEN stop all RCPs:
Reps: (NO) o0 SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF SI -
DELIVERING FLOW TO THE CORE o0 RCS Subcooling - << 35 degrees F [55 degrees F]
Appendix D D NUREG-1 021, Rev. 9, NUREG-iO2i, 9, Supp. 11
Appendix D D Operator Action Form ES-D-2 ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 1 Event #
Event 6, 7 & 8
_6;;;;.l.,..;.7...;;&;..;:8:.....-__ Page Page 19 19 of _2;;;;.,9 of 29_ _ _---i1 Event
Description:
Event
Description:
RCP "e" Rep Seal fails, requiring C, #2 Seal requiring aa Reactor Reactor Trip. Trip.
Steam Break Steam from S/Gs Break from S/Gs "B" B and and "e" C onon thethe Reactor Reactor Trip.
EDG "A" EDG A fails to start on Safety Safety Injection.
Injection.
Time II Position Position II Applicants Actions or Behavior Applicant's Behavior
- SI actuation criteria. IF EITHER condition occurs, THEN Actuate SI and Go To PATH-1,PATH-i, Entry Point A:
0o RCS Subcooling - << 35 degrees F [55 degrees F]
0o PZR Level-Level CAN NOT BE MAINTAINED>
- MAINTAINED > 10% [32%]
- MSR Isolation criteria. IF ANY Purge OR Shutoff Valve does NOT indicate fully closed, THEN place the associated RTGB Switch to CLOSE.
- S/G isolation criteria. IF both the following conditions are met, THEN perform the following:
- . Any S/GSIG pressure is decreasing in an uncontrolled manner OR
- . Any S/G has completely depressurized.
AND
- . At least ONE S/G SIG is intact.
o Reset SI.
0 o CLOSE the appropriate AFW isolation valves to the 0
faulted S/Gs AND OPEN the associated breaker for the valves closed.
- S/GSIG "B" B
- V2-14B, SDAFW PUMP DISCH, MCC-9, CMPT-- 1C CMPT
- a S/G "c" s
o WHEN the faulted S/Gs dry out, THEN dump steam 0
from intact S/G SIG to control RCS repressurization.
PATH-i actions PATH-1 RO Verify Phase A Isolation valves are closed. (YES)
BOP Verify FW Isolation valves are closed. (YES)
BOP Verify both FW pumps are tripped. (YES)
Appendix D D NUREG-i021, NUREG-1 021, Rev. 9, g, Supp. 11
Appendix 0D Operator Action Form ES-D-2 No.:
Op Test No.:
Op Scenario #
Scenario 11 Event #
Event 6, 77 &
6,
~~~----
& 88 Page Page 20 20 of of 29 29
~------~I Event
Description:
Event
Description:
RCP "e" Rep C, #2 Seal fails, requiring requiring aa Reactor Reactor Trip.
Break from S/Gs "B" Steam Break B and "e" C on the Reactor Reactor Trip.
EDG "A" A fails to start on Safety Injection.
Time II Position II Applicants Actions or Behavior Applicant's BOP Verify both MDAFW pumps are running. (YES)
NOTE: Crew may elect to reset 51 SI in order to control AFW and 5/G SIG levels.
BOP If additional Feedwater is required, start the SDAFW pump.
RO Verify 2 SI pumps running. (YES)
RD RO Verify Both RHR pumps running. (YES)
RD RO Verify SI valves are properly aligned. (YES)
RD RO At least 11 CCWCOW pump is running. (YES)
BOP All SW and SW Booster pumps running. (NO)
Attempt to start all SW and SW Booster pumps. (NO, SW Booster BOP Pump A "A" is unavailable)
BOP North OR South SW Header Lo Pressure alarm illuminated. (NO)
RD RO Verify CV Fans HVH-1, 2, 3, 4 running. (YES)
RD RO Verify IVSW initiated. (YES)
BOP Verify CV Ventilation isolation. (YES)
BOP Verify Control Room Vent aligned for Pressurization Mode. (YES)
Appendix D 0 NUREG..1 NUREG-1 021, 021, Rev. 9, Supp. 11
Appendix D Operator Action ESD-2 Form ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ## 11 Event #
Event 6, 7 & 8_ _ _ Page
_6;;,:,'..;..7..;;;;&~8 Page 21 21 of --=2:;;,9 of 29_ _ _-11
~-
Event
Description:
Event
Description:
RCP "C" RCP C #2 Seal Seal fails, requiring requiring aa Reactor Reactor Trip.
Steam Break Steam Break from S/Gs B and S/Gs "B" and "C" C on the Reactor Reactor Trip.
A fails to start on Safety Injection.
EDG "A" Time I Position I Applicants Actions or Behavior Applicant's BOP Verify both EDGs running. (NO)
NOTE: If requested to investigate what is wrong with the EDG, report that the EDG has tripped on OVERSPEED and you were unable to reset the fuel racks.
Continuous Action Step:
BOP Restart battery chargers within 30 minutes minutes of power loss using OP- OP 601.
Continuous Action Step:
RO CV Pressure has remained below 10 psig. (NO)
RO Verify CV Spray initiated. (YES)
RO Verify ALL CV Spray pumps running with valves aligned. (YES)
Verify approximately 12 12 GPM Spray additive tank flow. (Flow will be RO adjusted from - 30 GPM to 12 GPM)
RO Verify Phase B B isolation valves closed. (YES)
RO Stop ALL RCPs. (May be stopped previously)
Verify ALL MSIVs and MSIV bypasses closed. (YES, operator will take BOP MSIV switches to CLOSE)
BOP Locally open breaker for HVS-1 at MCC-5.
Appendix D D NUREG-1021, Rev. 9, Supp. 11 NUREG-1021,
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 11 Event ##
Event 6, 77 && 88 6, Page Page 22 22 of of 29 29
--.;...- ~~~---- ~------~I Event
Description:
Event
Description:
RCP "e" Rep C #2
- 2 Seal Seal fails, fails, requiring requiring aa Reactor Reactor Trip.
Trip.
Steam Break from Steam Break from S/Gs S/Gs "B"B and and "e" on the C on the Reactor Reactor Trip.
Trip.
EDG "A" EDG A fails fails to to start start onon Safety Safety Injection.
Injection.
Time Time I Position Position I Applicants Actions Applicant's Actions or or Behavior Behavior RCS pressure> 1350 RCS 1350 psig. [1250[1250 psig]
RO ** (YES, RCS RCS pressure is is> > 1250, skip the following 2 steps)
RO RCS Pressure Greater than 125 psig. (YES)
BOP At least 300 GPM AFW flow available. (YES)
BOP Verify AFW valves properly aligned.
BOP Control AFW flow to maintain SIG S/G levels between 8% [18%] and 50%.
RO RCP Thermal barrier cooling water HilLo Hi/Lo flow alarm illuminated. (YES)
RO At least one Charging Pump running. (YES)
BOP Place Steam Dump Mode Switch to Steam Pressure.
RO RCS Temp stable at OR trending to 547 degrees degrees F. F. (NO)
RO RCS temperature> 547 degrees F. (NO)
BOP BOP Attempt Attempt to to limit limit cooldown.
cooldown.
IF IF RCS RCS cooldown cool down continues continues and and is is NOT NOT duedue to SI flow, to SI flow, THEN THEN close close BOP BOP MSIVs MSIVs and and MSIV MSIV bypasses.
bypasses.
AppendixD Appendix D NUREG-1021, NUREG-1 021, Rev. Rev. 9,9, Supp.
Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 OpTestNo.:
Op Test No.: Scenario ##
Scenario 11 Event ##
Event 6, 77 && 88 6, Page Page 23 23 of of 29 29
-- ---------- --------~I Event
Description:
Event
Description:
Rcp "C" RCP c #2
- 2 Seal Seal fails, fails, requiring requiring aa Reactor Reactor Trip.
Trip.
Steam Break Steam Break from from S/Gs S/Gs "B" B and c and "C" onon the the Reactor Trip.
EDG "A" EDG A fails fails to to start start on on Safety Safety Injection.
Injection.
Time Time II Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior RO PZR PORVs closed. (YES)
PZR RO PZR Spray and Aux Spray valves closed. (YES)
RO At least 11 RCP running. (NO)
BOP Any S/G with uncontrolled depressurization. (YES)
RO Reset SPDS and initiate monitoring of CSFSTs.
SRO Go To EPP-11, FAULTED STEAM GENERATOR ISOLATION.
EPP-11 actions BOP Maintain At Least One S/G Available For RCS Cooldown.
BOP Any S/G pressure stable or increasing. (YES)
Any SIG S/G pressure decreasing in an uncontrolled manner OR any SIG S/G BOP completely depressurized. (YES)
Isolate faulted S/Gs using Supplement G, SIG S/G ISOLATION.
BOP (Supplement G G Steps are listed on pages 24-26)
Maintain A Faulted SIG S/G In The Isolated Condition During Subsequent BOP Recovery Actions Unless Needed For Cooldown.
BOP BOP Check Check CST CST levellevel greater greater than 10%. 10%. (YES)(YES)
BOP BOP Check Available Secondary Check Secondary Radiation Radiation Monitors Monitors normal.
normal. (YES)
(YES)
Appendix Appendix D D NUREG-1 NUREG-1 021, 021, Rev. 9, Supp.
Rev. 9, Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 11 Event ##
Event 6, 77 && 88 6, Page Page 24 24 of of 29 29
-- ~~~--- ~---~I Event
Description:
Event
Description:
- 2 Seal fails, requiring requiring aa Reactor Reactor Trip.
Trip.
Steam Break Steam from S/Gs Break from S/Gs "B" and "C" B and C on the Reactor on the Trip.
EDG "A" EDG A fails to start fails to start on Safety Injection.
on Safety Injection.
Time Time II Position Position I Applicants Actions Applicant's Actions or or Behavior Behavior CRITICAL TASK:
CRITICAL TASK: Isolate feedwater Isolate feedwater to to the the faulted faulted S/Gs using Foldout A OR SIGs using OR Supplement G prior to to transitioning transitioning to to PA PATH-i, TH-1, Entry Entry point C.
Check any S/G SIG with an uncontrolled level increase. (NO, Go To Path-RO 1, Entry Point C) (PATH-1 (PATH-i Steps continue on Page 28)
Supplement G, STEAM GENERATOR GENERATOR ISOLATION actions to isolate S/Gs "8" B and "e" C as faulted Steam Generators.
Go to the appropriate step from following table:
BOP ** SIG B to be isolated, Go To Step 18.
S/G
- S/G C to be isolated, Go To Step 34 34..
Check S/G "B" B faulted. (YES)
BOP Check S/G "c" C faulted. (YES)
Verify ViV1-3B,-3B, MSIV CLOSED. (YES)
BOP Vi -3C, MSIV CLOSED. (YES)
Verify V1-3C, Verify MS-353B, MSIV Vi -3B BYP CLOSED. (YES)
V1-3B BOP Verify MS-353C, MSIV Vi -3C BYP CLOSED. (YES)
V1-3C Verify FRV BB CLOSED. (YES)
BOP Verify FRV C C CLOSED. (YES)
Verify Verify FRV B B BYP BYP CLOSED. (YES)
BOP BOP Verify FRVFRV C C BYP BYP CLOSED. (YES) (YES)
Appendix Appendix D D NUREG-102 NUREG-1 021, 1, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix D Operator Action Form ES-D-2 Op Test Op Test No.:
No.: 1 Scenario #
Scenario 11 Event #
Event 6, 7 & 8_ _ _ Page
_6;.:.,...;..7...;;&:...;;8 Page 25 25 of .....:2~9 of 29_ _ _~1 Event
Description:
Event
Description:
RCP "e" Rep C#2 Seal fails,
- 2 Seal fails, requiring Reactor Trip.
requiring aa Reactor Steam Break Steam Break from S/Gs S!Gs "B" and "e" B and C on on the Reactor Reactor Trip.
EDO "A" EDG A fails to start on Safety Injection.
Time ~ Position II Applicants Actions or Behavior Applicant's V2-6B, FW HDR SECTION Valve CLOSED. (YES)
Verify V2-6S, BOP SOP Verify V2-6C, FW HDR SECTION Valve CLOSED. (YES)
V2-14B, SDAFW PUMP DISCH Valve CLOSED. (YES)
Verify V2-14S, BOP SOP Verify V2-14C, SDAFW PUMP DISCH Valve CLOSED. (YES)
Verify V2-16S, V2-16B, AFW HDR DISCH Valve CLOSED. (YES)
BOP SOP V2-1 6C, AFW HDR DISCH Valve CLOSED. (YES)
Verify V2-16C, BOP SOP Verify STEAM LINE PORVs CLOSED. (YES)
Verify V1-8S, Vi -8B, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)
BOP SOP Vi -8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)
Verify V1-8C, Verify S/Gs "S" B and "C" Blowdown and Slowdown C Slowdown Blowdown Sample Valve BOP SOP Status Light Indication CLOSED. (YES)
Dispatch an operator to the Pipe Jungle to close MS-29 and MS-38, BOP SOP SIG S/G B "S" and SIG "C" BYPASS S/G C SYPASS DRN and WARM.UP WARM-UP LINE TO AFW PUMP.
Check S/Gs B "S" and C"C" MSIV Above and Below Selow Seat Drain Valves B OP SOP CLOSED. (YES)
Appendix D D NUREG-i NUREG-1 02i, 021, Rev. 9, Supp. 11
Appendix D Operator Action Form ES-D-2 Op Test No.:
Op Test No.: 1 Scenario #
Scenario 11 Event #
Event _6;;,:,'...;..7...;;&~8~
6, 7 & 8 _ _ Page Page 26 26 of .....:2:;;9 of 29_ _ _-!1
~-
Event
Description:
Event
Description:
RCP "C" RCP Seal fails, requiring C #2 Seal Reactor Trip.
requiring aa Reactor Trip.
Steam Break Steam Break from S/GsS/Gs "B" B and and "C" C on the ReactorReactor Trip.
EDG "A"A fails to start on Safety Injection.
Time II Position II Annlicants Actions or Behavior Applicant's Dispatch an operator to E-1/E-2 E-l/E-2 Room to perform the following:
- . At MCC-9, verify V2-14B V2-i 4B and V2-16C V2-i 60 closed and open breakers 0o V2-14B, SDAFW PUMP TO S/G SIG B.
BOP 0o V2-16C, MDAFW PUMP HDR DISCH TO S/G C.
- . At MCC-6, verify V1-SB Vi -8B and V1-SC Vi -8C closed and open breakers 0o Vi-8B, SDAFW PUMP STEAM ISOLATION.
V1-SB, 0o Vi-80, SDAFW PUMP STEAM ISOLATION.
V1-SC, Dispatch operator to the Aux. Bldg. to perform the following:
- . MCC-i 0, verify V2-16B At MCC-10, V2-1 6B closed and open breaker V2-16B, V2-1 6B, BOP MDAFW PUMP HEADER DISCHARGE TO S/G SIG B.
- At MCC-10, MCC-i 0, verify V2-14C V2-i 4C closed and open breaker V2-i 4C, V2-14C, SDAFW PUMP TO S/G C.
BOP Check All Faulted and Ruptured S/Gs isolated. (YES)
WHEN the faulted S/Gs dry out, THEN dump steam from intact S/G to BOP control RCS repressurization.
BOP Check Any S/G ruptured. (NO)
SRO Return to procedure and step in effect.
Appendix D D NUREG-i NUREG-1 021, 021, Rev. 9, Supp. 11
Appendix 0D Appendix Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 11 Event ##
Event 9 & 10 O~_ _ Page
.....;9;;...&;;;....;..;1 Page 27 27 of of ...;2;;;.;9~
29 _ _--11 Event
Description:
Event
Description:
Loss of Loss of Off-Site Off-Site Power.
Power.
SW Pumps SW Pumps fail fail to to start start following following restoration restoration of of power.
power Time Time III Position Position II Applicant's ApIicants Actions Actions or or Behavior Behavior BOOTH OPERATOR:
BOOTH OPERATOR: After SIGs SIGs "B" B and and "C"C areare isolatedisolated and and at at the the discretion discretion of of thethe Chief Examiner, insert Chief Examiner, insert Events 99 and 10, Events 10, Loss of Off-Site Power with a failure of SW Pumps to restart.
The crew will continue in in PATH-1, PATH-i, but but will address components that did NOT restart using Supplement L: L:
ao Service Water Pump "C" C or "0" D to provide EDG cooling.
ao RHR Pump "B", B, HVH Units 3 & 4, SI Pump "C". C.
ao Charging Pump "c" C started OR FCV-626 opened to provide RCP Seal cooling.
lAW the note in PATH-1, PATH-i, the crew may choose to enter EPP-25, ENERGIZING SUPPLEMENTAL PLANT EQUIPMENT USING THE DSDG and start the OS DS Diesel following the loss of power.
Supplement L actions RO Verify Two SI Pumps RUNNING. (NO, will manually start SI Pump "C") C)
Verify Both RHR Pumps RUNNING. (NO, will manually start RHR RO Pump "B") B)
Verify ALL SW Pumps RUNNING. (NO, will manually start SW Pump BOP C OR "0")
"C" Verify CV RECIRC FANS RUNNING. (NO, will manually start HVH-3 RO and HVH-4)
HVH-4)
EPP-25 actions RO/BOP Check Desired Power Source DS OS Bus. (YES)
RO/BOP RO/BOP Check Check DS OS Bus Bus DEENERGIZED.
DEENERGIZED. (YES) (YES)
RO Check Check Any Any CCW Pump Pump RUNNING.
RUNNING. (YES) (YES)
SRO SRO Direct Direct Steps Steps 66 and and 77 of of EPP-25 EPP-25 be be performed performed to to start start the the DS OS Diesel.
Diesel.
Appendix Appendix D0 NUREG-1 021, NUREG-1 021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix DD Appendix Operator Action Operator Action Form Form ES-D-2 ES-D-2 No.:
Test No.:
Op Test Op Scenario Scenario ## 11 Event ##
Event 99 && 10 10
Page Page 28 28 of of 29 29
~I Event
Description:
Event
Description:
Loss of Loss Off-Site Power.
of Off-Site Power.
SW Pumps SW fail to Pumps fail to start start following following restoration restoration of power.
of power.
Time Time III Position Position I Arolicants Actions Applicant's or Behavior Actions or Behavior CRITICAL TASK:
CRITICAL TASK: Manually restart Manually restart a ServiceService Water Water Pump Pump to to provide cooling cooling to to the the only running EDG before damaging only damaging the the EDG.
PATH-i, Entry PATH-1, Entry Point Point CC Actions Reset SPDS and initiate monitoring of Critical Safety Function Status RO Trees.
Sf0 SRO Open Foldout B.
IF all conditions below occur, THEN Go To EPP-7, SI TERMINATION: TERMINATION:
- . RCS Subcooling > 35 degrees F [55 degrees F]
- . Heat Sink established as follows:
0o Total Feed flow to intact S/Gs S/Gs>> 300 GPM or 0.2x1066 PPH 0.2x10 OR 0o Level in at least one intact S/G greater than 8% [18%]
AND 0o Stable or Increasing
- PZR level greater than 10% [32%]
EPP-7 Actions SRO Open Foldout B.
SRO Check SW Header Pressure AND Transition To Step 5.
Continuous Action Step:
BOP Check Check DC Busses A "A" and B"B" energized. (YES)
Once SIGs B Once S/Gs "8" and C"C" have been isolated and and aa SW pump pump has has been started, the scenario may be terminated.
scenario may Appendix Appendix D D NUREG-102 NUREG-1021, 1, Rev.
Rev. 9, 9, Supp.
Supp. 11
HLC-O8 NRC HLC-08 NRC SCENARIO SCENARIO 11 TURNOVER TURNOVER SHEET SHEET POWER LEVEL:
POWER LEVEL: 68%, 17,000 MWD/MTU.
68%, 17,000 MWD/MTU.
Outage.
- Awaiting results Awaiting results of of post-outage post-outage testing.
testing.
BORON CONCENTRATION:
BORON CONCENTRATION: 106 106 ppm ppm EQUIPMENT UNDER EQUIPMENT UNDER CLEARANCE:
CLEARANCE:
oo LCO 3.7.7 3.7.7-A-A has been entered and is in hour hour 18 18 of a 72 TSAS.
o Expected return is within -18 hours.
Expected EQUIPMENT STATUS:
EQUIPMENT
- Main Turbine bearings #2, 3 and 4 vibration is elevated. All actions to inform station management have been performed.
INSTRUCTIONS FOR THE WATCH:
INSTRUCTIONS
- Maintain power at 68% RTP.
Appendix Appendix D 0 NUREG-1 021, NUREG-1 021, Rev.
Rev. 9, 9, Supp.
Supp. 11
I* Appendix D Scenario Outline Form ES-D-1 Facility:
Facility: HB ROBINSON HB ROBINSON Scenario No.:
Scenario No.: 33 Op Test No.:
Op No.:
Examiners:
Examiners: Operators: SRO - -
RO-RO BOP BOP-Initial Conditions: ** 7% BOL, 150 MWD/MTU, 1645 ppm Boron.
0o 3.7.7-A LCO 3.7.7 -A has been entered and is in hour 18 of a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement.
0o 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
Expected return is within -18
- Main Turbine Vibration for #2, 3 and 4 bearings is elevated.
Turnover: ** Continue with GP-005 to synchronize the Generator to the grid.
Critical Task: ** Manually trip the Reactor prior to transitioning out of AOP-001.
- Recognize that a SGTR has occurred and isolate the applicable S/G before transitioning to EPP-17.
Event MaIf. No.
Malf. Type*
Event Type* Event No. Description 1
1 (N) BOP, SRO Place the Generator Voltage Regulator in service.
2 (R) RO Inadvertent Turbine Trip with Power < < P-7.
(C) SRO 3 (C) BOP, SRO Service Water Pump "A" A breaker trips on overload.
4 (C) RO Low pressure on SI Accumulator "B". B.
(TS) SRO 5 (M) ALL Multiple dropped rods requiring a Reactor Trip.
6 (M) ALL S/G Tube Rupture on S/G C. "C".
(TS) SRO 7 (C) BOP "c" Safety fails 15% open.
S/G C 8 (C) RO Safety Injection Pump C "C" fails to start.
9 (C) BOP S/G Blowdown Sample valves fail to close.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix Appendix D D NUREG-1 021, NUREG-1 021, Rev. 9, 9, Supp.
Supp. 11
I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 3
SUMMARY
DESCRIPTION The crew will assume the watch with the plant at 7% Reactor Power, Power, with the Turbine rolling at 1800 RPM, but not synchronized to the grid. A Dedicated Operator (Surrogate) required by 1800 procedure, will be stationed for S/G level control. The previous shift identified increased vibration on Main Turbine bearing #3 during rollup and has taken all necessary actions to inform station management. Power was stabilized for shift turnover and to obtain vibration data on the Turbine. Service Water Booster Pump "A" A is under clearance for Motor Coupling Alignment.
Shift instructions are to continue with GP-OOS, GP-005, POWER OPERATION, to synchronize the Generator to the grid.
GP-005 to place the Generator Voltage Regulator in service in preparation to The crew will use GP-OOS synchronize the Generator to the grid. On cue from the Chief Examiner, the Turbine will inadvertently trip. The crew should respond lAW AOP-007, TURBINE TRIP BELOW P-7, by stabilizing Reactor Power at - 3%. During stabilization, the BOP will verify proper operation of the Condenser Steam Dumps. Following plant stabilization the Dedicated Operator will no longer be required and exit the simulator.
On cue from the Chief Examiner, Service Water Pump "A" A breaker will trip on overload. RTGB Annunciator APP-008-F4 will direct the operators to start a standby Service Water Pump. All of the actions will be directed from annunciators received during the Service Water pressure transient.
When Tech Specs are addressed, the Chief Examiner can cue a Low Pressure on SI B. The RO will reference APP-002-D4 and take action to repressurize the Accumulator "B".
Accumulator lAW OP-202. The SRO will enter LCO 3.S.1 3.5.1,, Condition C for the Low Pressure condition.
On cue from the Chief Examiner, all Control Bank C, Group 2 rods will drop. The SRO should PATH-i. On the Reactor trip, S/G "C" respond by directing a Reactor trip and enter PATH-1. C will develop 500 gpm tube rupture which will require a Safety Injection. On the Safety Injection, S/G "C" a SOO C 15% open and will not close, SI Pump "C" Safety Valve will fail 1S% C will fail to start, requiring the RO SIG "C" to start it manually, and S/G C Blowdown Sample valves will not close as expected.
The Chief Examiner may terminate the scenario at any time after all possible S/G isolation actions have been taken and the crew has transitioned to EPP-17.
EPP-i7.
Appendix D D NUREG-1 021, Rev. 9, Supp. 11
I Appendix 0D Scenario Outline Scenario Outline Form ES-D-1 Form ES-D-1 I HLC-08 NRC HLC-08 NRC SCENARIO SCENARIO 33 SIMULATOR SIMULATOR SETUP SETUP IC/SETUP:
- IC-603, SCN SON 006_Sim_3.
- SW Booster Pump "A" A is OFF, breaker OPEN and switch is RED CAPPED.
- Main Turbine Bearing #2 is OFFSET by 1.5, 1 .5, #3 by 2.3 and #4 by 1.7.
1 .7.
- Status board is correctly marked up for IC-3.
10-3.
- Provide candidates with a marked up (up to Step 8.4) copy of GP-005 to synchronize the Generator to the Grid.
PRE-LOADED EVENTS:
The following events should occur on the reactor trip:
- Event 8: SI Pump "c" C fails to start.
- Event 9: S/G Blowdown Sample valves fail to close.
EVENTSITRIGGERS INITIATED DURING THE SCENARIO:
- Event 2: Inadvertent Turbine Trip with Power < P-7.
- Event 3: SW Pump "A"A Breaker trips on overload.
- Event 4: Low pressure on SI Accumulator B. "B".
- Event 5: Multiple dropped rods requiring a Reactor Trip.
- Event 6: S!G S/G Tube Rupture on S/G C. "C".
- "c" Safety Valve fails 15%
Event 7: S/G C 15% open.
EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
GP-005, GP-005, Section 8.4; AOP-007; OP-202, Section 8.2.3; AOP-001; PATH-i; PATH-1; Foldout A; Supplement Supplement G;G; EPP-i EPP-11;1; PATH-2; Foldout Foldout C.
Appendix Appendix D 0 NUREG-i NUREG-1 021, 021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix D D Operator Action Operator Form ES-D-2 Form ESD-2 Test No.:
Op Test No.:
Op Scenario ##
Scenario 33 Event ##
Event _ 1 _ _ _ _ Page Page 44 of of _2=..:7 27_ _ _"",,1 Event
Description:
Event
Description:
Place the Place the Generator Generator VR VR inin service service and and synchronize synchronize the the Generator Generator toto the the grid.
grid.
Time II Position Position III Applicants Actions or Behavior Applicant's Behavior NOTE: The crew will brief Generator synchronization prior to entering the simulator. They will start with Step 8.4 of GP-OOS. GP-005.
SRO Inform the Load Dispatcher that the unit will be placed on the grid.
WHEN the turbine is at 1800 rpm, THEN close the Exciter Field BOP Breaker.
Place the Voltage Regulator in service:
- Slowly raise Generator volts to 22KV using the Manual Field Current Adjuster.
- . IIF F Generator voltage exceeds 22KV and the Exciter Field breaker has not tripped, THEN reduce voltage as soon as BOP possible.
- . Place the VOLTAGE REGULATOR in the TEST position.
- . Adjust Regulator Balance to zero using the VOLTAGE ADJUSTER.
- . Place the VOLTAGE REGULATOR in AUTO.
Place the MAIN GENERATOR synchroscope key switch in the GEN BOP NORTH position.
BOP Adjust the % DIFF VOLTS to zero using the VOLTAGE ADJUSTER.
Adjust Turbine speed so that the synchroscope is rotating SLOWLY SLOWLY in BOP the FAST direction. (Using Reference Setter, sets turbine speed to
...1802
-1802 RPM and depresses GO)
Verify TAVGT AVG is is at the high end of the 547°F to 551°F 551°F band and Reactor BOP BOP Power is is <.:s. 8%.
Appendix Appendix D D NUREG-1021, NUREG-1021, Rev. Rev. 9, 9, Supp.
Supp. 11
Appendix D Operator Action Form ES-D-2 Op Test No.: 1
.-;..._ Scenario # 3 Event # 1 Page 5 of 27
~-------- ~------~I Event
Description:
Place the Generator VR in service and synchronize the Generator to the grid.
Time I Position III Applicants Actions or Behavior Applicant's NOTE: The sequence of actions necessary to synchronize the unit to the grid is TIME CRITICAL. The RO, BOP and FW Operator shall verbally rehearse the actions of the following steps and coordinate their actions while synchronizing to the grid and loading the unit.
NOTE: Prior to the Generator output breaker being closed, insert Event 2, Inadvertent Turbine trip with Power < P-7.
Synchronize the Main Generator to the grid:
- . WHEN the synchroscope is rotating SLOWLY in the FAST direction and reaches the 5 minutes to 12 o'clock oclock position, THEN close the NORTH OCB BKR 52/9.
- . IF GLU and GLL remain closed, THEN within 30 seconds adjust Turbine load until GLU and GLL are off their closed seats. (Not to exceed 70 MWe)
BOP ** IF the Turbine cannot pick up at least 20 MWe, THEN reopen the OCB and inform the SSO and DO NOT CONTINUE.
- IF the unit is at 70 MWe and none of the GV closed lights are extinguished, THEN within the next 30 seconds:
o 0 Place Turbine Control in TURB MANUAL and use GV Down to shed load to minimum.
o 0 Verify Reactor Power is < < 10%.
o 0 Open the North OCB BKR 52/9.
Appendix D NUREG-1021, Rev. 9, Supp. 1 1
Appendix D Operator Action Form ES-D-2 Op Test No.:
Op Test No.: 1 Scenario #
Scenario 33 Event ##
Event 22 Page Page 66 of of 27 27
~------~I Event
Description:
Event
Description:
Inadvertent Turbine Trip with power Inadvertent power < P-7.
P-7.
Time II Position II Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 2, Inadvertent trip of the Turbine. (Ensure Reactor Power is below P-7)
EVENT INDICATIONS:
APP-008-B1; EH FLUID PMP AlB NB AUTO START APP-008-B2; EH FLUID SYSTEM HIILO HI/LO PRESS APP-008-C2; EH FLUID HI/LO-LO LEVEL APP-009-E2; GOV CAB MONITOR TROUBLE Turbine speed is decreasing and all Turbine valves indicate closed.
SRO Enters AOP-007, TURBINE TRIP BELOW P-7.
Check Turbine trip as follows:
- . Both Turbine Stop Valves closed (YES)
- . All Governor Valves Closed (YES)
RO/BOP Make PA announcement for AOP-007 entry.
Check Reactor Power less than 3%. (NO)
RO *
- Manually insert control rods or borate to reduce reactor power less than 3%.
NOTE: The crew will declare MODE 2 after going below 5% Reactor Power.
Check Turbine Oil system status:
- Turbine Bearing Oil Pressure> 6 psig. (YES)
BOP ** Turning Gear and Seal Oil Backup pumps running. (NO)
IF the Lube Oil system is intact, THEN start the Turning Gear and Seal Oil Backup pumps. (Will start Pumps using Manual switch)
Appendix D D NUREG-1 021, Rev. 9, Supp. 11 NUREG-1021,
Appendix D D Operator Action Operator Form ES-D-2 Form ES-D-2 Op Test Test No.:
No.:
Op Scenario ##
Scenario 33 Event ##
Event 22 Page Page 77 of of 27 27
~---~I Event
Description:
Event
Description:
Inadvertent Turbine Inadvertent Turbine Trip Trip with with power power << P-7.
P-7.
Time ~ Position Position I Applicants Actions or Behavior Applicant's Behavior Continuous Action Step:
Verify Bearing Oil Lift Pump running:
BOP BOP Check Turbine Check TurbIne Speed << 600 RPM. (NO) (NO)
WHEN Turbine Speed is is << 600 RPM, THEN verify Bearing Oil Lift Lift Pump is Pump is running.
Check North OCB BKR 52/9, South OCB BKR 52/8 and Exciter Field Breaker tripped. (NO, Exciter Field Breaker is still CLOSED)
BOP IF the Exciter Field Breaker has NOT tripped, THEN momentarily place the control switch in TRIP.
Check T AVG 547 of TAvG °F to 551°F.
551 °F.
(NO) IF Steam Dumps are available THEN:
RO/BOP
- . Adjust PC-464B to maintain 547-551 of. °F.
- . Verify Steam Dump Control switch is ON.
- . Verify Steam Dump Mode switch in Steam Press.
(YES) Continue with Step 8.
BOP Check 1 1 Main Condensate Pump AND 11 Feed Pump running. (YES)
BOP Maintain S/G levels 35 to 44% using FRV Bypass Valves.
Check PZR pressure between 2220 and 2250 PSIG. (YES)
RO IF pressure is << 2220, THEN Control Heaters and Spray valves to restore pressure to between 2220-2250.
RO Control Control Charging and Letdown to maintain maintain PZR level 22%.
-22%.
Determine if the Reactor should be shutdown:
Determine SRO SRO Check Check Reactor Power stable. (YES)
Appendix Appendix D D NUREG-1021, NUREG-1021, Rev. Rev. 9, 9, Supp.
Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 33 Event ##
Event 33 Page Page 88 of of 27 27
....;...- ~-------- ~------~I Event
Description:
Event
Description:
A trip.
Time Time I II Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior BOOTH OPERATOR:
BOOTH OPERATOR: When When directed directed by by the the Chief Chief Examiner, Examiner, insert insert Event Event 3, 3, Service Service Water Pump Water Pump "A" A trips trips on breaker overload.
on breaker overload.
EVENT INDICATIONS:
INDICATIONS:
APP-008-F4; SW APP-OOS-F4; PMP AlB/C/D SW PMP AIBICID OVLD OVLD APP-008-F7; SOUTH APP-OOS-F7; SOUTH SW SW HDR HDR LO LO PRESS PRESS APP-008-F8; NORTH APP-OOS-FS; NORTH SW SW HDR HDR LO LO PRESS PRESS APP-002-A8/B8/C81D8; HVH-1/2/3/4 APP-002-AS/BS/CS/DS; HVH-1121314 WTR OUTLET LO FLOW RO/BOP ROISOP Recognizes SW Pump "A" A has tripped and references APP-008-F4.
APP-008-F4 actions:
If an operating SW Pump has tripped, perform the following:
o 0 Start a standby pump. (Will start SW Pump "S" B or "D")
D)
0 Dispatch an operator to check breaker and current limiter fuses for SW Pump A - 480V Sus Bus E-1 E-1,, CMPT 20S.
20B.
o 0 Throttle CCW Heat Exchanger return valves to maintain header pressure at 40 - 50 psig.
Appendix Appendix D D NUREG-1 NUREG-1 021, 021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix DD Appendix Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test Test No.:
No.:
Op Scenario ##
Scenario 33 Event ##
Event 44
Page Page 99 of of 27 27
~I Event
Description:
Event
Description:
Low pressure Low pressure on on SI Accumulator "B".
SI Accumulator B.
Time Time II Position Position ~ Applicants Actions Applicant's Actions or or Behavior Behavior BOOTH OPERATOR:
800TH OPERATOR: When When directed directed by by the the Chief Chief Examiner, Examiner, insert insert Event Event 4, 4, Low Low pressure on pressure on SISI Accumulator Accumulator "8". B.
EVENT INDICATIONS:
EVENT INDICATIONS:
APP-002-D4; SI APP-002-D4; SI ACCUM ACCUM BB HI/LO HI/LO PRESS PRESS Decreasing Accumulator Decreasing Accumulator BB pressure pressure Recognizes that SI Accumulator "B" Recognizes B pressure pressure is decreasing slowly slowly and RO RO references APP-002-D4.
references APP-002-D4.
Reviews, briefs and directs Accumulator repressurization repressurization using OP- OP SRO 202, SAFETY INJECTION AND CONTAINMENT CONTAINMENT VESSEL SPRAY SYSTEM, Section 8.2.3.
RO Verify HIC-936, ACC VENT HDR FLOW CLOSED. (YES)
RO Verify SI-855, ACC NITROGEN ISOLATION OPEN. (YES)
RO OPEN Sl-853B, SI-853B, VENT.
WHEN the desired pressure is obtained, (Normal operating pressure is RO 630 PSIG) THEN close SI-853B. (APP-002-D (APP-002-D4 4 will clear)
Review ITSITS for applicable LCOs:
SRO SRO *
- LCO 3.5.1 3.5.1 - Condition C; C; Restore Accumulator to OPERABLE OPERABLE within within 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br />.
hours.
Appendix Appendix DD NUREG-102 NUREG-1 021, Rev. 9, 1, Rev. 9, Supp.
Supp. 11
Appendix DD Appendix Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 33 Event ##
Event 5, 6 5,6 Page Page 10 10 of of 27 27
~- ~~------ ~----~I Event
Description:
Event
Description:
Multiple dropped Multiple dropped rods rods requiring requiring aa Reactor Reactor Trip.
Trip.
S!G Tube S/G Rupture on Tube Rupture on S/G n S/G "CC.
- Time Time II Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior BOOTH OPERATOR:
BOOTH OPERATOR: When When directed directed by the Chief by the Chief Examiner, Examiner, insertinsert Event Event 5, 5, Multiple Multiple dropped rods. When dropped rods. When the reactor the reactor has has been been tripped, tripped, verify verify that that Event 6, Event SIG "C" 6, SIG Tube Rupture C Tube Rupture has has been been entered.
entered.
EVENT INDICATIONS:
EVENT INDICATIONS:
APP-005-F2; ROD APP-005-F2; ROD BOTTOM BOTTOM ROD DROP ROD DROP RBLs for RBLs for Control Control Bank Bank C, Group 22 are C, Group LIT are LIT Decreasing SUR Decreasing SUR Decreasing power.
Decreasing power.
Recognizes multiple dropped rods and performs Immediate actions of RO RO AOP-O01, MALFUNCTION AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM.
RO Check unexpected rod motion in progress. (NO)
RO/BOP Make PA Announceme Announcement nt for entry into AOP-001.
Determine if multiple rods have dropped:
- Prompt drop present. (YES)
- More than 1 1 RBL illuminated. (YES)
- More than 1 1 IRPI indicates on bottom. (YES)
RO Check Check multiple multiple dropped dropped rods present. (YES)
RO RO Check Reactor in Check in MODE MODE 11 or or 2.
- 2. (YES)
(YES)
SRO SRO Directs Directs tripping tripping thethe reactor reactor and and enters enters PATH-i.
PATH-1.
IMMEDIAT IMMEDIATE E ACTION ACTION STEP: STEP:
RO RO Reactor Reactor Tripped Tripped. (YES)
(YES)
Appendix Appendix DD NUREG-i NUREG-1 021,021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix D Operator Action Form ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 33 Event #
Event 5, 6 _ _ _ _ Page
_5;;.:"...;.6 Page 11 11 of of _2:;.;7 27_ _ _--11
~-
Event
Description:
Event
Description:
Multiple dropped Multiple dropped rods requiring aa Reactor rods requiring Reactor Trip.
S/G Tube Rupture S/G Rupture on SIG "C".
on S/G C.
Time III Position II Applicants Actions or Behavior Applicant's IMMEDIATE ACTION STEP:
BOP Turbine Tripped. (YES)
IMMEDIATE ACTION STEP:
BOP E-i AND E-2 energized. (YES)
E-1 IMMEDIATE ACTION STEP:
SI Initiation required. (NO)
CRITICAL TASK: Manually trip the Reactor prior to transitioning out of AOP-OO1. AOP-001.
RO Verify two Charging Pumps running.
SRO Transition to EPP-4, REACTOR TRIP RESPONSE.
Continuous Action Step:
Determine if procedure exit is warranted:
- Check attack on RNP site in progress. (NO)
- Check a total loss of SW OR Loss of Lake Robinson Dam ORLoss progress._(NO, integrity in progress. (NO, Go to Step Step_2) 2)
Continuous Action Step:
Check SI signal initiated. (NO, Go to Step 4)
RO IF SI initiation occurs during this procedure, THEN Go to PATH-i, PATH-1, Entry Point A.
Appendix D D NUREG-i021, NUREG-1021, Rev. 9, Supp. i1
Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6 _ _ _ _ Page
_5;.:,.,...;;,6 12 27_ _ _---11 of ...;2:;;.:7 Event
Description:
Multiple dropped rods requiring a Reactor Trip.
SIG "e".
S/G Tube Rupture on S/G C.
Time III Position III Applicant's Actions or Behavior Arlicants SRO Reset SPDS and initiate monitoring of CSFSTs.
CREW Open Foldout A.
- . criteria, IF BOTH conditions are met, THEN stop all RCP Trip criteria.
RCPs: (NO)
RO 0o SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0o RCS Subcooling - < 35 degrees F [55 degrees F]
- . SI actuation criteria. IF EITHER condition occurs, THEN Actuate SI and Go To PATH-1, PATH-i, Entry Point A: (YES)
SRO/RO 0o RCS Subcooling - < - < 35 degrees F [55 degrees F]
0o Level CAN NOT BE MAINTAINED> 10% [32%].
PZR Level- -
- . MSR Isolation criteria. IF ANY Purge OR Shutoff Valve does BOP not indicate fully closed, THEN place the associated RTGB Switch to CLOSE.
SRO Direct a manual SI and Transition to PATH-1, PATH-i, Entry Point A.
Appendix D D NUREG-i 021, Rev. 9, Supp. 11 NUREG-1
Appendix 0D Operator Action Form ES-D-2 Op Test Op Test No.:
No.: 1 Scenario #
Scenario 33 Event #
Event _7~'...;;.8~,
7, 8, &;.;...9~
& 9 _ _ Page Page 13 13 of .....:2:..;.7 of 27_ _ _-11
~-
Event
Description:
Event
Description:
Sf0 "C" S/G C Safety Safety Valve fails open. Safety Safety Injection Injection Pump Pump "C" C fails to start.
5/0 Blowdown S/G Blowdown Sample Sample valves fail to close.
Time II Position II Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When the crew actuates Safety Injection, verify Events 7,8 7, 8 and 9 are inserted.
NOTE: When radiation alarm R-19C is received, the CRSS may direct a member of the crew to take actions lAW AOP-005, RADIATION MONITORING SYSTEM.
The actions taken lAW AOP-005 are listed on Page 26 at the back of the exercise guide.
PATH-i actions continue below.
PATH-1 CREW Open Foldout A. (nothing additional to address)
Verify Phase A Isolation valves are closed. (NO, crew will direct local RO isolation of FCV FCV-1 935NB, S/G Blowdown Sample valves)
-1935A1B, BOP Verify FW Isolation valves are closed. (YES)
BOP Verify both FW pumps are tripped. (YES)
BOP Verify both MDAFW pumps are running. (YES)
BOP If additional Feedwater is required, start the SDAFW pump.
RD RO Verify 2 SI pumps running. (NO, "c" C will be manually started)
RO Verify Both RHR pumps running. (YES)
RO Verify SI valves are properly aligned. (YES)
RD RO At least 11 CCW pump is running. (YES)
Appendix D 0 NUREG-1 021,021, Rev. 9, Supp. 11
Appendix 0D Operator Action Operator Form ES-D-2 Form ES-D-2 Op Test No.:
Op Test No.: --.;.....-
Scenario ##
Scenario 33 Event ##
Event 7, 8, & 9 7,8,&9 Page Page 14 14 of of 27 27
~~~---- ~------~I Event
Description:
Event
Description:
S/G c Safety S!G "C" Safety Valve Valve fails fails open.
open. Safety Safety Injection Injection Pump Pump "C" C fails fails to to start.
start.
S/G Blowdown Sample S!G Blowdown Sample valves valves fail fail to to close.
close.
Time III Position Position i Applicants Actions or Behavior Applicant's Behavior BOP All SW and SW Booster pumps running. (NO)
Attempt to start all SW and SW booster pumps. (NO, SW Booster BOP Pump "A"A is unavailable and SW Pump "A" A is tripped)
BOP North OR South SW Header Lo Pressure alarm illuminated. (NO)
RO Verify CV Fans HVH-1, 2, 3, 4 running. (YES)
RO Verify IVSW System Initiated. (YES)
RO Verify CV Ventilation isolation. (YES)
BOP Verify Control Room Vent aligned for Pressurization Mode. (YES)
BOP Verify both EDGs running. (YES)
CONTINUOUS ACTION STEP:
BOP Restart battery chargers within 30 minutes of power loss using OP OP-601.
CONTINUOUS ACTION STEP:
RO CV Pressure has remained below 10 10 psig. (YES)
RO Automatic Steam Line Isolation Isolation initiated.
initiated. (NO)
RO Automatic Steam Line Isolation Isolation required. (NO)
Appendix Appendix D 0 NUREG-1021, NUREG-1 021, Rev. Rev. 9, 9, Supp.
Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 33 Event ##
Event 7, 8, &;.;..9~
& 9 _ _ Page
_7;":"..;;.8:..;' Page 15 15 of ....;2:.;,.7 of 27_ _ _-i1 Event
Description:
Event
Description:
SIG "C" S/G C Safety Safety Valve fails open.
Valve fails Safety Injection open. Safety Injection PumpPump "C" C fails fails to to start.
start.
SIG Blowdown S/G Blowdown Sample Sample valves valves fail fail to close.
to close.
Time Time II Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior SRO SRO Locally open locally breaker for open breaker for HVS-1 HVS-1 at at MCC-5.
MCC-5.
P0 RO RCS pressure> 1350 1350 psig. [1250 psig] (YES)
BOP At least 300 GPM AFW flow available. (YES)
BOP Verify AFW valves properly aligned.
BOP Control AFW flow to maintain S/G SIG levels between 8% [18%] and 50%.
RO RCP Thermal barrier cooling water Hillo Hi/Lo flow alarms illuminated. (NO)
BOP Place Steam Dump Mode Switch to Steam Pressure.
RO RCS Temp stable at OR trending to 547 degrees F. (NO)
P0 RO RCS temperature> 547 degrees F. (NO)
RO Attempt to limit cooldown.
IfIf RCS cooldown continues and is not due due to SI flow, then close MSIVs RO and MSIV bypasses.
RO RO PZR PZR SpraySpray andand Aux Spray valves closed.
Aux Spray closed. (YES)
(YES)
P0 RO At At least RCP running.
least 11 RCP running. (YES)
(YES)
Appendix Appendix D D NUREG-1 NUREG-1 021,021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 33 Event ##
Event 7, 8, &;;...;9~& 9 _ _ Page
_7;..:.,...;;.8:..;, Page 16 16 ofof .....;2;;.;.7 27_ _ _-11 Event
Description:
Event
Description:
SIG "C" S/G C Safety Valve fails Safety Valve fails open. Safety Injection open. Safety Injection Pump Pump "C" C fails fails to to start.
start.
SIG Slowdown S/G Blowdown Sample Sample valves valves fail fail to to close.
close.
Time Time II Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior RD RO At least At least 11 SI SI Pump Pump Running.
Running. (YES) (YES)
RO RCS Subcooling less than 35 35 degrees degrees F [55]. [55]. (NO)
BOP Any S/G with uncontrolled depressurization. (YES)
RD RO Reset SPDS and initiate monitoring of CSFSTs.
SRO Transition to EPP-11, FAULTED SIG ISOLATION.
BOP Maintain At Least One S/G Available For RCS Cooldown.
BOP SIG pressure stable or increasing. (YES)
Any S/G Any S/G pressure decreasing in an uncontrolled manner OR any S/G BOP completely depressurized. (YES)
Isolate faulted S/G using Supplement G, S/G ISOLATION.
BOP (Supplement G G Steps are listed on Pages 22-25)
Maintain A Faulted SIG S/G In The Isolated Condition During Subsequent BOP Recovery Actions Unless Needed For Cooldown.
BOP Check CST level greater than 10%. 10%. (YES)
BOP Check Available Secondary Secondary Radiation Monitors Monitors normal.
normal. (NO) (NO)
SRO SRO Transition Transition to PATH-2, Entry Entry Point Point J. J.
RO RO Reset Reset SPDS SPDS and and initiate initiate monitoring monitoring of of CSFSTs.
Appendix Appendix D D NUREG-1021, NUREG-1021, Rev. Rev. 9, 9, Supp.
Supp. 11
Appendix D Operator Action Form ES-D-2 Op Test Op Test No.:
No.: Scenario ##
Scenario 3 Event ##
Event 7, 8, &;;;..9~__
&9
_7;...l"...;,8...,;, Page Page 17 17 of _2;;.;7 of 27_ _ _----l1
~-
Event
Description:
Event
Description:
SIG "c" S/G c Safety Safety Valve Valve fails open.
open. Safety Safety Injection Pump "c" Injection Pump c fails fails to to start.
start.
SIG Blowdown S/G Blowdown Sample Sample valves fail to close.
close.
Time II Position II Applicants Actions or Behavior Applicant's CREW Open Foldout C.
WHEN below 10- 10b0 10 amps, THEN energize Source Range detectors RO and monitor recorder.
BOP Request periodic activity samples of all S/Gs BOP Place Steam Dump Mode Switch to Steam Pressure.
BOP QCV-1 Open QCV 0426, Bypass Condensate Polishers.
-10426, BOP Close C-48A and 48B to isolate Hotwell Return to CST.
RO At Least 1 1 RCP running. (YES)
RO At Least 1 1 SI pump running. (YES)
P0 RO RCS Subcooling less than 35 degrees F. [55] (NO)
BOP Ruptured SIG S/G identified. (YES)
RD RO Maintain at least 11 S/G SIG available for RCS Cooldown.
Verify ruptured steam line PORV setpoint at 1035 1035 psig using status BOP board.
P0 RO I Verify RCS temperature << 547 degrees FF prior to MSIV closure.
Appendix D D NUREG-1021, NUREG-1 021, Rev. 9, Supp. 11
Appendix 0D Operator Action Form ES-D-2 Op Test No.:
No.: Scenario #
Op Scenario 3 Event #
Event 7, 8, & 9 7,8,&9
~~~----
Page Page 18 18 of of 27 27
~I Event
Description:
Event
Description:
S/G "C" Safety Valve fails open.
C Safety open. Safety Safety Injection Injection Pump Pump "C" start.
C fails to start.
Blowdown Sample S/G Blowdown Sample valves fail to close.
Time ~ Position II Applicants Actions or Behavior Applicant's RD RO Close ruptured S/G MSIV and MSIV Bypass.
RO Ruptured S/G MSIV and MSIV bypass closed. (YES)
Continuous Action Step:
RD RO WHEN ruptured S/G pressure decreases below 1035 psig, THEN verify ruptured Steam Line PORV closed.
RD IF MDAFW pump is not available, THEN maintain at least 1 1 S/G RO supply to SDAFW pump.
CREW Close ruptured S/G SIG steam shutoff to SDAFW pump.
BOP Verify S/G Blowdown Isolation and Sample Valves Closed.
Locally close warmup steam supply from ruptured S/G to SDAFW BOP pump.
BOP Locally close above and below seat drains from ruptured S/G.
Isolate Feed Flow to any ruptured SIG S/G that is faulted unless needed BOP for RCS cooldown.
CRITICAL TASK: Recognize that a Steam Generator Tube Rupture has occurred and isolate the affected SIG before transitioning to EPP-17.
Appendix D 0 NUREG-1 021, Rev. 9, Supp. 11 NUREG-1
Appendix 0D Operator Action ES-D-2 Form ES-O-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 3 Event #
Event _7;":"...;.8':...;&;.;..;9~
7, 8, & 9 _ _ Page Page 19 19 of _2;;;.;7 of 27_ _ _--11 Event
Description:
Event
Description:
S/G "C" S/G Safety Valve C Safety Valve fails open.
open. Safety Safety Injection Injection Pump Pump "C" to start.
C fails to start.
S/G Blowdown S/G Blowdown Sample Sample valves fail to close.
close.
Time III Position III ApIicants Actions or Behavior Applicant's Continuous Action Step:
BOP ruptured S/G level is greater than 8% [18%], THEN isolate WHEN ruptured Feed Flow.
Continuous Action Step:
BOP Open breakers for V1-8, Vi -8, V2-14 V2-1 4 and V2-16 V2-1 6 valve closed to isolate SIG.
ruptured S/G.
Control Feed Flow to maintain intact S/G level between 8% [18%] and BOP 50%.
BOP Any other S/GSIG with uncontrolled level increase. (NO)
Open at least one PORV block unless closed to isolate an open RO PORV.
IF PORV opens on high pressure, THEN verify reclosure at or below RO 2335 PSIG, close PORV blocks as necessary.
IF offsite power is lost, THEN restart emergency safeguards CREW equipment.
RO Reset Phase A and Phase B.
Appendix D0 NUREG-1 021, Rev. 9, Supp. 11
Appendix D Appendix D Operator Action Operator Action Form ES-D-2 Form ES-D-2 Op Test No.:
Op Test No.: 1
-.;..._ Scenario ##
Scenario 33 Event ##
Event 7, 8, && 99 7,8, Page Page 20 20 of of 27 27
~~~---- ~------~I Event
Description:
Event
Description:
S/G "C" S/G C Safety Safety Valve Valve fails fails open.
open. Safety Safety Injection Injection Pump Pump "C" C fails fails to to start.
start.
S/G Blowdown S/G Blowdown Sample Sample valves valves fail fail to to close.
close.
Time ~ Position Position II Applicants Actions or Behavior Applicant's Behavior Establish Instrument Air to CV. IF compressor NOT running, running THEN RO start compressor.
BOP All AC Busses energized by offsite power. (YES)
IF RCS pressure decreases below 275 PSIG, PSG, THEN restart RHR RO Pumps.
BOP Ruptured S/G isolated. (YES, completed during Supplement G)
BOP Ruptured S/G pressure> 220 PSIG. (YES)
BOP At least one intact S/G available for RCS cooldown. (YES)
Sf0 SRO Determine required core exit temperature from Table 3.
WHEN PZR press decreases to << 2000 PSIG, THEN block PZR RO Pressure/Hi Steam Line SI signals.
RO IF RCPs are NOT running, THEN do NOT monitor CSF-4.
BOP Condenser available for Steam Dump. (YES)
Verify TAVG T AVG << 543 degrees F F AND block TAvG T AVG SI signal prior to RO maximum steam dump.
BOP BOP Dump Dump steam from intact S/G S/G to condenser at maximum rate.
RO Align Charging Charging Pump Pump suction suction to RWST.
Appendix Appendix D D NUREG-1 NUREG-1 021,021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix D Operator Action Form ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 33 Event ##
Event 7, 8, &;,;..9=.....-_
&9
_7;...l"..;.8.:...;, Page
_ Page 21 21 of 27_ _ _---i1 of ....;2:;.;7 Event
Description:
Event
Description:
SIG "C" S/G Safety Valve C Safety Valve fails fails open.
open. Safety Safety Injection Injection Pump Pump "C" C fails fails to to start.
start.
SIG Blowdown S/G Blowdown Sample Sample valves valves fail fail to to close.
close.
Time II Position Position II Applicants Actions or Applicant's or Behavior Behavior RO Establish Charging flow to maintain PZR level. level.
RO Core Exit Temperature less than required temperature. (YES)
BOP Reduce Steam flow to stabilize RCS temperature.
CREW Allow RCS temperature to stabilize from cooldown prior to continuing.
BOP Ruptured S/GSIG pressure stable or increasing. (NO)
Ruptured S/GSIG pressure decreases to << 250 PSIG above pressure of BOP intact S/G used for cooldown. (YES)
Transition to EPP-17, SGTR WITH LOSS OF REACTOR RO SRO COOLANT: SUBCOOLED RECOVERY.
At the discretion of the Chief Examiner, when the crew has transitioned to EPP-17 and SIG "C" S/G C has been isolated as a faulted and ruptured S/G, SIG, the scenario may be terminated.
Appendix D D NUREG-1 NUREG-1 021, Rev. 9, Supp. 11
Appendix D Operator Action Form ES-D-2 Op Test Op Test No.:
No.:
Event
Description:
Event
Description:
1 Scenario ##
Scenario S!G "C" S/G C Safety 33 Safety Valve Event #
Event Valve fails open.
_7;....,
open. Safety 8, &;.;..9~
7,*..;;.8l,..;'
Safety Injection
& 9 _ _ Page Injection Pump Page Pump "C" fails to C fails 22 22 to start.
of .....:2=.;.,7 of start.
27_ _ _-11 S!G Blowdown S/G Blowdown Sample Sample valves fail to close.
close.
Time II Position ~fi Acolicants Actions or Behavior Applicant's Supplement G, STEAM GENERATOR ISOLATION, Actions (to isolate SIGS/G "C" C as a faulted SIG AND to isolate SIG S/G "C" C as a ruptured S/G)
Go to the appropriate step from following table:
- isolated, Go To Step 34 S/G C to be isolated. 34..
BOP Check S/G "c" C faulted. (YES)
BOP Vi -3C, MSIV CLOSED. (YES)
Verify V1-3C, BOP Verify MS-353C, MSIV V1-3C Vl-3C BYP CLOSED. (YES)
BOP Verify FRV C CLOSED. (YES)
BOP Verify FRV C BYP CLOSED .(YES)
BOP Verify V2-6C, FW HDR SECTION Valve CLOSED. (YES)
BOP Verify V2-14C, SDAFW PUMP DISCH Valve CLOSED. (YES)
BOP Verify V2-1 V2-16C,6C, AFW HDR DISCH Valve CLOSED. (YES)
BOP Verify STEAM LINE PORV CLOSED. (YES)
BOP Verify Vi -8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)
V1-8C, Verify S/G C"C" Blowdown and Blowdown Sample Valve Status Light BOP Indication CLOSED. (NO)
Appendix D D NUREG-1021, NUREG-1 021, Rev. 9, Supp. 11
Appendix D D Operator Action Operator Form ES-D-2 Form ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 33 Event ##
Event 7,*....;;.8:....;.
_7;..:. 8, &;;..;9~
& 9 _ _ Page Page 23 23 of .....:2;;.;.,7 of 27_ _ _....,1 Event
Description:
Event
Description:
S!G "C" S/G Safety Valve C Safety Valve fails fails open.
open. Safety Safety Injection Injection Pump Pump "C" C fails fails to to start.
start.
S/G Blowdown Sample S/G Blowdown Sample valves valves fail fail to to close.
close.
Time II Position Position III Applicants Actions or Behavior Applicant's Behavior Deenergize R-19C. R-1 9C. (May have already been performed lAW AOP-OOS) AOP-005)
IF S/G "c" C Blowdown and Sample valves fail to close, THEN close:
BOP ** SGB-56C, SGBD HX "c" SGB-S6C, C BYPASS/HX FLOW CONTROL ISOLATION.
- SGB-60C, SGBD LINE "c" C TO WLU SYSTEM.
- SGB-38, S/G "c" C SAMPLE FLOW ISOLATION.
Dispatch an operator to the Pipe Jungle to close MS-38, S/G "c" C BOP BYPASS DRN and WARM-UP LINE TO AFW PUMP.
Check S/G C MSIV Above and Below Seat Drain Valves CLOSED.
BOP (YES)
Dispatch an operator to E-1/E-2 E-1IE-2 Room to perform the following:
- At MCC-6, verify Vi -8C closed and open breaker Vi V1-8C V1-8C, -8C, SDAFW PUMP STEAM ISOLATION.
Dispatch operator to the Aux. Bldg. to perform the following:
BOP ** At MCC-1O, MCC-10, verify V2-14C closed and open breaker V2-14C, SDAFW PUMP HEADER DISCHARGE TO S/G C.
BOP Check All Faulted and Ruptured S/Gs ISOLATED. (NO, Go Go To Step 1) 1)
Go Go to the appropriate step from following table:
BOP BOP
- S/G C C to be isolated, Go Go To Step 34.
Appendix Appendix D D NUREG-iO2i, NUREG-1 021, Rev.Rev. 9, 9, Supp.
Supp. 11
Appendix D Operator Action Form ES-D-2 Op Test Op Test No.:
No.: 1 Scenario #
Scenario 33 Event ##
Event 7, 8, & 9
_7;...:.,.;;;..8,:....;;&;.;..;9:......-_ Page
_ Page 24 24 of ....;2;;.;.7 of 27_ _ _...,1 Event
Description:
Event
Description:
S/G "C"C Safety Valve fails open. Safety Safety InjectionInjection Pump Pump "C" C fails to start.
SIG Blowdown S/G Blowdown Sample Sample valves fail to close.
Time II Position III Applicants Actions or Behavior Applicant's Check S/G SIG "C" C faulted. (NO)
BOP Verify ruptured Steam Line PORV setpoint at 1035 PSIG using Status Board.
BOP Vi -8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)
Verify V1-8C, Verify S/GSIG C Blowdown and Blowdown Sample Valve Status Light BOP Indication CLOSED. (NO)
Deenergize R-19C.
SIG "C" IF S/G C Blowdown and Sample valves fail to close, THEN close:
BOP ** SGB-56C, SGBD HX "C" C BYPASS/HX FLOW CONTROL ISOLATION.
- SGB-60C, SGBD LINE "C" C TO WLU SYSTEM.
- SGB-38, S/GSIG "C" C SAMPLE FLOW ISOLATION.
Dispatch an operator to the Pipe Jungle to close MS-38, S/G "C" C BOP BYPASS DRN and WARM-UP LINE TO AFW PUMP.
Check S/G C MSIV Above and Below Seat Drain Valves CLOSED.
BOP (YES)
Dispatch an operator to E-1/E-2 E-1IE-2 Room to perform the following:
- At MCC-6, verify Vi V1-8C-SC closed and open breaker Vi V1-8C, -SC, SDAFW PUMP STEAM ISOLATION.
Appendix D D NUREG-i NUREG-1 021, 021, Rev. 9, Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 33 Event ##
Event 7, 8, 7, 8, && 99 Page Page 25 25 ofof 27 27
~~~--- --------~I Event
Description:
Event
Description:
SIG "C" S/G C Safety Valve fails Safety Valve fails open.
open. Safety Safety Injection Injection Pump Pump "C" C fails fails to to start.
start.
SIG Blowdown S/G Blowdown Sample Sample valves valves fail fail to to close.
close.
I[ Time Time II Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior Dispatch operator Dispatch operator to to the Aux. Bldg.
the Aux. Bldg. toto perform perform the the following:
following:
BOP ** MOO-jo, verify V2-14C closed and open breaker V2-14C, At MCC-10, SDAFW PUMP HEADER HEADER DISCHARGE TO S/G SIG C.
BOP BOP Check All Check All Faulted Faulted and Ruptured Ruptured S/Gs ISOLATED. ISOLATED. (YES) (YES)
WHEN the faulted S/Gs dry out, THEN dump steam from intact S/G SIG to BOP control RCS repressurization.
BOP Check Any S/G RUPTURED. (YES)
Perform the following to minimize Secondary system contamination:
- Use Auxiliary boilers for auxiliary steam.
- Bypass the condensate polishers.
- Verify hotwell return to CST isolated:
o 0 Locally verify O-48A C-48A and C-48B CLOSED.
Dispatch an operator to close GS-36, MANUAL GLAND STEAM SRO/BOP DUMP.
SRO Return to procedure and step in effect.
Appendix Appendix DD NUREG-1021, NUREG-1021 , Rev. Rev. 9, 9, Supp.
Supp. 11
Appendix D Appendix D Operator Action Operator Action Form ES-D-2 Form ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 33 Event ##
Event Page Page 26 26 of of 27 27
-- ---------- --------~I Event
Description:
Event
Description:
AOP-005 actions AOP-005 actions for for R-19C R-1 9C alarm.
alarm.
Time Time III Position Position ~ Applicant's Applicants Actions Actions or or Behavior Behavior AOP-005 Actions AOP-005 Actions BOP BOP Makes announcement for AOP-005 entry and Goes Goes to Attachment 20.
S/G "C" Verify S/G C Blowdown Blowdown AND BlowdownBlowdown Sample Sample Valves CLOSED.
CLOSED.
BOP BOP (NO)
Deenergize R-19C.R-1 9C. (Directs the AO AC to Push the Power Switch located BOP in R-19C R-1 9C Cabinet bottom right)
IF S/G "C"C Blowdown and Sample isolation valves fail to close, THEN close:
- SGB-60C, SGB60C, SGBD LINE "C" C TO WLU SYSTEM.
- SGB-38, S/G "C" C SAMPLE FLOW ISOLATION.
(BOP will contact the AO and direct closing of the above valves)
Verify FCV-4204C, SG "C" C BLOWDOWN FLOW RATE CONTROL Valve CLOSED. (IF NO, THEN Close SGB-65C, FCV-4204C INLET)
BOP (BOP will contact the AC AO and direct closing of the above valve)
Check R-19R-1 9 Radiation Monitors Monitor's HIGH ALARM ALL ILLUMINATED.
BOP (NO. Go (NO, To Step 6) 6)
Check SGTR OR AOP-035 IN PROGRESS. (YES, Return to BOP Procedure And Step In In Effect)
Appendix Appendix D D NUREG-1 NUREG-1 021,021, Rev. 9, Supp.
Rev. 9, Supp. 11
HLC-08 NRC HLC-08 NRC SCENARIO SCENARIO 33 TURNOVER TURNOVER SHEETSHEET POWER LEVEL:
POWER LEVEL: 7%7% BOL, BOL, 150 150 MWD/MTU.
MWD/MTU.
BORON CONCENTRATION:
BORON CONCENTRATION: 1645 1645 ppmppm EQUIPMENT UNDER EQUIPMENT UNDER CLEARANCE:
CLEARANCE:
- SW Booster SW Booster Pump Pump "A" A is is out out of of service service and and under under clearance clearance for for Motor Motor Coupling Coupling Alignment.
Alignment.
oo LCO 3.7.7-A LCO 3.7.7-A has has been been entered entered and and is in hour is in hour 18 18 of of aa 72 72 Action Action Statement.
Statement.
oo Expected return Expected return isis within -18 1 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
hours.
EQUIPMENT STATUS:
EQUIPMENT
- Main Turbine bearings #2, 3 and 4 vibration is elevated. All actions to inform station management have been performed.
INSTRUCTIONS FOR THE WATCH:
INSTRUCTIONS
- Continue with GP-005 and synchronize the Generator to the Grid.
Appendix Appendix DD NUREG-1 NUREG-1021, 021, Rev.
Rev. 9,9, Supp.
Supp. 11
II Appendix D Scenario Outline Form ES-D-1 Facility: HB ROBINSON Scenario No.: 4 Op Test No.:
Examiners: Operators: SRO - -
RO-RO BOP BOP-Initial Conditions: ** 50% BOL, 150 MWD/MTU, 1306 ppm Boron.
0o 3.7.7-A LCO 3.7.7 -A has been entered and is in hour 18 of a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement.
0o Expected return is within -18 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
- Main Turbine Vibration for #2, 3 and 4 bearings is elevated.
Turnover: ** Returning to RTP following a Maintenance Outage. Increase power to 75%.
Critical Task: ** Manually initiate SI to provide injection flow from at least 11 SI Pump before Reactor Vessel level reaches 41 41% RVLIS indication.
% by Full Range RVLlS
- Ensure that ALL Phase A valves are closed upon receipt of a valid actuation signal prior to completion of Grid Location B-9 (SI Flow Verified).
Event Malf.
MaIf. Type*
Event Type* Event No. No. Description 1
1 (R) RO Increase power to 75% RTP.
(N) SRO, BOP 2 (TS) SRO Loop 11 T HOT Fails Low.
THQT 3 (C) BOP, SRO SW flooding from the South SW Header.
(TS) SRO 4 (C) RO, SRO PZR PORV PCV-456 fails 70% open.
(TS) SRO 5 (C) BOP, SRO HCV-1 459, Heater Bypass Valve fails OPEN.
HCV-1459, 6 (M) ALL High vibration on #3 Turbine bearing which leads to a manual Reactor trip.
7 (M) ALL Failure of the Reactor to trip. (ATWS) SDAFW Pump trips.
8 (M) ALL Small Break LOCA.
9 (C) RO Phase A fails to automatically actuate and several valves fail to automatically close.
10 (C) RO Safety Injection fails to automatically actuate.
11 11 (C) BOP Control Room HVAC Train A and Train B fail to automatically (HVE-1 9A fails to start and HVE-16 actuate. (HVE-19A HVE-1 6 fails to stop)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D D NUREG-1 NUREG-1021,021, Rev. 9, Supp. 1 1
II Appendix DD Scenario Outline Scenario Outline Form ES-D-1 Form ES-D-1 HLC-08 NRC HLC-08 NRC SCENARIO SCENARIO 4
SUMMARY
SUMMARY
DESCRIPTION DESCRIPTION crew will assume The crew assume the watch with the plant plant at at 50% RTP.
RTP. The previous previous shift identified identified increased vibration on Main increased Main Turbine bearing bearing #3 and has has taken all all necessary necessary actionsactions to inform inform station management. Service Water Booster Pump "A" A is under clearance for Motor Coupling Alignment. Shift instructions are to increase power to 75% and hold for Reactor Engineering instructions.
On cue from the Chief Examiner, Loop 11 T HOT will fail low. The crew will respond lAW APP-003-THOT A4, but will NOT remove the instrument from service using OWP- 028, T/DeltaT1. T/DeltaTl. The SRO will enter LCO 3.3.1-1, Condition E for the failed instrument.
On cue from the Chief Examiner, flooding will occur from the discharge of SW Pump "A" A at the Service Water intake. The BOP will take immediate actions to split the North and South SW headers. The crew should respond lAW AOP-022, LOSS OF SERVICE WATER and isolate the South SW Header, isolating the source of the flooding. The SRO will enter LCO 3.8.1, Condition B for the inoperable EDG.
On cue from the Chief Examiner, PZR PORV PCV-456 will fail 70% open. The crew should attempt to close PCV-456, which will not respond, requiring closing the block valve (RC-535).
The RO should control PZR Heaters and Spray valves to maintain RCS pressure above 2205 AOP-01 9, MALFUNCTION OF RCS PRESSURE psig. The crew should respond using AOP-019, CONTROL. The SRO should enter LCO 3.4.11, Condition B for the inoperable PORV, and may enter LCO 3.4.1, Condition A if pressure falls below 2205 psig. The PORV will remain unavailable throughout the scenario.
On cue from the Chief Examiner, HCV-1459, HCV-1 459, Heater Bypass Valve will fail OPEN. The crew will implement AOP-010, MAIN FEEDWATER I/ CONDENSATE MALFUNCTION. The crew will HCV-1 459 from the RTGB control switch and the valve will remain in the closed position as close HCV-1459 long as the valve switch remains in the CLOSE position.
On cue from the Chief Examiner, Turbine bearing #3 vibration will increase to the alarm point and AOP-006, TURBINE ECCENTRICITY ECCENTRICITY/VIBRATION, I VIBRATION, will be entered. High bearing vibrations will be reflected on adjacent bearings #2 # 2 and #4. Vibrations will increase to 14 14 mils and actions in AOP-006 will require the SRO to direct a manual Reactor trip and enter PATH-1. When the crew attempts to trip the reactor, both Reactor Trip pushbuttons will fail and the SRO will enter FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS. The SDAFW Pump will trip and remain unavailable for the remainder of the scenario. The AO will be successful in tripping the Reactor locally when directed.
When the crew has transitioned to EPP-.4, EPP-4, REACTOR TRIP RESPONSE and on cue from the Chief Examiner, a Small Break LOCA will be inserted. The LOCA will require a Safety Injection initiation and Phase A isolation, which will fail to automatically actuate. Manual operator actuation actuation will be successful, but three Phase A A valves will fail to close and and require the RO to manually close these valves from the RTGB. The Control Room HVAC HVAC System System Train A and Train BB will fail to automatically actuate, actuate, requiring the BOP BOP to manually manually align HVAC HVAC for Emergency Pressurization Mode.
The scenario can be terminated, at the Chief Chief Examiners Examiner's discretion, discretion, after after itit is is determined determined that SI SI termination criteria will not not be met.
met.
Appendix Appendix D D NUREG-1 NUREG-1 021, 021, Rev.Rev. 9, 9, Supp.
Supp. 11
I Appendix Appendix D D Outline Scenario Outline Scenario Form Form ES-D-1 ES-D-1 HLC-08 NRC HLC-08 NRC SCENARIO SCENARIO 44 SIMULATOR SIMULATOR SETUP SETUP IC/SETUP IC/SETUP
- 10-604, SCN:
IC-604, SCN: 006_Sim_
006_Sim_4. 4.
- Status board Status board updated updated to to reflect reflect IC-4.
10-4.
PRE-LOADED EVENTS:
The following events should occur on the the reactor trip:
- CVC-204B, CCW-739 and SI-855 fail to close on SI actuation.
Event 9: Phase A valves CVC-204B,
- Event 10: Safety Injection fails to automatically actuate.
- 11: Control Room HVAC Train A and Train B fail to automatically actuate.
Event 11:
EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:
EVENTSITRIGGERS
- Event 1: Increase power to 75%.
- Event 2: Loop 11 T HOT fails low.
THQT
- Event 4: PZR PORV PCV-456 fails 70% open.
- Event 5: HCV-1459, HCV-1 459, Heater Bypass Valve fails OPEN.
- Event 6: High vibration on #3 Turbine bearing which leads to a manual Reactor trip.
- Event 8: Small Break LOCA.
EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
OP-i OP-105,05, Section 8.4.2; AOP-022, Section F; AOP-019; AOP-006; PATH-i, PATH-1, FRP-S.1; EPP-4; FRP-P.1.
Appendix Appendix DD NUREG-1 NUREG-1 021, 021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix 0D Operator Action Form ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 4 Event ##
Event 1 Page Page 4 of of 36 36
~-------- ~~----~I Event
Description:
Event
Description:
Increase Increase power power to 75%.
Time II Position II Applicants Actions or Behavior Applicant's BOOTH OPERATOR: Event 11 is normal power ascension to 75% lAW OP-105. OP-i 05. The crew will brief the event in the classroom prior to entering the simulator and begin the ascension as soon as they take the shift.
OP-i 05 Actions OP-105 SRO Begins power ascension using OP-1 OP-i 05 Section 8.4.2.
IF Reactor Engineering has not provided technical guidance, THEN SRO determine the reactivity change required.
SRO Notify the Load Dispatcher that unit load will be increased.
RO TAvG T °F of T AVG is within 5 of TREF.
REF.
RO Monitor the highest operable PR and IR channels on NR-45.
Steam Dump controls are set as follows:
BOP ** Potentiometer set at 7.28 (1020 psig) psig)..
- In Automatic and T AVG Control.
TAVG BOP FRVs in AUTO and S/Gs are being maintained at programmed level.
IF the EH Turbine Control is in OPER AUTO, THEN verify the Turbine BOP Control is in IMP IN. (Preferred)
RO Check the ERFIS PDCIII Delta Flux monitoring program enabled.
Check the Turbine Lube Oil Cooler is maintaining the oil temperature BOP leaving the bearings within the limits of OP-506.
The Bulk Auxiliary electrical loads should be on the Unit Auxiliary BOP Transformer lAW OP-603.
Appendix D 0 NUREG-1 021, Rev. 9, Supp. 11
Appendix 0D Operator Action Operator Form ES-O-2 Form ESD-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 44 Event ##
Event 1 _ _ _ _ Page
......;.,. Page 55 of _3,;;.;6;......
of 36 _ _--11
~-
Event
Description:
Event
Description:
Increase power Increase power toto 75%.
75%.
Time II Position Position ~ Applicants Actions or Behavior Applicant's For each power change greater than or equal to 10%, update the SRO power change log in the Reactor Startups/Shutdowns/Trips Book.
While increasing power, Generator MVAR loading should be lAW the BOP Robinson Plant Voltage Support and Coordination Procedure.
BOP Verify the Valve Position Limit is adjusted to maximum.
IF EH Turbine Control is in OPER AUTO, THEN increase turbine load as follows:
BOP *. Adjust the SETTER indication using the REF UP pushbutton to the desired load.
- . Depress the GO and/or HOLD pushbuttons and the REF UP as necessary to continue the load increase.
NOTE: OP-301, Section 8.2.7 Quick Dilution Checklist (shaded area) is included in the following steps, but may be used prior to the commencement of the plant up power.
When power is between 55-60%, the crew will start the second MFP.
DETERMINE the amount of water to add to the RCS.
(The crew willwill calculate - 2000 gallons of water needed for the dilution to 75% power, based on Rods at 175 -175 steps. Water will be added in 4-6 dilutions)
OBTAIN an independent independent check of the volume of water water required.
OBTAIN permission permission from the CRSS OR OR the the SSO to dilute.
dilute.
PLACE PLACE the the RCS MAKEUP MAKEUP MODE MODE selector switch switch in DILUTE DILUTE.
Appendix Appendix D 0 NUREG-1021, NUREG-1021, Rev. Rev. 9, 9, Supp.
Supp. 11
Appendix D Operator Action Form ES-D-2 Op Test No.:
Scenario # 4 Event # 1
~-------
Page 6 of 36
~---~I Event
Description:
Increase power to 75%.
Time Position I Applicants Applicant's Actions or Behavior YIC-1 14, PRIMARY WTR TOTALIZER to the desired quantity.
SET YIC-114, IF desired, THEN PLACE FCV-114A, FCV-1 14A, PRIMARY WTR FLOW DILUTE MODE, in MAN AND adjust Primary Water Flow rate using the UP/DOWN pushbuttons.
Momentarily PLACE the RCS MAKEUP SYSTEM switch to START.
VERIFY proper operation of LCV-115A,LCV-1 1 5A, VCT/HLDP TK DIV valve.
IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:
- . Unanticipated Rod Motion. Motion
- . Primary Water addition exceeds the desired value. value WHEN desired amount of PW has been added, THEN verify:
- . FCV-114A, FCV 11 4A, PW TO BLENDER, closes.
- . FCV-114B, FCV-1 1 4B, BLENDED MU TO VCT, closes.
- . IF in Auto, THEN the operating Primary Water Pump stops.
- The RCS MAKEUP SYSTEM is OFF.
RETURN the RCS Makeup System to automatic:
- . VERIFY FCV-114A, FCV-1 14A, PRIMARY WTR FLOW DILUTE MODE is in AUTO.
- . PLACE the ReS RCS MAKEUP MODE switch in AUTO.
- . Momentarily PLACE RCS MAKEUP SYSTEM switch to START.
RECORD, in AUTO LOG, as indicated by PRIMARY WATER TOTALIZER, YIC-1 14 total amount of PW added during the dilution.
YIC-114 MONITOR parameters for the expected change in reactivity AND inform_the_CRSS_OR_the_SSO_of_the_results_of_the_dilution.
inform the CRSS OR the SSO of the results of the dilution.
Appendix D NUREG-1 021, Rev. 9, Supp. 1 1
Appendix D Operator Action Form ES-D-2 Op Test No.:
Op Test No.: 1 Scenario #
Scenario 4 Event #
Event 2
....;2=---____ Page Page 77 of _3:..;6:....-_
36 _---l 1
Event
Description:
Event
Description:
Loop 11 T Loop Fails Low.
HOT Fails THOT Time I Position II Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 2, Loop 11 T THOT HOT failure.
EVENT INDICATIONS:
APP-003-A4; RC LOOPS llT T DEV APP-003-A6; RCS HIILO HI/LO TAVG APP-003-B4; RC LOOPS TAVG DEV T (RED) pegged low.
TR-412 Pen 1, llT TR-412 T Power fails low.
TR-41211T Recognizes that instrument has failed and references APP-003-A4.
RO Recommends removing the instrument from service.
Reviews, briefs and directs taking Loop 11 T HOT instrument out of THQT SRO service using OWP-028, TILH1. T/tiTl.
Review ITS for applicable LCOs:
- Table 3.3.1-1, #5, 6 - Condition E; Place channel in Trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- 1 .f - Condition D; Place channel in Trip within 6 Table 3.3.2-1, # 1.f hours.
- Table 3.3.2-1, # 4.d & 6.b - Condition H; Verify interlock is in required state for existing unit condition within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
Appendix D D NUREG-1 021, Rev. 9, Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 44 Event ##
Event 33 Page Page 88 of of 36 36
~- ~-------- ~~----~I Event
Description:
Event
Description:
SW flooding SW flooding from from the the South South SW SW Header.
Time Time ]II Position Position I Applicants Actions Applicant's Actions or Behavior or Behavior BOOTH OPERATOR:
BOOTH OPERATOR: When When directed by by the Chief Chief Examiner, Examiner, insert Event 3, insert Event 3, SW Flooding Flooding in the Intake in Intake Bay Bay from the SouthSouth SW Header.
EVENT INDICATIONS:
EVENT INDICATIONS:
APP-008-F7; SOUTH APP-OOS-F7; SOUTH SW HDR LO SW HDR LO PRESS PRESS APP-008-F8; APP-OOS-FS; NORTHNORTH SW HDR LO PRESS HDR LO PRESS APP-008-E7; APP-OOS-E7; S SW HDR HDR STRAINER PIT HI PIT HI LEVEL LEVEL APP-008-E8; APP-OOS-ES; N N SW HDR HDR STRAINER PIT PIT HI LEVEL APP-002-A8; APP-002-AS; HVH-1 WTR OUTLET LO FLOW APP-002-B8; HVH-2 WTR OUTLET LO FLOW APP-002-BS; APP-002-C8; APP-002-CS; HVH-3 WTR OUTLET LO FLOW APP-002-D8; HVH-4 WTR OUTLET LO FLOW APP-002-DS; APP-008-D7; S SW HDR APP-OOS-D7; HDR STRAINER PIT HI-HI LVL (Delayed)
APP-008-D8; N SW HDR STRAINER PIT HI-HI LVL (Delayed)
APP-OOS-DS; SW Booster Pump "B" B trips due to low suction pressure.
Recognizes a Loss of Service Water has occurred and performs BOP Immediate Actions of AOP-022, LOSS OF SERVICE WATER.
NOTE: The crew will place the Turbine ramp on hold while this malfunction is addressed.
SRO Enters AOP-022, LOSS OF SERVICE WATER.
Immediate Immediate Action Step:
BOP Check Check APP-008-E7 APP-00S-E7 AND APP-008-E8APP-OOS-ES Extinguished. (NO)
. Closes valves V6-12B and V6-12C. V6-12C .
SRO Transitions to Section Section F.
RO/BOP RO/BOP Makes Makes PA PA announcement announcement for entry entry into into AOP-022.
BOP BOP Verify SW X-CONN Valves Verify SW Valves V6-12B V6-12B and and V6-12C V6-12C CLOSED.
CLOSED. (YES)
(YES)
Appendix Appendix DD NUREG-1 NUREG-1 021, 021, Rev. 9, Supp.
Rev. 9, Supp. 11
Appendix D D Operator Action Operator Form Form ES-D-2 ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 44 Event ##
Event 3 ____
_3~ Page Page 99 of .....;3;.;6 of 36_ _ _....,1 Event
Description:
Event
Description:
SW flooding SW flooding from from the the South South SW SW Header.
Time III Position Position I Anolicants Actions or Behavior Applicant's Behavior Evaluate Control Room Indications and perform local inspections to Crew determine source of leakage.
BOOTH OPERATOR: Report that water is gushing up through the deck plates above the South Service Water header. If the crew has closed both cross-connect valves and V6-12A, then report water has stopped, but was from the South header.
BOP Check SW source of flooding. (YES)
BOP Check SW leak on the South Header. (YES)
Verify the following:
- . SW Pump "C" C Running. (YES)
- . SW Pump "D" D Running. (NO, will start pump) 0o Will receive APP-008-E4, APP-OOS-E4, ES E5 & E6 alarms
- . SW Pump "A" A Stopped. (NO, will stop pump)
- SW Pump "B" B Stopped. (YES)
SRO/BOP ** Check South SW pressure Decreasing. (YES)
.* Check North SW pressure Stable or Increasing. (YES)
NOTE: With Service Water Pumps A "A" AND B "B" isolated, EDG A "A" is inoperable. ITS 3.8.13.B.1 requires SR 3.8.1.1 3.B.1.1 to be performed within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
With lowlow flow to all CV HVH units, units, LCO 3.6.6 applies for both CV Cooling Trains inoperable.
The crew may start SWBP SWBP B "B" using using APP-002-A81B81C81D8 APP-002-ABIBBICBIDB guidance.
guidance.
BOP BOP Close Close V6-12A. (APP-008-E4/E5/E6/F8 (APP-00S-E4/ES/E6/FS will clear)
Appendix Appendix DD NUREG-1 NUREG-1 021,021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix DD Appendix Operator Action Operator Action Form ES-D-2 Form ES-D-2 Op Test No.:
Op Test No.: Scenario ##
Scenario 44 Event ##
Event 33 Page Page 10 10 of of 36 36
......;....- ---------- -----~I Event
Description:
Event
Description:
SW flooding SW flooding from from the the South South SW SW Header.
Time Time III Position Position I Applicants Actions Applicant's Actions or Behavior or Behavior BOP BOP Verify SW-851 Verify SW-851 andand SW-857 SW-857 closed.
closed.
BOOTH OPERATOR: When requested, report report that SW-851 and SW-857 are closed. (Not modeled on simulator) modeled SRO/BOP Check Flooding status stopped. (YES)
BOOTH OPERATOR: Report water is no longer gushing up above the South SW header.
BOP Check North SW header pressure> pressure > 40 psig. (YES)
Remove Control Power fuses from breakers for SW Pumps "A" A & "B" B
SRO at 480V Bus E-1.
BOOTH OPERATOR: Rack out the breakers for SW Pumps A "A" & "B" B on 480V Bus E-1.
When requested, report that leak is from the connection of SW Pump "A" A and the 30 inch header.
Determine if a SW Booster Pump should be started:
SRO/BOP *
- Check SW Booster pumps all stopped. (YES)
- Start one SW Booster Pump. (APP-002-A8/B8/C8/D8 clear). clear) .
Appendix Appendix DD NUREG-1 NUREG-1 021,021, Rev. 9, Supp.
Rev. 9, Supp. 11
Appendix D Operator Action Operator Form ES-D-2 Form ES-D-2 Op Test No.:
Op No.:
Scenario Scenario ## 44 Event #
Event 33
~--------
Page Page 11 11 of of 36 36
~~----~I Event
Description:
Event
Description:
SW flooding from the South SW Header.Header.
Time ~ Position Position ~ Applicants Actions or Behavior Applicant's Behavior NOTE: When SW8P SWBP "8"B is started, SW pressure may drop to < <40 40 PSIG. If so, the crew may use Step 19 RNO to increase SW pressure.
Step 19, RNO Actions
BOP ** Perform 11 or both of the following to restore South SW header pressure to between 40 and 50 PSIG:
AOP-022 Actions BOP Check any CW OW Pump running. (YES)
Determine if adequate seal water is available to CW: OW:
- APP-008-E4, CW OW PMP A SEAL WTR LOST extinguished.
- APP-008-E5, CW OW PMP B SEAL WTR LOST extinguished.
- APP-008-E6, CW OW PMP C SEAL WTR LOST extinguished.
(YES, ALL extinguished)
Determine maximum allowable CCW COW temperature as follows:
RO ** ROS temperature $. 350 degrees F. (NO)
Check RCS
- COW Heat Exchanger outlet temperature indicated on Maintain CCW TI-607 less than or equal to 105 degrees F.
TI-6071ess Perform the following:
- Inspect the area of the leak.
- Report findings to the SSO.
- Identify and isolate the source of the SW leak.
Contact Maintenance to install temporary pumps to dewater Service SRO Water pits.
Appendix D D NUREG-1021, NUREG-1 021, Rev. 9, Supp. 11
Appendix 0D Appendix Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 44 Event ##
Event 33 Page Page 12 12 of of 36 36
~-------- ~---~I Event
Description:
Event
Description:
SW flooding SW flooding from from thethe South South SW SW Header.
Time Time II Position Position I Applicants Actions Applicant's Actions or Behavior or Behavior Contact Engineering Contact Engineering to to perform perform the the following:
following:
SRO SRO *. Evaluate operability Evaluate operability of of equipment equipment affected affected by by flooding.
flooding.
- . Provide corrective actions for flooding.
Refer to ITS Refer ITS for any applicable LCOs. LCOs.
- . LCO 3.6.6, Condition 0D - Restore one containment cooling train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. (Will only be in this LCO until a SW Booster Pump is started)
- . LCO 3.7.7, Condition A - Restore SWS train to OPERABLE SRO status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. (This LCO has already been entered due to the SWBP being out of service)
- . LCO 3.8.1, Condition B 0o 3.8.1 .1 for the offsite circuit within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
Perform SR 3.8.1.1 (Cascaded LCO from SW NOT available to EDG "A") A) 0o Perform SR 3.8.1.2 to verify EDG OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SRO Return to procedure and step in effect.
Appendix Appendix D 0 NUREG-1021, NUREG-1021, Rev. Rev. 9, 9, Supp.
Supp. 11
Appendix D Operator Action Form ES-D-2 ES.D-2 No.:
Op Test No.:
Scenario # 4 Event #
Event 4
_4_____ Page Page 13 13 36 _ _---11 of _3;;,;6;;...-.
Event
Description:
Event
Description:
PZR PORV PZR PORV PCV-456 PCV-456 fails 70% OPEN.
Time II Position ! Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 4, PZR PORV PCV-456 fails 70% OPEN.
EVENT INDICATIONS:
APP-003-C3;PRT HI PRESS APP-003-D6;PZR PORV/SAFETY VLV OPEN APP-003-E6;PZR PORV LN HI TEMP APP-003-F6;PZR SAFETY VLV LINE HI TEMP APP-003-D8;PZR CONTROL HIILO HI/LO PRESS Recognizes PORV is OPEN and takes Immediate Actions of AOP- AOP RO 019, MALFUNCTION OF RCS PRESSURE CONTROL.
SRO AOP-01 9, MALFUNCTION OF RCS PRESSURE CONTROL.
Enters AOP-019, Immediate Action Step:
Determine if PZR PORVs should be CLOSED:
RO ** Check PZR Pressure less than 2335 PSIG, PSIG (YES)
- Verify both PZR PORVs CLOSED. (NO)
IF any PZR PORV can NOT be CLOSED, THEN close itsPORV its PORV BLOCK valve.
Immediate Action Step:
Immediate RO Control Heaters and Spray Spray valves to restore RCS Pressure to desired control band.
RO Check PZR Pressure under operator control. (YES)
RO Check PC-444J, PZR PRESSURE operating in AUTO. (YES)
RO Check RCS pressure << required for current plant conditions. (YES)
Appendix D D NUREG-1 NUREG-1 021, 021, Rev. 9, Supp. 11
Appendix D D Operator Action Operator Form ES-D-2 Form ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 44 Event ##
Event _4~
4 ____ Page Page 14 14 of 36_ _ _~1 of ....;3;;.;;6 Event
Description:
Event
Description:
PZR PORV PZR PORV PCV-456 PcV-456 fails fails 70%
70% OPEN.
OPEN.
Time I Position Position II Applicants Actions or Behavior Applicant's Continuous Action Step:
Check PZR pressure less than 2205 PSIG. PSIG.
RO IF pressure IF pressure decreases to < 2205 PSIG, PSIG, THEN restore pressure pressure within within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Or be in MODE 2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. (lAW LCO 3.4.1)
RO Check BOTH PZR Spray valves CLOSED. (YES)
RO CVC-31 1, AUX PZR SPRAY valve CLOSED. (YES)
Check CVC-311, Check APP-003-F8, PZR LO LVL HTR OFF & LTDN SECURE RO extinguished. (YES)
Determine Heater Capacity:
SRO/RO ** Contact Maintenance and Engineering to check PZR Heater capacity.
- Check PZR Heater capacity REDUCED. (NO)
BOOTH OPERATOR: When requested, inform the crew that heater capacity has NOT changed since the last Refueling Outage test.
RO Check PZR Pressure stable or trending to required value. (YES)
SRO Contact l&C I&C To Make Repairs To The PZR Pressure Control System.
Review ITS ITS For Applicable LCOs:
- Remove power power within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
hour.
Appendix Appendix D D NUREG-1 NUREG-1 021,021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix D D Operator Action Operator Form Form ES-D-2ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 44 Event ##
Event 5 ____
_5~ Page Page 15 15 of of ...,;3;,;;6 36_ _ _-l
~- 1 Event
Description:
Event
Description:
HCV-1 459, Heater HCV-1459, Heater Bypass Bypass Valve Valve fails fails open.
open.
Time I Position I Applicants Actions or Behavior Applicant's Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 5, HCV-1459, HCV-1 459, Heater Bypass Valve failing OPEN.
EVENT INDICATIONS:
HI/LO LVL APP-007-B6, HDT HI/LO Recognizes Heater Bypass is OPEN and takes Immediate Actions of BOP AOP-01 0, MAIN FEEDWATER/CONDENSATE MALFUNCTION.
AOP-010, SRO Enters AOP-01 AOP-010.O.
Immediate Action Step~Step:
BOP Check Feedwater Regulating Valves operating properly in Auto or Manual. (FCV-478, 488 and 498) (YES)
Continuous Action Step:
Check Reactor Trip setpoint being approached. (NO)
BOP IF a Reactor Trip Setpoint is being approached, THEN trip the PATH-i.
Reactor and Go To PATH-1.
RO/BOP Makes PA announcement for entry into AOP-0i0. AOP-010.
Goes to the appropriate Step from the table. (HCV-i (HCV-1459459 Failed OPEN, SRO Step 35)
NOTE: HCV-i 459, LP HEATERS BYP, is interlocked with QCV-i HCV-1459, QCV-10426, 0426, SECONDARY BYPASS. HCV-1 HCV-1459 459 failing open will also result in QCV-i QCV-104260426 opening.
opening .
Appendix Appendix D D NUREG-i NUREG-1 021, 021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix D D Operator Action Operator Form ES-D-2 Form ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 44 Event ##
Event 55 Page Page 16 16 of of 36 36
~-------- ~~----~I Event
Description:
Event
Description:
HCV-1459, HCV-1459, Heater Heater Bypass Bypass Valve fails open. open.
Time II Position Position II Applicants Actions or Behavior Applicant's Behavior HCV-1 459 Has Failed:
Determine If HCV-1459
Check HCV-1459,
- . Maintain Reactor Power < 100% using Attachment 1.
(Due to the low power, a power reduction will not be BOP necessary)
0o P1-i 434 - "B" PI-1434 - B FW PUMP SUCTION PRESSURE.
BOP Check Feed Water Pump suction pressures> pressures > 400 PSIG. (YES)
BOP HCV-1 459 CLOSED. (Valve can be closed from the RTGB)
Verify HCV-1459 RO/BOP Contact I&C To Troubleshoot AND Correct HCV-1459 HCV-1 459 Problem.
BOP Check S/GSIG Level at or trending to PROGRAM. (YES)
RO T AVG at or trending to T Check TAvG REF. (YES)
TREF.
Check current loading for the following pumps less than MAXIMUM:
.* Main Feedwater Pump - 0.715 KAMPS -
- Condensate Pumps - 370 AMPS -
.* Heater Drain Pumps - 90 AMPS -
BOOTH 800TH OPERATOR: When requested, inform the crew that:
.* MFP A "A" is .605 KAMPS, MFP B is .605 "8" is is .590 KAMPS.
.* Condensate Pump A "A" is is 295 295 AMPS, B "8" is 305 AMPS.
is 305
.* HDP HOP A "A" isis 72 AMPS, B "8" is is 68 AMPS.
Appendix Appendix D D NUREG-1021, NUREG-1021, Rev. Rev. 9, 9, Supp.
Supp. 11
Appendix 0D Appendix Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test Test No.:
No.: Scenario ##
Op Scenario 44 Event ##
Event 5
_5=--_ _ _ _ Page Page 17 17 of 36_ _ _-iI of .....;3;.,.;;6 Event
Description:
Event
Description:
HCV-1 459, Heater HCV-1459, Heater Bypass Valve fails Bypass Valve fails open.
open.
Time Time I Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior Determine Iodine Determine Iodine Sampling Sampling Requirements:
Requirements:
SRO SRO
- . Check Power Power Change>
Change> 15% 15% ININ ONE HOUR.
HOUR. (NO)
(NO)
Check APP-005-B5, APP005-B5, ROD BANKS BANKS AlB/C/O AIB/C/D LO LIMIT, extinguished.
RO Monitor Axial Flux Difference To Ensure Compliance With ITS 3.2.3.
SRO Notify Load Dispatcher Of The Unit's Units Load Capability.
SRO Return To Procedure And Step In Effect.
Appendix Appendix D0 NUREG-1 NUREG-1 021,021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix DD Appendix Operator Action Operator Action Form Form ES-D-2 ES-D-2 Test No.:
Op Test No.:
Op Scenario ##
Scenario 44 Event ##
Event 66 && 77
Page Page 18 18 of of 36 36
~I Event
Description:
Event
Description:
High vibration High vibration on on #3 Turbine bearing
- 3 Turbine bearing which which leads leads to to aa manual manual Reactor Reactor trip.trip.
Failure of Failure of the Reactor to the Reactor trip. (ATWS) to trip. (ATWS) SDAFWSDAFW Pump Pump Trips.
Trips.
Time Time II Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior BOOTH OPERATOR:
BOOTH OPERATOR: When When directed directed by the Chief by the Chief Examiner, Examiner, insert insert Event Event 6, 6, Turbine Turbine bearing #3 bearing vibrations will
- 3 vibrations will increase increase above above the the alarm alarm setpoint setpoint and and require manual require manual Reactor and Reactor Turbine and Turbine trips. trips.
EVENT INDICATIONS:
EVENT INDICATIONS:
APP-008-A8; TURBINE APP-OOS-AS; TURBINE SUPERVISORY SUPERVISORY INSTRUMENTINSTRUMENT (Will (Will reflash reflash as as each each bearing bearing vibration vibration increases increases greater than greater than 77 mils) mils)
Turbine Generator Turbine Generator Supervisory Supervisory Recorder Recorder and and Vibration module module bearings bearings in in alarm.
alarm.
Recognizes alarm, monitors monitors vibration and references APP-OOB-AB. APP-008-A8.
- . Verify lube oil cooler discharge temperature between 115 1 15 -
BOP 125 degrees F. (YES)
- . If turbine bearing temperature is > > 225 degrees F, trip the turbine. (NO)
SRO Enters AOP-006, TURBINE ECCENTRICITY ECCENTRICITY / VIBRATION. VIBRATION.
BOP Check Turbine Speed:s Speed < 600 RPM. (NO, Go To Step 4)
Continuous Action Step:
BOP Check Bearing Vibration Levels on on the TURBINE GENERATO GENERATOR R SUPERVISO SUPERVISORY RY RECORDER less than 14.0 14.0 MILS. (YES)
NOTE:
NOTE: At this time, vibration level is is less less than 14 14 mils mils but StepStep 44 RNO will be be implemented as as vibration increases to> to > 1414 mils.
mils.
Attempt to Attempt to decrease decrease or or stabilize stabilize vibration vibration by by atat least least one one of of the the following following methods:
methods:
.* Vary load (MW Vary load (MW and/or and/or VARS)
VARS) or or turbine turbine speed.
speed.
BOP BOP o0 (Crew (Crew may may adjust adjust VARSVARS Up Up or or Down Down using using thethe Voltage Voltage Regulator Regulator to to attempt attempt to to stabilize stabilize the the vibration) vibration)
.* Vary Vary Hydrogen Hydrogen Side Side oror Air Air Side Side Seal Seal Oil Oil temperatures temperatures..
o__(Crew_m 0 (Crew may direct the_AO_to_a ay_direct the AO to adjust Seal Oil djust_Seal_O il Appendix Appendix DD NUREG-1 NUREG-1 021, 021, Rev.
Rev. 9,9, Supp.
Supp. 11
Appendix D Operator Action Form ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 44 Event ##
Event 6 & 7 _ _ _ Page
_6;;..&;.;...;..7 Page 19 19 of _3.;..;6~
of 36 _ _---!I Event
Description:
Event
Description:
High vibration on #3 Turbine bearing High bearing which leads to a manual manual Reactor Reactor trip.
Failure of the Reactor Failure Reactor to trip. (ATWS)
I Time II Position II Anolicants Actions or Behavior Applicant's Temperatures in an attempt to stabilize the vibration)
- . Vary Turbine Lube Oil cooler discharge temperature.
- . Increase Exciter Air discharge temperature.
BOOTH OPERATOR: As a Security Officer patrolling the Protected Area, provide input to the crew that increased vibration is noted on the Turbine Deck and adjacent to the Control Room.
NOTE: At this time, vibration level on #3 bearing will have increased to greater than 14 mils and Step 4 RNO actions will be implemented.
Continuous Action Step:
Check Bearing Vibration Levels on on the TURBINE GENERATOR SUPERVISORY RECORDER less than 14.0 MILS. (NO)
SRO IF vibration is felt in the Control Room, THEN perform one of the following:
- IF the REACTOR TRIP FROM TURB BLOCK P-7 permissive light is extinguished, THEN trip the Reactor AND Go To PATH- PATH
- 1. (YES)
Directs the RO to manually trip the Reactor and perform the immediate SRO actions of PAPATH-i.
TH-1.
PATH-i PATH-1 Actions Immediate Action Step Step:
Check REACTOR TRIP TRI P as follows:
- Reactor trip main and bypass breakers OPEN. (NO)
- Rod Position indication ZERO. (NO)
.* Rod Bottom Lights ILLUMINATED. (NO)
.* Neutron Flux Flux DECREASING. (NO)
SRO Transitions to FRP-Si.
FRP-S.1.
Appendix D D NUREG-1021, Rev. 9, Supp. i1 NUREG-i021,
Appendix 0D Operator Action Operator Form ES-D-2 Form ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 44 Event ##
Event 6 & 7 _ _ _ Page
_6;;;..&;;;;.....;..7 Page 20 20 of ....,;3:;.;;;6 of 36_ _ _...,1 Event
Description:
Event
Description:
High vibration High vibration on on #3#3 Turbine Turbine bearing bearing which leads leads to to aa manual manual Reactor Reactor trip. trip.
Failure of Failure of the the Reactor Reactor to to trip.
trip. (ATWS)
(ATWS) SDAFW SDAFW PumpPump Trips.
Trips.
Time I Position III Applicants Actions or Behavior Applicant's FRP-S.1 Actions Immediate Action Step:
Perform Perform the following:
- . Depress both Reactor Reactor Trip pushbuttons. pushbuttons.
- . If Reactor Trip breakers will not open, then perform the following:
RO/SRO
- . IInsert rods nsert control rods.
- . Dispatch an operator to the MG Set Room to trip Reactor Trip Breakers "A" A and "B" B AND MG Set Generator Circuit Breakers "A" A and "B". B.
- . Dispatch an operator to 480V Busses 2B and 3 to trip Rod Drive MGMG Set Breakers 'W' A and "B".
B.
NOTE: SRO will notify the Inside and Outside Auxiliary Operators while Control Room operators take appropriate actions. 3 minutes after being contacted, OPEN the RTBs and MG set breakers.
Immediate Action Step:
Check Turbine Trip as follows:
BOP *. Both Turbine Stop valves closed. (NO)
.* All Governor valves closed. (NO)
Perform the following:
BOP Manually trip the Turbine by simultaneously depressing the THINK and TURBINE TRIP Pushbuttons Verify All AFW Pumps running. (NO, SDAFW SDAFW Pump Pump will NOTNOT start and BOP BOP APP-007-F5, APP-007-FS, SD SO AFW PMP LO DISCH DISCH PRESS PRESS TRIP will illuminate) illuminate)
Appendix Appendix D 0 NUREG-1 NUREG-1 021,021, Rev.
Rev. 9,9, Supp.
Supp. 11
Appendix 0D Appendix Operator Action Operator Action Form Form ES-O-2 ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 44 Event ##
Event 66 && 77 Page Page 21 21 of of 36 36
~- ~~------ --------~I Event
Description:
Event
Description:
vibration on High vibration High on #3
- 3 Turbine Turbine bearing bearing which which leads leads to to aa manual manual Reactor Reactor trip.
trip.
Failure of Failure of the the Reactor Reactor toto trip.
trip. (ATWS)
(ATWS) SDAFWSDAFW Pump Pump Trips.
Trips.
Time Time I Position Position III Applicants Actions Applicant's Actions or Behavior or Behavior Initiate Emergency Initiate Emergency Boration, Boration, verify verify Charging Charging flowpath flowpath established:
established:
RO ** CVC-310B, LOOP 2 COLD LEG CHG, OPEN.
- . HIC-i 21, Charging HIC-121, Charging Flow Controller Controller demand at 0% 0%..
Verify Two Charging Pumps running at full speed. (NO, will increase RO speed on the Charging Pump running in Manual)
RO Verify Boric Acid Pump aligned for blend running. (YES)
RO Verify MOV-350, BA TO CHARGING PMP SUCT, OPEN. (YES)
RO Check flow on FI-11 Fl-i 10,0, BORIC ACID BYPASS FLOW, indicated. (YES)
RO Verify Charging Flow to RCS on FI-122A. Fl-i 22A. (YES)
BOP Verify CONTAINMENT VENTILATION ISOLATION initiated. (NO)
NOTE: It is expected that the CV Ventilation Signal has not been initiated.
To initiate the CV Ventilation Signal, the operator will take R-1 R-111 or R-12 high voltage pushbutton to OFF and return to ON to initiate the signal.
This can be verified by the 22 Amber lights ILLUMINATED ILLUMINATED below the Radiation Monitoring Monitoring System panel labeled labeled CV"CV Ventilation Isolation SignalSignal Relay V-i V-1 and V-2.V-2."
Continuous Action Step: Step:
initiated. (NO)
(NO)
RO RO IF IF an an SI Signal occurs, SI Signal occurs, THEN verify verify auto auto start of of all all SI SI equipment equipment using Supplement using Supplement LL while continuing with with this procedure.
procedure.
Appendix Appendix D0 NUREG-1 021, NUREG-i 021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix DD Appendix Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 44 Event ##
Event 6 & 7_ _ _ Page
_6;;..&;.;...;..7 Page 22 22 of 36_ _ _~1 of ....;3;;.;.6
~-
Event
Description:
Event
Description:
High vibration High vibration on on #3
- 3 Turbine Turbine bearing bearing which which leads leads to to aa manual manual Reactor Reactor trip. trip.
Failure of Failure of the the Reactor Reactor to trip. (ATWS) to trip. (ATWS) SDAFW SDAFW Pump Pump Trips.
Trips.
Time Time II Position Position I Applicants Actions Applicant's Actions or or Behavior Behavior Check ifif the Check the following following trips trips have have occurred: occurred:
RO/BOP RO/SOP ** Reactor Trip.
Reactor Trip. (YES)
(YES)
Turbine Trip. (YES)
(YES)
Continuous Action Step:
Check ifif Reactor Check Reactor is subcritical:
subcritical:
RO RO ** Check Power Range indication less than 5%. 5%. (YES)
- Check Intermediate Range Range indication negative negative SUR. (YES, (YES, Go To Step 24)
RO IRPI less than two rods stuck out. (YES)
Check IRPIless Boration:
Stop the RCS Soration:
- Verify MOV-3S0 MOV-350 closed.
RO ** Verify switch for Soric Boric Acid pump aligned for blend in AUTO.
- Check emergency boration performed using MOV-350. MOV-3S0.
- Notify Engineering to evaluate RCP Searing Bearing temperatures and No. 1 seal leakoff temperatures No.1 temperatures/flowrates. /flowrates.
Check emergency boration performed using RWST flowpath and it is RO desired to align Charging Pump suction to the VCT. (NO, Go Go To Step Step
\
25.i) 2S.i)
RO RO Control Control Charging Charging Pump Pump speed speed to to control PZR PZR Level.
Level.
Reset Reset SPDS/lnitiat SPDS/lnitiate e monitoring monitoring of of Critical Critical Safety Safety Function Function Status Status RO RO Trees.
Trees.
SRO SRO Return Return to to procedure procedure and and step step in in effect.
effect.
Appendix Appendix DD NUREG-102 NUREG-1021 1, , Rev. 9, Supp.
Rev. 9, Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test Op Test No.:
No.:
-- 1 Scenario #
Scenario # 44 Event ##
Event 6 & 7 _ _ _ Page
_6_&_7 Page 23 23 of 36_ _ _-l of ......:3:;,.;6 1
Event
Description:
Event
Description:
High vibration High vibration on on #3
- 3 Turbine Turbine bearing bearing which which leads leads to to aa manual manual Reactor Reactor trip. trip.
Failure of Failure of the the Reactor Reactor to to trip.
trip. (ATWS)
(ATWS) SDAFW SDAFW Pump Pump Trips.
Trips.
Time Time III Position Position ! Anolicants Actions Applicant's Actions or or Behavior Behavior SRO SRO Directs entry at the beginning Directs beginning of of PATH-1.
PATH-i.
PATH-i Actions PATH-1 IMMEDIATE ACTION ACTION STEP: STEP:
RO RO Reactor Tripped. (YES)
Reactor (YES)
IMMEDIATE ACTION STEP:
BOP Turbine Tripped. (YES)
IMMEDIATE ACTION STEP:
BOP E-1 AND E-2 energized. (YES)
IMMEDIATE ACTION STEP:
RO 0o SI Initiated. (NO) 0o SI Initiation Required. (NO)
RO Verify two Charging Pumps running. (YES)
SRO Transition to EPP-4, REACTOR TRIP RESPONSE.
Continuous Action Step:
Determine ifif procedure procedure exit exit is is warranted:
warranted:
SRO SRO ** Check Check attack attack on RNP RNP site in in progress. (NO)(NO)
.
- total loss Check aatotal loss of SW OR OR Loss of Lake Lake Robinson Dam integrity in progress. (NO, Go to Step Step 2)
Continuous Continuous Action Action Step:
Step:
Check Check SI signal initiated.
SI signal initiated. (NO, (NO, Go Go to to Step Step 4)4)
RO RO IF IF SI SI initiation initiation occurs occurs during during this this procedure, procedure, THENTHEN Go Go to to PATH-i, PATH-1, Entry Point Entry Point A. A.
Appendix Appendix D D NUREG-iO2i, NUREG-1021, Rev. Rev. 9,9, Supp.
Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test Test No.:
Op No.:
Scenario ##
Scenario 44 Event ##
Event 66 && 77 Page Page 24 24 of of 36 36
~I Event
Description:
Event
Description:
High vibration High vibration on on #3#3 Turbine Turbine bearing bearing which which leads leads to to aa manual manual Reactor Reactor trip.
trip.
Failure of Failure the Reactor of the Reactor to to trip. (ATWS) SDAFW trip. (ATWS) SDAFW Pump Pump Trips.
Trips.
Time Time I Position Position II AnDlicants Actions Applicant's Actions or or Behavior Behavior SRO Reset SPDS and initiate monitoring of CSFSTs.
CREW CREW Foldout A.
Open Foldout
- RCP Trip criteria. IF BOTH conditions are met, THEN stop all RCPs: (NO) 0a SI Pumps - AT LEAST ONE RUNNING
- RUNNING AND CAPABLE OF DELIVERING FLOW DELIVERING FLOW TO THE CORE 0o RCS Subcooling - < - < 35 degrees F [55 degrees F]
and Go To PATH-1, 0o RCS Subcooling - < - < 35 degrees F [55 degrees F]
0o PZR Level-Level CAN NOT BE MAINTAINED> 10% [32%]
- . MSR Isolation criteria. IF ANY Purge OR Shutoff Valve does not indicate fully closed, THEN place the associated RTGB Switch to CLOSE.
RO Check RCS temperature stable or trending to 547 degrees F. (YES)
SRO Transitions to Step 12, based on SW pressure between 40-50 PSIG.
Continuous Action Step:
Determine Feedwater status:
. Check RCS average temperature less than 554 of. (YES) 554 °F.
- Verify FW FW REG VALVEs CLOSED. (YES)
RO Check All Control Rods fully inserted. (YES)
Check (YES)
Appendix Appendix D D NUREG-i NUREG-1 021, 021, Rev.
Rev. 9,9, Supp.
Supp. 11
Appendix 0D Appendix Operator Operator Action Action Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 44 Event ##
Event 8,9,10&11 8, 9, 10 & 11 Page Page 25 25 of of 36 36
....;...- ";"~-----11 Event
Description:
Event
Description:
Small Break Small LOCA, Phase Break LOCA, Phase AA fails fails to actuate, SI to actuate, SI fails fails to actuate, CR to actuate, CR HVAC HVAC fails fails to to actuate.
actuate.
Time Time II Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior BOOTH OPERATOR:
BOOTH OPERATOR: When directed by When directed by the the Chief Chief Examiner, Examiner, insert insert Event Event 8,8, Small Small BreakBreak LOCA.
LOCA.
EVENT INDICATIONS:
PZR Level PZR Level and Pressure Pressure decreasing RR-1 Recorder RR-1 Point #11 Recorder Point #11 for for R-12 R-1 2 in in alarm alarm (later)
(later)
Phase "A" Phase A valves valves will not not close close automatically automatically Control Room HVAC Exhaust Dampers are not closed.
HVE-19A did not start; HVE-16 did not stop.
NOTE: The following actions may be performed using OMM-022 guidance:
Safety Injection fails to actuate on the LOCA, the crew will manually initiate SI which will start all SI and RHR pumps, but SI- SI 870A and 870B valves will NOT open.
Sl-870A and SI-870B SI-870A Sl-870B must be opened manually and at least one valve must be opened to provide an injection path.
CR HVAC will fail to shift to PRESSURIZATION MODE. The crew will manually start HVE-19A and HVE-16 will have to be manually stopped. CR-D1 CR-D1A-SA A-SA and D1 Dl B-SB will close --55 seconds after HVE-16 is stopped.
CREW Open Foldout A.
- RCP Trip criteria. IF BOTH conditions are met, THEN stop all RCPs: (YES) o0 SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE o0 RCS Subcooling - << 35 degrees FF [55 degrees F]
NOTE:
NOTE: Phase A fails to actuate, the crew will manually actuate Phase A, but valves CCW-739, CCW-739, CVC-204B and Sl-855 SI-855 will NOT close close on manual actuation actuation of the pushbutton. pushbutton.
Verify Phase Phase A A Isolation Isolation valves valves are are closed. (NO, (NO, must must be be manually RO RO actuated actuated using using the the pushbutton) pushbutton)
Appendix Appendix D0 NUREG-1021, Rev.
NUREG-1021, Rev. 9,9, Supp.
Supp. 11
Appendix D Operator Action Form ES-D-2 Op Test Op Test No.:
No.: 1 Scenario #
Scenario 4 Event ##
Event 8, 9, 10 & 11 8,9,10&11 Page Page 26 of ...,;3;;.;;6 of 36_ _ _-11 Event
Description:
Event
Description:
Small Break Small Break LOCA, LOCA, Phase Phase A fails to actuate, actuate, SI SI fails to actuate, actuate, CR CR HVAC HVAC fails to actuate.
actuate.
Time II Position I Applicants Actions or Behavior Applicant's NOTE: Valves CCW-739, CVC-204B, SI-855 Sl-855 will NOT close on manual actuation of the pushbutton. They will require manual closure from the RTGB control switches.
BOP Verify FW Isolation valves are closed. (YES)
BOP Verify both FW pumps are tripped. (YES)
BOP Verify both MDAFW pumps are running. (YES)
NOTE: Crew may elect to reset SI in order to control AFW and S/G SIG levels.
BOOTH OPERATOR: If the crew requests for the vacuum breakers to be opened to assist in turbine coast down, report that the Turbine Engineer requests that they allow the turbine to coast down normally as long as lube oil pressure remains above 5 psig.
If additional Feedwater is required, start the SDAFW pump. (Tripped BOP and will NOT restart)
RO Verify 2 SI pumps running. (YES)
RO Verify Both RHR pumps running. (YES)
Verify SI valves are properly aligned. (NO, SI-870A and 870B were RO manually aligned)
RO At least 11 COW CCW pump is running. (YES)
BOP All SW and SW Booster pumps running. (NO)
Appendix D D NUREG-1 NUREG-1 021, 021, Rev. 9, Supp. 11
Appendix 0D Appendix Operator Action Operator Action Form ES-D-2 Form ES-D-2 Test No.:
Op Test No.:
Op Scenario ##
Scenario 44 Event ##
Event 8,9,10&11 8, 9, 10 & 11 Page Page 27 27 of of _3;;.;6~
36 _ _~
Event
Description:
Event
Description:
Small Break Small Break LOCA, LOCA, Phase Phase A A fails fails to to actuate, actuate, SI SI fails fails to to actuate, actuate, CR CR HVAC HVAC fails fails to to actuate.
actuate.
Time Time III Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior Attempt to Attempt to start start all all SW SW and and SW SW Booster Booster pumps.pumps. (NO,(NO, SW SW Booster Booster BOP BOP Pump "A" Pump A and and SWSW Pumps Pumps "A" A && "B" B are unavailable) are unavailable)
BOP North OR South SW SW Header Header Lo PressurePressure alarm illuminated. (NO)
RO Verify CV Fans HVH-1, 2, 3, 4 running. (YES)
RO IVSW initiated. (YES)
Verify IVSW BOP Verify CV Ventilation isolation. (YES)
Verify Control Room Vent aligned for Pressurization Mode. (NO, HVE- HVE BOP 1 9A will be started using the control switch, HVE-16 19A HVE-1 6 will be stopped using the control switch)
NOTE: HVE-19A will be manually started and HVE-16 will have to be manually stopped. CR-Di CR-01 A-SA and 01 Di B-SB 8-S8 will close - 5 seconds after HVE-16 is stopped.
NOTE: CSFSTs will indicate an ORANGE PATH on RCS INTEGRITY at some point while the crew is performing actions in PATH-i. PATH-1.
At the discretion of the Chief Examiner and when the crew transitions to FRP-P.1, FRP-P.i, the scenario can be terminated. If needed, actions for FRP-P.i FRP-P.1 begin on page 33.
BOP Verify both EDGs running. (YES)
Continuous Action Action Step:
Step:
BOP BOP Restart battery chargers within 30 minutes Restart minutes of of power loss using using OP OP-601.
601.
RO RO Continuous Continuous ActionAction Step:
Step:
Appendix Appendix D 0 NUREG-1 NUREG-1 021, 021, Rev.
Rev. 9,9, Supp.
Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 44 Event ##
Event 8, 9, 10 & 11 8,9,10&11 Page Page 28 28 of .....;3;;.;;6 of 36_ _ _-11 Event
Description:
Event
Description:
Small Break Small Break LOCA, LOCA, Phase Phase AA fails fails to to actuate, actuate, SI SI fails fails to actuate, CR to actuate, CR HVAC HVAC fails fails to to actuate.
actuate.
Time Time II Position Position fi II Applicants Actions Applicant's Actions or or Behavior Behavior CV Pressure CV Pressure has has remained remained below below 10 10 psig.
psig (YES)
(YES)
BOP Automatic Steam Line Isolation Initiated.
Line Isolation Initiated. (NO)
BOP BOP Steam Line Automatic Steam Line Isolation Isolation Required.
Required. (NO) (NO)
BOP Locally open breaker for HVS-1 at MCC-5.
RO RCS pressure> 1350 psig. [1250 psig] (NO)
RO RCS Pressure Greater than 125 psig. (YES)
BOP At least 300 GPM AFW flow available. (YES)
BOP Verify AFW valves properly aligned.
BOP Control AFW flow to maintain S/G SIG levels between 8% [18%] and 50%.
NOTE: The crew may reset SI and secure a MDAFW Pump to control SIG S/G level.
RO RCP Thermal barrier cooling water Hi/Lo HilLo flow alarms illuminated. (NO)
BOP BOP Place Steam Steam Dump Dump Mode Mode Switch to Steam Pressure.
RO RO RCS Temp stable at RCS Temp OR trending to 547 degrees at OR degrees F. F. (NO)
temperature> 547 547 degrees degrees F. F. (NO)
(NO)
Appendix Appendix D D NUREG-1 NUREG-1 021, 021, Rev.
Rev. 9,9, Supp.
Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.: Scenario ##
Scenario 44 Event ##
Event 8, 9, 10 & 11 8,9,10&11 Page Page 29 29 of ..,.;3;;.,.;6 of 36_ _ _-11
~-
Event
Description:
Event
Description:
Small Break LOCA, Small Break LOCA, Phase Phase AA fails fails to actuate, SI to actuate, SI fails to actuate, fails to actuate, CR CR HVAC HVAC fails fails to to actuate.
actuate.
Time Time ~ Position Position II Applicants Actions Applicant's Actions or Behavior or Behavior BOP BOP Attempt to to limit limit cooldown.
cooldown.
RCS cooldown continues IfIf RCS continues and is is not not due to SI flow, then close close MSIVs MSIVs MSIV bypasses.
and MSIV bypasses.
BOP (The crew should determine that cooldown IS due to SI flow and should NOT close the MSIVs at this time)
RCS pressure>
RO PZR Spray and Aux Spray valves closed. (YES)
RO At least 11 RCP running. (NO)
BOP Any SIGS/G with uncontrolled depressurization. (NO)
BOP BOP Any Any S/GS/G Completely Completely Depressurized Depressurized (NO) (NO)
BOP BOP R-19s, R-31s and R-19s, R-31s and R-15 R-15 RadRad levels levels normal normal (YES) (YES)
Appendix Appendix DD NUREG-1021, NUREG-1021, Rev. Rev. 9,9, Supp.
Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test Op Test No.:
No.: 1 Scenario ##
Scenario 44 Event Event ## 8,9,10&11 8, 9, 10 & 11 Page Page 30 30 of of 36 36
-- -----II Event
Description:
Event
Description:
Small Break Small Break LOCA, LOCA, Phase Phase A A fails to actuate, fails to actuate, SI SI fails fails to to actuate, actuate, CR CR HVAC HVAC fails fails to to actuate.
actuate.
Time Time II Position Position I Applicants Actions Applicant's Actions or or Behavior Behavior BOP BOP R-2, R-32A, R-2, R-32B Rad R-32A, R-32B levels normal Rad levels normal (YES)(YES)
RO CV Pressure Normal (NO)
(This is (This PATH-i, Entry is PATH-1, Entry Point Point C)
RO Reset SPDS and initiate monitoring of CSFSTs.
CREW Open Foldout B.
BOP Request periodic activity samples of all S/Gs.
RO At least 1 1 RCP running. (NO)
BOP Any S/G with uncontrolled depressurization in progress. (NO)
BOP Control AFW flow to maintain S/G SIG levels between 8% [18%] and 50%.
BOP Any S/G with uncontrolled level increase. (NO)
BOP R-19s, R-31s and R-15 Rad levels normal. (YES)
R-31 sand RO PZR PORVs closed. (NO)
RO RCS pressure pressure> > 2335 PSIG. (NO)
RO RO PZR PZR PORVs PORVs closed.
closed. (NO)
(NO)
Appendix Appendix DD NUREG-1 NUREG-1 021, 021, Rev.
Rev. 9,9, Supp.
Supp. 11
Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 8, 9, 10 & 11 8,9,10&11 Page 31 36_ _ _-l of ...,;3;,;;6 1
Event
Description:
Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.
Time III Position IIfi Applicants Applicant's Actions or Behavior RO Close PORV blocks.
RO Open at least 11 PORV block unless closed to isolate open PZR PORV.
CONTINUOUS ACTION STEP RO If PZR PORV opens on high pressure, then verify reclosure at or below 2335 psig. Close PORV blocks as necessary.
CONTINUOUS ACTION STEP:
CREW If offsite power is lost, then restart emergency safeguard equipment.
RO Reset CV Spray.
RO Reset Phase A and Phase B.
Establish Instrument Air to CV. IF compressor not running, THEN start R0 RO compressor.
BOP Offsite power available to Charging Pumps. (YES)
RO At least 11 Charging Pump running. (YES)
RO Establish charging flow as necessary.
RO CV Spray Pumps running. (NO)
RO RCS Subcooling greater than 35 [55] degrees F. (NO)
Appendix D NUREG-1021, Rev. 9, Supp.1Supp. 1
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 44 Event ##
Event 8, 9, 10 & 11 8,9,10&11 Page Page 32 32 of .....;3;;,;6 of 36_ _ _...,1 Event
Description:
Event
Description:
Small Break LOCA, Small Break LOCA, Phase Phase AA fails fails to to actuate, actuate, SI SI fails to actuate, fails to actuate, CR CR HVAC HVAC fails fails to to actuate.
actuate.
Time Time iI Position Position II Applicants Actions Applicant's Actions or Behavior or Behavior 10 10.10 below 10-When below amps, then energize amps, energize Source Range detectors Source Range detectors and and RO RO monitor recorder.
monitor recorder.
RO RCS pressure greater than 275 psig psig [400 psig] (YES) (YES)
RO RCS pressure stable or increasing (NO)
BOP Any S/G with uncontrolled depressurization in progress. (NO) increasing.
RCS pressure increaSing.
RO PATH-i, Entry Point C. (Page 30)
(YES) Return to PATH-1, (NO) Continue below.
BOP E-1 and E-2 energized by offsite power. (YES)
BOP Starting air receivers re-pressurized to unloaded EDGs. (YES)
RO Supplement D D components capable of recirculation. (YES)
BOP BOP Aux Building radiation normal. (YES)
RO RCS pressure greater than 275 psig [400 psig]. (YES)
BOP BOP Obtain RCS boron, Obtain RCS boron, activity, and and Hydrogen Hydrogen samples. samples.
CREW CREW Transition Transition to EPP-8, EPP-8, POSTPOST LOCA LOCA CID C/D AND DEPRESSURIZATION.
Appendix Appendix D D NUREG-1021, NUREG-1 021, Rev. 9, Supp.
Rev. 9, Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test Test No.:
No.:
Op Scenario Scenario ## 44 Event ##
Event 8,9,10&11 8, 9, 10 & 11 Page Page 33 33 of .....;3:..;:;6 of 36_ _ _-11 Event
Description:
Event
Description:
Small Break Small Break LOCA, LOCA, Phase Phase AA fails fails to to actuate, actuate, SI SI fails fails to actuate, CR to actuate, CR HVAC HVAC fails fails to to actuate.
actuate.
Time Time II Position Position I Applicants Actions Applicant's Actions or Behavior or Behavior FRP-P.1, RESPONSE FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED TO IMMINENT PRESSURIZED THERMAL THERMAL SHOCK SHOCK Actions.
Actions.
Continuous Action Step: Step BOP BOP Check CST Check CST level.
level less less than 10%. 10%. (NO)
(NO)
IF CST level IF level decreases to less less than 10%, 10%, THEN perform perform Step 2.
Determine If RCS Cool Cooldown down Is Due To A Large Break LOCA:
BOP ** RCS pressure is less than 275 PSIG [400 PSIG] (NO)
AND
- RHR flow on FI-605 Fl-605 greater than 1200 GPM. (NO)
Check RCS Cold leg temperature decreasing.
BOP (NO, skip the next 5 Steps) (YES, continue below)
Attempt to Stop RCS cooldown:
- Verify STEAM LINE PORVs CLOSED.
RO/BOP
- Verify Condenser Dumps CLOSED.
- Check RHR system aligned for core cooling. (NO)
BOP Check any S/G intact. (YES)
Check level in at least one S/G >> 8% [18%].
BOP WHEN level in at least one S/G is> is > 8% [18%], THEN perform Step 8.
BOP Control Feed flow to intact S/G to stop RCS cooldown.
Identify Identify and Isolate faulted SIG:
Isolate faulted S/G:
- Any S/G S/G pressure decreasing decreasing in in an uncontrolled uncontrolled manner.
manner. (NO) (NO)
- Any Any SIG S/G completely completely depressurized.
depressurized. (NO) (NO)
Appendix Appendix DD NUREG-1 NUREG-1 021, 021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix D D Operator Action Operator Form ES-D-2 Form ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 44 Event ##
Event 8, 9, 10 & 11 8,9,10&11 Page Page 34 34 of ......;3;.;;6 of 36_ _ _..,1 Event
Description:
Event
Description:
Small Break Small Break LOCA, LOCA, Phase Phase A A fails fails to to actuate, actuate, SI SI fails fails to to actuate, actuate, CR CR HVAC HVAC fails fails to to actuate.
actuate.
Time Position I Applicants A Behavior licant's Actions or Behavior Check PORV block valves available.
RO ** Power available. (YES, Power is available to RC-536)
- At least one open. (YES)
Continuous Action Step:
- Check LLTOP TOP in service. (NO)
Check RCSpressure < 2335 PSIG. (YES)
RO Check SI Pumps running. (YES)
Determine if SI can be terminated.
- Check RCS subcooling > > 85 degrees F [105 degrees F]. (NO)
RO Check ALL RCPs stopped. (YES)
Determine If An RCP Can Be Started:
Subcooling > 35 degrees F [55 degrees F]
(NO, GoTo Go To Step 44)
Check Cooldown Cool down Rate In RCS Cold Legs> 100 100 degrees F F in any 60 RO minute period. (YES)
RO Check Check RCS Temperature - has has been stable for ONE ONE hour.
hour. (NO)
Appendix Appendix D D NUREG-1 NUREG-1 021, 021, Rev.
Rev. 9, 9, Supp.
Supp. 11
Appendix D Appendix D Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.: 1 Scenario ##
Scenario 44 Event ##
Event 8,9, 10 & 11 8,9,10&11 Page Page 35 35 of _3;;.;6~
of 36 _ _--I1 Event
Description:
Event
Description:
Small Break LOCA, Small Break Phase AA fails LOCA, Phase fails to to actuate, actuate, SI SI fails to actuate, fails to actuate, CR CR HVAC HVAC fails fails to to actuate.
actuate.
Time Time ~ Position Position III Applicants Actions Applicant's Actions or Behavior or Behavior
- Do NOT Do NOT increase increase RCS pressure.
RCS pressure.
Crew
- . Perform Perform actions of any other procedures in in effect which do NOT coolcooldown down the RCS OR increase RCS pressure. pressure.
WHEN RCS temperature has has been stable for one hour, hour, THEN Go Go To Step 46.
Observe The Following Restrictions:
- . Maintain RCS pressure and Cold Leg temperature within the limits of Attachment 1, Post Soak Cooldown Limit Curve, during ALL subsequent actions.
Crew ** Maintain coolcooldown down rate in RCS Cold Legs less than 50 degrees F/hr OR administrative limits of GP-007, PLANT COOLDOWN FROM HOT SHUTDOWN TO COLD SHUTDOWN, which ever is more restrictive in any 60 minute reriod.
period.
SRO Reset SPDS AND Return To Procedure And Step In Effect. (PATH-1) (PATH-i)
Appendix Appendix D D NUREG-i NUREG-1 021, 021, Rev.
Rev. 9,9, Supp.
Supp. i1
HLC-08 NRC HLC-08 NRC SCENARIO SCENARIO 44 TURNOVER TURNOVER SHEET SHEET POWER LEVEL:
POWER LEVEL: 50%,150 50%, 150 MWD/MTU.
MWD/MTU.
- Returning to Returning to RTP RTP following following aa short short Maintenance Maintenance Outage.
Outage.
BORON CONCENTRATION:
BORON CONCENTRATION: 1306 1306 ppm ppm EQUIPMENT UNDER EQUIPMENT UNDER CLEARANCE:
CLEARANCE:
Alignment.
oo LCO 3.7.7-A LCO 3.7.7-A has has been been entered entered and is in and is in hour hour 18 18 of of aa 72 72 TSAS.
TSAS.
o 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
Expected return is within -18 EQUIPMENT STATUS:
- Main Turbine bearings #2, 3 and 4 vibration is elevated. All actions to inform station management have been performed.
INSTRUCTIONS FOR THE WATCH:
- Increase power to 75% RTP.
Increase
- There are NO ramp rate restrictions.
Appendix Appendix DD NUREG-1021, NUREG-1021, Rev. Rev. 9, 9, Supp.
Supp. 11