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=Text=
=Text=
{{#Wiki_filter:I Appendix D Scenario Outline Form ES-D-1 Facility:
{{#Wiki_filter:I Appendix Appendix DD                                            Scenario Outline Scenario         Outline                                           Form Form ES-D-1 ES-D-l Facility:
HB ROBINSON Scenario No.: 1 Op Test No.: 2008 NRC Examiners:
Facility:            HB ROBINSON HB  ROBINSON                          Scenario No.:
Scenario        No.:          11    Op OpTest Test No.:
No.:      2008 2008 NRCNRC Examiners:
Examiners:                                                                Operators:
Operators:
Operators:
Initial Conditions:
Initial Conditions:
* 68% EOL, 17,000 MWD/MTU, 106 ppm Boron.
Conditions:            68% EOL, EOL, 17,000 17,000 MWD/MTU, MWD/MTU, 106 Initial                  **    68%                                        106 ppm     Boron.
* SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.
ppm Boron.
0 LCO 3.7.7 -A has been entered and is in hour 18 of a 72 hour action statement.
                          **      SW Booster SW    Booster Pump Pump "A"A isis Out-Of-Service Out-Of-Service for    for Motor Motor Coupling Coupling Alignment.
0 Expected return is within -18 hours.
Alignment.
* Main Turbine Vibration for #2, 3 and 4 bearings is elevated.
0o    LCO 3.7.7 LCO     3.7.7-A
                                                              -A hashas beenbeen entered entered and and isis inin hour hour 18 18 of of aa 72 72 hour hour action action statement.
statement.
0o    Expected return Expected    return isis within within -18
                                                                                      -18 hours.
hours.
                          *. Main Turbine Main  Turbine Vibration Vibration for for #2,
                                                                      #2, 33 and and 44 bearings bearings isis elevated.
elevated.
Turnover:
Turnover:
* Returning to RTP following a short Maintenance Outage. Awaiting results of post-outage testing. Maintain power at current level. Critical Task:
Turnover:                **     Returning to Returning   to RTP RTP following following aa short short Maintenance Maintenance Outage. Outage. Awaiting Awaiting results results of of post-outage testing.
* Manually restart SW pump to provide cooling to only running EDG before damaging the EDG.
post-outage     testing. Maintain Maintain powerpower at at current current level.
* Isolate feedwater to the faulted SIGs using Foldout A OR Supplement G prior to transitioning to PATH-1, Entry Point C. Event Malf. Event Type* Event No. No. Description 1 (C) BOP, SRO PR N-42 Upper Detector Fails Low. (TS) SRO 2 (I) BOP, SRO Feed Flow Channel FT-477 Fails High. (TS) SRO 3 (C) BOP, SRO Condensate Pump "A" trips which trips Feedwater Pump "A". 4 (R) RO Plant down power resulting from loss of Condensate Pump. (N) SRO, BOP 5 (C) RO, SRO RCP "C" #2 Seal fails, requiring a Reactor Trip. 6 (M) ALL Steam Break from S/Gs "8" and "C" on the Reactor Trip. 7 (C) BOP EDG "A" fails to start on the Safety Injection.
level.
8 (M) ALL Loss of Off-Site power. (Loss of SUT) 9 (C) BOP SW Pumps fail to start following restoration of power. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 1
Critical Task:
Critical  Task:                Manually restart SW  SW pump pump to provide cooling to only running EDG
                          **    Manually                                                                            EDG before damaging the EDG. EDG.
                          **     Isolate feedwater to the faulted SIGs using Foldout A OR Supplement G                                    G prior to transitioning to PATH-1, prior                            PATH-i, Entry Point C.
Event Event No.
No.
Malf.
Malf.
No.
No.
Type*
Event Type*
j J                                          Event Description 1
1                    (C) BOP, SRO           PR N-42 Upper Detector Fails Low.
(TS) SRO 22                    (I) BOP, SROSRO        Feed Flow Channel FT-477 Fails High.           High.
(TS) SRO 33                    (C) BOP, BOP, SRO SRO       Condensate Condensate Pump Pump A  "A" trips trips which which trips Feedwater Pump     Pump A."A".
44                    (R)
(R) RO                 Plant  down power Plant down     power resulting resulting from from loss loss of  of Condensate Condensate Pump. Pump.
(N)
(N) SRO, SRO, BOP BOP 55                      (C) RO, SRO (C) RO,  SRO          RCP RCP C "C" #2    Seal fails,
                                                                #2 Seal     fails, requiring requiring aa Reactor Reactor Trip.
Trip.
66                    (M)
(M) ALL ALL              Steam Steam Break Break fromfrom S/GsS/Gs B"8" and and C "C" on on the the Reactor Reactor Trip.
Trip.
77                    (C)
(C) BOP BOP              EDG   "A" fails EDG A            to start fails to   start on on the the Safety Safety Injection.
Injection.
88                    (M)
(M) ALL ALL            Loss Loss of of Off-Site Off-Site power.
power. (Loss (Loss of of SUT)
SUT) 99                      (C) BOP (C)   BOP             SW SW Pumps Pumps fail fail to to start start following following restoration restoration of of power.
power.
          * (N)ormal, (N)ormal, (R)eactivity, (R)eactivity, (I)nstrument, (I)nstrument, (C)omponen (C)omponent,   t, (M)ajor (M)ajor Appendix Appendix DD                                                                        NUREG-i NUREG-1021,    021, Rev.Rev. 9,9, Supp.
Supp. i 1
 
I Appendix DD                                Scenario Outline                             Form ES-D-i ES-D-1 SCENARIO 11


==SUMMARY==
==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.
DESCRIPTION HLC-08 NRC SCENARIO                          DESCRIPTION The crew will assume the watch with the plant at 68% RTP. The previous shift identified Turbine bearing #3 and has increased vibration on Main Turbine                       has taken all necessary   actions to inform necessary actions station management. Service Water Booster Pump A        "A" is under clearance for Motor Coupling Alignment. Shift instructions are to maintain power at current level.
Service Water Booster Pump "A" is under clearance for Motor Coupling Alignment.
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 should remove the instrument from service lAW OWP-01  OWP-011,  1, NUCLEAR INSTRUMENTATION, NI-2, NNI-42 1-42 POWER   RANGE. The   SRO will enter LCO   3.3.1. Conditions D, E, S  and T for the failed Sand instrument.
Shift instructions are to maintain power at current level. 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.
After ITS has been addressed for the PR detector, the Chief Examiner can cue the FT-477, S/G A Feed Flow instrument failure. The BOP should respond by taking Manual control of S/G A "A"                                                                                                "A" FRV and controlling S/G 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.
The crew should remove the instrument from service lAW OWP-011, NUCLEAR INSTRUMENTATION, NI-2, NI-42 POWER RANGE. The SRO will enter LCO 3.3.1. Conditions D, E, Sand T 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-01 AOP-010, 0, MAIN FEEDWATER I/ CONDENSATE MALFUNCTION. The crew should reduce Turbine load to less than 50% RTP lAW Attachment 1                  1 of AOP-010.
After ITS has been addressed for the PR detector, the Chief Examiner can cue the FT-477, S/G "A" Feed Flow instrument failure. The BOP should respond by taking Manual control of S/G "A" FRV and controlling S/G level within normal parameters.
When the Chief Examiner is satisfied with the power reduction, he can cue the RCP "c"       C #2 seal AOP-0i 8, REACTOR COOLANT PUMP ABNORMAL leak. The crew should respond using AOP-018, seal leakoff and determine a plant shutdown lAW GP-006, CONDITIONS, calculating a high sealleakoff NORMAL PLANT SHUTDOWN FROM POWER OPERATION TO HOT SHUTDOWN is required.
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 for the failed instrument.
At that time seal leakage will degrade to the point where the SRO will direct a Reactor Trip.
On cue from the Chief Examiner, Condensate Pump "A" will trip causing Feedwater Pump "A" to trip. This will result in an entry into AOP-010, MAIN FEEDWATER  
PATH-i will be entered and on the Reactor Trip a Steam Break will develop in S/Gs PATH-1                                                                                    B and "C".
/ CONDENSATE MALFUNCTION.
SIGs "B"      C.
The crew should reduce Turbine load to less than 50% RTP lAW Attachment 1 of AOP-010. When the Chief Examiner is satisfied with the power reduction, he can cue the RCP "c" #2 seal leak. The crew should respond using AOP-018, REACTOR COOLANT PUMP ABNORMAL CONDITIONS, calculating a high sealleakoff and determine a plant shutdown lAW GP-006, NORMAL PLANT SHUTDOWN FROM POWER OPERATION TO HOT SHUTDOWN is required.
After the Safety Injection has been reset and S/Gs "B"           C have been isolated, the Chief B and "C" 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.
At that time seal leakage will degrade to the point where the SRO will direct a Reactor Trip. PATH-1 will be entered and on the Reactor Trip a Steam Break will develop in S/Gs "B" and "C". After the Safety Injection has been reset and S/Gs "B" and "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" will load to the bus. Auxiliary Feedwater and Component Cooling Water loads will be restored.
The crew should respond lAW PATH-1 PATH-i and restart safeguards equipment (SI pump, RHR pump HVH units and SW pumps) manually.
The crew should respond lAW PATH-1 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.
The Chief Examiner may terminate the scenario at any time after the S/Gs have been isolated and Service Water cooling to the EDG has been restored.
Appendix D                                                     NUREG-iO2i, Rev. 9, Supp. 11 NUREG-1021,
Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 1 SIMULATOR SETUP IC/SETUP
 
* IC-601, SCN: 006_Sim_1.
I Appendix D                                 Scenario Outline                           Form ES-D-1 HLC-08 NRC SCENARIO 11 SIMULATOR SETUP IC/SETUP
* SW Booster Pump "A" is OFF, breaker OPEN and switch is RED CAPPED.
* lC-601, SCN:
IC-601, SON: 006_Sim_1.
* 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.
* Main Turbine Bearing #2 is OFFSET by 1.5, #3 by 2.3 and #4 by 1.7.
* Status board updated to reflect IC-17. PRE-LOADED EVENTS: The following events should occur on the reactor trip:
* 10-17.
* Event 6: Steam Break from S/Gs "B" and "c" on the Reactor Trip.
Status board updated to reflect IC-17.
* Event 7: EDG "A" fails to start on the Safety Injection.
PRE-LOADED EVENTS:
* Event 9: SW Pumps fail to start on restoration following LOOP. EVENTSITRIGGERS INITIATED DURING THE SCENARIO:
The following events should occur on the reactor trip:
* Event 6: Steam Break from S/Gs "B"   B and "c" 0 on the Reactor Trip.
* A fails to start on the Safety Injection.
Event 7: EDG "A"
* Event 9: SW Pumps fail to start on restoration following LOOP.
EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:
EVENTSITRIGGERS
* Event 1: PR N-42 Upper Detector fails low.
* Event 1: PR N-42 Upper Detector fails low.
* Event 2: Feed Flow channel FT-477 fails high.
* Event 2: Feed Flow channel FT-477 fails high.
* Event 3: Condensate Pump "A" trips causing Feedwater Pump "A" to trip.
* Event 3: Condensate Pump "A"   A trips causing Feedwater Pump "A"A to trip.
* Event 4: Plant down power resulting from Condensate Pump "A" trip.
* Event 4: Plant down power resulting from Condensate Pump A    "A" trip.
* Event 5: RCP "c" #2 Seal fails, requiring a Reactor Trip.
* Event 5: RCP "c" C #2 Seal fails, requiring a Reactor Trip.
* Event 8: Loss of Off-Site Power. (Loss of SUT) EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED: OWP-011, NI-2; AOP-025, Section E; OWP-026, FWF-2; AOP-010; AOP-018; PATH-1; Foldouts A & B; EPP-11; Supplement G. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # Event # Page 4 of 26 Event
* Event 8: Loss of Off-Site Power. (Loss of SUT)
EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
OWP-O11,   Nl-2; AOP-025, Section E; OWP-026, FWF-2; AOP-O1O; OWP-011, NI-2;                                                AOP-010; AOP-018; PATH-1; PATH-i; EPP-1 1; Supplement G.
Foldouts A & B; EPP-11; Appendix D D                                                    NUREG-1021, Rev. 9, Supp. 11
 
Appendix D                                       Operator Action                                         Form ES-D-2 Op Test Test No.:
No.:                Scenario #
Op Scenario          1      Event #
Event              1
                                                                      ~---------
Page Page   4   of of   26
                                                                                                        -~------~I Event


== Description:==
== Description:==


PR NI-42 Upper Detector fails low. Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR:
Event  
When directed by the Chief Examiner, insert Event 1, PR N-42 Upper Detector fails low. EVENT INDICATIONS:
APP-003-86; Overpower f1T APP-003-C6; Overtemp f1T APP-OOS-A3; PR Dropped Rod APP-OOS-C3; PR Channel Dev APP-OOS-DS; OTf1T/OPf1T Turbine Runback Rod Stop APP-OOS-F3; PR Upper Ch Hi Flux Dev I Auto Defeat APP-OOS-D6; f1 Flux Warning I Status N-42 f1 Flux meter (NI-42C) pegged LOW Upper Detector (A) on N-42 Drawer indicates low On NR-4S and NR-47 Recorders, N-42 reads lower than other Power Range Nis 8istables for: OT f1 T Loop 2 TC422C1, OT f1 T Rod Stop TC422C2 OPf1T Loop 2 TC42281, OPf1T Rod Stop TC42282 RO Recognizes that N-42 has failed and there is NO dropped rod. References APPs to determine actions or recommendations.
SRO Reviews, briefs and directs taking N-42 instrument out of service using OWP-011, NI-2. Reviews ITS for applicable LCOs
* Table 3.3.1-1, #2 -Condition D; Place channel in Trip within 6 hours.
* Table 3.3.1-1, #5 and 6 -Condition E: Place channel in Trip SRO within 6 hours.
* Table 3.3.1-1, #17c -Condition T; Verify interlock is in required state within 1 hour.
* Table 3.3.1-1, Item #17d -Condition S: Verify interlock is in required state within 1 hour. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 1 Event # Page 5 of 26 Event


== Description:==
== Description:==
PR NI-42 PR  Nl-42 Upper  Detector fails low.
Upper Detector        low.
Time      III  Position    II                                Alicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 1, PR N-42 Upper Detector fails low.
EVENT INDICATIONS:
APP-003-B6; Overpower f1T APP-003-86;                  T APP-003-C6; Overtemp f1T    T APP-005-A3; PR Dropped Rod APP-OOS-A3; APP-005-C3; PR Channel Dev APP-OOS-C3; APP-005-D5; OTf1T/OPf1T APP-OOS-DS;      OThT/OPT Turbine Runback Rod Stop APP-005-F3; PR Upper Ch Hi Flux Dev I Auto Defeat APP-OOS-F3; APP-005-D6; f1 Flux Warning I Status APP-OOS-D6; (Nl-42C) pegged LOW N-42 f1 Flux meter (NI-42C)
Upper Detector (A) on N-42 Drawer indicates low NR-45 and NR-47 Recorders, N-42 reads lower than other Power Range Nis On NR-4S                                                                                Nls Bistables for:
8istables OThT OT f1T Loop 2 TC422C1, OT    OThT f1T Rod Stop TC422C2 OPtJ Loop 2 TC42281, OPf1T            TC422B1, OPf1T OPAT Rod Stop TC42282 TC422B2 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.Nl-2.
Reviews ITS for applicable LCOs
                                      *. Table 3.3.1    -1, #2 - Condition D; Place channel in Trip within 6 3.3.1-1, hours.
                                      *. Table 3.3.1-1, #5 and 6-        6 - Condition E: Place channel in Trip SRO                    within 6 hours.
                                      .
* Table 3.3.1-1, #17c - Condition T; Verify interlock is in required state within 1  1 hour.
                                        **  Table 3.3.1-1, Item #17d - Condition S: Verify interlock is in required state within 1        1 hour.
Appendix D  D                                                                  NUREG-1 021, Rev. 9, Supp. 11


PR NI-42 Upper Detector fails low. Time II Position Applicant's Actions or Behavior Perform OWP-011, NI-2 actions to remove channel from service.
Appendix D                              Operator Action                                      Form ES-D-2 Op Test No.:        1    Scenario #    11    Event #        1                Page    5 of  26
* Removes N-42 from ERFIS scan. 0 (APP-005-D6 will be received)
                --                                          ~--------                        ~------~I Event
* Places DROPPED ROD MODE switch on N-42 drawer in the BYPASS position.
 
0 (APP-005-D4 will be received and NIS ROD DROP BYPASS N-42 status light will ILLUMINATE.) (APP-036-L 1 will be received when Hagan Rack door is opened)
== Description:==
* Places N-42 OUT OF SERVICE TRIP SWITCH in the TRIPPED position.
Nl-42 Upper Detector fails low.
BOP 0 (APP-005-A4 received)
PR NI-42 Time     II Position ~                            Applicants Applicant's Actions or Behavior OWP-01 1, NI-2 actions to remove channel from service.
* ROD STOP BYPASS switch selected to BYPASS PR42.
Perform OWP-011,
                                *. Removes N-42 from ERFIS scan.
0o  (APP-005D6 will be received)
(APP-005-D6
                                ** Places DROPPED ROD MODE switch on N-42 drawer in the BYPASS position.
0o  (APP-005-D4 will be received and NIS ROD DROP BYPASS N-42 status light will ILLUMINATE.)
(APP-036-L11 will be received when Hagan Rack door is opened)
(APP-036-L
                                *. Places N-42 OUT OF SERVICE TRIP SWITCH in the TRIPPED position.
BOP                   0o (APP-005-A4 received)
                                  *. ROD STOP BYPASS switch selected to BYPASS PR42.
* COMPARATOR CHANNEL DEFEAT switch placed in the PR42 position.
* COMPARATOR CHANNEL DEFEAT switch placed in the PR42 position.
0 (APP-005-C3 clears and COMPARATOR DEFEAT light illuminates above the switch)
0o (APP-005-C3 clears and COMPARATOR DEFEAT light illuminates above the switch)
* Selects PR42 on UPPER and LOWER SECTION Switches.
* Selects PR42 on UPPER and LOWER SECTION Switches.
0 (APP-005-F3 clears, UPPER SECTION DEVIATION light on drawer clears and CHANNEL DEFEAT light on drawer UPPER SECTION ILLUMINATES) 0 (CHANNEL DEFEAT light on drawer LOWER SECTION ILLUMINATES)
0o (APP-005-F3 clears, UPPER SECTION DEVIATION light on drawer clears and CHANNEL DEFEAT light on drawer UPPER SECTION ILLUMINATES) 0o (CHANNEL DEFEAT light on drawer LOWER SECTION ILLUMINATES)
Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-O-2 Op Test No.: Scenario # 1 Event # 2 Page 6 of 26 Event
Appendix D                                                           NUREG-1 021, Rev. 9, 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            11      Event ##
Event                22                Page Page     66    of of   26 26
                  ~-                                                      ~--------                                ~------~I Event


== Description:==
== Description:==


Feed Flow channel FT-477 fails high. Time J Position II Applicant's Actions or Behavior BOOTH OPERATOR:
Event
At the discretion of the Chief Examiner, insert Event 2, Feed Flow channel FT-477 fails high. EVENT INDICATIONS:
 
APP-006-A1; S/G A FW > STM FLOW (Clears on lamp Acknowledge)
== Description:==
APP-006-A2; S/G A STM > FW FLOW APP-006-A3; S/G A lVl DEV APP-006-D1:
Feed Flow Feed     Flow channel channel FT-477 FT-477 fails fails high.
S/G A NAR RANGE lO/lO-lO 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. BOP Immediate Actiol1 Step: Place the affectedFRV(FCV:'478.forS/G "A") in MAN . ...... BOP Immediate Action$tep:
high.
Restore Affected S/G Level To Between 39% And 52%. RO/BOP Make PA announcement for entry into AOP-025. BOP Place the affected S/G Feed Flow Selector Switch to the alternate channel. (CH-476, FR-478 recorder pen will return to normal status) Continuous Action Step: Restore Affected Controller To Automatic:
Time Time    J     Position Position     II                                     Applicants Actions Applicant's     Actions or or Behavior Behavior BOOTH OPERATOR:
BOP
BOOTH    OPERATOR: At          At the the discretion discretion of  of the the Chief Chief Examiner, Examiner, insert insert Event Event 2,2, Feed Feed Flow Flow channel FT-477 channel       FT-477 fails fails high.
* CheckS/G level within+/- 1 % of programmed level. (If YES, place in Auto and Go To Step 6) WHEN S/G level is within +/- 1 % ofprogrammed level, TH EN place the affected Controller in AUTO. Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # --2 Page 7 of 26 Event
high.
EVENT INDICATIONS:
EVENT   INDICATIONS:
APP-006-A1; S/G APP-006-A1;  SIG AA FW FW >> STM STM FLOWFLOW (Clears (Clears onon lamp Lamp Acknowledge)
Acknowledge)
APP-006-A2; S/G APP-006-A2;  SIG AA STM STM >> FW FW FLOW FLOW APP-006-A3; S/G APP-006-A3;  SIG AA lVl LVL DEV DEV APP-006-D1: S/G APP-006-D1:  SIG A NAR NAR RANGE RANGE lO/lO-lO LOILO-LO lEVELLEVEL FR-478 Green Pen FR-478          Pen goes high and        FCV-478 closes and FCV-478     closes Recognizes FT-477 has failed and performs Immediate                Immediate Actions for BOP AOP-025, RTGB INSTRUMENT INSTRUMENT FAILURE.
SRO           Enters AOP-025, RTGB INSTRUMENT        INSTRUMENT FAILURE, Section E.
Immediate Actiol1 Action Step:
BOP Place the affected        FRV  ...... (FCV-478 for S/G A) affectedFRV(FCV:'478.forS/G                     "A") in MAN MAN..
Immediate Immediate ActionAction$tep: Step:
BOP Restore Affected S/G Level To Between            Between 39% And 52%.
RO/BOP           Make PA announceme announcement         nt for entry into AOP-025.
Place Place the affected affected S/G Feed      Feed Flow Flow Selector Switch to   to the the alternate BOP BOP            channel. (CH-476, (CH-476, FR-478 FR-478 recorder pen          pen will will return to to normal status) status)
Continuous Continuous Action Action Step:
Step:
Restore Restore Affected Affected Controller Controller To        To Automatic:
Automatic:
BOP BOP                *
* Check CheckS/G SIG level level withinwithin+/-  +/- 1%
1% of of programmed programmed level. level. (If (If YES, YES, place place in in Auto Auto andand Go    Go To  To Step Step 6) 6)
WHEN WHEN S/G  S/G level         within +/-+/- 1%
is within level is                    1% of  programmed level, ofprogrammed       level, THEN TH EN place place the the affected affected Controller Controller in in AUTO.
AUTO.
Appendix Appendix D0                                                                          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 #      1 1    Event #      2                Page    7 of  26
                -    -                                      ~-------                        ~~----~I Event
 
== Description:==
Feed Flow channel FT-477 fails high.
Time      I  Position  III                          Applicant's Actions or Behavior Applicants Reviews, briefs and directs taking FT-477 instrument out of service SRO using OWP-026, FWF-2.
Remove the affected transmitter from service using OWP-026, FWF-2.
                                  *. FR.-478 selector switch selected to CH-476.
FR-478 BOP            **  Remove FT-477 input to the CALO program.
(APP-036-L11 will be received when Hagan Rack door is opened)
(APP-036-L
                                  **  Trip bistable FC-478B-1. (APP-006-A2 will be received)
SRO        Go To Procedure Main Body, Step 2.
SRO        Implement the EALs.
Review ITS for applicable LCO.
SRO
                                    ** 3.3.1-1, #14 Condition E - Trip bistable within 6 hours.
SRO        Return to procedure and step in effect.
Appendix D                                                          NUREG-1 021, Rev. 9, Supp. 11
 
Appendix D                                 Operator Action                                           Form ES-D-2 Op Test No.:       1      Scenario #     11      Event #       _3;;....
3 _ _ _ _ Page            8    of _2_6 26_ _ _ _
                  ~-                                                                                              11 Event
 
== Description:==
Condensate Pump "A" A trips which trips Feedwater Pump "A".
A.
Time Tim          Position    !                              Applicants Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 3, Condensate A trips which results in the tripping of MFP"A".
Pump "A"                                                    MFPA.
EVENT INDICATIONS:
APP-007-A1; APP-007-A1 j COND PMP A MOTOR OVLDrrRIPOVLDITRIP (Extinguishes on Lamp acknowledge)
APP-006-A3;  SIG A LVL DEV, APP-006-B3j APP-006-A3j S/G                                SIG 8B LVL DEV, APP-006-C3; APP-006-B3; S/G                                SIG C LVL DEV (later)
APP-006-C3j S/G Condensate Pump "A"  A and Main Feedwater Pump "A"    A breaker open.
Recognizes loss of Condensate/Feed Pump and performs immediate BOP          actions of AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION.
Immediate Action Step:
BOP                  Feedwater Regulating Valves.Operating Check FeedwaterRegulating Check                                  Valves Operating Properly in Manual OR Auto. (YES)
Continuous Action Step:
Reactor Trip Setpoint Being Approached.
Check Heactor                                Approached. (NO)
SRO IF a Reactor Trip Setpoint is approached, THEN      THEN trip the Reactor and PATH-i. (Go To Step 4)
Go To PATH.,.1.
RO      1 Make PA Announcement for Procedure Entry into AOP-0i          AOP-01 O. 0.
I SRO        I  Go to appropriate step: Condensate AND Feed Pump Trip, Step 10.
RO      1 Check Reactor Power less than 70%. (YES)
RO      1 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.
Appendix D                                                                  NUREG-i 021, Rev. 9, Supp. 11 NUREG-1
 
Appendix 0D Appendix                                      Operator Action Operator        Action                                                Form Form ES-D-2 ES-D-2 Test No.:
Op Test  No.:
Op Scenario ##
Scenario          11        Event ##
Event            44 Page Page       99  of of   26 26
                                                                                                                      ~~----~I Event


== Description:==
== Description:==


Feed Flow channel FT-477 fails high. Time I Position II Applicant's Actions or Behavior SRO Reviews, briefs and directs taking FT-477 instrument out of service using OWP-026, FWF-2. Remove the affected transmitter from service using OWP-026, FWF-2.
Event  
* FR-478 selector switch selected to CH-476. BOP
* Remove FT-477 input to the CALO program. (APP-036-L 1 will be received when Hagan Rack door is opened)
* Trip bistable FC-478B-1. (APP-006-A2 will be received)
SRO Go To Procedure Main Body, Step 2. SRO Implement the EALs. SRO Review ITS for applicable LCO.
* 3.3.1-1, #14 Condition E -Trip bistable within 6 hours. SRO Return to procedure and step in effect. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # _3;;.... ____ Page 8 of _2_6 ____ 11 Event


== Description:==
== Description:==
Plant down Plant  down power power resulting resulting from from Condensate Condensate PumpPump "A" A trip.
trip.
Time Time      I1  Position Position    I                                  Applicants Actions Applicant's  Actions or  or Behavior Behavior Attachment 11 - Turbine Attachment              Turbine Load  Load Reduction Reduction Check Turbine
                                    *. Check      Turbine Control Control ModeMode inin automatic.
automatic. (YES)(YES)
Depress the
                                    *. Depress        the IMP IMP IN  IN Pushbutton.
Pushbutton.
BOP BOP Set the
                                    *. Set  the desired desired loadload inin the the SETTER.
SETTER.
                                    ** Set Set desired desired load load rate.
rate.
                                    *. Depress the Depress      the GO      Pushbutton.
GO Pushbutton.
NOTE:                          OP-301, Section 8.2.8 Quick Boration        Boration Checklist (shaded area) is included in  in the following steps, but may be used following the commencement of the plant down power.
commencement The crew should add - 100 gallons of Boric Acid for the 18%
down power.
DETERMINE the amOl.lnt DETERMINE                amount of  of Boric Acid to add to the RCSand      RCS and RD RO OBTAIN an independent check of thevolume          the volume required.
RO        OBTAIN permission from the CRSS OR the SSO                          SSOto      borate.
to borate.
RD RO        PLACE the  theRCS RCS MAKEUP MAKEUP MODE selector switch to BORATE.
RD RO        SET SET YIC-1    13, BORIC YIC':113,                ACID TOTALIZER to BOR.ICACIDTOTALIZER                      to desired desired quantity.
quantity.
IF IF desired, desired,THENTHEN PLACE  PLACE FCV-1 FCV-113A,1 3A, BORIC BORIC ACID    ACID FLOW, FLOW, in in MAN MAN RD RO        AND AND ADJUST ADJUST using  using the the UP UP andand DOWN DOWN pushbuttons.
pushbuttons.
RD RO        Momentarily Momentarily PLACE  PLACE the        RCS MAKEUP SYSTEM switch the.RCS*MAKEUPSYSTEM                        switch toto START.
START.
IF IF any any of  the below ofthe    below conditions conditions occur, occur, THENTHEN momentarily momentarily placeplace the the RCS RGS MAKEUP MAKEUP SYSTEM  SYSTEM switch  sWitch inin the the STOP STOP position:
position:
RD RO            ** RodRod Motion Motion isis blocked blocked OR  OR isis inin the the wrong wrong direction direction
                                    ** TAvG      increases T AvGincreases
                                    .* Boric Boric AcidAcid addition addition exceeds exceeds the  the desired desired value value Appendix Appendix D0                                                                    NUREG-1021, NUREG-1            021, Rev.
Rev. 9,9, Supp.
Supp. 11


Condensate Pump "A" trips which trips Feedwater Pump "A". Tim Position ! Applicant's Actions or Behavior BOOTH OPERATOR:
Appendix D D                                          Operator Action                                                             Form ES  D2 ES-D-2 Op Test No.:
When directed by the Chief Examiner, insert Event 3, Condensate Pump "A" trips which results in the tripping of MFP"A". EVENT INDICATIONS:
APP-007-A1 j COND PMP A MOTOR OVLDrrRIP (Extinguishes on Lamp acknowledge)
APP-006-A3j S/G A LVL DEV, APP-006-B3j S/G 8 LVL DEV, APP-006-C3j S/G C LVL DEV (later) Condensate Pump "A" and Main Feedwater Pump "A" breaker open. Recognizes loss of Condensate/Feed Pump and performs immediate BOP actions of AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION.
Immediate Action Step: BOP Check FeedwaterRegulating Valves.Operating Properly in Manual OR Auto. (YES) Continuous Action Step: SRO Check Heactor Trip Setpoint Being Approached. (NO) IF a Reactor Trip Setpoint is approached, THEN trip the Reactor and Go To PATH.,.1. (Go To Step 4) RO Make PA Announcement for Procedure Entry into AOP-01 O. 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) BOP Reduce Turbine load at 1 %/MIN to 5%/MIN to achieve less than 50% Reactor Power using Attachment
: 1. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # --4 Page 9 of 26 ----------
Event
Event


== Description:==
== Description:==


Plant down power resulting from Condensate Pump "A" trip. Time II Position I Applicant's Actions or Behavior Attachment 1 -Turbine Load Reduction
1      Scenario #                    1 1          Event #
* Check Turbine Control Mode in automatic. (YES) BOP
Plant down power resulting from Condensate Pump "A" 4
* Depress the IMP IN Pushbutton.
                                                                                    ~--------
* Set the desired load in the SETTER.
Page A trip.
* Set desired load rate.
10 10  of  26
* Depress the GO Pushbutton.
                                                                                                                                    ~------~I Time     I  Position  II                                                 Applicant's Actions or Behavior Applicants WHEN the desired amount of Boric Acid                                Acid*hashas been added, THEN verify the following:
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. RO DETERMINE the amOl.lnt of Boric Acid to add to the RCSand OBTAIN an independent check of thevolume required.
RO              ** FCY-113A,  FCV-1 13A, BORIC ACID              ACID FLOW, closes.
RO OBTAIN permission from the CRSS OR the SSOto borate. RO PLACE theRCS MAKEUP MODE selector switch to BORATE. RO SET YIC':113, BOR.ICACIDTOTALIZER to desired quantity. . RO IF desired,THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN AND ADJUST using the UP and DOWN pushbuttons.
                                    ** FCY-113B,BLENDEDMU FCV-1 1 3B, BLENDED MU TO CHG                          CHGSUCT, SUCT, closes closes.
RO Momentarily PLACE the.RCS*MAKEUPSYSTEM switch to START. IF any ofthe below conditions occur, THEN momentarily place the RGS MAKEUP SYSTEM sWitch in the STOP position:
                                    ** IF              in     Auto,      THEN THEN    the   operating operating Boric    Boric  Acid  Pump stops.
RO
Pump
* Rod Motion is blocked OR is in the wrong direction
                                    ** The RCSMAKEUP        RCS MAKEUP SYSTEM isOFF.                 is OFF.
* T AvGincreases
IF desired, THEN            THEN FLUSH the           the*Boric       Acid flow path as follows.
* Boric Acid addition exceeds the desired value Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -----Scenario # 1 Event # 4 Page 10 of 26 Event
Boric Acid.flow                      follows:
                                      ** PLACEthe PLACE the RCS MAKEUP MODE selector switch in the AL                                    ALT T DILUTE DILUTEposition. position.
                                      ** SET YIC-114,        YIC-1 14, PRIMARY WTR TOTALIZER to 15-20 gallons.
                                        ** PLACE FCY-114B,         FCV-1 14B, BLENDED MU TO VCT                      YCT to CLOSE.
                                    ** Momentarily PLACE the RCS.MAKEUP                      RCS MAKEUP SYSTEM switch to the START ST  ART position~
position.
                                        ** IF any of the below              below conditions occur, THEN momentarily place RO                                      RCS MAKEUP SYSTEM switch in the RCSMAKEUP                                                  in the STOP position:
o Unanticipated R6d*Motion    Rod Motion 0o    Primary Water addition re.aches Prima.ryWateraddition                  reaches the  the desired value
                                          ** WHEN the desired amount of                          of Primary WaterhasWater has been added the RCS, THEN verify to the.                          verify the following:
0o    FCV-1        1 4A FCY:-114Acloses. closes.
0o      FCV-1 1 3B closes.
FCY-1136 0o    IF in Auto, IFin      Auto, THEN the operating PW Pump stops.
0o      The RCS MAKEUP SYSTEM is OFF.
TheRCS RETURN the RCS Makeup.                                System to automatic as Makeup System                                as follows:
                                      ** VERIFY FCV.::f14A          FCV-1 1 4A is in AUTO.
                                          ** PLACE FCY::114B      FCV-1 14B to the AUTO position.
RO                ** PLACE the RCSMAKEUP              RCS MAKEUP MODE switch in AUTO.
                                            ** VERIFY FCY-113A      FCV-1 1 3A is in AUTO; AUTO.
                                        *
* Momentarily PlACE.the        PLACE the RCS MAKEUP SYSTEM switch in the START position.
START RECORD, in AUTO LOG; RECORO,in                                    LOG, ?sindicated              by PRIMARY WATER as indicated byPRIMARYWATER RO          TOTALIZER, YIC-1 14 AND BoricAcid TOTALlZER,YIC-114ANO                                                      TOTALIZER, YIC-113 Boric Acid TOTALIZER,                  YIC-1 13 the total IDrm,r,            AI,fr amount of Primary Water ANDBoric.Acid.added during the mt-i          I,,f t-f                              AFJfl  Bfr      A,irl  rit1rl    rh  Irnt  fhc boration.
h,rfit,,,  -
MONITOR parameters                .-.rp.--,.--, for the expected change in reactivity AND RO                                                                                                      boration intorm the CRSSORthe inform                  GHS OR the SSG.            U ofthe ot the results of      ot the boration.
Appendix D                                                                                  NUREG-1 021, Rev. 9, Supp. 11
 
Appendix 0D Appendix                                     Operator Action Operator       Action                                             Form Form ES-D-2   ES-D-2 Test No.:
No.:
Op Test Op Scenario Scenario ##        11      Event ##
Event          4
_4..:....-_ _ _ _ Page  Page       11 11  of        26_ _ _-11 of .....:2:;.;;6 Event
 
== Description:==
 
Event


== Description:==
== Description:==
Plant  down power Plant down            resulting from power resulting    from Condensate Condensate Pump Pump "A" A trip.
trip.
Time Time    1    Position Position  II                                Applicants Actions Applicant's    Actions or or Behavior Behavior BOP BOP        Check at Check    at least least 11 Main Main Feed Feed Pump Pump running.
running. (YES, (YES, GoGo To StepStep 37)    37)
BOP        Check SIGS/G Level at or trending to program. (YES)
RO        Check T  TAVG AVG at or trending to T          REF. (YES)
TREF.
SRO        Contact Maintenance to troubleshoot and correct Feedwater problem.
SRO        Implement the EALs.
Check current loading for the following pumps less than maximum.
                                    *. Main Feedwater Pump -0.715          0.715 KAMPS BOP
* Condensate Pump - 370 AMPS
                                    *. Heater Drain Pumps - 90 AMPS BOOTH OPERATOR: When contacted, wait 3 minutes and report that Main Feedwater 800TH 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% in one hour. (NO, Go To Step 43)
Continuous Continuous Action Action* Step:
Check    APP-005~B5, ROD BANKS A/B/C/D Check APP-005-B5,                                AlB/C/DLO    LO LIMIT LIMIT extinguished.
RD RO        (YES)
IF alarm IF        is illuminated, THEN alarm is                    THEN Borate Borate to to clear the the alarm alarm using using OP-301    OP-301 while while continuing continuing in  in this this procedure.
procedure.
RO        Monitor Monitor Axial Flux Flux Difference Difference to ensure ensure compliance compliance with LCD    LCO 3.2.3 Appendix Appendix D0                                                                  NUREG-1021, NUREG-1021, Rev. Rev. 9, 9, Supp.
Supp. 11


Plant down power resulting from Condensate Pump "A" trip. Time I Position II Applicant's Actions or Behavior WHEN the desired amount of Boric Acid*has been added, THEN verify the following:
Appendix D Appendix     D                              Operator Action Operator        Action                                        Form Form ES-D-2 ES-D-2 Op Test No.:
* FCY-113A, BORIC ACID FLOW, closes. RO
Op Test No.:        1      Scenario ##
* FCY-113B,BLENDEDMU TO CHGSUCT, closes.
Scenario        1       Event ##
* IF in Auto, THEN the operating Boric Acid Pump stops.
Event          4
* The RCSMAKEUP SYSTEM isOFF. IF desired, THEN FLUSH the*Boric Acid.flow path as follows:
_4~_____            Page Page      12 12    of  26 of ....;;..;......-----ll 26 Event
* PLACEthe RCS MAKEUP MODE selector switch in the AL T DILUTEposition.
* SET YIC-114, PRIMARY WTR TOTALIZER to 15-20 gallons.
* PLACE FCY-114B, BLENDED MU TO YCT to CLOSE.
* Momentarily PLACE the RCS.MAKEUP SYSTEM switch to the ST ART
* IF any of the below conditions occur, THEN momentarily place RO the RCSMAKEUP SYSTEM switch in the STOP position:
o Unanticipated R6d*Motion 0 Prima.ryWateraddition re.aches the desired value
* WHEN the desired amount of Primary Waterhas been added to the. RCS, THEN verify the following:
0 FCY:-114Acloses.
0 FCY-1136 closes. 0 IFin Auto, THEN the operating PW Pump stops. 0 TheRCS MAKEUP SYSTEM is OFF. ... .. .. RETURN the RCS Makeup. System to automatic as follows:
* VERIFY FCV.::f14A is in AUTO.
* PLACE FCY::114B to the AUTO position.
RO
* PLACE the RCSMAKEUP MODE switch in AUTO.
* VERIFY FCY-113A is in AUTO;
* Momentarily PlACE.the RCS MAKEUP SYSTEM switch in the START position.
RECORO,in AUTO LOG; ?sindicated byPRIMARYWATER RO TOTALlZER,YIC-114ANO BoricAcid TOTALIZER, YIC-113 the total amount of Primary Water ANDBoric.Acid.added during the boration.
RO MONITOR parameters for the expected change in reactivity AND inform the CRSSORthe SSG. ofthe results of the boration.
Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: --Scenario # 1 Event # _4..:....-
____ Page 11 of .....:2:;.;;6
___ -11 Event


== Description:==
== Description:==


Plant down power resulting from Condensate Pump "A" trip. Time 1 Position II Applicant's Actions or Behavior BOP Check at least 1 Main Feed Pump running. (YES, Go To Step 37) BOP Check SIG Level at or trending to program. (YES) RO Check T AVG at or trending to T REF. (YES) SRO Contact Maintenance to troubleshoot and correct Feedwater problem. SRO Implement the EALs. Check current loading for the following pumps less than maximum. BOP
Event
* Main Feedwater Pump -0.715 KAMPS
* Condensate Pump -370 AMPS
* Heater Drain Pumps -90 AMPS 800TH OPERATOR:
When contacted, wait 3 minutes and report that Main Feedwater Pump "8" is 530 AMPS, Condensate Pump "8" is 320 AMPS and Heater Drain Pumps are 80 AMPS each. RO Determine Iodine Sampling Requirements:
Check Power change> 15% in one hour. (NO, Go To Step 43) Continuous Action* Step: Check ROD BANKS AlB/C/DLO LIMIT extinguished.
RO (YES) IF alarm is illuminated, THEN Borate to clear the alarm using OP-301 while continuing in this procedure.
RO Monitor Axial Flux Difference to ensure compliance with LCO 3.2.3 Appendix 0 NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ....;..--Scenario # Event #
Page 12 of 26 ....;;..;......-----ll Event


== Description:==
== Description:==
Plant down Plant down power power resulting resulting from from Condensate Condensate Pump Pump "A" A trip.
trip.
Time Time    J    Position Position    II                              Applicants Actions Applicant's Actions or or Behavior Behavior SRO SRO          Notify Load Notify Load Dispatcher Dispatcher of  of the the unit's units load load capability.
capability.
SRO          Return to procedure and step in effect.
Examiner, insert Event 5.
At the discretion of the Chief Examiner, Appendix Appendix D  D                                                            NUREG-1 021, NUREG-1      021, Rev. 9, Supp.
Rev. 9,  Supp. 11


Plant down power resulting from Condensate Pump "A" trip. Time J Position II Applicant's Actions or Behavior SRO Notify Load Dispatcher of the unit's load capability.
Appendix D D                                Operator Action                                      Form ES-D-2 Op Test No.:
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 Appendix D Op Test No.: --Event
Scenario #        1 1      Event #        5, 6 & 7
                                                                ~~~----
Page    13 of  26
                                                                                                  ~~----~I Event


== Description:==
== Description:==
RCP "e" Rep  C #2 Seal fails, requiring a Reactor Trip.
Steam Break from S/Gs      B and "e" S!Gs "B"      C on the Reactor Trip.
A fails to start on Safety Injection.
EDG "A" Time      II  Position  I                                Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 5, RCP "C"                          C #2 Seal failure requiring Reactor Trip.
EVENT INDICATIONS:
APP-OO1-C5; RCP STANDPIPE HI/LO LVL (RCP C STP HI)
APP-001-C5; FR 154A, Pen 3 (Blue), C RCP Seal Leakoff decreasing RO      Recognizes decreasing sealleakoffseal leakoff and references APP-001-C5.
APP-001 -C5.
IF Standpipe level is High, THEN check for rising level in the Reactor RO Coolant Drain Tank.
BOOTH OPERATOR: When requested by the crew wait 3 minutes and inform the crew that RCDT level is slowly rising. (1% in the last 3 min.)        mm.)
SRO                AOP-01 8, RCP ABNORMAL CONDITIONS, Section A.
Enters AOP-018, Continuous Action Step:
RO      Check any RCP#1 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        < 0.8 GPM. (NO, Go To Step 14)
IF Seal Leakoff decreases to <          < 0.8 GPM, THEN Go To Step 9.
RO      Check RCP #2 Seal problem suspected. (YES)
Check RCP #2 Seal Leakoff rate known. (NO)
SRO      Dispatch an operator to perform Att. 2, RCP Seal Leak Rate Calculation. WHEN calculation is complete, THEN Go To Step 16.
Appendix D D                                                            NUREG1 021, Rev. 9, Supp. 11 NUREG-1


Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 13 of 26 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.
Appendix D                                    Operator Action                                           Form ES-D-2 Op Test No.:
Time II Position I Applicant's Actions or Behavior BOOTH OPERATOR:
Op      No.:        1 Scenario ##
When directed by the Chief Examiner, insert Event 5, RCP "C" #2 Seal failure requiring Reactor Trip. EVENT INDICATIONS:
Scenario            11      Event #
APP-001-C5; RCP STANDPIPE HI/LO LVL (RCP C STP HI) FR 154A, Pen 3 (Blue), C RCP Seal Leakoff decreasing RO Recognizes decreasing sealleakoff and references APP-001-C5.
Event          5, 66 &
RO IF Standpipe level is High, THEN check for rising level in the Reactor Coolant Drain Tank. BOOTH OPERATOR:
5,   & 77          Page Page    14 14  of of  26 26
When requested by the crew wait 3 minutes and inform the crew that RCDT level is slowly rising. (1% in the last 3 min.) SRO Enters AOP-018, RCP ABNORMAL CONDITIONS, Section A. Continuous Action Step: RO Check any RCP#1 Sealleakoff flow> 5.7 GPM. (NO, Go To Step 8) IF sealleakoff*
                                                                    ~~~----                             ~~----~I Event
exceeds 5.7 GPM, THEN Go To Step 2. Continuous Action Step: RO Check indicated
#1 Seal Leakoff <0.8 GPM. (NO, Go To Step 14) IF Seal Leakoff decreases to < 0.8 GPM, THEN Go To Step 9. RO Check RCP #2 Seal problem suspected. (YES) Check RCP #2 Seal Leakoff rate known. (NO) SRO Dispatch an operator to perform Att. 2, RCP Seal Leak Rate Calculation.
WHEN calculation is complete, THEN Go To Step 16. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: .-;...-Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 14 of 26 RCP "C" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "C" on the Reactor Trip. EDG "A" fails to start on Safety Injection.
Event
Time II Position Applicant's Actions or Behavior BOOTH OPERATOR:
 
When requested to perform Leak Rate Calculation, wait 5 minutes and inform the crew that RCP #2 Seal leakoff is 1.3 GPM. Continuous Action Step: RO Check calculated RCP #2 Seal.leakoff  
== Description:==
< 1.1 GPM. (NO) Place the plant in Mode. 3 within 8 hours using GP-006, WHEN the plant is in Mode 3, THEN stop the affected RCP. BOOTH OPERATOR:
RCP "C" RCP    C,, #2 Seal Seal fails, requiring requiring a Reactor Reactor Trip.
The crew will make the decision to shut down the plant lAW 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:
Break from S/Gs Steam Break             S/Gs "B"   and "C" B and  C on the Reactor Reactor Trip.
APP-001-B2; RCP LABYRTH SEAL LO DP APP-001-D2; RCP #1 SEAL LEAKOFF HI FLOW APP-001-E2; RCP #1 SEAL LEAKOFF LO FLOW PZR level decreasing, Charging Pump Speed increasing FR 154A, A and B Pens decreasing, C Pen pegged HIGH. RO Continuous Action Step: Check any RCP #1 Sealleakoffflow>5.7 GPM. (YES) Check RCP #1 seal leakoff flow RO OR RCP Thermal Barrier b.P on affected RCP(s) decreased. (YES) RO Check Plant in MODE 1. (YES) Perform the following:
EDG "A"A fails to start on Safety Injection.
Time     II Position   I
                            ~                                  Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When requested to perform Leak Rate Calculation, wait 5 minutes and inform the crew that RCP #2 Seal leakoff is 1.3 GPM.
Continuous Action Step:
Check calculated RCP #2 Seal.leakoff Seal leakoff <  < 1.1 GPM. (NO)
RO Place the plant in Mode. Mode 3 within 8 hours using GP-006,  GP-006, WHEN the Mode 3, THEN stop the affected RCP.
plant is in Mode 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; RCP #1 SEAL LEAKOFF LO FLOW APP-001-E2; PZR level decreasing, Charging Pump Speed increasing Aand FR 154A, A and B Pens decreasing, C Pen pegged HIGH.
A Continuous Action Step:
                              .,VIILIIIUUU MI.L1011 RO Check Check any RCP #1 Sealleakoffflow>5.7 Seal leakoff flow> 5.7 GPM. (YES)
Check RCP #1 seal leakoff flow RO                   OR RCP Thermal Barrier b.P       AP on affected RCP(s) decreased. (YES)
RO         Check Plant in MODEl. MODE 1. (YES)
Perform the following:
                                    ** Trip the reactor.
RO
RO
* Trip the reactor.
                                      ** Trip RCP C.  "C".
* Trip RCP "C".
                                    .* Go To Path-i  Path-1 while continuing with this procedure.
* Go To Path-1 while continuing with this procedure.
Appendix D D                                                                NUREG-1 021, Rev. 9, Supp. 11
Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: --:....-Event
 
Appendix D                                 Operator Action                                            Form ES-D-2 Op Test Test No.:
No.:       1    Scenario          11      Event #        5, 6 & 7
_5~,_6_&_7___        Page    15 Op              --:....- Scenario #                Event                            Page    15  of ,...;2::,;6;....-_
26            _--11 Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 1 Event #
Event
Page 15 of ,...;2::,;6;....-
__ --11 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.
Time II Position i Applicant's Actions or Behavior NOTE: Following the performance and verification of PATH-1 Immediate Actions, the crew will continue with AOP-018. These steps may be handed off to the RO/BOP to perform independently.
The remaining steps of AOP-018 are listed here. PATH-1 actions begin on page 16. PHASE B isolation has occurred, so AL RCPs will be secured. RO WHEN at least 3 minutes have elapsed since tripping the affected RCP, THEN Close Sealleakoff valve for RCP "C". (CVC-303C)
RO Check RCP "B" or "c" running. (NO) RO Check RCP seal injection flow between 8 and 13 GPM. (YES) RO Check FCV-626, THERM BAR FLOW CO NT Valve CLOSED. (YES) Continuous Action Step: RO Check Thermal Barrier intact. (YES) WHEN.this procedure is completed,THENGoTo AOP-014, CCW SYSTEM MALFUNCTION. . RO Check APP-002-D2, CV ISOL PHASE B extinguished. (NO) SRO Implement EALs. SRO Review ITS for applicable LCOs: LCO 3.4.13, Condition A -Reduce leakage to within limits within 4 hrs. Appendix D NUREG-1021 , Rev. 9, Supp. 1 Appendix D Op Test No.: --Event


== Description:==
== Description:==
RCP "e" Rep  C #2 Seal fails, requiring requiring aa Reactor Reactor Trip.
Steam Break from S/Gs      B and "e" S!Gs "B"                  Reactor Trip.
C on the Reactor A fails to start on Safety Injection.
EDG "A" Time      II  Position  iI                                Applicants Actions or Behavior Applicant's NOTE:                      Following the performance and verification of PATH-1              PATH-i Immediate Actions, the crew will continue with AOP-018. These steps may be handed off to the RO/BOP to perform independently. The remaining steps of AOP-018 are listed here. PATH-1              PATH-i actions begin on page 16. PHASE B isolation has occurred, so AL RCPs will be secured.
WHEN at least 3 minutes have elapsed since tripping the affected RO RCP, THEN Close SealleakoffSeal leakoff valve for RCP "C". C. (CVC-303C)
RD RO        Check RCP "B"    B or "c" C running. (NO)
RD RO        Check RCP seal injection flow between 8 and 13 GPM. (YES)
RD RO        Check FCV-626, THERM BAR FLOW CO                  CONTNT Valve CLOSED. (YES)
Continuous Action Step:
Check Thermal Barrier intact. (YES)
RD RO WHEN this procedure is completed,THENGoTo WHEN.this                          completed, THEN Go To AOP-014, CCW SYSTEM MALFUNCTION.                                    .
RO        Check APP-002-D2, CV ISOL PHASE B extinguished. (NO)
SRO        Implement EALs.
Review ITS for applicable LCOs:
SRO LCD LCO 3.4.13, Condition A - Reduce leakacje
                                                                -          leakage to within limits within 4 hrs.
Appendix D  D                                                            NUREG-1021, NUREG-1021 , Rev. 9,    9, Supp. 11


Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 16 of 26 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.
AppendixDD Appendix                                            OperatorAction Operator       Action                                               Form Form ES-D-2 ES-D-2 TestNo.:
Time J Position II Applicant's Actions or Behavior 800TH OPERATOR:
OpTest  No.:
Steam break for SIGs "8" and "C" are triggered to occur when the reactor trip breakers open. Verify steam break malfunction is inserted.
Op Scenario##
SRO Directs tripping the Reactor, tripping Rep "e" and enters PATH-1. RO Immediate Action Step: Reactor Tripped .. (YES) BOP Immediate Action Step: Turbine Tripped. (YES) BOP Immediate Action* Step: E-1 AND E-2 energized. (YES) RO Immediate Action Step: SI Initiated. (YES) NOTE: Phase 8 isolation has occurred; the crew will stop ALL RCPs due to a loss of RCP COOling. When Foldout A is addressed the crew may isolate SIGs "8" and "C" using Foldout A. SI will have to be reset prior to manipulating valves. SRO Open Foldout A.
Scenario                11        Event##
* Rep Trip criteria.
Event            5,5, 66&&77
IF BOTH conditions are met, THEN stop all RCPs: (NO) 0 SI Pumps -AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0 RCS Subcooling
                                                                            ~~~----
-< 35 degrees F [55 degrees F] Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: ...;....-Event
Page Page      16 16 ofof  26 26
                                                                                                                        ~~----~I EventDescription:
Event  


== Description:==
== Description:==
RCP "e" Rep      C#2#2 Seal Seatfails, fails, requiring requiring aa Reactor ReactorTrip.Trip.
Steam Break Steam      Breakfrom from S/Gs S/Gs"B" Band and "e" Conon the the Reactor ReactorTrip.
Trip.
EDG "A" EDG      A fails failstoto start startonon Safety Safety Injection.
Injection.
Time Time    J    Position Position    II                                      Applicants Actions Applicant's      Actions or or Behavior Behavior BOOTH OPERATOR:
800TH    OPERATOR: Steam      Steam break break for  for SIGs SIGs "8"B and and "C" C areare triggered triggered to  to occur occur whenwhen the the reactor      trip    breakers reactor trip breakers open.          open. VerifyVerify steam steam break break malfunction malfunction is    is inserted.
inserted.
SRO SRO          Directs tripping Directs      tripping the  the Reactor, Reactor, tripping tripping Rep RCP "e" C and and enters enters PATH-1.
PATH-i.
Immediate Action Immediate            Action Step:Step:
RO RO Reactor Tripped Reactor      Tripped... (YES)(YES)
Immediate Action Step:
BOP Turbine Tripped. (YES)
Immediate Action*  Action Step:
BOP E-i AND E-2 energized. (YES)
E-1                                      (YES)
Immediate Immediate Action Step:          Step:
RO SI SI Initiated.
Initiated. (YES) (YES)
NOTE:
NOTE:                        Phase Phase B    8 isolation isolation has    has occurred; occurred; the      the crew crew will will stop stop ALL ALL RCPs RCPs due  due to to aa loss loss of  of RCPRCP cooling.
COOling. When When Foldout Foldout A    A is is addressed addressed the  the crew crew may may isolate isolate S/Gs SIGs B  "8" and and C "C" using using Foldout Foldout A. A. SI SI will will have have to to be be reset      prior reset prior to      to manipulating manipulating valves. valves.
SRO SRO          Open Open Foldout Foldout A. A.
                                      .* RCP Rep Trip  Trip criteria.
criteria. IFIF BOTH BOTH conditions conditions areare met, met, THEN THEN stop stop all all RCPs:
RCPs: (NO)  (NO) o0          Pumps - AT SI Pumps SI            -  AT LEAST LEAST ONE  ONE RUNNING RUNNING AND  AND CAPABLE CAPABLE OF    OF DELIVERIN DELIVERING    G FLOW FLOW TO    TO THE THE CORE CORE o0    RCS RCS Subcooling Subcooling -<<35 -    35 degrees degrees FF[55[55 degrees degrees F]F]
Appendix Appendix DD                                                                            NUREG-1021, NUREG-i        021, Rev.
Rev. 9,9, Supp.
Supp. 11


Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 17 of 26 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.
Appendix D                                    Operator Action                                           Form ES-D-2 Op Test No.:        1 Scenario #           11    Event #         5, 6 & 7         Page     17   of 26
Time I Position II Applicant's Actions or Behavior
                                                                      ~~~----                            ~~----~I Event
* SI actuation criteria.
 
IF EITHER condition occurs, THEN Actuate SI and Go To PATH-1, Entry Point A: 0 RCS Subcooling  
== Description:==
-< 35 degrees F [55 degrees F] 0 PZR Level-CAN NOT BE MAINTAINED>
RCP "e" Rep  C #2 Seal fails, requiring a Reactor Trip.
10% [32%1
Steam Break from S/Gs "B"   B and "e" C on the Reactor Trip.
* MSR Isolation criteria.
A fails to start on Safety Injection.
IF ANY Purge OR Shutoff Valve does NOT indicate fully closed, THEN place the associated RTGB Switch to CLOSE.
EDG "A" Time     I   Position   II                               Applicants Applicant's Actions or Behavior
* S/G isolation criteria.
                                    ** SI actuation criteria. IF EITHER condition occurs, THEN Actuate SI PATH-i, Entry Point A:
IF both the following conditions are met, THEN perform the following:
and Go To PATH-1, 0o  RCS Subcooling - <     -              F [55 degrees F]
* Any S/G pressure is decreasing in an uncontrolled manner OR
                                                                            < 35 degrees F PZR Level- CAN NOT BE MAINTAINED> 10% [32%1 0o__PZR_Level_-_CAN_NOT_BE_MAINTAINED>_10%_[32%]
* Any S/G has completely depressurized.
* MSR Isolation criteria. IF ANY Purge OR Shutoff Valve does NOT indicate fully closed, THEN place the associated RTGB Switch to CLOSE.
                                    **   SIG isolation criteria. IF both the following conditions are met, S/G THEN perform the following:
                                        *. Any S/G pressure is decreasing in an uncontrolled manner OR
                                        *. Any S/G has completely depressurized.
AND
AND
* At least ONE S/G is intact. 0 Reset SI. 0 CLOSE the appropriate AFW isolation valves to the faulted S/Gs AND OPEN the associated breaker for the valves closed.
                                        *. At least ONE S/G SIG is intact.
* S/G "B"
0o  Reset SI.
* V2-14B, SDAFW PUMP DISCH, MCC-9, CMPT -1C
0o  CLOSE the appropriate AFW isolation valves to the faulted S/Gs AND OPEN the associated breaker for the valves closed.
* V2-16B, AFW HDR DISCH, MCC-10, CMPT -4F
                                                        ** S/G SIG "B" B
* S/G "c"
                                                                  *. V2-14B, SDAFW PUMP DISCH, MCC-9, CMPT-- 1C CMPT      iC
* V2-14C, SDAFW PUMP DISCH, MCC-10, CMPT -4M
                                                                    ** V2-16B, AFW HDR DISCH, MCC-10, CMPT - 4F
* V2-16C, AFW HDR DISCH, MCC-9, CMPT -3J 0 WHEN the faulted S/Gs dry out, THEN dump steam from intact S/G to control RCS mgressurization.
* S/G "c"     C
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 NUREG-1 021, Rev. g, Supp. 1 Appendix 0 Op Test No.: -.;...-Event
                                                                  *. V2-14C, SDAFW PUMP DISCH, MCC-           MCC 10, CMPT - 4M
                                                                  *. V2-16C, AFW HDR DISCH, MCC-9, CMPT - 3J o
0   WHEN the faulted S/Gs dry out, THEN dump steam from_intact_SIG_to_control_RCS_repressurization.
from intact S/G to control RCS mgressurization.
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                                                                   NUREG-1 021, Rev. g,  9, Supp. 11
 
Appendix 0D                                  Operator Action Operator                                                Form ES-D-2 Form  ES-D-2 Op Test Op Test No.:
No.:        1 Scenario ##
Scenario            11      Event #
Event          5, 66 && 77 5,                  Page Page 18 18 of of  26 26
                                                                  ---------                        ~------~I Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 18 of 26 ---------
Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.
Time i Position i Applicant's Actions or Behavior BOP Verify both MDAFW pumps are running. (YES) NOTE: Crew may elect to reset SI in order to control AFW and S/G levels. BOP If additional Feedwater is required, start the SDAFW pump. RO Verify 2 SI pumps running. (YES) RO Verify Both RHR pumps running. (YES) RO Verify SI valves are properly aligned. (YES) RO At least 1 CCW pump is running. (YES) BOP All SW and SW Booster pumps running. (NO) BOP Attempt to start all SW and SW Booster pumps. (NO, SW Booster Pump "A" is unavailable)
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 initiated. (YES) BOP Verify CV Ventilation isolation. (YES) BOP Verify Control Room Vent aligned for Pressurization Mode. (YES) Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Op Test No.: ......;...-
Event
Event


== Description:==
== Description:==
RCP "e" Rep  C,, #2 Seal Seal fails, requiring requiring aa Reactor Reactor Trip.
Steam Break Steam  Break from from S/Gs S/Gs "B" B and and "e"  on the Reactor C on        Reactor Trip.
EDG "A" EDG  A fails to start on Safety  Injection.
Safety Injection.
Time      i  Position Position  i                                  Applicants Actions or Behavior Applicant's 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.
BOP      If additional Feedwater is required, start the SDAFW pump.
RO      Verify 2 SI pumps running. (YES)
RO      Verify Both RHR pumps running. (YES)
RO      Verify SI valves are properly aligned. (YES)
RO      At least 1  1 CCW 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)
RO        Verify CV Fans HVH-1, 2, 3, 4 running. (YES)
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-1 021, Rev. 9, Supp. 11


Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 19 of 26 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.
Appendix 0D Appendix                                          Operator Action Operator        Action                                            Form Form ES-D-2 ES-D-2 Op Test No.:
Time I Position II Applicant's Actions or Behavior 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 of power loss using OP-601. RO Continuous Action Step: 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) RO Verify approximately 12 GPM Spray additive tank flow. (Flow will be adjusted from -30 GPM to 12 GPM) RO Verify Phase B isolation valves closed. (YES) RO Stop ALL RCPs. (May be stopped previously)
Op Test No.:        1 Scenario ##
BOP Verify ALL MSIVs and MSIV bypasses closed. (YES, operator will take MSIV switches to CLOSE) BOP Locally open breaker for HVS-1 at MCC-5. Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: ......;.--
Scenario            11        Event ##
Event          5, 5, 66 && 77          Page Page   19 19    of of 26 26
                                                                        ~~~----                                  ~~----~I 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" on the C on   the Reactor  Trip.
Reactor Trip.
EDG "A" EDG    A fails fails to to start start on on Safety Safety Injection.
Injection.
Time Time      I   Position Position      II                                   Applicants Actions Applicant's     Actions or or Behavior Behavior BOP           Verify both EDGs running. running. (NO)
NOTE:                                                   investigate what is If requested to investigate                           is wrong with the EDG, 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 of power loss using OP-                   OP 601.
Continuous Action Step:
RD RO CV Pressure has remained below 10 psig. (NO)
RD RO           Verify CV Spray initiated. (YES)
RD 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              12 GPM)
RO           Verify Phase BB isolation valves closed. (YES)
RD RO           Stop ALL RCPs. (May be stopped previously)
Verify ALL MSIVsMSIVs and         MSIV bypasses closed.
and MSIV                      closed. (YES, (YES, operator operator will will take take BOP BOP MSIV MSIV switches switches to    to CLOSE)
CLOSE)
BOP BOP           Locally Locally open open breaker breaker for for HVS-1 HVS-1 at   at MCC-5.
MCC-5.
Appendix Appendix D0                                                                          NUREG-1 021, 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            11        Event ##
Event            5, 6 & 7_ _ _ Page
_5;;.:"..;;,6,.;;;&;..;,7        Page    20 20        26_ _ _...,1 of _2_6 of Event
 
== Description:==
 
Event
 
== Description:==
RCP "C" RCP    C #2 Seal Seal fails, fails, requiring requiring aa Reactor Reactor Trip.      Trip.
Steam Break Steam    Break from S/Gs S/Gs "B" B and and "C"  on the Reactor C on                  Reactor Trip.
Trip.
EDG "A" EDG                start on Safety A fails to start      Safety Injection.
Injection.
Time      i  Position Position    II                                  Applicants Actions or Behavior Applicant's                          Behavior RCS pressure> 1350 psig. [1250 psig]
RO              **      (YES, RCS pressure is> 1250, skip the following 2 steps)
                                    **      (NO, RCS pressure is < 1250,                    1250, Go To the next step)
RO          SI Flow Verified. (YES)
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%]      [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 F. (NO)
RO            RCS temperature> 547 degrees F. (NO)
BOP          Attempt to limit cooldown.
IF RCS cooldown continues and is NOT due to SI flow, THEN close BOP MSIVs and MSIV bypasses.
Appendix D D                                                                                NUREG-1 021, Rev. 9, Supp. 11
 
Appendix DD Appendix                                        Operator Action Operator        Action                                            Form Form ES-D-2 ES-D-2 Op Test Op Test No.:
No.:              Scenario ##
Scenario            11        Event ##
Event            5, 66 && 77 5,                    Page Page    21 21    of of  26 26
                  ~-                                                    ~~~----                                    ~---~I Event
 
== Description:==
 
Event
 
== Description:==
Rep  c #2 RCP "e"  #2 Seal Seal fails,    requiring aa Reactor fails, requiring                  Trip.
Reactor Trip.
Steam Break Steam  Break fromfrom S/Gs S/Gs "B" B and  c on and "e"  on the the Reactor Reactor Trip.
Trip.
EDG "A" EDG  A fails  to start fails to  start onon Safety  Injection.
Safety Injection.
Time Time    J II  Position Position  !                                    Applicants Actions Applicant's      Actions or  Behavior or Behavior RO RO        PZR PORVs PZR    PORVs closed. closed. (YES)
(YES)
RO RO        PZR Spray PZR    Spray and  and AuxAux Spray        valves closed.
Spray valves          closed. (YES)
(YES)
RO RO          least 11 RCP At least                  running. (NO)
RCP running.          (NO)
BOP              SIG with uncontrolled depressurization.
Any S/G                                    depressurization. (YES)
RO        Reset SPDS and initiate monitoring of CSFSTs.
SRO        Go To EPP-11, FAULTED STEAM GENERATOR                      GENERATOR ISOLATION.
ISOLATION.
BOP        Maintain At Least One S/G          SIG Available For RCS Cooldown.
BOP        Any SIG S/G pressure stable or increasing. (YES)
Any S/G pressure decreasing in an uncontrolled manner OR any S/G BOP completely depressurized depressurized.. (YES)
Isolate Isolate faulted S/Gs using      using Supplement 0,          G, 5/0 S/G ISOLATION ISOLATION..
BOP BOP        (Supplement (Supplement G Steps    G  Steps    are    listed    on on page 22        24) 22 & 24)
Maintain Maintain A    A Faulted Faulted S/G S/G In    The Isolated In The      Isolated Condition Condition During During Subsequent Subsequent BOP BOP        Recovery Recovery Actions Unless      Unless Needed Needed For      For Cooldown.
Cooldown.
BOP BOP        Check Check CST CST level          greater than level greater      than 10%.10%. (YES)(YES)
BOP BOP        Check Check Available Available Secondary Secondary Radiation Radiation Monitors Monitors normal.
normal. (YES)
(YES)
Appendix Appendix DD                                                                        NUREG-102 NUREG-1 021,        Rev. 9, 1, Rev. 9, Supp.
Supp. 11
 
Appendix D                                    Operator Action                                            Form ES-D-2 Op Test Op Test No.:
No.:        1 Scenario ##
Scenario            11      Event #
Event          5, 66 &
5,    & 77          Page Page    22 22  of of  26 26
                                                                    ~~------                              ~------~I Event
 
== Description:==
 
Event
 
== Description:==
RCP "e" Rep  C #2  Seal fails, requiring
                                      #2 Seal                    Reactor Trip.
requiring aa Reactor    Trip.
Steam Break Steam  Break from S/GsS/Gs "B" B and and "e"  on the Reactor C on        Reactor Trip.
EDG "A" EDG  A fails to start on Safety  Injection.
Safety Injection.
Time      III Position Position    I                                Applicants Actions or Behavior Applicant's              Behavior CRITICAL TASK:              Isolate feedwater to the faulted S/Gs            SIGs using Foldout A OR Supplement G prior to transitioning to PATH-1,            PATH-I, Entry point C.
Check any S/G with an uncontrolled level increase. (NO, Go To Path-            Path RO (PATH-i Steps continue on Page 1, Entry Point C) (PATH-1                                     Paqe 25)
Pages 22-24 are steps from Supplement G, STEAM GENERATOR ISOLATION to isolate B "e" S/Gs "8"    C as faulted Steam Generators.
Go to the appropriate step from following table:
BOP            **    S/G B to be isolated, Go To Step 18.
                                  **    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)
Vi -3B, MSIV CLOSED. (YES)
Verify V1-3B, BOP Verify Vi    -3C, MSIV CLOSED. (YES)
V1-3C, Verify MS-353B, MSIV Vi            -3B BYP CLOSED. (YES)
V1-3B BOP Verify MS-353C, MSIV V1-3C      Vi -3C BYP CLOSED. (YES)
Verify FRV B CLOSED. (YES)
BOP Verify FRV C CLOSED. (YES)
Verify FRV B BYP CLOSED. (YES)
BOP Verify FRV C BYP CLOSED. (YES)
Appendix D D                                                                NUREG-1 021, Rev. 9, Supp. 11 NUREG-i
 
Appendix D  D                                Operator Action Operator                                                                    Form ES-D-2 Form        ES-D-2 Op Test Op Test No.:
No.:       1    Scenario ##
Scenario          11        Event ##
Event            5, 6 & 7_ _ _ Page
_5;;.1"...;;.6..;;;&;..;.7        Page    23 23            26_ _ _-i1 of .....;2;.,;6 of
                  ~-
Event
Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 1 Event # _5;;.:"..;;,6,.;;;&;..;,7
Event
___ Page 20 of _2_6 ___ ...,1 RCP "C" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "C" on the Reactor Trip. EDG "A" fails to start on Safety Injection.
Time i Position II Applicant's Actions or Behavior RCS pressure>
1350 psig. [1250 psig] RO * (YES, RCS pressure is> 1250, skip the following 2 steps) * (NO, RCS pressure is < 1250, Go To the next step) RO SI Flow Verified. (YES) 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 levels between 8% [18%] and 50%. RO RCP Thermal barrier cooling water HilLo 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 F. (NO) RO RCS temperature>
547 degrees F. (NO) BOP Attempt to limit cooldown.
BOP IF RCS cooldown continues and is NOT due to SI flow, THEN close MSIVs and MSIV bypasses.
Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event


== Description:==
== Description:==
RCP "e" Rep  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 and "e" C on on the  the Reactor Reactor Trip.
Trip.
EDG "A" EDG  A fails to start start on Safety Injection.
Injection.
Time      II  Position Position  I                                    Applicants Actions or Behavior Applicant's                          Behavior V2-6B, FW HDR SECTION Valve CLOSED. (YES)
Verify V2-6S, BOP SOP Verify V2-6C, FW HDR SECTION Valve CLOSED. (YES)
Verify V2-14S, V2-14B, SDAFW PUMP DISCH Valve CLOSED. (YES)
BOP SOP Verify V2-14C, SDAFW PUMP DISCH Valve CLOSED. (YES)
V2-l 6B, AFW HDR DISCH Valve CLOSED. (YES)
Verify V2-16S, BOP SOP Verify V2-16C, V2-i 6C, AFW HDR DISCH Valve CLOSED. (YES)
BOP SOP      Verify STEAM LINE PORVs CLOSED. (YES)
Vi -8B, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)
Verify V1-8S, 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      S/G B "S" and S/G C      "C" BYPASS SYPASS DRN and WARM-UP LINE TO AFW PUMP.
Check S/Gs B      "S" and C "C" MSIV Above and Below                  Selow Seat Drain Valves BO SOP CLOSED. (YES)
Appendix Appendix D  D                                                                              NUREG-iO2i, NUREG-1021, Rev. Rev. 9, 9, Supp.
Supp. i1


Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 21 of 26 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.
Appendix D                                    Operator Action Operator                                                    Form ES-D-2 Op Test Test No.:
Time II Position ! Applicant's Actions or Behavior RO PZR PORVs closed. (YES) RO PZR Spray and Aux Spray valves closed. (YES) RO At least 1 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.
No.:
BOP Maintain At Least One S/G Available For RCS Cooldown.
Op Scenario ##
BOP Any S/G pressure stable or increasing. (YES) BOP Any S/G pressure decreasing in an uncontrolled manner OR any S/G completely depressurized. (YES) BOP Isolate faulted S/Gs using Supplement G, S/G ISOLATION. (Supplement G Steps are listed on page 22 & 24) BOP Maintain A Faulted S/G In The Isolated Condition During Subsequent Recovery Actions Unless Needed For Cooldown.
Scenario            11      Event #
BOP Check CST level greater than 10%. (YES) BOP Check Available Secondary Radiation Monitors normal. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: ...;...-Event
Event          5, 66 && 77 5,
                                                                    ~~~----
Page Page    24 24 of of  26 26
                                                                                                          ~---~I Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 22 of 26 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.
Event
Time II Position I Applicant's Actions or Behavior CRITICAL TASK: Isolate feedwater to the faulted S/Gs using Foldout A OR Supplement G prior to transitioning to PATH-1, Entry point C. RO Check any S/G with an uncontrolled level increase. (NO, Go To Path-1, Entry Point C) (PATH-1 Steps continue on Page 25) Pages 22-24 are steps from Supplement G, STEAM GENERATOR ISOLATION to isolate S/Gs "8" "e" as faulted Steam Generators.
Go to the appropriate step from following table: BOP
* S/G B to be isolated, Go To Step 18.
* S/G C to be isolated, Go To Step 34 . BOP Check S/G "B" faulted. (YES) Check S/G "C" faulted. (YES) BOP Verify V1-3B, MSIV CLOSED. (YES) Verify V1-3C, MSIV CLOSED. (YES) BOP Verify MS-353B, MSIV V1-3B BYP CLOSED. (YES) Verify MS-353C, MSIV V1-3C BYP CLOSED. (YES) BOP Verify FRV B CLOSED. (YES) Verify FRV C CLOSED. (YES) BOP Verify FRV B BYP CLOSED. (YES) Verify FRV C BYP CLOSED. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event


== Description:==
== Description:==
RCP "e" Rep            Seal fails, requiring C,, #2 Seal        requiring a Reactor Reactor Trip.
Steam Break Steam    Break from S/GsS/Gs "B" B and and "e"  on the Reactor C on        Reactor Trip.
EDG "A" EDG    A fails to start on Safety Injection.
Injection.
Time      i  Position  II                                Applicants Actions or Behavior Applicant's Dispatch an operator to E-1/E-2 Room to perform the following:
                                    *. At MCC-9, verify V2-14B  V2-1 4B and V2-16CV2-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 V1-8B  Vi -8B and V1-8C Vi -8C closed and open breakers 0o  V1-8B, SDAFW PUMP STEAM ISOLATION.
0o    Vi-8C, SDAFW PUMP STEAM ISOLATION.
V1-8C, Dispatch operator to the Aux. Bldg. to perform the following:
                                    *.        MOO-i 0, verify V2-16B At MCC-1                  V2-i 6B closed and open breaker V2-16B, V2-i 6B, BOP                    MDAFW PUMP HEADER DISCHARGE TO S/G B.
                                    *.        MCC-iO, verify V2-14C At MCC-10,                V2-i4C closed and open breaker V2-14C,  V2-i4C, 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, Rev. 9, Supp. i1


Operator Action Form ES-D-2 Scenario # 1 Event # _5;;.1"...;;.6..;;;&;..;.7
Appendix 0D                                    Operator Action                                       Form ES-D-2 Op Test No.:
___ Page 23 of .....;2;.,;6
Op      No.:        1 Scenario #
___ -i1 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.
Scenario          1     Event ##
Time II Position I Applicant's Actions or Behavior SOP Verify V2-6S, FW HDR SECTION Valve CLOSED. (YES) Verify V2-6C, FW HDR SECTION Valve CLOSED. (YES) SOP Verify V2-14S, SDAFW PUMP DISCH Valve CLOSED. (YES) Verify V2-14C, SDAFW PUMP DISCH Valve CLOSED. (YES) SOP Verify V2-16S, AFW HDR DISCH Valve CLOSED. (YES) Verify V2-16C, AFW HDR DISCH Valve CLOSED. (YES) SOP Verify STEAM LINE PORVs CLOSED. (YES) SOP Verify V1-8S, SDAFW STEAM SHUTOFF Valve CLOSED. (YES) Verify V1-8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES) SOP Verify S/Gs "S" and "C" Slowdown and Slowdown Sample Valve Status Light Indication CLOSED. (YES) Dispatch an operator to the Pipe Jungle to close MS-29 and MS-38, SOP S/G "S" and S/G "C" SYPASS DRN and WARM-UP LINE TO AFW PUMP. SOP Check S/Gs "S" and "C" MSIV Above and Selow Seat Drain Valves CLOSED. (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event
Event        88 &
                                                                        & 99            Page Page    25 25  of 26 26
                                                                    ~~------                           ~~----~I Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 1 Event # 5, 6 & 7 Page 24 of 26 Rep "e" #2 Seal fails, requiring a Reactor Trip. Steam Break from S/Gs "B" and "e" on the Reactor Trip. EDG "A" fails to start on Safety Injection.
Event
Time i Position II Applicant's Actions or Behavior Dispatch an operator to E-1/E-2 Room to perform the following:
* At MCC-9, verify V2-14B and V2-16C closed and open breakers 0 V2-14B, SDAFW PUMP TO S/G B. BOP V2-16C, MDAFW PUMP HDR DISCH TO S/G C. 0
* At MCC-6, verify V1-8B and V1-8C closed and open breakers 0 V1-8B, SDAFW PUMP STEAM ISOLATION.
0 V1-8C, SDAFW PUMP STEAM ISOLATION.
Dispatch operator to the Aux. Bldg. to perform the following:
* At MCC-1 0, verify V2-16B closed and open breaker V2-16B, BOP MDAFW PUMP HEADER DISCHARGE TO S/G B.
* At MCC-10, verify V2-14C closed and open breaker V2-14C, SDAFW PUMP TO S/G C. BOP Check All Faulted and Ruptured S/Gs isolated. (YES) BOP WHEN the faulted S/Gs dry out, THEN dump steam from intact S/G to control RCS repressurization.
BOP Check Any S/G ruptured. (NO) SRO Return to procedure and step in effect. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: --.;.....-
Scenario # Event # 8 & 9 Page 25 of 26 Event


== Description:==
== Description:==
Loss of Off-Site Loss    Off-Site Power.
Power.
SW Pumps fail to start following restoration restoration of power.
Time      II  Position    Ifi                            Acolicants Actions or Behavior Applicant's BOOTH OPERATOR: After S/Gs 800TH                                  SIGs "8"B and "C" C are isolated and at the discretion of the Chief Examiner, insert Events 8 and 9, Loss of Off-Site Power with a failure of SW Pumps to restart.
The crew will continue in PATH-1,  PATH-i, but will address components that did NOT restart:
0o  Service Water Pump "C"      C or "0"                EDG cooling.
D to provide EOG 0o  RHR Pump "8",  B, HVH Units 3 &      & 4, SI Pump "C".
C.
0o  Charging Pump "C"    C started OR FCV-626 opened to provide RCP Seal cooling.
CRITICAL TASK:                    Manually restart a Service Water Pump to provide cooling to the only running EDG before damaging the EDG.
Reset SPDS and initiate monitoring of Critical Safety Function Status RO Trees.
SRO            Open Foldout B.
SRO            Request periodic samples of ALL S/Gs.
RO            At least one RCP running. (NO)
BOP            Any SIG S/G with uncontrolled depressurization. (YES)
BOP            Faulted S/G isolated using EPP-11.EPP-1 1. (YES)
Once S/Gs B  "8" and C  "C" have been isolated and aa SW pump has been started, the scenario may be terminated.
Appendix D  0                                                                NUREG-1021, Rev. 9, Supp. 11 NUREG-1021,


Loss of Off-Site Power. SW Pumps fail to start following restoration of power. Time II Position I Applicant's Actions or Behavior 800TH OPERATOR:
HLC-08 NRC HLC-08     NRC SCENARIO SCENARIO 11 TURNOVER TURNOVER SHEETSHEET POWER LEVEL:
After S/Gs "8" and "C" are isolated and at the discretion of the Chief Examiner, insert Events 8 and 9, Loss of Off-Site Power with a failure of SW Pumps to restart. The crew will continue in PATH-1, but will address components that did NOT restart: 0 Service Water Pump "C" or "0" to provide EOG cooling. 0 RHR Pump "8", HVH Units 3 & 4, SI Pump "C". 0 Charging Pump "C" started OR FCV-626 opened to provide RCP Seal cooling. CRITICAL TASK: Manually restart a Service Water Pump to provide cooling to the only running EDG before damaging the EDG. RO Reset SPDS and initiate monitoring of Critical Safety Function Status Trees. SRO Open Foldout B. SRO Request periodic samples of ALL S/Gs. RO At least one RCP running. (NO) BOP Any S/G with uncontrolled depressurization. (YES) BOP Faulted S/G isolated using EPP-11. (YES) Once S/Gs "8" and "C" have been isolated and a SW pump has been started, the scenario may be terminated.
POWER       LEVEL: 68%,
Appendix 0 NUREG-1021, Rev. 9, Supp. 1 HLC-08 NRC SCENARIO 1 TURNOVER SHEET POWER LEVEL: 68%, 17,000 MWO/MTU.
68%, 17,000 17,000 MWO/MTU.
* Returning to RTP following a short Maintenance Outage.
MWD/MTU.
* Awaiting results of post-outage testing. BORON CONCENTRATION:
    **   Returning to Returning   to RTP RTP following following aa short short Maintenance Maintenance Outage.
106 ppm EQUIPMENT UNDER CLEARANCE:
Outage.
* SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.
    **    Awaiting results Awaiting  results of of post-outage post-outage testing.
o LCO 3.7.7 -A has been entered and is in hour 18 of a 72 TSAS. o Expected return is within -18 hours. EQUIPMENT STATUS:
testing.
* Main Turbine Vibration for #2, 3 and 4 bearings is elevated.
BORON CONCENTRATION:
INSTRUCTIONS FOR THE WATCH:
BORON      CONCENTRATION: 106       106 ppm ppm EQUIPMENT UNDER EQUIPMENT        UNDER CLEARANCE:
* Maintain power at 68% RTP. Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 Facility:
CLEARANCE:
HB ROBINSON Scenario No.: 2 Op Test No.: 2008 NRC Examiners:
* SW Booster Pump "A" A is Out-Of-Service for Motor Coupling Alignment.
o         3.7.7-A LCO 3.7.7   -A has been entered and is in hour 18 of a 72 TSAS.
o   Expected return is within -18 18 hours.
EQUIPMENT STATUS:
**   Main Turbine Vibration for #2, 3 and 4 bearings is elevated.
Main INSTRUCTIONS FOR THE WATCH:
**   Maintain power at 68% RTP.
Maintain Appendix Appendix DD                                                        NUREG-1021, Rev.
NUREG-1021,   Rev. 9, 9, Supp.
Supp. 11
 
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.:       22        Test No.:
Op Test Op        No.:     2008 NRC 2008   NRC Examiners:
Examiners:                                                      Operators:
Operators:
Operators:
Initial Conditions:
Initial Conditions:   **   100% MOL, 9000 MWD/MTU, 766 ppm Boron.
* 100% MOL, 9000 MWD/MTU, 766 ppm Boron.
                        **   SW Booster Pump "A"   A is Out-Of-Service for Motor Coupling Alignment.
* SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.
0o        3.7.7-A LCO 3.7.7 -A has been entered and is in hour 18 of a 72 hour action statement.
0 LCO 3.7.7 -A has been entered and is in hour 18 of a 72 hour action statement.
0o  Expected return is within -18 hours.
0 Expected return is within -18 hours.
                        **    Main Turbine Vibration for #2, 3 and 4 bearings is elevated.
* Main Turbine Vibration for #2, 3 and 4 bearings is elevated.
Turnover:             **   Maintain power at normal levels.
Turnover:
Critical Task:         **   Initiate isolation of the applicable S/G using Supplement G before exiting EPP-     EPP 11.
* Maintain power at normal levels. Critical Task:
                        **    Verify CVC-381 closed before transitioning to FRP-H.1.
* Initiate isolation of the applicable S/G using Supplement G before exiting EPP-11.
Event     MaIf. No.
* Verify CVC-381 closed before transitioning to FRP-H.1. Event Malf. No. Event Type* Event No. Description 1 (C) RO, SRO Charging Pump "B" trip. 2 (I) RO, SRO IRPI K8 Fails Low simulating a dropped rod. (TS) SRO 3 (I) BOP, SRO Controlling Steam Flow channel FT -494 for S/G "C" fails LOW. (TS) SRO 4 (C) BOP, SRO FWH 4A Tube Leak. 5 (R) RO Downpower to support removing FWH 4A from service. (N) SRO, BOP 6 (C) RO Rods continue to step requiring Reactor Trip. (M) ALL 7 (C) BOP Failure of the Turbine to trip. 8 (M) ALL FW break on S/G "B" inside CV. Loss of all Feedwater.
Malf.                  Type*
9 (C) RO Containment Spray Pump "A" fails to Auto Start. 10 (C) RO Phase B Isolation Valves FCV-626 and CVC-381 fail to close. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 2
Event Type*                                           Event No.                                                                       Description 1
1                  (C) RO, SRO         Charging Pump "B" B trip.
2                     (I) RO, SRO               KB Fails Low simulating a dropped rod.
IRPI K8 (TS) SRO 3                   (I) BOP, SRO         Controlling Steam Flow channel FT    FT-494
                                                                                          -494 for S/G "C" C fails LOW.
(TS) SRO 4                     (C) BOP, SRO         FWH 4A Tube Leak.
55                  (R) RO               Downpower to support removing FWH 4A from service.
(N) SRO, BOP 66                    (C) RO               Rods continue to step requiring Reactor Trip.
(M) ALL 77                    (C) BOP             Failure of the Turbine to trip.
88                    (M) ALL             FW break on S/G B  "B" inside CV. Loss of all Feedwater.
9                     (C) RO               Containment Spray Pump A    "A" fails to Auto Start.
10 10                   (C) RO               Phase Phase B B Isolation Isolation Valves FCV-626 FCV-626 and and CVC-381 CVC-381 fail to close.
          * (N)ormal, (N)ormal,    (R)eactivity,      (l)nstrument, (I)nstrument,     (C)omponent, (C)omponent,        (M)ajor Appendix Appendix D  D                                                           NUREG-1021, NUREG-1021, Rev. Rev. 9,9, Supp.
Supp. 11
 
II Appendix Appendix DD                                  Scenario Outline Scenario     Outline                                   Form Form ES-D-1 ES-D-1 HLC-08 NRC HLC-08   NRC SCENARIO SCENARIO 22
 
==SUMMARY==


==SUMMARY==
==SUMMARY==
DESCRIPTION The crew will assume the watch with the plant at 100% RTP. The previous shift identified increased vibration on Main Turbine bearing #3 and has taken all necessary actions to inform station management.
DESCRIPTION DESCRIPTION The crew The  crew will will assume assume thethe watch watch with with the the plant plant atat 100%
Service Water Booster Pump "A" is under clearance for Motor Coupling Alignment.
100% RTP.RTP. The     previous shift The previous          identified shift identified increased vibration increased   vibration on on Main Main Turbine Turbine bearing bearing #3#3 and and has has taken taken all   necessary actions all necessary    actions toto inform inform station management.
Shift instructions are to maintain the plant at 100% RTP. On cue from the Chief Examiner, Charging Pump "B" will trip. The RO should respond lAW APP-003-F4, starting the standby Charging pump to maintain PZR level on program. On cue from the Chief Examiner, IRPI K8 will fail low simulating a dropped rod. The crew should respond lAW AOP-001 , MALFUNCTION OF REACTOR CONTROL SYSTEM, and verify that no dropped rod exists due to stable Reactor parameters.
station  management. ServiceService Water Water Booster Booster Pump Pump "A"A is is under    clearance for under clearance     for Motor Motor Coupling Coupling Alignment. Shift Alignment.          instructions are Shift instructions are to to maintain maintain the the plant plant at at 100%
The SRO should enter LCO 3.1.7, Condition A for the failed IRPI. On cue from the Chief Examiner, the controlling steam flow channel (FT-494) for S/G "c" will fail low. The BOP will take Manual control of Feedwater Regulating valve FCV-498, lAW AOP-025, RTGB INSTRUMENT FAILURE, to match Feed Flow and Steam Flow in order to control S/G "c" water level. An alternate controlling channel will be selected, FCV-498 will be returned to automatic control and FT-494 will be removed from service lAW OWP-034, STEAM FLOW, SF-5, STEAM FLOW TRANSMITTER FT-494. The SRO should enter LCO 3.3.1 Condition E and 3.3.2 Condition D, for the failed instrument.
100% RTP.RTP.
As soon as Tech Specs are addressed, the Chief Examiner can cue a tube leak in Feed Water Heater 4A. The crew should respond lAW APP-007-E7, identifying the leak and entering AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION and using requirements from OP-407, HEATER DRAINS AND VENTS, ramp the plant down in power to 517 MWe in order to remove the FWH from service. As soon as the Chief Examiner is satisfied with the power maneuver, he can cue the Rod Control System failure. Control Rods will continually step in the direction moved and the crew will be unable to stop rod motion. The SRO should respond by directing a Reactor trip and enter PATH-1. On the Reactor trip, the turbine will not trip and cannot be tripped from the RTGB, requiring the BOP to Manually runback the turbine. Shortly after the Reactor Trip, a Feedwater Break will develop inside CV, resulting in a Safety Injection.
On cue On  cue from from the the Chief Chief Examiner, Examiner, Charging Charging PumpPump "B" B will will trip.
On the SI, all Auxiliary Feedwater Pumps will fail to start or will trip, resulting in a complete loss of feed. On the SI and CV Spray, Containment Spray Pump "A" will fail to Auto start, Phase B isolation valves CVC-381 and FCV-626 will fail to close. The crew should respond and take actions lAW PATH-1, transitioning to FRP-H.1 , LOSS OF SECONDARY HEAT SINK. The Chief Examiner may terminate the scenario at any time after S/G "B" Feedwater break is isolated and feedwater is restored to at least 1 S/G. Appendix D NUREG-1 021, Rev. 9, Supp. 1 I Appendix 0 Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 2 SIMULATOR SETUP IC/SETUP:
trip. The The RO     should respond RO should    respond lAW lAW APP-003-F4, starting the standby Charging pump to maintain PZR level on program.
* SW 800ster Pump "A" is OFF, breaker OPEN and switch is RED CAPPED.
cue from the Chief On cue              Chief Examiner, IRPI K8 will fail low   low simulating simulating aa dropped dropped rod.
* Main Turbine 8earing #2 is OFFSET by 1.5, #3 by 2.3 and #4 by 1.7.
rod. The crew crew should should respond lAW lAW AOP-001 AOP-001,, MALFUNCTION MALFUNCTION OF    OF REACTOR REACTOR CONTROL CONTROL SYSTEM,SYSTEM, and verify that no dropped rod rod exists due to stable Reactor Reactor parameters.
* Status board is correctly marked up for IC-13. PRE-LOADED EVENTS: The following events should occur on the reactor trip:
parameters. The SRO should enter LCO           LCO 3.1.7, 3.1 .7, Condition A for the failed IRPI.
* Event 8: FW break on S/G "8" inside CV. Loss of all Feedwater.
On cue from the Chief Examiner, the controlling steam flow channel (FT-494) for S/G                   SIG "c" C will fail low. The BOP will take Manual control of Feedwater Regulating valve FCV-498, lAW AOP-025, RTGB INSTRUMENT FAILURE, to match Feed Flow and Steam Flow in order to control S/G                             SIG "c"
* Event 9: Containment Spray Pump "A" fails to Auto Start.
C water level. An alternate controlling channel will be selected, FCV-498 will be returned to automatic control and FT-494 will be removed from service lAW OWP-034, STEAM FLOW, SF-5, STEAM FLOW TRANSMITTER FT-494. The SRO should enter LCO 3.3.1 Condition E and 3.3.2 Condition D, for the failed instrument.
* Event 10: Phase 8 Isolation Valves FCV-626 and CVC-381 fail to close. EVENTSITRIGGERS INITIATED DURING THE SCENARIO:
As soon as Tech Specs are addressed, the Chief Examiner can cue a tube leak in Feed Water Heater 4A. The crew should respond lAW APP-007-E7, identifying the leak and entering AOP-                       AOP 010, MAIN FEEDWATER/CONDENSATE MALFUNCTION and using requirements from OP-                                     OP 407, HEATER DRAINS AND VENTS, ramp the plant down in power to 517 MWe in order to remove the FWH from service.
* Event 1: Charging Pump "8" trip.
As soon as the Chief Examiner is satisfied with the power maneuver, he can cue the Rod Control System failure. Control Rods will continually step in the direction moved and the crew will be unable to stop rod motion. The SRO should respond by directing a Reactor trip and enter PATH-i.
* Event 2: IRPI K8 Fails Low simulating a dropped rod.
PATH-1. On the Reactor trip, the turbine will not trip and cannot be tripped from the RTGB, requiring the BOP to Manually runback the turbine. Shortly after the Reactor Trip, a Feedwater Break will develop inside CV, resulting in a Safety Injection. On the SI, all Auxiliary Feedwater Pumps will fail to start or will trip, resulting in a complete loss of feed. On the SI and CV Spray, Containment Spray Pump A        "A" will fail to Auto start, Phase B      B isolation valves CVC CVC-381 and FCV-626 will fail to close. The crew should respond and take actions lAW PATH-i,                PATH-1, transitioning to FRP-H.i, FRP-H.1 , LOSS OF SECONDARY SECONDARY HEAT SINK.
* Event 3: Controlling Steam Flow Channel FT-494 for S/G "C" Fails LOW.
The Chief Examiner may terminate the scenario at any time after SIG                S/G B "B" Feedwater break is isolated and feedwater is restored to at least 11 S/G.
Appendix Appendix D D                                                            NUREG-i NUREG-1 021, 021, Rev. 9, Supp.
Rev. 9,  Supp. 11
 
I Appendix 0D                                  Scenario Outline                                   ES-D-i Form ES-D-1 HLC-08 NRC SCENARIO 2 SIMULATOR SETUP IC/SETUP:
* IC-602, SON 006_Sim_2.
* Booster Pump "A" SW 800ster          A is OFF, breaker OPEN and switch is RED CAPPED.
* Main Turbine 8earing Bearing #2 is OFFSET by 1.5, #3 by 2.3 and #4 by 1.7. 1 .7.
* IC-i 3.
Status board is correctly marked up for IC-13.
PRE-LOADED EVENTS:
The following events should occur on the reactor trip:
* Event 8: FW break on S/G SIG "8" B inside CV. Loss of all Feedwater.
* Event 9: Containment Spray Pump "A"   A fails to Auto Start.
* Event 10: Phase 8 B Isolation Valves FCV-626 and CVC-381 fail to close.
EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:
EVENTSITRIGGERS
* Event 1: Charging Pump "8" B trip.
* KS Fails Low simulating a dropped rod.
Event 2: IRPI K8
* Event 3: Controlling Steam Flow Channel FT-494 for SIG          "C" Fails LOW.
S/G C
* Event 4: FWH 4A Tube Leak
* Event 4: FWH 4A Tube Leak
* Event 5: Downpower to support removing FWH 4A from service.
* Event 5: Downpower to support removing FWH 4A from service.
* Event 6: Rods continue to step requiring Reactor Trip.
* Event 6: Rods continue to step requiring Reactor Trip.
* Event 7: Failure of the Turbine to trip. EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
* Event 7: Failure of the Turbine to trip.
* AOP-001, Section 0; AOP-025, Section F; OWP-034, SF-5; AOP-01 0; OP-407; OP-105, Section 8.4; AOP-001; PATH-1; Supplement G; Foldout A and 8; FRP-H.1; EPP-11. Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ......;....-
EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
Scenario # 2 Event # Page 4 of 28 Event
* AOP-OOi, AOP-001, Section D; 0; AOP-025, Section F; OWP-034, SF-5; AOP-Oi  AOP-01 0; OP-407; OP-i    05, OP-105, Section 8.4; AOP-OOi; AOP-001; PATH-i; PATH-1; Supplement G; Foldout A and B;    8; FRP-H.i; FRP-H.1; EPP-i EPP-11.1.
Appendix Appendix D 0                                                   NUREG-i NUREG-1 021, 021, Rev. 9, 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             22      Event ##
Event         1                  Page Page     44  of of   28 28
                                                                            ~--------                                ~~----~I Event


== Description:==
== Description:==


Charging Pump "B" trip Time Position I Applicant's Actions or Behavior 800TH OPERATOR:
Event
When directed by the Chief Examiner, insert Event 1, Charging Pump "8" trip. EVENT INDICATIONS:
APP-003-F5; CHG PMP MOTOR OVLDfTRIP APP-001-86; LP LTDN LN HI TEMP (will clear as the running Charging Pump speeds up) APP-003-F4; CHG PMP HI SPEED (after short delay) RO Receives APP-003-FS, notes dual indication for Charging Pump "S", references APP-003-FS actions. RO
* Verifies at least 1 Charging Pump is running and supplying adequate RCP seal injection flow. RO
* Dispatch an operator to check Charging Pump "S" breaker at 480V Sus E-1. RO
* Dispatch operator to check the Charging Pumps. RO
* IF adequate RCP seal injection flow cannot be maintained, THEN refer to AOP-018. RO Receives APP-003-F4 and reviews actions. RO
* IF RCS leakage is indicated, THEN refer to AOP-016. RO
* IF required to maintain level, THEN start standby Charging Pump. (Will clear APP-003-F4)
Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ......;....-
Scenario # 2 Event #
____ Page 5 of ....;2:;,;;8
___ ...,1 Event


== Description:==
== Description:==
Charging Pump Charging    Pump "B"B trip trip Time Time      ~fi    Position Position      I                                    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 1,1, Charging Charging Pump "8" Pump        B trip.
trip.
INDICATIONS:
EVENT INDICATIONS:
APP-003-F5; CHG PMP APP-003-F5;            PMP MOTOR OVLDfTRIP OVLDITRIP APP-OO1-B6; LP APP-001-86;        LTDN LN LP LTDN      LN HI  TEMP (will HI TEMP      (will clear clear asas the the running  Charging Pump running Charging            speeds up)
Pump speeds    up)
APP-003-F4; CHG PMP    PMP HI  HI SPEED (after (after short delay)
APP-003-F5, notes dual indication for Charging Pump "S",
Receives APP-003-FS,                                                                  B, RO APP-003-F5 actions.
references APP-003-FS RO                **      Verifies at least 1    1 Charging Pump is running and supplying adequate RCP seal injection flow.
RO                **    Dispatch an operator to check Charging Pump "S"              B breaker at 480V Sus Bus E-1.
RO                **    Dispatch operator to check the Charging Pumps.
RO                **    IF adequate RCP seal injection flow cannot be maintained, THEN refer to AOP-O1  AOP-018. 8.
RO            Receives APP-003-F4 and reviews actions.
RO                **    IF RCS leakage is indicated, THEN refer to AOP-O1 IF                                                          AOP-016. 6.
RO                  *
* IF required to maintain level, THEN start standby Charging IF Pump._(Will_clear Pump. (Will clear APP-003-F4)
Appendix Appendix D  D                                                                      NUREG-1021, NUREG-1021, Rev. Rev. 9, 9, Supp.
Supp. 11


IRPI K8 Fails Low simulating a dropped rod. Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR:
Appendix D                                       Operator Action                                       Form ES-D-2 Op Test No.:
At the discretion of the Chief Examiner, insert Event 2, IRPI K8 fails low simulating a dropped rod. EVENT INDICATIONS:
Op Test No.:        1 Scenario #
APP-005-F2; ROD BOTTOM ROD DROP Shutdown Bank B, Group 2, K8 indicates 0 inches with RBL ON RO Recognizes K8 RBL and performs Immediate Actions of AOP-001. SRO Enters AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM. RO Immediate Action Step: Check Unexpected Rod Motion in Progress. (NO, Go To Step 7) RO/BOP Make PA Announcement for entry into AOP-001. Determine if multiple rods have dropped:
Scenario           22    Event #
* Prompt Drop present. (NO) RO
Event        2 ____
* More than 1 RBL illuminated. (NO)
                                                                    ....;2~            Page Page   55    of ....;2:;,;;8 of      28_ _ _...,1 Event
* More than 1 IRPI indicates on bottom. (NO) RO Check multiple dropped rods present. (NO, Go To Step 11) RO Check T AVG trending to T REF. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: ......;...-
Scenario # 2 Event # ....;2=--____ Page 6 of ...;2::.;;8
___ ..,1 Event


== Description:==
== Description:==


IRPI K8 Fails Low simulating a dropped rod. Time II Position I Applicant's Actions or Behavior Determine the status of rods.
Event
* APP-005-A3 Illuminated (NO)
* APP-005-F2 Illuminated (YES) SRO/RO
* RBL for affected rod illuminated (YES)
* Indication of Prompt Drop (NO)
* Quadrant Power Tilt indications present (NO)
* APP-005-F3 and F4 extinguished, ERFIS shows no tilt. SRO/RO Check dropped rod present (NO, Go To Step 14) Determine The Status Of IRPI:
* IRPI Indication
-Indicator drift with no flux effects. (NO)
* IRPllndication
-Erratic movement with no flux effects. (YES)
* IRPllndication
-Off-scale high/low with no flux effects. (YES) RO
* Dropped Rod Indication with no flux changes
* Rod Bottom Light for K8 illuminated. (YES) AND
* APP-005-A3, PR DROP ROD extinguished. (YES)
* Simultaneous loss of ALL IRPI Indication present. (NO) SRO Checks IRPI malfunction present. (YES, Go To Section D) RO Check IRPI energized. (YES) SRO Check current plant status MODE 1 or MODE 2. (YES) Review ITS for applicable LCOs: SRO
* 3.1.7, Condition A; Verify Rod position by movable in-core detectors OR Decrease power to .$ 50% within 8 hrs. Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-O-2 Op Test No.: ...;....-Scenario # 2 Event # ____ Page 7 of ....;2::.::8::..-
__ ---l 1 Event


== Description:==
== Description:==
IRPI K8 Fails IRPI        Fails Low simulating a dropped rod.
rod.
Time      II  Position      II                            Applicants Actions or Behavior Applicant's BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 2, IRPI K8 fails low simulating a dropped rod.
EVENT INDICATIONS:
APP-005-F2; ROD BOTTOM ROD DROP Shutdown Bank B, Group 2, K8 indicates 0 inches with RBL ON RO            Recognizes K8 RBL and performs Immediate Actions of AOP-001.
AOP-O01, MALFUNCTION OF REACTOR CONTROL Enters AOP-001, SRO SYSTEM.
Immediate Action Step:
RD RO Check Unexpected Rod Motion in Progress. (NO, Go To Step 7)
RO/BOP            Make PA Announcement for entry into AOP-001. AOP-0O1.
Determine if multiple rods have dropped:
RO
                                      **    Prompt Drop present. (NO)
                                      **    More than 1 1 RBL illuminated. (NO)
                                        **    More than 1 1 IRPI indicates on bottom. (NO)
RD RO            Check multiple dropped rods present. (NO, Go To Step 11)          1 1)
RO            Check TAVGTAVG trending to TREF.
T REF. (YES)
Appendix D  D                                                              NUREG-1 NUREG-1 021,021, Rev. 9, 9, Supp. 11


IRPI K8 Fails Low simulating a dropped rod. Time i Position II Applicant's Actions or Behavior BOOTH OPERATOR:
Appendix 0D                                        Operator Action Operator                                                  Form ES-D-2 Form       ES-D-2 Op Test No.:
If the crew chooses to perform a power reduction lAW LeO 3.1.7, inform the CRSS to wait for Rx Engineering to perform a flux map. SRO Check Adjustment to IRPI will be performed. (NO, Notify I&C, Go To Step 8) SRO Implement the EALs and return to procedure and step in effect. Appendix 0 NUREG-1021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-O-2 Op Test No.: ......;...-
Op Test No.:        1        Scenario ##
Scenario # 2 Event # 3 Page 8 of 28 Event
Scenario            22      Event ##
Event          2
                                                                      ....;2=--_ _ _ _ PagePage    66    of ...;2::.;;8 of     28_ _ _..,1 Event


== Description:==
== Description:==


Steam Flow Channel FT-494 Fails Low. Time Position I Applicant's Actions or Behavior BOOTH OPERATOR:
Event
At the discretion of the Chief Examiner, insert Event 3, Steam Flow channel FT-494 fails low. EVENT INDICATIONS:
APP-006-C1; S/G C FW > STM FLOW APP-006-C2:
S/G C STM > FW FLOW APP-006-C3; S/G C L VL DEV FR-498, Pen #1 (Red) decreasing and FCV-498 CLOSING. BOP Recognizes FT -494 has failed and performs Immediate Actions of AOP-025. SRO Enters AOP-025, and determines Section F is the applicable section. BOP Immediate Action Step: Place the affected FRV (FeV-498 for S/G "C") in MAN. BOP Immediate Action Step: Restore Affected S/G Level To Between 39% And 52%. NOTE: The crew may receive a Power Limit Warning and reduce the Turbine Limiter to maintain power < 100%. RO/BOP Make PA announcement for entry into AOP-025. Place The Affected S/G Steam Flow Selector Switch To The Alternate BOP Channel. (CH-495) (Recorder pen will return to normal status on FR-498) Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # 3 Page 9 of 28 Event


== Description:==
== Description:==
IRPI K8 IRPI  K8 Fails Fails Low Low simulating simulating aa dropped dropped rod.rod.
Time      III  Position Position      I                                  Aoclicants Actions or Behavior Applicant's            Behavior Determine the status of rods.
                                      **    APP-005-A3 Illuminated (NO)
                                      **    APP-005-F2 Illuminated (YES)
SRO/RO              **      RBL for affected rod illuminated (YES)
                                      **      Indication of Prompt Drop (NO)
                                        **    Quadrant Power Tilt indications present (NO)
                                                    **  APP-005-F3 and F4 extinguished, ERFIS    ERRS shows no tilt.
S RO/RO SRO/RO          Check dropped rod present (NO, Go To Step 14)
Determine The Status Of IRPI:
                                        **    IRPI Indication - Indicator drift with no flux effects. (NO)
                                        **    IRPI Indication - Erratic movement with no flux effects. (YES)
IRPllndication     
                                        **    IRPI Indication - Off-scale high/low with no flux effects. (YES)
IRPllndication RO                **      Dropped Rod Indication with no flux changes
                                                  **    Rod Bottom Light for K8 illuminated. (YES)
AND
                                                    **  APP-005-A3, PR DROP ROD extinguished. (YES)
                                      **    Simultaneous loss of ALL IRPI Indication present. (NO)
SRO            Checks IRPI malfunction present. (YES, Go To Section D)
RO            Check IRPI energized. (YES)
SRO SRO            Check Check current plant    plant status MODE 11 or MODE 2. (YES)
Review ITS  ITS for applicable LCOs:
SRO SRO                *
* 3.1  .7, Condition A; Verify Rod position by 3.1.7,                                            by movable in-core detectors detectors OR Decrease Decrease power power to .$
                                                                                          < 50% within 8 8 hrs.
hrs.
Appendix Appendix D  0                                                                    NUREG-1 NUREG-1 021, 021, Rev.
Rev. 9, 9, Supp.
Supp. 11


Steam Flow Channel FT-494 Fails Low. Time 1 Position I Applicant's Actions or Behavior CONTINUOUS ACTION STEP: Restore Affected Controller To Automatic:
Appendix 0D Appendix                                    Operator Action Operator  Action                                          Form Form ES-O-2    ES-D-2 Op Test No.:
BOP
Op Test No.:        1 Scenario ##
* Check S/G level within +/- 1 % of PROGRAMMED LEVEL (If YES -Place in Auto and Go To Step 6) WHEN S/G level is within +/- 1 % of PROGRAMMED LEVEL, THEN place the affected Controller in AUTO. SRO Reviews, briefs and directs taking FT-494 instrument out of service using OWP-034, SF-5. Perform OWP-034, SF-5 actions to remove channel from service.
Scenario          22    Event ##
* Remove FT-494 input to the CALO program by removing ERFIS Point. SRO/BOP
Event        2 ____
* FR-498 Steam Flow Selector Switch selected to CH 495. (APP-036-L 1 will be received for entering Hagan Racks)
_2~                  Page Page    77    of of ....;2::.::8::..-_
* Trip bistable FC-494 (APP-006-F4 received)
28            _---l 1
* Trip bistable FC-498B-1 (APP-006-C2 received)
Event
SRO Go To Procedure Main Body, Step 2. SRO Implement the EALs. Review applicable ITS. SRO
 
* Table 3.3.1-1, #14, Condition E -Trip bistables within 6 hours.
== Description:==
* Table 3.3.2-1, #1f, 1 g, 4d, 4e, Condition D -Place Channel in trip within 6 hours. SRO Return to procedure and step in effect. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ....;...-Scenario # 2 Event # 4 Page 10 of 28 Event
 
Event
 
== Description:==
IRPI K8 IRPI      Fails Low K8 Fails    simulating aa dropped Low simulating    dropped rod.
rod.
Time Time      i  Position Position    III                          Acolicants Actions Applicant's Actions or Behavior or Behavior BOOTH OPERATOR:
BOOTH    OPERATOR: IfIf the      the crew crew chooses chooses to to perform perform aa power      reduction lAW power reduction      lAW LeOLCO 3.1.7,    3.t7, inform the CRSS to wait for Rx Engineering to perform a flux map.
Check Adjustment to IRPIIRPI will be performed. (NO, Notify Notify I&C, l&C, Go To SRO Step 8)
SRO          Implement the EALs and return to procedure and step in effect.
Appendix Appendix D0                                                            NUREG-1021, NUREG-1021, Rev. Rev. 9, 9, Supp.
Supp. 11
 
Appendix 0D                                  Operator Action                                            ES-D-2 Form ES-O-2 Op Test No.:
Op      No.:        1 Scenario ##
Scenario      22    Event #
Event        33                Page Page    88  of of  28 28
                                                                ~--------                          ~------~I Event
 
== Description:==
 
Event
 
== Description:==
Flow Channel FT-494 Steam Flow            FT-494 Fails Fails Low.
Time      ~    Position      I                          Applicants Actions or Behavior Applicant's BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 3, Steam Flow channel FT-494 fails low.
EVENT INDICATIONS:
APP-006-C1; S/G    C FW > STM FLOW SIG C APP-006-C2: S/GSIG C STM >    > FW FLOW APP-006-C3; S/GSIG C LLVL VL DEV FR-498, Pen #1 (Red) decreasing and FCV-498 CLOSING.
Recognizes FT  FT-494
                                                  -494 has failed and performs Immediate Actions of BOP AOP-025.
SRO            Enters AOP-025, and determines Section F is the applicable section.
Immediate Action Step:
BOP (FCV-498 for Place the affected FRV (FeV-498              S/G "C")
for SIG  C) in MAN.
Immediate Action Step:
BOP Restore Affected S/G Level To Between 39% And 52%.
NOTE:                            The crew may receive a Power Limit Warning and reduce the Turbine Limiter to maintain power <        < 100%.
100%.
RO/BOP          Make PA announcement for entry into AOP-025.
Place The Affected S/G Steam Flow Selector Switch To The Alternate BOP            Channel. (CH-495) (Recorder pen will return to normal status on FR-    FR 498)
Appendix D  0                                                            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 Op Test No.:
No.:        1    Scenario ##
Scenario        22      Event ##
Event        33                  Page Page      99    of of  28 28
                  ~-                                          ~--------                              ~------~I Event
 
== Description:==
 
Event
 
== Description:==
Steam Flow Steam    Flow Channel Channel FT-494 FT-494 Fails Fails Low.
Low.
Time Time     1   Position Position I                               Applicants Actions Applicant's Actions or Behavior or Behavior CONTINUOUS ACTION CONTINUOUS          ACTION STEP:STEP:
Restore Affected Controller Restore                Controller To    Automatic:
To Automatic:
BOP BOP          *. Check S/G Check                  within +/-
SIG level within       1% of
                                                                      +/-1%   of PROGRAMMED LEVEL (If YES - Place in in Auto Auto and Go To Step  Step 6)
WHEN S/G level WHEN            level is within +/-+/- 11%% of PROGRAMMED PROGRAMMED LEVEL,    LEVEL, THEN Controller in AUTO.
place the affected Controller Reviews, briefs and directs taking FT-494 instrument out of service SRO using OWP-034, SF-5.
Perform OWP-034, SF-5 actions to remove channel from service.
                                *. Remove FT-494 input to the CALO program by removing ERFIS Point.
SRO/BOP           *. FR-498 Steam Flow Selector Switch selected to CH 495.
(APP-036-L11 will be received for entering Hagan Racks)
(APP-036-L
                                *. Trip bistable FC-494 (APP-006-F4 received)
                                  *. Trip bistable FC-498B-1 (APP-006-C2 received)
SRO       Go To Procedure Main Body, Step 2.
SRO       Implement the EALs.
Review applicable ITS. ITS.
                                **   Table 3.3.1-1, 3.3.1-1, #14, Condition EE - Trip bistables within 66 hours.
SRO SRO
                                  .* Table 3.3.2-1, #lf, #1f, 11g, 4d, 4e, Condition D    D - Place Channel in trip within 6 hours.
hours.
SRO SRO      Return to to procedure procedure and      step in and step     in effect.
effect.
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 Op Test No.:
No.:        1      Scenario ##
Scenario          22      Event ##
Event        44                Page Page    10 10    of of    28 28
                  ....;...-                                       ~--------                              ~~----~
Event
 
== Description:==
 
Event


== Description:==
== Description:==
FWH 4A FWH    4A Tube Tube Leak.
Leak.
Time Time      II  Position Position  II                                Applicants Actions Applicant's Actions or or Behavior Behavior BOOTH OPERATOR:
BOOTH    OPERATOR: At          At the    discretion of the discretion        of the the Chief  Examiner, insert Chief Examiner,      insert Event Event 4,4, FWH FWH 4A 4A Tube Tube Leak.Leak.
EVENT INDICATIONS:
APP-007-E7; HTR APP-007-E7;    HTR 4A HI/LO HI/LO LVL APP-007-D8; HTR APP-007-08;    HTR 38 3B HI/LO HI/LO LVL LVL (-2
(-.2 minutes minutes later) later)
APP-007-E8; HTR APP-007-E8;    HTR 48 4B HI/LO HI/LO LVL LVL (Later)
BOP          Respond to alarms and references APP-007-E7.
Dispatch an operator to check sight glass level and Level Control SRO/BOP Valve position.
NOTE:                        The crew may receive a Power Limit Warning ERFIS alarm due to the feedwater transient. If so, they will use the Turbine GV limiter to reduce power to <          < 100%.
BOOTH OPERATOR: When requested, FW Heater 4A is flooded and both Normal and Alternate Drains are open. 4A Shell Side Relief valve is cycling. 4B has a high level and the Normal valve is OPEN and the Alternate drain is cycling.
NOTE:                        The crew may enter AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION due to the transient on the Feedwater system.
AOP-010 steps are listed for reference, but are NOT necessary for successful mitigation of the event.
Enters AOP-O10, AOP-010, MAIN MAIN FEEDWATER/CONDENSATE SRO MALFUNCTION.
MALFUNCTION.
Immediate      Action Step:
Immediate .Action*        Step:
BOP          Check Fdwtr flhnk    Feedwater Regulating        Valves flnrtinn Rcni iItinn Vlvc      Operating  properly in nronrki    in Al AUTO  or ITO or r--.--- r-i**J              .
MANUAL.
MANUAL.*(YES)(YES)
Appendix Appendix DD                                                                NUREG-1 021, NUREG-1      021, Rev.
Rev. 9, 9, Supp.
Supp. 11


FWH 4A Tube Leak. Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR:
Appendix D                                       Operator Action                                               Form ES-D-2 Op Test No.:       1 Scenario #         2       Event #       4
At the discretion of the Chief Examiner, insert Event 4, FWH 4A Tube Leak. EVENT INDICATIONS:
_4..;...-_ _ _ _ Page           11 11            28 _ _---11 of ...,;2;;;,;8;......
APP-007-E7; HTR 4A HI/LO LVL APP-007-08; HTR 38 HI/LO LVL (-2 minutes later) APP-007-E8; HTR 48 HI/LO LVL (Later) BOP Respond to alarms and references APP-007-E7.
Event
SRO/BOP Dispatch an operator to check sight glass level and Level Control Valve position.
NOTE: The crew may receive a Power Limit Warning ERFIS alarm due to the feedwater transient.
If so, they will use the Turbine GV limiter to reduce power to < 100%. BOOTH OPERATOR:
When requested, FW Heater 4A is flooded and both Normal and Alternate Drains are open. 4A Shell Side Relief valve is cycling. 4B has a high level and the Normal valve is OPEN and the Alternate drain is cycling. NOTE: The crew may enter AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION due to the transient on the Feedwater system. AOP-010 steps are listed for reference, but are NOT necessary for successful mitigation of the event. SRO Enters AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION.
Immediate .Action* Step: BOP Check Feedwater Regulating Valves Operating properly in AUTO or MANUAL.*(YES)
Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ......;....-
Scenario # 2 Event # _4..;...-____ Page 11 of ...,;2;;;,;8;......
__ ---11 Event


== Description:==
== Description:==


FWH 4A Tube Leak. Time I Position ! Applicant's Actions or Behavior Continuous Action Step: RO CheckReactorTripSetpoint being approached. (NO, Go To Step 4) I F Reactor Trip Setpointis being approached, THEN trip the Reactor and Go To Path:-1. RO/BOP Make PA Announcement For Entry into AOP-01 O. SRO Goes to Step 21, Pipe Break/Leak.
Event
 
== Description:==
FWH 4A Tube Leak.
Time     I   Position     !                                 Applicants Actions or Behavior Applicant's Continuous Action Step:
I            D-.&.-...                    k;                    IKIfi        r-. Ci.,.. A RO KU            CheckReactorTripSetpoint     JLJII IL being
                                  .jI IL,r I IQi..LiJI I I IJ ...eL 1          LJII I approached.
ajji LJ.,I ILl. (NO, 11J.J, Go U To I Li Step )L.) 4) 1.)
I IF  Prfrir    Trir      irirf                            TI.4FKI IF Reactor Trip Setpointis being approached, THEN trip the Reactor     +rr th        Prfrr nd Go and     (o To Path:-1.
Pth-1 RO/BOP           Make PA Announcement For Entry into AOP-01 O.                 0.
SRO           Goes to Step 21, Pipe Break/Leak.
Match Steam Flow With Feed Flow:
Match Steam Flow With Feed Flow:
* Reduce Turbine Load to match Feed Flow and Steam Flow BOP using Attachment
                                        *. Reduce Turbine Load to match Feed Flow and Steam Flow BOP                       using Attachment 1.
: 1.
* Check Feed Flow matched with Steam Flow. (YES)
* Check Feed Flow matched with Steam Flow. (YES)
* Stop the power reduction Determine location of the leak:
                                        ** Stop the power reduction Determine location of the leak:
* Visual observation of an external leak. CREW
                                        *. Visual observation of an external leak.
* Feed Water Heater level alarms.
CREW                   ** Feed Water Heater level alarms.
* Feed Water Heater Normal and Alternate drain valve positions.
                                        ** Feed Water Heater Normal and Alternate drain valve positions.
* Feed Water Heater #1 & #2 Emergency Dump valve positions.
                                        ** Feed Water Heater #1 & #2 Emergency Dump valve positions.
CREW If tube leakage is occurring, then bypass the affected string of heaters for repair of defective tubes using OP-407, Heater Drains and Vents. SRO Determine that heater must be bypassed and isolated per OP-407 and commence a plant down power to < 517 MWe. Appendix D NUREG-1 021, Rev. 9, SUpp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ......;...-
If tube leakage is occurring, then bypass the affected string of heaters CREW for repair of defective tubes using OP-407, Heater Drains and Vents.
Scenario # 2 Event # 5 Page 12 of 28 Event
Determine that heater must be bypassed and isolated per OP-407 and SRO commence a plant down power to << 517 MWe.
Appendix D D                                                                  NUREG-1 NUREG-1 021, 021, Rev. 9, Supp.SUpp. 11
 
AppendixDD Appendix                                           OperatorAction Operator       Action                                             Form Form ES-D-2 ES-D2 OpTest Op TestNo.:
No.:         1        Scenario##
Scenario            22      Event##
Event        55                    Page Page      12 12 ofof    28 28
                  ......;...-                                           ~--------                                  ~------~I EventDescription:
Event
 
== Description:==
Downpowerto Downpower        to support support removing removing FWHFWH 4A 4A from from service.
service.
Time Time      II    Position Position      II                                  Applicants Actions Applicant's  Actions oror Behavior Behavior NOTE:
NOTE:                              The crew The      crew will will use use OP-105, OP-105, MANEUVERING MANEUVERING THE          THE PLANT PLANT WHEN WHEN GREATER THAN GREATER          THAN 25%  25% POWER, POWER, to    to perform the plant down perform      the  plant    down power.
power.
Only the Only    the applicable applicable stepssteps have have been been listed.
listed.
SRO SRO              Notify  the Load NoUfy the    Load Dispatcher Dispatcher that that unit unit load    will be load will    be reduced.
reduced.
Notify RC Notify  RC that that increased increased radiation radiation levels levels are are expected expected in  in the the CVCV Pump Pump SRO SRO              Bays and Bays    and Pipe Pipe Alley Alley due due to to normal normal shutdown shutdown crud        bursts.
crud bursts.
Monitor the Monitor    the highest highest operable operable Power Range Channel    Channel and and the highest highest RO RO              operable Intermediate Range Channel on NR-45.
IF Reactor Engineering has not provided technical guidance, THEN SRO/RO determine the reactivity change  chanqe required.
IF additional letdown flow is desired, THEN:
RO                ** Start additional Charging Pumps as necessary,
                                        *. Place additional letdown orifice in service.      service .
IF a significant change in RCS Boron concentration occurs, THEN RO energize additional PZR heaters as needed.
NOTE:
NOTE:                            OP-301, OP-301, Section Section 8.2.8 8.2.8 Quick Quick Boration Boration Checklist (shaded area)          area) is is included included in      the following in the    following steps, steps, butbut may may be be used used following following the the commencem commencement      ent of of the the plant plant down down power.
power.
DETERMIN DETERMINE      E the the amount amount of of Boric Boric Acid Acid toto add add toto the the RCS RCS andand RO RO            OBTAIN OBTAIN an    an independent independent checkcheck of of the the volume volume required.
required.
NOTE:
NOTE:                            -.160
                                  -160 gallons gallons of  of Boric Boric Acid Acid will    be added will be    added based based on  on rods rods stepping stepping to to 160 160 steps.
steps. (The(The crew crew will will add add Boric Boric Acid Acid in in 2-4 2-4 batches.)
batches.)
RO RO            OBTAIN OBTAIN permission permission from from the the CRSS CRSS OR    OR thethe SSO SSO toto borate.
borate.
Appendix Appendix DD                                                                      NUREG-1021, NUREG-1                Rev. 9,9, Supp.
021, Rev.        Supp. 11
 
Appendix 0D                                        Operator Action Operator    Action                                          Form ES-D-2 Form          ES-D-2 Op Test Op Test No.:
No.:        1 Scenario ##
Scenario            22      Event ##
Event        5
_5;;...-_ _ _ _ Page Page     13 13    of .....:2:.;;8 of       28_ _ _-11 Event


== Description:==
== Description:==


Downpower to support removing FWH 4A from service. Time II Position II Applicant's Actions or Behavior NOTE: The crew will use OP-105, MANEUVERING THE PLANT WHEN GREATER THAN 25% POWER, to perform the plant down power. Only the applicable steps have been listed. SRO Notify the Load Dispatcher that unit load will be reduced. SRO Notify RC that increased radiation levels are expected in the CV Pump Bays and Pipe Alley due to normal shutdown crud bursts. RO Monitor the highest operable Power Range Channel and the highest operable Intermediate Range Channel on NR-45. SRO/RO IF Reactor Engineering has not provided technical guidance, THEN determine the reactivity change required.
Event
IF additional letdown flow is desired, THEN: RO
* Start additional Charging Pumps as necessary,
* Place additional letdown orifice in service . RO IF a significant change in RCS Boron concentration occurs, THEN energize additional PZR heaters as needed. 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. RO DETERMINE the amount of Boric Acid to add to the RCS and OBTAIN an independent check of the volume required.
NOTE: -160 gallons of Boric Acid will be added based on rods stepping to 160 steps. (The crew will add Boric Acid in 2-4 batches.)
RO OBTAIN permission from the CRSS OR the SSO to borate. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: ......;....-
Scenario # 2 Event # _5;;...-____ Page 13 of .....:2:.;;8
___ -11 Event


== Description:==
== Description:==
Downpower to Downpower        to support support removing removing FWHFWH 4A 4A from from service.
service.
Time Time      ~I  Position Position      ~                                  Applicants Actions or Behavior Applicant's            Behavior RO RO            PLACE the    the RCS RCS MAKEUP MODE  MODE selector selector switch to BORATE.
RO                      YIC-1 13, BORIC ACID TOTALIZER to desired quantity.
SET YIC-113, IF desired, THEN PLACE FCV-113A,      FCV-1 13A, BORIC BORIC ACID FLOW, in MAN              MAN RO RO AND ADJUST using the UP and DOWN pushbuttons.
RO          Momentarily PLACE the RCS MAKEUP SYSTEM switch to START.
IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:
RO              ** Rod Motion is blocked or in the wrong direction
                                    ** TTpv    AVG increases
                                          ** Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:
RO                ** FCV-113A, FCV-1 13A, BORIC ACID FLOW, closes.
                                        ** 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.
The RCS MAKEUP SYSTEM is OFF.
IF desired, THEN FLUSH the Boric Acid flow path as follows:
                                      ** PLACE the RCS MAKEUP MODE selector switch in the ALT                                ALT DILUTE position.
                                      ** SET YIC-1          14, PRIMARY WTR TOTALIZER to 115-20 YIC-114,                                              5-20 gallons.
                                    ** PLACE FCV-1      FCV-114B,14B, BLENDED MU TO VCT to CLOSE.
                                    ** Momentarily PLACE RCS MAKEUP            MAKEUP SYSTEM switch to START.
START.
RO                ** IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:
Unanticipated Rod Motion o0 Unanticipated            Motion Primary o0 Primary      Water    addition reaches the addition            the desired desired value
                                      **    WHEN the desired amount of Primary Water has              has been added    added to the    RCS, THEN verify the following:
the RCS, o0 FCV-1 FCV-114A14A closes.
FCV-113B o0 FCV-1          closes.
1 3B closes.
IF in Auto, THEN the operating Primary Water_Pump o__IF_in_Auto,_THEN_the_operating_Primary 0                                                    Water Pump Appendix Appendix D  0                                                                  NUREG-1 NUREG-1 021,021, Rev.
Rev. 9,9, Supp.
Supp. 11


Downpower to support removing FWH 4A from service. Time Position Applicant's Actions or Behavior RO PLACE the RCS MAKEUP MODE selector switch to BORATE. RO SET YIC-113, BORIC ACID TOTALIZER to desired quantity.
Appendix D Appendix     D                               Operator Action Operator   Action                                         Form Form ES-D-2 ES-D-2 Op Test Op Test No.:
RO IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN AND ADJUST using the UP and DOWN pushbuttons.
No.:        1      Scenario #
RO Momentarily PLACE the RCS MAKEUP SYSTEM switch to START. IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:
                  --:...- Scenario #         22    Event ##
RO
Event      _5~5 ____             Page Page    14 14  of      28_ _ _...,1 of ,..;2;;,;;8 Event
* Rod Motion is blocked or in the wrong direction
* T AVG increases
* Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:
* FCV-113A, BORIC ACID FLOW, closes. RO FCV-113B, 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:
* PLACE the RCS MAKEUP MODE selector switch in the AL T DILUTE position.
* SET YIC-114, PRIMARY WTR TOTALIZER to 15-20 gallons.
* PLACE FCV-114B, BLENDED MU TO VCT to CLOSE.
* Momentarily PLACE RCS MAKEUP SYSTEM switch to START. RO
* IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:
0 Unanticipated Rod Motion 0 Primary Water addition reaches the desired value
* WHEN the desired amount of Primary Water has been added to the RCS, THEN verify the following:
0 FCV-114A closes. 0 FCV-113B closes. 0 IF in Auto, THEN the operating Primary Water Pump Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --:...-Scenario # 2 Event # ____ Page 14 of ,..;2;;,;;8
___ ...,1 Event


== Description:==
== Description:==


Downpower to support removing FWH 4A from service. Time II Position II Applicant's Actions or Behavior stops. 0 The RCS MAKEUP SYSTEM is OFF. RETURN the RCS Makeup System to automatic as follows:
Event
* VERIFY FCV-114A is in AUTO.
 
* PLACE FCV-114B to the AUTO position.
== Description:==
RO
Downpower to Downpower      to support support removing removing FWHFWH 4A 4A from from service.
* PLACE the RCS MAKEUP MODE switch in AUTO.
service.
* VERIFY FCV-113A is in AUTO.
Time Time     III  Position Position III                            Apolicants Actions Applicant's Actions or  Behavior or Behavior stops.
* Momentarily PLACE the RCS MAKEUP SYSTEM switch in the START position.
stops.
RECORD, in AUTO LOG, as indicated by PRIMARY WATER RO TOTALIZER, YIC-114 AND Boric Acid TOTALIZER, YIC-113 the total amount of Primary Water AND Boric Acid added during the boration.
0o  The The RCS     MAKEUP SYSTEM RCS MAKEUP          SYSTEM is    is OFF.
RO MONITOR parameters for the expected change in reactivity AND inform the CRSS OR the SSO of the results of the boration.
OFF.
RETURN the RCS Makeup  Makeup System to automatic automatic as follows:
                                    *. VERIFY FCV-114A FCV-1 14A is in AUTO.
                                    *. PLACE PLACE FCV-114B FCV-1 1 4B to the AUTO position.position.
RO RO              *. PLACE PLACE the RCS        MAKEUP MODE RCS MAKEUP         MODE switch in AUTO.
                                    * . VERIFY     FCV-1 FCV-113A1 3A  is in AUTO.
                                    *. Momentarily PLACE the RCS MAKEUP        MAKEUP SYSTEM switch in the START position.
RECORD, in AUTO LOG, as indicated by PRIMARY WATER RO                           YIC-1 14 AND Boric Acid TOTALIZER, YIC-113 TOTALIZER, YIC-114                                                YIC-1 13 the total amount of Primary Water AND Boric Acid added during           durinq the boration.
MONITOR parameters for the expected change in reactivity AND RO inform the CRSS OR the SSO of the results of the boration.
IF EH Turbine Control is in OPER AUTO, THEN reduce turbine load as follows:
IF EH Turbine Control is in OPER AUTO, THEN reduce turbine load as follows:
* Place the EH Turbine Control in the desired position:
BOP              *. Place the EH Turbine Control in the desired position: IMP IN.
IMP IN. BOP
                                    *. Set the desired load in the SETTER.
* Set the desired load in the SETTER.
                                    *. Select the desired Load Rate.
* Select the desired Load Rate.
                                    ** Depress the GO pushbutton.
* Depress the GO pushbutton.
Verify proper programming of the following:
Verify proper programming of the following:
RO
RO               ** TAvG TAVG tracks within 5 degrees FF of TREF. T REF.
* T AVG tracks within 5 degrees F of T REF.
                                    .* PZR level tracks within 5% of reference level.
* PZR level tracks within 5% of reference level. SRO/RO Maintain the control rods above the minimum allowable rod height borating the RCS lAW OP-301. BOOTH OPERATOR:
Maintain the control rods above the minimum allowable rod height SRO/RO borating the RCS lAW OP-301.
As soon as the power reduction is 2: 5% or at the discretion of the Chief Examiner, insert the next event. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # 6 and 7 Page 15 of 28 ----------
BOOTH BOOTH OPERATOR: As soon            soon as the power power reduction is    is 2: 5% or at the discretion discretion of      of the Chief Examiner,       insert the next event.
Examiner, insert                event.
Appendix Appendix D   D                                                          NUREG-1 021, NUREG-1      021, Rev.
Rev. 9, 9, Supp.
Supp. 11
 
Appendix 0D                              Operator Action Operator                                                    Form ES-D-2 Form  ES-D-2 Op Test Op Test No.:
No.:       1    Scenario ##
Scenario        22    Event ##
Event        66 and and 77          Page Page        15 15  of of  28 28
                  ~-                                         ----------                              ~------~I Event
 
== Description:==
 
Event
Event


== Description:==
== Description:==
Rods continue Rods  continue to to step step requiring requiring aa Reactor Reactor Trip, Trip, Failure Failure of of the the Turbine Turbine to to Trip.
Trip.
Time      ~  Position Position  II                            Applicants Actions or Behavior Applicant's            Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 6, Control Rods continue to step requiring a Reactor Trip.
EVENT INDICATIONS:
Rod speed indication and directional lights Control Rod step counters RD notices that rods are stepping when not demanded and performs RO RD RO                                  AOP-OO1, MALFUNCTION OF REACTOR Immediate Actions of AOP-001, CONTROL SYSTEM.
Immediate Action Step:
RD RO Check unexpected rod motion  motion in progress. (YES)
Action Step:
Immediate Action RD RO Check Reactor Power greater than 15%. (YES)
Immediate Action Step: Step:
Check Turbine Load:
CheckTurbine      Loa&
RO/BOP            **  Control rods stepping in AND unexpected Control.                              unexpected load reduction in progress. (NO)                        .
OR
                                  .*  Unexpected Unexpected load reduction has occurred. (NO)
Immediate Action Step: Step:
Attempt  to Stop Rod AttempttoSt6p      Rod Motion as follows:
                                  .*  IF ROD BANK SELECTOR Switch is in AUTO, THEN place the IFBODBANKSELECTORSwitch ROD    BANK SELECTOR Switch in ROD I3ANKSELECTOHSwitch                  in Manual.
Manual.
RD RO
                                  .*  IF IF ROD ROD BANKBANK SELECTOR Switch is          is in in Manual, Manual, THEN place the theRODROD BANK BANK SELECTOR Switch in Auto.        Auto.
                                  .*  IF IF Rod Rod Motion Motion does NOT        stop, THEN NOTstop,      THEN trip trip the Reactor and and Go Go To PATH-i.
PATH..:l.
Appendix Appendix D  0                                                          NUREG-1021, NUREG-1021, Rev. Rev. 9,9, Supp.
Supp. 11


Rods continue to step requiring a Reactor Trip, Failure of the Turbine to Trip. Time Position II Applicant's Actions or Behavior BOOTH OPERATOR:
Appendix D                                 Operator Action                                         Form ES-D-2 Op Test Test No.:
At the discretion of the Chief Examiner, insert Event 6, Control Rods continue to step requiring a Reactor Trip. EVENT INDICATIONS:
No.:
Rod speed indication and directional lights Control Rod step counters RO notices that rods are stepping when not demanded and performs RO Immediate Actions of AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM. RO Immediate Action Step: Check unexpected rod motion in progress. (YES) RO Immediate Action Step: Check Reactor Power greater than 15%. (YES) Immediate Action Step: CheckTurbine Load: RO/BOP
Op Scenario #
* Control. rods stepping in AND unexpected load reduction in progress. (NO) . OR
Scenario          2     Event #
* Unexpected load reduction has occurred. (NO) Immediate Action Step: AttempttoSt6p Rod Motion as follows:
Event          and 77 66 and
* IFBODBANKSELECTORSwitch is in AUTO, THEN place the ROD I3ANKSELECTOHSwitch in Manual. RO
                                                              ~~------
* IF ROD BANK SELECTOR Switch is in Manual, THEN place theROD BANK SELECTOR Switch in Auto.
Page Page       16 16   of of  28 28
* IF Rod Motion does NOTstop, THEN trip the Reactor and Go To PATH..:l.
                                                                                                    ~------~I Event
Appendix 0 NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 2 Event # 6 and 7 Page 16 of 28 Event


== Description:==
== Description:==


Rods continue to step requiring a Reactor Trip, Failure of the Turbine to Trip. Time II Position II Applicant's Actions or Behavior RO Manually trips the Reactor by depressing the Reactor Trip pushbutton.
Event
Notices that the Turbine failed to trip. Attempts to manually trip the BOP turbine by depressing the Turbine Trip pushbutton and THINK pushbutton simultaneously.
Turbine will not trip from the RTGB. BOP manually runs back the turbine: BOP
* Verifies the Turbine is in TURBINE MANUAL.
* Depresses the GV DOWN and FAST button simultaneously until ALL GV valves indicate CLOSED. RO Immediate Action Step: Reactor Tripped. (YES) " Immediate Action Step: BOP Turbine Tripped.(NO)
Trip or Runback the Turbine. (YES, RLinback was successful)
,,' . BOP Immediate Action' Step: E-1 AND E-2 energized.
'(YES) RO Immediate Action Step: SI Initiated. (YES) Appendix D NUREG-1021 , Rev. g, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # ......;....-
-8,9 and 10 Page 17 of 28 Event


== Description:==
== Description:==
Rods continue to step requiring Rods                      requiring a Reactor Reactor Trip, Failure Failure of the Turbine to Trip.
Time      IIH Position  III                            Applicants Actions or Behavior Applicant's RO          Manually trips the Reactor by depressing the Reactor Trip pushbutton.
Notices that the Turbine failed to trip. Attempts to manually trip the BOP        turbine by depressing the Turbine Trip pushbutton and THINK pushbutton simultaneously.
Turbine will not trip from the RTGB. BOP manually runs back the turbine:
BOP            ** Verifies the Turbine is in TURBINE MANUAL.
                                  ** Depresses the GV DOWN and FAST button simultaneously until ALL GV valves indicate CLOSED.
Immediate Action Step:
RO Reactor Tripped. (YES)
Immediate Action Step:
BOP        Turbine Tripped.(NO)
Turbine.. (YES, RLinback Trip or Runback the Turbine.
Runback was successful)
Immediate Action Action' Step:
Step:
BOP E-1 AND E-2 energized. '(YES)(YES)
Immediate Action Step:
RO SI Initiated. (YES)
Appendix D  D                                                          NUREG-1021 , Rev. 9, NUREG-1021,              g, Supp. 11


FW Break on S/G "B" inside CV with a loss of ALL feedwater.
Appendix DD Appendix                                                  OperatorAction Operator        Action                                                Form Form ES-D-2 ES-D-2 TestNo.:
CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time 1 Position II Applicant's Actions or Behavior BOOTH OPERATOR:
OpTest  No.:         1        Scenario##
As soon as the Reactor Trips, verify Events 8, 9 and 10 are inserted.
Op Scenario
If requested, Manually trip the Turbine locally. NOTE: The crew may take action lAW OMM-022 to start CV Spray Pump "A" and shut Phase B valves CVC-381 and FCV-626 following verification of Immediate Actions. The crew may also stop ALL RCPs due to a Phase B isolation.
                                                    - 22          Event##
CREW Open Foldout A.
Event          8,9andlO 8,9
* RCP Trip criteria.
                                                                                ~~~~--
IF BOTH conditions are met, THEN stop all RCPs: (NO) RO 0 SI Pumps -AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0 RCS Subcooling -< 35 degrees F [55 degrees F]
and 10         Page Page      1717 ofof    28 28
* SI actuation criteria.
                                                                                                                            ~~----~I EventDescription:
IF EITHER condition occurs, THEN Actuate SI SRO/RO and Go To PATH-1, Entry Point A: 0 RCS Subcooling -< 35 degrees F [55 degrees F] 0 PZR Level-CAN NOT BE MAINTAINED>
Event  
10% [32%].
* MSR Isolation criteria.
IF ANY Purge OR Shutoff Valve does not BOP indicate fully closed, THEN place the associated RTGB Switch to CLOSE. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --.;....-Event


== Description:==
== Description:==
FW Break FW      Break on  on S/G S/G "B" B inside inside CV CV with with aa loss loss of of ALL ALL feedwater.
feedwater. CV  CV Spray Spray Pump Pump A fails "A"    fails toto start, start, Phase Phase BB valves valves FCV-626 FCV-626 and  and CVC-381 CVC-381 fail fail to to CLOSE.
CLOSE.
Time Time    1      Position Position        II                                      Applicants Actions Applicant's    Actions or or Behavior Behavior BOOTH OPERATOR:
BOOTH      OPERATOR: As            As soon soon as    as the the Reactor Reactor Trips, Trips, verify verify Events Events 8, 8, 99 and and 10  10 are are inserted. IfIf requested, inserted.              requested, Manually Manually trip  trip the    Turbine    locally.
the Turbine locally.
NOTE:
NOTE:                              The crew The      crew may may take  take action action lAWlAW OMM-022 OMM-022 to    to start start CV CV Spray Spray Pump Pump A and "A"    and shut shut PhasePhase BB valves valves CVC-381 CVC-381 and        FCV-626        following and FCV-626 following verification of verification                Immediate Actions.
of Immediate        Actions. The The crew crew may may also also stop stop ALL ALL RCPs RCPs due to due    to aa Phase Phase BB isolation.
isolation.
CREW CREW                Open Foldout Open      Foldout A. A.
                                          *.      RCP Trip criteria. IF BOTH RCP                            BOTH conditions are met, THEN stop          stop all RCPs: (NO)
RCPs:      (NO)
RO                                0o      SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF OF DELIVERING FLOW TO THE CORE DELIVERING 0o    RCS Subcooling - <    -  < 35 degrees F [55 degrees F]
                                          *. SI actuation criteria. IF EITHER condition occurs, THEN Actuate SI                    SI and Go To PATH-1,PATH-i, Entry Point A:
RO/ R 0 SRO/RO o0 RCS Subcooling - <      -  < 35 degrees F [55 degrees F]
o0            Level- CAN NOT BE MAINTAINED>
PZR Level      -                    MAINTAINED> 10%      10% [32%].
                                          **      MSR Isolation criteria. IF ANY Purge OR Shutoff Valve does not BOP BOP                          indicate indicate fully closed, THEN place the associated    associated RTGB Switch  Switch to CLOSE.
CLOSE.
Appendix Appendix DD                                                                              NUREG-1021, NUREG-i              Rev. 9,9, Supp.
021, Rev.          Supp. 11
Appendix D                                    Operator Action                                                        Form ES-D-2 Op Test No.:        1 Scenario #        2        Event #          8, 9 and 10_ _ Page
_8;.:.,...;,9...;;;a;.;.;nd;;..1;..;;O    18        28_ _ _-11 of ...,;2;;,;;8 Event


Operator Action Form ES-D-2 Scenario # 2 Event # _8;.:.,...;,9...;;;a;.;.;nd;;..1;..;;O
== Description:==
__ Page 18 of ...,;2;;,;;8
FW Break on S/G SIG "B"B inside CV with a loss of ALL feedwater. CV Spray Pump A fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE.
___ -11 FW Break on S/G "B" inside CV with a loss of ALL feedwater.
                              "A" I   Time     I  Position     I                              Applicants Applicant's Actions or Behavior
CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. I Time II Position II Applicant's Actions or Behavior
                                      **  S/G isolation criteria. IF both the following conditions are met, THEN perform the following:
* S/G isolation criteria.
                                          *. Any S/G pressure is decreasing in an uncontrolled manner OR
IF both the following conditions are met, THEN perform the following:
                                          *. Any   S/G   has completely depressurized.
* Any S/G pressure is decreasing in an uncontrolled manner OR
* Any S/G has completely depressurized.
AND
AND
* At least ONE S/G is intact. 0 Reset SI. 0 CLOSE the appropriate AFW isolation valves to the faulted S/G AND OPEN the associated breaker for the valves closed.
                                          *. At least ONE S/G   SIG is intact.
* S/G "B"
0o  Reset SI.
* V2-14B, SDAFW PUMP DISCH, MCC-9, CMPT -1C
0o  CLOSE the appropriate AFW isolation valves to the SIG AND OPEN the associated breaker for the faulted S/G valves closed.
* V2-16B, AFW HDR DISCH, MCC-10, CMPT -4F 0 WHEN the faulted S/G drys out, THEN dump steam from intact S/Gs to control RCS repressurization.
* S/G SIG "B" B
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) BOP Verify both MDAFW pumps are running. (NO) BOP If additional Feedwater is required, start the SDAFW pump. (NO, Pump started but tripped) RO Verify 2 SI pumps running. (YES) RO Verify Both RHR pumps running. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event
                                                                  *. V2-14B, SDAFW PUMP DISCH, MCC-9, CMPT--1C CMPT                        1C
                                                                    .*           V2-16B, AFW HDR DISCH, MCC-10,      MCC-1O, CMPT - 4F                 -
0o  WHEN the faulted S/G                     SIG drys out, THEN dump steam from intact S/Gs to control RCS repressurization.
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)
BOP         Verify both MDAFW pumps are running. (NO)
If additional Feedwater is required, start the SDAFW pump. (NO, BOP Pump started but tripped)
RO           Verify 2 SI pumps running. (YES)
RO           Verify Both RHR pumps running. (YES)
Appendix D D                                                                                NUREG-1 021, Rev. 9, Supp. 1         1
 
AppendixDD Appendix                                            OperatorAction Operator      Action                                              Form Form ES-D-2 ES-D-2 TestNo.:
No.:        1      Scenario##
OpTest Op
                  --        Scenario              22        Event##
Event          8, 9 and 10 8,9and10              Page Page      1919 ofof  ......;.;.;.---...,1 28 28 EventDescription:
Event
 
== Description:==
FW Break FW    Break on  on S/G S/G "B"    inside CV B inside  CVwith with aa loss loss ofofALL ALLfeedwater.
feedwater. CV  CV Spray Spray PumpPump A fails "A"  fails toto start, start, Phase Phase BB valves valves FCV-626 FCV-626 and  and CVC-381 CVC-381 failfail toto CLOSE.
CLOSE.
Time Time      II    Position Position    II                                    ApplicantsActions Applicant's    Actions oror Behavior Behavior RO RO          Verify SI Verify          valves are SI valves    are properly properly aligned.
aligned. (YES)(YES)
RO RO          At least At  least 11 CCW CCW pump pump isis running.
running. (YES)
(YES)
BOP BOP          All SW All  SW and  and SW SW Booster Booster pumps pumps running.
running. (NO) (NO)
Attempt to Attempt        to start start all all SW SW andand SW SW booster booster pumps.
pumps. (NO,(NO, SW  SW Booster Booster BOP BOP          Pump "A" Pump      A isis unavailable) unavailable)
BOP          North OR  OR South South SW Header Lo Pressure alarm illuminated.        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 BOP          Verify Verify Control Control RoomRoom Vent aligned aligned for Pressurizatio Pressurization        Mode. (YES) n Mode.        (YES)
BOP BOP          Verify Verify bothboth EDGs EDGs running.
running. (YES)
(YES)
CONTINUO CONTINVOUS          US ACTION ACTION*STEP:STEP:
BOP BOP          Restart Restart battery battery chargers chargers within within 3030 minutes minutes of  of power power.loss        using OP OP-loss using 601.
601.
CONTINUO CONTINUOUS        US ACTION ACTION STEP: STEP:
RO RO CV  Pressure has CVPressure            has remained remained below b.elow 10 10psig~
psig. (NO)
(NO)
RO RO          Verify Verify CV  CV Spray Spray initiated.
initiated. (YES)
(YES)
Appendix Appendix DD                                                                      NUREG-1 NUREG-1021,    021, Rev.
Rev. 9,9, Supp.
Supp. 11
 
Appendix D                                       Operator Action                                    Form ES-D-2 Op Test No.:         1 Scenario #        2    Event #      8, 9 and 10 8,9              Page    20 of  28
                                                                  ~~~~--                            ~---~I Event


== Description:==
== Description:==
FW Break on S/G SIG "B" B inside CV with a loss of ALL feedwater. CV Spray Pump A fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE.
                              "A" Time      II1 Position        I                            Applicants Actions or Behavior Applicant's Verify all CV Spray pumps running with valves properly aligned.
RO (NO, CV Spray Pump "A"    A did not Auto start)
NOTE:                            The crew may have already taken action to start CV Spray Pump A per guidance in OMM-022.
                                "A" RO            Verify - 12 GPM spray additive tank flow. (Will require adjustment)
Verify Phase B isolation valves closed. (NO, takes action to close RO CVC-381 and FCV-626 from the RTGB.)
CRITICAL TASK:                  Verify CVC-381, Phase B CV Isolation Valve is closed prior to PATH-i.
transitioning from PATH-1.
RO            Stop all RCPs. (May be previously stopped)
Verify all MSIVs and MSIV bypass valves closed. (YES)
BOP            (Operator will ensure that switches for the MSIVs are placed in the CLOSE position)
SRO            Locally open breaker for HVS-1 at MCC-5.
RO            RCS pressure> 1350  1350 psig. [1250 psig] (YES)
BOP            At least 300 GPM AFW flow available. (NO)
BOP            Level in at least one S/G greater than 8% [18%] (NO)
Appendix D  D                                                              NUREG-1 021, Rev. 9, Supp. 1 1


Operator Action Form ES-D-2 Scenario # 2 Event # 8,9and10 Page 19 of 28 ......;.;.;.---...,1 FW Break on S/G "B" inside CV with a loss of ALL feedwater.
Appendix D  D                                    Operator Action Operator      Action                                                                  Form ES-D-2 Form            ES-D-2 Op Test Op Test No.:
CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time II Position II Applicant's Actions or Behavior RO Verify SI valves are properly aligned. (YES) RO At least 1 CCW pump is running. (YES) BOP All SW and SW Booster pumps running. (NO) BOP Attempt to start all SW and SW booster pumps. (NO, SW Booster Pump "A" is unavailable)
No.:
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) CONTINVOUS ACTION*STEP:
BOP Restart battery chargers within 30 minutes of power.loss using OP-601. .. CONTINUOUS ACTION STEP: RO CVPressure has remained b.elow (NO) RO Verify CV Spray initiated. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: ......;....-
Event
Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 2 Event # 8,9 and 10 Page 20 of 28 FW Break on S/G "B" inside CV with a loss of ALL feedwater. CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time II Position I Applicant's Actions or Behavior RO Verify all CV Spray pumps running with valves properly aligned. (NO, CV Spray Pump "A" did not Auto start) NOTE: The crew may have already taken action to start CV Spray Pump "A" per guidance in OMM-022. RO Verify -12 GPM spray additive tank flow. (Will require adjustment)
Event
RO Verify Phase B isolation valves closed. (NO, takes action to close CVC-381 and FCV-626 from the RTGB.) CRITICAL TASK: Verify CVC-381, Phase B CV Isolation Valve is closed prior to transitioning from PATH-1. RO Stop all RCPs. (May be previously stopped) Verify all MSIVs and MSIV bypass valves closed. (YES) BOP (Operator will ensure that switches for the MSIVs are placed in the CLOSE position)
SRO Locally open breaker for HVS-1 at MCC-5. RO RCS pressure>
1350 psig. [1250 psig] (YES) BOP At least 300 GPM AFW flow available. (NO) BOP Level in at least one S/G greater than 8% [18%] (NO) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: -----Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 2 Event # _8;.:"..;;,,9.,;;;a;.;,;nd;;,..1;.,;;O
1    Scenario ##
__ Page 21 of ,....;2::..;;8
Scenario FW Break FW    Break on 22 on S/G Event ##
___ -11 FW Break on S/G "B" inside CV with a loss of ALL feedwater.
Event B inside S/G "B"    inside CV 8, 9 and 10_ _ Page
CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time II Position II Applicant's Actions or Behavior BOP Align AFW valves. BOP At least 300 GPM AFW flow verified (NO) RO Reset SPDS and Initiate monitoring of Critical Safety Function Status Trees SRO Transition to FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK. BOP Check Total Feed Flow less than 300 GPM due to operator action. (NO) Determine if Secondary Heat Sink is required:
_8;.:"..;;,,9.,;;;a;.;,;nd;;,..1;.,;;O CV with aa loss            loss of      of ALL Page ALL feedwater.
* Check RCS pressure greater than any non-faulted S/G RO pressure. (YES)
21 21 feedwater. CV of ,....;2::..;;8 of CV Spray 28_ _ _-11 Spray Pump     Pump A fails "A"   fails to to start, start, Phase Phase B  B valves valves FCV-626 FCV-626 and                       and CVC-381 CVC-381 fail fail to to CLOSE.
* Check RCS temperature greater than 350 degrees F [310 degrees F] (YES) Continuous Action Step: BOP Check Any TWQ S/G Wide Range Levels less than 10%. [19%1 (NO) IF any TWO S/GWR levels decrease.
CLOSE.
to < 10% [19%], THEN Go To Step 5. BOP Check CST level greater than 10%. (YES) RO Verify All S/G Blowdown and Sample Isolation Valves CLOSED. (YES) BOP Check AFW Lines INTACT. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Op Test No.: Event
Time     II Position   II                                     ADDlicants Actions or Behavior Applicant's                                   Behavior BOP         Align AFW valves.
BOP         At least 300 GPM AFW flow verified (NO)
Reset SPDS and Initiate monitoring of Critical Safety Function Status RO Trees Transition to FRP-H.1, RESPONSE TO LOSS OF SECONDARY SRO HEAT SINK.
Check Total Feed Flow less than 300 GPM due to operator action.
BOP (NO)
Determine if Secondary Heat Sink is required:
                                      *. Check RCS pressure greater than any non-faulted S/G RO                       pressure. (YES)
                                      **     Check RCS temperature greater than 350 degrees F [310 degrees F] (YES) r%....4.              A4.
Continuous             Action     Step:
                              ..&#xf8;JI I LII IUIJU IiLLIIJI I LejJ.
Check Check Any TWO      TWQ S/G Wide Ranae      Range Levels less than 10%.                         10%. Ii u[19%1 9%1    (NO
                                                                                                                                                -a(NO) bL)I-BOP                          A                                                                                                        ,
IF IF any TWO S/GWR levels decreaseto          decrease. to <                        < 10% [19%1.
[19%], THENGo THEN Go To step Step 5.
BOP BOP        Check CST level greater than 10%.                      10%. (YES)
RO         Verify All S/G Blowdown and Sample Isolation Valves CLOSED.                                          CLOSED. (YES)
BOP BOP         Check Check AFW Lines INTACT.        INTACT. (YES)
Appendix Appendix D D                                                                                  NUREG-1 NUREG-1 021,        021, Rev.
Rev. 9, 9, Supp.
Supp. 11
 
Appendix 0D                                    Operator Action Operator      Action                                          Form ES-D-2 Form        ES-D-2 Op Test Op Test No.:
No.:       1    Scenario ##
Scenario            22      Event ##
Event          8, 9 and 8,9  and 1010      Page Page    22 22              28_ _ _...,1 of .....;2;.;8 of
                  ~-
Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 2 Event # 8,9 and 10 Page 22 of .....;2;.;8
Event
___ ...,1 FW Break on S/G "B" inside CV with a loss of ALL feedwater. CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time II Position Applicant's Actions or Behavior BOP Try to Establish Motor Driven AFW Flow To At Least One S/G:
 
* Check AFW Pump Breakers TRIPPED. (NO) BOP Verify AFW HDR DISCH valves (V2-16A/B/C)
== Description:==
OPEN. (YES) BOP Check AFW flow to SIGs > 300 GPM. (NO) Attempt to Start SDAFW Pump: BOP
FW Break FW   Break on      SIG "B" on S/G   B inside inside CV CV with with aa loss loss of of ALL ALL feedwater.
* Verify STEAM DRIVEN AFW PUMP STM SHUTOFF VALVES OPEN. (V1-8A, V1-8B, V1-8C) (NO) SRO IF the steam supply valves cannot be opened, THEN Go To Step 11. Locally Investigate AND Attempt To Restore AFW Flow: BOP
feedwater. CV    Spray Pump CV Spray         Pump A fails "A" fails toto start, start, Phase Phase B  B valves valves FCV-626 FCV-626 and  and CVC-381 CVC-381 fail fail to to CLOSE.
* Verify AFW Pump suction supply is available. (YES)
CLOSE.
* Position MDAFW Pump LOCAUREMOTE Switch to LOCAL. Attempt to reclose any tripped breakers:
Time     III Position   ~                                  ADelicants Actions or Behavior Applicant's Try to Establish Motor Driven AFW Flow To At Least One S/G:
* Depress the MDAFW Pump local STOP pushbutton.
BOP
BOP
* Depress the MDAFW Pump local START pushbutton.
                                  **      Check AFW Pump Breakers TRIPPED. (NO)
* Check MDAFW Pump started. (YES) BOP Continuous*
BOP        Verify AFW HDR DISCH valves (V2-16A/B/C)      (V2-1 6AJBIC) OPEN. (YES)
Action Step: Check AFW Flow To SIGs greater than 300 GPM. (YES) RO Reset SPDS and Return to Procedure and Step In Effect. (PATH-1, grid location B-11) Appendix 0 NUREG-1021 , Rev. 9, Supp. 1 Appendix D Op Test No.: Event
BOP        Check AFW flow to SIGs        S/Gs>> 300 GPM. (NO)
Attempt to Start SDAFW Pump:
BOP
                                  **      Verify STEAM DRIVEN AFW PUMP STM SHUTOFF VALVES OPEN. (V1-8A, (Vi-8A, V1-8B, Vi-8B, V1-8C) (NO)
SRO        IF the steam supply valves cannot be opened, THEN Go To Step 11.                              1 1.
Locally Investigate AND Attempt To Restore AFW Flow:
BOP              **    Verify AFW Pump suction supply is available. (YES)
                                    **    Position MDAFW Pump LOCAUREMOTE  LOCAL/REMOTE Switch to LOCAL.
Attempt to reclose any tripped breakers:
                                      **    Depress the MDAFW Pump local STOP pushbutton.
BOP
                                      **    Depress the MDAFW Pump local START pushbutton.
                                      **   Check MDAFW Pump started. (YES)
Continuous Continuous* Action  Action Step:
Step:
BOP BOP Check Check AFW   AFW FlowFlow To S/GsSIGs greater than  than 300 GPM.
GPM. (YES)
(YES)
Reset SPDS and Return to Procedure and Step In                     In Effect.
Effect. (PATH-i, (PATH-1, RO grid grid location location B-i    1)
B-11)
Appendix Appendix D  0                                                                 NUREG-iO2i, NUREG-1021 , 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          22      Event ##
Event              8, 9 and 10_ _ Page
                                                                .....;8;;;.:.,..;;.9.;;;a;.;.;nd;;...1;.,;;O      Page    23 23    of      28_ _ _...,1 of ....;2:;;8
                  ~-
Event
 
== Description:==
 
Event


== Description:==
== Description:==
FW Break FW    Break onon S/G S/G "B" B inside inside CV CV with with aa loss              loss of        of ALL ALL feedwater.
feedwater. CVCV Spray Spray Pump  Pump A fails "A"  fails to to start, start, Phase Phase B B valves valves FCV-626 FCV-626 and                          and CVC-381 CVC-381 fail fail to to CLOSE.
CLOSE.
Time      i  Position  ~                                Applicants Actions or Behavior Applicant's BOP        Control AFW flow to maintain S/G levels between 8% [18%] and 50%
RCP Thermal Barrier Cooling Water High or Low Flow alarms RO illuminated. (YES)
RO        At least One Charging Pump Running. (YES)
BOP        Place Steam Dump Mode switch to Steam Pressure.
RO        RCS Temperature stable at or trending to 547 degrees F. (NO)
RO        RCS temperature greater than 547 degrees F. (NO)
BOP        Attempt to limit cooldown.
If RCS cooldown continues and is not due to SI flow, Then close BOP MSIVs and MSIV Bypasses.
RO        PZR PORVs closed. (YES)
P0 RO        PZR Spray and Aux Spray valves closed. (YES)
RO        At least One RCP running. (NO)
Any SIGS/G with uncontrolled uncontrolled depressurization or completely BOP depressurized (YES) (YES)
Reset Reset SPDS and Initiate  Initiate monitoring monitoring of Critical Safety Function                          Function Status RO Trees.
Appendix Appendix D  D                                                                                NUREG-1 NUREG-1 021,        021, Rev.
Rev. 9, 9, Supp.
Supp. 11


Operator Action Form ES-D-2 Scenario # 2 Event # .....;8;;;.:.,..;;.9.;;;a;.;.;nd;;...1;.,;;O
Appendix D Appendix    D                                  Operator Action Operator     Action                                           Form Form ES-D-2 ES-D-2 Op Test Op Test No.:
__ Page 23 of ....;2:;;8
No.:        1      Scenario ##
___ ...,1 FW Break on S/G "B" inside CV with a loss of ALL feedwater.
Scenario              22      Event ##
CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time i Position Applicant's Actions or Behavior BOP Control AFW flow to maintain S/G levels between 8% [18%] and 50% RO RCP Thermal Barrier Cooling Water High or Low Flow alarms illuminated. (YES) RO At least One Charging Pump Running. (YES) BOP Place Steam Dump Mode switch to Steam Pressure.
Event          8, 9 and 8,9  and 10 10        Page Page       24 24    of of   28 28
RO RCS Temperature stable at or trending to 547 degrees F. (NO) RO RCS temperature greater than 547 degrees F. (NO) BOP Attempt to limit cooldown.
                  ~-                                                ~~------                                  --------~I Event
BOP If RCS cooldown continues and is not due to SI flow, Then close MSIVs and MSIV Bypasses.
RO PZR PORVs closed. (YES) RO PZR Spray and Aux Spray valves closed. (YES) RO At least One RCP running. (NO) BOP Any S/G with uncontrolled depressurization or completely depressurized (YES) RO Reset SPDS and Initiate monitoring of Critical Safety Function Status Trees. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 2 Event # 8,9 and 10 Page 24 of 28 FW Break on S/G "B" inside CV with a loss of ALL feedwater.
Event
CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time II Position II Applicant's Actions or Behavior SRO Transition to EPP-11, FAULTED SIG ISOLATION.
BOP Maintain at least One S/G available for RCS Cooldown.
BOP Identify intact S/Gs:
* ANY S/G Pressure Stable or Increasing (YES,"A" and "C") Identify faulted S/Gs: BOP
* Any S/G Pressure decreasing In An Uncontrolled Manner OR Any S/G Completely Depressurized. (YES, "B") BOP Isolate faulted S/G using Supplement G. (See pg. 26-27 for steps) BOP Maintain a faulted S/G in the isolated condition during subsequent recovery actions unless needed for cooldown.
BOP Check CST Level greater than 10%. (YES) BOP Check available Secondary Radiation Monitors normal. (YES) BOP Check any S/G with an uncontrolled level increase. (NO) SRO Go To PATH-1, Entry Point C. SRO Reset SPDS and initiate monitoring of CSFSTs. SRO Open Foldout B. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event


== Description:==
== Description:==
FW Break FW      Break on    SIG "B" on S/G        inside CV B inside  CV with with aa loss loss of of ALL ALL feedwater.
feedwater. CV  CV Spray Spray Pump Pump A fails "A"    fails to to start, start, Phase Phase B B valves valves FCV-626 FCV-626 and and CVC-381 CVC-381 fail fail to to CLOSE.
CLOSE.
Time Time      II  Position Position  II                                  Applicants Actions Applicant's  Actions or or Behavior Behavior SRO        Transition to EPP-11,EPP-11, FAULTED FAULTED SIG ISOLATION.
ISOLATION.
BOP BOP          Maintain at least Maintain          least One S/G SIG available for RCS Cooldown.
Identify intact S/Gs:SIGs:
BOP
                                      *. ANY S/G SIG Pressure Stable or Increasing (YES,"A"    (YES,A and "C") C)
Identify faulted S/Gs:SIGs:
BOP              **    Any S/G Pressure decreasing In An Uncontrolled Manner OR SIG Completely Depressurized. (YES, "B")
Any S/G                                                  B)
BOP          Isolate faulted S/G using Supplement G. (See pg. 26-27 for steps)
Maintain a faulted S/G    SIG in the isolated condition during subsequent BOP recovery actions unless needed for cooldown.
BOP        Check CST Level greater than 10%. (YES)
BOP        Check available Secondary Radiation Monitors normal. (YES)
BOP        Check any SIG      S/G with an uncontrolled level increase. (NO)
SRO          Go To PATH-i, PATH-1, Entry Point C.
SRO SRO          Reset Reset SPDS SPDS and and initiate initiate monitoring monitoring of  of CSFSTs.
CSFSTs.
SRO SRO        Open Open Foldout Foldout B. B.
Appendix Appendix D  D                                                                NUREG-i NUREG-1 021,021, Rev.
Rev. 9, 9, Supp.
Supp. 11


Operator Action Form ES-D-2 Scenario # 2 Event # _8;...:. * ...;.9...;,;a;.;.;nd;;.,.1;..;.O
Appendix D  D                                  Operator Action Operator                                                                                Form Form ES-D-2ES-D-2 Op Test Op Test No.:
__ Page 25 of
No.:        1    Scenario ##
___ -I1 FW Break on S/G "B" inside CV with a loss of ALL feedwater.
Scenario              22      Event ##
CV Spray Pump "A" fails to start. Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time II Position II Applicant's Actions or Behavior
Event            8,*...;.9...;,;a;.;.;nd;;.,.1;..;.O
* SI Termination criteria; 0 IF ALL conditions below occur. THEN Go To EPP-7. SI TERMINATION:
_8;...:. 9 and 10_ _ Page                    Page     25 25     of .....;2~8 of      28_ _ _-I1
* RCS subcooling greater than 35&deg;F [55 OF]
                  ~-
* Heat Sink established as follows: 0 Total feed flow to intact S/Gs > 300 GPM OR SRO 0.2x10 6 PPH. OR 0 Level in at least one intact S/G > greater than 8% [18%]
Event
* RCS pressure >1650 PSIG [1750 PSIG] AND STABLE OR INCREASING
* PZR level> 10% [32%] SRO Determines that SI termination criteria are met and transitions to EPP-7, SI TERMINATION.
The Chief Examiner may terminate the scenario anytime after flow is established to at least one SIG and the faulted SIG has been isolated lAW Supplement G. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 2 Event # 8, 9 and 10 Page 26 of .....;2;;;.;8
Event
___ FW 8reak on S/G "8" inside CV with a loss of ALL feedwater.
CV Spray Pump "A" fails to start, Phase 8 valves FCV-626 and CVC-381 fail to CLOSE. Time I Position I Applicant's Actions or Behavior Pages 26-27 are steps from Supplement G, STEAM GENERATOR ISOLATION to isolate SIG "8" as a faulted Steam Generator.
BOP Go to the appropriate step from following table: S/G B to be isolated, Go To Step 18. BOP Check S/G "B" faulted. (YES) BOP Verify V1-3B, MSIV CLOSED. (YES) BOP Verify MS-353B, MSIV V1-3B BYP CLOSED. (YES) BOP Verify FRV B CLOSED. (YES) BOP Verify FRV B BYP CLOSED. (YES) BOP Verify V2-6B, FW HDR SECTION Valve CLOSED. (YES) BOP Verify V2-14B, SDAFW PUMP DISCH Valve CLOSED. (YES) BOP Verify V2-16B, AFW HDR DISCH Valve CLOSED. (YES) BOP Verify STEAM LINE PORV CLOSED. (YES) BOP Verify V1-8B, SDAFW STEAM SHUTOFF Valve CLOSED. (YES) BOP Verify S/G B Blowdown and Blowdown Sample Valve Status Light Indication CLOSED. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event


== Description:==
== Description:==
AN Break FW      Break on    SIG "B" on S/G    B inside inside CVCV with with aa loss        loss of          of ALL ALL feedwater.
feedwater. CV  CV Spray Spray Pump Pump A fails "A"    fails to to start.
start, Phase Phase B B valves valves FCV-626 FCV-626 and                      and CVC-381 CVC-381 fail fail to to CLOSE.
CLOSE.
Time      II1 Position  III                                  Applicants Actions or Behavior Applicant's                                      Behavior
                                    *. SI Termination criteria; 0o    IF ALL conditions below occur.                            occur, THEN Go To EPP-7.      EPP-7, SI TERMINATION:
                                                      *. RCS subcooling greater than 35&deg;F [55 OF]                                      &deg;F]
                                                      *. Heat Sink established as follows:
0o    Total feed flow to intact S/Gs                        S/Gs>    > 300 GPM OR SRO                                                66 PPH.
0.2x10 0.2x10 OR o
0    Level              in      at least one intact S/G >            > greater than 8% [18%]
                                                      *. RCS    pressure                  >1650 PSIG [1750 PSIG] AND STABLE OR INCREASING
                                                      *. PZR level> 10% [32%]
SRO          Determines that SI termination criteria are met and transitions to EPP-                                            EPP 7, SI TERMINATION.
The Chief Examiner may terminate the scenario anytime after flow is established to at least one SIG and the faulted SIG has been isolated lAW Supplement G.
Appendix Appendix D  D                                                                                NUREG-1 NUREG-1 021,          021, Rev.
Rev. 9, 9, Supp.
Supp. 11


Operator Action Form ES-D-2 Scenario # 2 Event # 8,9and10 Page 27 of 28 -----II FW Break on S/G "B" inside CV with a loss of ALL feedwater.
Appendix D  D                                Operator Action Operator                                                      Form ES-D-2 Form           ES-D-2 Op Test No.:
CV Spray Pump "A" fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE. Time i Position i Applicant's Actions or Behavior Dispatch an operator to the Pipe Jungle to close MS-29, S/G B BOP BYPASS DRN and WARM-UP LINE TO AFW PUMP (located above / right of V1-SB) BOP Check S/G B MSIV Above and Below Seat Drain Valves CLOSED. (YES) Dispatch an operator to E-1/E-2 Room to perform the following:
Op Test  No.:        1    Scenario ##
* At MCC-9, verify V2-14B closed and open breaker V2-14B, BOP SDAFW PUMP TO S/G B (CMPT-1C)
Scenario          22      Event ##
* At MCC-6, verify V1-SB closed and open breaker V1-SB, SDAFW PUMP STEAM ISOLATION (CMPT-16M)
Event        8, 99 and 8,   and 10 10      Page Page     26 26    of .....;2;;;.;8 of       28_ _ _~1
                  ~-
Event
 
== Description:==
 
Event
 
== Description:==
FW 8reak FW   Break onon S/G  B inside S/G "8"   inside CV CV with with aa loss loss of of ALL ALL feedwater.
feedwater. CVCV Spray Spray Pump   Pump A fails "A" fails to to start, start, Phase Phase 8B valves valves FCV-626 FCV-626 and  and CVC-381 CVC-381 fail fail to to CLOSE.
CLOSE.
Time      I  Position Position  I                                Applicants Actions or Behavior Applicant's Pages 26-27 are steps from Supplement G, STEAM GENERATOR ISOLATION to isolate B as a faulted Steam Generator.
SIG "8" Go to the appropriate step from following table: S/G B to be isolated, BOP Go To Step 18.
BOP        Check S/G "B"    B faulted. (YES)
BOP                  Vi -3B, MSIV CLOSED. (YES)
Verify V1-3B, BOP        Verify MS-353B, MSIV V1-3B      Vi -3B BYP CLOSED. (YES)
BOP        Verify FRV B CLOSED. (YES)
BOP        Verify FRV B BYP CLOSED. (YES)
BOP        Verify V2-6B, FW HDR SECTION Valve CLOSED. (YES)
BOP        Verify V2-14B, SDAFW PUMP DISCH Valve CLOSED. (YES)
BOP        Verify V2-i    6B, AFW HDR DISCH Valve CLOSED. (YES)
V2-16B, BOP        Verify STEAM LINE PORV CLOSED. (YES)
BOP BOP        Verify Vi    -8B, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)
V1-8B,                                                                  (YES)
Verify S/G BB Blowdown Blowdown and Blowdown Blowdown Sample Valve Status Light BOP BOP Indication CLOSED. (YES)
Appendix Appendix D  D                                                              NUREG-i NUREG-1 021,021, Rev.
Rev. 9, 9, Supp.
Supp. 11
 
AppendixDD Appendix                                          OperatorAction Operator      Action                                              Form FormES-D-2 ES-D-2 OpTest Op  TestNo.:
No.:        1      Scenario##
Scenario              22      Event##
Event        8,9and10 8, 9 and 10          Page Page      27 27 ofof    28
                --                                                                                                - 28
                                                                                                                      ----II EventDescription:
Event
 
== Description:==
FW Break FW    Breakon  on S/G S/G "B" B inside insideCV    withaaloss CVwith      lossofofALL ALLfeedwater.
feedwater. CV  CVSpray SprayPump Pump Afails "A"  failstotostart, start, Phase PhaseBBvalves valvesFCV-626 FCV-626and  and CVC-381 CVC-381 failfailtotoCLOSE.
CLOSE.
Time Time     i     Position Position     i                                   ApplicantsActions Applicant's   ActionsororBehavior Behavior Dispatch an Dispatch        an operator operator toto the the Pipe Pipe Jungle Jungle to to close close MS-29, MS-29, S/G  S/G BB BOP BOP           BYPASS DRN BYPASS         DRN and and WARM-UP WARM-UP LINE   LINE TOTO AFW  AFW PUMP (located above PUMP      (located    above /I right of right     of V1-SB)
Vi -8B)
BOP         Check S/G Check        SIG BB MSIV MSIV Above Above andand Below Below SeatSeat Drain Drain Valves Valves CLOSED.
CLOSED.
BOP          (YES)
(YES)
Dispatch an Dispatch       an operator operator toto E-1/E-2 E-1IE-2 RoomRoom to  to perform perform the the following:
following:
                                      *. At MCC-9, MCC-9, verify verify V2-14B V2-14B closed closed and and open open breaker breaker V2-14B, V2-14B, BOP BOP                       SDAFW PUMP SDAFW       PUMP TO   TO S/G S/G B  B (CMPT-1C)
(CMPT-1C)
                                      *. At MCC-6, verify V1-SB Vi -8B closed closed and and open open breaker breaker V1-SB, Vi -SB, SDAFW PUMP STEAM ISOLATION (CMPT-16M)              (CMPT-16M)
Dispatch operator to the Aux. Bldg. to perform the following:
Dispatch operator to the Aux. Bldg. to perform the following:
BOP
BOP                       At MCC-10, MCC-i 0, verify V2-i
* At MCC-10, verify V2-16B closed and open breaker V2-16B, MDAFW PUMP HEADER DISCHARGE TO S/G B (CMPT-4F)
                                      *.                              V2-16B 6B closed and open breaker V2-i          V2-16B, 6B, MDAFW PUMP HEADER DISCHARGE        DISCHARGE TO S/G B                 (CMPT-4F))
SRO Go To Step 49. BOP Check All Faulted and Ruptured S/Gs ISOLATED. (YES) BOP WHEN the faulted S/Gs dry out, THEN dump steam from intact S/G to control RCS repressurization.
B(CMPT-4F SRO         Go To Step 49.
BOP Check Any S/G RUPTURED. (NO) SRO Return to procedure and step in effect. Appendix D NUREG-1 021, Rev. 9, Supp. 1 HLC-08 NRC SCENARIO 2 TURNOVER SHEET POWER LEVEL: 100%, 9000 MWO/MTU BORON CONCENTRATION:
BOP BOP         Check Check All   All Faulted Faulted andand Ruptured Ruptured S/Gs  S/Gs ISOLATED.
766 ppm EQUIPMENT UNDER CLEARANCE:
ISOLATED. (YES)  (YES)
* SW Booster Pump "A" is out of service and under clearance for Motor Coupling Alignment.
WHEN WHEN the     the faulted faulted SIGs S/Gs drydry out, out, THEN THEN dump  dump steam steam fromfrom intact intact SIG S/G to to BOP BOP        control control RCS  RCS repressurizat      ion.
o LCO 3.7.7-A has been entered and is in hour 18 of a 72 Action Statement.
repressurization.
o Expected return is within -18 hours. EQUIPMENT STATUS:
BOP BOP        Check Check Any   Any SIG S/G RUPTURED RUPTURED.. (NO)  (NO)
SRO SRO          Return Return to    to procedure procedure and        step inin effect.
and step       effect.
Appendix AppendixDD                                                                      NUREG-1 021, NUREG-iO2              Rev. 9,9, Supp.
i, Rev.        Supp. i 1
 
HLC-08 NRC HLC-08   NRC SCENARIO 2 TURNOVER SHEET POWER LEVEL: 100%, 9000 MWO/MTUMWD/MTU BORON CONCENTRATION: 766 ppm EQUIPMENT UNDER CLEARANCE:
* SW Booster Pump "A"A is out of service and under clearance for Motor Coupling Alignment.
o   LCO 3.7.7-A has been entered and is in hour 18 of a 72 Action Statement.
o                             1 8 hours.
Expected return is within -18 EQUIPMENT STATUS:
* Main Turbine bearing #3 has a slightly elevated vibration and is being monitored by Systems Engineering.
* Main Turbine bearing #3 has a slightly elevated vibration and is being monitored by Systems Engineering.
INSTRUCTIONS FOR THE WATCH:
INSTRUCTIONS FOR THE WATCH:
* Maintain power at 100% RTP. Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 Facility:
* Maintain power at 100% RTP.
HB ROBINSON Scenario No.: 3 Op Test No.: 2008 NRC Examiners:
Appendix D0                                                NUREG-1 021, Rev. 9, 9, Supp. 11
 
I Appendix Appendix DD                                        Scenario Outline Scenario     Outline                                 Form Form ES-D-1 ES-D-1 Facility:
Facility:            HB ROBINSON HB ROBINSON                      Scenario No.:
Scenario    No.:      33    Op  Test No.:
Op Test     No.:     2008 2008 NRC NRC Examiners:
Examiners:                                                        Operators:
Operators:
Operators:
Initial Conditions:
Initial Conditions:
* 7% BOl, 150 MWD/MTU, 1645 ppm Boron.
Initial    Conditions:    **   7% BOl, 7%  BOL, 150150 MWD/MTU, MWD/MTU, 1645  1645 ppm ppm Boron.
* SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.
Boron.
0 lCO 3.7.7 -A has been entered and is in hour 18 of a 72 hour action statement.
                            *.      Booster Pump SW Booster     Pump "A" A is is Out-Of-Service for Motor Motor Coupling Alignment.
0 Expected return is within -18 hours.
0o    LCO 3.7.7 lCO   3.7.7-A        been entered
* Main Turbine Vibration for #2, 3 and 4 bearings is elevated.
                                                            -A has been   entered and and is is in hour 18 18 of of aa 72 hour action action statement.
Turnover:
statement.
* Continue with GP-005 to synchronize the Generator to the grid. Critical Task:
0o  Expected return is within -1818 hours.
* Manually trip the Reactor prior to transitioning out of AOP-001.
                            **  Main Turbine Vibration for #2, 3 and 4 bearings is elevated.
* Recognize that a SGTR has occurred and isolate the applicable S/G before transitioning to EPP-17. Event Malt. No. Event Type* Event No. Description 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" breaker trips on overload.
Turnover:                 **   Continue with GP-005 to synchronize the Generator to the grid.
4 (C) RO low pressure on SI Accumulator "B". (TS) SRO 5 (M) All Multiple dropped rods requiring a Reactor Trip. 6 (M) All S/G Tube Rupture on S/G "C". (TS) SRO 7 (C) BOP S/G "c" Safety fails 15% open. 8 (C) RO Safety Injection Pump "C" fails to start. 9 (C) BOP S/G Blowdown Sample valves fail to close. I * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 3  
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.
Malt.                Type*
Event Type*                                       Event No.                                                                     Description 11                    (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".
low                                    B.
(TS) SRO 5                     (M) ALL All             Multiple dropped rods requiring a Reactor Trip.
66                      (M) ALL All             S/G Tube Rupture on S/G C.  "C".
(TS) SRO 7                       (C) BOP                   "c" Safety fails 15% open.
S/G C 88                    (C) RO               Safety Injection Injection Pump C "C" fails to start.
99                      (C) BOP             S/G Blowdown Sample valves fail to close.
k I         * (N)ormal, (N)ormal,   (R)eactivity,     (I)nstrument,      (C)omponent, (C)omponent,       (M)ajor Appendix Appendix D     D                                                          NUREG-1 021, NUREG-1       021, Rev.
Rev. 9, 9, Supp.
Supp. 11
 
I Appendix D                               Scenario Outline                               Form ES-D-1   I HLC-08 NRC SCENARIO 3  


==SUMMARY==
==SUMMARY==
DESCRIPTION The crew will assume the watch with the plant at 7% Reactor Power, with the Turbine rolling at 1800 RPM, but not synchronized to the grid. A Dedicated Operator (Surrogate) required by 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.
DESCRIPTION The crew will assume the watch with the plant at 7% Reactor Power, with the Turbine rolling at 1800 RPM, but not synchronized to the grid. A Dedicated Operator (Surrogate) required by SIG level control. The previous shift identified increased procedure, will be stationed for S/G 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.
Power was stabilized for shift turnover and to obtain vibration data on the Turbine. Service Water Booster Pump "A" is under clearance for Motor Coupling Alignment.
Shift instructions are to continue with GP-005, POWER OPERATION, to synchronize the Generator to the grid.
Shift instructions are to continue with GP-005, POWER OPERATION, to synchronize the Generator to the grid. The crew will use GP-005 to place the Generator Voltage Regulator in service in preparation to 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.
The crew will use GP-005 to place the Generator Voltage Regulator in service in preparation to 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" breaker will trip on overload.
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.
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 Accumulator "B".
When Tech Specs are addressed, the Chief Examiner can cue a Low Pressure on SI Accumulator "B". The RO will reference APP-002-D4 and take action to repressurize the Accumulator lAW OP-202. The SRO will enter LCO 3.5.1, Condition C for the Low Pressure condition.
B. The RO will reference APP-002-D4 and take action to repressurize the Accumulator lAW OP-202. The SRO will enter LCO 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 respond by directing a Reactor trip and enter PATH-1. On the Reactor trip, S/G "C" will develop a 500 gpm tube rupture which will require a Safety Injection.
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 a 500 gpm tube rupture which will require a Safety Injection. On the Safety Injection, S/G "C"     C C will fail to start, requiring the RO Safety Valve will fail 15% open and will not close, SI Pump "C" C Blowdown Sample valves will not close as expected.
On the Safety Injection, S/G "C" Safety Valve will fail 15% open and will not close, SI Pump "C" will fail to start, requiring the RO to start it manually, and S/G "C" Blowdown Sample valves will not close as expected.
to start it manually, and S/G "C" The Chief Examiner may terminate the scenario at any time after all possible S/G isolation EPP-i 7.
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. Appendix D NUREG-1 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 3 SIMULATOR SETUP IC/SETUP:
actions have been taken and the crew has transitioned to EPP-17.
Appendix D                                                 NUREG-i 021, Rev. 9, Supp. 11 NUREG-1
 
II Appendix DD                                Scenario Outline                           Form ES-D-1 HLC-08 NRC SCENARIO 3 SIMULATOR SETUP IC/SETUP:
* IC-603, SCN 006_Sim_3.
* IC-603, SCN 006_Sim_3.
* SW Booster Pump "A" is OFF, breaker OPEN and switch is RED CAPPED.
* 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.
* Main Turbine Bearing #2 is OFFSET by 1.5,    1.5, #3 by 2.3 and #4 by 1.7.
* Status board is correctly marked up for IC-3.
* Status board is correctly marked up for IC-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:
lC-3.
* Event 8: SI Pump "c" fails to start.
* Provide candidates with a marked up (up to Step 8.4) copy of GP-005 to synchronize the Generator to the Grid.
* Event 9: S/G Blowdown Sample valves fail to close. EVENTSITRIGGERS INITIATED DURING THE SCENARIO:
PRE-LOADED EVENTS:
* Event 2: Inadvertent Turbine Trip with Power < P-7.
The following events should occur on the reactor trip:
* Event 3: SW Pump "A" Breaker trips on overload.
* Event 8: SI Pump "c" C fails to start.
* Event 4: Low pressure on SI Accumulator "B".
* 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 5: Multiple dropped rods requiring a Reactor Trip.
* Event 6: S/G Tube Rupture on S/G "C".
* Event 6: S/G Tube Rupture on S/G "C". C.
* Event 7: S/G "c" Safety Valve fails 15% open. EXPECTED PROCEDURE FLOW PATH OR COPIES NEEDED: GP-005, Section 8.4; AOP-007; OP-202, Section 8.2.3; AOP-001; PATH-1; Foldout A; Supplement G; EPP-11; PATH-2; Foldout C. Appendix D NUREG-1021 , Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ......;....-
* Event 7: S/G "c" C Safety Valve fails 15% open.
Scenario # 3 Event # --.;... ____ Page 4 of .....;2;;.;6
EXPECTED PROCEDURE FLOW       FLOWPATHPATH OR COPIES NEEDED:
___ ..,1 Event
GP-005, Section 8.4; AOP-007; OP-202, Section 8.2.3; AOP-001; AOP-OO1; PATH-1; PATH-i; Foldout A; EPP-1 1; Supplement G; EPP-11;     PATH-2;     Foldout C.
AppendixD Appendix   D                                                     NUREG-1021,, Rev. 9, Supp. 11 NUREG-1021
 
Appendix D                                     Operator Action                                               Form ES-D-2 Op Test No.:
Op Test No.:        1 Scenario ##
Scenario           33  Event ##
Event             1 _ _ _ _ Page
                                                                    --.;...               Page   44      of of .....;2;;.;6 26_ _ _..,1 Event
 
== Description:==
 
Event


== Description:==
== Description:==
Place      Generator VR Place the Generator  VA in in service service and and synchronize synchronize the Generator  to the Generator to  the grid.
grid.
Time      I  Position      I                              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 breaker BOP                    has not tripped, THEN reduce voltage as soon as 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 SLOWL              SLOWLY    Y in BOP            the FAST direction. (Using Reference Setter, sets turbine speed to
                                  .-1802
                                  -1802 RPM and depresses GO)
Verify TAVG TAVG is at the high end of the 547&deg;F to 551&deg;F band and Reactor BOP Power is .:s.< 8%.
Appendix D  D                                                                  NUREG-1 021, Rev. 9, Supp. 11


Place the Generator VR in service and synchronize the Generator to the grid. Time I Position I Applicant's Actions or Behavior NOTE: The crew will brief Generator synchronization prior to entering the simulator.
Appendix D                               Operator Action                                         Form ES-D-2 Op Test No.:       1
They will start with Step 8.4 of GP-OOS. SRO Inform the Load Dispatcher that the unit will be placed on the grid. BOP WHEN the turbine is at 1800 rpm, THEN close the Exciter Field Breaker. Place the Voltage Regulator in service:
                -:..._   Scenario #     3     Event #     _ 1 _ _ _ _ Page             5   of   26 _ _----41
* Slowly raise Generator volts to 22KV using the Manual Field Current Adjuster.
_2;;;;,;6~
* I F Generator voltage exceeds 22KV and the Exciter breaker BOP has not tripped, THEN reduce voltage as soon as possible.
Event
* Place the VOLTAGE REGULATOR in the TEST position.
* Adjust Regulator Balance to zero using the VOLTAGE ADJUSTER.
* Place the VOLTAGE REGULATOR in AUTO. BOP Place the MAIN GENERATOR synchroscope key switch in the GEN NORTH position.
BOP Adjust the % DIFF VOLTS to zero using the VOLTAGE ADJUSTER.
Adjust Turbine speed so that the synchroscope is rotating SLOWL Y in BOP the FAST direction. (Using Reference Setter, sets turbine speed to -1802 RPM and depresses GO) BOP Verify T AVG is at the high end of the 547&deg;F to 551&deg;F band and Reactor Power is .:s. 8%. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -:..._ Scenario # 3 Event # _____ Page 5 of
__ ----41 Event


== Description:==
== Description:==
Place the Generator VR in service and synchronize the Generator to the grid.
Time      I  Position  I                          Aijplicants 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 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:
0o  Place Turbine Control in TURB MANUAL and use GV Down to shed load to minimum.
0o  Verify Reactor Power is <      < 10%.
0o  Open the North OCB BKR 52/9.
Appendix D                                                            NUREG-1 021, Rev. 9, Supp. 1        1
Appendix D                                  Operator Action                                          ESD-2 Form ES-D-2 Op Test No.:        1 Scenario #      3      Event #      2                Page    6 of  26
                                                              ~--------                        ~~----~I Event
== Description:==
                                            < po?~
Inadvertent Turbine Trip with power < P-7.
Time      ~  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    A/B 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:
BOP
                                    *. Both Turbine Stop Valves closed (YES)
OR
                                    *. 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


Place the Generator VR in service and synchronize the Generator to the grid. Time I Position I Applicant's Actions or Behavior NOTE: The sequence of actions necessary to synchronize the unit to the grid is TIME CRITICAL.
Appendix D                                   Operator Action                                       Form ES-D-2 op Test No.:
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 trip with Power < P-7. Synchronize the Main Generator to the grid:
Op      No.:        1    Scenario #         3     Event #
* WHEN the synchroscope is rotating SLOWLY in the FAST direction and reaches the 5 minutes to 12 o'clock position, THEN close the NORTH OCB BKR 52/9.
Event        2                 Page Page     7  of 26
* 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
                  ~-                                            ~--------                          ~------~I Event
* 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: 0 Place Turbine Control in TURB MANUAL and use GV Down to shed load to minimum. 0 Verify Reactor Power is < 10%. 0 Open the North OCB BKR 52/9. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ....;...-Scenario # 3 Event # 2 Page 6 of 26 Event


== Description:==
== Description:==


Inadvertent Turbine Trip with power <
Event
Time Position I Applicant's Actions or Behavior 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 AUTO START APP-008-B2; EH FLUID SYSTEM HIILO 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) BOP OR
* 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 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # 2 Page 7 of 26 Event


== Description:==
== Description:==
Inadvertent Turbine Trip with power < P-7.
Inadvertent Time      i  Position  III                            Applicants Actions or Behavior Applicant's Continuous Action Step:  SteD:
Verify Bearing Oil LinLift Pump Pump running:
BOP          Check Turbine Speed < 600 RPM. (NO)
WHEN Turbine Speed is <.600            RPM, THEN verify Bearing Oil Lift
                                                              < 600 RPM,THENverify                      Lift 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 TRI  TRIP.
P.
Check TTAVG        &deg;F to 551&deg;F.
AVG 547 of      551 &deg;F.
(NO) IF Steam Dumps are available THEN:
RO/BO P RO/BOP
                                        *. Adjust PC-464B to maintain 547-551 of.        &deg;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 Charging and Letdown to maintain PZR level -22%.
Determine if the Reactor should be shutdown:
SRO Check Reactor Power stable. (YES)
Appendix D  D                                                          NUREG-1 NUREG-1 021,021, Rev. 9, Supp. 11


Inadvertent Turbine Trip with power < P-7. Time i Position II Applicant's Actions or Behavior Continuous Action Step: Verify Bearing Oil Lin Pump running: BOP Check Turbine Speed < 600 RPM. (NO) WHEN Turbine Speed is <.600 RPM,THENverify Bearing Oil Lift Pump is running. Check North OCB BKR 52/9, South OCB BKR 52/8 and Exciter Field BOP Breaker tripped. (NO, Exciter Field Breaker is still CLOSED) IF the Exciter Field Breaker has NOT tripped, THEN momentarily place the control switch in TRI P. Check T AVG 547 of to 551&deg;F. (NO) IF Steam Dumps are available THEN:
Appendix D                                       Operator Action Operator                                                Form ES-D-2 Form Op Test Op Test No.:
* Adjust PC-464B to maintain 547-551 of. RO/BOP
No.:        1 Scenario #
* Verify Steam Dump Control switch is ON.
Scenario              33    Event ##
* Verify Steam Dump Mode switch in Steam Press. (YES) Continue with Step 8. BOP Check 1 Main Condensate Pump AND 1 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.
Event          33                Page Page    88  of of   26 26
RO Control Charging and Letdown to maintain PZR level -22%. Determine if the Reactor should be shutdown:
                                                                    ~--------                            ~~----~I Event
SRO Check Reactor Power stable. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --.;...-Scenario # 3 Event # 3 Page 8 of 26 Event


== Description:==
== Description:==


SW Pump "An trip. Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR:
Event
When directed by the Chief Examiner, insert Event 3, Service Water Pump "A" trips on breaker overload.
 
== Description:==
SW Pump SW    Pump "AnA trip.
Time     II   Position Position   III                                Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 3, Service Water Pump "A"       A trips on breaker overload.
EVENT INDICATIONS:
EVENT INDICATIONS:
APP-OOS-F4; SW PMP AlB/C/D OVLD APP-OOS-F7; SOUTH SW HDR LO PRESS APP-OOS-FS; NORTH SW HDR LO PRESS APP-002-AS/BS/CS/DS; HVH-1/213/4 WTR OUTLET LO FLOW RO/BOP Recognizes that SW Pump "A" has tripped and references applicable APP-008-F4.
APP-008-F4; SW PMP AlB/C/D APP-OOS-F4;              AIBICID OVLD APP-008-F7; SOUTH APP-OOS-F7;     SOUTH SW HDRHDR LO LO PRESS PRESS APP-008-F8; NORTH SW HDR LO APP-OOS-FS;                        LO PRESS APP-002-A8/B8/C8/D8; HVH-1/213/4 APP-002-AS/BS/CS/DS;      HVH-1121314 WTR OUTLET LO FLOW Recognizes that SW Pump "A"           A has tripped and references applicable RO/BOP AP P-008-F4.
APP-008-F4 actions: If an operating SW Pump has tripped, perform the following:
APP-008-F4.
0 Start a standby pump. (Will start SW Pump "B" or "D") BOP Dispatch an operator to check breaker and current limiter fuses 0 for SW Pump A -480V Bus E-1 , CMPT 20B. 0 Throttle CCW Heat Exchanger return valves to maintain header pressure at 40 -50 psig. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # 4 Page 9 of 26 Event
APP-008-F4 actions:
If an operating SW Pump has tripped, perform the following:
0o    Start a standby pump. (Will start SW Pump "B"         B or "D")
D)
BOP 0o    Dispatch an operator to check breaker and current limiter fuses for SW Pump A - 480V Bus E-1 E-1,, CMPT 20B.
0o              COW Heat Exchanger return valves to maintain Throttle CCW header pressure at 40 - 50 psig.
Appendix D D                                                                NUREG-1 021, Rev. 9, Supp. 11
 
Appendix D D                              Operator Action Operator                                                  Form Form ES-D-2 ES-D-2 Op Test No.:
Op Test No.:        1    Scenario ##
Scenario          33    Event ##
Event          44                Page Page     99    of of 26 26
                  ~-                                            ~--------                            ~---~I Event


== Description:==
== Description:==


Low pressure on SI Accumulator "B". Time I Position I Applicant's Actions or Behavior BOOTH OPERATOR:
Event
When directed by the Chief Examiner, insert Event 4, Low pressure on SI Accumulator "B", EVENT INDICATIONS:
APP-002-D4; SI ACCUM B HI/LO PRESS Decreasing Accumulator B pressure RO Recognizes that SI Accumulator "8" pressure is decreasing slowly and references APP-002-D4.
Reviews, briefs and directs Accumulator repressurization using OP-SRO 202, SAFETY INJECTION AND 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 SI-8538, VENT. RO WHEN the desired pressure is obtained, (Normal operating pressure is 630 PSIG) THEN close SI-8538. (APP-002-D4 will clear) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event


== Description:==
== Description:==
Low pressure Low  pressure on on SI SI Accumulator Accumulator "B".
8.
Time      II  Position  IH                            Applicants Actions or Behavior Applicant's            Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 4, Low pressure on SI Accumulator "B",        B.
EVENT INDICATIONS:
HI/LO PRESS APP-002-D4; SI ACCUM B HI/LO Decreasing Accumulator B pressure Recognizes that SI Accumulator "8"      B pressure is decreasing slowly and RD RO references APP-002-D4.
Reviews, briefs and directs Accumulator repressurization using OP-          OP SRO        202, SAFETY INJECTION AND CONTAINMENT VESSEL SPRAY SYSTEM, Section 8.2.3.
RD RO        Verify HIC-936, ACC VENT HDR FLOW CLOSED. (YES)
RD RO        Verify SI-855, ACC NITROGEN ISOLATION OPEN. (YES)
RD RO                SI-853B, VENT.
OPEN SI-8538, WHEN the desired pressure is obtained, (Normal operating pressure is RD RO 630 PSIG) THEN close SI-853B.SI-8538. (APP-002-D4 will clear)
Appendix Appendix D  D                                                          NUREG-1021, NUREG-1021, Rev. Rev. 9, 9, Supp.
Supp. 11


Operator Action Form ES-D-2 Scenario # 3 Event # 5,6 Page 10 of 26 Multiple dropped rods requiring a Reactor Trip. S/G Tube Rupture on S/G "en. Time Position I Applicant's Actions or Behavior BOOTH OPERATOR:
Appendix D  D                              Operator Action                                     Form ES-D-2 Op Test No.:
When directed by the Chief Examiner, insert Event 5, Multiple dropped rods. When the reactor has been tripped, verify that Event 6, SIG "C" Tube Rupture has been entered. EVENT INDICATIONS:
Scenario #         33    Event #       5, 5,66
APP-005-F2; ROD BOTTOM ROD DROP RBLs for Control Bank C, Group 2 are LIT Decreasing SUR Decreasing power. RO Recognizes multiple dropped rods and performs Immediate actions of AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM. RO Check unexpected rod motion in progress. (NO) RO/BOP Make PA Announcement for entry into AOP-001. Determine if multiple rods have dropped:
                                                              ~--------
* Prompt drop present. (YES) RO
Page    10 10 of  26
* More than 1 RBL illuminated. (YES)
                                                                                                ~------~I Event
* More than 1 IRPI indicates on bottom. (YES) RO Check multiple dropped rods present. (YES) RO Check Reactor in MODE 1 or 2. (YES) SRO Directs tripping the reactor and enters PATH-1. IMMEDIATE ACTION STEP: RO Reactor Tripped. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event


== Description:==
== Description:==
Multiple dropped rods requiring a Reactor Trip.
                                                    "en.
S/G Tube Rupture on S/G C.
Time          Position  I[                            Applicant's Actions or Behavior Applicants BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 5, Multiple dropped rods. When the reactor has been tripped, verify that Event 6, SIG "C" C Tube Rupture has been entered.
EVENT INDICATIONS:
APP-005-F2; ROD BOTTOM ROD DROP RBLs for Control Bank C, Group 2 are LIT Decreasing SUR Decreasing power.
Recognizes multiple dropped rods and performs Immediate actions of RO AOP-O01, AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM.
RO          Check unexpected rod motion in progress. (NO)
RO/BOP        Make PA Announcement for entry into AOP-001.
Determine if multiple rods have dropped:
                                  **  Prompt drop present. (YES)
RO
                                  **  More than 1  1 RBL illuminated. (YES)
                                  **  More than 1  1 IRPI indicates on bottom. (YES)
RO        Check multiple dropped rods present. (YES)
RO        Check Reactor in MODE 1      1 or 2. (YES)
SRO        Directs tripping the reactor and enters PATH-1.PATH-i.
IMMEDIATE ACTION STEP:
RO Reactor Tripped. (YES)
Appendix D                                                            NUREG-1 021, Rev. 9, Supp. 11
Appendix D                                  Operator Action                                      Form ES-D-2 Op Test Test No.:
No.:              Scenario #
Op Scenario          33      Event ##
Event        5, 6 5,
                                                                ~~-----
Page Page    11 11 of of  26 26
                                                                                                    ~---~I Event
== Description:==
Event
== Description:==
Multiple dropped Multiple  dropped rods rods requiring requiring a Reactor Reactor Trip.
S/G Tube Rupture Rupture on S/G SIG "C".
C.
Time      I  Position  IH                              Applicants Actions or Behavior Applicant's IMMEDIATE ACTION STEP:
BOP Tripped... (YES)
Turbine Tripped IMMEDIATE ACTION STEP:
BOP E-i AND E-2 energized. (YES)
E-l ACTION STEP:
IMMEDIATE ACTION.STEP:
RO        SI Initiated. (NO)
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 procepureexit exit is warranted:
warranted:
SRO            .*  Check    attack on Check.atlack          RNP site in progress. (NO) onRNPsite
                                    **  Check Check a total loss of SW OR. OR Loss of Lake Robinson Dam integrity in progress. (NO, Go to Step 2)
Continuous Action Step:
Check CheckSI  SI signal initiated. (NO, Go to Step  Step 4)
RO IF SI initiation occurs during this procedure, THEN Go to PATH-i, IfSI                                                                PATH-1, Entry Point A  A.
Appendix D  D                                                            NUREG-102i, NUREG-1021, Rev. 9, Supp. 11
Appendix D                                Operator Action                                        Form ES-D-2 Op Test No.:        1 Scenario #      3      Event #      5, 6 5,6              Page    12  of  26
                                                              ~~------                          ~------~I Event
== Description:==
Multiple dropped rods requiring a Reactor Trip.
S/G Tube Rupture on S/G "e".
C.
Time      I  Position    I                            Applicants Applicant's Actions or Behavior SRO        Reset SPDS and initiate monitoring of CSFSTs.
CREW          Open Foldout A.
* RCP Trip criteria. IF BOTH conditions are met, THEN stop all RCPs: (NO)
RO                      0o  SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 00  RCS Subcooling - < - < 35 degrees FF [55 degrees F]
* SI actuation criteria. IF EITHER condition occurs, THEN PATH-i, Entry Point A: (YES)
Actuate SI and Go To PATH-1, S RO/RO 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                                                              NUREG-iO2i, Rev. 9, Supp. 11 NUREG-1021,
Appendix D  D                              Operator Action                                                              Form ES-D-2 Op Op Test Test No.:
No.:      1 Scenario #      33      Event #          7, 8, &
_7;..l"..;;.81..,;'  9 _ _ Page
                                                                                    &;.;..9;.....              13 13              26_ _ _~1 of .....;2;;;.;;6 Event
== Description:==
== Description:==
              "C" Safety Valve fails open.
S/G C S!G                        open. Safety InjectionInjection Pump C    "C" fails to start.
S/G Blowdown S/G  Blowdown Sample    valves fail to Sample valves        to close.
close.
Time      II  Position    ~                              Applicant's Actions or Behavior Applicants BOOTH OPERATOR: When the crew actuates Safety Injection, verify Events 7, 8 and 9 are inserted.
CREW          Open Foldout A. (nothing additional to address)
Verify Phase A Isolation valves are closed. (NO, crew will direct local RO isolation of the open S/G Blowdown Sample valves)
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.
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)
RO                      COW pump is running. (YES)
At least 11 CCW 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)
Appendix D                                                                            NUREG-1 021, Rev. 9, Supp. 11
Appendix 0D                                Operator Action                                                      Form ES-O-2  ES-D-2 Op Test No.:        1 Scenario #        3      Event #    _7;..,l.'      &;;..;9~
7, ..;;.8:..;;'
8, &    9 _ _ Page          14            26_ _ _...,1 of .....;2;;.;;6 Event
== Description:==
C Safety Valve fails open. Safety Injection Pump "C" S/G "C"                                                          C fails to start.
SIG Blowdown S/G  Slowdown Sample valves fail to close.
Time      i  Position  iI                            Applicants Actions or Behavior Applicant's 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                      EDGs running. (YES)
Verify both EOGs CONTINUOUS ACTION STEP:
BOP        Restart battery chargers withinwithin.30      30 minutes of power loss using OP-              OP 601.
CONTINUOUS ACTION STEP:
RO Pressure has remained below.10 CV Pressure.hasremained            below 10 psig. (YES)
RO        Automatic Steam Line Isolation initiated. (NO)
RO        Automatic Steam Line Isolation required. (NO)
SRO        Locally open breaker for HVS-1 at MCC-5.
RO        RCS pressure> 1350 psig. [1250 psig]                psigj (YES)
BOP        At least 300 GPM AFW flow available. (YES)
Appendix 0D                                                                        NUREG-1021,, Rev. 9, Supp. 11 NUREG-1021
Appendix D                                Operator Action                                                    Form ES-D-2 Op Test No.:        1    Scenario #      3      Event #      7, 8, &;.;..9~& 9 _ _ Page
_7;"':"..;;.8:..;'                    15    of -:2:.;:6 26_ _ _-11
                ~-
Event
== Description:==
C Safety Valve fails open. Safety Injection Pump "C" S/G "C"                                                        C fails to start.
Slowdown Sample valves fail to close.
S/G Blowdown Time      II  Position  II                            Applicants Actions or Behavior Applicant's BOP        Verify AFW valves properly aligned.
BOP        Control AFW flow to maintain S/G          SIG level between 8% [18%] and 50%.
RO        RCP Thermal barrier cooling water 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)
RO        RCS temperature> 547 degrees F. (NO)
RO        Attempt to limit cooldown.
If RCS cooldown continues and is not due to SI flow, then close MSIVs RO and MSIV bypasses.
RO        PZR PORVs closed. (YES)
RO        PZR Spray and Aux Spray valves closed. (YES)
P0 RO        At least 11 RCP running. (YES)
RO        At least 11 SI Pump Running. (YES)
RO        RCS Subcooling less than 35 degrees F [55]. (NO)
BOP        Any S/G with uncontrolled depressurization. (YES)
Appendix D  D                                                                    NUREG-1 021, Rev. 9, 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;..."..;;.8.:..;,          Page Page        16 16    of ....;2::.;6~
of    26 _ _---i1
                  ~-
Event
== Description:==
Event
== Description:==
SIG "C" S/G      Safety Valve fails open.
C Safety            open. Safety Safety Injection Injection Pump Pump "C" C fails to start.
S/G  Blowdown Sample valves fail to close.
S/G Blowdown                            close.
Time      I  Position  I                            Applicants Actions or Behavior Applicant's RO        Reset SPDS and initiate monitoring of CSFSTs.
SRO        Transition to EPP-11, FAULTED SIG ISOLATION.
BOP        Maintain At Least One S/G    SIG Available For RCS Cooldown.
BOP        Any S/G pressure stable or increasing. (YES)
SIG pressure decreasing in an uncontrolled manner OR any S/G Any S/G BOP completely depressurized. (YES)
Isolate faulted S/G SIG using Supplement G, S/G              SIG ISOLATION.
BOP (Supplement G Steps are listed on pages 22-25)
Maintain A Faulted S/G In The Isolated Condition During Subsequent BOP Recovery Actions Unless Needed For Cooldown.
BOP        Check CST level greater than 10%. (YES)
BOP        Check Available Secondary Radiation Monitors normal. (NO)
SRO        Transition to PATH-2, Entry Point J.
RO        Reset SPDS and initiate monitoring of CSFSTs.
CREW        Open Foldout C.
WHEN below 10b0  10-10 amps, THEN energize Source Range detectors RO and monitor recorder.
BOP        Request periodic activity samples of all S/Gs Appendix D  D                                                                      NUREG-1  021, Rev. 9, NUREG-1 021,            9, Supp. 11


Operator Action Form ES-D-2 Scenario # 3 Event # 5, 6 Page 11 of 26 Multiple dropped rods requiring a Reactor Trip. S/G Tube Rupture on S/G "C". Time I Position I Applicant's Actions or Behavior IMMEDIATE ACTION STEP: BOP Turbine Tripped
Appendix DD Appendix                                      Operator Action Operator     Action                                                   Form Form ES-D-2 ES-D-2 Op Test Op Test No.:
.. (YES) IMMEDIATE ACTION STEP: BOP E-l AND E-2 energized. (YES) IMMEDIATE ACTION.STEP:
No.:               Scenario ##
RO SI Initiated. (NO) SI Initiation required. (NO)
Scenario          33      Event ##
* CRITICAL TASK: Manually trip the Reactor prior to transitioning out of AOP-001. RO Verify two Charging Pumps running. SRO Transition to EPP-4, REACTOR TRIP RESPONSE.
Event              7, 8, & 9 7,8,&9              Page Page          17 17  ofof  26 26
Continuous Action Step: Determine if procepureexit is warranted:
                  ~-                                                ~~~----                                        ~---~
SRO
Event
* Check.atlack onRNPsite in progress. (NO)
* Check a total loss of SW OR. Loss of Lake Robinson Dam integrity in progress. (NO, Go to Step 2) Continuous Action Step: RO CheckSI signal initiated. (NO, Go to Step 4) IfSI initiation occurs during this procedure, THEN Go to PATH-1, Entry Point A Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: ...;....-Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 3 Event # 5,6 Page 12 of 26 Multiple dropped rods requiring a Reactor Trip. S/G Tube Rupture on S/G "e". Time I Position I Applicant's Actions or Behavior SRO Reset SPDS and initiate monitoring of CSFSTs. CREW Open Foldout A.
Event
* RCP Trip criteria.
IF BOTH conditions are met, THEN stop all RCPs: (NO) RO 0 SI Pumps -AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0 RCS Subcooling
-< 35 degrees F [55 degrees F]
* SI actuation criteria.
IF EITHER condition occurs, THEN Actuate SI and Go To PATH-1, Entry Point A: (YES) SRO/RO RCS Subcooling
-< 35 degrees F [55 degrees F] 0 0 PZR Level-CAN NOT BE MAINTAINED>
10% [32%].
* 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, Entry Point A. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --.;...-Event


== Description:==
== Description:==
S/G "C" S/G  C Safety Safety Valve Valve fails fails open. Safety Injection open. Safety      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 Time      I    Position Position    II                                Applicants Actions Applicant's    Actions or or Behavior Behavior BOP BOP          Place Steam Place  Steam Dump Dump Mode Mode SwitchSwitch to to Steam Steam Pressure.
Pressure.
BOP BOP          Open QCV Open    QCV-1    0426, Bypass
                                              -10426,    Bypass Condensate Condensate Polishers.
Polishers.
BOP BOP          Close C-48A Close  C-48A andand 48B to isolateisolate Hotwell Hotwell Return Return to CST. CST.
RO          At Least 11 RCP running. (YES)
RO          At Least 11 SI pump running. (YES)
RO          RCS Subcooling less than 35 degrees F. [55]                [55j (NO)
BOP          Ruptured S/GSIG identified. (YES)
RO          Maintain at least 11 S/G  SIG available for RCS Cooldown.
Verify ruptured steam line PORV setpoint at 1035              1035 psig using    using status BOP board.
RO          Verify RCS temperature << 547        547 degrees degrees FF prior to MSIV closure.
RO RO          Close Close ruptured S/G  S/G MSIV MSIV and  and MSIV MSIV Bypass.
Bypass.
RO RO          Ruptured Ruptured SIG S/G MSIV MSIV and  and MSIV MSIV bypass bypass closed.
closed. (YES)
(YES)
Continuous Continuous ActionAction Step:
Step:
RO RO          WHEN WHEN ruptured ruptured SIG S/G pressure pressure decreases decreases belowbelow 10351035 psig,psig, THEN THEN verify ruptured Steam verifyruptured    Steam Line Line PORVPORV closed.
closed.
Appendix Appendix DD                                                                    NUREG-1 NUREG-1021,  021, Rev.Rev. 9,  9, Supp.
SUpp. 11


Operator Action Form ES-D-2 Scenario # 3 Event # _7;..l"..;;.81..,;'
Appendix 0D                                    Operator Action Operator                                                              Form ES-D-2 Form        ESD-2 Op Test Op Test No.:
&;.;..9;.....
No.:        1    Scenario ##
__ Page 13 of .....;2;;;.;;6
Scenario              33    Event ##
___ S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time II Position Applicant's Actions or Behavior BOOTH OPERATOR:
Event            7, 8, &_9;.,...-_
When the crew actuates Safety Injection, verify Events 7, 8 and 9 are inserted.
                                                                                    &9
CREW Open Foldout A. (nothing additional to address) RO Verify Phase A Isolation valves are closed. (NO, crew will direct local isolation of the open S/G Blowdown Sample valves) 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. RO Verify 2 SI pumps running. (NO, "C" will be manually started) RO Verify Both RHR pumps running. (YES) RO Verify SI valves are properly aligned. (YES) RO At least 1 CCW pump is running. (YES) BOP All SW and SW Booster pumps running. (NO) BOP Attempt to start all SW and SW booster pumps. (NO, SW Booster Pump "A" is unavailable and SW Pump "A" is tripped) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Op Test No.: --.;...-Event
_7...:,._8:...;'          Page
_ Page           18 18    of .....:2:..;6 of       26_ _ _-11 n
Event


== Description:==
== Description:==


Operator Action Form ES-O-2 Scenario # 3 Event # _7;..,l.'..;;.8:..;;'
Event
__ Page 14 of .....;2;;.;;6
___ ...,1 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time i Position i Applicant's Actions or Behavior 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 EOGs running. (YES) CONTINUOUS ACTION STEP: BOP Restart battery chargers within.30 minutes of power loss using OP-601. CONTINUOUS ACTION STEP: RO CV Pressure.hasremained below.10 psig. (YES) RO Automatic Steam Line Isolation initiated. (NO) RO Automatic Steam Line Isolation required. (NO) SRO Locally open breaker for HVS-1 at MCC-5. RO RCS pressure>
1350 psig. [1250 psig] (YES) BOP At least 300 GPM AFW flow available. (YES) Appendix 0 NUREG-1021 , Rev. 9, Supp. 1 Appendix D Op Test No.: Event


== Description:==
== Description:==
S/G "C S/G    Cn 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 Sample S/G Blowdown        Sample valves valves fail fail to to close.
close.
Time      ~  Position Position  II                                ADDlicants Actions or Behavior Applicant's                  Behavior IF MDAFW pump is not available, THEN maintain at least 11 S/G RO supply to SDAFW pump.
CREW          Close ruptured S/G  SIG steam shutoff to SDAFW pump.
BOP          Verify S/GSIG Blowdown Isolation and Sample Valves Closed.
Locally close warmup steam supply from ruptured S/G                        SIG to SDAFW BOP pump.
BOP          Locally close above and below seat drains from ruptured S/G.
Isolate Feed Flow to any ruptured 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    S/G before transitioning to EPP-17.
Continuous Action Step:
BOP          WHEN ruptured SIG      S/G level is greater than 8% [18%], THEN isolate Feed Flow.
Continuous Action  Action Step:
Step:
D        I.
BOP 1
upen Open* reaers breakers ror for V1..,8,  v-14 ana vi-, V2-14                  V-1b vaive and V2-16  valve ciosea closed*to isolateisolate ruptured rupturedS/G. SIG.
Control Control Feed Flow  Flow to maintain intact S/G level between 8%                    8% [18%] and BOP BOP 50%.
Appendix Appendix D  0                                                                        NUREG-1021, NUREG-1021 , Rev. Rev. 9, 9, Supp.
Supp. 11


Operator Action Form ES-D-2 Scenario # 3 Event # _7;"':"..;;.8:..;'
Appendix 0D                                Operator Action Operator     Action                                                     Form ES-O-2 Form           ES-D-2 Op Test No.:
__ Page 15 of -:2:.;:6 ___ -11 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time II Position I Applicant's Actions or Behavior BOP Verify AFW valves properly aligned. BOP Control AFW flow to maintain S/G level between 8% [18%] and 50%. RO RCP Thermal barrier cooling water Hi/Lo flow alarms illuminated. (NO) BOP Place Steam Dump Mode Switch to Steam Pressure.
Op Test No.:    -.;...-
RO RCS Temp stable at OR trending to 547 degrees F. (NO) RO RCS temperature>
Scenario ##
547 degrees F. (NO) RO Attempt to limit cooldown.
Scenario        33      Event ##
RO If RCS cooldown continues and is not due to SI flow, then close MSIVs and MSIV bypasses.
Event          _7;..:" 8, &;.;..;9~__
RO PZR PORVs closed. (YES) RO PZR Spray and Aux Spray valves closed. (YES) RO At least 1 RCP running. (YES) RO At least 1 SI Pump Running. (YES) RO RCS Subcooling less than 35 degrees F [55]. (NO) BOP Any S/G with uncontrolled depressurization. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event
7, ...;;,8:.,;;,
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of      26          _---l 1
Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 3 Event # _7;..."..;;.8.:..;, &;.;..9;;....-__
Event
Page 16 of
__ ---i1 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time I Position I Applicant's Actions or Behavior 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 Any S/G pressure stable or increasing. (YES) BOP Any S/G pressure decreasing in an uncontrolled manner OR any S/G completely depressurized. (YES) BOP Isolate faulted S/G using Supplement G, S/G ISOLATION. (Supplement G Steps are listed on pages 22-25) BOP Maintain A Faulted S/G In The Isolated Condition During Subsequent Recovery Actions Unless Needed For Cooldown.
BOP Check CST level greater than 10%. (YES) BOP Check Available Secondary Radiation Monitors normal. (NO) SRO Transition to PATH-2, Entry Point J. RO Reset SPDS and initiate monitoring of CSFSTs. CREW Open Foldout C. RO WHEN below 10-10 amps, THEN energize Source Range detectors and monitor recorder.
BOP Request periodic activity samples of all S/Gs Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event


== Description:==
== Description:==
SIG "C" S/G  C Safety Safety Valve Valve fails fails open.
open. Safety Safety Injection Injection PumpPump "C" fails to C fails to start.
start.
S/G  Blowdown Sample S/G Blowdown    Sample valves valves fail fail to to close.
close.
Time      ~I  Position  I                              Applicants Actions or Behavior Applicant's BOP        Any other S/GSIG with uncontrolled level increase. (NO)
RO        PZR PORVs closed. (YES)
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.
RO        Reset SI.
IF offsite power is lost, THEN restart emergency safeguards CREW equipment.
RO        Reset CV Spray.
RO        Reset Phase A and Phase B.
Establish Instrument Air to CV. IF compressor NOT running                    running, THEN ,
RO start compressor.
BOP        All AC Busses energized by offsite power. (YES)
IF IF RCS pressure decreases below 275 PSIG,                  PSIG, THEN restart RHR RO Pumps.
BOP BOP        Ruptured S/GS/G isolated. (YES, completed during              during Supplement G)
Appendix Appendix D  0                                                                      NUREG-1 NUREG-1 021, 021, Rev.
Rev. 9, 9, Supp.
Supp. 11


Operator Action Form ES-D-2 Scenario # 3 Event # 7,8,&9 Page 17 of 26 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time I Position II Applicant's Actions or Behavior BOP Place Steam Dump Mode Switch to Steam Pressure.
Appendix D                                Operator Action                                                     Form ES-D-2 ESD-2 Op Test No.:
BOP Open QCV -10426, Bypass Condensate Polishers.
Op      No.:        1 Scenario #
BOP Close C-48A and 48B to isolate Hotwell Return to CST. RO At Least 1 RCP running. (YES) RO At Least 1 SI pump running. (YES) RO RCS Subcooling less than 35 degrees F. [55] (NO) BOP Ruptured S/G identified. (YES) RO Maintain at least 1 S/G available for RCS Cooldown.
Scenario        3       Event #
BOP Verify ruptured steam line PORV setpoint at 1035 psig using status board. RO Verify RCS temperature
Event      _7;...l,' 8, &;;..;9~
< 547 degrees F prior to MSIV closure. RO Close ruptured S/G MSIV and MSIV Bypass. RO Ruptured S/G MSIV and MSIV bypass closed. (YES) Continuous Action Step: RO WHEN ruptured S/G pressure decreases below 1035 psig, THEN verifyruptured Steam Line PORV closed. Appendix D NUREG-1021, Rev. 9, SUpp. 1 Appendix 0 Op Test No.: --Event
7, ..;;.8:..;'
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26 _ _----11 Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 3 Event # _7...:,._8:...;'
Event
&_9;.,...-
__ Page 18 of .....:2:..;6
___ -11 S/G "C n Safety Valve fails open. Safety Injection Pump "C n fails to start. S/G Blowdown Sample valves fail to close. Time Position II Applicant's Actions or Behavior RO IF MDAFW pump is not available, THEN maintain at least 1 S/G supply to SDAFW pump. CREW Close ruptured S/G steam shutoff to SDAFW pump. BOP Verify S/G Blowdown Isolation and Sample Valves Closed. BOP Locally close warmup steam supply from ruptured S/G to SDAFW pump. BOP Locally close above and below seat drains from ruptured S/G. BOP Isolate Feed Flow to any ruptured S/G that is faulted unless needed for RCS cooldown.
CRITICAL TASK: Recognize that a Steam Generator Tube Rupture has occurred and isolate the affected S/G before transitioning to EPP-17. Continuous Action Step: BOP WHEN ruptured S/G level is greater than 8% [18%], THEN isolate Feed Flow. Continuous Action Step: BOP Open* breakers for V1..,8, V2-14 and V2-16 valve closed* to isolate rupturedS/G.
BOP Control Feed Flow to maintain intact S/G level between 8% [18%] and 50%. Appendix 0 NUREG-1021 , Rev. 9, Supp. 1 Appendix 0 Op Test No.: -.;...-Event


== Description:==
== Description:==
S/G "C" S/G      Safety Valve fails open. Safety C Safety                  Safety Injection Injection Pump Pump "C" C fails to start.
S/G Blowdown Sample valves fail to close.
Time      II  Position  ~                              Applicants Actions or Behavior Applicant's BOP        Ruptured S/GSIG pressure> 220 PSIG. (YES)
BOP        At least one intact S/G available for RCS cooldown. (YES)
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 <  < 543 degrees F AND block TAVG SI signal prior to RO maximum steam dump.
BOP        Dump steam from intact S/G to condenser at maximum rate.
RO        Align Charging Pump suction to RWST.
RO        Establish Charging flow to maintain PZR 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/G pressure stable or increasing. (NO)
Appendix D  D                                                                  NUREG-1 NUREG-1 021, 021, Rev. 9,  9, Supp. 11


Operator Action Form ES-O-2 Scenario # 3 Event # _7;..:" ...;;,8:.,;;,
Appendix D                                Operator Action                                                       Form ES-D-2 Op Test No.:        1    Scenario #       3       Event #       7, 8, &          &;;..9~
Page 19 of ...;2=..:6:....-
_7.;..:.,...;.8.:..;,  9 _ _ Page        21        26_ _ _---i1 of _2_6
__ ---l 1 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time Position I Applicant's Actions or Behavior BOP Any other S/G with uncontrolled level increase. (NO) RO PZR PORVs closed. (YES) RO Open at least one PORV block unless closed to isolate an open PORV. RO IF PORV opens on high pressure, THEN verify reclosure at or below 2335 PSIG, close PORV blocks as necessary.
                --=---
RO Reset SI. CREW IF offsite power is lost, THEN restart emergency safeguards equipment.
Event
RO Reset CV Spray. RO Reset Phase A and Phase B. RO Establish Instrument Air to CV. IF compressor NOT running, THEN start compressor.
BOP All AC Busses energized by offsite power. (YES) RO IF RCS pressure decreases below 275 PSIG, THEN restart RHR Pumps. BOP Ruptured S/G isolated. (YES, completed during Supplement G) Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: -.;...-Event


== Description:==
== Description:==
S/G  c Safety Valve fails open. Safety Injection Pump "COO SIG "COO                                                          C fails to start.
SIG Blowdown Sample valves fail to close.
S/G Time      I  Position  I                            Arclicants Actions or Behavior Applicant's Ruptured S/GSIG pressure decreases to < 250 PSIG above pressure of BOP intact S/G SIG used for cooldown. (YES)
Transition to EPP-17, SGTR WITH LOSS OF RCS: SUBCOOLED SRO RECOVERY.
At the discretion of the Chief Examiner, when the crew has transitioned to EPP-17 and SIG "C" C has been isolated as a faulted and ruptured SIG, the scenario may be terminated.
Appendix D                                                                          NUREG-1 021, Rev. 9, Supp. 11 NUREG-1021,


Operator Action Form ES-D-2 Scenario # 3 Event # _7;...l,'..;;.8:..;'
Appendix D                                    Operator Action                                               Form ES-D-2 Op Test No.:
__ Page 20 of
Op Test  No.:
__ ----11 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time II Position Applicant's Actions or Behavior BOP Ruptured S/G pressure>
                  -- 1    Scenario ##
220 PSIG. (YES) BOP At least one intact S/G available for RCS cooldown. (YES) SRO Determine required core exit temperature from Table 3. RO WHEN PZR press decreases to < 2000 PSIG, THEN block PZR 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) RO Verify TAVG < 543 degrees F AND block TAVG SI signal prior to maximum steam dump. BOP Dump steam from intact S/G to condenser at maximum rate. RO Align Charging Pump suction to RWST. RO Establish Charging flow to maintain PZR level. RO Core Exit Temperature less than required temperature. (YES) BOP Reduce Steam flow to stabilize RCS temperature.
Scenario          33      Event ##
CREW Allow RCS temperature to stabilize from cooldown prior to continuing.
Event          7, 8, &
BOP Ruptured S/G pressure stable or increasing. (NO) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: --=---Event
7,8,
                                                                  ~~~---
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                                                                                                            ~---~I Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 3 Event # _7.;..:.,...;.8.:..;,
Event  
__ Page 21 of _2_6 ___ ---i1 S/G "COO Safety Valve fails open. Safety Injection Pump "COO fails to start. S/G Blowdown Sample valves fail to close. Time I Position I Applicant's Actions or Behavior BOP Ruptured S/G pressure decreases to < 250 PSIG above pressure of intact S/G used for cooldown. (YES) SRO Transition to EPP-17, SGTR WITH LOSS OF RCS: SUBCOOLED RECOVERY.
At the discretion of the Chief Examiner, when the crew has transitioned to EPP-17 and SIG "C" has been isolated as a faulted and ruptured SIG, the scenario may be terminated.
Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event


== Description:==
== Description:==
SIG "c" S/G        Safety Valve fails open. Safety C Safety                    Safety Injection  Pump "c" Injection Pump C fails to start.
SIG Blowdown S/G  Blowdown Sample valves fail to close.
Time      ~  Position  iI                                Applicants Actions or Behavior Applicant's Pages 22-25 are steps from Supplement G, STEAM GENERATOR ISOLATION to isolate C, as a faulted SIG SIG "C"                    S/G and to isolate SIG "C"      C as a ruptured S/G.
Go to the appropriate step from following table:
BOP
                                    *. SIG C to be isolated, GO To Step 34 S/G                                        34..
BOP        Check S/G "C"  C faulted. (YES)
BOP        Verify V1-3C, MSIV CLOSED. (YES)
BOP        Verify MS-353C, MSIV V1-3C      Vi -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-i    6C, AFW HDR DISCH Valve CLOSED. (YES)
V2-16C, BOP        Verify STEAM LINE PORV CLOSED. (YES)
BOP        Verify Vi-8C, V1-8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)
Verify SIG    "C" Blowdown and Blowdown Sample Valve Status Light S/G C BOP Indication CLOSED. (NO)
Appendix D  D                                                              NUREG-1021, Rev. 9, Supp. 11


Operator Action Form ES-D-2 Scenario # 3 Event # 7,8, & 9 Page 22 of 26 S/G "c" Safety Valve fails open. Safety Injection Pump "c" fails to start. S/G Blowdown Sample valves fail to close. Time Position i Applicant's Actions or Behavior Pages 22-25 are steps from Supplement G, STEAM GENERATOR ISOLATION to isolate SIG "C" as a faulted SIG and to isolate SIG "C" as a ruptured S/G. BOP Go to the appropriate step from following table:
Appendix D                                      Operator Action                                                 Form ES-D-2 Op Test No.:
* S/G C to be isolated, GO To Step 34 . BOP Check S/G "C" faulted. (YES) BOP Verify V1-3C, MSIV CLOSED. (YES) BOP Verify MS-353C, MSIV V1-3C 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 V2-16C, AFW HDR DISCH Valve CLOSED. (YES) BOP Verify STEAM LINE PORV CLOSED. (YES) BOP Verify V1-8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES) BOP Verify S/G "C" Blowdown and Blowdown Sample Valve Status Light Indication CLOSED. (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: -.;...-Event
Op Test No.:        1 Scenario #
Scenario              33      Event #
Event          7, 8, 7,  8, &
                                                                            & 99        Page Page        23 23    of of   26
                                                                    ~~~----                                     ~---~
Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 3 Event # 7, 8, & 9 Page 23 of 26 S/G "C n Safety Valve fails open. Safety Injection Pump "C n fails to start. S/G Blowdown Sample valves fail to close. Time II Position I Applicant's Actions or Behavior Deenergize R-19C. IF S/G "c" Blowdown and Sample valves fail to close, THEN close:
Event
* SGB-38C, SGBD HX "C". BOP
 
* SGB-56C, SGBD HX "c" BYPASS/HX FLOW CONTROL ISOLATION.
== Description:==
* SGB-60C, SGBD LINE "c" TO WLU SYSTEM.
S/G  Cn Safety S/G "C                                 Safety Injection Safety Valve fails open. Safety   Injection Pump Cn fails to start.
* SGB-38, S/G "c" SAMPLE FLOW ISOLATION.
Pump "C SIG Blowdown S/G Blowdown Sample valves fail to close. close.
BOP Dispatch an operator to the Pipe Jungle to close MS-38, S/G "c" BYPASS DRN and WARM-UP LINE TO AFW PUMP. BOP Check S/G C MSIV Above and Below Seat Drain Valves CLOSED. (YES) Dispatch an operator to E-1/E-2 Room to perform the following:
Time     II Position   I                                   Aolicants Actions or Behavior Applicant's Deenergize R-19C.
* At MCC-9, verify V2-16C closed and open breaker V2-16C, BOP MDAFW PUMP TO S/G C.
IF S/G "c"   C Blowdown and Sample valves fail to close, THEN close:
* At MCC-6, verify V1-8C closed and open breaker V1-8C, SDAFW PUMP STEAM ISOLATION.
                                    **      SGB-38C, SGBD HX "C".       C.
BOP                       SGB-56C, SGBD HX "c"
                                    **                                    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:
                                      *.                          V2-i 6C closed and open breaker V2-16C, At MCC-9, verify V2-16C                                             V2-i 6C, BOP                     MDAFW PUMP TO S/G C.
                                      *. 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:
Dispatch operator to the Aux. Bldg. to perform the following:
BOP                                  0, verify V2-14C closed and open breaker V2-i4C,
                                      .*    At MOO-i MCC-10,                                                          V2-14C, SDAFW PUMP HEADER DISCHARGE TO S/G C.
BOP        Check All Faulted and Ruptured S/Gs ISOLATED. (NO, Go To Step 1)                            1)
Go to the appropriate step from following table:
BOP
BOP
* At 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 To Step 1) BOP Go to the appropriate step from following table:
                                      **   S/G C to be isolated, Go To Step 34.
* S/G C to be isolated, Go To Step 34. Appendix D NUREG-1021, Rev. g, Supp. 1 Appendix D Op Test No.: --.;...-Event
SIG Appendix D D                                                                NUREG-iO2i, NUREG-1021, Rev. 9,        g, Supp. 11
 
Appendix D                                 Operator Action                                                              Form ES-D-2 Op Test No.:       1 Scenario #      3      Event #        7, 8, & 9 _ _ Page
_7;,..:.,..;;,8,:,.;&;.;.,;9;;...-.            24            26_ _ _-l of .....;2:..;;6 1
Event


== Description:==
== Description:==
C Safety Valve fails open. Safety Injection Pump "C" S/G "C"                                                                  C fails to start.
SIG Blowdown Sample valves fail to close.
S/G Time      III Position  I                            Applicant's Actions or Behavior A&#xf8;plicants Check S/G "C" C faulted. (NO)
BOP        Verify ruptured Steam Line PORV setpoint at 1035 PSIG using Status Board.
BOP        Verify Vi  -8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)
V1-8C, SIG C Blowdown and Blowdown Sample Valve Status Light Verify S/G BOP Indication CLOSED. (NO)
R-1 9C.
Deenergize R-19C.
C Blowdown and Sample valves fail to close, THEN close:
IF S/G "C"
* SGB-38C, SGBD HX "C".            C.
BOP            **    SGB-56C, SGBD HX "C"              C BYPASS/HX FLOW CONTROL ISOLATION.
* SGB-60C, SGBD LINE "C"                  C TO WLU SYSTEM.
* SGB-38, S/G SIG "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)
E-iIE-2 Room to perform the following:
Dispatch an operator to E-1/E-2
                                  **  At MCC-9, verify V2-16C V2-i 6C closed and open breaker V2-16C,                      V2-i 6C, BOP                MDAFW PUMP TO S/G C.
                                  **  At MCC-6, verify V1-8CVi -80 closed and open breaker Vi                          V1-8C,  -8C, SDAFW PUMP STEAM ISOLATION.
Appendix D                                                                          NUREG-i 021, Rev. 9, Supp. 11 NUREG-1


Operator Action Form ES-D-2 Scenario # 3 Event # _7;,..:.,..;;,8,:,.;&;.;.,;9;;...-.
Appendix D  D                                Operator Action Operator                                                                      Form ES-D-2 Form         ES-D-2 Op Test Op Test No.:
__ Page 24 of .....;2:..;;6
No.:        1 Scenario ##
___ -l 1 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time II Position I Applicant's Actions or Behavior Check S/G "C" faulted. (NO) BOP Verify ruptured Steam Line PORV setpoint at 1035 PSIG using Status Board. BOP Verify V1-8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES) BOP Verify S/G C Blowdown and Blowdown Sample Valve Status Light Indication CLOSED. (NO) Deenergize R-19C. IF S/G "C" Blowdown and Sample valves fail to close, THEN close:
Scenario          33      Event ##
* SGB-38C, SGBD HX "C". BOP
Event              7, 8, &;;...9:.....-_
* SGB-56C, SGBD HX "C" BYPASS/HX FLOW CONTROL ISOLATION.
                                                                                          &9
* SGB-60C, SGBD LINE "C" TO WLU SYSTEM.
_7;..:.,....;;.8.:....;,         Page
* SGB-38, S/G "C" SAMPLE FLOW ISOLATION.
_ Page          25 25    of ....;2;;.,;;6 of        26_ _ _-11 Event
BOP Dispatch an operator to the Pipe Jungle to close MS-38, S/G "C" BYPASS DRN and WARM-UP LINE TO AFW PUMP. BOP Check S/G C MSIV Above and Below Seat Drain Valves CLOSED. (YES) Dispatch an operator to E-1/E-2 Room to perform the following:
* At MCC-9, verify V2-16C closed and open breaker V2-16C, BOP MDAFW PUMP TO S/G C.
* At MCC-6, verify V1-8C closed and open breaker V1-8C, SDAFW PUMP STEAM ISOLATION.
Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: .-;...-Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 3 Event # _7;..:.,....;;.8.:....;, &;;...9:.....-
Event
__ Page 25 of ....;2;;.,;;6
 
___ -11 S/G "C" Safety Valve fails open. Safety Injection Pump "C" fails to start. S/G Blowdown Sample valves fail to close. Time II Position I Applicant's Actions or Behavior Dispatch operator to the Aux. Bldg. to perform the following:
== Description:==
BOP
SIG "C" S/G       Safety Valve C Safety   Valve fails fails open.
* At MCC-1 0, 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. (YES) BOP WHEN the faulted S/Gs dry out, THEN dump steam from intact S/G to control RCS repressurization.
open. Safety Safety Injection   Injection PumpPump "C" C fails fails to to start.
BOP Check Any S/G RUPTURED. (YES) Perform the following to minimize Secondary system contamination:
start.
* Use Auxiliary boilers for auxiliary steam.
S/G Blowdown Sample S/G Blowdown      Sample valves valves fail fail to to close.
* Bypass the condensate polishers.
close.
* Verify hotwell return to CST isolated:
Time     II Position Position  I                                 Aoolicants Actions or Behavior Applicant's                         Behavior Dispatch operator to the Aux. Bldg. to perform the following:
0 Locally verify C-48A and C-48B CLOSED. SRO/BOP Dispatch an operator to close GS-36, MANUAL GLAND STEAM DUMP. SRO Return to procedure and step in effect. Appendix D NUREG-1 021, Rev. 9, Supp. 1 HLC-08 NRC SCENARIO 3 TURNOVER SHEET POWER LEVEL: 7% BOL, 150 MWD/MTU. BORON CONCENTRATION:
BOP             *. At MCC-1 MCC-10,  0, verify V2-14C closed and open breaker V2-14C,                              V214C, SDAFW PUMP HEADER DISCHARGE TO S/G C.
1645 ppm EQUIPMENT UNDER CLEARANCE:
BOP       Check All Faulted and Ruptured S/Gs ISOLATED. (YES)
* SW Booster Pump "A" is out of service and under clearance for Motor Coupling Alignment.
WHEN the faulted S/Gs dry out, THEN dump steam from intact S/G to BOP control RCS repressurization.
o LCO 3.7.7 -A has been entered and is in hour 18 of a 72 Action Statement.
BOP       Check Any S/G RUPTURED. (YES)
o Expected return is within -18 hours. EQUIPMENT STATUS:
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 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 D   D                                                                              NUREG-1 NUREG-1 021, 021, Rev.
Rev. 9, 9, Supp.
Supp. 11
 
HLC-08 NRC SCENARIO 3 TURNOVER SHEET POWER LEVEL: 7% BOL, 150 MWD/MTU.
BORON CONCENTRATION: 1645 ppm EQUIPMENT UNDER CLEARANCE:
* SW Booster Pump "A"A is out of service and under clearance for Motor Coupling Alignment.
o       3.7.7-A LCO 3.7.7 -A has been entered and is in hour 18 of a 72 Action Statement.
o                             .18 hours.
Expected return is within -18 EQUIPMENT STATUS:
* Main Turbine bearing #3 has a slightly elevated vibration and is being monitored by Systems Engineering.
* Main Turbine bearing #3 has a slightly elevated vibration and is being monitored by Systems Engineering.
INSTRUCTIONS FOR THE WATCH:
INSTRUCTIONS FOR THE WATCH:
* Continue with GP-005 and synchronize the Generator to the Grid. Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 Facility:
* Continue with GP-005 and synchronize the Generator to the Grid.
HB ROBINSON Scenario No.: 4 Op Test No.: 2008 NRC Examiners:
Appendix D 0                                               NUREG-1 021, Rev. 9, Supp. 11
 
I Appendix Appendix D  D                                     Scenario Outline Scenario     Outline                                   Form Form ES-D-1 ES-D-1 Facility:
Facility:          HB ROBINSON HB ROBINSON                       Scenario No.:
Scenario    No.:          44        Test No.:
Op Test Op        No.:       2008 NRC 2008  NRC Examiners:
Examiners:                                                        Operators:
Operators:
Operators:
Initial Conditions:
Initial Conditions:
* 50% BOL, 150 MWD/MTU, 1285 ppm Boron.
Initial                **    50% BOL, 150 MWD/MTU, 1285 ppm Boron.
* SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.
                        **    SW Booster Pump "A"   A is Out-Of-Service for Motor Coupling Alignment.
0 LCO 3.7.7 -A has been entered and is in hour 18 of a 72 hour action statement.
0o    LCO 3.7.7 3.7.7-A
0 Expected return is within -18 hours.
                                                          -A has been entered and is in hour 18    18 of a 72 hour action statement.
* Main Turbine Vibration for #2, 3 and 4 bearings is elevated.
0o    Expected return is within .18 hours.
Turnover:
                        **     Main Turbine Vibration for #2, 3 and 4 bearings is elevated.
* Returning to RTP following a Maintenance Outage. Increase power to 75%. Critical Task:
Turnover:             **     Returning to RTP following a Maintenance Outage. Increase power to 75%.
* Manually initiate SI to provide injection flow from at least 1 SI Pump before Reactor Vessel level reaches 41 % by Full Range RVLlS indication.
Critical Task:         **     Manually initiate SI to provide injection flow from at least 11 SI Pump before Reactor Vessel level reaches 41   41%% by Full Range RVLlSRVLIS indication.
* 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).
                        **     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. Event Type* Event No. No. Description 1 (R) RO Increase power to 75% RTP. (N) SRO, BOP 2 (I) BOP, SRO Loop 1 T HOT Fails Low. (TS) SRO 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 (M) ALL High vibration on #3 Turbine bearing which leads to a manual Reactor trip. 6 (M) ALL Failure of the Reactor to trip. (ATWS) SDAFW Pump trips. 7 (M) ALL Small Break LOCA. (TS) SRO 8 (C) RO Phase A fails to automatically actuate and several valves fail to automatically close. 9 (C) RO Safety Injection fails to automatically actuate. 10 (C) BOP Control Room HVAC Train A and Train B fail to automatically actuate. (HVE-19A fails to start and HVE-16 fails to stop) * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 4  
Event         MaIf.
Malf.             Type*
Event Type*                                             Event No.         No.                                                         Description 1
1                  (R) RO               Increase power to 75% RTP.
(N) SRO, BOP 2                   (I) BOP, SRO         Loop 11 THOT T HOT Fails Low.
(TS) SRO 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                   (M) ALL             High vibration on #3 Turbine bearing which leads to a manual Reactor trip.
66                  (M) ALL             Failure of the Reactor to trip. (ATWS) SDAFW Pump trips.
7                   (M) ALL             Small Break LOCA.
(TS) SRO 88                  (C) RO               Phase Phase AA fails to automatically automatically actuate and several several valves fail to automatically close.
99                  (C) RO (C)                  Safety Safety Injection Injection fails to automatically actuate.
10 10                   (C) BOP (C)                  Control Control Room HVACHVAC Train A and Train Train B B fail to automatically automatically actuate. (HVE-1 (HVE-19A 9A fails to to start start and and HVE-1 HVE-166 fails to stop)
          * (N)ormal,   (R)eactivity,      (I)nstrument, (I)nstrument,   (C)omponent,       (M)ajor Appendix Appendix D   D                                                            NUREG-1021, Rev.
NUREG-1021,        Rev. 9,9, Supp.
Supp. 11
 
I Appendix D                                   Scenario Outline                             Form ES-D-1 HLC-08 NRC SCENARIO 4  


==SUMMARY==
==SUMMARY==
DESCRIPTION The crew will assume the watch with the plant at 50% RTP. The previous shift identified increased vibration on Main Turbine bearing #3 and has taken all necessary actions to inform station management.
DESCRIPTION    DESCRIPTION The crew will assume the watch with the plant at 50% 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 increase power to 75% and hold for Reactor Engineering instructions.
Service Water Booster Pump "A" is under clearance for Motor Coupling Alignment.
On cue from the Chief Examiner, Loop 11 T      -
Shift instructions are to increase power to 75% and hold for Reactor Engineering instructions.
1 T-HOT will fail low. The crew will respond lAW APP-003-A4, and remove the instrument from service using OWP- 028, T/DeltaT1. T/DeltaTl. The SRO will enter 3.3.1-1,, Condition E LCO 3.3.1-1                Efor for the failed instrument.
On cue from the Chief Examiner, Loop 1 T HOT will fail low. The crew will respond lAW APP-003-A4, and remove the instrument from service using OWP-028, T/DeltaT1.
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 header. 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.
The SRO will enter LCO 3.3.1-1 , Condition E for the failed instrument.
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).
On cue from the Chief Examiner, flooding will occur from the discharge of SW Pump "A" at the Service Water intake. The BOP will take immediate actions to split the North and South SW header. 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 psig. The crew should respond using AOP-019, MALFUNCTION OF RCS PRESSURE 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.
The RO should control PZR Heaters and Spray valves to maintain RCS pressure above 2205 psig. The crew should respond using AOP-019, MALFUNCTION OF RCS PRESSURE 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, Turbine bearing #3 vibration will increase to the alarm point and AOP-006, TURBINE ECCENTRICITY I VIBRATION, will be entered. High bearing vibrations will be reflected on adjacent bearings # 2 and #4. Vibrations will increase to 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.
On cue from the Chief Examiner, Turbine bearing #3 vibration will increase to the alarm point and AOP-006, TURBINE ECCENTRICITY ECCENTRICITY!I VIBRATION, will be entered. High bearing vibrations will be reflected on adjacent bearings #   #22 and #4. Vibrations will increase to 14 mils and actions in AOP-006 will require the SRO to direct a manual Reactor trip and enter PATH-1. PATH-i. When the crew attempts to trip the reactor, both Reactor Trip pushbuttons will fail and the SRO will enter FRP-S.i, RESPONSE TO NUCLEAR POWER GENERATION/ATWS. The SDAFW Pump will FRP-S.1, trip and remain unavailable for the remainder of the scenario. The AO will be successful in tripping the Reactor locally when directed.
The SDAFW Pump will trip and remain unavailable for the remainder of the scenario.
When the crew has transitioned to 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 will be successful, but three Phase A valves will fail to close and require the RO to manually close these valves from the RTGB. The Control Room HVAC System Train A and Train B will fail to automatically actuate, requiring the BOP to manually align HVAC for Emergency Pressurization Mode.
The AO will be successful in tripping the Reactor locally when directed.
The scenario can be terminated, at the Chief Examiners Examiner's discretion, after it is determined that SI termination criteria will not be met.
When the crew has transitioned to EPP-4, REACTOR TRIP RESPONSE and on cue from the Chief Examiner, a Small Break LOCA will be inserted.
Appendix D D                                                      NUREG-i021, NUREG-1021 , Rev. 9, Supp. 11
The LOCA will require a Safety Injection initiation and Phase A isolation, which will fail to automatically actuate. Manual operator actuation will be successful, but three Phase A valves will fail to close and require the RO to manually close these valves from the RTGB. The Control Room HVAC System Train A and Train B will fail to automatically actuate, requiring the BOP to manually align HVAC for Emergency Pressurization Mode. The scenario can be terminated, at the Chief Examiner's discretion, after it is determined that SI termination criteria will not be met. Appendix D NUREG-1021 , Rev. 9, Supp. 1 I Appendix 0 Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 4 SIMULATOR SETUP IC/SETUP
 
* IC-604, SCN: 006_Sim_4.
I Appendix 0D                                Scenario Outline                           Form ES-D-1 HLC-O8 NRC SCENARIO 4 SIMULATOR SETUP HLC-08 IC/SETUP
* Status board updated to reflect IC-4. PRE-LOADED EVENTS: The following events should occur on the reactor trip:
* IC-604, SCN:
* Event 6: Failure of the Reactor to trip. (A TWS) SDAFW Pump trips.
SON: 006_Sim_4.
* Event 8: Phase A valves CVC-204B, CCW-739 and SI-855 fail to close on SI actuation.
* 10-4.
Status board updated to reflect IC-4.
PRE-LOADED EVENTS:
The following events should occur on the reactor trip:
      *                                             (ATWS)
Event 6: Failure of the Reactor to trip. (A TWS) SDAFW Pump trips.
* Event 8: Phase A valves CVC-204B, CCW-739OOW-739 and SI-855 fail to close on SI actuation.
* Event 9: Safety Injection fails to automatically actuate.
* Event 9: Safety Injection fails to automatically actuate.
* Event 10: Control Room HVAC Train A and Train B fail to automatically actuate. EVENTSITRIGGERS INITIATED DURING THE SCENARIO:
* Event 10: Control Room HVAC Train A and Train B fail to automatically actuate.
EVENTSITRIGGERS INITIATED DURING THE SCENARIO:
* Event 1: Increase power to 75%.
* Event 1: Increase power to 75%.
* Event 2: Loop 1 T HOT fails low.
* Event 2: Loop 11 T THaT HOT fails low.
* Event 3: SW flooding from the South SW Header.
* Event 3: SW flooding from the South SW Header.
* Event 4: PZR PORV PCV-456 fails 70% open.
* Event 4: PZR PORV PCV-456 fails 70% open.
* Event 5: High vibration on #3 Turbine bearing which leads to a manual Reactor trip.
* Event 5: High vibration on #3 Turbine bearing which leads to a manual Reactor trip.
* Event 7: Small Break LOCA. EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED: OP-105, Section 8.4.2; OWP-028, T/Deita T 1; AOP-022, Section F; AOP-019; AOP-006; PATH-1, FRP-S.1; EPP-4; FRP-P.1; Supplement D. Appendix 0 NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # Page 4 of 31 ----------
* Event 7: Small Break LOCA.
EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
OP-i  05, Section 8.4.2; OWP-028, T/Deita OP-105,                                T/Delta T 1; AOP-022, Section F; AOP-0i AOP-019;9; AOP-006; PATH-i, PATH-1, FRP-S.1; EPP-4; FRP-P.i; FRP-P.1; Supplement D.
Appendix D 0                                                 NUREG-1021, Rev. 9, NUREG-102i,          9, Supp. 11
 
Appendix D                                 Operator Action                                     Form ES-D-2 Op Test No.:
Op      No.:        1    Scenario #
Scenario        44    Event ##
Event          1                Page Page   44 of   31 31
                  ~-                                         ----------                        ~---~I Event
 
== Description:==
 
Event
Event


== Description:==
== Description:==
Increase power Increase  power to 75%.
Time      ~  Position  I                            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.
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                &deg;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).
                                  **  In Automatic and T  TAVG AVG Control.
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  D                                                        NUREG-i NUREG-1 021, Rev. 9, Supp. 11


Increase power to 75%. Time Position I Applicant's Actions or Behavior BOOTH OPERATOR:
Appendix D  D                                  Operator Action                                        Form ES-D-2 Op Test No.:        1        Scenario #        4    Event #      1                  Page      5  of  31
Event 1 is normal power ascension to 75% lAW OP-105. 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. SRO Begins power ascension using OP-1 05 Section 8.4.2. SRO IF Reactor Engineering has not provided technical guidance, THEN determine the reactivity change required.
                ......;....-                                    ----------                            ~------~I Event
SRO Notify the Load Dispatcher that unit load will be increased.
 
RO T AVG is within 5 of of T REF. RO Monitor the highest operable PR and IR channels on NR-45. Steam Dump controls are set as follows: BOP
== Description:==
* Potentiometer set at 7.28 (1020 psig).
Increase power to 75%.
* In Automatic and T AVG Control. BOP FRVs in AUTO and S/Gs are being maintained at programmed level. BOP IF the EH Turbine Control is in OPER AUTO, THEN verify the Turbine Control is in IMP IN. (Preferred)
Time     III Position       I                           Applicant's Actions or Behavior Applicants For each power change greater than or equal to 10%, update the SRO power change log in the Reactor Startups/Shutdowns/Trips Book.
RO Check the ERFIS PDCIII Delta Flux monitoring program enabled. BOP Check the Turbine Lube Oil Cooler is maintaining the oil temperature leaving the bearings within the limits of OP-506. BOP The Bulk Auxiliary electrical loads should be on the Unit Auxiliary Transformer lAW OP-603. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ......;....-
While increasing power, Generator MVAR loading should be lAW the BOP Robinson Plant Voltage Support and Coordination Procedure.
Scenario # 4 Event # Page 5 of 31 ----------
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 amount of water to add to the RCS.
crE~wwill (The crew    will calculate - 2000 gallons of water needed    needed for the diliitinn to dilution    tn 75%power,basedon 7S% nnwr hisd nn Rods      Rnds at   .175 steps.
it ...;175 stRns Water Witr will be hc added.in 4-6 dilutions) ..
OBTAIN an independent cneckof .the volume of water. required.
permission from the CRSS OR the SSOto OBTAIN permissionJrom OBTAIN                                                SSO to dilute.
PLACE the RCS MAKEUP MODE selector switch in DILUTE.
Appendix D                                                               NUREG-1 021, Rev. 9, Supp. 1     1
 
Appendix D                                     Operator Action                                                         Form ES-D-2 Op Test Op Test No.:
No.:
Event
Event


== Description:==
== Description:==


Increase power to 75%. Time II Position I Applicant's Actions or Behavior SRO For each power change greater than or equal to 10%, update the power change log in the Reactor Startups/Shutdowns/Trips Book. BOP While increasing power, Generator MVAR loading should be lAW the Robinson Plant Voltage Support and Coordination Procedure.
Event
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 calculate
-2000 gallons of water needed for the dilution to 75%power,basedon Rods at ...;175 steps. Water will be added.in 4-6 dilutions)
.. OBTAIN an independent cneckof .the volume of water. required.
OBTAIN permissionJrom the CRSS OR the SSOto dilute. PLACE the RCS MAKEUP MODE selector switch in DILUTE. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -----Scenario # 4 Event # ......;....
____ Page 6 of ....,;3;.,;.1
___ -11 Event


== Description:==
== Description:==


Increase power to 75%. Time Position I Applicant's Actions or Behavior SETYIC-114, PRIMARY WTR TOTAUZERto the desired quantity.
1      Scenario #
IFdesired,THENPLACEFCV-114A, PRIMARY WTR FLOW DILUTE MODE, in MAN:ANDadjust Primary Water Flow rate using the UP/DOWN push buttons. . .... Momentarily PLACE the RCS MAKEUP SYSTEM switch to START. VERIFY proper operation VCT/HLDP TK DIV valve. IF any of thebelowconditions occur, THEN momentarily place the RCS MAKEUPSYSTEM switch in.the STOP position:
Scenario            4 Increase power to 75%.
* UnantiCipated Rod>Motion.
Increase Event ##
* Primary Water addition . exceeds the desired value. WHEN desired amount of PYV has been added, THENverify:
Event              1 _ _ _ _ Page
* FCV-t14A, PW TO BLENDER; doses.
                                                                        ......;....                    Page    66  of of ....,;3;.,;.1 31_ _ _-11 Time     fi
* FCY-114B, BLENDED MUTO YCT, closes.
            ~  Position   II                                    Applicants Actions or Behavior Applicant's SET YIC-1 14, PRIMARY WTR TOTAUZERto SETYIC-114,                                          TOTALIZER to the desired quantity.
* IF inAuto, THEN the operating Primary Water Pump stops.
IF desired, THEN PLACE FCV 1 14A, PRIMARY WTR FLOW IFdesired,THENPLACEFCV-114A,                                                         FLOW DILUTE MAN AND adjust Primary Water Flow rate using the MODE, in MAN:ANDadjust UP/DOWN push       pushbuttons.
* TheHCSMAKEUPSYSTEM is OFF. ... ... ... . .
buttons.                         .
* VERIFY FCV-114A,PRIMARY WTR FLOW DILUTE MODE is in AUTO.
Momentarily PLACE the RCS MAKEUP SYSTEM                           SYSTEM switch switch to START.
* PLACEtheHCSMAKEUP MODE switch in AUTO.
VERIFY proper operation ofLCV~115A,    of LCV-1 1 5A, VCT/HLDP TK DIV valve.
* Momentarily Pl.ACE RCS MAKEUP SYSTEM switch to START. ... . RECORD,inAUTO LOG,* as .indicated*
the below conditions occur, THEN momentarily place the IF any of thebelowconditions MAKEUP SYSTEM switch in.the RCS MAKEUPSYSTEM                                       in the STOP position:
by PRIMARY WATER TOTALlZER,.YIC-114 total amount of PW added during the dilution . .. MONITOR pqrameters for the.expected*change in reactivity AND informtheCRSS OR theSSO the results pfthedilutiort  
                                    ** UnantiCipated             Rod Motion.
.. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ...;....-Scenario # 4 Event # _2 _____ Page 7 of _3;:;.1:"'-
Unanticipated Rod>Motion.
__ Event
                                  *. Primary Water addition .exceeds the desired                  desired value.
desired amount of PYV WHEN desired                              PW has been    been added, THENverify:
THEN verify:
FCV-1 1 4A, PW
                                  *. FCV-t14A,               PW TO BLENDER;BLENDER, doses. closes.
                                  * . FCV-1 FCY-114B, 14B,      BLENDED BLENDED               MU MUTO TO    VCT, YCT,     closes.
                                  * . IF in  Auto, inAuto,       THEN     the       operating     Primary     Water Pump stops.
                                  *. TheHCSMAKEUPSYSTEM The RCS MAKEUP SYSTEM is is OFF.
RETURNt~eRCSMakeup.System.to*al.ltornatic:
RETURN        the RCS Makeup System to automatic:
                                    .*   VERIFY FCV-114A,PRIMARY FCV-1 14A, PRIMARY WTR FLOW DILUTE MODE is in AUTO.
                                    .*   PLACE the RCS MAKEUP MODE switch in AUTO.
PLACEtheHCSMAKEUP
                                    .* Momentarily PLACE      Pl.ACE RCS MAKEUP SYSTEM switch to START.
START.              ...               .
RECORD, in AUTO LOG,*
RECORD,inAUTO                   LOG, as .indicated* indicated by PRIMARYPRIMARY WATER TOTALIZER, TOTALlZER,.YIC-114   YIC-1    14  total   amount amount of PW      PW added duringduring the dilution. dilution .
MONITOR parameterspqrameters for the                 expected change in reactivity AND the.expected*change inform    the CRSS OR the informtheCRSS                     theSSOSSO the results of                the dilution.
pfthedilutiort Appendix D   D                                                                        NUREG-1 021, Rev. 9, Supp. 11 NUREG-1
 
Appendix D                                   Operator Action                                         Form ES-D-2 Op Test No.:       1 Scenario #       4       Event #     _22_ _ _ _ _ Page           7   of _3;:;.1:"'-_
31        _~1 Event


== Description:==
== Description:==
Loop 11 T  HOT Fails Low.
THOT Time      II  Position  i                              Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 2, Loop 1                                  1 T TH0T HOT failure.
EVENT INDICATIONS:
APP-003-A4; RC LOOPS I1T    T DEV HI/LO TAVG APP-003-A6; RCS HIILO APP-003-B4; RC LOOPS TAVG DEV tT (RED) pegged low.
TR-412 Pen 1, I1T 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 1          1 T HOT instrument out of THQT SRO service using OWP-028, T/LlT1. T/liTl.
Perform OWP-028, T/LlT1  T/tT1 actions to remove channel from service.
(APP-036-L1; (APP-036-L      1; will be received when Hagan Rack door is opened.)
The following alarms will be received when the bistables are tripped:
BOP
                                    *. APP-003-B6; OVERPOWER Ll            LT T
                                    *. APP-005-D5; OTLlT/OPLlT OThT/OPtT TURBINE RUNBACK ROD STOP
                                    *. APP-003-C6; OVERTEMP Ll          T T Review ITS for applicable LCOs:
                                    *. Table 3.3.1-1, #5, 6  6 - Condition E; Place channel in Trip within 6 hours.
SRO
                                    **  Table 3.3.2-1, # 1.f1 .f - Condition D; Place channel in Trip within 6 hours.
                                    **  Table 3.3.2-1, # 4.d & 6.b - Condition H; Verify interlock is in required state for existing unit condition within 1    1 hour.
Appendix D  D                                                            NUREG-1 021, Rev. 9, Supp. 1        1


Loop 1 T HOT Fails Low. Time II Position i Applicant's Actions or Behavior BOOTH OPERATOR:
Appendix D D                             Operator Action                                     Form ES-D-2 Op Test No.:
When directed by the Chief Examiner, insert Event 2, Loop 1 T HOT failure. EVENT INDICATIONS:
Scenario #           4 4     Event #     3
APP-003-A4; RC LOOPS I1T DEV APP-003-A6; RCS HIILO TAVG APP-003-B4; RC LOOPS TAVG DEV TR-412 Pen 1, I1T (RED) pegged low. TR-41211T Power fails low. RO Recognizes that instrument has failed and references APP-003-A4.
                                                            ~-------
Recommends removing the instrument from service. SRO Reviews, briefs and directs taking Loop 1 T HOT instrument out of service using OWP-028, T/LlT1. Perform OWP-028, T/LlT1 actions to remove channel from service. (APP-036-L 1; will be received when Hagan Rack door is opened.) BOP The following alarms will be received when the bistables are tripped:
Page   8   of 31
* APP-003-B6; OVERPOWER Ll T
                                                                                                ~~----~I Event
* APP-005-D5; OTLlT/OPLlT TURBINE RUNBACK ROD STOP
* APP-003-C6; OVERTEMP Ll T Review ITS for applicable LCOs:
* Table 3.3.1-1, #5, 6 -Condition E; Place channel in Trip within 6 hours. SRO
* Table 3.3.2-1, # 1.f -Condition D; Place channel in Trip within 6 hours.
* Table 3.3.2-1, # 4.d & 6.b -Condition H; Verify interlock is in required state for existing unit condition within 1 hour. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # --4 Event # 3 Page 8 of 31 Event


== Description:==
== Description:==
SW flooding from the South SW Header.
Time      I    Position  II                          Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 3, SW Flooding in the Intake Bay from the South SW Header.
EVENT INDICATIONS:
APP-008-F7; SOUTH SW HDR LO PRESS APP-008-F8; NORTH SW HDR LO PRESS APP-008-E7; S SW HDR STRAINER PIT HI LEVEL APP-008-E8; N SW HDR STRAINER PIT HI LEVEL APP-002-A8; HVH-1 WTR OUTLET LO FLOW APP-002-B8; HVH-2 WTR OUTLET LO FLOW APP-002-C8; HVH-3 WTR OUTLET LO FLOW APP-002-D8; HVH-4 WTR OUTLET LO FLOW APP-008-D7; SSWS SW HDR STRAINER PIT HI-HI LVL (Delayed)
APP-008-D8; N  N SW HDR STRAINER PIT HI-HI LVL (Delayed)
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 Action Step:
BOP          CheckAPP~008-E7 Check  APP-008-E7 AND APP-008-E8            Extinguished. (NO)
APP-008-E8Extinguished.
                                  **          valves V6-12B and V6-12C Closes valves.V6-12B            V6-12C..
SRO          Transitions to Section F.
RO/BO P RO/BOP        Makes PA announcement for entry into AOP-022.
Evaluate Control Room Indications and perform local inspections to C rew Crew determine source of leakage.
Appendix D                                                            NUREG-1021, Rev. 9, Supp. 1  1


SW flooding from the South SW Header. Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR:
Appendix D  D                            Operator Action Operator    Action                                        Form ES-D-2 Form  ES-D-2 Op Test Op Test No.:
When directed by the Chief Examiner, insert Event 3, SW Flooding in the Intake Bay from the South SW Header. EVENT INDICATIONS:
No.:       1    Scenario ##
APP-008-F7; SOUTH SW HDR LO PRESS APP-008-F8; NORTH SW HDR LO PRESS APP-008-E7; S SW HDR STRAINER PIT HI LEVEL APP-008-E8; N SW HDR STRAINER PIT HI LEVEL APP-002-A8; HVH-1 WTR OUTLET LO FLOW APP-002-B8; HVH-2 WTR OUTLET LO FLOW APP-002-C8; HVH-3 WTR OUTLET LO FLOW APP-002-D8; HVH-4 WTR OUTLET LO FLOW APP-008-D7; SSW HDR STRAINER PIT HI-HI LVL (Delayed)
Scenario        44      Event ##
APP-008-D8; N SW HDR STRAINER PIT HI-HI LVL (Delayed)
Event        33                Page Page      99    of of    31 31
SW Booster Pump "B" trips due to low suction pressure.
                --                                           ~--------                             --------~I Event
BOP Recognizes a Loss of Service Water has occurred and performs 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 Action Step: BOP AND APP-008-E8Extinguished. (NO)
* Closes valves.V6-12B and V6-12C . SRO Transitions to Section F. RO/BOP Makes PA announcement for entry into AOP-022. Crew Evaluate Control Room Indications and perform local inspections to determine source of leakage. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --3 Page 9 of 31 Event


== Description:==
== Description:==


SW flooding from the South SW Header. Time I Position i Applicant's Actions or Behavior BOOTH OPERATOR:
Event
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" Running. (YES)
* SW Pump "D" Running. (NO, will start pump) BOP 0 Will receive APP-008-E4, ES & E6 alarms
* SW Pump "A" Stopped. (NO, will stop pump)
* SW Pump "B" Stopped. (YES) Evaluate SW Header Pressure:
SRO/BOP
* Check South SW pressure Decreasing. (YES)
* Check North SW pressure Stable or Increasing. (YES) NOTE: With Service Water Pumps "A" AND "B" isolated, EDG "A" is inoperable.
ITS 3.S.1 requires SR 3.S.1.1 to be performed within 1 hour. With low flow to all CV HVH units, LCO 3.6.6 applies for both CV Cooling Trains inoperable.
The crew may start SWBP "B" using APP-002-ASIBSICSIDS guidance.
BOP Close V6-12A (APP-008-E4/ES/E6/F8 will clear) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --.;...-Scenario # 4 Event # ____ Page 10 of ...,;3;;..;,1
___ -11 Event


== Description:==
== Description:==
SW flooding SW  flooding from from the the South South SW SW Header.
Header.
Time      I  Position Position  i                              Applicants Actions or Behavior Applicant's            Behavior 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)
BOP 0o  Will receive APP-008-E4, ES      E5 & E6 alarms
                                  *. SW Pump "A"  A Stopped. (NO, will stop pump)
                                  **  SW Pump "B"  B Stopped. (YES)
Evaluate SW Header Pressure:
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.S.1 requires SR 3.8.1.1 3.S.1.1 to be performed within 11 hour.
With low flow to all CV HVH 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-ASIBSICSIDS guidance.
BOP BOP      Close V6-12A (APP-008-E41E51E6/F8 (APP-008-E4/ES/E6/F8 will clear)
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 No.:        1 Scenario #      4    Event #      3 ____
_3~                Page    10          31 _ _ _-11 of ...,;3;;..;,1 Event


SW flooding from the South SW Header. Time II Position I Applicant's Actions or Behavior BOP Verify SW-S51 and SW-S57 closed. BOOTH OPERATOR:
== Description:==
When requested, report that SW-851 and SW-857 are closed. (Not modeled on simulator)
SW flooding from the South SW Header.
SRO/BOP Check Flooding status stopped. (YES) BOOTH OPERATOR:
Time     II Position I                           Applicants Actions or Behavior Applicant's BOP               SW-851 and SW-S57 Verify SW-S51         SW-857 closed.
Report water is no longer gushing up above the South SW header. BOP Check North SW header pressure>
BOOTH OPERATOR: When requested, report that SW-851 and SW-857 are closed. (Not modeled on simulator)
40 psig. (YES) SRO Remove Control Power fuses from breakers for SW Pumps "A" & "B". BOOTH OPERATOR:
SRO/BOP     Check Flooding status stopped. (YES)
Rack out the breakers for Service Water Pumps "A" and "B" on 480V Bus E-1. When requested, report that leak is from the connection of SW Pump "A" and the 30 inch header. Determine if a SW Booster Pump should be started: SRO/BOP
BOOTH OPERATOR:             Report water is no longer gushing up above the South SW header.
* Check SW Booster pumps all stopped. (YES)
BOP       Check North SW header pressure> 40 psig. (YES)
* Start one SW Booster Pump. (APP-002-AS/BS/CS/DS clear). BOP Check any CW Pump running. (YES) Determine if adequate seal water is available to CW:
SRO       Remove Control Power fuses from breakers for SW Pumps "A"                 A & "B".
* APP-00S-E4, CW PMP A SEAL WTR LOST extinguished.
B.
BOOTH OPERATOR:             Rack out the breakers for Service Water Pumps "A"         A and "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)
                                *                                       (APP-002-A81B81C8/D8 clear).
Start one SW Booster Pump. (APP-002-AS/BS/CS/DS BOP       Check any CW Pump running. (YES)
Determine if adequate seal water is available to CW:
* APP-008-E4, APP-00S-E4, CW PMP A SEAL WTR LOST extinguished.
BOP
BOP
* APP-00S-E5, CW PMP B SEAL WTR LOST extinguished.
                                  **  APP-008-E5, APP-00S-E5, CW PMP B SEAL WTR LOST extinguished.
* APP-00S-E6, CW PMP C SEAL WTR LOST extinguished. (YES, ALL extinguished)
                                  **   APP-008-E6, CW PMP C SEAL WTR LOST extinguished.
Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -:...-Scenario # 4 Event # 3 Page 11 of 31 Event
APP-00S-E6, (YES, ALL extinguished)
Appendix D                                                         NUREG-1 021, Rev. 9, Supp. 1           1
 
Appendix D Appendix     D                             Operator Action Operator   Action                                           Form ES-D-2 Form   ES-D-2 Op Test Op Test No.:
No.:       1    Scenario Scenario ##      44    Event Event ##      33                  Page Page     11 11   of of 31 31
                  -:...-                                      ~--------                              ~~----~I Event


== Description:==
== Description:==


SW flooding from the South SW Header. Time II Position II Applicant's Actions or Behavior Determine maximum allowable CCW temperature as follows: RO
Event
* Check RCS temperature 350 degrees F. (NO)
 
* Maintain CCW Heat Exchanger outlet temperature indicated on TI-607 less than or equal to 105 degrees F. Perform the following:
== Description:==
* Inspect the area of the leak. SRO
SW flooding SW             from the flooding from the South South SW SW Header.
* Report findings to the SSO.
Header.
* Identify and isolate the source of the SW leak. SRO Contact Maintenance to install temporary pumps to dewater Service Water pits. Contact Engineering to perform the following:
Time Time     III Position III                            Applicant's Actions Applicants          or Behavior Actions or Determine     maximum allowable CCW temperature as follows:
Determine maximum RO
                                  .* Check RCS temperature ~ 350 degrees        degrees F. (NO)
                                  .* Maintain CCW Heat  Heat Exchanger outlet temperature indicated on TI-607 less than or equal to 105      105 degrees F.
Perform the following:
                                  .* Inspect the area of the leak.
SRO
SRO
* Evaluate operability of equipment affected by flooding.
                                  .*  Report findings to the SSO.
* Provide corrective actions for flooding.
                                  .*  Identify and isolate the source of the SW leak.
Contact Maintenance to install temporary pumps to dewater Service SRO Water pits.
Contact Engineering to perform the following:
SRO              *. Evaluate operability of equipment affected by flooding.
                                    *. Provide corrective actions for flooding.
Refer to ITS for any applicable LCOs.
Refer to ITS for any applicable LCOs.
* LCO 3.6.6, Condition D -Restore one containment cooling train to OPERABLE status within 72 hours. (Will only be in this LCO until a SW Booster Pump is started) SRO
                                  *. LCO 3.6.6, Condition D - Restore one containment cooling train to OPERABLE status within 72 hours. (Will only be in this LCO until a SW Booster Pump is started)
* LCO 3.7.7, Condition A -Restore SWS train to OPERABLE status within 72 hours. (This LCO has already been entered due to the SWBP being out of service)
SRO             *. LCO 3.7.7, Condition A - Restore SWS train to OPERABLE status within 72 hours. (This LCO has already been entered due to the SWBP being out of service)
* LCO 3.8.1, Condition B -Perform SR 3.8.1.1 for the offsite circuit within 1 hour. (Cascaded LCO from SW NOT available to EDG "A") SRO Implement the EALs. SRO Return to procedure and step in effect. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --:...._ Scenario # 4 Event # _4..:..-____ Page 12 of _3 ... 1 ___ -i1 Event
                                    *. LCO 3.8.1, Condition B - Perform SR 3.8.1.1 3.8.1 .1 for the offsite circuit within 11 hour. (Cascaded LCO from SW NOT available A
to EDG "A")
SRO         Implement the EALs.
SRO         Return to procedure and step in effect.
Appendix D   D                                                            NUREG-1 021, NUREG-1            Rev. 9, 021, Rev. 9, Supp.
Supp. 11
 
Appendix D Appendix     D                               Operator Action Operator    Action                                          Form ES-D-2 Form   ES-D-2 Op Test Op Test No.:
No.:      --:...._
1      Scenario ##
Scenario          44    Event Event ##      4
_4..:..-_  _ _ _ Page  Page     12 12 of  31 of _3...1_ _ _-i1 Event


== Description:==
== Description:==


PZR PORV PCV-4S6 fails 70% open. Time Position II Applicant's Actions or Behavior BOOTH OPERATOR:
Event
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 PORVISAFETY 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 PRESS RO Recognizes PORV is OPEN and takes Immediate Actions of AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL. SRO Enters AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL. Immediate Action Step:** Determine.if*PZR PORVs should be CLOSED:* RO
* Check PZR Pressure less than 2335PSIG. (YES)
* Verify both PZR PORVs CLOSED. (NO) IF anyPZR PORVcan NOT be CLOSED,THEN close its PORV BLOCK valve. . Immediate Acti()nStep:
RO ControlHeaters and Spray valves torestore.HCS Pressure to desired corttrolband; 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 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ....;...-Scenario # 4 Event # 4 Page 13 of 31 Event


== Description:==
== Description:==
PZR PORV PZR    PORV PCV-456 PCV-4S6 fails fails 70%
70% open.
open.
Time Time      ~  Position Position    II                              Applicant's Actions Applicants            or Behavior Actions or BOOTH OPERATOR: When directed          directed by the Chief Examiner, insert Event 4, PZR PORV PCV-456 fails 70%  70% OPEN.
OPEN.
INDICATIONS:
EVENT INDICATIONS:
APP-003-C3;PRT HI  HI PRESS PORVISAFETY VLV OPEN APP-003-D6;PZR PORV/SAFETY APP-003-E6;PZR PORV LN HI TEMP APP-003-F6;PZR SAFETY VLV LINE HI TEMP APP-003-D8;PZR CONTROL HI/LO    HIILO PRESS Recognizes PORV is OPEN and takes Immediate Actions of AOP                      AOP-RO 019, MALFUNCTION OF RCS PRESSURE                          CONTROL.
SRO          Enters AOP-01 AOP-019,  9, MALFUNCTION OF RCS PRESSURE CONTROL.
Immediate Action Step:** Step:
Determine.if*PZR Determine if PZR PORVs should be CLOSED:*        CLOSED:
RO              **  Check PZRPZR Pressure Pressure less              2335 PSIG. (YES) less than 2335PSIG.
                                    *. Verify both PZR PORVs CLOSED. (NO)
IF anyPZR      PORV can NOT any PZR PORVcan                        CLOSED, THEN close its PORV NOT be CLOSED,THEN BLOCK valve.                                    .
Immediate      Action Step:
Immediate Acti()nStep:
RO RO        ControlHeaters Control Heaters and                          to restore RCS Pressure to desired valves torestore.HCS and Spray valves corttrolband; control band.
RO RO        Check PZRPZR Pressure      under operator control.
Pressure under                    control. (YES)
RO RO        Check Check PC-444J, PC-444J, PZR      PRESSURE operating PZR PRESSURE              operating in    AUTO. (YES) in AUTO.  (YES)
RO RO        Check Check RCS                    required for pressure << required RCS pressure                      for current current plant                  (YES) conditions. (YES) plant conditions.
Appendix Appendix D  D                                                              NUREG-1 021, NUREG-1            Rev. 9, 021, Rev.      Supp. 11 9, Supp.


PZR PORV PCV-456 fails 70% open. Time II Position Applicant's Actions or Behavior Continuous.
Appendix D  D                            Operator Action Operator                                                  Form ES-D-2 Form  ES-D-2 Op Test Op Test No.:
Action<Step:
No.:       1 Scenario ##
.. RO Check PZR pressure less than 2205 PSIG. IF pressure decreases to <:: 2205 PSIG, THEN restore pressure within 2. hours Or be in MODE 2 within 6 hours. RO Check BOTH PZR Spray valves CLOSED. (YES) RO Check CVC-311, AUX PZR SPRAY valve CLOSED. (YES) RO Check APP-003-F8, PZR LO LVL HTR OFF & L TDN SECURE extinguished. (YES) Determine Heater Capacity:
Scenario        44    Event ##
SRO/RO
Event        44                Page Page      13 13    of of  31 31
* Contact Maintenance and Engineering to check PZR Heater capacity.
                                                              ~--------                              ~------~I Event
* 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 Implement The EALs. SRO Contact I&C To Make Repairs To The PZR Pressure Control System. Review ITS For Applicable LCOs: SRO
* LCO 3.4.11, Condition B, Close Block valve within 1 hour AND
* Remove power within 1 hour. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 4 Event # 5&6 Page 14 of 31 High vibration on #3 Turbine bearing which leads to a manual Reactor trip. Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips. Time Position II Applicant's Actions or Behavior BOOTH OPERATOR:
When directed by the Chief Examiner, insert Event 5, Turbine bearing #3 vibrations will increase above the alarm setpoint and require manual Reactor and Turbine trips. EVENT INDICATIONS:
APP-OOS-AS; TURBINE SUPERVISORY INSTRUMENT (Will reflash as each bearing vibration increases greater than 7 mils) Turbine Generator Supervisory Recorder and Vibration module bearings in alarm. BOP Recognizes alarm, monitors vibration recorder and references APP-OOB-AB. BOP
* Verify lube oil cooler discharge temperature between 115-125 degrees F. (YES) BOP
* If turbine bearing temperature is > 225 degrees F, trip the turbine. (NO) SRO Enters AOP-006, TURBINE ECCENTRICITY
/ VIBRATION.
BOP Check Turbine Speed 600 RPM. (NO, Go To Step 4) Continuous Action . Step: BOP Check Bearing Vibration Levels on theTURBINE GENERATOR SUPERVISORY RECORDER less than 14.0 MILS. (YES) NOTE: At this time, vibration level is less than 14 mils but Step 4 RNO will be implemented as vibration increases.
Attempt to decrease or stabilize vibration by at least one of the following methods: BOP Vary load (MW and/or VARS) or turbine speed. *
* Vary Hydrogen Side or Air Side Seal Oil temperatures.
Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: .....;...-
Event
Event


== Description:==
== Description:==
PZR PORV PZR    PORV PCV-456 PCV-456 fails fails 70%
70% open.
open.
Time      II  Position Position  ~                            Applicants Actions or Behavior Applicant's            Behavior Continuous Action<Step:
Continuous. Action Step:
Check PZR pressure less than  than 2205 PSIG.
PSIG.
RO IF pressure decreases to <::< 2205 PSIG, THEN restore IF                                                      restore pressure within hours Or be in 2 hours
: 2.              in MODE 2 within 6 hours.
RO        Check BOTH PZR Spray valves CLOSED. (YES)
RO                CVC-31 1 ,AUX Check CVC-311,      AUX PZR SPRAY valve CLOSED. (YES)
Check APP-003-F8, PZR LO LVL HTR OFF & LLTDN              TDN 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        Implement The EALs.
SRO        Contact I&C To Make Repairs To The PZR Pressure Control System.
Review ITS ITS For Applicable LCOs:
                                  **  LCO 3.4.11, Condition Condition B, B, Close Block valve within 11 hourhour SRO SRO AND
                                  ** Remove power within 11 hour. hour.
Appendix Appendix D  D                                                          NUREG-1 NUREG-1 021, 021, Rev.
Rev. 9, 9, Supp.
Supp. 11


Operator Action Form ES-D-2 Scenario # 4 Event # _5;;;...;;.;.&..;;.6
Appendix D  D                                    Operator Action Operator                                                                  Form Form ES-D-2 ES-D-2 Op Test Op Test No.:
___ Page 15 of _3_1 ___ --11 High vibration on #3 Turbine bearing which leads to a manual Reactor trip. Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips. Time II Position i Applicant's Actions or Behavior
No.:       1      Scenario ##
* Vary Turbine Lube Oil cooler discharge temperature.
Scenario              44      Event ##
* Increase Exciter Air discharge temperature.
Event            5&6 5&6                        Page Page        14 14     of of   31 31
BOOTH OPERATOR:
                  ~-                                                      ~~------                                           ~~----~I Event
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 Bearil'1g.Vibration LevelsoritheTURBINEGENt=RATOR SUPERVISORY RECORDER less than 14;0 MILS. (NO) SRO IF vibration is*felt in theControlRoom,THEN perform one of the following:
* IF the REACTORTRIP FROM TURBBLOCK P-7 permissive light is extinguished, THEN trip the Heactbr AND GoTo PATH-1. (YES) SRO Directs the RO to manually trip the Reactor and perform the immediate actions of PATH-1. Immediate J\,ction*
Step: Check REACTOR TRI Pasfollows:
* Reactor trip main and bypass breakers OPEN. (NO) RO
* Rod Position indication ZERO. (NO)
* Rod Bottom Lights I LLUMINATEO> (NO)
* Neutron Flux DECREASING. (NO) Appendix D NUREG-1021 , Rev. 9, Supp. 1 Appendix D Op Test No.: --=--Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 4 Event # 5 & 6 Page 16 of 31 ---------
Event
High vibration on #3 Turbine bearing which leads to a manual Reactor trip. Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips. Time I Position II Applicant's Actions or Behavior Immediate Action Step: Perform the following:
 
* Depress both Reactor Trip*pushbuttons.
== Description:==
* If Reactor Trip breakerswillnot.open,.
High vibration High  vibration on  on #3 #3 Turbine Turbine bearing bearing which which leads leads to  to aa manual manual Reactor Reactor trip.
then perform the follQWing:
trip.
RO/SRO f nsert.control.
Failure of Failure    of the the Reactor Reactor to  to trip.
rods. *
trip. (ATWS)
* Dispatch an operator to theMG Set Room to trip Reactor Trip Breakers "A" and "B" AND MGSet Generator Circuit Breakers "A" and "B".
(ATWS) SDAFW  SDAFW PumpPump Trips.Trips.
* Dispatch an operator to 480V Busses 2B and 3 to trip Rod Drive MG SetBrs.akers "A".and "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.
Time      ~  Position    II                                      Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 5, Turbine bearing #3 vibrations will increase above the alarm setpoint and require manual Reactor and Turbine trips.
Immediate Action Step: Check Turbine Trip as follows: BOP
EVENT INDICATIONS:
* Both Turbine Stop valves closed. (NO) OR
APP-008-A8; TURBINE SUPERVISORY INSTRUMENT (Will reflash as each bearing vibration increases APP-OOS-AS; greater than 7 mils)
* All Governor (NO) Perform the following:
Turbine Generator Supervisory Recorder and Vibration module bearings in alarm.
SOP          Recognizes alarm, monitors vibration recorder and references APP-BOP 008-A8.
OOB-AB.
SOP BOP                  **    Verify lube oil cooler discharge temperature between 115-                          1 15 125 degrees F. (YES)
BOP                  **    If turbine bearing temperature is > 225 degrees F, trip the turbine. (NO)
SRO          Enters AOP-006, TURBINE ECCENTRICITY / VIBRATION.
BOP          Check Turbine Speed ~                < 600 RPM. (NO, Go To Step 4)
Continuous Action .Step:
BOP r,(
                      )I-.    %t........I Check BearingID...  ... I Vibration ILevels
                                ,IItiIDt1IIIIU VIUILIIJII LVII IJIILIIt
                                                                              ...I... L. ri ,r,rI,ir on theTURBINE I IJIEIIJI GENERATOR
                                                                                                                    -rIr-r IJIEI-k I iri
: a. ifl,fl ,I flfl n, nrfl flnnn I                      .1      -J  &#xa3;      *11  fl  IS SUPERVISORY RECORDER urizi-ivicjriy              r-itLur1Lnz11 iess    less man than 14.0        MILS. (Y) 14.U IVIIL.        (YES)
NOTE:                          At this time, vibration level is less than 14                        14 mils but Step 4 RNO will be implemented as vibration increases.
Attempt to decreasedecrease or stabilize vibration by              by at least least one of the following methods:
SOP BOP
                                        **    Vary loadload (MW and/or and/or VARS) or turbine speed.
                                        **    Vary Hydrogen Hydrogen Side or Air Side        Side Seal Seal Oil  Oil temperatures.
temperatures.
Appendix Appendix D  D                                                                        NUREG-1 NUREG-1 021,    021, Rev.
Rev. 9,  9, Supp.
Supp. 11
 
Appendix D  D                                  Operator Action                                                     Form ES-D-2 Op Test No.:
Op      No.:        1
                  .....;...- Scenario #         44      Event #         5 & 6 _ _ _ Page
_5;;;...;;.;.&..;;.6                    15 15 of _3_1 31_ _ _--11 Event
 
== Description:==
 
== Description:==
High vibration on #3 Turbine bearing which leads High                                                            leads to to a manual Reactor trip.
the Reactor to Failure of the Failure                    to trip.
trip. (ATWS) SDAFW Pump            Pump Trips.
Trips.
Time      III Position    Ii                                Applicant's Actions or Behavior Aoclicants
                                      . Vary Turbine Lube Oil cooler discharge temperature.
                                      . Increase Exciter Air discharge temperature.
BOOTH OPERATOR: As aa 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 Check    Bearil'1g.Vibration      Levels on the TURBINE GENERATOR Vibration LevelsoritheTURBINEGENt=RATOR SUPERVISORY RECORDER less than 14;0                            14.0 MILS.
MILS. (NO)
SRO              vibration is*felt IF vibration                the Control Room, THEN perform one of the is felt in theControlRoom,THEN following:
                                      *.            REACTOR TRIP FROM IF the REACTORTRIP                                TURB BLOCK P-7 permissive FROM TURBBLOCK light is extinguished, THEN trip the Heactbr light                                                  Reactor AND GoToGo To PATH-
: 1. (YES)
Directs the RO to manually trip the Reactor and perform the immediate SRO actions of PATH-1.
PATH-i.
Immediate J\,ction*
Action Step:
Check REACTOR TRI          TRIP    as follows:
Pasfollows:
RO
                                      **  Reactor trip main and bypass breakers OPEN. (NO)
                                      **  Rod Position indication ZERO.              ZERO. (NO)
                                      **  Rod Bottom Lights Lights IILLUMINATED.
LLUMINATEO> (NO)
                                      **  Neutron Flux DECREASING. (NO)
Appendix D                                                                                NUREG-1021      Rev. 9, Supp. 11 NUREG-1021,, Rev.
 
Appendix D                                  Operator Action                                    Form ES-D-2 Op Test No.:        1
                --=--   Scenario #        4      Event #
5&6
                                                                  &              Page    16 of  31
                                                                                                ~~----~
Event
 
== Description:==
High vibration on #3 Turbine bearing which leads to a manual Reactor trip.
Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.
Time     I   Position II                             Applicants Actions or Behavior Applicant's Immediate Action Step:
Perform the following:
                                  **                              Trip pushbuttons.
Depress both Reactor Trip*pushbuttons.
* breakers will not open, then perform the If Reactor Trip breakerswillnot.open,.
following:
follQWing:
RO/SRO
                                      **  finsert nsert.control.
coritroi rods.
rous.
                                      **   Dispatch an operator to  to theMG the MG Set Room to trip Reactor Breakers "A" Trip Breakers    A and "B" B AND MGSet MG Set Generator Circuit Breakers "A"A and "B".
B.
                                      **  Dispatch an operator to 480V Busses  Busses 2B and 3 to trip Rod Set Breakers "A".and Drive MG SetBrs.akers         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       RTB5 and MG set breakers.
Immediate Action Step:
Check Turbine Trip Trip as follows:
BOP             **   Both Turbine Stop valves closed. (NO)
Both OR
                                  **                  valve~closed.
All Governor valves    closed. (NO)
Perform the following:
BOP
BOP
* Manually trip the Turbine by simultaneously depressing the THINK and TURBINE TRIP Pushbuttons BOP Verify All AFW Pumps running. (NO, SDAFW Pump will NOT start and APP-007-F5, SD AFW PMP LO DISCH PRESS TRIP will illuminate)
                                    **  Manually trip the Turbine by simultaneously depressing the THINK and TURBINE TRIP Pushbuttons Verify All AFW Pumps running. (NO, SDAFW Pump will NOT start and BOP APP-007-F5, SD AFW PMP LO DISCH PRESS TRIP will illuminate)
Appendix D NUREG-1021 , Rev. 9, Supp. 1 Appendix D Op Test No.: --:...-Event
Appendix D D                                                          NUREG-1021, NUREG-1021 , Rev. 9, Supp. 1  1
 
Appendix D                                  Operator Action                                    Form ES-D-2 Op Test No.:      1
                --:...- Scenario #          4    Event #      5&6 5&6              Page    17 of  31
                                                              --~------                          ~------~I Event
 
== Description:==
High vibration on #3 Turbine bearing which leads to a manual Reactor trip.
Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.
Time      II  Position  II                            Applicants Applicant's Actions or Behavior Verify Charging flowpath established as follows:
RO              **    CVC-310B, LOOP 2 COLD LEG CHG OPEN.
                                    *. HIC-1 21, Charging Flow Controller demand at 0%.
HIC-121, RO          Verify Two Charging Pumps running at full speed.
RO          Verify Boric Acid Pump aligned for blend running.
RO          Verify MOV-3S0, MOV-350, BA TO CHARGING PMP SUCT open.
RO          Checkflowon Check              Fl-hO, BORIC ACID BYPASS FLOW indicated.
flow on FI-110, RO          Verify Charging Flow to RCS on FI-122A  Fl-i 22A BOP        Verify CONTAINMENT VENTILATION ISOLATION initiated.
NOTE:                        It is expected that if the CV Ventilation Signal has not been initiated, the operator will take R-11  R-i1 or R-12 high voltage pushbutton to OFF and return to ON to initiate the signal. This can be verified by the 2 Amber lights ILLUMINATED below the Radiation Monitoring System panel labeled "CV          CV Ventilation Isolation Signal Relay V-1  V-i and V-2.
V-2."
Check SI initiated. (NO)
RO          IF an SI Signal occurs, THEN verify auto start of all SI equipment using Supplement L while continuing with this procedure.
Check if the following trips have occurred:
RO/BOP              **  Reactor Trip. (YES)
                                      **  Turbine Trip. (YES)
Appendix D                                                            NUREG-1021,, Rev. 9, Supp. 11 NUREG-1021
 
Appendix D                                        Operator Action                                                            Form ES-D-2 Op Test No.:        1 Scenario #            4          Event #    _5;;..&;;;.;....;.6 5 & 6 _ _ _ Page                      18    of _3.;,..1 31_ _ _---lI Event
 
== Description:==
High vibration on #3 Turbine bearing which leads to a manual Reactor trip.
Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.
Time      i  Position      i                                      ADDlicants Actions or Behavior Applicant's Continuous Action Step:
Check if Reactor is subcritical:
RO                **  Check Power.
Check          Power Range indicatiohless indication less than 5%. (YES)
                                      **  ,*s I_
Check I I Lr1ecIc Intermediate iritermeuiae Range I              fl i-lange indicationirioicauori negative
                                                                                                                  . . t. .In,s, I %
riegaiive SUR.
UM. (YES,  IY ,
t.
Go O
To Step.
Step 24)
RO          Check IRPI has less than two rods stuck out. (YES)
Stop the RCS Boration:
* Verify MOV-35G MOV-350 closed.
* Verify control switch for Boric Acid pump aligned for blend in AUTO.
RO                **  Check emergency boration performed using MOV-35G                            MOV-350 flowpath.
* Notify Engineering to evaluate:
                                                    **      RCP Bearing temperatures
                                                    **      No. 1 seal leakoff temperatures and flowrates.
No.1                                                     flowrates .
Check emergency boration performed using RWST flowpath and it is RO          desired to align Charging Pump suction to the VCT. (NO, Go To Step 25.i)
RO          Control Charging Pump speed to control PZR Level.
Reset SPDS and Initiate monitoring of Critical Safety Function Status RO Trees.
SRO          Return to procedure and step in effect.
Appendix D                                                                                     NUREG-1021, Rev. 9, Supp. 11 NUREG-1G21,
 
Appendix D                                Operator Action                                                    Form ES-D-2 Op Test No.:       1
                --:....- Scenario #      4      Event #          5 & 6 _ _ _ Page
                                                              .....;5;;...;&;;;..;;..6                19        31 _ _ _-i1 of _3;;.,;1 Event


== Description:==
== Description:==
High vibration on #3 Turbine bearing which leads to a manual Reactor trip.
Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.
Time      i  Position  II                            Applicants Actions or Behavior Applicant's SRO        Directs entry at the beginning of PATH-1.                PATH-i.
IMMEDIATE ACTION STEP:
RO Reactor Tripped. (YES)
IMMEDIATE ACTION STEP:
BOP Turbine Tripped. (YES)
IMMEDIATE ACTION STEP:
BOP AND E-2 energized. (YES)
E-1 AND*E-2 IMMEDIATE ACTION STEP:
RO            0o  SI Initiated... (NO)
Sllnitiated 0o  SI Initiation Required. (NO)
Sllnitiation RO        Verify two Charging Pumps running. (YES)
SRO        Transition to EPP-4, REACTOR TRIP RESPONSE.
Continuous Action Step:
procedure exit is warranted:
Determine if procedure                        warranted SRO            **            affack on .RNPsite Check attack          RNP site in progress. (NO)
                                  **  Check a total loss of SW .OR                    OR Loss Loss of Lake Robinson Dam in progress. *(NO, integrity inprogress.            (NO, Go to Step 2)
Continuous Action Step:
Check SI signal initiated. (NO, Go                  Go to Step 4)
RO IF SI initiation occurs during this procedure, THEN Go to PATH-1,                PATH-i, Point A. (Page 21 Entry Point.A.            21))
Appendix D                                                                              NUREG-i 021, Rev. 9, Supp. 1i NUREG-1


Operator Action Form ES-D-2 Scenario # 4 Event # 5&6 Page 17 of 31 High vibration on #3 Turbine bearing which leads to a manual Reactor trip. Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips. Time II Position II Applicant's Actions or Behavior Verify Charging flowpath established as follows: RO
Appendix D                                  Operator Action                                                       Form ES-D-2 Op Test No.:        1 Scenario #       4       Event #         5 & 6 _ _ _ Page
* CVC-310B, LOOP 2 COLD LEG CHG OPEN.
                                                                ...,;5;;..&;;.;..;;;.6                    20            31 _ _ _-l of ...,;3;;..;.1 1
* HIC-121, Charging Flow Controller demand at 0%. RO Verify Two Charging Pumps running at full speed. RO Verify Boric Acid Pump aligned for blend running. RO Verify MOV-3S0, BA TO CHARGING PMP SUCT open. RO Check flow on FI-110, BORIC ACID BYPASS FLOW indicated.
RO Verify Charging Flow to RCS on FI-122A BOP Verify CONTAINMENT VENTILATION ISOLATION initiated.
NOTE: It is expected that if the CV Ventilation Signal has not been initiated, the operator will take R-11 or R-12 high voltage pushbutton to OFF and return to ON to initiate the signal. This can be verified by the 2 Amber lights ILLUMINATED below the Radiation Monitoring System panel labeled "CV Ventilation Isolation Signal Relay V-1 and V-2." Check SI initiated. (NO) RO IF an SI Signal occurs, THEN verify auto start of all SI equipment using Supplement L while continuing with this procedure.
Check if the following trips have occurred:
RO/BOP
* Reactor Trip. (YES)
* Turbine Trip. (YES) Appendix D NUREG-1021 , Rev. 9, Supp. 1 Appendix D Op Test No.: ......;...-
Event
Event


== Description:==
== Description:==
High vibration on #3 Turbine bearing which leads to a manual Reactor trip.
Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.
Time      ~  Position  I                              Applicants Actions or Behavior Applicant's SRO      Reset SPDS and initiate monitoring of CSFSTs.
CREW        Open Foldout A.
                                  *. RCP Trip criteria. IF BOTH conditions are met, THEN stop all RCPs: (NO)
SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF
                                            &deg;o            -
DELIVERING FLOW TO THE CORE RCS Subcooling - <                < 35 degrees F [55 degrees F]
                                            &deg;o                                -
* SI actuation criteria. IF EITHER condition occurs, THEN Actuate SI and Go To PATH-1, PATH-i, Entry Point A:
o RCS Subcooling - <                  < 35 degrees F [55 degrees F]
                                            &deg;                                -
Level CAN NOT BE MAINTAINED> 10% [32%]
o PZR Level-
                                            &deg;                -
                                    ** 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 F. (YES)
Transitions to Step 12, based on SW Header pressure between 40-50 SRO PSIG.
Continuous Action Step:
Determine Feedwater status:
                                    **  Check RCSaverage Check    RCS average temperature less than 554 &deg;F.                    OF. (YES)
ROP BOP Verity FWI-W Hht Verify        REG VALVEs VALVEs ULOS1+/-LJ.          CLOSED. (YES)
                                  **  Establish FW bypass flow to maintain                        level in intact S/Gs rriaintainlevel between 39% 39% and 50%. (Will stop                      MDAFW pumps and throttle stopMDAFW open ALL open*        S/G Bypass valves to control SIG level)
ALL S/GBypass RO      Check All Control Rods fully inserted. (YES)
Appendix D                                                                            NUREG-i NUREG-1 021, Rev. 9, Supp. 11


Operator Action Form ES-D-2 Scenario # 4 Event # _5;;..&;;;.;....;.6
Appendix D0 Appendix                                    Operator Action Operator   Action                                               Form ES-D-2 Form      ES-D-2 Op Test Op Test No.:
___ Page 18 of _3.;,..1 ___ ---lI High vibration on #3 Turbine bearing which leads to a manual Reactor trip. Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips. Time i Position i Applicant's Actions or Behavior Continuous Action Step: Check if Reactor is subcritical:
No.:
RO
Scenario Scenario ##      44    Event Event ##        7, 8, 9 & 10 7,8,9&10
* Check Power. Range indicatiohless than 5%. (YES)
                                                                  ~~--~--
* Check Intermediate Range indication negative SUR. (YES, Go To Step. 24) RO Check IRPI has less than two rods stuck out. (YES) Stop the RCS Boration:
Page Page      21 21  of of    31 31
* Verify MOV-35G closed.
                                                                                                            ~~----~I Event
* Verify control switch for Boric Acid pump aligned for blend in AUTO. RO
* Check emergency boration performed using MOV-35G flowpath.
* Notify Engineering to evaluate:
* RCP Bearing temperatures
* No.1 seal leakoff temperatures and flowrates . Check emergency boration performed using RWST flowpath and it is RO desired to align Charging Pump suction to the VCT. (NO, Go To Step 25.i) RO Control Charging Pump speed to control PZR Level. RO Reset SPDS and Initiate monitoring of Critical Safety Function Status Trees. SRO Return to procedure and step in effect. Appendix D NUREG-1G21, Rev. 9, Supp. 1 Appendix D Op Test No.: --:....-Event


== Description:==
== Description:==


Operator Action Form ES-D-2 Scenario # 4 Event # .....;5;;...;&;;;..;;..6
Event
___ Page 19 of _3;;.,;1 ___ -i1 High vibration on #3 Turbine bearing which leads to a manual Reactor trip. Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips. Time i Position I Applicant's Actions or Behavior SRO Directs entry at the beginning of PATH-1. IMMEDIATE ACTION STEP: RO Reactor Tripped. (YES) BOP IMMEDIATE ACTION STEP: Turbine Tripped. (YES) IMMEDIATE ACTION STEP: BOP E-1 AND*E-2 energized. (YES) IMMEDIATE ACTION STEP: RO 0 Sllnitiated
.. (NO) 0 Sllnitiation Required. (NO) RO Verify two Charging Pumps running. (YES) SRO Transition to EPP-4, REACTOR TRIP RESPONSE.
Continuous Action Step: Determine if procedure exit is warranted:
SRO
* Check attack on .RNPsite in progress. (NO)
* Check a total loss of SW .OR Loss of Lake Robinson Dam integrity inprogress.
*(NO, Go to Step 2) Continuous Action Step: RO Check SI signal initiated. (NO, Go to Step 4) IF SI initiation occurs during this procedure, THEN Go to PATH-1, Entry Point.A. (Page 21 ) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Op Test No.: .-;...-Event


== Description:==
== Description:==
Small Small Break Break LOCA,    Phase A LOCA, Phase      fails to A fails    actuate, SI to actuate,  SI fails fails to to actuate,  CR HVAC actuate, CR  HVAC fails fails to to actuate.
actuate.
Time Time      II  Position Position  ~                              Applicants    Actions or Applicant's Actions    or Behavior Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 7, Small Break BOOTH LOCA.
EVENT INDICATIONS:
EVENT    INDICATIONS:
Reactor Trip Reactor Trip Breakers open open PZR Level PZR  Level and and Pressure decreasing RR-1 Recorder Point RR-1            Point #11 for R-12 R-12 in alarm (later) in alarm "A" valves will not close automatically Phase A 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. These  valves    must    be opened manually and at least one valve must be opened to provide an injection path.
Phase A fails to actuate, the crew will manually actuate Phase A, but valves CCW-739, CVC-204B and SI-855            Sl-855 will NOT close on manual actuation of the pushbutton. They will require manual closure from the RTGB control switches.
CR HVAC will fail to shift to PRESSURIZATION MODE. The crew will manually start HVE-19A and HVE-16 will have to be manually CR-D1A-SA stopped. CR-D1      A-SA and D1    Dl B-SB will close - 5 seconds after HVE-16 is stopped.
CREW          Open Foldout A.
* RCP Trip criteria. IF BOTH conditions are met, THEN stop all RCPs: (YES) 0o  SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0o  RCS Subcooling - << 35 degrees F [55 degrees F]
Verify Phase A Isolation valves are closed. (NO, must be manually RO actuated using the pushbutton)
Appendix 0D                                                                NUREG-1 NUREG-1 021,  021, Rev.
Rev. 9, 9, Supp.
Supp. 11


Operator Action Form ES-D-2 Scenario # 4 Event # ...,;5;;..&;;.;..;;;.6
Appendix D                                Operator Action                                         Form ES-D-2     ES-D2 Op Test No.:      1      Scenario #       4   Event #       7, 8, 9 & 10 7,8,9&10            Page      22          31 _ _ _..,1 of .....;3;;..;.1
___ Page 20 of ...,;3;;..;.1
                  ~-
___ -l 1 High vibration on #3 Turbine bearing which leads to a manual Reactor trip. Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips. Time Position I Applicant's Actions or Behavior SRO Reset SPDS and initiate monitoring of CSFSTs. CREW Open Foldout A.
Event
* RCP Trip criteria.
IF BOTH conditions are met, THEN stop all RCPs: (NO) &deg; SI Pumps -AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE &deg; RCS Subcooling
-< 35 degrees F [55 degrees F]
* SI actuation criteria.
IF EITHER condition occurs, THEN Actuate SI and Go To PATH-1, Entry Point A: &deg; RCS Subcooling
-< 35 degrees F [55 degrees F] &deg; PZR 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 F. (YES) SRO Transitions to Step 12, based on SW Header pressure between 40-50 PSIG. Continuous Action Step: Determine Feedwater status:
* Check RCSaverage temperature less than 554 OF. (YES) BOP Verify FW REG VALVEs CLOSED. (YES) *
* Establish FW bypass flow to rriaintainlevel in intact S/Gs between 39% and 50%. (Will stopMDAFW pumps and throttle open* ALL S/GBypass valves to control SIG level) RO Check All Control Rods fully inserted. (YES) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: Scenario # --4 Event # 7,8,9&10 Page 21 of 31 Event


== Description:==
== Description:==
Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.
Time      II  Position  ~                          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 Sl-870A and 870B were RO manually aligned)
RO                    cow pump is running. (YES)
At least 11 CCW BOP            sw and SW Booster pumps running. (NO)
All SW Appendix D                                                            NUREG-1 021, Rev. 9, Supp. 1                1


Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time I Position Applicant's Actions or Behavior BOOTH OPERATOR:
Appendix D                                 Operator Action                                                         Form ES-D-2 Op Test No.:       1 Scenario #       4         Event #       7, 8, 9 & 10 7,8,9&10             Page         23          31 of _3.:,..1:.....-_ _---l 1
When directed by the Chief Examiner, insert Event 7, Small Break LOCA. EVENT INDICATIONS:
Event
Reactor Trip Breakers open PZR Level and Pressure decreasing RR-1 Recorder Point #11 for R-12 in alarm (later) Phase "A" valves will not close 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-870A and 870B valves will NOT open. These valves must be opened manually and at least one valve must be opened to provide an injection path. Phase A fails to actuate, the crew will manually actuate Phase A, but valves CCW-739, CVC-204B and SI-855 will NOT close on manual actuation of the pushbutton.
They will require manual closure from the RTGB control switches.
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 A-SA and D1 B-SB will close -5 seconds after HVE-16 is stopped. CREW Open Foldout A.
* RCP Trip criteria.
IF BOTH conditions are met, THEN stop all RCPs: (YES) 0 SI Pumps -AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0 RCS Subcooling
-< 35 degrees F [55 degrees F] RO Verify Phase A Isolation valves are closed. (NO, must be manually actuated using the pushbutton)
Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 7,8,9&10 Page 22 of .....;3;;..;.1
___ ..,1 Event


== Description:==
== Description:==
Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.
Time      i  Position  !                                  Applicants Actions or Behavior Applicant's Attempt to start all SW and SW Booster pumps. (NO, SW Booster BOP Pump "A" A and SW Pumps "A"          A & "B" B are unavailable)
SOP 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 initiated. (YES)
BOP      Verify CV Ventilation isolation. (YES)
SOP BOP      Verify Control Room Vent aligned for Pressurization Mode. (NO)
NOTE:                      HVE-19A will be manually started and HVE-16 will have to be manually stopped. CR-01      CR-D1A-SA  A-SA and 01    Di 8-S8 B-SB 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-1.                      PATH-i. At the discretion of the Chief Examiner and when the crew transitions to FRP-P.i, the scenario can be terminated. If needed, actions for FRP-P.1, FRP-P.1 begin on page 29.
SOP BOP      Verify both EDGs running. (YES)
ContinuoOs Artinn Stnn Cnntiniiniic .Action          St~p:
RflP BOP                  L..........  ..1.        ...:L:... .-.r VVIIIIIII 30
                                                                            .tJ minutes HhIII1IILS of (ii power i.....
LJLJVVtH loss ILJSS using (15111(1 OP-Restart I(,StrJlI battery L)HIIHIV chargers t;II1IL1lIs within
                                ---------,    ----v-01.
601.
Continuous Action. Action Step:
RO CV Pressure has remained below 10 psig. (YES)
CV Appendix D                                                                    NUREG-1021, Rev. 9, Supp. 1                    1


Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time I Position Applicant's Actions or Behavior NOTE: Valves CCW-739, CVC-204B, SI-855 will NOT close on manual actuation of the pushbutton.
Appendix D                               Operator Action                                         Form ES-D-2 Op Test No.:       1    Scenario #     4     Event #     7, 8, 9 & 10 7,8,9&10           Page     24  of 31
They will require manual closure from the RTGB control switches.
                ~-                                                                                -----il Event
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 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. BOP If additional Feedwater is required, start the SDAFW pump. (Tripped and will NOT restart) RO Verify 2 SI pumps running. (YES) RO Verify Both RHR pumps running. (YES) RO Verify SI valves are properly aligned. (NO, SI-870A and 870B were manually aligned) RO At least 1 CCW pump is running. (YES) BOP All SW and SW Booster pumps running. (NO) Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: .-;...-Scenario # 4 Event # 7,8,9&10 Page 23 of _3.:,..1:.....-
__ ---l 1 Event


== Description:==
== Description:==
Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.
Time      !  Position  II                          Applicants Applicant's Actions or Behavior BOP        Automatic Steam Line Isolation Initiated. (NO)
BOP        Automatic Steam Line Isolation Required. (NO)
BOP        Locally open breaker for HVS-1 at MCC-5.
RO        RCS pressure> 1350 psig. [1250 psig] (NO)
RO        SI Flow Verified. (YES)
RO        RCS Pressure Greater than 125 psig. (YES)
SOP BOP        At least 300 GPM AFW flow available. (YES)
BOP        Verify AFW valves properly aligned.
SOP BOP        Control AFW flow to maintain S/G levels between 8% [18%]        [1 8%j 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 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)
RO        RCS temperature> 547 degrees F. (NO)
BOP        Attempt to limit cooldown.
Appendix D  D                                                        NUREG-1021, Rev. 9, Supp. 1        1


Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time i Position ! Applicant's Actions or Behavior BOP Attempt to start all SW and SW Booster pumps. (NO, SW Booster Pump "A" and SW Pumps "A" & "B" are unavailable)
Appendix D                               Operator Action                                         Form ES-D-2 Op Test No.:             Scenario #       4   Event #       7, 8, 9 & 10 7,8,9&10            Page     25      31 of _3;;:.,.1:...-_ _--11
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 initiated. (YES) BOP Verify CV Ventilation isolation. (YES) BOP Verify Control Room Vent aligned for Pressurization Mode. (NO) NOTE: HVE-19A will be manually started and HVE-16 will have to be manually stopped. CR-01 A-SA and 01 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-1. At the discretion of the Chief Examiner and when the crew transitions to FRP-P.1, the scenario can be terminated.
                ~-
If needed, actions for FRP-P.1 begin on page 29. BOP Verify both EDGs running. (YES) ContinuoOs .Action BOP Restart battery chargers within 30 minutes of power loss using OP-601. RO Continuous Action. Step: CV Pressure has remained below 10 psig. (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 7,8,9&10 Page 24 of 31 -----il Event
Event


== Description:==
== Description:==
Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.
Time LII      Position  II                        Applicants Actions or Behavior Applicant's If RCS cooldown continues and is not due to SI flow, then close MSIVs BOP and MSIV bypasses.
RO        PZR PORVs closed. (NO)
RO        RCS pressure> 2335 PSIG. (NO)
RO        Close PZR PORVs.
RO        PZR PORVs closed. (NO)
RO        Close PORV blocks.
RO        PORV blocks closed. (YES)
RO        PZR Spray and Aux Spray valves closed. (YES)
RO        At least 11 RCP running. (NO)
BOP        Any SIG S/G with uncontrolled depressurization. (NO)
BOP        Any S/G Completely Depressurized (NO)
BOP        R-1 9s, R-31 ssand R-19s,        and R-15 R-1 5 Rad levels normal (YES)
BOP        R-2, R-32A, R-32B Rad levels normal (YES)
RO        CV Pressure Normal (NO)
Appendix D  D                                                        NUREG-1 NUREG-1021,  021, Rev. 9, Supp. 11


Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time ! Position I Applicant's Actions or Behavior BOP Automatic Steam Line Isolation Initiated. (NO) BOP Automatic Steam Line Isolation Required. (NO) BOP Locally open breaker for HVS-1 at MCC-5. RO RCS pressure>
Appendix D                               Operator Action                                           Form ES-D-2 Op Test No.:
1350 psig. [1250 psig] (NO) RO SI Flow Verified. (YES) 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 levels between 8% [18%] and 50%. NOTE: The crew may reset SI and secure a MDAFW Pump to control S/G level. RO RCP Thermal barrier cooling water HilLo 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) RO RCS temperature>
Scenario #     4     Event #       7, 8, 9 & 10 7,8,9&10           Page     26  of
547 degrees F. (NO) BOP Attempt to limit cooldown.
                                                                                                  ----....,1 31 Event
Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 7,8,9&10 Page 25 of _3;;:.,.1:...-
__ --11 Event


== Description:==
== Description:==
Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.
Time      III Position  I                          Applicants Applicant's Actions or Behavior RO        Reset SPDS and initiate monitoring of CSFSTs. (Entry Point C)
CREW        Open Foldout B.
BOP      Request periodic activity samples of all S/Gs.
RO      At least 11 RCP running. (NO)
BOP      Any S/G SIG with uncontrolled depressurization in progress. (NO)
BOP      Control AFW flow to maintain S/G levels between 8% [18%] and 50%.
BOP      Any S/G with uncontrolled level increase. (NO)
BOP      R-1 9s, R-31 sand R-19s,        s and R-15 R-1 5 Rad levels normal. (YES)
RO      PZR PORVs closed. (NO)
RO              pressure > 2335 PSIG. (NO)
RCS pressure>
RO      Close PZR PORVs.
RO      PZR PORVs closed. (NO)
RO      Close PORV blocks.
Open at least one PORV block unless closed to isolate an open PZR RO PORV.
Appendix D                                                          NUREG-1 021, Rev. 9, Supp. 1        1


Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time II Position II Applicant's Actions or Behavior BOP If RCS cooldown continues and is not due to SI flow, then close MSIVs and MSIV bypasses.
Appendix D                                     Operator Action                                             Form ES-D-2 Op Test No.:       1 Scenario #         4     Event #       7, 8, 9 & 10 7,8,9&10         Page       27    of . . .:331
RO PZR PORVs closed. (NO) RO RCS pressure>
: . . :,1_ _ _-l 1
2335 PSIG. (NO) RO Close PZR PORVs. RO PZR PORVs closed. (NO) RO Close PORV blocks. RO PORV blocks closed. (YES) RO PZR Spray and Aux Spray valves closed. (YES) RO At least 1 RCP running. (NO) BOP Any S/G with uncontrolled depressurization. (NO) BOP Any S/G Completely Depressurized (NO) BOP R-19s, R-31 sand R-15 Rad levels normal (YES) BOP R-2, R-32A, R-32B Rad levels normal (YES) RO CV Pressure Normal (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 7,8,9&10 Page 26 of 31 ----....,1 Event
Event


== Description:==
== Description:==
Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.
Time      ~  Position      III                            Applicant's Actions or Behavior Aoolicants ONTINUOUS ACTION STEP CONTINUOUS RO
                    -            If PZR PORV opens oens on high hiah pressure, Dressure. then verify reclosure at or ow 233b psig.
below2335      psg. Close Ulose PORV lOHV blocks as necessary.
RO            Reset SI.
ONTINUOUS ACTION STEP:
CONTINUOlJSACTIONSTEP:
flfl FW CREW rc. +n nn,A,nr e Intl +knn rnnfnrt nmnrnnnn          e-sn nra-I nnnrnnn+
Ifoffsite II.ZIL poweris JJVVI IQ lost,then 1          IJL U II I restart I OLI L emergency I I II  i.,y safeguard OC.tIUjL4CiI L4 equipment.
4 nn 9UIJJI I II IL.
RO            Reset CV Spray.
RO            Reset Phase A and Phase B.
Establish Instrument Air to CV. IF compressor not running, THEN start RO compressor.
BOP            Offsite power available to Charging Pumps. (YES)
RO            At least 1 1 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) 10 10b0 When below 10-        amps, then energize Source Range detectors and RO monitor recorder.
Appendix D                                                                  NUREG-1021, Rev. 9, Supp. 1                      1


Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time II Position I Applicant's Actions or Behavior RO Reset SPDS and initiate monitoring of CSFSTs. (Entry Point C) CREW Open Foldout B. BOP Request periodic activity samples of all S/Gs. RO At least 1 RCP running. (NO) BOP Any S/G with uncontrolled depressurization in progress. (NO) BOP Control AFW flow to maintain S/G levels between 8% [18%] and 50%. BOP Any S/G with uncontrolled level increase. (NO) BOP R-19s, R-31 sand R-15 Rad levels normal. (YES) RO PZR PORVs closed. (NO) RO RCS pressure>
Appendix 0D Appendix                                     Operator Action Operator   Action                                                 Form Form ES-D-2    ES-D-2 Op Test No.:
2335 PSIG. (NO) RO Close PZR PORVs. RO PZR PORVs closed. (NO) RO Close PORV blocks. RO Open at least one PORV block unless closed to isolate an open PZR PORV. Appendix D NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: ......;...-
Op Test No.:        1 Scenario ##
Scenario # 4 Event # 7,8,9&10 Page 27 of .....:3::....:,1
Scenario       44    Event ##
___ -l 1 Event
Event             7,8,9&10 7, 8, 9 & 10           Page Page      28 28  of of ....,;3;..;,1 31_ _ _-l 1
Event


== Description:==
== Description:==


Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time Position II Applicant's Actions or Behavior CONTINUOUS ACTION STEP RO If PZR PORV opens on high pressure, then verify reclosure at or below2335 psig. Close PORV blocks as necessary.
Event
RO Reset SI. CREW CONTINUOlJSACTIONSTEP:
Ifoffsite poweris lost,then restart emergency safeguard equipment.
RO Reset CV Spray. RO Reset Phase A and Phase B. RO Establish Instrument Air to CV. IF compressor not running, THEN start compressor.
BOP Offsite power available to Charging Pumps. (YES) RO At least 1 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) RO When below 10-10 amps, then energize Source Range detectors and monitor recorder.
Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-D-2 Op Test No.: ......;....-
Scenario # 4 Event # 7,8,9&10 Page 28 of ....,;3;..;,1
___ -l 1 Event


== Description:==
== Description:==
Small  Break LOCA, Small Break  LOCA, Phase Phase AA fails fails to  actuate, SI to actuate,  SI fails fails to to actuate, actuate, CR CR HVAC HVAC fails fails to  to actuate.
actuate.
Time Time      IIPosition Position      II                            Applicants Actions Applicant's    Actions or or Behavior Behavior RO RO            RCS    pressure greater RCS pressure    greater than than 275 275 psig psig [400        psig] (YES)
[400 psig]    (YES)
RO            RCS pressure stable RCS              stable or increasing (NO)
BOP BOP                SIG with uncontrolled depressurization in Any S/G                                                      in progress (NO)
RCS pressure increasing RO            (YES) Return to PATH-1, PATH-i, Entry Point C. (page 25)
(NO) Continue below.
BOP            El and E-2 energized by offsite power (YES)
E-1 BOP            Starting air receivers re-pressurized to unloaded EDGs (YES)
BOP            Stop the unloaded EDGs RO            Supplement 0  D components capable of recirc (YES)
BOP            Aux Building radiation normal (YES)
RO            RCS pressure greater than 275 psig [400 psig] (YES)
BOP BOP            Obtain RCS boron, boron, activity, and Hydrogen Hydrogen samples CREW CREW            Transition Transition to EPP-8, EPP-8, POSTPOST LOCA  LOCA CID  C/D AND  AND DEPRESSURIZATION.
Appendix Appendix D  0                                                                NUREG-1 NUREG-1 021,    021, Rev.
Rev. 9,9, Supp.
Supp. 11


Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time II Position I Applicant's Actions or Behavior RO RCS pressure greater than 275 psig [400 psig] (YES) RO RCS pressure stable or increasing (NO) BOP Any S/G with uncontrolled depressurization in progress (NO) RCS pressure increasing RO (YES) Return to PATH-1, Entry Point C. (page 25) (NO) Continue below. BOP E-1 and E-2 energized by offsite power (YES) BOP Starting air receivers re-pressurized to unloaded EDGs (YES) BOP Stop the unloaded EDGs RO Supplement 0 components capable of recirc (YES) BOP Aux Building radiation normal (YES) RO RCS pressure greater than 275 psig [400 psig] (YES) BOP Obtain RCS boron, activity, and Hydrogen samples CREW Transition to EPP-8, POST LOCA C/D AND DEPRESSURIZATION.
Appendix D                               Operator Action                                             Form ES-D-2 Op Test Test No.:
Appendix 0 NUREG-1 021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 4 Event # 7,8,9&10 Page 29 of 31 ..;;..----11 Event
No.:
Op Scenario ##
Scenario        4     Event #
Event          7, 8, 9 & 10 7,8,9&10            Page Page      29 29   of of   31 31
                                                                                                    ..;;..----11 Event


== Description:==
== Description:==


Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time II Position i Applicant's Actions or Behavior FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK actions begin here. Continuous Action Step: BOP Check CST level less than 10%. (NO) IF CST level decreases to .Iess than 10%, THEN perform Step 2. Determine If RCS Cooldown Is Due To A Large Break LOCA: BOP
Event
* RCS pressure is less than 275 PSIG [400 PSIG] (NO) AND
* RHR flow on FI-605 greater than 1200 GPM. (NO) BOP Check RCS Cold leg temperature decreasing. (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) BOP Check level in at least one S/G > 8% [18%]. WHEN level in at least one S/G is> 8% [18%], THEN perform Step 8. BOP Control Feed flow to intact S/G to stop RCS cooldown.
Identify and Isolate faulted S/G:
* Any S/G pressure decreasing in an uncontrolled manner. (NO) BOP OR
* Any S/G completely depressurized. (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 7,8,9&10 Page 30 of 31 "';;";'---'-'1 Event


== Description:==
== Description:==
Small Break Small Break LOCA, LOCA, Phase        to actuate, SI fails to actuate, CR Phase A fails to                              CR HVAC HVAC fails to actuate.
actuate.
Time      II  Position  i                          Applicants Actions or Behavior Applicant's FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK actions begin here.
Continuous Action Step:
BOP      Check CST level less than 10%. 10%. (NO)
IF CST level decreases to .Iess IF                              less than than 10%, THEN THEN perform Step 2. 2 Determine If RCS Cooldown Is Due To A Large Break LOCA:
BOP          **    RCS pressure is less than 275 PSIG [400 PSIG] (NO)
AND
                                *.                  Fl-605 greater than 1200 GPM. (NO)
RHR flow on FI-605 Check RCS Cold leg temperature decreasing.
BOP (NO, skip the next 5 Steps) (YES, continue below)
Attempt to Stop RCS cooldown:
RO/BO P RO/BOP
                                  **  Verify STEAM LINE PORVs CLOSED.
                                  **  Verify Condenser Dumps CLOSED.
                                  **  Check RHR system aligned for core cooling. (NO)
BOP      Check any SIGS/G intact. (YES)
Check level in at least one SIG  S/G >> 8% [18%].
BOP WHEN level in at least one S/G is> 8% [18%], THEN perform Step 8.
BOP      Control Feed flow to intact SIG  S/G to stop RCS cooldown.
Identify and Isolate faulted SIG: S/G:
                                  **  Any S/G pressure decreasing in an uncontrolleduncontrolled manner. (NO)
BOP OR
                                    ** Any SIG S/G completely depressurized. (NO)
Appendix D  D                                                        NUREG-1021, Rev. 9, Supp. 11
Appendix D                                  Operator Action                                                      ES-.D-2 Form ES-D-2 Op Test No.:      1      Scenario #        4        Event #            7, 8, 9 & 10 7,8,9&10        Page    30  of  31 31
                ~-                                                                                        "';;";'---'-'1 Event


Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate. Time Position I Applicant's Actions or Behavior Check PORV block valves available.
== Description:==
Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.
Time     ~  Position I                                     Applicants Applicant's Actions or Behavior Check PORV block valves available.
RO            *. Power available. (YES, Power is available to one block valve)
                                *. At least one open. (YES)
Continuous Action*
Continuous*        Action Step:
                                                      ,r.. i                      *
                                **    ,.t_
Check LiHUK L
                                                - I LITOPL) in t
III service.
S[VIU. (NO)
                                                                      -      /  I l,INLJ)
RO      I    *a  flhrk Rfl nriir <2335PSIG.
CheckRCSpressure                        - 9 PIfl (YES)
(VF I    *. Verify VerifyPORVs PORVs CLOSED. (NO, (NO. PCV-455C is closed to isolate PCV-456)
UV-45b) 3 I-0o    Verify associated PORV        PORV block valve is closed.
RO        Check SI Pumps running. (YES)
Determine if SI can be terminated.
RO
RO
* Power available. (YES, Power is available to one block valve)
                                  *. Check RCS subcooling >                    > 85 degrees F [105 degrees F]. (NO)
* At least one open. (YES) Continuous*
RO         Check ALL RCPs stopped. (YES)
Action* Step:
Appendix D                                                                         NUREG-1021, Rev. 9, Supp. 1 1
* Check L TOP in service. (NO) RO
 
* CheckRCSpressure
HLC-08 NRC SCENARIO 4 TURNOVER SHEET POWER LEVEL: 50%, 150 MWO/MTU. MWD/MTU.
<2335PSIG. (YES)
* Returning to RTP following a short Maintenance Outage.
* VerifyPORVs CLOSED. (NO, PCV-455C is closed to isolate PCV-456) 0 Verify associated PORV block valve is closed. RO Check SI Pumps running. (YES) Determine if SI can be terminated.
BORON CONCENTRATION: 1285 ppm EQUIPMENT UNDER CLEARANCE:
RO
* SW Booster Pump "A"A is Out-Of-Service for Motor Coupling Alignment.
* Check RCS subcooling  
o   LCO 3.7.7-A has been entered and is in hour 18 of a 72 TSAS.
> 85 degrees F [105 degrees F]. (NO) RO Check ALL RCPs stopped. (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 HLC-08 NRC SCENARIO 4 TURNOVER SHEET POWER LEVEL: 50%, 150 MWO/MTU.
o                             18 hours.
* Returning to RTP following a short Maintenance Outage. BORON CONCENTRATION:
Expected return is within -18 EQUIPMENT STATUS:
1285 ppm EQUIPMENT UNDER CLEARANCE:
* SW Booster Pump "A" is Out-Of-Service for Motor Coupling Alignment.
o LCO 3.7.7-A has been entered and is in hour 18 of a 72 TSAS. o Expected return is within -18 hours. EQUIPMENT STATUS:
* Main Turbine Vibration for #2, 3 and 4 bearings is elevated.
* Main Turbine Vibration for #2, 3 and 4 bearings is elevated.
INSTRUCTIONS FOR THE WATCH:
INSTRUCTIONS FOR THE WATCH:
* Increase power to 75% RTP. Appendix D NUREG-1 021, Rev. 9, Supp. 1}}
* Increase power to 75% RTP.
Appendix D                                                       NUREG-1 021, Rev. 9, Supp. 1 1}}

Latest revision as of 22:11, 11 March 2020

Initial Exam 2008-301 Draft Simulator Scenarios
ML101970333
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Site: Robinson Duke Energy icon.png
Issue date: 06/28/2010
From:
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To:
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References
50-261/08-301 50-261/08-301
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Text

I Appendix Appendix DD Scenario Outline Scenario Outline Form Form ES-D-1 ES-D-l Facility:

Facility: HB ROBINSON HB ROBINSON Scenario No.:

Scenario No.: 11 Op OpTest Test No.:

No.: 2008 2008 NRCNRC Examiners:

Examiners: Operators:

Operators:

Initial Conditions:

Conditions: 68% EOL, EOL, 17,000 17,000 MWD/MTU, MWD/MTU, 106 Initial ** 68% 106 ppm Boron.

ppm Boron.

    • SW Booster SW Booster Pump Pump "A"A isis Out-Of-Service Out-Of-Service for for Motor Motor Coupling Coupling Alignment.

Alignment.

0o LCO 3.7.7 LCO 3.7.7-A

-A hashas beenbeen entered entered and and isis inin hour hour 18 18 of of aa 72 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> hour action action statement.

statement.

0o Expected return Expected return isis within within -18

-18 hours.

hours.

  1. 2, 33 and and 44 bearings bearings isis elevated.

elevated.

Turnover:

Turnover: ** Returning to Returning to RTP RTP following following aa short short Maintenance Maintenance Outage. Outage. Awaiting Awaiting results results of of post-outage testing.

post-outage testing. Maintain Maintain powerpower at at current current level.

level.

Critical Task:

Critical Task: Manually restart SW SW pump pump to provide cooling to only running EDG

    • Isolate feedwater to the faulted SIGs using Foldout A OR Supplement G G prior to transitioning to PATH-1, prior PATH-i, Entry Point C.

Event Event No.

No.

Malf.

Malf.

No.

No.

Type*

Event Type*

j J Event Description 1

1 (C) BOP, SRO PR N-42 Upper Detector Fails Low.

(TS) SRO 22 (I) BOP, SROSRO Feed Flow Channel FT-477 Fails High. High.

(TS) SRO 33 (C) BOP, BOP, SRO SRO Condensate Condensate Pump Pump A "A" trips trips which which trips Feedwater Pump Pump A."A".

44 (R)

(R) RO Plant down power Plant down power resulting resulting from from loss loss of of Condensate Condensate Pump. Pump.

(N)

(N) SRO, SRO, BOP BOP 55 (C) RO, SRO (C) RO, SRO RCP RCP C "C" #2 Seal fails,

  1. 2 Seal fails, requiring requiring aa Reactor Reactor Trip.

Trip.

66 (M)

(M) ALL ALL Steam Steam Break Break fromfrom S/GsS/Gs B"8" and and C "C" on on the the Reactor Reactor Trip.

Trip.

77 (C)

(C) BOP BOP EDG "A" fails EDG A to start fails to start on on the the Safety Safety Injection.

Injection.

88 (M)

(M) ALL ALL Loss Loss of of Off-Site Off-Site power.

power. (Loss (Loss of of SUT)

SUT) 99 (C) BOP (C) BOP SW SW Pumps Pumps fail fail to to start start following following restoration restoration of of power.

power.

  • (N)ormal, (N)ormal, (R)eactivity, (R)eactivity, (I)nstrument, (I)nstrument, (C)omponen (C)omponent, t, (M)ajor (M)ajor Appendix Appendix DD NUREG-i NUREG-1021, 021, Rev.Rev. 9,9, Supp.

Supp. i 1

I Appendix DD Scenario Outline Form ES-D-i ES-D-1 SCENARIO 11

SUMMARY

DESCRIPTION HLC-08 NRC SCENARIO DESCRIPTION The crew will assume the watch with the plant at 68% RTP. The previous shift identified Turbine bearing #3 and has increased vibration on Main Turbine has taken all necessary actions to inform necessary actions 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, 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 should remove the instrument from service lAW OWP-01 OWP-011, 1, NUCLEAR INSTRUMENTATION, NI-2, NNI-42 1-42 POWER RANGE. The SRO will enter LCO 3.3.1. Conditions D, E, S and T for the failed Sand instrument.

After ITS has been addressed for the PR detector, the Chief Examiner can cue the FT-477, S/G A Feed Flow instrument failure. The BOP should respond by taking Manual control of S/G A "A" "A" FRV and controlling S/G 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-01 AOP-010, 0, 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 RCP "c" C #2 seal AOP-0i 8, REACTOR COOLANT PUMP ABNORMAL leak. The crew should respond using AOP-018, seal leakoff and determine a plant shutdown lAW GP-006, CONDITIONS, calculating a high sealleakoff NORMAL PLANT SHUTDOWN 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" C have been isolated, the Chief B and "C" 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-1 PATH-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-iO2i, Rev. 9, Supp. 11 NUREG-1021,

I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 11 SIMULATOR SETUP IC/SETUP

  • lC-601, SCN:

IC-601, SON: 006_Sim_1.

  • 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 6: Steam Break from S/Gs "B" B and "c" 0 on the Reactor Trip.
  • A fails to start on the Safety Injection.

Event 7: EDG "A"

  • Event 9: SW Pumps fail to start on restoration following LOOP.

EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:

EVENTSITRIGGERS

  • Event 1: PR N-42 Upper Detector fails low.
  • Event 2: Feed Flow channel FT-477 fails high.
  • Event 3: Condensate Pump "A" A trips causing Feedwater Pump "A"A to trip.
  • Event 4: Plant down power resulting from Condensate Pump A "A" trip.
  • Event 8: Loss of Off-Site Power. (Loss of SUT)

EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

OWP-O11, Nl-2; AOP-025, Section E; OWP-026, FWF-2; AOP-O1O; OWP-011, NI-2; AOP-010; AOP-018; PATH-1; PATH-i; EPP-1 1; Supplement G.

Foldouts A & B; EPP-11; Appendix D D NUREG-1021, Rev. 9, Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test Test No.:

No.: Scenario #

Op Scenario 1 Event #

Event 1

~---------

Page Page 4 of of 26

-~------~I Event

Description:

Event

Description:

PR NI-42 PR Nl-42 Upper Detector fails low.

Upper Detector low.

Time III Position II Alicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 1, PR N-42 Upper Detector fails low.

EVENT INDICATIONS:

APP-003-B6; Overpower f1T APP-003-86; T APP-003-C6; Overtemp f1T T APP-005-A3; PR Dropped Rod APP-OOS-A3; APP-005-C3; PR Channel Dev APP-OOS-C3; APP-005-D5; OTf1T/OPf1T APP-OOS-DS; OThT/OPT Turbine Runback Rod Stop APP-005-F3; PR Upper Ch Hi Flux Dev I Auto Defeat APP-OOS-F3; APP-005-D6; f1 Flux Warning I Status APP-OOS-D6; (Nl-42C) pegged LOW N-42 f1 Flux meter (NI-42C)

Upper Detector (A) on N-42 Drawer indicates low NR-45 and NR-47 Recorders, N-42 reads lower than other Power Range Nis On NR-4S Nls Bistables for:

8istables OThT OT f1T Loop 2 TC422C1, OT OThT f1T Rod Stop TC422C2 OPtJ Loop 2 TC42281, OPf1T TC422B1, OPf1T OPAT Rod Stop TC42282 TC422B2 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.Nl-2.

Reviews ITS for applicable LCOs

  • . Table 3.3.1 -1, #2 - Condition D; Place channel in Trip within 6 3.3.1-1, hours.
  • . Table 3.3.1-1, #5 and 6- 6 - Condition E: Place channel in Trip 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 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
    • Table 3.3.1-1, Item #17d - Condition S: Verify interlock is in required state within 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Appendix D D NUREG-1 021, Rev. 9, Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 11 Event # 1 Page 5 of 26

-- ~-------- ~------~I Event

Description:

Nl-42 Upper Detector fails low.

PR NI-42 Time II Position ~ Applicants Applicant's Actions or Behavior OWP-01 1, NI-2 actions to remove channel from service.

Perform OWP-011,

  • . Removes N-42 from ERFIS scan.

0o (APP-005D6 will be received)

(APP-005-D6

    • Places DROPPED ROD MODE switch on N-42 drawer in the BYPASS position.

0o (APP-005-D4 will be received and NIS ROD DROP BYPASS N-42 status light will ILLUMINATE.)

(APP-036-L11 will be received when Hagan Rack door is opened)

(APP-036-L

  • . Places N-42 OUT OF SERVICE TRIP SWITCH in the TRIPPED position.

BOP 0o (APP-005-A4 received)

  • . ROD STOP BYPASS switch selected to BYPASS PR42.
  • COMPARATOR CHANNEL DEFEAT switch placed in the PR42 position.

0o (APP-005-C3 clears and COMPARATOR DEFEAT light illuminates above the switch)

  • Selects PR42 on UPPER and LOWER SECTION Switches.

0o (APP-005-F3 clears, UPPER SECTION DEVIATION light on drawer clears and CHANNEL DEFEAT light on drawer UPPER SECTION ILLUMINATES) 0o (CHANNEL DEFEAT light on drawer LOWER SECTION ILLUMINATES)

Appendix D NUREG-1 021, Rev. 9, 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 11 Event ##

Event 22 Page Page 66 of of 26 26

~- ~-------- ~------~I Event

Description:

Event

Description:

Feed Flow Feed Flow channel channel FT-477 FT-477 fails fails high.

high.

Time Time J Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior BOOTH OPERATOR:

BOOTH OPERATOR: At At the the discretion discretion of of the the Chief Chief Examiner, Examiner, insert insert Event Event 2,2, Feed Feed Flow Flow channel FT-477 channel FT-477 fails fails high.

high.

EVENT INDICATIONS:

EVENT INDICATIONS:

APP-006-A1; S/G APP-006-A1; SIG AA FW FW >> STM STM FLOWFLOW (Clears (Clears onon lamp Lamp Acknowledge)

Acknowledge)

APP-006-A2; S/G APP-006-A2; SIG AA STM STM >> FW FW FLOW FLOW APP-006-A3; S/G APP-006-A3; SIG AA lVl LVL DEV DEV APP-006-D1: S/G APP-006-D1: SIG A NAR NAR RANGE RANGE lO/lO-lO LOILO-LO lEVELLEVEL FR-478 Green Pen FR-478 Pen goes high and FCV-478 closes and FCV-478 closes Recognizes FT-477 has failed and performs Immediate Immediate Actions for BOP AOP-025, RTGB INSTRUMENT INSTRUMENT FAILURE.

SRO Enters AOP-025, RTGB INSTRUMENT INSTRUMENT FAILURE, Section E.

Immediate Actiol1 Action Step:

BOP Place the affected FRV ...... (FCV-478 for S/G A) affectedFRV(FCV:'478.forS/G "A") in MAN MAN..

Immediate Immediate ActionAction$tep: Step:

BOP Restore Affected S/G Level To Between Between 39% And 52%.

RO/BOP Make PA announceme announcement nt for entry into AOP-025.

Place Place the affected affected S/G Feed Feed Flow Flow Selector Switch to to the the alternate BOP BOP channel. (CH-476, (CH-476, FR-478 FR-478 recorder pen pen will will return to to normal status) status)

Continuous Continuous Action Action Step:

Step:

Restore Restore Affected Affected Controller Controller To To Automatic:

Automatic:

BOP BOP *

  • Check CheckS/G SIG level level withinwithin+/- +/- 1%

1% of of programmed programmed level. level. (If (If YES, YES, place place in in Auto Auto andand Go Go To To Step Step 6) 6)

WHEN WHEN S/G S/G level within +/-+/- 1%

is within level is 1% of programmed level, ofprogrammed level, THEN TH EN place place the the affected affected Controller Controller in in AUTO.

AUTO.

Appendix Appendix D0 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 # 1 1 Event # 2 Page 7 of 26

- - ~------- ~~----~I Event

Description:

Feed Flow channel FT-477 fails high.

Time I Position III Applicant's Actions or Behavior Applicants Reviews, briefs and directs taking FT-477 instrument out of service SRO using OWP-026, FWF-2.

Remove the affected transmitter from service using OWP-026, FWF-2.

  • . FR.-478 selector switch selected to CH-476.

FR-478 BOP ** Remove FT-477 input to the CALO program.

(APP-036-L11 will be received when Hagan Rack door is opened)

(APP-036-L

    • Trip bistable FC-478B-1. (APP-006-A2 will be received)

SRO Go To Procedure Main Body, Step 2.

SRO Implement the EALs.

Review ITS for applicable LCO.

SRO

    • 3.3.1-1, #14 Condition E - Trip bistable within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SRO Return to procedure and step in effect.

Appendix D NUREG-1 021, Rev. 9, Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 11 Event # _3;;....

3 _ _ _ _ Page 8 of _2_6 26_ _ _ _

~- 11 Event

Description:

Condensate Pump "A" A trips which trips Feedwater Pump "A".

A.

Time Tim Position  ! Applicants Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 3, Condensate A trips which results in the tripping of MFP"A".

Pump "A" MFPA.

EVENT INDICATIONS:

APP-007-A1; APP-007-A1 j COND PMP A MOTOR OVLDrrRIPOVLDITRIP (Extinguishes on Lamp acknowledge)

APP-006-A3; SIG A LVL DEV, APP-006-B3j APP-006-A3j S/G SIG 8B LVL DEV, APP-006-C3; APP-006-B3; S/G SIG C LVL DEV (later)

APP-006-C3j S/G Condensate Pump "A" A and Main Feedwater Pump "A" A breaker open.

Recognizes loss of Condensate/Feed Pump and performs immediate BOP actions of AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION.

Immediate Action Step:

BOP Feedwater Regulating Valves.Operating Check FeedwaterRegulating Check Valves Operating Properly in Manual OR Auto. (YES)

Continuous Action Step:

Reactor Trip Setpoint Being Approached.

Check Heactor Approached. (NO)

SRO IF a Reactor Trip Setpoint is approached, THEN THEN trip the Reactor and PATH-i. (Go To Step 4)

Go To PATH.,.1.

RO 1 Make PA Announcement for Procedure Entry into AOP-0i AOP-01 O. 0.

I SRO I Go to appropriate step: Condensate AND Feed Pump Trip, Step 10.

RO 1 Check Reactor Power less than 70%. (YES)

RO 1 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.

Appendix D NUREG-i 021, Rev. 9, Supp. 11 NUREG-1

Appendix 0D Appendix Operator Action Operator Action Form Form ES-D-2 ES-D-2 Test No.:

Op Test No.:

Op Scenario ##

Scenario 11 Event ##

Event 44 Page Page 99 of of 26 26

~~----~I Event

Description:

Event

Description:

Plant down Plant down power power resulting resulting from from Condensate Condensate PumpPump "A" A trip.

trip.

Time Time I1 Position Position I Applicants Actions Applicant's Actions or or Behavior Behavior Attachment 11 - Turbine Attachment Turbine Load Load Reduction Reduction Check Turbine

  • . Check Turbine Control Control ModeMode inin automatic.

automatic. (YES)(YES)

Depress the

  • . Depress the IMP IMP IN IN Pushbutton.

Pushbutton.

BOP BOP Set the

  • . Set the desired desired loadload inin the the SETTER.

SETTER.

    • Set Set desired desired load load rate.

rate.

  • . Depress the Depress the GO Pushbutton.

GO Pushbutton.

NOTE: OP-301, Section 8.2.8 Quick Boration Boration Checklist (shaded area) is included in in the following steps, but may be used following the commencement of the plant down power.

commencement The crew should add - 100 gallons of Boric Acid for the 18%

down power.

DETERMINE the amOl.lnt DETERMINE amount of of Boric Acid to add to the RCSand RCS and RD RO OBTAIN an independent check of thevolume the volume required.

RO OBTAIN permission from the CRSS OR the SSO SSOto borate.

to borate.

RD RO PLACE the theRCS RCS MAKEUP MAKEUP MODE selector switch to BORATE.

RD RO SET SET YIC-1 13, BORIC YIC':113, ACID TOTALIZER to BOR.ICACIDTOTALIZER to desired desired quantity.

quantity.

IF IF desired, desired,THENTHEN PLACE PLACE FCV-1 FCV-113A,1 3A, BORIC BORIC ACID ACID FLOW, FLOW, in in MAN MAN RD RO AND AND ADJUST ADJUST using using the the UP UP andand DOWN DOWN pushbuttons.

pushbuttons.

RD RO Momentarily Momentarily PLACE PLACE the RCS MAKEUP SYSTEM switch the.RCS*MAKEUPSYSTEM switch toto START.

START.

IF IF any any of the below ofthe below conditions conditions occur, occur, THENTHEN momentarily momentarily placeplace the the RCS RGS MAKEUP MAKEUP SYSTEM SYSTEM switch sWitch inin the the STOP STOP position:

position:

RD RO ** RodRod Motion Motion isis blocked blocked OR OR isis inin the the wrong wrong direction direction

    • TAvG increases T AvGincreases

.* Boric Boric AcidAcid addition addition exceeds exceeds the the desired desired value value Appendix Appendix D0 NUREG-1021, NUREG-1 021, Rev.

Rev. 9,9, Supp.

Supp. 11

Appendix D D Operator Action Form ES D2 ES-D-2 Op Test No.:

Event

Description:

1 Scenario # 1 1 Event #

Plant down power resulting from Condensate Pump "A" 4

~--------

Page A trip.

10 10 of 26

~------~I Time I Position II Applicant's Actions or Behavior Applicants WHEN the desired amount of Boric Acid Acid*hashas been added, THEN verify the following:

RO ** FCY-113A, FCV-1 13A, BORIC ACID ACID FLOW, closes.

    • FCY-113B,BLENDEDMU FCV-1 1 3B, BLENDED MU TO CHG CHGSUCT, SUCT, closes closes.
    • IF in Auto, THEN THEN the operating operating Boric Boric Acid Pump stops.

Pump

    • The RCSMAKEUP RCS MAKEUP SYSTEM isOFF. is OFF.

IF desired, THEN THEN FLUSH the the*Boric Acid flow path as follows.

Boric Acid.flow follows:

    • PLACEthe PLACE the RCS MAKEUP MODE selector switch in the AL ALT T DILUTE DILUTEposition. position.
    • SET YIC-114, YIC-1 14, PRIMARY WTR TOTALIZER to 15-20 gallons.
    • PLACE FCY-114B, FCV-1 14B, BLENDED MU TO VCT YCT to CLOSE.
    • Momentarily PLACE the RCS.MAKEUP RCS MAKEUP SYSTEM switch to the START ST ART position~

position.

    • IF any of the below below conditions occur, THEN momentarily place RO RCS MAKEUP SYSTEM switch in the RCSMAKEUP in the STOP position:

o Unanticipated R6d*Motion Rod Motion 0o Primary Water addition re.aches Prima.ryWateraddition reaches the the desired value

    • WHEN the desired amount of of Primary WaterhasWater has been added the RCS, THEN verify to the. verify the following:

0o FCV-1 1 4A FCY:-114Acloses. closes.

0o FCV-1 1 3B closes.

FCY-1136 0o IF in Auto, IFin Auto, THEN the operating PW Pump stops.

0o The RCS MAKEUP SYSTEM is OFF.

TheRCS RETURN the RCS Makeup. System to automatic as Makeup System as follows:

    • VERIFY FCV.::f14A FCV-1 1 4A is in AUTO.
    • PLACE FCY::114B FCV-1 14B to the AUTO position.

RO ** PLACE the RCSMAKEUP RCS MAKEUP MODE switch in AUTO.

    • VERIFY FCY-113A FCV-1 1 3A is in AUTO; AUTO.
  • Momentarily PlACE.the PLACE the RCS MAKEUP SYSTEM switch in the START position.

START RECORD, in AUTO LOG; RECORO,in LOG, ?sindicated by PRIMARY WATER as indicated byPRIMARYWATER RO TOTALIZER, YIC-1 14 AND BoricAcid TOTALlZER,YIC-114ANO TOTALIZER, YIC-113 Boric Acid TOTALIZER, YIC-1 13 the total IDrm,r, AI,fr amount of Primary Water ANDBoric.Acid.added during the mt-i I,,f t-f AFJfl Bfr A,irl rit1rl rh Irnt fhc boration.

h,rfit,,, -

MONITOR parameters .-.rp.--,.--, for the expected change in reactivity AND RO boration intorm the CRSSORthe inform GHS OR the SSG. U ofthe ot the results of ot the boration.

Appendix D NUREG-1 021, Rev. 9, Supp. 11

Appendix 0D Appendix Operator Action Operator Action Form Form ES-D-2 ES-D-2 Test No.:

No.:

Op Test Op Scenario Scenario ## 11 Event ##

Event 4

_4..:....-_ _ _ _ Page Page 11 11 of 26_ _ _-11 of .....:2:;.;;6 Event

Description:

Event

Description:

Plant down power Plant down resulting from power resulting from Condensate Condensate Pump Pump "A" A trip.

trip.

Time Time 1 Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior BOP BOP Check at Check at least least 11 Main Main Feed Feed Pump Pump running.

running. (YES, (YES, GoGo To StepStep 37) 37)

BOP Check SIGS/G Level at or trending to program. (YES)

RO Check T TAVG AVG at or trending to T REF. (YES)

TREF.

SRO Contact Maintenance to troubleshoot and correct Feedwater problem.

SRO Implement the EALs.

Check current loading for the following pumps less than maximum.

  • Condensate Pump - 370 AMPS
  • . Heater Drain Pumps - 90 AMPS BOOTH OPERATOR: When contacted, wait 3 minutes and report that Main Feedwater 800TH 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% in one hour. (NO, Go To Step 43)

Continuous Continuous Action Action* Step:

Check APP-005~B5, ROD BANKS A/B/C/D Check APP-005-B5, AlB/C/DLO LO LIMIT LIMIT extinguished.

RD RO (YES)

IF alarm IF is illuminated, THEN alarm is THEN Borate Borate to to clear the the alarm alarm using using OP-301 OP-301 while while continuing continuing in in this this procedure.

procedure.

RO Monitor Monitor Axial Flux Flux Difference Difference to ensure ensure compliance compliance with LCD LCO 3.2.3 Appendix Appendix D0 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 No.:

Op Test No.: 1 Scenario ##

Scenario 1 Event ##

Event 4

_4~_____ Page Page 12 12 of 26 of ....;;..;......-----ll 26 Event

Description:

Event

Description:

Plant down Plant down power power resulting resulting from from Condensate Condensate Pump Pump "A" A trip.

trip.

Time Time J Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior SRO SRO Notify Load Notify Load Dispatcher Dispatcher of of the the unit's units load load capability.

capability.

SRO Return to procedure and step in effect.

Examiner, insert Event 5.

At the discretion of the Chief Examiner, Appendix Appendix D D NUREG-1 021, NUREG-1 021, Rev. 9, Supp.

Rev. 9, Supp. 11

Appendix D D Operator Action Form ES-D-2 Op Test No.:

Scenario # 1 1 Event # 5, 6 & 7

~~~----

Page 13 of 26

~~----~I Event

Description:

RCP "e" Rep C #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs B and "e" S!Gs "B" C on the Reactor Trip.

A fails to start on Safety Injection.

EDG "A" Time II Position I Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 5, RCP "C" C #2 Seal failure requiring Reactor Trip.

EVENT INDICATIONS:

APP-OO1-C5; RCP STANDPIPE HI/LO LVL (RCP C STP HI)

APP-001-C5; FR 154A, Pen 3 (Blue), C RCP Seal Leakoff decreasing RO Recognizes decreasing sealleakoffseal leakoff and references APP-001-C5.

APP-001 -C5.

IF Standpipe level is High, THEN check for rising level in the Reactor RO Coolant Drain Tank.

BOOTH OPERATOR: When requested by the crew wait 3 minutes and inform the crew that RCDT level is slowly rising. (1% in the last 3 min.) mm.)

SRO AOP-01 8, RCP ABNORMAL CONDITIONS, Section A.

Enters AOP-018, Continuous Action Step:

RO Check any RCP#1 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 < 0.8 GPM. (NO, Go To Step 14)

IF Seal Leakoff decreases to < < 0.8 GPM, THEN Go To Step 9.

RO Check RCP #2 Seal problem suspected. (YES)

Check RCP #2 Seal Leakoff rate known. (NO)

SRO Dispatch an operator to perform Att. 2, RCP Seal Leak Rate Calculation. WHEN calculation is complete, THEN Go To Step 16.

Appendix D D NUREG1 021, Rev. 9, Supp. 11 NUREG-1

Appendix D Operator Action Form ES-D-2 Op Test No.:

Op No.: 1 Scenario ##

Scenario 11 Event #

Event 5, 66 &

5, & 77 Page Page 14 14 of of 26 26

~~~---- ~~----~I Event

Description:

Event

Description:

RCP "C" RCP C,, #2 Seal Seal fails, requiring requiring a Reactor Reactor Trip.

Break from S/Gs Steam Break S/Gs "B" and "C" B and C on the Reactor Reactor Trip.

EDG "A"A fails to start on Safety Injection.

Time II Position I

~ Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When requested to perform Leak Rate Calculation, wait 5 minutes and inform the crew that RCP #2 Seal leakoff is 1.3 GPM.

Continuous Action Step:

Check calculated RCP #2 Seal.leakoff Seal leakoff < < 1.1 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, GP-006, WHEN the Mode 3, THEN stop the affected RCP.

plant is in Mode 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; RCP #1 SEAL LEAKOFF LO FLOW APP-001-E2; PZR level decreasing, Charging Pump Speed increasing Aand FR 154A, A and B Pens decreasing, C Pen pegged HIGH.

A Continuous Action Step:

.,VIILIIIUUU MI.L1011 RO Check Check any RCP #1 Sealleakoffflow>5.7 Seal leakoff flow> 5.7 GPM. (YES)

Check RCP #1 seal leakoff flow RO OR RCP Thermal Barrier b.P AP on affected RCP(s) decreased. (YES)

RO Check Plant in MODEl. MODE 1. (YES)

Perform the following:

    • Trip the reactor.

RO

    • Trip RCP C. "C".

.* Go To Path-i Path-1 while continuing with this procedure.

Appendix D D NUREG-1 021, Rev. 9, Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test Test No.:

No.: 1 Scenario 11 Event # 5, 6 & 7

_5~,_6_&_7___ Page 15 Op --:....- Scenario # Event Page 15 of ,...;2::,;6;....-_

26 _--11 Event

Description:

Event

Description:

RCP "e" Rep C #2 Seal fails, requiring requiring aa Reactor Reactor Trip.

Steam Break from S/Gs B and "e" S!Gs "B" Reactor Trip.

C on the Reactor A fails to start on Safety Injection.

EDG "A" Time II Position iI Applicants Actions or Behavior Applicant's NOTE: Following the performance and verification of PATH-1 PATH-i Immediate Actions, the crew will continue with AOP-018. These steps may be handed off to the RO/BOP to perform independently. The remaining steps of AOP-018 are listed here. PATH-1 PATH-i actions begin on page 16. PHASE B isolation has occurred, so AL RCPs will be secured.

WHEN at least 3 minutes have elapsed since tripping the affected RO RCP, THEN Close SealleakoffSeal leakoff valve for RCP "C". C. (CVC-303C)

RD RO Check RCP "B" B or "c" C running. (NO)

RD RO Check RCP seal injection flow between 8 and 13 GPM. (YES)

RD RO Check FCV-626, THERM BAR FLOW CO CONTNT Valve CLOSED. (YES)

Continuous Action Step:

Check Thermal Barrier intact. (YES)

RD RO WHEN this procedure is completed,THENGoTo WHEN.this completed, THEN Go To AOP-014, CCW SYSTEM MALFUNCTION. .

RO Check APP-002-D2, CV ISOL PHASE B extinguished. (NO)

SRO Implement EALs.

Review ITS for applicable LCOs:

SRO LCD LCO 3.4.13, Condition A - Reduce leakacje

- leakage to within limits within 4 hrs.

Appendix D D NUREG-1021, NUREG-1021 , Rev. 9, 9, Supp. 11

AppendixDD Appendix OperatorAction Operator Action Form Form ES-D-2 ES-D-2 TestNo.:

OpTest No.:

Op Scenario##

Scenario 11 Event##

Event 5,5, 66&&77

~~~----

Page Page 16 16 ofof 26 26

~~----~I EventDescription:

Event

Description:

RCP "e" Rep C#2#2 Seal Seatfails, fails, requiring requiring aa Reactor ReactorTrip.Trip.

Steam Break Steam Breakfrom from S/Gs S/Gs"B" Band and "e" Conon the the Reactor ReactorTrip.

Trip.

EDG "A" EDG A fails failstoto start startonon Safety Safety Injection.

Injection.

Time Time J Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior BOOTH OPERATOR:

800TH OPERATOR: Steam Steam break break for for SIGs SIGs "8"B and and "C" C areare triggered triggered to to occur occur whenwhen the the reactor trip breakers reactor trip breakers open. open. VerifyVerify steam steam break break malfunction malfunction is is inserted.

inserted.

SRO SRO Directs tripping Directs tripping the the Reactor, Reactor, tripping tripping Rep RCP "e" C and and enters enters PATH-1.

PATH-i.

Immediate Action Immediate Action Step:Step:

RO RO Reactor Tripped Reactor Tripped... (YES)(YES)

Immediate Action Step:

BOP Turbine Tripped. (YES)

Immediate Action* Action Step:

BOP E-i AND E-2 energized. (YES)

E-1 (YES)

Immediate Immediate Action Step: Step:

RO SI SI Initiated.

Initiated. (YES) (YES)

NOTE:

NOTE: Phase Phase B 8 isolation isolation has has occurred; occurred; the the crew crew will will stop stop ALL ALL RCPs RCPs due due to to aa loss loss of of RCPRCP cooling.

COOling. When When Foldout Foldout A A is is addressed addressed the the crew crew may may isolate isolate S/Gs SIGs B "8" and and C "C" using using Foldout Foldout A. A. SI SI will will have have to to be be reset prior reset prior to to manipulating manipulating valves. valves.

SRO SRO Open Open Foldout Foldout A. A.

.* RCP Rep Trip Trip criteria.

criteria. IFIF BOTH BOTH conditions conditions areare met, met, THEN THEN stop stop all all RCPs:

RCPs: (NO) (NO) o0 Pumps - AT SI Pumps SI - AT LEAST LEAST ONE ONE RUNNING RUNNING AND AND CAPABLE CAPABLE OF OF DELIVERIN DELIVERING G FLOW FLOW TO TO THE THE CORE CORE o0 RCS RCS Subcooling Subcooling -<<35 - 35 degrees degrees FF[55[55 degrees degrees F]F]

Appendix Appendix DD NUREG-1021, NUREG-i 021, Rev.

Rev. 9,9, Supp.

Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 11 Event # 5, 6 & 7 Page 17 of 26

~~~---- ~~----~I Event

Description:

RCP "e" Rep C #2 Seal fails, requiring a Reactor Trip.

Steam Break from S/Gs "B" B and "e" C on the Reactor Trip.

A fails to start on Safety Injection.

EDG "A" Time I Position II Applicants Applicant's Actions or Behavior

    • SI actuation criteria. IF EITHER condition occurs, THEN Actuate SI PATH-i, Entry Point A:

and Go To PATH-1, 0o RCS Subcooling - < - F [55 degrees F]

< 35 degrees F PZR Level- CAN NOT BE MAINTAINED> 10% [32%1 0o__PZR_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.
    • SIG isolation criteria. IF both the following conditions are met, S/G THEN perform the following:
  • . Any S/G pressure is decreasing in an uncontrolled manner OR
  • . Any S/G has completely depressurized.

AND

  • . At least ONE S/G SIG is intact.

0o Reset SI.

0o CLOSE the appropriate AFW isolation valves to the faulted S/Gs AND OPEN the associated breaker for the valves closed.

    • S/G SIG "B" B
  • . V2-14B, SDAFW PUMP DISCH, MCC-9, CMPT-- 1C CMPT iC
    • V2-16B, AFW HDR DISCH, MCC-10, CMPT - 4F
  • S/G "c" C
  • . V2-14C, SDAFW PUMP DISCH, MCC- MCC 10, CMPT - 4M
  • . V2-16C, AFW HDR DISCH, MCC-9, CMPT - 3J o

0 WHEN the faulted S/Gs dry out, THEN dump steam from_intact_SIG_to_control_RCS_repressurization.

from intact S/G to control RCS mgressurization.

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 NUREG-1 021, Rev. g, 9, Supp. 11

Appendix 0D Operator Action Operator Form ES-D-2 Form ES-D-2 Op Test Op Test No.:

No.: 1 Scenario ##

Scenario 11 Event #

Event 5, 66 && 77 5, Page Page 18 18 of of 26 26

~------~I Event

Description:

Event

Description:

RCP "e" Rep C,, #2 Seal Seal fails, requiring requiring aa Reactor Reactor Trip.

Steam Break Steam Break from from S/Gs S/Gs "B" B and and "e" on the Reactor C on Reactor Trip.

EDG "A" EDG A fails to start on Safety Injection.

Safety Injection.

Time i Position Position i Applicants Actions or Behavior Applicant's 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.

BOP If additional Feedwater is required, start the SDAFW pump.

RO Verify 2 SI pumps running. (YES)

RO Verify Both RHR pumps running. (YES)

RO Verify SI valves are properly aligned. (YES)

RO At least 1 1 CCW 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)

RO Verify CV Fans HVH-1, 2, 3, 4 running. (YES)

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-1 021, 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 5, 5, 66 && 77 Page Page 19 19 of of 26 26

~~~---- ~~----~I Event

Description:

Event

Description:

RCP "e" Rep C #2

  1. 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" on the C on the Reactor Trip.

Reactor Trip.

EDG "A" EDG A fails fails to to start start on on Safety Safety Injection.

Injection.

Time Time I Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior BOP Verify both EDGs running. running. (NO)

NOTE: investigate what is If requested to investigate is wrong with the EDG, 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 of power loss using OP- OP 601.

Continuous Action Step:

RD RO CV Pressure has remained below 10 psig. (NO)

RD RO Verify CV Spray initiated. (YES)

RD 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 12 GPM)

RO Verify Phase BB isolation valves closed. (YES)

RD RO Stop ALL RCPs. (May be stopped previously)

Verify ALL MSIVsMSIVs and MSIV bypasses closed.

and MSIV closed. (YES, (YES, operator operator will will take take BOP BOP MSIV MSIV switches switches to to CLOSE)

CLOSE)

BOP BOP Locally Locally open open breaker breaker for for HVS-1 HVS-1 at at MCC-5.

MCC-5.

Appendix Appendix D0 NUREG-1 021, 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 11 Event ##

Event 5, 6 & 7_ _ _ Page

_5;;.:"..;;,6,.;;;&;..;,7 Page 20 20 26_ _ _...,1 of _2_6 of Event

Description:

Event

Description:

RCP "C" RCP C #2 Seal Seal fails, fails, requiring requiring aa Reactor Reactor Trip. Trip.

Steam Break Steam Break from S/Gs S/Gs "B" B and and "C" on the Reactor C on Reactor Trip.

Trip.

EDG "A" EDG start on Safety A fails to start Safety Injection.

Injection.

Time i Position Position II Applicants Actions or Behavior Applicant's Behavior RCS pressure> 1350 psig. [1250 psig]

RO ** (YES, RCS pressure is> 1250, skip the following 2 steps)

    • (NO, RCS pressure is < 1250, 1250, Go To the next step)

RO SI Flow Verified. (YES)

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%] [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 F. (NO)

RO RCS temperature> 547 degrees F. (NO)

BOP Attempt to limit cooldown.

IF RCS cooldown continues and is NOT due to SI flow, THEN close BOP MSIVs and MSIV bypasses.

Appendix D D NUREG-1 021, Rev. 9, Supp. 11

Appendix DD Appendix Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test Op Test No.:

No.: Scenario ##

Scenario 11 Event ##

Event 5, 66 && 77 5, Page Page 21 21 of of 26 26

~- ~~~---- ~---~I Event

Description:

Event

Description:

Rep c #2 RCP "e" #2 Seal Seal fails, requiring aa Reactor fails, requiring Trip.

Reactor Trip.

Steam Break Steam Break fromfrom S/Gs S/Gs "B" B and c on and "e" on the the Reactor Reactor Trip.

Trip.

EDG "A" EDG A fails to start fails to start onon Safety Injection.

Safety Injection.

Time Time J II Position Position  ! Applicants Actions Applicant's Actions or Behavior or Behavior RO RO PZR PORVs PZR PORVs closed. closed. (YES)

(YES)

RO RO PZR Spray PZR Spray and and AuxAux Spray valves closed.

Spray valves closed. (YES)

(YES)

RO RO least 11 RCP At least running. (NO)

RCP running. (NO)

BOP SIG with uncontrolled depressurization.

Any S/G depressurization. (YES)

RO Reset SPDS and initiate monitoring of CSFSTs.

SRO Go To EPP-11, FAULTED STEAM GENERATOR GENERATOR ISOLATION.

ISOLATION.

BOP Maintain At Least One S/G SIG Available For RCS Cooldown.

BOP Any SIG S/G pressure stable or increasing. (YES)

Any S/G pressure decreasing in an uncontrolled manner OR any S/G BOP completely depressurized depressurized.. (YES)

Isolate Isolate faulted S/Gs using using Supplement 0, G, 5/0 S/G ISOLATION ISOLATION..

BOP BOP (Supplement (Supplement G Steps G Steps are listed on on page 22 24) 22 & 24)

Maintain Maintain A A Faulted Faulted S/G S/G In The Isolated In The Isolated Condition Condition During During Subsequent Subsequent BOP BOP Recovery Recovery Actions Unless Unless Needed Needed For For Cooldown.

Cooldown.

BOP BOP Check Check CST CST level greater than level greater than 10%.10%. (YES)(YES)

BOP BOP Check Check Available Available Secondary Secondary Radiation Radiation Monitors Monitors normal.

normal. (YES)

(YES)

Appendix Appendix DD NUREG-102 NUREG-1 021, Rev. 9, 1, Rev. 9, Supp.

Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test Op Test No.:

No.: 1 Scenario ##

Scenario 11 Event #

Event 5, 66 &

5, & 77 Page Page 22 22 of of 26 26

~~------ ~------~I Event

Description:

Event

Description:

RCP "e" Rep C #2 Seal fails, requiring

  1. 2 Seal Reactor Trip.

requiring aa Reactor Trip.

Steam Break Steam Break from S/GsS/Gs "B" B and and "e" on the Reactor C on Reactor Trip.

EDG "A" EDG A fails to start on Safety Injection.

Safety Injection.

Time III Position Position I Applicants Actions or Behavior Applicant's Behavior CRITICAL TASK: Isolate feedwater to the faulted S/Gs SIGs using Foldout A OR Supplement G prior to transitioning to PATH-1, PATH-I, Entry point C.

Check any S/G with an uncontrolled level increase. (NO, Go To Path- Path RO (PATH-i Steps continue on Page 1, Entry Point C) (PATH-1 Paqe 25)

Pages 22-24 are steps from Supplement G, STEAM GENERATOR ISOLATION to isolate B "e" S/Gs "8" C as faulted Steam Generators.

Go to the appropriate step from following table:

BOP ** S/G B to be isolated, Go To Step 18.

    • 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)

Vi -3B, MSIV CLOSED. (YES)

Verify V1-3B, BOP Verify Vi -3C, MSIV CLOSED. (YES)

V1-3C, Verify MS-353B, MSIV Vi -3B BYP CLOSED. (YES)

V1-3B BOP Verify MS-353C, MSIV V1-3C Vi -3C BYP CLOSED. (YES)

Verify FRV B CLOSED. (YES)

BOP Verify FRV C CLOSED. (YES)

Verify FRV B BYP CLOSED. (YES)

BOP Verify FRV C BYP CLOSED. (YES)

Appendix D D NUREG-1 021, Rev. 9, Supp. 11 NUREG-i

Appendix D D Operator Action Operator Form ES-D-2 Form ES-D-2 Op Test Op Test No.:

No.: 1 Scenario ##

Scenario 11 Event ##

Event 5, 6 & 7_ _ _ Page

_5;;.1"...;;.6..;;;&;..;.7 Page 23 23 26_ _ _-i1 of .....;2;.,;6 of

~-

Event

Description:

Event

Description:

RCP "e" Rep C #2

  1. 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 and "e" C on on the the Reactor Reactor Trip.

Trip.

EDG "A" EDG A fails to start start on Safety Injection.

Injection.

Time II Position Position I Applicants Actions or Behavior Applicant's Behavior V2-6B, FW HDR SECTION Valve CLOSED. (YES)

Verify V2-6S, BOP SOP Verify V2-6C, FW HDR SECTION Valve CLOSED. (YES)

Verify V2-14S, V2-14B, SDAFW PUMP DISCH Valve CLOSED. (YES)

BOP SOP Verify V2-14C, SDAFW PUMP DISCH Valve CLOSED. (YES)

V2-l 6B, AFW HDR DISCH Valve CLOSED. (YES)

Verify V2-16S, BOP SOP Verify V2-16C, V2-i 6C, AFW HDR DISCH Valve CLOSED. (YES)

BOP SOP Verify STEAM LINE PORVs CLOSED. (YES)

Vi -8B, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)

Verify V1-8S, 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 S/G B "S" and S/G C "C" BYPASS SYPASS DRN and WARM-UP LINE TO AFW PUMP.

Check S/Gs B "S" and C "C" MSIV Above and Below Selow Seat Drain Valves BO SOP CLOSED. (YES)

Appendix Appendix D D NUREG-iO2i, NUREG-1021, Rev. Rev. 9, 9, Supp.

Supp. i1

Appendix D Operator Action Operator Form ES-D-2 Op Test Test No.:

No.:

Op Scenario ##

Scenario 11 Event #

Event 5, 66 && 77 5,

~~~----

Page Page 24 24 of of 26 26

~---~I Event

Description:

Event

Description:

RCP "e" Rep Seal fails, requiring C,, #2 Seal requiring a Reactor Reactor Trip.

Steam Break Steam Break from S/GsS/Gs "B" B and and "e" on the Reactor C on Reactor Trip.

EDG "A" EDG A fails to start on Safety Injection.

Injection.

Time i Position II Applicants Actions or Behavior Applicant's Dispatch an operator to E-1/E-2 Room to perform the following:

  • . At MCC-9, verify V2-14B V2-1 4B and V2-16CV2-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 V1-8B Vi -8B and V1-8C Vi -8C closed and open breakers 0o V1-8B, SDAFW PUMP STEAM ISOLATION.

0o Vi-8C, SDAFW PUMP STEAM ISOLATION.

V1-8C, Dispatch operator to the Aux. Bldg. to perform the following:

  • . MOO-i 0, verify V2-16B At MCC-1 V2-i 6B closed and open breaker V2-16B, V2-i 6B, BOP MDAFW PUMP HEADER DISCHARGE TO S/G B.
  • . MCC-iO, verify V2-14C At MCC-10, V2-i4C closed and open breaker V2-14C, V2-i4C, 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, Rev. 9, Supp. i1

Appendix 0D Operator Action Form ES-D-2 Op Test No.:

Op No.: 1 Scenario #

Scenario 1 Event ##

Event 88 &

& 99 Page Page 25 25 of 26 26

~~------ ~~----~I Event

Description:

Event

Description:

Loss of Off-Site Loss Off-Site Power.

Power.

SW Pumps fail to start following restoration restoration of power.

Time II Position Ifi Acolicants Actions or Behavior Applicant's BOOTH OPERATOR: After S/Gs 800TH SIGs "8"B and "C" C are isolated and at the discretion of the Chief Examiner, insert Events 8 and 9, Loss of Off-Site Power with a failure of SW Pumps to restart.

The crew will continue in PATH-1, PATH-i, but will address components that did NOT restart:

0o Service Water Pump "C" C or "0" EDG cooling.

D to provide EOG 0o RHR Pump "8", B, HVH Units 3 & & 4, SI Pump "C".

C.

0o Charging Pump "C" C started OR FCV-626 opened to provide RCP Seal cooling.

CRITICAL TASK: Manually restart a Service Water Pump to provide cooling to the only running EDG before damaging the EDG.

Reset SPDS and initiate monitoring of Critical Safety Function Status RO Trees.

SRO Open Foldout B.

SRO Request periodic samples of ALL S/Gs.

RO At least one RCP running. (NO)

BOP Any SIG S/G with uncontrolled depressurization. (YES)

BOP Faulted S/G isolated using EPP-11.EPP-1 1. (YES)

Once S/Gs B "8" and C "C" have been isolated and aa SW pump has been started, the scenario may be terminated.

Appendix D 0 NUREG-1021, Rev. 9, Supp. 11 NUREG-1021,

HLC-08 NRC HLC-08 NRC SCENARIO SCENARIO 11 TURNOVER TURNOVER SHEETSHEET POWER LEVEL:

POWER LEVEL: 68%,

68%, 17,000 17,000 MWO/MTU.

MWD/MTU.

    • Returning to Returning to RTP RTP following following aa short short Maintenance Maintenance Outage.

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:

  • SW Booster Pump "A" A is Out-Of-Service for Motor Coupling Alignment.

o 3.7.7-A LCO 3.7.7 -A has been entered and is in hour 18 of a 72 TSAS.

o 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 />.

EQUIPMENT STATUS:

    • Main Turbine Vibration for #2, 3 and 4 bearings is elevated.

Main INSTRUCTIONS FOR THE WATCH:

    • Maintain power at 68% RTP.

Maintain Appendix Appendix DD NUREG-1021, Rev.

NUREG-1021, Rev. 9, 9, Supp.

Supp. 11

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.: 22 Test No.:

Op Test Op No.: 2008 NRC 2008 NRC Examiners:

Examiners: Operators:

Operators:

Initial Conditions: ** 100% MOL, 9000 MWD/MTU, 766 ppm Boron.

    • SW Booster Pump "A" A is Out-Of-Service for Motor Coupling Alignment.

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 hours.

    • Main Turbine Vibration for #2, 3 and 4 bearings is elevated.

Turnover: ** Maintain power at normal levels.

Critical Task: ** Initiate isolation of the applicable S/G using Supplement G before exiting EPP- EPP 11.

    • Verify CVC-381 closed before transitioning to FRP-H.1.

Event MaIf. No.

Malf. Type*

Event Type* Event No. Description 1

1 (C) RO, SRO Charging Pump "B" B trip.

2 (I) RO, SRO KB Fails Low simulating a dropped rod.

IRPI K8 (TS) SRO 3 (I) BOP, SRO Controlling Steam Flow channel FT FT-494

-494 for S/G "C" C fails LOW.

(TS) SRO 4 (C) BOP, SRO FWH 4A Tube Leak.

55 (R) RO Downpower to support removing FWH 4A from service.

(N) SRO, BOP 66 (C) RO Rods continue to step requiring Reactor Trip.

(M) ALL 77 (C) BOP Failure of the Turbine to trip.

88 (M) ALL FW break on S/G B "B" inside CV. Loss of all Feedwater.

9 (C) RO Containment Spray Pump A "A" fails to Auto Start.

10 10 (C) RO Phase Phase B B Isolation Isolation Valves FCV-626 FCV-626 and and CVC-381 CVC-381 fail to close.

  • (N)ormal, (N)ormal, (R)eactivity, (l)nstrument, (I)nstrument, (C)omponent, (C)omponent, (M)ajor Appendix Appendix D D NUREG-1021, NUREG-1021, Rev. Rev. 9,9, Supp.

Supp. 11

II Appendix Appendix DD Scenario Outline Scenario Outline Form Form ES-D-1 ES-D-1 HLC-08 NRC HLC-08 NRC SCENARIO SCENARIO 22

SUMMARY

SUMMARY

DESCRIPTION DESCRIPTION The crew The crew will will assume assume thethe watch watch with with the the plant plant atat 100%

100% RTP.RTP. The previous shift The previous identified shift identified increased vibration increased vibration on on Main Main Turbine Turbine bearing bearing #3#3 and and has has taken taken all necessary actions all necessary actions toto inform inform station management.

station management. ServiceService Water Water Booster Booster Pump Pump "A"A is is under clearance for under clearance for Motor Motor Coupling Coupling Alignment. Shift Alignment. instructions are Shift instructions are to to maintain maintain the the plant plant at at 100%

100% RTP.RTP.

On cue On cue from from the the Chief Chief Examiner, Examiner, Charging Charging PumpPump "B" B will will trip.

trip. The The RO should respond RO should respond lAW lAW APP-003-F4, starting the standby Charging pump to maintain PZR level on program.

cue from the Chief On cue Chief Examiner, IRPI K8 will fail low low simulating simulating aa dropped dropped rod.

rod. The crew crew should should respond lAW lAW AOP-001 AOP-001,, MALFUNCTION MALFUNCTION OF OF REACTOR REACTOR CONTROL CONTROL SYSTEM,SYSTEM, and verify that no dropped rod rod exists due to stable Reactor Reactor parameters.

parameters. The SRO should enter LCO LCO 3.1.7, 3.1 .7, Condition A for the failed IRPI.

On cue from the Chief Examiner, the controlling steam flow channel (FT-494) for S/G SIG "c" C will fail low. The BOP will take Manual control of Feedwater Regulating valve FCV-498, lAW AOP-025, RTGB INSTRUMENT FAILURE, to match Feed Flow and Steam Flow in order to control S/G SIG "c"

C water level. An alternate controlling channel will be selected, FCV-498 will be returned to automatic control and FT-494 will be removed from service lAW OWP-034, STEAM FLOW, SF-5, STEAM FLOW TRANSMITTER FT-494. The SRO should enter LCO 3.3.1 Condition E and 3.3.2 Condition D, for the failed instrument.

As soon as Tech Specs are addressed, the Chief Examiner can cue a tube leak in Feed Water Heater 4A. The crew should respond lAW APP-007-E7, identifying the leak and entering AOP- AOP 010, MAIN FEEDWATER/CONDENSATE MALFUNCTION and using requirements from OP- OP 407, HEATER DRAINS AND VENTS, ramp the plant down in power to 517 MWe in order to remove the FWH from service.

As soon as the Chief Examiner is satisfied with the power maneuver, he can cue the Rod Control System failure. Control Rods will continually step in the direction moved and the crew will be unable to stop rod motion. The SRO should respond by directing a Reactor trip and enter PATH-i.

PATH-1. On the Reactor trip, the turbine will not trip and cannot be tripped from the RTGB, requiring the BOP to Manually runback the turbine. Shortly after the Reactor Trip, a Feedwater Break will develop inside CV, resulting in a Safety Injection. On the SI, all Auxiliary Feedwater Pumps will fail to start or will trip, resulting in a complete loss of feed. On the SI and CV Spray, Containment Spray Pump A "A" will fail to Auto start, Phase B B isolation valves CVC CVC-381 and FCV-626 will fail to close. The crew should respond and take actions lAW PATH-i, PATH-1, transitioning to FRP-H.i, FRP-H.1 , LOSS OF SECONDARY SECONDARY HEAT SINK.

The Chief Examiner may terminate the scenario at any time after SIG S/G B "B" Feedwater break is isolated and feedwater is restored to at least 11 S/G.

Appendix Appendix D D NUREG-i NUREG-1 021, 021, Rev. 9, Supp.

Rev. 9, Supp. 11

I Appendix 0D Scenario Outline ES-D-i Form ES-D-1 HLC-08 NRC SCENARIO 2 SIMULATOR SETUP IC/SETUP:

  • IC-602, SON 006_Sim_2.
  • Booster Pump "A" SW 800ster A is OFF, breaker OPEN and switch is RED CAPPED.
  • Main Turbine 8earing Bearing #2 is OFFSET by 1.5, #3 by 2.3 and #4 by 1.7. 1 .7.
  • IC-i 3.

Status board is correctly marked up for IC-13.

PRE-LOADED EVENTS:

The following events should occur on the reactor trip:

  • Event 8: FW break on S/G SIG "8" B inside CV. Loss of all Feedwater.
  • Event 10: Phase 8 B Isolation Valves FCV-626 and CVC-381 fail to close.

EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:

EVENTSITRIGGERS

  • Event 1: Charging Pump "8" B trip.
  • KS Fails Low simulating a dropped rod.

Event 2: IRPI K8

  • Event 3: Controlling Steam Flow Channel FT-494 for SIG "C" Fails LOW.

S/G C

  • Event 4: FWH 4A Tube Leak
  • Event 7: Failure of the Turbine to trip.

EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

Appendix Appendix D 0 NUREG-i NUREG-1 021, 021, Rev. 9, 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 22 Event ##

Event 1 Page Page 44 of of 28 28

~-------- ~~----~I Event

Description:

Event

Description:

Charging Pump Charging Pump "B"B trip trip Time Time ~fi Position Position I 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 1,1, Charging Charging Pump "8" Pump B trip.

trip.

INDICATIONS:

EVENT INDICATIONS:

APP-003-F5; CHG PMP APP-003-F5; PMP MOTOR OVLDfTRIP OVLDITRIP APP-OO1-B6; LP APP-001-86; LTDN LN LP LTDN LN HI TEMP (will HI TEMP (will clear clear asas the the running Charging Pump running Charging speeds up)

Pump speeds up)

APP-003-F4; CHG PMP PMP HI HI SPEED (after (after short delay)

APP-003-F5, notes dual indication for Charging Pump "S",

Receives APP-003-FS, B, RO APP-003-F5 actions.

references APP-003-FS RO ** Verifies at least 1 1 Charging Pump is running and supplying adequate RCP seal injection flow.

RO ** Dispatch an operator to check Charging Pump "S" B breaker at 480V Sus Bus E-1.

RO ** Dispatch operator to check the Charging Pumps.

RO ** IF adequate RCP seal injection flow cannot be maintained, THEN refer to AOP-O1 AOP-018. 8.

RO Receives APP-003-F4 and reviews actions.

RO ** IF RCS leakage is indicated, THEN refer to AOP-O1 IF AOP-016. 6.

RO *

  • IF required to maintain level, THEN start standby Charging IF Pump._(Will_clear Pump. (Will clear APP-003-F4)

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.:

Op Test No.: 1 Scenario #

Scenario 22 Event #

Event 2 ____

....;2~ Page Page 55 of ....;2:;,;;8 of 28_ _ _...,1 Event

Description:

Event

Description:

IRPI K8 Fails IRPI Fails Low simulating a dropped rod.

rod.

Time II Position II Applicants Actions or Behavior Applicant's BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 2, IRPI K8 fails low simulating a dropped rod.

EVENT INDICATIONS:

APP-005-F2; ROD BOTTOM ROD DROP Shutdown Bank B, Group 2, K8 indicates 0 inches with RBL ON RO Recognizes K8 RBL and performs Immediate Actions of AOP-001.

AOP-O01, MALFUNCTION OF REACTOR CONTROL Enters AOP-001, SRO SYSTEM.

Immediate Action Step:

RD RO Check Unexpected Rod Motion in Progress. (NO, Go To Step 7)

RO/BOP Make PA Announcement for entry into AOP-001. AOP-0O1.

Determine if multiple rods have dropped:

RO

    • Prompt Drop present. (NO)
    • More than 1 1 RBL illuminated. (NO)
    • More than 1 1 IRPI indicates on bottom. (NO)

RD RO Check multiple dropped rods present. (NO, Go To Step 11) 1 1)

RO Check TAVGTAVG trending to TREF.

T REF. (YES)

Appendix D D NUREG-1 NUREG-1 021,021, Rev. 9, 9, Supp. 11

Appendix 0D Operator Action Operator Form ES-D-2 Form ES-D-2 Op Test No.:

Op Test No.: 1 Scenario ##

Scenario 22 Event ##

Event 2

....;2=--_ _ _ _ PagePage 66 of ...;2::.;;8 of 28_ _ _..,1 Event

Description:

Event

Description:

IRPI K8 IRPI K8 Fails Fails Low Low simulating simulating aa dropped dropped rod.rod.

Time III Position Position I Aoclicants Actions or Behavior Applicant's Behavior Determine the status of rods.

    • APP-005-A3 Illuminated (NO)
    • APP-005-F2 Illuminated (YES)

SRO/RO ** RBL for affected rod illuminated (YES)

    • Indication of Prompt Drop (NO)
    • Quadrant Power Tilt indications present (NO)
    • APP-005-F3 and F4 extinguished, ERFIS ERRS shows no tilt.

S RO/RO SRO/RO Check dropped rod present (NO, Go To Step 14)

Determine The Status Of IRPI:

    • IRPI Indication - Indicator drift with no flux effects. (NO)
    • IRPI Indication - Erratic movement with no flux effects. (YES)

IRPllndication

    • IRPI Indication - Off-scale high/low with no flux effects. (YES)

IRPllndication RO ** Dropped Rod Indication with no flux changes

    • Rod Bottom Light for K8 illuminated. (YES)

AND

    • APP-005-A3, PR DROP ROD extinguished. (YES)
    • Simultaneous loss of ALL IRPI Indication present. (NO)

SRO Checks IRPI malfunction present. (YES, Go To Section D)

RO Check IRPI energized. (YES)

SRO SRO Check Check current plant plant status MODE 11 or MODE 2. (YES)

Review ITS ITS for applicable LCOs:

SRO SRO *

  • 3.1 .7, Condition A; Verify Rod position by 3.1.7, by movable in-core detectors detectors OR Decrease Decrease power power to .$

< 50% within 8 8 hrs.

hrs.

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 22 Event ##

Event 2 ____

_2~ Page Page 77 of of ....;2::.::8::..-_

28 _---l 1

Event

Description:

Event

Description:

IRPI K8 IRPI Fails Low K8 Fails simulating aa dropped Low simulating dropped rod.

rod.

Time Time i Position Position III Acolicants Actions Applicant's Actions or Behavior or Behavior BOOTH OPERATOR:

BOOTH OPERATOR: IfIf the the crew crew chooses chooses to to perform perform aa power reduction lAW power reduction lAW LeOLCO 3.1.7, 3.t7, inform the CRSS to wait for Rx Engineering to perform a flux map.

Check Adjustment to IRPIIRPI will be performed. (NO, Notify Notify I&C, l&C, Go To SRO Step 8)

SRO Implement the EALs and return to procedure and step in effect.

Appendix Appendix D0 NUREG-1021, NUREG-1021, Rev. Rev. 9, 9, Supp.

Supp. 11

Appendix 0D Operator Action ES-D-2 Form ES-O-2 Op Test No.:

Op No.: 1 Scenario ##

Scenario 22 Event #

Event 33 Page Page 88 of of 28 28

~-------- ~------~I Event

Description:

Event

Description:

Flow Channel FT-494 Steam Flow FT-494 Fails Fails Low.

Time ~ Position I Applicants Actions or Behavior Applicant's BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 3, Steam Flow channel FT-494 fails low.

EVENT INDICATIONS:

APP-006-C1; S/G C FW > STM FLOW SIG C APP-006-C2: S/GSIG C STM > > FW FLOW APP-006-C3; S/GSIG C LLVL VL DEV FR-498, Pen #1 (Red) decreasing and FCV-498 CLOSING.

Recognizes FT FT-494

-494 has failed and performs Immediate Actions of BOP AOP-025.

SRO Enters AOP-025, and determines Section F is the applicable section.

Immediate Action Step:

BOP (FCV-498 for Place the affected FRV (FeV-498 S/G "C")

for SIG C) in MAN.

Immediate Action Step:

BOP Restore Affected S/G Level To Between 39% And 52%.

NOTE: The crew may receive a Power Limit Warning and reduce the Turbine Limiter to maintain power < < 100%.

100%.

RO/BOP Make PA announcement for entry into AOP-025.

Place The Affected S/G Steam Flow Selector Switch To The Alternate BOP Channel. (CH-495) (Recorder pen will return to normal status on FR- FR 498)

Appendix D 0 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 Op Test No.:

No.: 1 Scenario ##

Scenario 22 Event ##

Event 33 Page Page 99 of of 28 28

~- ~-------- ~------~I Event

Description:

Event

Description:

Steam Flow Steam Flow Channel Channel FT-494 FT-494 Fails Fails Low.

Low.

Time Time 1 Position Position I Applicants Actions Applicant's Actions or Behavior or Behavior CONTINUOUS ACTION CONTINUOUS ACTION STEP:STEP:

Restore Affected Controller Restore Controller To Automatic:

To Automatic:

BOP BOP *. Check S/G Check within +/-

SIG level within 1% of

+/-1% of PROGRAMMED LEVEL (If YES - Place in in Auto Auto and Go To Step Step 6)

WHEN S/G level WHEN level is within +/-+/- 11%% of PROGRAMMED PROGRAMMED LEVEL, LEVEL, THEN Controller in AUTO.

place the affected Controller Reviews, briefs and directs taking FT-494 instrument out of service SRO using OWP-034, SF-5.

Perform OWP-034, SF-5 actions to remove channel from service.

  • . Remove FT-494 input to the CALO program by removing ERFIS Point.

SRO/BOP *. FR-498 Steam Flow Selector Switch selected to CH 495.

(APP-036-L11 will be received for entering Hagan Racks)

(APP-036-L

  • . Trip bistable FC-494 (APP-006-F4 received)
  • . Trip bistable FC-498B-1 (APP-006-C2 received)

SRO Go To Procedure Main Body, Step 2.

SRO Implement the EALs.

Review applicable ITS. ITS.

    • Table 3.3.1-1, 3.3.1-1, #14, Condition EE - Trip bistables within 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br />.

SRO SRO

.* Table 3.3.2-1, #lf, #1f, 11g, 4d, 4e, Condition D D - 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 />.

hours.

SRO SRO Return to to procedure procedure and step in and step in effect.

effect.

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 Op Test No.:

No.: 1 Scenario ##

Scenario 22 Event ##

Event 44 Page Page 10 10 of of 28 28

....;...- ~-------- ~~----~

Event

Description:

Event

Description:

FWH 4A FWH 4A Tube Tube Leak.

Leak.

Time Time II Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior BOOTH OPERATOR:

BOOTH OPERATOR: At At the discretion of the discretion of the the Chief Examiner, insert Chief Examiner, insert Event Event 4,4, FWH FWH 4A 4A Tube Tube Leak.Leak.

EVENT INDICATIONS:

APP-007-E7; HTR APP-007-E7; HTR 4A HI/LO HI/LO LVL APP-007-D8; HTR APP-007-08; HTR 38 3B HI/LO HI/LO LVL LVL (-2

(-.2 minutes minutes later) later)

APP-007-E8; HTR APP-007-E8; HTR 48 4B HI/LO HI/LO LVL LVL (Later)

BOP Respond to alarms and references APP-007-E7.

Dispatch an operator to check sight glass level and Level Control SRO/BOP Valve position.

NOTE: The crew may receive a Power Limit Warning ERFIS alarm due to the feedwater transient. If so, they will use the Turbine GV limiter to reduce power to < < 100%.

BOOTH OPERATOR: When requested, FW Heater 4A is flooded and both Normal and Alternate Drains are open. 4A Shell Side Relief valve is cycling. 4B has a high level and the Normal valve is OPEN and the Alternate drain is cycling.

NOTE: The crew may enter AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION due to the transient on the Feedwater system.

AOP-010 steps are listed for reference, but are NOT necessary for successful mitigation of the event.

Enters AOP-O10, AOP-010, MAIN MAIN FEEDWATER/CONDENSATE SRO MALFUNCTION.

MALFUNCTION.

Immediate Action Step:

Immediate .Action* Step:

BOP Check Fdwtr flhnk Feedwater Regulating Valves flnrtinn Rcni iItinn Vlvc Operating properly in nronrki in Al AUTO or ITO or r--.--- r-i**J .

MANUAL.

MANUAL.*(YES)(YES)

Appendix Appendix DD NUREG-1 021, NUREG-1 021, Rev.

Rev. 9, 9, Supp.

Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4

_4..;...-_ _ _ _ Page 11 11 28 _ _---11 of ...,;2;;;,;8;......

Event

Description:

Event

Description:

FWH 4A Tube Leak.

Time I Position  ! Applicants Actions or Behavior Applicant's Continuous Action Step:

I D-.&.-... k; IKIfi r-. Ci.,.. A RO KU CheckReactorTripSetpoint JLJII IL being

.jI IL,r I IQi..LiJI I I IJ ...eL 1 LJII I approached.

ajji LJ.,I ILl. (NO, 11J.J, Go U To I Li Step )L.) 4) 1.)

I IF Prfrir Trir irirf TI.4FKI IF Reactor Trip Setpointis being approached, THEN trip the Reactor +rr th Prfrr nd Go and (o To Path:-1.

Pth-1 RO/BOP Make PA Announcement For Entry into AOP-01 O. 0.

SRO Goes to Step 21, Pipe Break/Leak.

Match Steam Flow With Feed Flow:

  • . Reduce Turbine Load to match Feed Flow and Steam Flow BOP using Attachment 1.
  • Check Feed Flow matched with Steam Flow. (YES)
    • Stop the power reduction Determine location of the leak:
  • . Visual observation of an external leak.

CREW ** Feed Water Heater level alarms.

    • Feed Water Heater Normal and Alternate drain valve positions.
    • Feed Water Heater #1 & #2 Emergency Dump valve positions.

If tube leakage is occurring, then bypass the affected string of heaters CREW for repair of defective tubes using OP-407, Heater Drains and Vents.

Determine that heater must be bypassed and isolated per OP-407 and SRO commence a plant down power to << 517 MWe.

Appendix D D NUREG-1 NUREG-1 021, 021, Rev. 9, Supp.SUpp. 11

AppendixDD Appendix OperatorAction Operator Action Form Form ES-D-2 ES-D2 OpTest Op TestNo.:

No.: 1 Scenario##

Scenario 22 Event##

Event 55 Page Page 12 12 ofof 28 28

......;...- ~-------- ~------~I EventDescription:

Event

Description:

Downpowerto Downpower to support support removing removing FWHFWH 4A 4A from from service.

service.

Time Time II Position Position II Applicants Actions Applicant's Actions oror Behavior Behavior NOTE:

NOTE: The crew The crew will will use use OP-105, OP-105, MANEUVERING MANEUVERING THE THE PLANT PLANT WHEN WHEN GREATER THAN GREATER THAN 25% 25% POWER, POWER, to to perform the plant down perform the plant down power.

power.

Only the Only the applicable applicable stepssteps have have been been listed.

listed.

SRO SRO Notify the Load NoUfy the Load Dispatcher Dispatcher that that unit unit load will be load will be reduced.

reduced.

Notify RC Notify RC that that increased increased radiation radiation levels levels are are expected expected in in the the CVCV Pump Pump SRO SRO Bays and Bays and Pipe Pipe Alley Alley due due to to normal normal shutdown shutdown crud bursts.

crud bursts.

Monitor the Monitor the highest highest operable operable Power Range Channel Channel and and the highest highest RO RO operable Intermediate Range Channel on NR-45.

IF Reactor Engineering has not provided technical guidance, THEN SRO/RO determine the reactivity change chanqe required.

IF additional letdown flow is desired, THEN:

RO ** Start additional Charging Pumps as necessary,

  • . Place additional letdown orifice in service. service .

IF a significant change in RCS Boron concentration occurs, THEN RO energize additional PZR heaters as needed.

NOTE:

NOTE: OP-301, OP-301, Section Section 8.2.8 8.2.8 Quick Quick Boration Boration Checklist (shaded area) area) is is included included in the following in the following steps, steps, butbut may may be be used used following following the the commencem commencement ent of of the the plant plant down down power.

power.

DETERMIN DETERMINE E the the amount amount of of Boric Boric Acid Acid toto add add toto the the RCS RCS andand RO RO OBTAIN OBTAIN an an independent independent checkcheck of of the the volume volume required.

required.

NOTE:

NOTE: -.160

-160 gallons gallons of of Boric Boric Acid Acid will be added will be added based based on on rods rods stepping stepping to to 160 160 steps.

steps. (The(The crew crew will will add add Boric Boric Acid Acid in in 2-4 2-4 batches.)

batches.)

RO RO OBTAIN OBTAIN permission permission from from the the CRSS CRSS OR OR thethe SSO SSO toto borate.

borate.

Appendix Appendix DD NUREG-1021, NUREG-1 Rev. 9,9, Supp.

021, Rev. Supp. 11

Appendix 0D Operator Action Operator Action Form ES-D-2 Form ES-D-2 Op Test Op Test No.:

No.: 1 Scenario ##

Scenario 22 Event ##

Event 5

_5;;...-_ _ _ _ Page Page 13 13 of .....:2:.;;8 of 28_ _ _-11 Event

Description:

Event

Description:

Downpower to Downpower to support support removing removing FWHFWH 4A 4A from from service.

service.

Time Time ~I Position Position ~ Applicants Actions or Behavior Applicant's Behavior RO RO PLACE the the RCS RCS MAKEUP MODE MODE selector selector switch to BORATE.

RO YIC-1 13, BORIC ACID TOTALIZER to desired quantity.

SET YIC-113, IF desired, THEN PLACE FCV-113A, FCV-1 13A, BORIC BORIC ACID FLOW, in MAN MAN RO RO AND ADJUST using the UP and DOWN pushbuttons.

RO Momentarily PLACE the RCS MAKEUP SYSTEM switch to START.

IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:

RO ** Rod Motion is blocked or in the wrong direction

    • TTpv AVG increases
    • Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:

RO ** FCV-113A, FCV-1 13A, BORIC ACID FLOW, closes.

    • 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.

The RCS MAKEUP SYSTEM is OFF.

IF desired, THEN FLUSH the Boric Acid flow path as follows:

    • PLACE the RCS MAKEUP MODE selector switch in the ALT ALT DILUTE position.
    • SET YIC-1 14, PRIMARY WTR TOTALIZER to 115-20 YIC-114, 5-20 gallons.
    • PLACE FCV-1 FCV-114B,14B, BLENDED MU TO VCT to CLOSE.
    • Momentarily PLACE RCS MAKEUP MAKEUP SYSTEM switch to START.

START.

RO ** IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:

Unanticipated Rod Motion o0 Unanticipated Motion Primary o0 Primary Water addition reaches the addition the desired desired value

    • WHEN the desired amount of Primary Water has has been added added to the RCS, THEN verify the following:

the RCS, o0 FCV-1 FCV-114A14A closes.

FCV-113B o0 FCV-1 closes.

1 3B closes.

IF in Auto, THEN the operating Primary Water_Pump o__IF_in_Auto,_THEN_the_operating_Primary 0 Water Pump 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 # 22 Event ##

Event _5~5 ____ Page Page 14 14 of 28_ _ _...,1 of ,..;2;;,;;8 Event

Description:

Event

Description:

Downpower to Downpower to support support removing removing FWHFWH 4A 4A from from service.

service.

Time Time III Position Position III Apolicants Actions Applicant's Actions or Behavior or Behavior stops.

stops.

0o The The RCS MAKEUP SYSTEM RCS MAKEUP SYSTEM is is OFF.

OFF.

RETURN the RCS Makeup Makeup System to automatic automatic as follows:

  • . VERIFY FCV-114A FCV-1 14A is in AUTO.
  • . PLACE PLACE FCV-114B FCV-1 1 4B to the AUTO position.position.

RO RO *. PLACE PLACE the RCS MAKEUP MODE RCS MAKEUP MODE switch in AUTO.

  • . VERIFY FCV-1 FCV-113A1 3A is in AUTO.
  • . Momentarily PLACE the RCS MAKEUP MAKEUP SYSTEM switch in the START position.

RECORD, in AUTO LOG, as indicated by PRIMARY WATER RO YIC-1 14 AND Boric Acid TOTALIZER, YIC-113 TOTALIZER, YIC-114 YIC-1 13 the total amount of Primary Water AND Boric Acid added during durinq the boration.

MONITOR parameters for the expected change in reactivity AND RO inform the CRSS OR the SSO of the results of the boration.

IF EH Turbine Control is in OPER AUTO, THEN reduce turbine load as follows:

BOP *. Place the EH Turbine Control in the desired position: IMP IN.

  • . Set the desired load in the SETTER.
  • . Select the desired Load Rate.
    • Depress the GO pushbutton.

Verify proper programming of the following:

RO ** TAvG TAVG tracks within 5 degrees FF of TREF. T REF.

.* PZR level tracks within 5% of reference level.

Maintain the control rods above the minimum allowable rod height SRO/RO borating the RCS lAW OP-301.

BOOTH BOOTH OPERATOR: As soon soon as the power power reduction is is 2: 5% or at the discretion discretion of of the Chief Examiner, insert the next event.

Examiner, insert event.

Appendix Appendix D D NUREG-1 021, NUREG-1 021, Rev.

Rev. 9, 9, Supp.

Supp. 11

Appendix 0D Operator Action Operator Form ES-D-2 Form ES-D-2 Op Test Op Test No.:

No.: 1 Scenario ##

Scenario 22 Event ##

Event 66 and and 77 Page Page 15 15 of of 28 28

~- ---------- ~------~I Event

Description:

Event

Description:

Rods continue Rods continue to to step step requiring requiring aa Reactor Reactor Trip, Trip, Failure Failure of of the the Turbine Turbine to to Trip.

Trip.

Time ~ Position Position II Applicants Actions or Behavior Applicant's Behavior BOOTH OPERATOR: At the discretion of the Chief Examiner, insert Event 6, Control Rods continue to step requiring a Reactor Trip.

EVENT INDICATIONS:

Rod speed indication and directional lights Control Rod step counters RD notices that rods are stepping when not demanded and performs RO RD RO AOP-OO1, MALFUNCTION OF REACTOR Immediate Actions of AOP-001, CONTROL SYSTEM.

Immediate Action Step:

RD RO Check unexpected rod motion motion in progress. (YES)

Action Step:

Immediate Action RD RO Check Reactor Power greater than 15%. (YES)

Immediate Action Step: Step:

Check Turbine Load:

CheckTurbine Loa&

RO/BOP ** Control rods stepping in AND unexpected Control. unexpected load reduction in progress. (NO) .

OR

.* Unexpected Unexpected load reduction has occurred. (NO)

Immediate Action Step: Step:

Attempt to Stop Rod AttempttoSt6p Rod Motion as follows:

.* IF ROD BANK SELECTOR Switch is in AUTO, THEN place the IFBODBANKSELECTORSwitch ROD BANK SELECTOR Switch in ROD I3ANKSELECTOHSwitch in Manual.

Manual.

RD RO

.* IF IF ROD ROD BANKBANK SELECTOR Switch is is in in Manual, Manual, THEN place the theRODROD BANK BANK SELECTOR Switch in Auto. Auto.

.* IF IF Rod Rod Motion Motion does NOT stop, THEN NOTstop, THEN trip trip the Reactor and and Go Go To PATH-i.

PATH..:l.

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 Test No.:

No.:

Op Scenario #

Scenario 2 Event #

Event and 77 66 and

~~------

Page Page 16 16 of of 28 28

~------~I Event

Description:

Event

Description:

Rods continue to step requiring Rods requiring a Reactor Reactor Trip, Failure Failure of the Turbine to Trip.

Time IIH Position III Applicants Actions or Behavior Applicant's RO Manually trips the Reactor by depressing the Reactor Trip pushbutton.

Notices that the Turbine failed to trip. Attempts to manually trip the BOP turbine by depressing the Turbine Trip pushbutton and THINK pushbutton simultaneously.

Turbine will not trip from the RTGB. BOP manually runs back the turbine:

BOP ** Verifies the Turbine is in TURBINE MANUAL.

    • Depresses the GV DOWN and FAST button simultaneously until ALL GV valves indicate CLOSED.

Immediate Action Step:

RO Reactor Tripped. (YES)

Immediate Action Step:

BOP Turbine Tripped.(NO)

Turbine.. (YES, RLinback Trip or Runback the Turbine.

Runback was successful)

Immediate Action Action' Step:

Step:

BOP E-1 AND E-2 energized. '(YES)(YES)

Immediate Action Step:

RO SI Initiated. (YES)

Appendix D D NUREG-1021 , Rev. 9, NUREG-1021, g, Supp. 11

Appendix DD Appendix OperatorAction Operator Action Form Form ES-D-2 ES-D-2 TestNo.:

OpTest No.: 1 Scenario##

Op Scenario

- 22 Event##

Event 8,9andlO 8,9

~~~~--

and 10 Page Page 1717 ofof 28 28

~~----~I EventDescription:

Event

Description:

FW Break FW Break on on S/G S/G "B" B inside inside CV CV with with aa loss loss of of ALL ALL feedwater.

feedwater. CV CV Spray Spray Pump Pump A fails "A" fails toto start, start, Phase Phase BB valves valves FCV-626 FCV-626 and and CVC-381 CVC-381 fail fail to to CLOSE.

CLOSE.

Time Time 1 Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior BOOTH OPERATOR:

BOOTH OPERATOR: As As soon soon as as the the Reactor Reactor Trips, Trips, verify verify Events Events 8, 8, 99 and and 10 10 are are inserted. IfIf requested, inserted. requested, Manually Manually trip trip the Turbine locally.

the Turbine locally.

NOTE:

NOTE: The crew The crew may may take take action action lAWlAW OMM-022 OMM-022 to to start start CV CV Spray Spray Pump Pump A and "A" and shut shut PhasePhase BB valves valves CVC-381 CVC-381 and FCV-626 following and FCV-626 following verification of verification Immediate Actions.

of Immediate Actions. The The crew crew may may also also stop stop ALL ALL RCPs RCPs due to due to aa Phase Phase BB isolation.

isolation.

CREW CREW Open Foldout Open Foldout A. A.

  • . RCP Trip criteria. IF BOTH RCP BOTH conditions are met, THEN stop stop all RCPs: (NO)

RCPs: (NO)

RO 0o SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF OF DELIVERING FLOW TO THE CORE DELIVERING 0o RCS Subcooling - < - < 35 degrees F [55 degrees F]

  • . SI actuation criteria. IF EITHER condition occurs, THEN Actuate SI SI and Go To PATH-1,PATH-i, Entry Point A:

RO/ R 0 SRO/RO o0 RCS Subcooling - < - < 35 degrees F [55 degrees F]

o0 Level- CAN NOT BE MAINTAINED>

PZR Level - MAINTAINED> 10% 10% [32%].

    • MSR Isolation criteria. IF ANY Purge OR Shutoff Valve does not BOP BOP indicate indicate fully closed, THEN place the associated associated RTGB Switch Switch to CLOSE.

CLOSE.

Appendix Appendix DD NUREG-1021, NUREG-i Rev. 9,9, Supp.

021, Rev. Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 8, 9 and 10_ _ Page

_8;.:.,...;,9...;;;a;.;.;nd;;..1;..;;O 18 28_ _ _-11 of ...,;2;;,;;8 Event

Description:

FW Break on S/G SIG "B"B inside CV with a loss of ALL feedwater. CV Spray Pump A fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE.

"A" I Time I Position I Applicants Applicant's Actions or Behavior

    • S/G isolation criteria. IF both the following conditions are met, THEN perform the following:
  • . Any S/G pressure is decreasing in an uncontrolled manner OR
  • . Any S/G has completely depressurized.

AND

  • . At least ONE S/G SIG is intact.

0o Reset SI.

0o CLOSE the appropriate AFW isolation valves to the SIG AND OPEN the associated breaker for the faulted S/G valves closed.

  • S/G SIG "B" B
  • . V2-14B, SDAFW PUMP DISCH, MCC-9, CMPT--1C CMPT 1C

.* V2-16B, AFW HDR DISCH, MCC-10, MCC-1O, CMPT - 4F -

0o WHEN the faulted S/G SIG drys out, THEN dump steam from intact S/Gs to control RCS repressurization.

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)

BOP Verify both MDAFW pumps are running. (NO)

If additional Feedwater is required, start the SDAFW pump. (NO, BOP Pump started but tripped)

RO Verify 2 SI pumps running. (YES)

RO Verify Both RHR pumps running. (YES)

Appendix D D NUREG-1 021, Rev. 9, Supp. 1 1

AppendixDD Appendix OperatorAction Operator Action Form Form ES-D-2 ES-D-2 TestNo.:

No.: 1 Scenario##

OpTest Op

-- Scenario 22 Event##

Event 8, 9 and 10 8,9and10 Page Page 1919 ofof ......;.;.;.---...,1 28 28 EventDescription:

Event

Description:

FW Break FW Break on on S/G S/G "B" inside CV B inside CVwith with aa loss loss ofofALL ALLfeedwater.

feedwater. CV CV Spray Spray PumpPump A fails "A" fails toto start, start, Phase Phase BB valves valves FCV-626 FCV-626 and and CVC-381 CVC-381 failfail toto CLOSE.

CLOSE.

Time Time II Position Position II ApplicantsActions Applicant's Actions oror Behavior Behavior RO RO Verify SI Verify valves are SI valves are properly properly aligned.

aligned. (YES)(YES)

RO RO At least At least 11 CCW CCW pump pump isis running.

running. (YES)

(YES)

BOP BOP All SW All SW and and SW SW Booster Booster pumps pumps running.

running. (NO) (NO)

Attempt to Attempt to start start all all SW SW andand SW SW booster booster pumps.

pumps. (NO,(NO, SW SW Booster Booster BOP BOP Pump "A" Pump A isis unavailable) unavailable)

BOP North OR OR South South SW Header Lo Pressure alarm illuminated. 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 BOP Verify Verify Control Control RoomRoom Vent aligned aligned for Pressurizatio Pressurization Mode. (YES) n Mode. (YES)

BOP BOP Verify Verify bothboth EDGs EDGs running.

running. (YES)

(YES)

CONTINUO CONTINVOUS US ACTION ACTION*STEP:STEP:

BOP BOP Restart Restart battery battery chargers chargers within within 3030 minutes minutes of of power power.loss using OP OP-loss using 601.

601.

CONTINUO CONTINUOUS US ACTION ACTION STEP: STEP:

RO RO CV Pressure has CVPressure has remained remained below b.elow 10 10psig~

psig. (NO)

(NO)

RO RO Verify Verify CV CV Spray Spray initiated.

initiated. (YES)

(YES)

Appendix Appendix DD NUREG-1 NUREG-1021, 021, Rev.

Rev. 9,9, Supp.

Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 8, 9 and 10 8,9 Page 20 of 28

~~~~-- ~---~I Event

Description:

FW Break on S/G SIG "B" B inside CV with a loss of ALL feedwater. CV Spray Pump A fails to start, Phase B valves FCV-626 and CVC-381 fail to CLOSE.

"A" Time II1 Position I Applicants Actions or Behavior Applicant's Verify all CV Spray pumps running with valves properly aligned.

RO (NO, CV Spray Pump "A" A did not Auto start)

NOTE: The crew may have already taken action to start CV Spray Pump A per guidance in OMM-022.

"A" RO Verify - 12 GPM spray additive tank flow. (Will require adjustment)

Verify Phase B isolation valves closed. (NO, takes action to close RO CVC-381 and FCV-626 from the RTGB.)

CRITICAL TASK: Verify CVC-381, Phase B CV Isolation Valve is closed prior to PATH-i.

transitioning from PATH-1.

RO Stop all RCPs. (May be previously stopped)

Verify all MSIVs and MSIV bypass valves closed. (YES)

BOP (Operator will ensure that switches for the MSIVs are placed in the CLOSE position)

SRO Locally open breaker for HVS-1 at MCC-5.

RO RCS pressure> 1350 1350 psig. [1250 psig] (YES)

BOP At least 300 GPM AFW flow available. (NO)

BOP Level in at least one S/G greater than 8% [18%] (NO)

Appendix D D NUREG-1 021, Rev. 9, Supp. 1 1

Appendix D D Operator Action Operator Action Form ES-D-2 Form ES-D-2 Op Test Op Test No.:

No.:

Event

Description:

Event

Description:

1 Scenario ##

Scenario FW Break FW Break on 22 on S/G Event ##

Event B inside S/G "B" inside CV 8, 9 and 10_ _ Page

_8;.:"..;;,,9.,;;;a;.;,;nd;;,..1;.,;;O CV with aa loss loss of of ALL Page ALL feedwater.

21 21 feedwater. CV of ,....;2::..;;8 of CV Spray 28_ _ _-11 Spray Pump Pump A fails "A" fails to to start, start, Phase Phase B B valves valves FCV-626 FCV-626 and and CVC-381 CVC-381 fail fail to to CLOSE.

CLOSE.

Time II Position II ADDlicants Actions or Behavior Applicant's Behavior BOP Align AFW valves.

BOP At least 300 GPM AFW flow verified (NO)

Reset SPDS and Initiate monitoring of Critical Safety Function Status RO Trees Transition to FRP-H.1, RESPONSE TO LOSS OF SECONDARY SRO HEAT SINK.

Check Total Feed Flow less than 300 GPM due to operator action.

BOP (NO)

Determine if Secondary Heat Sink is required:

  • . Check RCS pressure greater than any non-faulted S/G RO pressure. (YES)
    • Check RCS temperature greater than 350 degrees F [310 degrees F] (YES) r%....4. A4.

Continuous Action Step:

..øJI I LII IUIJU IiLLIIJI I LejJ.

Check Check Any TWO TWQ S/G Wide Ranae Range Levels less than 10%. 10%. Ii u[19%1 9%1 (NO

-a(NO) bL)I-BOP A ,

IF IF any TWO S/GWR levels decreaseto decrease. to < < 10% [19%1.

[19%], THENGo THEN Go To step Step 5.

BOP BOP Check CST level greater than 10%. 10%. (YES)

RO Verify All S/G Blowdown and Sample Isolation Valves CLOSED. CLOSED. (YES)

BOP BOP Check Check AFW Lines INTACT. INTACT. (YES)

Appendix Appendix D D NUREG-1 NUREG-1 021, 021, Rev.

Rev. 9, 9, Supp.

Supp. 11

Appendix 0D Operator Action Operator Action Form ES-D-2 Form ES-D-2 Op Test Op Test No.:

No.: 1 Scenario ##

Scenario 22 Event ##

Event 8, 9 and 8,9 and 1010 Page Page 22 22 28_ _ _...,1 of .....;2;.;8 of

~-

Event

Description:

Event

Description:

FW Break FW Break on SIG "B" on S/G B inside inside CV CV with with aa loss loss of of ALL ALL feedwater.

feedwater. CV Spray Pump CV Spray Pump A fails "A" fails toto start, start, Phase Phase B B valves valves FCV-626 FCV-626 and and CVC-381 CVC-381 fail fail to to CLOSE.

CLOSE.

Time III Position ~ ADelicants Actions or Behavior Applicant's Try to Establish Motor Driven AFW Flow To At Least One S/G:

BOP

    • Check AFW Pump Breakers TRIPPED. (NO)

BOP Verify AFW HDR DISCH valves (V2-16A/B/C) (V2-1 6AJBIC) OPEN. (YES)

BOP Check AFW flow to SIGs S/Gs>> 300 GPM. (NO)

Attempt to Start SDAFW Pump:

BOP

    • Verify STEAM DRIVEN AFW PUMP STM SHUTOFF VALVES OPEN. (V1-8A, (Vi-8A, V1-8B, Vi-8B, V1-8C) (NO)

SRO IF the steam supply valves cannot be opened, THEN Go To Step 11. 1 1.

Locally Investigate AND Attempt To Restore AFW Flow:

BOP ** Verify AFW Pump suction supply is available. (YES)

    • Position MDAFW Pump LOCAUREMOTE LOCAL/REMOTE Switch to LOCAL.

Attempt to reclose any tripped breakers:

    • Depress the MDAFW Pump local STOP pushbutton.

BOP

    • Depress the MDAFW Pump local START pushbutton.
    • Check MDAFW Pump started. (YES)

Continuous Continuous* Action Action Step:

Step:

BOP BOP Check Check AFW AFW FlowFlow To S/GsSIGs greater than than 300 GPM.

GPM. (YES)

(YES)

Reset SPDS and Return to Procedure and Step In In Effect.

Effect. (PATH-i, (PATH-1, RO grid grid location location B-i 1)

B-11)

Appendix Appendix D 0 NUREG-iO2i, NUREG-1021 , 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 22 Event ##

Event 8, 9 and 10_ _ Page

.....;8;;;.:.,..;;.9.;;;a;.;.;nd;;...1;.,;;O Page 23 23 of 28_ _ _...,1 of ....;2:;;8

~-

Event

Description:

Event

Description:

FW Break FW Break onon S/G S/G "B" B inside inside CV CV with with aa loss loss of of ALL ALL feedwater.

feedwater. CVCV Spray Spray Pump Pump A fails "A" fails to to start, start, Phase Phase B B valves valves FCV-626 FCV-626 and and CVC-381 CVC-381 fail fail to to CLOSE.

CLOSE.

Time i Position ~ Applicants Actions or Behavior Applicant's BOP Control AFW flow to maintain S/G levels between 8% [18%] and 50%

RCP Thermal Barrier Cooling Water High or Low Flow alarms RO illuminated. (YES)

RO At least One Charging Pump Running. (YES)

BOP Place Steam Dump Mode switch to Steam Pressure.

RO RCS Temperature stable at or trending to 547 degrees F. (NO)

RO RCS temperature greater than 547 degrees F. (NO)

BOP Attempt to limit cooldown.

If RCS cooldown continues and is not due to SI flow, Then close BOP MSIVs and MSIV Bypasses.

RO PZR PORVs closed. (YES)

P0 RO PZR Spray and Aux Spray valves closed. (YES)

RO At least One RCP running. (NO)

Any SIGS/G with uncontrolled uncontrolled depressurization or completely BOP depressurized (YES) (YES)

Reset Reset SPDS and Initiate Initiate monitoring monitoring of Critical Safety Function Function Status RO Trees.

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 22 Event ##

Event 8, 9 and 8,9 and 10 10 Page Page 24 24 of of 28 28

~- ~~------ --------~I Event

Description:

Event

Description:

FW Break FW Break on SIG "B" on S/G inside CV B inside CV with with aa loss loss of of ALL ALL feedwater.

feedwater. CV CV Spray Spray Pump Pump A fails "A" fails to to start, start, Phase Phase B B valves valves FCV-626 FCV-626 and and CVC-381 CVC-381 fail fail to to CLOSE.

CLOSE.

Time Time II Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior SRO Transition to EPP-11,EPP-11, FAULTED FAULTED SIG ISOLATION.

ISOLATION.

BOP BOP Maintain at least Maintain least One S/G SIG available for RCS Cooldown.

Identify intact S/Gs:SIGs:

BOP

  • . ANY S/G SIG Pressure Stable or Increasing (YES,"A" (YES,A and "C") C)

Identify faulted S/Gs:SIGs:

BOP ** Any S/G Pressure decreasing In An Uncontrolled Manner OR SIG Completely Depressurized. (YES, "B")

Any S/G B)

BOP Isolate faulted S/G using Supplement G. (See pg. 26-27 for steps)

Maintain a faulted S/G SIG in the isolated condition during subsequent BOP recovery actions unless needed for cooldown.

BOP Check CST Level greater than 10%. (YES)

BOP Check available Secondary Radiation Monitors normal. (YES)

BOP Check any SIG S/G with an uncontrolled level increase. (NO)

SRO Go To PATH-i, PATH-1, Entry Point C.

SRO SRO Reset Reset SPDS SPDS and and initiate initiate monitoring monitoring of of CSFSTs.

CSFSTs.

SRO SRO Open Open Foldout Foldout B. B.

Appendix Appendix D D NUREG-i 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 22 Event ##

Event 8,*...;.9...;,;a;.;.;nd;;.,.1;..;.O

_8;...:. 9 and 10_ _ Page Page 25 25 of .....;2~8 of 28_ _ _-I1

~-

Event

Description:

Event

Description:

AN Break FW Break on SIG "B" on S/G B inside inside CVCV with with aa loss loss of of ALL ALL feedwater.

feedwater. CV CV Spray Spray Pump Pump A fails "A" fails to to start.

start, Phase Phase B B valves valves FCV-626 FCV-626 and and CVC-381 CVC-381 fail fail to to CLOSE.

CLOSE.

Time II1 Position III Applicants Actions or Behavior Applicant's Behavior

  • . SI Termination criteria; 0o IF ALL conditions below occur. occur, THEN Go To EPP-7. EPP-7, SI TERMINATION:
  • . RCS subcooling greater than 35°F [55 OF] °F]
  • . Heat Sink established as follows:

0o Total feed flow to intact S/Gs S/Gs> > 300 GPM OR SRO 66 PPH.

0.2x10 0.2x10 OR o

0 Level in at least one intact S/G > > greater than 8% [18%]

  • . RCS pressure >1650 PSIG [1750 PSIG] AND STABLE OR INCREASING
  • . PZR level> 10% [32%]

SRO Determines that SI termination criteria are met and transitions to EPP- EPP 7, SI TERMINATION.

The Chief Examiner may terminate the scenario anytime after flow is established to at least one SIG and the faulted SIG has been isolated lAW Supplement G.

Appendix Appendix D D 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 22 Event ##

Event 8, 99 and 8, and 10 10 Page Page 26 26 of .....;2;;;.;8 of 28_ _ _~1

~-

Event

Description:

Event

Description:

FW 8reak FW Break onon S/G B inside S/G "8" inside CV CV with with aa loss loss of of ALL ALL feedwater.

feedwater. CVCV Spray Spray Pump Pump A fails "A" fails to to start, start, Phase Phase 8B valves valves FCV-626 FCV-626 and and CVC-381 CVC-381 fail fail to to CLOSE.

CLOSE.

Time I Position Position I Applicants Actions or Behavior Applicant's Pages 26-27 are steps from Supplement G, STEAM GENERATOR ISOLATION to isolate B as a faulted Steam Generator.

SIG "8" Go to the appropriate step from following table: S/G B to be isolated, BOP Go To Step 18.

BOP Check S/G "B" B faulted. (YES)

BOP Vi -3B, MSIV CLOSED. (YES)

Verify V1-3B, BOP Verify MS-353B, MSIV V1-3B Vi -3B BYP CLOSED. (YES)

BOP Verify FRV B CLOSED. (YES)

BOP Verify FRV B BYP CLOSED. (YES)

BOP Verify V2-6B, FW HDR SECTION Valve CLOSED. (YES)

BOP Verify V2-14B, SDAFW PUMP DISCH Valve CLOSED. (YES)

BOP Verify V2-i 6B, AFW HDR DISCH Valve CLOSED. (YES)

V2-16B, BOP Verify STEAM LINE PORV CLOSED. (YES)

BOP BOP Verify Vi -8B, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)

V1-8B, (YES)

Verify S/G BB Blowdown Blowdown and Blowdown Blowdown Sample Valve Status Light BOP BOP Indication CLOSED. (YES)

Appendix Appendix D D NUREG-i NUREG-1 021,021, Rev.

Rev. 9, 9, Supp.

Supp. 11

AppendixDD Appendix OperatorAction Operator Action Form FormES-D-2 ES-D-2 OpTest Op TestNo.:

No.: 1 Scenario##

Scenario 22 Event##

Event 8,9and10 8, 9 and 10 Page Page 27 27 ofof 28

-- - 28

II EventDescription:

Event

Description:

FW Break FW Breakon on S/G S/G "B" B inside insideCV withaaloss CVwith lossofofALL ALLfeedwater.

feedwater. CV CVSpray SprayPump Pump Afails "A" failstotostart, start, Phase PhaseBBvalves valvesFCV-626 FCV-626and and CVC-381 CVC-381 failfailtotoCLOSE.

CLOSE.

Time Time i Position Position i ApplicantsActions Applicant's ActionsororBehavior Behavior Dispatch an Dispatch an operator operator toto the the Pipe Pipe Jungle Jungle to to close close MS-29, MS-29, S/G S/G BB BOP BOP BYPASS DRN BYPASS DRN and and WARM-UP WARM-UP LINE LINE TOTO AFW AFW PUMP (located above PUMP (located above /I right of right of V1-SB)

Vi -8B)

BOP Check S/G Check SIG BB MSIV MSIV Above Above andand Below Below SeatSeat Drain Drain Valves Valves CLOSED.

CLOSED.

BOP (YES)

(YES)

Dispatch an Dispatch an operator operator toto E-1/E-2 E-1IE-2 RoomRoom to to perform perform the the following:

following:

  • . At MCC-9, MCC-9, verify verify V2-14B V2-14B closed closed and and open open breaker breaker V2-14B, V2-14B, BOP BOP SDAFW PUMP SDAFW PUMP TO TO S/G S/G B B (CMPT-1C)

(CMPT-1C)

  • . At MCC-6, verify V1-SB Vi -8B closed closed and and open open breaker breaker V1-SB, Vi -SB, SDAFW PUMP STEAM ISOLATION (CMPT-16M) (CMPT-16M)

Dispatch operator to the Aux. Bldg. to perform the following:

BOP At MCC-10, MCC-i 0, verify V2-i

  • . V2-16B 6B closed and open breaker V2-i V2-16B, 6B, MDAFW PUMP HEADER DISCHARGE DISCHARGE TO S/G B (CMPT-4F))

B(CMPT-4F SRO Go To Step 49.

BOP BOP Check Check All All Faulted Faulted andand Ruptured Ruptured S/Gs S/Gs ISOLATED.

ISOLATED. (YES) (YES)

WHEN WHEN the the faulted faulted SIGs S/Gs drydry out, out, THEN THEN dump dump steam steam fromfrom intact intact SIG S/G to to BOP BOP control control RCS RCS repressurizat ion.

repressurization.

BOP BOP Check Check Any Any SIG S/G RUPTURED RUPTURED.. (NO) (NO)

SRO SRO Return Return to to procedure procedure and step inin effect.

and step effect.

Appendix AppendixDD NUREG-1 021, NUREG-iO2 Rev. 9,9, Supp.

i, Rev. Supp. i 1

HLC-08 NRC HLC-08 NRC SCENARIO 2 TURNOVER SHEET POWER LEVEL: 100%, 9000 MWO/MTUMWD/MTU BORON CONCENTRATION: 766 ppm EQUIPMENT UNDER CLEARANCE:

  • SW Booster Pump "A"A is out of service and under clearance for Motor Coupling Alignment.

o LCO 3.7.7-A has been entered and is in hour 18 of a 72 Action Statement.

o 1 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Expected return is within -18 EQUIPMENT STATUS:

  • Main Turbine bearing #3 has a slightly elevated vibration and is being monitored by Systems Engineering.

INSTRUCTIONS FOR THE WATCH:

  • Maintain power at 100% RTP.

Appendix D0 NUREG-1 021, Rev. 9, 9, Supp. 11

I Appendix Appendix DD Scenario Outline Scenario Outline Form Form ES-D-1 ES-D-1 Facility:

Facility: HB ROBINSON HB ROBINSON Scenario No.:

Scenario No.: 33 Op Test No.:

Op Test No.: 2008 2008 NRC NRC Examiners:

Examiners: Operators:

Operators:

Initial Conditions:

Initial Conditions: ** 7% BOl, 7% BOL, 150150 MWD/MTU, MWD/MTU, 1645 1645 ppm ppm Boron.

Boron.

  • . Booster Pump SW Booster Pump "A" A is is Out-Of-Service for Motor Motor Coupling Alignment.

0o LCO 3.7.7 lCO 3.7.7-A been entered

-A has been entered and and is is in hour 18 18 of of aa 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action action statement.

statement.

0o Expected return is within -1818 hours.

    • 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.

Malt. Type*

Event Type* Event No. Description 11 (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".

low B.

(TS) SRO 5 (M) ALL All Multiple dropped rods requiring a Reactor Trip.

66 (M) ALL All S/G Tube Rupture on S/G C. "C".

(TS) SRO 7 (C) BOP "c" Safety fails 15% open.

S/G C 88 (C) RO Safety Injection Injection Pump C "C" fails to start.

99 (C) BOP S/G Blowdown Sample valves fail to close.

k I * (N)ormal, (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (C)omponent, (M)ajor Appendix Appendix D D NUREG-1 021, NUREG-1 021, Rev.

Rev. 9, 9, Supp.

Supp. 11

I Appendix D Scenario Outline Form ES-D-1 I HLC-08 NRC SCENARIO 3

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 7% Reactor Power, with the Turbine rolling at 1800 RPM, but not synchronized to the grid. A Dedicated Operator (Surrogate) required by SIG level control. The previous shift identified increased procedure, will be stationed for S/G 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-005, POWER OPERATION, to synchronize the Generator to the grid.

The crew will use GP-005 to place the Generator Voltage Regulator in service in preparation to 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 Accumulator "B".

B. The RO will reference APP-002-D4 and take action to repressurize the Accumulator lAW OP-202. The SRO will enter LCO 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 a 500 gpm tube rupture which will require a Safety Injection. On the Safety Injection, S/G "C" C C will fail to start, requiring the RO Safety Valve will fail 15% open and will not close, SI Pump "C" C Blowdown Sample valves will not close as expected.

to start it manually, and S/G "C" The Chief Examiner may terminate the scenario at any time after all possible S/G isolation EPP-i 7.

actions have been taken and the crew has transitioned to EPP-17.

Appendix D NUREG-i 021, Rev. 9, Supp. 11 NUREG-1

II Appendix DD Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 3 SIMULATOR SETUP IC/SETUP:

  • IC-603, SCN 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.
  • Status board is correctly marked up for IC-3.

lC-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 3: SW Pump "A" A Breaker trips on overload.
  • Event 6: S/G Tube Rupture on S/G "C". C.
  • Event 7: S/G "c" C Safety Valve fails 15% open.

EXPECTED PROCEDURE FLOW FLOWPATHPATH OR COPIES NEEDED:

GP-005, Section 8.4; AOP-007; OP-202, Section 8.2.3; AOP-001; AOP-OO1; PATH-1; PATH-i; Foldout A; EPP-1 1; Supplement G; EPP-11; PATH-2; Foldout C.

AppendixD Appendix D NUREG-1021,, Rev. 9, Supp. 11 NUREG-1021

Appendix D Operator Action Form ES-D-2 Op Test No.:

Op Test No.: 1 Scenario ##

Scenario 33 Event ##

Event 1 _ _ _ _ Page

--.;... Page 44 of of .....;2;;.;6 26_ _ _..,1 Event

Description:

Event

Description:

Place Generator VR Place the Generator VA in in service service and and synchronize synchronize the Generator to the Generator to the grid.

grid.

Time I Position I 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 breaker BOP has not tripped, THEN reduce voltage as soon as 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 SLOWL SLOWLY Y in BOP the FAST direction. (Using Reference Setter, sets turbine speed to

.-1802

-1802 RPM and depresses GO)

Verify TAVG TAVG is at the high end of the 547°F to 551°F band and Reactor BOP Power is .:s.< 8%.

Appendix D D NUREG-1 021, Rev. 9, Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test No.: 1

-:..._ Scenario # 3 Event # _ 1 _ _ _ _ Page 5 of 26 _ _----41

_2;;;;,;6~

Event

Description:

Place the Generator VR in service and synchronize the Generator to the grid.

Time I Position I Aijplicants 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 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:

0o Place Turbine Control in TURB MANUAL and use GV Down to shed load to minimum.

0o Verify Reactor Power is < < 10%.

0o Open the North OCB BKR 52/9.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 1

Appendix D Operator Action ESD-2 Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 2 Page 6 of 26

~-------- ~~----~I Event

Description:

< po?~

Inadvertent Turbine Trip with power < P-7.

Time ~ 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 A/B 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:

BOP

  • . Both Turbine Stop Valves closed (YES)

OR

  • . 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

Appendix D Operator Action Form ES-D-2 op Test No.:

Op No.: 1 Scenario # 3 Event #

Event 2 Page Page 7 of 26

~- ~-------- ~------~I Event

Description:

Event

Description:

Inadvertent Turbine Trip with power < P-7.

Inadvertent Time i Position III Applicants Actions or Behavior Applicant's Continuous Action Step: SteD:

Verify Bearing Oil LinLift Pump Pump running:

BOP Check Turbine Speed < 600 RPM. (NO)

WHEN Turbine Speed is <.600 RPM, THEN verify Bearing Oil Lift

< 600 RPM,THENverify Lift 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 TRI TRIP.

P.

Check TTAVG °F to 551°F.

AVG 547 of 551 °F.

(NO) IF Steam Dumps are available THEN:

RO/BO P 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 Charging and Letdown to maintain PZR level -22%.

Determine if the Reactor should be shutdown:

SRO Check Reactor Power stable. (YES)

Appendix D D NUREG-1 NUREG-1 021,021, Rev. 9, Supp. 11

Appendix D Operator Action Operator Form ES-D-2 Form Op Test Op Test No.:

No.: 1 Scenario #

Scenario 33 Event ##

Event 33 Page Page 88 of of 26 26

~-------- ~~----~I Event

Description:

Event

Description:

SW Pump SW Pump "AnA trip.

Time II Position Position III Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 3, Service Water Pump "A" A trips on breaker overload.

EVENT INDICATIONS:

APP-008-F4; SW PMP AlB/C/D APP-OOS-F4; AIBICID OVLD APP-008-F7; SOUTH APP-OOS-F7; SOUTH SW HDRHDR LO LO PRESS PRESS APP-008-F8; NORTH SW HDR LO APP-OOS-FS; LO PRESS APP-002-A8/B8/C8/D8; HVH-1/213/4 APP-002-AS/BS/CS/DS; HVH-1121314 WTR OUTLET LO FLOW Recognizes that SW Pump "A" A has tripped and references applicable RO/BOP AP P-008-F4.

APP-008-F4.

APP-008-F4 actions:

If an operating SW Pump has tripped, perform the following:

0o Start a standby pump. (Will start SW Pump "B" B or "D")

D)

BOP 0o Dispatch an operator to check breaker and current limiter fuses for SW Pump A - 480V Bus E-1 E-1,, CMPT 20B.

0o COW Heat Exchanger return valves to maintain Throttle CCW header pressure at 40 - 50 psig.

Appendix D D NUREG-1 021, Rev. 9, Supp. 11

Appendix D D Operator Action Operator Form Form ES-D-2 ES-D-2 Op Test No.:

Op Test No.: 1 Scenario ##

Scenario 33 Event ##

Event 44 Page Page 99 of of 26 26

~- ~-------- ~---~I Event

Description:

Event

Description:

Low pressure Low pressure on on SI SI Accumulator Accumulator "B".

8.

Time II Position IH Applicants Actions or Behavior Applicant's Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 4, Low pressure on SI Accumulator "B", B.

EVENT INDICATIONS:

HI/LO PRESS APP-002-D4; SI ACCUM B HI/LO Decreasing Accumulator B pressure Recognizes that SI Accumulator "8" B pressure is decreasing slowly and RD RO references APP-002-D4.

Reviews, briefs and directs Accumulator repressurization using OP- OP SRO 202, SAFETY INJECTION AND CONTAINMENT VESSEL SPRAY SYSTEM, Section 8.2.3.

RD RO Verify HIC-936, ACC VENT HDR FLOW CLOSED. (YES)

RD RO Verify SI-855, ACC NITROGEN ISOLATION OPEN. (YES)

RD RO SI-853B, VENT.

OPEN SI-8538, WHEN the desired pressure is obtained, (Normal operating pressure is RD RO 630 PSIG) THEN close SI-853B.SI-8538. (APP-002-D4 will clear)

Appendix Appendix D D NUREG-1021, NUREG-1021, Rev. Rev. 9, 9, Supp.

Supp. 11

Appendix D D Operator Action Form ES-D-2 Op Test No.:

Scenario # 33 Event # 5, 5,66

~--------

Page 10 10 of 26

~------~I Event

Description:

Multiple dropped rods requiring a Reactor Trip.

"en.

S/G Tube Rupture on S/G C.

Time Position I[ Applicant's Actions or Behavior Applicants BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 5, Multiple dropped rods. When the reactor has been tripped, verify that Event 6, SIG "C" C Tube Rupture has been entered.

EVENT INDICATIONS:

APP-005-F2; ROD BOTTOM ROD DROP RBLs for Control Bank C, Group 2 are LIT Decreasing SUR Decreasing power.

Recognizes multiple dropped rods and performs Immediate actions of RO AOP-O01, AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM.

RO Check unexpected rod motion in progress. (NO)

RO/BOP Make PA Announcement for entry into AOP-001.

Determine if multiple rods have dropped:

    • Prompt drop present. (YES)

RO

    • More than 1 1 RBL illuminated. (YES)
    • More than 1 1 IRPI indicates on bottom. (YES)

RO Check multiple dropped rods present. (YES)

RO Check Reactor in MODE 1 1 or 2. (YES)

SRO Directs tripping the reactor and enters PATH-1.PATH-i.

IMMEDIATE ACTION STEP:

RO Reactor Tripped. (YES)

Appendix D NUREG-1 021, Rev. 9, Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test Test No.:

No.: Scenario #

Op Scenario 33 Event ##

Event 5, 6 5,

~~-----

Page Page 11 11 of of 26 26

~---~I Event

Description:

Event

Description:

Multiple dropped Multiple dropped rods rods requiring requiring a Reactor Reactor Trip.

S/G Tube Rupture Rupture on S/G SIG "C".

C.

Time I Position IH Applicants Actions or Behavior Applicant's IMMEDIATE ACTION STEP:

BOP Tripped... (YES)

Turbine Tripped IMMEDIATE ACTION STEP:

BOP E-i AND E-2 energized. (YES)

E-l ACTION STEP:

IMMEDIATE ACTION.STEP:

RO SI Initiated. (NO)

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 procepureexit exit is warranted:

warranted:

SRO .* Check attack on Check.atlack RNP site in progress. (NO) onRNPsite

    • Check Check a total loss of SW OR. OR Loss of Lake Robinson Dam integrity in progress. (NO, Go to Step 2)

Continuous Action Step:

Check CheckSI SI signal initiated. (NO, Go to Step Step 4)

RO IF SI initiation occurs during this procedure, THEN Go to PATH-i, IfSI PATH-1, Entry Point A A.

Appendix D D NUREG-102i, NUREG-1021, Rev. 9, Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5, 6 5,6 Page 12 of 26

~~------ ~------~I Event

Description:

Multiple dropped rods requiring a Reactor Trip.

S/G Tube Rupture on S/G "e".

C.

Time I Position I Applicants Applicant's Actions or Behavior SRO Reset SPDS and initiate monitoring of CSFSTs.

CREW Open Foldout A.

  • RCP Trip criteria. IF BOTH conditions are met, THEN stop all RCPs: (NO)

RO 0o SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 00 RCS Subcooling - < - < 35 degrees FF [55 degrees F]

  • SI actuation criteria. IF EITHER condition occurs, THEN PATH-i, Entry Point A: (YES)

Actuate SI and Go To PATH-1, S RO/RO 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 NUREG-iO2i, Rev. 9, Supp. 11 NUREG-1021,

Appendix D D Operator Action Form ES-D-2 Op Op Test Test No.:

No.: 1 Scenario # 33 Event # 7, 8, &

_7;..l"..;;.81..,;' 9 _ _ Page

&;.;..9;..... 13 13 26_ _ _~1 of .....;2;;;.;;6 Event

Description:

Description:

"C" Safety Valve fails open.

S/G C S!G open. Safety InjectionInjection Pump C "C" fails to start.

S/G Blowdown S/G Blowdown Sample valves fail to Sample valves to close.

close.

Time II Position ~ Applicant's Actions or Behavior Applicants BOOTH OPERATOR: When the crew actuates Safety Injection, verify Events 7, 8 and 9 are inserted.

CREW Open Foldout A. (nothing additional to address)

Verify Phase A Isolation valves are closed. (NO, crew will direct local RO isolation of the open S/G Blowdown Sample valves)

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.

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)

RO COW pump is running. (YES)

At least 11 CCW 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)

Appendix D NUREG-1 021, Rev. 9, Supp. 11

Appendix 0D Operator Action Form ES-O-2 ES-D-2 Op Test No.: 1 Scenario # 3 Event # _7;..,l.' &;;..;9~

7, ..;;.8:..;;'

8, & 9 _ _ Page 14 26_ _ _...,1 of .....;2;;.;;6 Event

Description:

C Safety Valve fails open. Safety Injection Pump "C" S/G "C" C fails to start.

SIG Blowdown S/G Slowdown Sample valves fail to close.

Time i Position iI Applicants Actions or Behavior Applicant's 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 EDGs running. (YES)

Verify both EOGs CONTINUOUS ACTION STEP:

BOP Restart battery chargers withinwithin.30 30 minutes of power loss using OP- OP 601.

CONTINUOUS ACTION STEP:

RO Pressure has remained below.10 CV Pressure.hasremained below 10 psig. (YES)

RO Automatic Steam Line Isolation initiated. (NO)

RO Automatic Steam Line Isolation required. (NO)

SRO Locally open breaker for HVS-1 at MCC-5.

RO RCS pressure> 1350 psig. [1250 psig] psigj (YES)

BOP At least 300 GPM AFW flow available. (YES)

Appendix 0D NUREG-1021,, Rev. 9, Supp. 11 NUREG-1021

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 7, 8, &;.;..9~& 9 _ _ Page

_7;"':"..;;.8:..;' 15 of -:2:.;:6 26_ _ _-11

~-

Event

Description:

C Safety Valve fails open. Safety Injection Pump "C" S/G "C" C fails to start.

Slowdown Sample valves fail to close.

S/G Blowdown Time II Position II Applicants Actions or Behavior Applicant's BOP Verify AFW valves properly aligned.

BOP Control AFW flow to maintain S/G SIG level between 8% [18%] and 50%.

RO RCP Thermal barrier cooling water 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)

RO RCS temperature> 547 degrees F. (NO)

RO Attempt to limit cooldown.

If RCS cooldown continues and is not due to SI flow, then close MSIVs RO and MSIV bypasses.

RO PZR PORVs closed. (YES)

RO PZR Spray and Aux Spray valves closed. (YES)

P0 RO At least 11 RCP running. (YES)

RO At least 11 SI Pump Running. (YES)

RO RCS Subcooling less than 35 degrees F [55]. (NO)

BOP Any S/G with uncontrolled depressurization. (YES)

Appendix D D NUREG-1 021, Rev. 9, 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;..."..;;.8.:..;, Page Page 16 16 of ....;2::.;6~

of 26 _ _---i1

~-

Event

Description:

Event

Description:

SIG "C" S/G Safety Valve fails open.

C Safety open. Safety Safety Injection Injection Pump Pump "C" C fails to start.

S/G Blowdown Sample valves fail to close.

S/G Blowdown close.

Time I Position I Applicants Actions or Behavior Applicant's RO Reset SPDS and initiate monitoring of CSFSTs.

SRO Transition to EPP-11, FAULTED SIG ISOLATION.

BOP Maintain At Least One S/G SIG Available For RCS Cooldown.

BOP Any S/G pressure stable or increasing. (YES)

SIG pressure decreasing in an uncontrolled manner OR any S/G Any S/G BOP completely depressurized. (YES)

Isolate faulted S/G SIG using Supplement G, S/G SIG ISOLATION.

BOP (Supplement G Steps are listed on pages 22-25)

Maintain A Faulted S/G In The Isolated Condition During Subsequent BOP Recovery Actions Unless Needed For Cooldown.

BOP Check CST level greater than 10%. (YES)

BOP Check Available Secondary Radiation Monitors normal. (NO)

SRO Transition to PATH-2, Entry Point J.

RO Reset SPDS and initiate monitoring of CSFSTs.

CREW Open Foldout C.

WHEN below 10b0 10-10 amps, THEN energize Source Range detectors RO and monitor recorder.

BOP Request periodic activity samples of all S/Gs Appendix D D NUREG-1 021, Rev. 9, NUREG-1 021, 9, Supp. 11

Appendix DD Appendix Operator Action Operator Action Form Form ES-D-2 ES-D-2 Op Test Op Test No.:

No.: Scenario ##

Scenario 33 Event ##

Event 7, 8, & 9 7,8,&9 Page Page 17 17 ofof 26 26

~- ~~~---- ~---~

Event

Description:

Event

Description:

S/G "C" S/G C Safety Safety Valve Valve fails fails open. Safety Injection open. Safety 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 Time I Position Position II Applicants Actions Applicant's Actions or or Behavior Behavior BOP BOP Place Steam Place Steam Dump Dump Mode Mode SwitchSwitch to to Steam Steam Pressure.

Pressure.

BOP BOP Open QCV Open QCV-1 0426, Bypass

-10426, Bypass Condensate Condensate Polishers.

Polishers.

BOP BOP Close C-48A Close C-48A andand 48B to isolateisolate Hotwell Hotwell Return Return to CST. CST.

RO At Least 11 RCP running. (YES)

RO At Least 11 SI pump running. (YES)

RO RCS Subcooling less than 35 degrees F. [55] [55j (NO)

BOP Ruptured S/GSIG identified. (YES)

RO Maintain at least 11 S/G SIG available for RCS Cooldown.

Verify ruptured steam line PORV setpoint at 1035 1035 psig using using status BOP board.

RO Verify RCS temperature << 547 547 degrees degrees FF prior to MSIV closure.

RO RO Close Close ruptured S/G S/G MSIV MSIV and and MSIV MSIV Bypass.

Bypass.

RO RO Ruptured Ruptured SIG S/G MSIV MSIV and and MSIV MSIV bypass bypass closed.

closed. (YES)

(YES)

Continuous Continuous ActionAction Step:

Step:

RO RO WHEN WHEN ruptured ruptured SIG S/G pressure pressure decreases decreases belowbelow 10351035 psig,psig, THEN THEN verify ruptured Steam verifyruptured Steam Line Line PORVPORV closed.

closed.

Appendix Appendix DD NUREG-1 NUREG-1021, 021, Rev.Rev. 9, 9, Supp.

SUpp. 11

Appendix 0D Operator Action Operator Form ES-D-2 Form ESD-2 Op Test Op Test No.:

No.: 1 Scenario ##

Scenario 33 Event ##

Event 7, 8, &_9;.,...-_

&9

_7...:,._8:...;' Page

_ Page 18 18 of .....:2:..;6 of 26_ _ _-11 n

Event

Description:

Event

Description:

S/G "C S/G Cn 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 Sample S/G Blowdown Sample valves valves fail fail to to close.

close.

Time ~ Position Position II ADDlicants Actions or Behavior Applicant's Behavior IF MDAFW pump is not available, THEN maintain at least 11 S/G RO supply to SDAFW pump.

CREW Close ruptured S/G SIG steam shutoff to SDAFW pump.

BOP Verify S/GSIG Blowdown Isolation and Sample Valves Closed.

Locally close warmup steam supply from ruptured S/G SIG to SDAFW BOP pump.

BOP Locally close above and below seat drains from ruptured S/G.

Isolate Feed Flow to any ruptured 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 S/G before transitioning to EPP-17.

Continuous Action Step:

BOP WHEN ruptured SIG S/G level is greater than 8% [18%], THEN isolate Feed Flow.

Continuous Action Action Step:

Step:

D I.

BOP 1

upen Open* reaers breakers ror for V1..,8, v-14 ana vi-, V2-14 V-1b vaive and V2-16 valve ciosea closed*to isolateisolate ruptured rupturedS/G. SIG.

Control Control Feed Flow Flow to maintain intact S/G level between 8% 8% [18%] and BOP BOP 50%.

Appendix Appendix D 0 NUREG-1021, NUREG-1021 , Rev. Rev. 9, 9, Supp.

Supp. 11

Appendix 0D Operator Action Operator Action Form ES-O-2 Form ES-D-2 Op Test No.:

Op Test No.: -.;...-

Scenario ##

Scenario 33 Event ##

Event _7;..:" 8, &;.;..;9~__

7, ...;;,8:.,;;,

&9 Page Page 19 19 of ...;2=..:6:....-_

of 26 _---l 1

Event

Description:

Event

Description:

SIG "C" S/G C Safety Safety Valve Valve fails fails open.

open. Safety Safety Injection Injection PumpPump "C" fails to C fails to start.

start.

S/G Blowdown Sample S/G Blowdown Sample valves valves fail fail to to close.

close.

Time ~I Position I Applicants Actions or Behavior Applicant's BOP Any other S/GSIG with uncontrolled level increase. (NO)

RO PZR PORVs closed. (YES)

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.

RO Reset SI.

IF offsite power is lost, THEN restart emergency safeguards CREW equipment.

RO Reset CV Spray.

RO Reset Phase A and Phase B.

Establish Instrument Air to CV. IF compressor NOT running running, THEN ,

RO start compressor.

BOP All AC Busses energized by offsite power. (YES)

IF IF RCS pressure decreases below 275 PSIG, PSIG, THEN restart RHR RO Pumps.

BOP BOP Ruptured S/GS/G isolated. (YES, completed during during Supplement G)

Appendix Appendix D 0 NUREG-1 NUREG-1 021, 021, Rev.

Rev. 9, 9, Supp.

Supp. 11

Appendix D Operator Action Form ES-D-2 ESD-2 Op Test No.:

Op No.: 1 Scenario #

Scenario 3 Event #

Event _7;...l,' 8, &;;..;9~

7, ..;;.8:..;'

& 9 _ _ Page 20 of ...;2;;;.;6~

26 _ _----11 Event

Description:

Event

Description:

S/G "C" S/G Safety Valve fails open. Safety C Safety Safety Injection Injection Pump Pump "C" C fails to start.

S/G Blowdown Sample valves fail to close.

Time II Position ~ Applicants Actions or Behavior Applicant's BOP Ruptured S/GSIG pressure> 220 PSIG. (YES)

BOP At least one intact S/G available for RCS cooldown. (YES)

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 < < 543 degrees F AND block TAVG SI signal prior to RO maximum steam dump.

BOP Dump steam from intact S/G to condenser at maximum rate.

RO Align Charging Pump suction to RWST.

RO Establish Charging flow to maintain PZR 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/G pressure stable or increasing. (NO)

Appendix D D NUREG-1 NUREG-1 021, 021, Rev. 9, 9, Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 7, 8, & &;;..9~

_7.;..:.,...;.8.:..;, 9 _ _ Page 21 26_ _ _---i1 of _2_6

--=---

Event

Description:

S/G c Safety Valve fails open. Safety Injection Pump "COO SIG "COO C fails to start.

SIG Blowdown Sample valves fail to close.

S/G Time I Position I Arclicants Actions or Behavior Applicant's Ruptured S/GSIG pressure decreases to < 250 PSIG above pressure of BOP intact S/G SIG used for cooldown. (YES)

Transition to EPP-17, SGTR WITH LOSS OF RCS: SUBCOOLED SRO RECOVERY.

At the discretion of the Chief Examiner, when the crew has transitioned to EPP-17 and SIG "C" C has been isolated as a faulted and ruptured SIG, the scenario may be terminated.

Appendix D NUREG-1 021, Rev. 9, Supp. 11 NUREG-1021,

Appendix D Operator Action Form ES-D-2 Op Test No.:

Op Test No.:

-- 1 Scenario ##

Scenario 33 Event ##

Event 7, 8, &

7,8,

~~~---

& 99 Page Page 22 22 of of 26

~---~I Event

Description:

Event

Description:

SIG "c" S/G Safety Valve fails open. Safety C Safety Safety Injection Pump "c" Injection Pump C fails to start.

SIG Blowdown S/G Blowdown Sample valves fail to close.

Time ~ Position iI Applicants Actions or Behavior Applicant's Pages 22-25 are steps from Supplement G, STEAM GENERATOR ISOLATION to isolate C, as a faulted SIG SIG "C" S/G and to isolate SIG "C" C as a ruptured S/G.

Go to the appropriate step from following table:

BOP

  • . SIG C to be isolated, GO To Step 34 S/G 34..

BOP Check S/G "C" C faulted. (YES)

BOP Verify V1-3C, MSIV CLOSED. (YES)

BOP Verify MS-353C, MSIV V1-3C Vi -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-i 6C, AFW HDR DISCH Valve CLOSED. (YES)

V2-16C, BOP Verify STEAM LINE PORV CLOSED. (YES)

BOP Verify Vi-8C, V1-8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)

Verify SIG "C" Blowdown and Blowdown Sample Valve Status Light S/G C BOP Indication CLOSED. (NO)

Appendix D D NUREG-1021, Rev. 9, Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test No.:

Op Test No.: 1 Scenario #

Scenario 33 Event #

Event 7, 8, 7, 8, &

& 99 Page Page 23 23 of of 26

~~~---- ~---~

Event

Description:

Event

Description:

S/G Cn Safety S/G "C Safety Injection Safety Valve fails open. Safety Injection Pump Cn fails to start.

Pump "C SIG Blowdown S/G Blowdown Sample valves fail to close. close.

Time II Position I Aolicants Actions or Behavior Applicant's Deenergize R-19C.

IF S/G "c" 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/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:

  • . V2-i 6C closed and open breaker V2-16C, At MCC-9, verify V2-16C V2-i 6C, BOP MDAFW PUMP TO S/G C.
  • . 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 0, verify V2-14C closed and open breaker V2-i4C,

.* At MOO-i MCC-10, V2-14C, SDAFW PUMP HEADER DISCHARGE TO S/G C.

BOP Check All Faulted and Ruptured S/Gs ISOLATED. (NO, Go To Step 1) 1)

Go to the appropriate step from following table:

BOP

    • S/G C to be isolated, Go To Step 34.

SIG Appendix D D NUREG-iO2i, NUREG-1021, Rev. 9, g, Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 7, 8, & 9 _ _ Page

_7;,..:.,..;;,8,:,.;&;.;.,;9;;...-. 24 26_ _ _-l of .....;2:..;;6 1

Event

Description:

C Safety Valve fails open. Safety Injection Pump "C" S/G "C" C fails to start.

SIG Blowdown Sample valves fail to close.

S/G Time III Position I Applicant's Actions or Behavior Aøplicants Check S/G "C" C faulted. (NO)

BOP Verify ruptured Steam Line PORV setpoint at 1035 PSIG using Status Board.

BOP Verify Vi -8C, SDAFW STEAM SHUTOFF Valve CLOSED. (YES)

V1-8C, SIG C Blowdown and Blowdown Sample Valve Status Light Verify S/G BOP Indication CLOSED. (NO)

R-1 9C.

Deenergize R-19C.

C Blowdown and Sample valves fail to close, THEN close:

IF S/G "C"

BOP ** SGB-56C, SGBD HX "C" C BYPASS/HX FLOW CONTROL ISOLATION.

  • SGB-60C, SGBD LINE "C" C TO WLU SYSTEM.
  • SGB-38, S/G SIG "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)

E-iIE-2 Room to perform the following:

Dispatch an operator to E-1/E-2

    • At MCC-9, verify V2-16C V2-i 6C closed and open breaker V2-16C, V2-i 6C, BOP MDAFW PUMP TO S/G C.
    • At MCC-6, verify V1-8CVi -80 closed and open breaker Vi V1-8C, -8C, SDAFW PUMP STEAM ISOLATION.

Appendix D NUREG-i 021, Rev. 9, Supp. 11 NUREG-1

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, &;;...9:.....-_

&9

_7;..:.,....;;.8.:....;, Page

_ Page 25 25 of ....;2;;.,;;6 of 26_ _ _-11 Event

Description:

Event

Description:

SIG "C" S/G Safety Valve C Safety Valve fails fails open.

open. Safety Safety Injection Injection PumpPump "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 I Aoolicants Actions or Behavior Applicant's Behavior Dispatch operator to the Aux. Bldg. to perform the following:

BOP *. At MCC-1 MCC-10, 0, verify V2-14C closed and open breaker V2-14C, V214C, SDAFW PUMP HEADER DISCHARGE 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. (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 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 D D NUREG-1 NUREG-1 021, 021, Rev.

Rev. 9, 9, Supp.

Supp. 11

HLC-08 NRC SCENARIO 3 TURNOVER SHEET POWER LEVEL: 7% BOL, 150 MWD/MTU.

BORON CONCENTRATION: 1645 ppm EQUIPMENT UNDER CLEARANCE:

  • SW Booster Pump "A"A is out of service and under clearance for Motor Coupling Alignment.

o 3.7.7-A LCO 3.7.7 -A has been entered and is in hour 18 of a 72 Action Statement.

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 bearing #3 has a slightly elevated vibration and is being monitored by Systems Engineering.

INSTRUCTIONS FOR THE WATCH:

  • Continue with GP-005 and synchronize the Generator to the Grid.

Appendix D 0 NUREG-1 021, Rev. 9, Supp. 11

I Appendix Appendix D D Scenario Outline Scenario Outline Form Form ES-D-1 ES-D-1 Facility:

Facility: HB ROBINSON HB ROBINSON Scenario No.:

Scenario No.: 44 Test No.:

Op Test Op No.: 2008 NRC 2008 NRC Examiners:

Examiners: Operators:

Operators:

Initial Conditions:

Initial ** 50% BOL, 150 MWD/MTU, 1285 ppm Boron.

    • SW Booster Pump "A" A is Out-Of-Service for Motor Coupling Alignment.

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 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%% by Full Range RVLlSRVLIS indication.

    • 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 MaIf.

Malf. Type*

Event Type* Event No. No. Description 1

1 (R) RO Increase power to 75% RTP.

(N) SRO, BOP 2 (I) BOP, SRO Loop 11 THOT T HOT Fails Low.

(TS) SRO 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 (M) ALL High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

66 (M) ALL Failure of the Reactor to trip. (ATWS) SDAFW Pump trips.

7 (M) ALL Small Break LOCA.

(TS) SRO 88 (C) RO Phase Phase AA fails to automatically automatically actuate and several several valves fail to automatically close.

99 (C) RO (C) Safety Safety Injection Injection fails to automatically actuate.

10 10 (C) BOP (C) Control Control Room HVACHVAC Train A and Train Train B B fail to automatically automatically actuate. (HVE-1 (HVE-19A 9A fails to to start start and and HVE-1 HVE-166 fails to stop)

  • (N)ormal, (R)eactivity, (I)nstrument, (I)nstrument, (C)omponent, (M)ajor Appendix Appendix D D NUREG-1021, Rev.

NUREG-1021, Rev. 9,9, Supp.

Supp. 11

I Appendix D Scenario Outline Form ES-D-1 HLC-08 NRC SCENARIO 4

SUMMARY

DESCRIPTION DESCRIPTION The crew will assume the watch with the plant at 50% 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 increase power to 75% and hold for Reactor Engineering instructions.

On cue from the Chief Examiner, Loop 11 T -

1 T-HOT will fail low. The crew will respond lAW APP-003-A4, and remove the instrument from service using OWP- 028, T/DeltaT1. T/DeltaTl. The SRO will enter 3.3.1-1,, Condition E LCO 3.3.1-1 Efor 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 header. 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 psig. The crew should respond using AOP-019, MALFUNCTION OF RCS PRESSURE 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, Turbine bearing #3 vibration will increase to the alarm point and AOP-006, TURBINE ECCENTRICITY ECCENTRICITY!I VIBRATION, will be entered. High bearing vibrations will be reflected on adjacent bearings # #22 and #4. Vibrations will increase to 14 mils and actions in AOP-006 will require the SRO to direct a manual Reactor trip and enter PATH-1. PATH-i. When the crew attempts to trip the reactor, both Reactor Trip pushbuttons will fail and the SRO will enter FRP-S.i, RESPONSE TO NUCLEAR POWER GENERATION/ATWS. The SDAFW Pump will FRP-S.1, 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, 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 will be successful, but three Phase A valves will fail to close and require the RO to manually close these valves from the RTGB. The Control Room HVAC System Train A and Train B will fail to automatically actuate, requiring the BOP to manually align HVAC for Emergency Pressurization Mode.

The scenario can be terminated, at the Chief Examiners Examiner's discretion, after it is determined that SI termination criteria will not be met.

Appendix D D NUREG-i021, NUREG-1021 , Rev. 9, Supp. 11

I Appendix 0D Scenario Outline Form ES-D-1 HLC-O8 NRC SCENARIO 4 SIMULATOR SETUP HLC-08 IC/SETUP

  • IC-604, SCN:

SON: 006_Sim_4.

  • 10-4.

Status board updated to reflect IC-4.

PRE-LOADED EVENTS:

The following events should occur on the reactor trip:

Event 6: Failure of the Reactor to trip. (A TWS) SDAFW Pump trips.

  • Event 8: Phase A valves CVC-204B, CCW-739OOW-739 and SI-855 fail to close on SI actuation.
  • Event 9: Safety Injection fails to automatically actuate.
  • Event 10: Control Room HVAC Train A and Train B fail to automatically actuate.

EVENTSITRIGGERS INITIATED DURING THE SCENARIO:

  • Event 1: Increase power to 75%.
  • Event 2: Loop 11 T THaT HOT fails low.
  • Event 4: PZR PORV PCV-456 fails 70% open.
  • Event 7: Small Break LOCA.

EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

OP-i 05, Section 8.4.2; OWP-028, T/Deita OP-105, T/Delta T 1; AOP-022, Section F; AOP-0i AOP-019;9; AOP-006; PATH-i, PATH-1, FRP-S.1; EPP-4; FRP-P.i; FRP-P.1; Supplement D.

Appendix D 0 NUREG-1021, Rev. 9, NUREG-102i, 9, Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test No.:

Op No.: 1 Scenario #

Scenario 44 Event ##

Event 1 Page Page 44 of 31 31

~- ---------- ~---~I Event

Description:

Event

Description:

Increase power Increase power to 75%.

Time ~ Position I 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.

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).

    • In Automatic and T TAVG AVG Control.

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 D NUREG-i NUREG-1 021, Rev. 9, Supp. 11

Appendix D D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 1 Page 5 of 31

......;....- ---------- ~------~I Event

Description:

Increase power to 75%.

Time III Position I Applicant's Actions or Behavior Applicants 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 amount of water to add to the RCS.

crE~wwill (The crew will calculate - 2000 gallons of water needed needed for the diliitinn to dilution tn 75%power,basedon 7S% nnwr hisd nn Rods Rnds at .175 steps.

it ...;175 stRns Water Witr will be hc added.in 4-6 dilutions) ..

OBTAIN an independent cneckof .the volume of water. required.

permission from the CRSS OR the SSOto OBTAIN permissionJrom OBTAIN SSO to dilute.

PLACE the RCS MAKEUP MODE selector switch in DILUTE.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 1

Appendix D Operator Action Form ES-D-2 Op Test Op Test No.:

No.:

Event

Description:

Event

Description:

1 Scenario #

Scenario 4 Increase power to 75%.

Increase Event ##

Event 1 _ _ _ _ Page

......;.... Page 66 of of ....,;3;.,;.1 31_ _ _-11 Time fi

~ Position II Applicants Actions or Behavior Applicant's SET YIC-1 14, PRIMARY WTR TOTAUZERto SETYIC-114, TOTALIZER to the desired quantity.

IF desired, THEN PLACE FCV 1 14A, PRIMARY WTR FLOW IFdesired,THENPLACEFCV-114A, FLOW DILUTE MAN AND adjust Primary Water Flow rate using the MODE, in MAN:ANDadjust UP/DOWN push pushbuttons.

buttons. .

Momentarily PLACE the RCS MAKEUP SYSTEM SYSTEM switch switch to START.

VERIFY proper operation ofLCV~115A, of LCV-1 1 5A, VCT/HLDP TK DIV valve.

the below conditions occur, THEN momentarily place the IF any of thebelowconditions MAKEUP SYSTEM switch in.the RCS MAKEUPSYSTEM in the STOP position:

    • UnantiCipated Rod Motion.

Unanticipated Rod>Motion.

  • . Primary Water addition .exceeds the desired desired value.

desired amount of PYV WHEN desired PW has been been added, THENverify:

THEN verify:

FCV-1 1 4A, PW

  • . FCV-t14A, PW TO BLENDER;BLENDER, doses. closes.
  • . FCV-1 FCY-114B, 14B, BLENDED BLENDED MU MUTO TO VCT, YCT, closes.
  • . IF in Auto, inAuto, THEN the operating Primary Water Pump stops.
  • . TheHCSMAKEUPSYSTEM The RCS MAKEUP SYSTEM is is OFF.

RETURNt~eRCSMakeup.System.to*al.ltornatic:

RETURN the RCS Makeup System to automatic:

.* VERIFY FCV-114A,PRIMARY FCV-1 14A, PRIMARY WTR FLOW DILUTE MODE is in AUTO.

.* PLACE the RCS MAKEUP MODE switch in AUTO.

PLACEtheHCSMAKEUP

.* Momentarily PLACE Pl.ACE RCS MAKEUP SYSTEM switch to START.

START. ... .

RECORD, in AUTO LOG,*

RECORD,inAUTO LOG, as .indicated* indicated by PRIMARYPRIMARY WATER TOTALIZER, TOTALlZER,.YIC-114 YIC-1 14 total amount amount of PW PW added duringduring the dilution. dilution .

MONITOR parameterspqrameters for the expected change in reactivity AND the.expected*change inform the CRSS OR the informtheCRSS theSSOSSO the results of the dilution.

pfthedilutiort Appendix D D NUREG-1 021, Rev. 9, Supp. 11 NUREG-1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # _22_ _ _ _ _ Page 7 of _3;:;.1:"'-_

31 _~1 Event

Description:

Loop 11 T HOT Fails Low.

THOT Time II Position i Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 2, Loop 1 1 T TH0T HOT failure.

EVENT INDICATIONS:

APP-003-A4; RC LOOPS I1T T DEV HI/LO TAVG APP-003-A6; RCS HIILO APP-003-B4; RC LOOPS TAVG DEV tT (RED) pegged low.

TR-412 Pen 1, I1T 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 1 1 T HOT instrument out of THQT SRO service using OWP-028, T/LlT1. T/liTl.

Perform OWP-028, T/LlT1 T/tT1 actions to remove channel from service.

(APP-036-L1; (APP-036-L 1; will be received when Hagan Rack door is opened.)

The following alarms will be received when the bistables are tripped:

BOP

  • . APP-003-B6; OVERPOWER Ll LT T
  • . APP-005-D5; OTLlT/OPLlT OThT/OPtT TURBINE RUNBACK ROD STOP
  • . APP-003-C6; OVERTEMP Ll T T Review ITS for applicable LCOs:
  • . Table 3.3.1-1, #5, 6 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 />.

SRO

    • Table 3.3.2-1, # 1.f1 .f - Condition D; 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 />.
    • Table 3.3.2-1, # 4.d & 6.b - Condition H; Verify interlock is in required state for existing unit condition within 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Appendix D D NUREG-1 021, Rev. 9, Supp. 1 1

Appendix D D Operator Action Form ES-D-2 Op Test No.:

Scenario # 4 4 Event # 3

~-------

Page 8 of 31

~~----~I Event

Description:

SW flooding from the South SW Header.

Time I Position II Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 3, SW Flooding in the Intake Bay from the South SW Header.

EVENT INDICATIONS:

APP-008-F7; SOUTH SW HDR LO PRESS APP-008-F8; NORTH SW HDR LO PRESS APP-008-E7; S SW HDR STRAINER PIT HI LEVEL APP-008-E8; N SW HDR STRAINER PIT HI LEVEL APP-002-A8; HVH-1 WTR OUTLET LO FLOW APP-002-B8; HVH-2 WTR OUTLET LO FLOW APP-002-C8; HVH-3 WTR OUTLET LO FLOW APP-002-D8; HVH-4 WTR OUTLET LO FLOW APP-008-D7; SSWS SW HDR STRAINER PIT HI-HI LVL (Delayed)

APP-008-D8; N N SW HDR STRAINER PIT HI-HI LVL (Delayed)

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 Action Step:

BOP CheckAPP~008-E7 Check APP-008-E7 AND APP-008-E8 Extinguished. (NO)

APP-008-E8Extinguished.

    • valves V6-12B and V6-12C Closes valves.V6-12B V6-12C..

SRO Transitions to Section F.

RO/BO P RO/BOP Makes PA announcement for entry into AOP-022.

Evaluate Control Room Indications and perform local inspections to C rew Crew determine source of leakage.

Appendix D NUREG-1021, Rev. 9, Supp. 1 1

Appendix D D Operator Action Operator Action Form ES-D-2 Form ES-D-2 Op Test Op Test No.:

No.: 1 Scenario ##

Scenario 44 Event ##

Event 33 Page Page 99 of of 31 31

-- ~-------- --------~I Event

Description:

Event

Description:

SW flooding SW flooding from from the the South South SW SW Header.

Header.

Time I Position Position i Applicants Actions or Behavior Applicant's Behavior 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)

BOP 0o Will receive APP-008-E4, ES E5 & E6 alarms

  • . SW Pump "A" A Stopped. (NO, will stop pump)
    • SW Pump "B" B Stopped. (YES)

Evaluate SW Header Pressure:

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.S.1 requires SR 3.8.1.1 3.S.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 low flow to all CV HVH 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-ASIBSICSIDS guidance.

BOP BOP Close V6-12A (APP-008-E41E51E6/F8 (APP-008-E4/ES/E6/F8 will clear)

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 No.: 1 Scenario # 4 Event # 3 ____

_3~ Page 10 31 _ _ _-11 of ...,;3;;..;,1 Event

Description:

SW flooding from the South SW Header.

Time II Position I Applicants Actions or Behavior Applicant's BOP SW-851 and SW-S57 Verify SW-S51 SW-857 closed.

BOOTH OPERATOR: When requested, report that SW-851 and SW-857 are closed. (Not modeled on simulator)

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> 40 psig. (YES)

SRO Remove Control Power fuses from breakers for SW Pumps "A" A & "B".

B.

BOOTH OPERATOR: Rack out the breakers for Service Water Pumps "A" A and "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)

  • (APP-002-A81B81C8/D8 clear).

Start one SW Booster Pump. (APP-002-AS/BS/CS/DS BOP Check any CW Pump running. (YES)

Determine if adequate seal water is available to CW:

  • APP-008-E4, APP-00S-E4, CW PMP A SEAL WTR LOST extinguished.

BOP

    • APP-008-E5, APP-00S-E5, CW PMP B SEAL WTR LOST extinguished.
    • APP-008-E6, CW PMP C SEAL WTR LOST extinguished.

APP-00S-E6, (YES, ALL extinguished)

Appendix D NUREG-1 021, Rev. 9, Supp. 1 1

Appendix D Appendix D Operator Action Operator Action Form ES-D-2 Form ES-D-2 Op Test Op Test No.:

No.: 1 Scenario Scenario ## 44 Event Event ## 33 Page Page 11 11 of of 31 31

-:...- ~-------- ~~----~I Event

Description:

Event

Description:

SW flooding SW from the flooding from the South South SW SW Header.

Header.

Time Time III Position III Applicant's Actions Applicants or Behavior Actions or Determine maximum allowable CCW temperature as follows:

Determine maximum RO

.* Check RCS temperature ~ 350 degrees degrees F. (NO)

.* Maintain CCW Heat Heat Exchanger outlet temperature indicated on TI-607 less than or equal to 105 105 degrees F.

Perform the following:

.* Inspect the area of the leak.

SRO

.* 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.

Contact Engineering to perform the following:

SRO *. Evaluate operability of equipment affected by flooding.

  • . Provide corrective actions for flooding.

Refer to ITS for any applicable LCOs.

  • . LCO 3.6.6, Condition D - 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)

SRO *. LCO 3.7.7, Condition A - Restore SWS 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 />. (This LCO has already been entered due to the SWBP being out of service)

  • . LCO 3.8.1, Condition B - Perform SR 3.8.1.1 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 />. (Cascaded LCO from SW NOT available A

to EDG "A")

SRO Implement the EALs.

SRO Return to procedure and step in effect.

Appendix D D NUREG-1 021, NUREG-1 Rev. 9, 021, Rev. 9, Supp.

Supp. 11

Appendix D Appendix D Operator Action Operator Action Form ES-D-2 Form ES-D-2 Op Test Op Test No.:

No.: --:...._

1 Scenario ##

Scenario 44 Event Event ## 4

_4..:..-_ _ _ _ Page Page 12 12 of 31 of _3...1_ _ _-i1 Event

Description:

Event

Description:

PZR PORV PZR PORV PCV-456 PCV-4S6 fails fails 70%

70% open.

open.

Time Time ~ Position Position II Applicant's Actions Applicants or Behavior Actions or BOOTH OPERATOR: When directed directed by the Chief Examiner, insert Event 4, PZR PORV PCV-456 fails 70% 70% OPEN.

OPEN.

INDICATIONS:

EVENT INDICATIONS:

APP-003-C3;PRT HI HI PRESS PORVISAFETY VLV OPEN APP-003-D6;PZR PORV/SAFETY APP-003-E6;PZR PORV LN HI TEMP APP-003-F6;PZR SAFETY VLV LINE HI TEMP APP-003-D8;PZR CONTROL HI/LO HIILO PRESS Recognizes PORV is OPEN and takes Immediate Actions of AOP AOP-RO 019, MALFUNCTION OF RCS PRESSURE CONTROL.

SRO Enters AOP-01 AOP-019, 9, MALFUNCTION OF RCS PRESSURE CONTROL.

Immediate Action Step:** Step:

Determine.if*PZR Determine if PZR PORVs should be CLOSED:* CLOSED:

RO ** Check PZRPZR Pressure Pressure less 2335 PSIG. (YES) less than 2335PSIG.

  • . Verify both PZR PORVs CLOSED. (NO)

IF anyPZR PORV can NOT any PZR PORVcan CLOSED, THEN close its PORV NOT be CLOSED,THEN BLOCK valve. .

Immediate Action Step:

Immediate Acti()nStep:

RO RO ControlHeaters Control Heaters and to restore RCS Pressure to desired valves torestore.HCS and Spray valves corttrolband; control band.

RO RO Check PZRPZR Pressure under operator control.

Pressure under control. (YES)

RO RO Check Check PC-444J, PC-444J, PZR PRESSURE operating PZR PRESSURE operating in AUTO. (YES) in AUTO. (YES)

RO RO Check Check RCS required for pressure << required RCS pressure for current current plant (YES) conditions. (YES) plant conditions.

Appendix Appendix D D NUREG-1 021, NUREG-1 Rev. 9, 021, Rev. Supp. 11 9, Supp.

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 44 Page Page 13 13 of of 31 31

~-------- ~------~I Event

Description:

Event

Description:

PZR PORV PZR PORV PCV-456 PCV-456 fails fails 70%

70% open.

open.

Time II Position Position ~ Applicants Actions or Behavior Applicant's Behavior Continuous Action<Step:

Continuous. Action Step:

Check PZR pressure less than than 2205 PSIG.

PSIG.

RO IF pressure decreases to <::< 2205 PSIG, THEN restore IF restore pressure within hours Or be in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

2. in MODE 2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

RO Check BOTH PZR Spray valves CLOSED. (YES)

RO CVC-31 1 ,AUX Check CVC-311, AUX PZR SPRAY valve CLOSED. (YES)

Check APP-003-F8, PZR LO LVL HTR OFF & LLTDN TDN 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 Implement The EALs.

SRO Contact I&C To Make Repairs To The PZR Pressure Control System.

Review ITS ITS For Applicable LCOs:

    • LCO 3.4.11, Condition Condition B, B, Close Block valve within 11 hourhour SRO SRO AND
    • Remove 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-2 ES-D-2 Op Test Op Test No.:

No.: 1 Scenario ##

Scenario 44 Event ##

Event 5&6 5&6 Page Page 14 14 of of 31 31

~- ~~------ ~~----~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 of the the Reactor Reactor to to trip.

trip. (ATWS)

(ATWS) SDAFW SDAFW PumpPump Trips.Trips.

Time ~ Position II Applicants Actions or Behavior Applicant's BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 5, Turbine bearing #3 vibrations will increase above the alarm setpoint and require manual Reactor and Turbine trips.

EVENT INDICATIONS:

APP-008-A8; TURBINE SUPERVISORY INSTRUMENT (Will reflash as each bearing vibration increases APP-OOS-AS; greater than 7 mils)

Turbine Generator Supervisory Recorder and Vibration module bearings in alarm.

SOP Recognizes alarm, monitors vibration recorder and references APP-BOP 008-A8.

OOB-AB.

SOP BOP ** Verify lube oil cooler discharge temperature between 115- 1 15 125 degrees F. (YES)

BOP ** If turbine bearing temperature is > 225 degrees F, trip the turbine. (NO)

SRO Enters AOP-006, TURBINE ECCENTRICITY / VIBRATION.

BOP Check Turbine Speed ~ < 600 RPM. (NO, Go To Step 4)

Continuous Action .Step:

BOP r,(

)I-. %t........I Check BearingID... ... I Vibration ILevels

,IItiIDt1IIIIU VIUILIIJII LVII IJIILIIt

...I... L. ri ,r,rI,ir on theTURBINE I IJIEIIJI GENERATOR

-rIr-r IJIEI-k I iri

a. ifl,fl ,I flfl n, nrfl flnnn I .1 -J £ *11 fl IS SUPERVISORY RECORDER urizi-ivicjriy r-itLur1Lnz11 iess less man than 14.0 MILS. (Y) 14.U IVIIL. (YES)

NOTE: At this time, vibration level is less than 14 14 mils but Step 4 RNO will be implemented as vibration increases.

Attempt to decreasedecrease or stabilize vibration by by at least least one of the following methods:

SOP BOP

    • Vary loadload (MW and/or and/or VARS) or turbine speed.
    • Vary Hydrogen Hydrogen Side or Air Side Side Seal Seal Oil Oil temperatures.

temperatures.

Appendix Appendix D D NUREG-1 NUREG-1 021, 021, Rev.

Rev. 9, 9, Supp.

Supp. 11

Appendix D D Operator Action Form ES-D-2 Op Test No.:

Op No.: 1

.....;...- Scenario # 44 Event # 5 & 6 _ _ _ Page

_5;;;...;;.;.&..;;.6 15 15 of _3_1 31_ _ _--11 Event

Description:

Description:

High vibration on #3 Turbine bearing which leads High leads to to a manual Reactor trip.

the Reactor to Failure of the Failure to trip.

trip. (ATWS) SDAFW Pump Pump Trips.

Trips.

Time III Position Ii Applicant's Actions or Behavior Aoclicants

. Vary Turbine Lube Oil cooler discharge temperature.

. Increase Exciter Air discharge temperature.

BOOTH OPERATOR: As aa 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 Check Bearil'1g.Vibration Levels on the TURBINE GENERATOR Vibration LevelsoritheTURBINEGENt=RATOR SUPERVISORY RECORDER less than 14;0 14.0 MILS.

MILS. (NO)

SRO vibration is*felt IF vibration the Control Room, THEN perform one of the is felt in theControlRoom,THEN following:

  • . REACTOR TRIP FROM IF the REACTORTRIP TURB BLOCK P-7 permissive FROM TURBBLOCK light is extinguished, THEN trip the Heactbr light Reactor AND GoToGo To PATH-
1. (YES)

Directs the RO to manually trip the Reactor and perform the immediate SRO actions of PATH-1.

PATH-i.

Immediate J\,ction*

Action Step:

Check REACTOR TRI TRIP as follows:

Pasfollows:

RO

    • Rod Position indication ZERO. ZERO. (NO)
    • Rod Bottom Lights Lights IILLUMINATED.

LLUMINATEO> (NO)

    • Neutron Flux DECREASING. (NO)

Appendix D NUREG-1021 Rev. 9, Supp. 11 NUREG-1021,, Rev.

Appendix D Operator Action Form ES-D-2 Op Test No.: 1

--=-- Scenario # 4 Event #

5&6

& Page 16 of 31

~~----~

Event

Description:

High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time I Position II Applicants Actions or Behavior Applicant's Immediate Action Step:

Perform the following:

    • Trip pushbuttons.

Depress both Reactor Trip*pushbuttons.

  • breakers will not open, then perform the If Reactor Trip breakerswillnot.open,.

following:

follQWing:

RO/SRO

    • finsert nsert.control.

coritroi rods.

rous.

    • Dispatch an operator to to theMG the MG Set Room to trip Reactor Breakers "A" Trip Breakers A and "B" B AND MGSet MG Set Generator Circuit Breakers "A"A and "B".

B.

    • Dispatch an operator to 480V Busses Busses 2B and 3 to trip Rod Set Breakers "A".and Drive MG SetBrs.akers 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 RTB5 and MG set breakers.

Immediate Action Step:

Check Turbine Trip Trip as follows:

BOP ** Both Turbine Stop valves closed. (NO)

Both OR

    • valve~closed.

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 Pump will NOT start and BOP APP-007-F5, SD AFW PMP LO DISCH PRESS TRIP will illuminate)

Appendix D D NUREG-1021, NUREG-1021 , Rev. 9, Supp. 1 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1

--:...- Scenario # 4 Event # 5&6 5&6 Page 17 of 31

--~------ ~------~I Event

Description:

High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time II Position II Applicants Applicant's Actions or Behavior Verify Charging flowpath established as follows:

RO ** CVC-310B, LOOP 2 COLD LEG CHG OPEN.

  • . HIC-1 21, Charging Flow Controller demand at 0%.

HIC-121, RO Verify Two Charging Pumps running at full speed.

RO Verify Boric Acid Pump aligned for blend running.

RO Verify MOV-3S0, MOV-350, BA TO CHARGING PMP SUCT open.

RO Checkflowon Check Fl-hO, BORIC ACID BYPASS FLOW indicated.

flow on FI-110, RO Verify Charging Flow to RCS on FI-122A Fl-i 22A BOP Verify CONTAINMENT VENTILATION ISOLATION initiated.

NOTE: It is expected that if the CV Ventilation Signal has not been initiated, the operator will take R-11 R-i1 or R-12 high voltage pushbutton to OFF and return to ON to initiate the signal. This can be verified by the 2 Amber lights ILLUMINATED below the Radiation Monitoring System panel labeled "CV CV Ventilation Isolation Signal Relay V-1 V-i and V-2.

V-2."

Check SI initiated. (NO)

RO IF an SI Signal occurs, THEN verify auto start of all SI equipment using Supplement L while continuing with this procedure.

Check if the following trips have occurred:

RO/BOP ** Reactor Trip. (YES)

Appendix D NUREG-1021,, Rev. 9, Supp. 11 NUREG-1021

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # _5;;..&;;;.;....;.6 5 & 6 _ _ _ Page 18 of _3.;,..1 31_ _ _---lI Event

Description:

High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time i Position i ADDlicants Actions or Behavior Applicant's Continuous Action Step:

Check if Reactor is subcritical:

RO ** Check Power.

Check Power Range indicatiohless indication less than 5%. (YES)

    • ,*s I_

Check I I Lr1ecIc Intermediate iritermeuiae Range I fl i-lange indicationirioicauori negative

. . t. .In,s, I %

riegaiive SUR.

UM. (YES, IY ,

t.

Go O

To Step.

Step 24)

RO Check IRPI has less than two rods stuck out. (YES)

Stop the RCS Boration:

  • Verify MOV-35G MOV-350 closed.
  • Verify control switch for Boric Acid pump aligned for blend in AUTO.

RO ** Check emergency boration performed using MOV-35G MOV-350 flowpath.

  • Notify Engineering to evaluate:
    • RCP Bearing temperatures
    • No. 1 seal leakoff temperatures and flowrates.

No.1 flowrates .

Check emergency boration performed using RWST flowpath and it is RO desired to align Charging Pump suction to the VCT. (NO, Go To Step 25.i)

RO Control Charging Pump speed to control PZR Level.

Reset SPDS and Initiate monitoring of Critical Safety Function Status RO Trees.

SRO Return to procedure and step in effect.

Appendix D NUREG-1021, Rev. 9, Supp. 11 NUREG-1G21,

Appendix D Operator Action Form ES-D-2 Op Test No.: 1

--:....- Scenario # 4 Event # 5 & 6 _ _ _ Page

.....;5;;...;&;;;..;;..6 19 31 _ _ _-i1 of _3;;.,;1 Event

Description:

High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time i Position II Applicants Actions or Behavior Applicant's SRO Directs entry at the beginning of PATH-1. PATH-i.

IMMEDIATE ACTION STEP:

RO Reactor Tripped. (YES)

IMMEDIATE ACTION STEP:

BOP Turbine Tripped. (YES)

IMMEDIATE ACTION STEP:

BOP AND E-2 energized. (YES)

E-1 AND*E-2 IMMEDIATE ACTION STEP:

RO 0o SI Initiated... (NO)

Sllnitiated 0o SI Initiation Required. (NO)

Sllnitiation RO Verify two Charging Pumps running. (YES)

SRO Transition to EPP-4, REACTOR TRIP RESPONSE.

Continuous Action Step:

procedure exit is warranted:

Determine if procedure warranted SRO ** affack on .RNPsite Check attack RNP site in progress. (NO)

    • Check a total loss of SW .OR OR Loss Loss of Lake Robinson Dam in progress. *(NO, integrity inprogress. (NO, Go to Step 2)

Continuous Action Step:

Check SI signal initiated. (NO, Go Go to Step 4)

RO IF SI initiation occurs during this procedure, THEN Go to PATH-1, PATH-i, Point A. (Page 21 Entry Point.A. 21))

Appendix D NUREG-i 021, Rev. 9, Supp. 1i NUREG-1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 5 & 6 _ _ _ Page

...,;5;;..&;;.;..;;;.6 20 31 _ _ _-l of ...,;3;;..;.1 1

Event

Description:

High vibration on #3 Turbine bearing which leads to a manual Reactor trip.

Failure of the Reactor to trip. (ATWS) SDAFW Pump Trips.

Time ~ Position I Applicants Actions or Behavior Applicant's SRO Reset SPDS and initiate monitoring of CSFSTs.

CREW Open Foldout A.

  • . RCP Trip criteria. IF BOTH conditions are met, THEN stop all RCPs: (NO)

SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF

°o -

DELIVERING FLOW TO THE CORE RCS Subcooling - < < 35 degrees F [55 degrees F]

°o -

  • SI actuation criteria. IF EITHER condition occurs, THEN Actuate SI and Go To PATH-1, PATH-i, Entry Point A:

o RCS Subcooling - < < 35 degrees F [55 degrees F]

° -

Level CAN NOT BE MAINTAINED> 10% [32%]

o PZR Level-

° -

    • 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 F. (YES)

Transitions to Step 12, based on SW Header pressure between 40-50 SRO PSIG.

Continuous Action Step:

Determine Feedwater status:

    • Check RCSaverage Check RCS average temperature less than 554 °F. OF. (YES)

ROP BOP Verity FWI-W Hht Verify REG VALVEs VALVEs ULOS1+/-LJ. CLOSED. (YES)

    • Establish FW bypass flow to maintain level in intact S/Gs rriaintainlevel between 39% 39% and 50%. (Will stop MDAFW pumps and throttle stopMDAFW open ALL open* S/G Bypass valves to control SIG level)

ALL S/GBypass RO Check All Control Rods fully inserted. (YES)

Appendix D NUREG-i NUREG-1 021, Rev. 9, Supp. 11

Appendix D0 Appendix Operator Action Operator Action Form ES-D-2 Form ES-D-2 Op Test Op Test No.:

No.:

Scenario Scenario ## 44 Event Event ## 7, 8, 9 & 10 7,8,9&10

~~--~--

Page Page 21 21 of of 31 31

~~----~I Event

Description:

Event

Description:

Small Small Break Break LOCA, Phase A LOCA, Phase fails to A fails actuate, SI to actuate, SI fails fails to to actuate, CR HVAC actuate, CR HVAC fails fails to to actuate.

actuate.

Time Time II Position Position ~ Applicants Actions or Applicant's Actions or Behavior Behavior BOOTH OPERATOR: When directed by the Chief Examiner, insert Event 7, Small Break BOOTH LOCA.

EVENT INDICATIONS:

EVENT INDICATIONS:

Reactor Trip Reactor Trip Breakers open open PZR Level PZR Level and and Pressure decreasing RR-1 Recorder Point RR-1 Point #11 for R-12 R-12 in alarm (later) in alarm "A" valves will not close automatically Phase A 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. These valves must be opened manually and at least one valve must be opened to provide an injection path.

Phase A fails to actuate, the crew will manually actuate Phase A, but valves CCW-739, CVC-204B and SI-855 Sl-855 will NOT close on manual actuation of the pushbutton. They will require manual closure from the RTGB control switches.

CR HVAC will fail to shift to PRESSURIZATION MODE. The crew will manually start HVE-19A and HVE-16 will have to be manually CR-D1A-SA stopped. CR-D1 A-SA and D1 Dl B-SB will close - 5 seconds after HVE-16 is stopped.

CREW Open Foldout A.

  • RCP Trip criteria. IF BOTH conditions are met, THEN stop all RCPs: (YES) 0o SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0o RCS Subcooling - << 35 degrees F [55 degrees F]

Verify Phase A Isolation valves are closed. (NO, must be manually RO actuated using the pushbutton)

Appendix 0D NUREG-1 NUREG-1 021, 021, Rev.

Rev. 9, 9, Supp.

Supp. 11

Appendix D Operator Action Form ES-D-2 ES-D2 Op Test No.: 1 Scenario # 4 Event # 7, 8, 9 & 10 7,8,9&10 Page 22 31 _ _ _..,1 of .....;3;;..;.1

~-

Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time II Position ~ 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 Sl-870A and 870B were RO manually aligned)

RO cow pump is running. (YES)

At least 11 CCW BOP sw and SW Booster pumps running. (NO)

All SW Appendix D NUREG-1 021, Rev. 9, Supp. 1 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 7, 8, 9 & 10 7,8,9&10 Page 23 31 of _3.:,..1:.....-_ _---l 1

Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time i Position  ! Applicants Actions or Behavior Applicant's Attempt to start all SW and SW Booster pumps. (NO, SW Booster BOP Pump "A" A and SW Pumps "A" A & "B" B are unavailable)

SOP 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 initiated. (YES)

BOP Verify CV Ventilation isolation. (YES)

SOP BOP Verify Control Room Vent aligned for Pressurization Mode. (NO)

NOTE: HVE-19A will be manually started and HVE-16 will have to be manually stopped. CR-01 CR-D1A-SA A-SA and 01 Di 8-S8 B-SB 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-1. PATH-i. At the discretion of the Chief Examiner and when the crew transitions to FRP-P.i, the scenario can be terminated. If needed, actions for FRP-P.1, FRP-P.1 begin on page 29.

SOP BOP Verify both EDGs running. (YES)

ContinuoOs Artinn Stnn Cnntiniiniic .Action St~p:

RflP BOP L.......... ..1. ...:L:... .-.r VVIIIIIII 30

.tJ minutes HhIII1IILS of (ii power i.....

LJLJVVtH loss ILJSS using (15111(1 OP-Restart I(,StrJlI battery L)HIIHIV chargers t;II1IL1lIs within

, ----v-01.

601.

Continuous Action. Action Step:

RO CV Pressure has remained below 10 psig. (YES)

CV Appendix D NUREG-1021, Rev. 9, Supp. 1 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 7, 8, 9 & 10 7,8,9&10 Page 24 of 31

~- -----il Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time  ! Position II Applicants Applicant's Actions or Behavior BOP Automatic Steam Line Isolation Initiated. (NO)

BOP Automatic Steam Line Isolation Required. (NO)

BOP Locally open breaker for HVS-1 at MCC-5.

RO RCS pressure> 1350 psig. [1250 psig] (NO)

RO SI Flow Verified. (YES)

RO RCS Pressure Greater than 125 psig. (YES)

SOP BOP At least 300 GPM AFW flow available. (YES)

BOP Verify AFW valves properly aligned.

SOP BOP Control AFW flow to maintain S/G levels between 8% [18%] [1 8%j 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 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)

RO RCS temperature> 547 degrees F. (NO)

BOP Attempt to limit cooldown.

Appendix D D NUREG-1021, Rev. 9, Supp. 1 1

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 7, 8, 9 & 10 7,8,9&10 Page 25 31 of _3;;:.,.1:...-_ _--11

~-

Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time LII Position II Applicants Actions or Behavior Applicant's If RCS cooldown continues and is not due to SI flow, then close MSIVs BOP and MSIV bypasses.

RO PZR PORVs closed. (NO)

RO RCS pressure> 2335 PSIG. (NO)

RO Close PZR PORVs.

RO PZR PORVs closed. (NO)

RO Close PORV blocks.

RO PORV blocks closed. (YES)

RO PZR Spray and Aux Spray valves closed. (YES)

RO At least 11 RCP running. (NO)

BOP Any SIG S/G with uncontrolled depressurization. (NO)

BOP Any S/G Completely Depressurized (NO)

BOP R-1 9s, R-31 ssand R-19s, and R-15 R-1 5 Rad levels normal (YES)

BOP R-2, R-32A, R-32B Rad levels normal (YES)

RO CV Pressure Normal (NO)

Appendix D D NUREG-1 NUREG-1021, 021, Rev. 9, Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test No.:

~-

Scenario # 4 Event # 7, 8, 9 & 10 7,8,9&10 Page 26 of

....,1 31 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time III Position I Applicants Applicant's Actions or Behavior RO Reset SPDS and initiate monitoring of CSFSTs. (Entry Point C)

CREW Open Foldout B.

BOP Request periodic activity samples of all S/Gs.

RO At least 11 RCP running. (NO)

BOP Any S/G SIG with uncontrolled depressurization in progress. (NO)

BOP Control AFW flow to maintain S/G levels between 8% [18%] and 50%.

BOP Any S/G with uncontrolled level increase. (NO)

BOP R-1 9s, R-31 sand R-19s, s and R-15 R-1 5 Rad levels normal. (YES)

RO PZR PORVs closed. (NO)

RO pressure > 2335 PSIG. (NO)

RCS pressure>

RO Close PZR PORVs.

RO PZR PORVs closed. (NO)

RO Close PORV blocks.

Open at least one PORV block unless closed to isolate an open PZR RO PORV.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 7, 8, 9 & 10 7,8,9&10 Page 27 of . . .:331

. . :,1_ _ _-l 1

Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time ~ Position III Applicant's Actions or Behavior Aoolicants ONTINUOUS ACTION STEP CONTINUOUS RO

- If PZR PORV opens oens on high hiah pressure, Dressure. then verify reclosure at or ow 233b psig.

below2335 psg. Close Ulose PORV lOHV blocks as necessary.

RO Reset SI.

ONTINUOUS ACTION STEP:

CONTINUOlJSACTIONSTEP:

flfl FW CREW rc. +n nn,A,nr e Intl +knn rnnfnrt nmnrnnnn e-sn nra-I nnnrnnn+

Ifoffsite II.ZIL poweris JJVVI IQ lost,then 1 IJL U II I restart I OLI L emergency I I II i.,y safeguard OC.tIUjL4CiI L4 equipment.

4 nn 9UIJJI I II IL.

RO Reset CV Spray.

RO Reset Phase A and Phase B.

Establish Instrument Air to CV. IF compressor not running, THEN start RO compressor.

BOP Offsite power available to Charging Pumps. (YES)

RO At least 1 1 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) 10 10b0 When below 10- amps, then energize Source Range detectors and RO monitor recorder.

Appendix D NUREG-1021, Rev. 9, Supp. 1 1

Appendix 0D 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 7,8,9&10 7, 8, 9 & 10 Page Page 28 28 of of ....,;3;..;,1 31_ _ _-l 1

Event

Description:

Event

Description:

Small Break LOCA, Small Break LOCA, Phase Phase AA fails fails to actuate, SI to actuate, SI fails fails to to actuate, actuate, CR CR HVAC HVAC fails fails to to actuate.

actuate.

Time Time IIPosition Position II Applicants Actions Applicant's Actions or or Behavior Behavior RO RO RCS pressure greater RCS pressure greater than than 275 275 psig psig [400 psig] (YES)

[400 psig] (YES)

RO RCS pressure stable RCS stable or increasing (NO)

BOP BOP SIG with uncontrolled depressurization in Any S/G in progress (NO)

RCS pressure increasing RO (YES) Return to PATH-1, PATH-i, Entry Point C. (page 25)

(NO) Continue below.

BOP El and E-2 energized by offsite power (YES)

E-1 BOP Starting air receivers re-pressurized to unloaded EDGs (YES)

BOP Stop the unloaded EDGs RO Supplement 0 D components capable of recirc (YES)

BOP Aux Building radiation normal (YES)

RO RCS pressure greater than 275 psig [400 psig] (YES)

BOP BOP Obtain RCS boron, boron, activity, and Hydrogen Hydrogen samples CREW CREW Transition Transition to EPP-8, EPP-8, POSTPOST LOCA LOCA CID C/D AND AND DEPRESSURIZATION.

Appendix Appendix D 0 NUREG-1 NUREG-1 021, 021, Rev.

Rev. 9,9, Supp.

Supp. 11

Appendix D Operator Action Form ES-D-2 Op Test Test No.:

No.:

Op Scenario ##

Scenario 4 Event #

Event 7, 8, 9 & 10 7,8,9&10 Page Page 29 29 of of 31 31

..;;..----11 Event

Description:

Event

Description:

Small Break Small Break LOCA, LOCA, Phase to actuate, SI fails to actuate, CR Phase A fails to CR HVAC HVAC fails to actuate.

actuate.

Time II Position i Applicants Actions or Behavior Applicant's FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK actions begin here.

Continuous Action Step:

BOP Check CST level less than 10%. 10%. (NO)

IF CST level decreases to .Iess IF less than than 10%, THEN THEN perform Step 2. 2 Determine If RCS Cooldown Is Due To A Large Break LOCA:

BOP ** RCS pressure is less than 275 PSIG [400 PSIG] (NO)

AND

  • . Fl-605 greater than 1200 GPM. (NO)

RHR flow on FI-605 Check RCS Cold leg temperature decreasing.

BOP (NO, skip the next 5 Steps) (YES, continue below)

Attempt to Stop RCS cooldown:

RO/BO P RO/BOP

    • Verify STEAM LINE PORVs CLOSED.
    • Verify Condenser Dumps CLOSED.
    • Check RHR system aligned for core cooling. (NO)

BOP Check any SIGS/G intact. (YES)

Check level in at least one SIG S/G >> 8% [18%].

BOP WHEN level in at least one S/G is> 8% [18%], THEN perform Step 8.

BOP Control Feed flow to intact SIG S/G to stop RCS cooldown.

Identify and Isolate faulted SIG: S/G:

    • Any S/G pressure decreasing in an uncontrolleduncontrolled manner. (NO)

BOP OR

    • Any SIG S/G completely depressurized. (NO)

Appendix D D NUREG-1021, Rev. 9, Supp. 11

Appendix D Operator Action ES-.D-2 Form ES-D-2 Op Test No.: 1 Scenario # 4 Event # 7, 8, 9 & 10 7,8,9&10 Page 30 of 31 31

~- "';;";'---'-'1 Event

Description:

Small Break LOCA, Phase A fails to actuate, SI fails to actuate, CR HVAC fails to actuate.

Time ~ Position I Applicants Applicant's Actions or Behavior Check PORV block valves available.

RO *. Power available. (YES, Power is available to one block valve)

  • . At least one open. (YES)

Continuous Action*

Continuous* Action Step:

,r.. i *

    • ,.t_

Check LiHUK L

- I LITOPL) in t

III service.

S[VIU. (NO)

- / I l,INLJ)

RO I *a flhrk Rfl nriir <2335PSIG.

CheckRCSpressure - 9 PIfl (YES)

(VF I *. Verify VerifyPORVs PORVs CLOSED. (NO, (NO. PCV-455C is closed to isolate PCV-456)

UV-45b) 3 I-0o Verify associated PORV PORV block valve is closed.

RO Check SI Pumps running. (YES)

Determine if SI can be terminated.

RO

  • . Check RCS subcooling > > 85 degrees F [105 degrees F]. (NO)

RO Check ALL RCPs stopped. (YES)

Appendix D NUREG-1021, Rev. 9, Supp. 1 1

HLC-08 NRC SCENARIO 4 TURNOVER SHEET POWER LEVEL: 50%, 150 MWO/MTU. MWD/MTU.

  • Returning to RTP following a short Maintenance Outage.

BORON CONCENTRATION: 1285 ppm EQUIPMENT UNDER CLEARANCE:

  • SW Booster Pump "A"A is Out-Of-Service for Motor Coupling Alignment.

o LCO 3.7.7-A has been entered and is in hour 18 of a 72 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 Vibration for #2, 3 and 4 bearings is elevated.

INSTRUCTIONS FOR THE WATCH:

  • Increase power to 75% RTP.

Appendix D NUREG-1 021, Rev. 9, Supp. 1 1

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