ML101970333

Initial Exam 2008-301 Draft Simulator Scenarios

ML101970333
Person / Time
Site:	Robinson
Issue date:	06/28/2010
From:	NRC/RGN-II
To:	Progress Energy Carolinas
References
50-261/08-301 50-261/08-301
Download: ML101970333 (111)

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.

• . Main Turbine Main Turbine Vibration Vibration for for #2,

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

• • 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,

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 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-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.

• . 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

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

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 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 5: Downpower to support removing FWH 4A from service.

• Event 6: Rods continue to step requiring Reactor Trip.

• Event 7: Failure of the Turbine to trip.

EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

• 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:

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 2: Inadvertent Turbine Trip with Power < < P-7.

• Event 3: SW Pump "A" A Breaker trips on overload.

• Event 4: Low pressure on SI Accumulator "B". B.

• Event 5: Multiple dropped rods requiring a Reactor Trip.

• Event 6: S/G 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:

"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:

• • 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:

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"

• 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

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:

• (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 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 3: SW flooding from the South SW Header.

• 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 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:

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

• • 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)

• • 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:

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